WO2016197807A1

WO2016197807A1 - Implementation method for fast reactor type coupled nuclear reaction and nuclear reactor therefor

Info

Publication number: WO2016197807A1
Application number: PCT/CN2016/082774
Authority: WO
Inventors: 陈安海; 陈邦才; 陈昆
Original assignee: 陈安海
Priority date: 2015-06-12
Filing date: 2016-05-20
Publication date: 2016-12-15
Also published as: CN105023621A; CN105023621B

Abstract

Disclosed are an implementation method for a fast reactor type coupled nuclear reaction, a nuclear reactor and a fuel element therefor. A main reactor vessel of the nuclear reactor comprises a fission pool (201) and a moderation pool (301) which are completely isolated from each other but coupled with each other, a reactor core (250) with fast neutron characteristics is arranged in the fission pool (201), moderator is arranged in the moderation pool (301), primary coolant is separated from the moderator, and the primary coolant passes through the fission pool (201) rather than the moderation pool (301); and a heat insulation layer is arranged between the fission pool (201) and the moderation pool (301) to block the heat exchange therebetween. Neutrons are allowed to pass through between the fission pool (201) and the moderation pool (301), so that the fission pool (201) and the moderation pool (301) can perform neutron exchange and a coupled nuclear reaction, fast neutrons produced by the reactor core (250) and moderated neutrons reflected into the fission pool (201) from the moderation pool (301) can make the reactor core (250) simultaneously perform coupled nuclear reactions induced by the fast neutrons and the moderated neutrons, thermal neutron nuclear reaction can take place in the moderation pool (301), and the moderation pool (301) can be provided with a nuclear control system and can implement ex-core coupled nuclear control. Because the moderation pool (301) of the fast reactor type coupled nuclear reactor is provided with a thorium breeding fuel system, bred fuel can be extracted on line, nuclear element separation is safe and simple, and a solution is provided for the bottleneck of the thorium reactor technology.

Description

Method for implementing fast reactor-type coupled nuclear reaction and nuclear reactor thereof

The present invention relates to nuclear fission reactors and methods of operation thereof.

Background technique

[0002] There are two sets of U-238/PU-239 and Th-232/U-233 that are known to be available for heavy nuclear fission. The corresponding main nuclear materials are: The former corresponds to natural uranium Nuclear waste (including depleted uranium), the latter corresponding to strontium. In addition to nuclear fusion energy, it is known that the energy contained in thorium on Earth is much larger than the sum of other fossil energy reserves, and the thorium reserves are four times larger than uranium. With fast reactors, nuclear fuel utilization can be increased to 60-70%, and optimistic estimates suggest that globally available uranium resources can sustain all energy needs for more than 20,000 years. However, the current main nuclear power technology - pressurized water reactor fuel utilization rate is only 0.17% (calculated as natural uranium), the amount of nuclear waste generated is large, and there is a danger of high pressure explosion. Obviously, pressurized water reactors cannot be used as the development direction of nuclear power in the future. The nuclear power industry is increasingly acknowledging the development of advanced nuclear power based on fast reactors. The fourth generation of nuclear power technology represented by gas cooled reactors and lead cold reactors has begun to emerge, with ADS. The research and development of the fifth-generation nuclear power technology, which is the pusher of the Helium reactor, is also quietly underway.

[0003] The conversion of U-238/Pu-239 is no longer a problem in the fast reactor, but the conversion of Th-232/U-233 is different, and the half-life of the intermediate product Pa-233 decays to U-233 up to 27 It takes 300 days for complete decay, which is too long for the reactor, which makes it difficult to operate and control the reactor. The acquisition of the primary fuel U-233 is difficult. The main reasons are: the gamma-based fuel has a strong Y-ray; the sintered cerium-based oxide in the spent fuel is extremely difficult to dissolve; the Pa-233 accumulated in the core during the reactor operation The easy capture of neutrons into non-fissile elements reduces the yield of U-233. These problems have not been effectively solved so far. Although it is a good way to use the accelerator spallation neutron source to irradiate Th-232 to obtain U-233, the cost and energy consumption of the high-energy proton accelerator are too high, and it is difficult to operate stably for a long time. Mass promotion. It is generally believed that the best solution is to extract the intermediate product Pa-233 from the reactor.

[0004] The most memorable process in the development of the sputum is the "Fluoride Hydroxide Molten Salt Reactor". In the cesium fluoride smelting salt heap test, the intermediate product Pa-233, which is a quinone/uranium conversion intermediate, was tried. Unfortunately, this remarkable nuclear reactor goes beyond the limits of materials science, and the special Hastelloy-N alloy, which is most resistant to molten salt corrosion, also undergoes dangerous circuit intergranular corrosion during operation. At present, the possibility of solving the corrosion problem of the material of the molten salt reactor is still embarrassing. Even if the material corrosion problem is overcome in the future, the high material and running cost will become an insurmountable gully. There are still two weaknesses in the molten salt reactor: The primary circuit has too many functions for the molten salt, and the multi-functional binding leads to mutual restriction; the high-radioactive and complex composition of the first-circuit molten salt must be frequently subjected to high-energy purification treatment, online molten salt management. Complex and self-contained.

[0005] In the 1950s and 1960s, R. AVERY et al. proposed and developed fast-thermal neutron coupling. Heterogeneous reactor, the core includes a fast neutron energy spectrum core and a thermal neutron energy spectrum core, and the fast neutron energy spectrum core uses a saturated water vapor as a moderator to obtain a harder neutron spectrum, heat The neutron energy spectrum core is made of pressurized water as a moderator. Chinese scholars Zhang Yuman and Li Yulun proposed a similarly designed water-cooled two-zone proliferation nuclear reactor in 2008. In the 1960s, in order to improve the thermal efficiency of nuclear power plants and save nuclear fuel, General Electric Company (GE) developed a method to generate saturated steam in a boiling water reactor, which produced a hard neutron spectrum to form a fast-thermal neutron mixture. Energy spectrum reactor. Strictly speaking, the cores of these designs use water or water vapor as a moderator, and the amount of fast neutrons is small. The energy spectrum is still in the category of thermal neutrons. Because the engineering difficulty is greater than that of pressurized water reactors, the economy is not high. Not implemented in the project.

[0006] If we further expand the study of "fast-thermal neutron-coupled nuclear reactions", we may find new ways to develop alternative nuclear power technologies. Can a fast neutron core perform a fast-thermal neutron coupling nuclear reaction? Is it possible to isolate the moderator from the fast neutron core? Can you release the functional binding of the moderator and coolant? Is it possible to use a moderator outside the core to increase the nuclear reactor efficiency of the fast reactor? Is it possible to reduce the physical conditions in the nuclear reaction vessel and implement online extraction of proliferating fuel? To date, no literature has been consulted on the use of moderators in fast reactors or fast-thermal neutron-coupled nuclear reactors based on fast neutron cores. Summary of the invention

[0007] The "on-line extraction of strontium-proliferating fuel" and the "high-efficiency conversion and safe separation of strontium/uranium" have been in existence for a long time. For more than 60 years, it has been the key technical bottleneck restricting the research and development of "钍 nuclear reactor" and has become a century old. problem. It is an object of the present invention to provide a solution to the above problems and to some of the shortcomings of current nuclear power technology.

[0008] The present invention relates to a fast reactor type coupled nuclear reaction, which is a fast-thermal neutron coupling nuclear reaction mainly composed of a fast neutron core, and the specific implementation method thereof is:

(1) splitting the reactor main container into fission pools and slower pools that are completely isolated from each other; slowing tank built-in moderator; setting core in fission pool, core has fast neutron core characteristics; Separated from the primary coolant, the fission cell and core are free of moderator, and the primary coolant passes through the fission pool without passing through the moderator.

[0009] (2) The fission pool and the moderated pool are inlaid or movably combined with each other to couple the structure and function of the two; an insulation layer is disposed between the fission pool and the moderated pool to block heat exchange between the two, The slowing pool is controlled to be close to normal temperature and normal pressure.

[0010] (3) Allowing neutrons to pass through the structure between the fission pool and the slowing pool, enabling the fission pool and the slowing pool to perform neutron exchange and coupling nuclear reactions, and the fast neutrons generated by the core and the slower The slowed neutrons reflected into the fission pool in the pool allow the core to simultaneously perform coupled nuclear reactions initiated by fast neutrons and slower neutrons (including thermal neutrons and mesenchytrons), which have the characteristics of fast neutron reactors and Function, the thermal neutron nuclear reaction (such as thermal neutron capture reaction) can be performed in the slowing pool.

[0011] (4) Optimizing the structure and material of the main vessel of the reactor, and providing a large-area thin-walled neutron exchange window on the side wall of the main vessel of the reactor to increase the neutron exchange efficiency while ensuring the structural strength.

[0012] (5) setting a coupled nuclear control system in the slowing pool, and performing coupled nuclear control and passive shutdown using the coupled nuclear reaction. Controlling the reactivity of the core by changing the neutron function of the moderator and the controllability of the moderator or the controllable displacement of the moderator by changing the neutron exchange between the fission cell and the moderation cell; The passive method is used to make the slowing pool quickly discharge the slowing liquid or the rapid displacement slowing pool. The slowing pool loses the neutron moderating function, and the slowing pool is terminated to transport the slowed neutrons to the core, and the core reactivity decreases rapidly. The chain fission reaction cannot be maintained, thereby achieving passive shutdown.

[0013] (6) Using the high efficiency of the thermal neutron nuclear reaction, under the condition that the slowing pool is close to the normal temperature and pressure, the on-line extraction of the nuclear fuel proliferation and the proliferating fuel is carried out, and the Pa-233/U-233 conversion is realized outside the reactor. And the separation of Th-232/U-233. In the slowing pool, a proliferating fuel system capable of replacing fuel online is provided. The initial proliferating fuel raw material contains only one type of radionuclide Th-232, and only the thermal neutron capture nuclear reaction of Th-232 is performed, thereby avoiding the capture of Pa-233 and U-233. Sub-negative neutron and effective nuclear fuel double loss, improve proliferation efficiency and neutron utilization; moderate physical conditions of moderated pool, no difficulty in extracting proliferating fuel online, simple nuclear separation in the later stage, only Th-232/U -233 A simple separation of two elements.

[0014] (7) Optimizing the core design, such as the candle core design, to improve the nuclear reaction efficiency and fuel consumption rate.

[0015] (8), the reactor main container is reduced, simplified, low cost and modularized, the overall replacement of the fission pool or the implementation of the fission pool module one-time decommissioning (the fission pool is retired with the core replacement), Improve maintenance efficiency and overall safety.

[0016] (9) Modularizing the main components of the reactor so that the reactor can be split and combined. The difficulty of splitting and reorganizing the reactor module is mainly reflected in the splitting and reorganization of the pipeline. Simplify the splitting and recombination of reactor modules with easy-to-reassemble casing connections and splitting methods. The casing connection and splitting method adopts vertical socket or non-vertical sleeve or non-vertical rotation vertical socket.

[0017] Vertical socket: The connecting sleeve is long and can be reused many times. The lower tube head is a fixed tube head, the upper tube head is a detachable tube head, and the two tube heads are on the same vertical axis, perpendicular Lift and install. Before the initial connection, the connecting sleeve is welded to the lower tube head in advance. When connecting, the upper tube head is aligned and inserted into the connecting sleeve a little and then welded. The welding surface is upwards and the welding effect is the best; the splitting only needs to be connected. The welding at the upper end of the casing is cut and separated, and the connecting sleeve is slightly shortened. During the reorganization, the residue in the connecting sleeve is cleaned, and the upper tube head is appropriately lengthened compared with the previous one, and the previous connecting process can be repeated.

[0018] Non-vertical splicing: non-vertical splicing is mainly based on horizontal pipe connection, and is installed by vertical hoisting. The pipe head connected to the split module is a detachable pipe head, and the corresponding other pipe head is a fixed pipe. Head; The connecting sleeve is shorter as a disposable part, and then the connecting sleeve is lengthened as needed or the length is detachable. When connecting, put the connecting sleeve on the fixed pipe head in advance, but do not weld it. The sliding connecting sleeve exposes the fixed pipe head. After the two pipe ends are aligned, the connecting sleeve is sleeved, and then the two ends are welded separately. When disassembling, the entire connecting sleeve should be cut. When reassembling, replace the new connecting sleeve with the appropriate length and repeat the previous connecting process. The welding of non-vertical sleeves is difficult and the welding effect is not easy to guarantee.

[0019] Non-vertical to vertical socket: The two pipes connected are non-vertical pipes, and the two pipe heads to be connected are respectively converted into concentric vertical pipe heads by elbows, and the fixed pipe heads are below, and can be split. The tube head is on, and the subsequent methods of joining, splitting, and recombining are the same as vertical sockets. [0020]

The invention relates to a fast reactor type coupled nuclear reactor, the main features of which are:

(1) The reactor main vessel comprises a fission pool and a moderated pool which are coupled to each other and isolated from each other; a slowering tank has a built-in moderator, a fission pool has a built-in core, and the core has a fast neutron core characteristic; a moderator and a master The coolant is separated and the moderator does not enter the fission cell; the main coolant does not enter the moderation cell.

[0021] (2) The fission pool is completely isolated from the slowing pool, and an insulation layer is provided between the two to prevent heat exchange, and the heat insulation layer is a vacuum structure or a filling heat insulating material.

[0022] (3) The fission pool and the slowing pool can perform neutron exchange without heat exchange.

[0023] (4) The main coolant is a specific liquid metal or molten salt, especially lead or lead-bismuth eutectic.

[0024] (5) The slowing tank is filled with a moderator, and the moderator is a solid moderator or a liquid moderator. Solid state moderators are graphite or ruthenium compounds, especially graphite. The liquid moderator is a heavy or heavy aqueous solution or a light or light aqueous solution, especially heavy water. The moderator pool filled with liquid moderator sets the moderator loop.

[0025] (6) The fission pool and the slowing pool are combined to form a main container coupling structure, and the main container coupling structure is a single slowing pool built-in coupling structure or a single slowing pool external coupling structure or a double slowing pool coupling structure. The built-in coupling structure of the single slowing pool is a slow pool in the center of the reactor, and the fission pool is in the annular pool structure outside the slowing pool. The single moderator pool external coupling structure is that the fission pool is located in the center of the reactor as a barrel-shaped structure, and the moderated pool is located in the outer side of the fission pool in an annular pool structure or a cylindrical structure. The double slowing pool coupling structure is that the inner slowing pool is located in the center of the reactor as a barrel-shaped structure, the outer slowing pool is located in the outer side of the annular pool structure, and the fission pool is located in the inner and outer slowing pools as an annular pool structure.

(7) The main container coupling structure may be configured as a detachable combined structure.

[0027] (8) The main container outer casing may be disposed on the outer circumference of the main container of the reactor. The main container outer casing is a thickened pool metal shell, and the fission pool and the slowing pool are placed and fixed in the main container outer casing.

[0028] The present invention relates to a fast reactor type coupled nuclear reactor in a majority of 6 to explain: reactor main container; core and fuel components; slow fluid circuit and nuclear control system; proliferating fuel system; other facilities; fast reactor coupled nuclear reactor Types of.

[0029] reactor main container

The reactor main vessel includes a fission pool, a moderated tank, and a main vessel casing.

[0030] The main container of the fast reactor type coupled nuclear reactor (especially the fission pool) can be provided with a large area neutron exchange window, the neutron exchange window is a thin wall structure, and the thin wall structure is a frame skin structure or a thin wall rib structure. . The frame skin structure is provided with a frame on the side wall portion of the neutron exchange area, and a thin plate skin is provided on the frame, and the main container portion other than the frame skin structure may adopt a non-thin wall structure such as a bottom plate, a side close to the bottom and the top The wall can be constructed in a thick wall. The thin-walled rib structure is such that the side wall is mainly made of a thin wall, and the rib is reinforced on the thin wall. The frame skin structure or the thin-walled rib structure can be constructed in one piece. Master The main ribs or the main frame can be arranged in a vertically symmetrical position on the side wall of the device, and the hoisting load is borne by the main rib or the main frame. A special reinforcement structure can be provided at the location where the main container is heavily loaded, such as a main coolant outlet or a stiffener or reinforcing frame.

[0031] a sidewall insulation layer is disposed between the sidewall of the fission pool and the sidewall of the slowing pool, and the sidewall insulation material is solid particles; the side wall of the fission pool and the side wall of the moderate tank pass through the sidewall insulation layer The pressure is formed to laterally support each other, similar to the support of the tire casing to the inner tube. The fissile pool structure material is difficult to achieve high neutron transparency, and a thin wall structure is required; the slower tank and the heat insulation layer can be made of a material with high neutron transparency, and the relatively thicker slower pool can serve the side wall of the fission pool. Lateral support. The solid particles of the sidewall insulation layer may be selected from honeycomb particles or honeycomb pellets or hollow pellets or solid pellets or solid pellets, wherein the irregular honeycomb particles are optimal, the core density is small, and the flow is not easy to flow. Fill and suck. The solid particle component has properties of strong, heat resistant, high thermal resistance and neutron transparency, such as silica, silica-alumina, zirconia or alumina, of which silica is the most cost-effective. If pellets are used, a pressing device is added to the uppermost part of the side wall insulation layer to restrict the movement of the heat insulating material to prevent deformation of the fission pool; the compacting device structure includes a compression spring, a briquetting block and a spring retainer.

[0032] The bottom of the fission pool is provided with a load-bearing heat insulation layer, and the load-bearing heat insulation layer is a block solid, which has strong and heat-resistant characteristics, such as an insulating ceramic block, and the load-bearing heat insulation layer material has no requirement for neutron transparency, and has absorption. The neutron-capable material may be better, it can act as a bottom neutron shielding, and inexpensive non-nuclear grade materials can be used.

[0033] The fissile pool top cover or the slowing tank top cover can be sealed with a sealant. The conventional flange seal is not only bulky and requires high precision, and is not suitable for the top cover of the compact fission pool and the moderated pool. seal. Sealing the top cover with a sealant simplifies the seal and reduces the weight of the main container top. The sealant is a metal sealant or sealant, and the metal sealant is a fusible metal or a fusible alloy, especially heavy metals and alloys thereof. Sealants are only suitable for low temperature vessels such as slower tanks. The upper edge of the side wall of the container is provided with an annular groove, the inner edge of the annular groove is higher than the outer edge to prevent the sealant from falling into the container, and the outer edge of the top cover of the container is provided with an annular skirt downward. The sealing structure of the top cover and the side wall may be provided with a locking device to prevent the top cover from being punched by the internal pressure, and the locking device is a thread structure or a bolt structure or a spring clamp; when sealing the cover, the annular groove is uniformly filled with an appropriate amount. The liquid sealant inserts the annular skirt into the annular groove before the sealant solidifies, and then fastens the locking device, and the sealant solidifies to form a sealed structure; the metal sealant solidifies to form the top cover and the side wall firmly The sealing structure can heat the sealing structure to separate the metal sealant when it is separated; the heating structure can be provided by the sealing structure of the fusible metal. The fissile pool is selected from heavy metal sealant, and the slower tank is selected to be resistant to temperature and corrosion.

[0034] The fission cell provided with the thin-wall structure needs to minimize the weight of the top cover. When the fission cell air chamber is arranged at the top of the fission pool, the fission pool top cover can be reused without being affected by the corrosion of the main coolant, and the light weight can be used. High strength materials such as titanium alloys.

[0035] The slowing cell material selects a metal having high neutron transparency, such as aluminum, aluminum alloy, zirconium alloy, aluminum zirconium alloy, aluminum titanium alloy, zirconium-niobium alloy, nickel aluminum alloy. Among them, aluminum-based metal materials have the highest cost performance, and can meet the requirements of water corrosion resistance under the conditions of low temperature and low pressure in slower cells. In order to further improve the water corrosion resistance of aluminum-based metals, the surface of the slow-dissolving pool of aluminum or aluminum alloy may be plated with water-resistant gold Genus, water-resistant metal is zirconium or nickel or titanium.

[0036] Core and fuel element

Core and fuel components include: core characteristics and structure; fuel liner; closed fuel rod; rod bundle closed fuel assembly; casing closed fuel assembly; open fuel rod; rod bundle open fuel assembly; Casing open fuel assembly; exhaust member (including valveless exhaust member and valved exhaust member); fixation and positioning of fuel assembly and fuel rod; fuel chemical composition and physical form.

[0037] Core characteristics and structure:

A coupling core is provided in the fission pool of the fast reactor-type coupled nuclear reactor, which has the characteristics of a fast neutron core. The coupling core is a solid core composed of a fuel rod assembly composed of a fuel rod assembly, and a fuel tank may be disposed in the fuel rod, and the fuel is filled into the fuel tank or the fuel rod. The fuel assembly is a bundle fuel assembly or a casing fuel assembly, the bundle fuel assembly has no main casing, and the casing fuel assembly has a main casing. The fuel rod is a closed fuel rod or an open fuel rod, and the closed fuel rod constitutes a rod bundle closed fuel assembly or a casing closed fuel assembly; the open fuel rod constitutes a bundle open fuel assembly or a casing open fuel assembly .

[0038] The coupling core edge can be filled to make the core edge closer to complete. Bar bundle closed fuel assembly, casing closed fuel assembly, bundle open fuel assembly or casing open fuel assembly. The four fuel rod assemblies may have corresponding half-shaped or profiled components, half-shaped components or shaped The component fills in the nick of the core edge. The cross-section of the half-shaped component is half of the diagonal cut of the cross-section of the corresponding component, and the cross-section of the profiled component can be any shape, and the choice of shape depends on the complement effect.

[0039] A core base is disposed under the core, the core is fixed on the core base, and the core base is fixed on the bottom of the fission pool, and the core is mainly supported by the bottom of the fission pool, thereby reducing the bearing of the side wall of the fission pool. force. The coupled core can be designed as a candle core; the candle core is gradually burned from bottom to top, and the initial fissile nuclide is mainly distributed under the core fuel zone, and the concentration gradient is lower and higher, and the upper fuel passes through the proliferation. The reaction accumulates, and the cumulative speed is adapted to the upward velocity of the combustion zone. The higher the core fuel consumption rate is, the higher the lower the core, the more the core fissile initial charge is saved, the core life is longer, and the total fuel consumption depth is Big.

[0040] The coupled core sets a radial partition of two or three characteristics. Radial partitioning of two characteristics: The area near the slowing pool is the coupling area, and the area away from the slowing pool is the fast spectrum area. Radial zoning of three characteristics: adding a buffer between the coupling region and the fast spectral region to enhance core safety; the coupling region simultaneously performs thermal neutron and fast neutron nuclear reactions, and its fuel distribution ratio is close to that of the thermal neutron reactor Core; fast spectral region for fast neutron nuclear reaction, its fuel distribution ratio is close to the fast neutron core; buffer fuel distribution ratio characteristics are determined by the core safety design. A conversion fuel zone or a shield zone may be added to the periphery of the core of the special stack.

[0041] Fuel tank:

The fast reactor type coupled nuclear reactor uses a fuel rod assembly core, and the conventional fuel rod is a fuel directly filled into the fuel rod. Fuel The liner is a fuel inclusion that is filled into the fuel rod in a unitary form to isolate the fuel and fuel rods. The fuel tank is first subjected to the stress and corrosion of the fuel to protect the fuel rod cladding tube. The fuel liner is a seal that can be stored separately for long periods of time. The fuel bladder body includes a bladder tube, a bottom plug, a plug, a packing, a compression spring, a gas injection hole or a gas injection pipe. The outer diameter of the fuel liner is slightly smaller than the inner diameter of the fuel rod cladding tube, and the fuel expansion space is reserved. The inner tube is a cladding of the fuel inner liner, and both ends of the inner tube are sealed by a bottom plug and a top plug. The top plug is provided with a gas injection hole or a gas injection pipe, and a filler and a compression spring are arranged in the fuel tank, and the filler includes fuel. The gas injection hole or the gas injection pipe is used for pumping or injecting or exhausting, the gas injection hole is hole-shaped, and the gas injection pipe is short tubular; the gas injection hole or the gas injection pipe can be set as a self-opening sealing structure, and is sealed after the gas injection is completed. . After the fuel tank is heated or boosted or warmed up and boosted, the gas injection hole or the gas injection pipe is opened and exhausted by itself; the self-opening sealing structure is a burstable structure or a fusible sealing plug. Explosive structure: The gas injection pipe can burst, the burst type is burst of low-strength material or burst of low-strength structure; the low-strength material is material with low-strength material or low strength after heating, when the fuel tank temperature rises internally The air pressure is increased, and the gas injection pipe is opened and exhausted by pressure bursting; the low-strength structure is provided with a bursting groove on the gas injection pipe, the gas injection pipe wall is thin at the explosion groove, the gas pressure difference causes the cracking groove to form a crack, and the gas injection pipe is cracked and exhausted. Fusible sealing plug: The fusible sealing plug can be melted after heating, and can be composed of a single sealing agent or a plurality of sealing agents; a plurality of sealing agents are a plurality of sealing agents having different melting points, and the sealing plug has a lower melting point than the inner layer, and is sealed. The outer sealant is equivalent to the brazing material. After the core is started to warm up, the sealing plug is completely melted by heat, and the gas injection hole is opened and exhausted. A protective cover may be added to the top of the fuel tank. The protective cover is a sleeve-like or cap-shaped shape. The protective cover is provided with a hole for gas communication, and the protective cover is disposed outside the gas injection hole or the gas injection pipe. After the fuel liner is filled with the gas-filled seal, the sleeve-like shield is directly welded to the top of the plug; when the fuel tank is filled into the fuel rod, the cap-shaped shield is fixed on the plug by the fuel rod compression spring. The shield prevents the explosion or splash from contacting the fuel rod cladding tube; the fuel rod or fuel liner can be filled with a heat transfer medium such as helium or sodium.

[0042] Closed fuel rod: The closed fuel rod is a closed structure of a conventional fuel rod, and the main structure of the closed fuel rod is a rod-shaped shell tube structure closed at both ends, and the closed fuel rod body includes a lower end plug and a cladding Tube, compression spring, upper end plug, packing or fuel liner. The upper end plug and the lower end plug seal both ends of the cladding tube, the shell tube has a long air chamber, the air chamber is located at the upper part or the lower part, and a compression spring is arranged on the filler or the fuel tank; the filler in the fuel rod or the fuel tank The setting is the same, the nuclide filler is divided into three zones, from bottom to top: the down conversion zone, the fuel zone and the upconversion zone. The conversion zone is only initially loaded with convertible nuclide, and the fuel zone is initially filled with fissile nuclide.

[0043] Bar bundle closed fuel assembly: The rod bundle closed fuel assembly body includes a lower header, a bundle bottom grid, a skeleton tube, a spacer grid, a closed fuel rod, and an upper header. The skeleton tube, the positioning grid and the upper and lower sockets together form a skeleton of the fuel rod assembly, and a plurality of positioning grids are fixed on the skeleton tube bundle, and both ends of the skeleton tube are fixed to the upper and lower tube holders. The skeleton tube is of two types. The first type is a through-tube, which can be used as a guide tube (such as a guide tube for measurement). The second type is a solid tube. The ends of the tube are welded with end plugs, and the end plugs are fixed to the upper and lower tubes. The tube is provided with a convertible fuel, a compression spring and a short air chamber, and the solid tube is equivalent to a conversion fuel rod. The fuel rod passes through the positioning grid and is constrained and positioned; the fuel rod is fixed on the bottom layer of the bundle beam, and the bottom grid of the rod bundle is fixed to the lower tube seat The upper end is fixed to the skeleton tube. The lower header is provided with a positioning pin or a pin hole and a core bottom grid, and the lower tube seat is provided with a fixed structure (such as a bolt structure) to fix the component to the core bottom grid. The upper header has a positioning pin and a pin hole positioning on the core top grid.

[0044] Casing Closed Fuel Assembly: The casing closed fuel assembly body includes a pin, a bundle bottom grid, a main sleeve, and a closed fuel rod. The pin is provided with a sealed structure to prevent leakage, and the pin is also provided with a fixed structure (such as a bolt structure) fixed to the core bottom grid, a plurality of coolant inlet holes on the pin and a structure for controlling leakage flow, the main sleeve The lower end is connected to the pin, the fuel rod is located in the main sleeve, and the upper shield body can be added on the fuel rod. The middle part of the fuel rod is positioned by grid positioning or wire winding, and the bottom end of the fuel rod is fixed with the bottom layer of the rod bundle, the bundle The bottom grid plate is fixed at the lower end of the main sleeve or the upper end of the pin. The top end of the main sleeve is provided with a lifting operation head and a coolant outlet, and the upper part of the outer side of the main sleeve is provided with a distance between the block maintaining components.

[0045] Open fuel rod:

The most significant difference between open fuel rods and their components and conventional fuel rods and their components is that the upper portion is provided with an exhaust configuration.

[0046] The open fuel rod main body structure is a rod-shaped cladding tube structure with a bottom end closed and a top end opening, and an exhaust pipe is disposed at the top opening. The open fuel rod body includes a lower end plug, a cladding tube, a compression spring, an upper end plug, an exhaust capillary, a packing or a fuel liner. The ends of the fuel rod are respectively welded with end plugs, the bottom end is sealed by a lower end plug, the upper end plug is provided with an opening, the opening is welded with an exhaust pipe, and the fissile gas is discharged by the exhaust pipe. The open fuel rod has no air chamber or a short upper air chamber, and a compression spring is arranged on the filler or the fuel tank; the filler in the fuel rod or the fuel tank is set in the same manner, and the nuclide filler is divided into three regions. From the bottom to the top are the down conversion zone, the fuel zone and the upconversion zone. The up and down conversion zones are only initially loaded with convertible nuclei, and the fuel zone is initially filled with fissile nuclide. One or two shielding zones may be added to the fuel rod filling, and the neutron absorber is disposed in the shielding area to shield the remaining neutrons, thereby increasing the axial shielding function of the core. Set a shield area: Set an upper shield area at the top of the fill; Set two shield areas: Set the lower shield area at the bottom of the fill and the upper shield area at the top. The fuel rod filling may be provided with an adsorption zone filled with a honeycomb solid adsorbent to adsorb fission volatiles, the adsorption zone is located between the upconversion zone and the upper shielding zone or at the uppermost end of the filler, and the adsorption zone and the upper shielding zone may be exchanged. . There are six combinations of fuel rod fillings from bottom to top: downconversion zone - fuel zone - upconversion zone; downconversion zone - fuel zone - upconversion zone - adsorption zone; downconversion zone - fuel zone - upconversion zone - Upper shield area; Down conversion area - Fuel area - Up conversion area - Adsorption area - Upper shield area; Lower shield area - Down conversion area - Fuel area - Up conversion area - Upper shield area; Lower shield area - Down conversion area - Fuel zone - upconversion zone - adsorption zone - upper shield zone.

[0047] Bundle Open Fuel Assembly: The bundle open fuel assembly body includes a lower header, a bundle bottom grid, a skeleton tube, a spacer grid, an open fuel rod, an upper header, and an exhaust member. The skeleton tube, the positioning grid and the upper and lower sockets together form a skeleton of the fuel assembly, and a plurality of positioning grids are fixed on the skeleton tube bundle, and both ends of the skeleton tube are fixed to the upper and lower tube holders. The skeleton tube is divided into two types. The first type is a through-tube, which can be used as a guide tube (such as a guide tube for nuclear measurement); the second type is a real tube, and the end of the tube is welded with an end plug, through the end plug and the upper and lower tubes The seat is fixed, and the real tube is provided with a convertible fuel, a compression spring and a short air chamber. Convert fuel rods. The fuel rod passes through the positioning grid and is constrained and positioned. The lower end of the fuel rod is fixed on the bottom layer of the rod bundle, and the bottom grid of the rod bundle is fixed on the upper end of the lower tube seat or fixed on the skeleton tube.

[0048] Casing Open Fuel Assembly: The ferrule open fuel assembly body includes a pin, a bundle bottom grid, a main sleeve, an open fuel rod, and an exhaust member. The pin is provided with a sealed structure to prevent leakage, and the pin is also provided with a fixed structure (such as a bolt structure) fixed to the core bottom grid, a plurality of coolant inlet holes on the pin and a structure for controlling leakage flow. The middle section of the fuel rod is positioned by grid or wire. The bottom end of the fuel rod is fixed to the bottom of the rod bundle, and the bottom grid of the rod bundle is fixed at the lower end of the main sleeve or the upper end of the tube. The upper portion of the outer side of the main sleeve can be provided with a spacer to maintain the distance between the components.

[0049] The open fuel rod assembly may be provided with a bundle top grid. The top layer of the bundle beam is fixed on the upper end of the main body of the fuel assembly, that is, in the upper tube seat or the upper end of the main sleeve, and the top layer of the rod bundle is provided with a positioning hole and a coolant hole, and the exhaust thin tube passes through the top layer of the bundle beam The positioning hole on the upper side allows the fuel rod to be positioned, and an anti-vibration spring is arranged between the upper end plug of the fuel rod and the top grid of the rod bundle, and the anti-vibration spring is sleeved at the base of the exhaust thin tube. The base of the exhaust pipe that requires the top positioning can be appropriately thickened and thickened to enhance the strength against external forces.

[0050] Exhaust member:

An exhaust member is disposed at an upper portion of the open fuel rod assembly, and a lower end of the exhaust member is coupled to the fuel assembly body. The exhaust member body includes a restraining portion and an exhaust main pipe. The lower part of the exhaust member is a restraining portion, and the restraining portion is sleeve-shaped or flared or claw-shaped; the upper end of the sleeve-shaped restraining portion may be provided with a restraining portion receiving plate, and the restraining portion receiving plate is provided with a coolant outlet hole and fixing with other components Construction; The upper part of the exhaust member is the exhaust main. The pressure relief valve is provided at the top of the exhaust main pipe or the pressure relief valve is not provided; the exhaust member of the pressure relief valve is a valved exhaust member, and the exhaust member without the pressure relief valve is a valveless exhaust member. A lifting head can be provided outside the exhaust member.

[0051] Valveless Exhaust Member: The valveless exhaust member body includes a restraining portion, an exhaust pipe bundle, and an exhaust main pipe, and the exhaust pipe is simply restrained into a tight exhaust pipe bundle and directly inserted into the exhaust pipe. Supervisor, the exhaust pipe can be extended and retracted in the exhaust main.

[0052] Valve Exhaust Member:

The valved exhaust member body includes a restraining portion, a seal sleeve, an exhaust pipe bundle, a seal head, an exhaust main pipe, and a pressure relief valve. The pressure relief valve is arranged at the top of the exhaust main pipe, and after the exhaust pipe in the valve exhausting member is firstly subjected to the rotational bending constraint in the restraining portion, the upper end portion is constrained into a tight exhaust pipe bundle, that is, the exhaust pipe is in The constrained section has a loosely rotating state, and the twisted exhaust pipe has a spring-like function, and has a certain flexing and extension function to buffer the fuel rod deformation stress and meet the requirement of the fuel rod irradiation elongation. The lower end of the sealing sleeve is fixed to the upper end of the restraining portion, and the sealing sleeve is sleeved into the exhaust pipe bundle, and the two are integrally sealed at the top end (such as brazing seal) to form an exhaustable sealing head, and the exhaust main pipe and the sealing sleeve are further The seal is fixed so that fissile gas can only be discharged through the exhaust main and the pressure relief valve. Brazing solder is generally difficult to meet the high requirements of high temperature resistance and corrosion resistance. The sealing head of the brazed seal needs to be isolated from the main coolant. The sealing sleeve is appropriately lengthened, and the retaining gas is retained in the sealing sleeve when the main coolant is poured. The discharged trapped gas acts as a barrier between the seal head and the primary coolant. a gas injection hole is provided in the exhaust main pipe Or the gas injection pipe, after the fuel assembly is manufactured, vacuuming and gas injection are performed, and the gas injection hole or the gas injection pipe is closed.

[0053] The sealing head is brazed and sealed, and the process flow is: after the fuel rod is finished, vacuuming and closing the end of the exhaust pipe

(such as mechanical pressure sealing after induction heating), before the exhaust pipe can be closed, the test gas can be poured according to the need. The length of the exhaust pipe is slightly longer than the top of the sealing sleeve. → Complete the fuel rod air tightness and flaw detection → complete Main assembly of the fuel rod assembly → Annealing the exhaust pipe and rotating the lower part of the exhaust pipe → Restricting the upper part of the exhaust pipe to form a tight exhaust pipe bundle → Welding joint and sealing sleeve connection → Connection constraint And the fuel assembly body and the bundle of the exhaust pipe into the sealing sleeve → the gap between the exhaust pipe with the wire plugged → the surface treatment of the seal → heating the solder pool to the solder melting (the melting point of the solder is higher than the main cooling Maximum operating temperature of the agent → Inverted fuel rod assembly, insert the sealing part into the solder tank at a suitable depth, and after the soldering liquid is fully immersed, take it out and cool it into a sealing head → Finish the polished sealing sleeve → Cut off the end of the sealing head, finish polishing The exhaust pipe port ensures that each exhaust pipe is unobstructed.

[0054] Pressure relief valve:

A pressure relief valve is provided at the top of the valve exhausting member, and the pressure relief valve is a spring type pressure relief valve or a fusible heavy metal pressure relief valve or a double pressure relief valve. An exhaust adsorption zone may be disposed in the exhaust main body of the valve exhaust member, and the exhaust adsorption zone includes an adsorbent body positioner, an adsorbent body, and a suction body compression spring. The adsorbent is a rod-shaped box with a mesh hole filled with an adsorbent. The sorbent positioner is a positioning spring or an elastic clamp to prevent displacement of the absorbing body. The absorbing body is pressed against the spring to compress the absorbing body against air flow impact and displacement.

[0055] Spring type pressure relief valve: The spring type pressure relief valve is cylindrical, and its main body includes a valve housing, a lower valve body, an upper valve body, a spring, a spring positioning head and a pressing screw. The valve housing is cylindrical, and the side of the lower valve body is fixed and sealed with the valve housing; the lower valve body and the upper valve body are convex and concave corresponding valve structures, and the convex and concave surfaces are closely attached to achieve sealing, and the convex and concave surfaces can be separated to realize the discharge. Air venting pressure; the corresponding structure of the lower convex and concave concave is favorable for the gas to wash away the condensate, the valve body is not easy to scale; the vent hole is arranged in the middle of the lower valve body, and the vent hole is arranged on the side of the upper valve body; the upper end of the upper valve body is connected with the spring, A spring positioning head is connected to the upper end of the spring, the pressing screw presses down the spring positioning head, the pressing screw and the upper end of the valve housing are screwed, and the spring positioning head and the pressing screw are provided with a vent hole for gas discharge.

[0056] Fusible heavy metal type pressure relief valve: The valve function of the fusible heavy metal type pressure relief valve is replaced by liquid heavy metal, and the fusible heavy metal type pressure relief valve includes an annular groove, a cap, a fusible heavy metal and an anti-deblocking head. The cap is the upper valve body, which is a blind tube shape, the annular groove is a lower valve body, and the cap and the annular groove form a mosaic structure with a gap. The gap of the annular groove is filled with a fusible heavy metal, and the fusible heavy metal is sealed. The anti-deblocking cap prevents the cap from being washed away by the internal high-pressure airflow, such as anti-off screws. The working temperature of the fusible heavy metal pressure relief valve is above the melting point of the fusible heavy metal. The heavy metal solidified below the working temperature is equivalent to the fixing and sealing action of the solder; when the pressure is released, the differential pressure pushes the gas through the heavy metal liquid. The U-channel, the pressure difference is determined by the specific gravity and height of the heavy metal liquid. The annular groove may be a single member or a composite member, and the annular groove of the single member, that is, the lower valve body is an annular groove-like whole; the annular groove of the composite member is welded by the valve housing, the lower valve body and the central air pipe Constructed after sealing. [0057] Double pressure relief valve: Double pressure relief valve is two pressure relief valves connected in series at the top of the open fuel assembly, the lower pressure relief valve is a fusible heavy metal pressure relief valve, and the upper is a spring type pressure relief valve, and the lower valve body It can be used as an anti-deblocking head for fusible heavy metal type pressure relief valves. The advantages of the double pressure relief valve are good sealing effect. The heavy metal solidified at low temperature can be completely sealed. The double pressure relief valve can double protect the oil at high temperature. The heavy metal liquid can also absorb the volatile matter in the fission gas to prevent the valve body from scaling and increase. The reliability of the spring type pressure relief valve.

[0058] Fixing and positioning of fuel assemblies and fuel rods:

The main coolant of the fast reactor type coupled nuclear reactor mainly uses heavy metals, and the core has a large buoyancy. The fuel rod and fuel assembly are suitable for fixing at the bottom and positioning at the top. The bottom fixing is advantageous for resisting the primary coolant buoyancy and the upper momentum, and the force of the fuel assembly can reduce the bending deformation of the fuel rod and the assembly. The top positioning defines the radial position and the fuel rod and fuel assembly can still be displaced vertically to meet the material's radiation elongation requirements.

[0059] Fixing and positioning of the fuel assembly: The bottom plate of the fuel assembly may be fixed, and the lower header or the pin of the fuel assembly is fixed to the bottom plate of the core, such as bolt fixing; the top of the fuel assembly may be a top plate Positioning, the positioning pin at the upper end of the closed fuel rod assembly is positioned with the core top grid. The open fuel rod assembly is positioned with the upper end of the exhaust main pipe passing through the positioning hole of the core top grid plate, and the anti-vibration spring is disposed or not disposed between the exhaust main pipe and the core top grid plate. Set anti-vibration spring: Set the fixed spring collar on the exhaust main pipe, the anti-vibration spring sleeve is placed on the exhaust main pipe, the lower end of the anti-vibration spring abuts on the fixed spring bead, and the upper end of the anti-vibration spring bears against the core top grid plate, The vibrating spring prevents the fuel assembly from vibrating and also meets the component's radiation elongation.

[0060] Fuel rod fixing method: a lower portion of the fuel assembly is provided with a bundle bottom grid plate, and the fuel rod is fixed on the bottom layer of the bundle beam, and the fixing manner may be screw fixing or welding fixing or insert fixing. Threading: The bottom end of the fuel rod and the bottom of the rod bundle are provided with bosses, grooves and screw holes for fixing. Firstly, the boss and groove are positioned to prevent the fuel rod from rotating loosely. The screw is fixed by screws; the other configuration is that the lower end of the fuel rod is screwed with the screw hole and the screw hole of the bottom of the bundle bottom. Welding fixing: The bottom end of the fuel rod is provided with a notch, and the strip grid of the bottom layer of the rod bundle is inserted into the notch of the lower end plug and then fixed by welding. Inlaid fixing: The bottom end of the fuel rod is provided with a keyway, and the corresponding bottom beam guide plate is provided with a corresponding beam guide rail, and the beam guide rail is slid into the keyway for inlaid fixing.

[0061] Fuel chemical composition and physical form:

Fast-stack coupling nuclear reactors can use either traditional oxide ceramic fuels or advanced ceramic fuels such as nitride or carbide or silicide fuels; pellet fuels or pellet fuels can be used. The fuel liner is more suitable for directly filling the particulate fuel, which can solve the problem that the advanced ceramic fuel is not easily sintered, and the fuel liner can restrain the pellet fuel from sintering. The fuel particles are in close contact with the inner tube, and the inner tube is subjected to the first expansion stress. When the fuel gradually expands to the maximum diameter, the fuel inner liner and the cladding tube are pressed together, the heat transfer efficiency is increased, and the overall heat transfer efficiency is better. The pellet fuel advantageously reduces the fuel rod temperature. The initial heat transfer can rely on a gas or liquid heat transfer medium such as helium or sodium. The fuel liner separates the fuel from the cladding tube, which reduces the stress and corrosion of the cladding tube, and the cladding tube is not easily broken, which is beneficial to prolong the life of the fuel rod. Fuel liner The inner wall of the fuel rod cladding tube is isolated and protected. Depending on the function and environment of the inner and outer tubes, the two materials can be optimized in different directions. Open-ended fuel rods are more suitable for advanced nuclear fuels than closed fuel rods. Open-type fuel rods can use high thermal conductivity nitride or carbide or silicide fuels to reduce fuel pellet temperatures and avoid certain fission product pairs. The corrosion of the shell tube, such as yttrium oxide; the open fuel rod self-venting can solve the problem of excessive gas production of the nitride fuel. More importantly, nitride or carbide or silicide fuel is the way to solve the problem of post-treatment of bismuth-based spent fuel, because sintered sulfhydryl oxide is extremely difficult to dissolve, and hydrofluoric acid must be added to the strong acid solution when dissolved. Severe corrosion of the facility.

[0062] Slowing liquid circuit and nuclear control system

The contents of the slow fluid circuit and the nuclear control system include: a slower liquid circuit; a slower liquid level nuclear control system; a barrier screen nuclear control system.

[0063] The slowing tank is filled with a liquid moderator, the slowing tank is provided with a slowing liquid circuit, and the slowing liquid is cooled by the slowing liquid cooler; the reactor is provided with a nuclear control system to regulate the core power and perform the shutdown operation, and the nuclear control The system is a slowing pool liquid level nuclear control system or a barrier screen nuclear control system or a slowing pool displacement nuclear control system or a control rod nuclear control system; the slowing pool liquid level nuclear control system is set in a specific slowing liquid circuit, The slowing liquid circuit is a one-way slowing liquid circuit, and the slowing liquid is always input from the top of the slowing pool; the slowing liquid level nuclear control system changes the neutron exchange and medium by adjusting the liquid level height of the moderator in the slowing pool. The sub-energy spectrum is used to achieve the purpose of regulating the reactivity of the core, and the passive shutdown is automatically performed in an emergency; the slowing liquid in the one-way slowing liquid circuit is not filled with the slowing tank, and the reactor movement can cause the slowing liquid to fluctuate. The slowing pool level nuclear control system is not suitable for mobile reactors; the barrier screen nuclear control system includes a specific slowing liquid circuit and a barrier screen mechanism, and the slowing liquid circuit is a variable direction slowing liquid circuit, which is slow in normal operation. Chemical fluid from slow At the bottom of the chemical tank, the top output is input, and the slowing tank is filled with the slowing liquid, which is not affected by the reactor movement; during the shutdown, the slowing liquid is changed to the input from the top of the slowing pool, and the slowing pool does not accumulate the slowing liquid; The system regulates core reactivity by blocking neutron exchange, which has no slowing fluid fluctuations, is suitable for mobile reactors, and can also be used for stationary reactors. The slowing pool displacement nuclear control system is an overall mobile slowing pool. By changing the coupling structure between the slowing pool and the fission pool, the neutron exchange and the coupled nuclear reaction are changed, thereby regulating the core reactivity; the slowing pool displacement nuclear control system is suitable. Micro or small nuclear reactors, especially space nuclear reactors.

[0064] Slowing pool level nuclear control system:

The slowing pool level nuclear control system adopts a one-way slowing liquid circuit. The one-way slowing liquid circuit inputs the slowing liquid from the top of the slowing tank, and the main body thereof includes a slowing tank, a liquid storage tank, a slowing liquid, an infusion pump, an infusion tube, a liquid sprayer, a return pipe, and a slow solution liquid cooler. The one-way slowing liquid circuit is driven by the infusion pump, and the circulation path is: liquid storage tank→infusion pump→sprayer→slowing pool→return pipe→moderator liquid cooler→liquid storage tank. The position of the reservoir is lower than that of the slower tank, and the slower liquid relies on gravity to return. The larger the difference between the reservoir and the slower pool, the greater the backflow potential. The infusion tube is provided with an infusion pump, and the infusion pump quantitatively supplies the slowing liquid to the slowing tank, the first end of the infusion tube is connected to the bottom of the liquid storage tank, and the other end is connected to the liquid sprayer on the upper part of the slowing pool, and the main body of the liquid sprayer is provided with a nozzle. Container Or a pipe fitting (such as a hollow grid plate container or a mesh pipe or a branch pipe), the function of which is to spray or spray the slowing liquid to the surface of each device in the slowing tank, and the slowing liquid from the top to the side The lower stream takes away the heat from the device. The return pipe is a large-diameter pipe to meet the requirements of fast shutdown; the slower liquid cooler is a cooling and temperature control device for the slowing liquid, which is disposed inside or outside the liquid storage tank. The surface of the parts to be cooled in the slowing tank may be provided with a screen, and the screen reduces the slowing flow rate of the liquid, helps the slowing liquid to evenly distribute on the surface of the part, and prevents the slowing liquid from splashing.

[0065] The main body of the slowing pool level nuclear control system comprises a one-way slowing liquid circuit, a gas balance tube and a liquid flow control mechanism. The gas balance tube connects the top of the slowing tank and the top of the reservoir to balance the pressure of the two tanks. The liquid flow control mechanism comprises a liquid flow controller, a shutdown valve, a monitoring device and a control circuit; the liquid flow controller is a single electric regulating valve or is composed of a plurality of electric regulating valves, and the function thereof is to precisely adjust the level of the slowing pool; The stack valve is normally closed and opened during shutdown. The shutdown valve can be one or more large-diameter normally closed electric valves connected in series; the monitoring device includes a moderator liquid level monitoring device and a temperature sensor. When the slowing tank liquid level nuclear control system is in normal operation, the infusion pump pumps the slowing liquid into the slowing tank, and the sprayer disperses the slowing liquid to the surface of each device and flows down in the slowing tank, and the slowing liquid depends on gravity. The liquid flow controller is returned to the liquid storage tank through the return pipe at a certain flow rate, and is cooled and controlled by the slow solution liquid cooler. When the reactor is shut down, the shutdown program is started or the power supply of the shutdown valve is cut off. The normally closed shutdown valve is automatically opened, and the slowing liquid in the slowing tank is quickly returned to the liquid storage tank through the large-diameter shutdown valve, and the slowing pool is not Accumulation of slowing liquid, thermal neutron and thermal neutron fission reaction disappears, core reactivity drops sharply, so as to achieve passive shutdown; slowing liquid circuit continues to perform cooling function during shutdown; slowing pool level The workflow of the nuclear control system:

(1) Reactor power control: It is executed by the liquid flow controller to adjust the level of the moderator liquid in the slowing tank → change the neutron exchange and neutron energy spectrum → regulate the core power.

[0066] (2) Shutdown operation: start the shutdown program or cut off the power of the shutdown valve → the shutdown valve is automatically opened → the slow solution is quickly returned to the storage tank through the large-diameter shutdown valve → the slowing pool is slow The liquid loses the neutron moderation function → the thermal neutron fission reaction is terminated → the core cannot stop the chain reaction and stops.

[0067] (3), shutdown cooling: the shutdown valve is in the power-off state → the infusion pump continues to run → the slow fluid circuit continues to circulate → the sprayer sprays the moderator to the components in the slowing tank and cools → slow The chemical liquid is quickly returned to the liquid storage tank through the shutdown valve, and the slowing liquid cannot be accumulated in the slowing tank.

[0068] (4) Recovery of the slowing pool liquid level nuclear control system: shutting down the shutdown operation or restoring the power supply of the shutdown valve → the shutdown valve is in the closed state → the slowing liquid is returned to the liquid storage tank through the liquid flow controller → Adjust the flow controller to keep the slowing tank level at a suitable height.

[0069] Barrier screen nuclear control system:

The barrier screen nuclear control system uses a variable direction slowing liquid circuit. The main body of the variable direction slowing liquid circuit comprises a slowing pool, a liquid storage tank, a slowing liquid, an infusion tube, an infusion pump, an upper infusion tube, an upper infusion valve, a lower infusion tube, a lower infusion valve, a liquid sprayer, an upper return tube, Lower reflux Tube, lower return valve and slower liquid cooler. The slowing liquid of the variable direction slowing liquid circuit is transported by the infusion pump. During the normal operation period, the infusion pump provides all the power for transporting the slowing liquid; during the shutdown period, the gravity return is increased, and the difference between the liquid storage tank and the slowing pool is larger. The greater the backflow potential. The lower end of the infusion tube is connected to the bottom of the liquid storage tank, and the infusion tube is provided with an infusion pump, and the upper infusion tube and the lower infusion tube are separated above the infusion pump. The upper infusion tube is connected to the sprayer, and the main body of the sprayer is a container or a pipe member provided with a nozzle (such as a hollow grid plate container or a mesh pipe or a branch pipe), and the slow solution passes through the spray device. The slowing liquid is dispersed to the surface of each device in the slowing tank, and the slowing liquid flows from the top to the bottom to carry away the heat on the device. The lower infusion tube is connected to the bottom of the slowing pool; the lower return tube is a large diameter tube to meet the requirements of fast shutdown. The lower infusion valve is normally open, closed during shutdown, and the lower infusion valve can be a normally open electric valve. The upper infusion valve and the lower return valve are in a normally closed state, and are opened during shutdown, and the upper infusion valve and the lower return valve may be normally closed electric valves. The circulation path during normal operation is: reservoir → infusion tube → infusion pump → lower infusion valve → lower infusion tube → slowing pool → upper return tube → slow solution cooler → reservoir. The circulation path during shutdown is: reservoir → infusion tube → infusion pump → upper infusion valve → upper infusion tube → sprayer → slowing pool → lower return valve → lower return tube → slow solution cooler → liquid storage Pool. The upper return pipe function during shutdown is converted to gas balance, balancing the air pressure in the slowing tank and the reservoir. The surface of the parts to be cooled in the slowing tank can be provided with a screen, and the screen reduces the slowing flow rate of the liquid, helps the slowing liquid to evenly distribute on the surface of the part, and prevents the slowing liquid from splashing.

[0070] The main body of the barrier screen nuclear control system comprises a variable direction slowing liquid circuit and a blocking screen mechanism; the main body of the blocking screen mechanism comprises a barrier screen driver, a driving belt, an upper guiding rod, a sealing sliding sleeve, a sealing ring, a blocking screen, a lower guiding rod and Lower guide tube. The blocking screen is disposed on the side of the slowing pool near the fission pool, the blocking screen is a cylindrical or curved plate body of the lower part of the fork, the lower guiding rod is provided with a lower guiding rod, and the upper guiding rod is arranged at the upper part of the blocking screen. The sealing sleeve is arranged on the top of the slowing pool or on the upper deck of the slowing pool. The sealing sleeve is provided with a sealing ring and a sliding structure, and the upper guiding rod can slide in the sealing sleeve; the lower guiding rod slides and is positioned at the lower guiding Inside the tube, the lower guide tube is provided with a leak hole. The barrier screen has the function of blocking heat-insulating neutrons or all neutrons. The barrier screen driver drives the barrier screen to move up and down. The moving barrier screen changes the neutron distribution and neutron exchange in the main container, thereby changing the core reactivity and regulating the core power. . The shutdown operation is performed by the variable direction slowing liquid circuit, the shutdown program is started or the power supply of the valve is shut off, the normally open lower infusion valve is closed, the normally closed upper infusion valve and the lower return valve are automatically opened, and the slowed liquid passes through the lower return tube. Rapidly flow into the reservoir, the gas in the reservoir enters the slow pool to balance the two chambers through the upper return tube, the slower pool can not accumulate the slow solution, the thermal neutron and thermal neutron fission reaction disappears, and the core reactivity drops sharply. In order to achieve the purpose of passive shutdown; during normal operation, the slowing liquid circulates from bottom to top, the slowing tank is filled with slowing liquid, and the cooling function is efficient; during the shutdown, the slowing liquid circuit changes direction from top to bottom. The slowing liquid flows on the surface of each device to continue the cooling function.

[0071] Proliferation fuel system

The contents of the proliferating fuel system include: a proliferative rod system; separation and purification of the proliferating fuel.

[0072] The proliferation fuel system is provided in the slowing tank, and the proliferating fuel system is cooled by the slowing liquid. Proliferation fuel system Colonized fuel system or isolated proliferating fuel system. The proliferating fuel feedstock (convertible nuclides) of the immersion-proliferating fuel system is immersed in the slowing liquid, and the slowing liquid performs a solvent function to dissolve a part of the nuclide in the proliferating fuel, and is taken out of the reactor through the slowing liquid circuit and outside the reactor It is extracted online. The immersed proliferating fuel system has a complicated structure, and also increases the functional load of the slowing liquid. The composition of the slowing liquid is complex and corrosive, and the structural material of the slowing tank is required to be high, which causes fouling of the slowing liquid circuit, and the slowing liquid circuit It has a negative impact and is difficult to operate. The isolated proliferating fuel system is a proliferative rod system, the proliferating fuel is filled in the proliferative rod, and the proliferating fuel is isolated from the moderator; the isolated proliferative rod system has a simple structure and high efficiency, and the slowed liquid has high purity, single function and high stability. .

[0073] Proliferation rod system:

The proliferative rod system body includes a slow solution loop, a proliferation rod, a proliferation rod sleeve, a cannula grid, a rod changing mechanism, and an attachment. The proliferative rod is a rod-shaped shell tube structure sealed at both ends, and is filled with a proliferating fuel raw material (convertible nuclides). The proliferative rod sleeve is a cannula, which is a isolating sleeve between the proliferative rod and the slowing tank, and is fixed on the slowing tank top cover or the slowing tank upper deck or the slowing tank bottom plate, and the open end thereof is outside the slowing pool The joint of the proliferative rod sleeve and the fixing surface is a sealed structure. The proliferative rod cannula isolates the growth rod and the slowing solution, facilitating the online replacement of the proliferative rod, and its length and cross-sectional shape are compatible with the proliferative rod. The casing grid is reinforced with a proliferation rod sleeve to prevent deformation. The tube portion of the proliferative rod and the proliferative rod sleeve is made of a material having a high transparency to the neutron, such as an aluminum- or zirconium-based metal material. The bar changing mechanism is an online replacement device for the proliferation rod. The bar changing mechanism can be arranged above or below the slowing pool, and there is a bar barrier area (such as a pipe) above the slowing pool, and the bar changing method or setting is selected below. Replacement replaces the proliferation rod; the replacement does not need to be replaced online, only need to be replaced when the slower tank is opened, the substitute can be a secondary neutron source component or a reflective rod or reaction rod, and the secondary neutron source assembly is used under the reactor The secondary start or new heap start, the reaction rod is used to make artificial elements. The rod changing mechanism of the proliferative rod system can be provided with a positioning function for the proliferative rod and an automatic rod changing function. The accessory device includes a temperature detecting device, and the temperature sensor is built in the proliferative rod. When the temperature inside the proliferative rod is higher than the normal value, it indicates that a fission reaction occurs in the proliferative rod, and the content of U-233 has reached an extractable range, and the rod must be Replacement; In order to increase the heat dissipation effect of the proliferative rod and the proliferative rod sleeve, the thermal fluid may be filled in the proliferative rod sleeve or the proliferation rod.

[0074] The main coolant outlet pipe and other pipes passing over the slowing pool have an effect on the online replacement of the proliferative rod, and the setting method is:

(1) Reduce the overall height of the slowing pool, and the main coolant output pipe directly passes over the top cover of the slowing pool.

[0075] (2) only reducing the height of the localized area of the slowing pool through which the main coolant output pipe passes, the area forming a closed "U" shaped zone, and the main coolant output pipe is located in the "U" shaped zone, moderated The top cover of the pool is discontinuous by the "U" shaped area.

[0076] (3) In order to reduce the influence of the main coolant output pipe on the online replacement of the growth rod, the relevant main coolant output pipe section may be designed as a side flat outlet and a side flat pipe to reduce the shielding area.

[0077] The proliferation rod includes a bottom plug or bottom plate, a cladding tube, a filler, a temperature sensor, and a tip portion. The bottom end is plugged by the bottom end or The bottom plate is sealed, the upper end is sealed by the top end portion, and the operation head is arranged on the top end portion for the rod changing mechanism to grasp. The initial filler (proliferating fuel feedstock) is a hydrazine compound and the temperature sensor is placed in the fill. The proliferative rod is a repetitive use member or a disposable member, the repetitive growth rod can be used multiple times, the bottom plug and the top end portion can be separated from the cladding tube, and the cladding tube is screwed and sealed with the bottom end plug and the tip end portion. .

[0078] Separation and purification of proliferating fuel:

Separation and purification of proliferating fuels uses a sparingly soluble compound separation process: Separation of certain types of antimony compounds over the inert nature of uranium compounds, proliferating fuel feedstocks are insoluble bismuth compounds, and uranium compounds converted from such insoluble bismuth compounds are soluble. . The poorly soluble compound is specific to a specific solvent, and thus there are various kinds of poorly soluble cerium compounds; the solvent may be water or an acid or an alkali solution or an organic solvent, and the poorly soluble cerium compound is a crystalline cerium oxide or hydrogen. A cerium oxide or cerium salt or a cerium or an organic cerium compound.

[0079] The separation process of the insoluble bismuth compound: the refractory bismuth compound in the proliferative rod receives the neutron radiation→ the in-line extracted proliferative rod is placed in the storage chamber (9-11 months) until the Pa-233 is fully decayed into U-233- The proliferative rod is taken out and the pulverized fuel is taken out. The proliferating fuel is taken out from the proliferative rod and pulverized. The pulverized proliferating fuel is put into a dissolution tank, and after thorough stirring, clarification → separation of the solution and precipitation; and the precipitate is dried to obtain a Th-232 compound. The separated solution is subjected to solute and solvent separation, and the solute isolate is dried to obtain a U-233 compound.

[0080] The separation and purification of the proliferating fuel employs a soluble compound separation process: The proliferating fuel feedstock is a soluble cerium compound, and the uranium compound converted by the soluble cerium compound is also soluble. The soluble compound is for a specific solvent, and thus there are various kinds of soluble cerium compounds; the solvent may be water or an acid or an alkali solution or an organic solvent, and the soluble cerium compound is amorphous cerium oxide or Barium hydroxide or strontium salt or citrate or organic hydrazine compound.

[0081] The separation process of the soluble cerium compound: the insoluble bismuth compound in the proliferative rod receives the neutron radiation→ the in-line extracted proliferative rod is placed in the storage chamber (9-11 months) until the Pa-233 is fully decayed into U-233- The proliferative rod is taken out of the proliferative fuel and pulverized → the pulverized proliferating fuel is put into the dissolution tank, stirred and dissolved → the proliferating fuel solution is extracted → U-233 is extracted from the solution; the solute is separated from the extract and dried to obtain the U-233 compound; The solute is separated from the remaining liquid and dried to obtain a Th-232 compound.

Other facilities

Other facilities include: main coolant auxiliary heating and insulation device; main coolant oxygen control system; fission pool air chamber and fission gas purification system; residual heat removal system; neutron source mechanism and nuclear measurement device.

[0083] Main coolant auxiliary heating and heat preservation device:

The main coolant is liquid heavy metal, especially lead or lead bismuth eutectic; the main circuit is the main coolant circuit, the main circuit can be set with the main coolant auxiliary heating and insulation device, the main coolant auxiliary heating and insulation device is set at the bottom of the fission pool and the circulation Its function on the pipeline is to melt the solidified main coolant and prevent the main coolant from solidifying. [0084] Main coolant oxygen control system:

Liquid heavy metals have certain solubility and corrosiveness to metal materials. The most effective anti-corrosion method is to maintain the integrity of the oxide film on the metal surface by oxygen control technology. The available data show that under the condition of strictly controlling the oxygen content of lead and antimony liquids. , The protective oxide film on some stainless steel surfaces can be intact for a long time. The main circuit is provided with an oxygen control system, which can reduce the corrosion of the main coolant to the material. The oxygen control system is a gas phase oxygen control system or a solid phase oxygen control system. The oxygen measuring probe of the oxygen control system can be selected from a zirconia oxygen sensor.

Gas phase oxygen control system: The gas phase oxygen control system main body includes an oxygen control gas circuit, a gas diffusion device, a gas pump, and a prosecution device. The oxygen-controlled gas circuit includes a gas mixing chamber and a circulation air passage, and the gas mixing chamber mixes the oxygen-control gas component to a proper ratio; the gas diffusion device is a pipe or a container through which the coolant flows, and may include a stirring device, and the gas diffusion device may The main circulation pump or the main circulation tube or the fission pool air chamber is replaced; the air pump blasts the oxygen control gas into the gas diffusion device, the oxygen control gas is evenly dispersed into the main coolant, and the remaining dissolved gas is returned to the gas mixing chamber for re-distribution . The prosecution device detects the oxygen content of the main circuit and the proportion of the gas component in the oxygen-controlled gas circuit, and instructs the gas mixing chamber to regulate each gas component. The gas phase oxygen control system can adopt a ternary gas combination, the ternary gas includes an oxidizing gas, a reducing gas and a carrier gas; the oxidizing gas can be selected from water vapor or oxygen or carbon dioxide, and the water vapor is most easily regulated; the reducing gas can be selected from hydrogen or Carbon monoxide, hydrogen is most suitable, hydrogen can reduce excess heavy metal oxide to remove solid impurities; carrier gas can choose argon, argon is the most cost-effective; ternary gas combination can choose H ₂ 0 / H ₂ / Ar or 0 ₂ / H ₂ / Ar or C0 ₂ / CO/ Ar; It is more feasible to combine H ₂ 0/W Ar, H ₂ / Ar with low concentration of hydrogen into water with adjustable temperature to obtain H ₂ 0 with adjustable water vapor content. / H ₂ / Ar ₀

[0086] Solid Phase Oxygen Control System: The main body of the solid phase oxygen control system includes a mass exchanger and a prosecution device. The mass exchanger is a vessel type device filled with oxide solid particles, which can be disposed on the branch circuit of the main circuit. The oxide solid particles can be dissolved in the main coolant in a small amount, such as lead oxide PbO; the main coolant flows through mass exchange. The solute exchange is performed on the oxide solid particles, that is, the oxide dissolution and solute deposition of the solid phase reaction. The prosecution device includes a thermostat and a flow controller, and the prosecution device detects and regulates the temperature or flow rate of the main coolant flowing through the oxide solid particles or the branch opening time, and controls the main coolant by controlling the oxide dissolution and precipitation process. Oxygen content. The branch power can be provided by the main circuit jet pressure differential. The solid phase oxygen control system may add a bypass arrangement to the hydride dissolution unit to coordinate the regulation of the oxygen content of the main circuit, and the hydride dissolution unit may be disposed at the other end of the main circuit opposite the mass exchanger.

[0087] Fission cell chamber and fission gas purification system:

A fission cell chamber may be disposed at the top of the fission cell of the fixed reactor, and the gas generated in the fission pool or the fissile gas discharged from the open fuel rod may be discharged to the fission cell chamber. The fission cell with the open fuel rod assembly can be provided with a double-layer fission cell chamber, the exhaust main pipe of the open fuel rod assembly passes through the core top grid plate, and the core top grid plate separates the fission pool air chamber into the fission pool gas chamber Room and fission pool under the air chamber. [0088] The reactor may be provided with a fissile gas purification system, which is a gas circulation purification system, and functions to cool components and remove fission gas components such as iodine, hydrazine, bromine, and hydrazine having chemical activity and nuclear activation. The fission gas purification system is a closed gas circulation circuit, and the main body of the fission gas purification system includes a fission pool air chamber, an air pump, a gas purification cooling chamber, an exhaust gas tank, a gas distribution tank, a gas mixing chamber, a gas supply pump, a flow control valve, and a monitoring device. The fission gas is cooled and purified in the gas purification cooling chamber, and the excess purified gas is injected into the exhaust gas tank for storage, and the gas mixing chamber will receive the gas in the gas distribution tank (such as the oxygen tank, the hydrogen tank, the argon tank) as needed. The formulated gas components meet special requirements, such as oxygen content. The gas flow direction in the double-layer fission cell gas chamber is: the circulating gas first enters the lower chamber of the fission pool, and then enters the upper chamber of the fission pool through the gap between the two gas chambers, and then exits the fission pool; the circulating gas flowing from the bottom to the top is taken away The fission gas blocks the fission gas from contacting the main coolant to prevent harmful gases from contaminating the main coolant. The working process of the fission gas purification system is: fission cell gas chamber→exhaust pump→gas purification cooling chamber→gas mixing chamber→air supply pump→gas flow control valve→fission cell gas chamber.

[0089] Reactor waste heat removal system:

The reactor is provided with a small circulation pump residual heat discharge device and an emergency passive residual heat removal system. After the shutdown, the small circulation pump residual heat discharge device replaces the main circulation system to discharge the residual heat in the reactor.

[0090] Emergency passive residual heat removal system:

When the small circulating pump residual heat discharge device fails to work due to a fault during shutdown, the reactor immediately activates the emergency passive residual heat removal system. The emergency passive residual heat removal system is located higher than the main vessel, the initial operating power is gravity, and the subsequent power is from steam. The main body of the emergency passive residual heat removal system includes a heat transfer tank, a cooling water tank, a vacuum chamber, a flow control valve, a start valve and a pipe. The height of the position is: The vacuum chamber is the highest, the cooling water tank is the second, and the second is the hydrothermal tank, and the fission pool is the lowest. The carrier tank stores pure water or an aqueous solution, and the aqueous solution may contain a neutron absorber such as a boron-containing aqueous solution. The cooling water tank stores cooling water, and the amount of cooling water depends on the set residual heat output. The vacuum chamber initially functions to absorb the gas in the main container and the circuit. The vacuum chamber is connected to an air suction pipe and a drain pipe. The suction pipe is connected to the end of the condensation pipe, and the liquid discharge pipe is connected to the heat transfer liquid. box. The flow control valve is normally closed, usually set to a flow rate setting, or can be adjusted by the control line. The flow control valve can be a normally closed electric valve; the other valves are all starting valves, and the starting valve is closed during normal operation. All channels are cut off. When the emergency is started, the start valve is open. The start valve can be a normally closed electric valve. After the start valve is fully opened, the residual heat of the reactor is passively discharged into the fission pool in the form of water vapor. The entire system has two loops: one loop is the gas loop and the other loop is the water-steam loop; the workflow of the passive residual heat removal system is:

(I) Start-up procedure: Reactor shutdown → Small circulation pump residual heat removal system can not work normally → Start emergency passive residual heat removal system.

[0091] (2) Gas circuit working process: The vacuum chamber absorbs the gas in the main container and the pipe at one time, and the fission pool air chamber

→ Steam tube → Condensation tube → Vacuum chamber One discharge tube and one hydrothermal tank. [0092] (3) Water-steam circuit working process: heat carrier tank → heat transfer liquid → flow control valve → fission pool air chamber → dispersed to main coolant surface → water vapor → steam tube → condensation tube → condensed water → Carrying a hot liquid tank.

[0093] Neutron source mechanism and nuclear test device:

The neutron source mechanism and the nuclear test device may be disposed in the fission pool or the moderated pool to be disposed at the bottom of the fission pool or at the top of the moderated pool. The conditions of the fission pool are severe. It is necessary to provide a finger casing that can be isolated from the main coolant. The neutron source mechanism or the nuclear measuring device is inserted into the finger casing with the insert. The moderated tank condition can be mildly sealed, and the neutron source mechanism or the nuclear measuring device can directly contact the moderator.

[0094] A neutron source mechanism may be disposed at the bottom of the fission pool, and the neutron source mechanism body includes a neutron source assembly, a neutron source cooler, a neutron source sleeve, a sliding sleeve, and a neutron source driver. The neutron source bushing is a isolating sleeve of the neutron source component and the main coolant. The neutron source bushing and the sliding bushing are connected and are on the same center line, and the two are fixed on the fission pool bottom plate. The former is located in the fission pool. The latter is located outside the fission pool, except for the rest of the neutron source mechanism, which can be separated from the fission pool; the cross-sectional shape of the neutron source casing can be adapted to the core fuel assembly, such as a hexagon . The neutron source component is a columnar seal structure, the base is a smooth sliding part, the neutron source assembly is internally provided with a neutron source and a coolant circulation channel; the neutron source cooler cools the neutron source component, and the neutron source cooler is a gas Or a liquid cooling circuit, the coolant can enter from the center of the neutron source assembly and then recirculate from the periphery. The function of the neutron source driver is to drive the neutron source component to slide in the sliding sleeve. The neutron source component slides up and down. The neutron source driver can be a motor-driven simple lifting platform (such as hydraulic, screw, Rack type) or complex electromagnetic drive. The neutron source mechanism at the bottom of the fission pool can simplify the fission pool structure, reduce the fission pool height, and reduce the difficulty of reactor manufacturing.

[0095] The sub-source mechanism in the slowing pool may be disposed at the top of the slowing pool, and the sub-source mechanism body in the slowing pool includes a neutron source component, a sealing sleeve, a sealing ring and a neutron source driver. The sealing sleeve is fixed on the top of the slowing pool, and the neutron source assembly is a smooth cylindrical sealed container with a neutron source. The neutron source assembly and the sealing sleeve form a slidable sealing structure, and the neutron source driver drives the neutron source assembly to move within the sealing sleeve, and the neutron source driver is a lifting device or an electromagnetic driving device. The neutron source component is directly cooled by the moderator, and the neutron source component can be filled with a thermal fluid or a heat conductive gas to enhance the cooling effect. The neutrons released by the neutron source component are slowed down into thermal neutrons in the slower pool, and thermal neutron exchange into the fission pool triggers the core fission reaction.

[0096] The devices in the slowing tank are all cooled by the slowing liquid, and the gap between the inserts in the slowing tank (such as the proliferating rod) and the isolating sleeve can be filled with the thermal fluid to improve the cooling efficiency.

[0097] Fast reactor type coupled nuclear reactor type

The types of fast reactor-type coupled nuclear reactors include: double-moderated pool coupled nuclear reactor; single moderated pool externally coupled nuclear reactor; single moderated pool built-in coupled nuclear reactor; space coupled nuclear reactor.

[0098] Double slower pool coupled nuclear reactor: The double slower pool coupled nuclear reactor is a medium-sized fixed reactor, suitable for power stations, heating and seawater desalination. The reactor main container is a double moderation pool coupling structure, and the main container is a detachable combined structure. There is a main container housing. The reactor has internal and external double slowing pools. The internal slowing pool is located in the center of the reactor as a barrel-shaped structure, and the outer slowing pool is located in the outer side of the reactor as an annular pool structure; the fission pool is located in the middle of the two slowing pools as an annular pool structure. . The inner and outer sidewalls of the fission pool are provided with a large-area thin-walled neutron exchange window. The fissile pool top cover is sealed with a metal sealant, which is a fusible heavy metal alloy. The fission pool is provided with a fission pool air chamber, and the fission pool top cover is made of a high-strength lightweight roof. The slowing tank top cover is sealed with a sealed silicone. The main coolant is lead or lead-bismuth alloy, the core is the fuel rod core, the fuel assembly can be an open fuel rod assembly or a closed fuel rod assembly, and the open fuel assembly is superior to the closed fuel rod assembly, which can reduce the fission pool height. The moderator is heavy water, and the slowing tank is provided with a slow solution circuit. The external slowing pool specializes in fuel proliferation and is set up as a proliferative rod system, which can extract the proliferating fuel online and produce U-233 nuclear fuel. The internal slowing pool specializes in nuclear control, which is set to a slower pool level nuclear control system. At the time of shutdown, the internal and external double slowing tanks simultaneously discharge the slowing liquid quickly, and the reactor is stopped due to the lack of slowing function and cannot maintain the chain reaction.

[0099] Single Moderator Pool Externally Coupled Nuclear Reactor: Single Moderator Pool Externally coupled nuclear reactor is a multi-reactor type, which can range from small to large, and can be either a fixed reactor or a mobile reactor. The reactor main vessel is of a detachable modular construction with a main vessel casing. The main container is a single moderation pool external coupling structure, the fission pool is located at the center of the barrel-shaped structure, and the moderated pool is located outside the fission pool with an annular pool structure. The side wall of the fission pool is provided with a large-area thin-walled neutron exchange window. The fissile pool top cover is sealed with a metal sealant, which is a fusible heavy metal alloy. The slowing tank top cover is sealed with silicone. The main coolant is lead or lead-bismuth alloy, and the core is the fuel rod core. The moderator is heavy water, the slowing tank is provided with a slowing liquid circuit, and the slowing pool is provided with a proliferation rod system, and the proliferating fuel can be extracted online to produce U-233 nuclear fuel. The core of the fixed single slowing tank externally coupled nuclear reactor can adopt an open fuel assembly or a closed fuel assembly, and the nuclear control system adopts a moderated tank liquid level nuclear control system. The core of the mobile single moderation pool externally coupled nuclear reactor adopts a closed fuel assembly, and the nuclear control system adopts a barrier screen nuclear control system.

[0100] Single Moderator Pool Built-in Coupled Nuclear Reactor: Single Moderator Pool Built-in coupled nuclear reactor is a simplified small or micro reactor, and the heat exchanger is integrated with the reactor. The main reactor of the reactor is a built-in coupling structure of a single slowing tank. The slowing tank is located in the center of the reactor as a barrel-shaped structure, and the moderator is heavy water or light water. The fission pool is located in the outer side of the slowing tank and has an annular pool structure. The inner side wall of the fission pool is provided with a large-area thin-walled neutron exchange window. The main coolant is lead or lead-bismuth alloy, and the fixed reactor fission cell can be provided with a fission cell chamber; the core can be a closed fuel rod assembly or an open fuel rod assembly (fixed reactor), and a conversion fuel zone can be arranged around the core. A shielded area is disposed outside the core. The slowing pool is set to a slower tank level nuclear control system (fixed stack) or a barrier screen nuclear control system (mobile stack). The neutron source mechanism is placed in the fission pool or the moderated pool. A heat exchange pool is disposed outside the reactor, a heat transfer wall is shared between the inner side of the heat exchange pool and the outer side of the fission pool, and a heat transfer tube is disposed outside the heat transfer wall, and the main coolant circulates in the heat transfer tube and the fission pool, the heat transfer tube and the heat transfer wall A heat sink is disposed thereon, and the heat transfer tube and the heat transfer wall collectively derive core heat. The heat exchange tank is equivalent to the first and second loop heat exchangers, and the second loop coolant is water. The first circuit is equipped with an exhaust pipe and a bursting valve. When the raw water leaks into the heat transfer tube and enters the collecting chamber, the water vaporizes into steam, and the light with a very small specific gravity enters the exhaust pipe upwards, and the explosion valve discharges the water vapor to suppress the water or steam from entering the core. When the water leaks into the fission cell chamber, the detonating tube and the blasting valve provided on the top of the fission pool can also discharge water vapor. A baffle can be placed in the fission pool. The main circuit is set or not in the primary circuit. The primary circulation pump is set in the primary circuit: The primary coolant is forced to circulate. The main circuit is not provided in the primary circuit: the main coolant is self-circulating. The heat exchange efficiency of the built-in coupled nuclear reactor in the single moderator pool is not high, and it is suitable as a nuclear energy device with less demanding water temperature.

[0101] Space-Coupled Nuclear Reactor: The reactor is a miniature or small-space nuclear power plant with no main vessel casing, and the reactor may be provided with no shielding structure. The main container is a single moderation pool external coupling structure, the fission pool is in the center of the barrel shape, the slowing pool is located on the outer side of the annular cylinder, the moderator is graphite, filled in the cylindrical slowing pool; the reactor uses the slowing pool In the displacement nuclear control system, the slowing pool does not contact the fission pool, and the slowing pool moves axially around the fission pool. The main coolant is a liquid metal, especially a liquid alkali metal, such as lithium -7. The core body is composed of a closed fuel rod assembly, and the fission cell can be provided with a draft tube. The fission pool heat energy is conducted from the liquid metal to the thermoelectric conversion device. The slowing pool displacement nuclear control system performs neutron moderation and nuclear control functions, and the moderated pool position shifting nuclear control system includes a slowing pool and a slowing pool driving mechanism. The slowing pool drive mechanism body includes a slower pool drive, a clutch, a center guide, and a rebound device. The center guide rod is axially fixed in the center of the fission pool floor. During normal operation, the clutch engages with the center guide rod to slow the movement and positioning of the tank driver along the center guide rod. The slowing pool drive can be a stepping or rotating motor, the center guide is a screw, the motor rotor core is hollow, the center guide rod passes through the motor rotor shaft center, and the motor rotor rotates around the center guide rod. In normal operation, the clutch engages with the center guide and the motor pushes the slower drive mechanism to move and position along the center guide. When the reactor is shut down, the clutch is separated from the center guide. The rebound device pulls the slower tank back or pushes it back to the far end, that is, the slower tank is away from the fission pool, and the core is shut down due to the lack of slowing neutron reactivity. The spring force of the rebound device is provided by a spring.

[0102] The technical advantages of the present invention are:

(1) The main coolant of the fast reactor type coupled nuclear reactor can be chemically stable liquid heavy metal, especially lead or lead bismuth eutectic, the main container is operated under normal pressure, and the reactor has inherent safety.

[0103] (2) The main container of the fast reactor-type coupled nuclear reactor is split into fission pools and moderated pools that are coupled to each other but completely isolated from each other, and an insulation layer is disposed between the two to relieve the moderator and the main coolant. The functional bundle, the fission pool and the slower pool can each be optimized in the most favorable direction. The main components of the reactor can be split and combined to implement a modular design. Its main container can be constructed with a thin wall structure with low consumables. The fissile and slower pools are made of cheap ferritic alloys and aluminum alloys, respectively, which are low in engineering difficulty and manufacturing cost.

[0104] (3) The fast reactor type coupled nuclear reactor uses a moderator outside the core to realize a fast-thermal neutron coupling nuclear reaction in the fast neutron core, and the nuclear reaction efficiency is greatly improved compared with the fast reactor, and the core is fissile core The content of the prime can be significantly reduced. Compared with other fast reactors, the initial volume of expensive fissile nuclide decreases, the fuel proliferation efficiency increases, and the "double cycle" of nuclear fuel proliferation can be achieved. shorten.

[4105] (4) The slowing pool can be close to the normal temperature and pressure, and the slowing pool function can be extended without difficulty. The slower pool can increase the function of fuel proliferation, coupled nuclear control and nuclear testing.

[5] (5) The fast reactor type coupled nuclear reactor can adopt the slowing pool liquid level nuclear control system, which can quickly control all residual reactivity, without the need of control rods, adjusting rods, shielding rods and chemical control. The fission pool does not require a neutron shield in the radial direction. The reactor uses less neutron absorber, which saves equipment and equipment costs, reduces neutron loss in the reactor, and improves neutron economy. It can eliminate costly and difficult to control the control rod drive mechanism, can remove the weight and functional load of about half of the fission pool, simplify the construction of the fission pool and core, and reduce the height of the fission pool. The fission pool is only equivalent to the core basket. . The entire replacement of the fission pool or one-time decommissioning (decommissioning with core replacement) can be implemented to improve maintenance safety and maintenance efficiency.

[6107] (6) In the slower pool, the online extraction of fuel proliferation and proliferating fuel can be implemented, and the Pa-233/U-233 can be converted to the outside of the reactor to reduce the negative impact of Pa-233. The thermal neutron capture cross section of Th-232 is 19 times higher than that of fast neutrons. The slower cell proliferation fuel contains only a single nuclide Th-232. Initially only a single efficient Th-232 thermal neutron capture reaction, fissile nuclide The double loss of nuclear fuel and neutrons caused by the trapping reaction is negligible, so the neutron utilization rate of the proliferating fuel in the slowing pool is high. The slowing pool has a single fuel composition, and the chemical elements that need to be separated after the converted proliferating fuel are only Th-232 and U-233, that is, the separation of the nuclide is simple. The U-233 nuclear fuel produced in the slower tank does not contain the Th-228 daughter emitting high-energy gamma rays, so the U-233 nuclear fuel produced in the slower tank is safe, and does not require costly facilities and production to protect the Y-ray. Process. The bismuth-based spent fuel in the core still has high-energy Y-rays, which can be solved by increasing the fuel consumption of the core and increasing the proportion of the U-233 nuclear fuel produced by the slow-tempering tank, which can greatly reduce the frequency of spent fuel reprocessing (ie, the number of closed loops). It may even be possible to save.

[7108] (7) The fast reactor type coupled nuclear reactor can adopt "candle core", which can be matched with the slowing pool liquid level nuclear control system, both of which support the gradual combustion method from bottom to top, "candle type" The core "pre-assembled fissile nuclide is mainly distributed below the core fuel zone. The concentration ladder is lower and higher, and the upper fuel is accumulated by the proliferative reaction. The cumulative velocity is compatible with the upward velocity of the combustion zone. The higher the rate is, the higher the lower part of the core is. The initial capacity of the core fissile nuclide is relatively saved, the core life is long, and the total fuel consumption depth is large.

[8] (8) The simplified fission cell enables the core to adopt an open fuel rod assembly. The open fuel rod can reduce the neutron loss, reduce the internal pressure of the fuel rod, prolong the life of the fuel rod cladding tube, and improve the core. Fuel consumption rate. Open fuel rods create conditions for the use of high thermal conductivity advanced ceramic fuels (such as nitrides, carbides, and silicide fuels) to overcome the drawbacks of nitride fuels that are susceptible to high temperature decomposition and release of nitrogen. More importantly, advanced ceramic fuel is the best way to solve the post-treatment problem of bismuth-based spent fuel. This is because the sintered bismuth-based oxide is extremely difficult to dissolve. When dissolved, hydrofluoric acid must be added to the strong acid solution, which will cause the facility. Severe corrosion.

[0110] (9) The nuclear material of the fast reactor-type coupled nuclear reactor is mainly cheap Th-232, followed by nuclear waste. Core center It is suitable for burning U-233, U-235 and Pu-239, and is also suitable for burning transuranic elements, which can provide a solution for pressurized water reactor nuclear waste. With cheap plutonium and nuclear waste, fuel costs are reduced, nuclear resource utilization is increasing, and the global nuclear fission energy sustainability can grow to more than 10,000 years.

DRAWINGS

[0111] FIG. 1 is a schematic view of the disassembly and assembly of the vertical connecting sleeve;

Figure 2 Schematic diagram of disassembly and assembly of non-vertical connection sleeves;

Figure 3 Schematic diagram of disassembly and assembly of non-vertical to vertical connection sleeves;

Figure 4 Schematic diagram of the main container of the frame skin structure;

Figure 5 Schematic diagram of the main container of the thin-walled rib structure;

Figure 6 Schematic diagram of the seal structure of the main container top cover sealant;

Figure 7 is a longitudinal section view of a double slowed pool coupled nuclear reactor;

Figure 8 is a cross-sectional view of a double slowed pool coupled nuclear reactor;

Figure 9 is a longitudinal section view of a single moderator pool externally coupled nuclear reactor;

Figure 10 is a cross-sectional view of a single moderator pool externally coupled nuclear reactor;

Figure 11 is a longitudinal section view of a built-in coupled nuclear reactor in a single moderation cell;

Figure 12 is a cross-sectional view of a built-in coupled nuclear reactor in a single moderation cell;

Figure 13 is a longitudinal sectional view of a space coupled nuclear reactor;

Figure 14 Cross-sectional view of a space-coupled nuclear reactor;

Figure 15 The shield is a schematic view of the casing-like fuel liner;

Figure 16 is a schematic view of the fuel cap of the cap;

Figure 17 Schematic diagram of an open fuel rod filling a fuel tank;

Figure 18 Schematic diagram of open fuel rods and threaded connections;

Figure 19 is a structural view of the bottom end plug of the fuel rod of the threaded connection;

Figure 20 is a structural view of the bottom end plug of the welded fuel rod;

Figure 21 is a structural view of the bottom end plug of the fuel rod inlaid;

Figure 22 is a schematic view of a bundle open fuel assembly;

Figure 23 Schematic diagram of a casing open fuel assembly;

Figure 24 is a schematic longitudinal section of the valveless exhaust member;

Figure 25 Valveless exhaust member (claw type) top view;

Figure 26 is a schematic longitudinal sectional view of a valve exhaust member; Figure 27 is a longitudinal sectional view of a spring type pressure relief valve;

Figure 28 is a longitudinal sectional view of a fusible heavy metal pressure relief valve;

Figure 29 is a longitudinal sectional view of a double pressure relief valve;

Figure 30 Schematic diagram of closed fuel rods and threaded connections;

Figure 31 Schematic diagram of a closed bundle fuel assembly;

Figure 32 is a schematic view of a casing closed fuel assembly;

Figure 33 Schematic diagram of a fission gas purification system;

Figure 34 Flow chart of the fission gas purification system;

Figure 35 Schematic diagram of gas phase oxygen control of the main coolant;

Figure 36 Schematic diagram of the main coolant solid phase oxygen control;

Figure 37 Schematic diagram of the slowing pool level nuclear control system;

Figure 38 Schematic diagram of the barrier screen nuclear control system;

Figure 39 shows the structure of the cylindrical barrier screen;

Figure 40 Schematic diagram of the arc-shaped barrier screen;

Figure 41 Schematic diagram of the neutron source mechanism at the bottom of the fission pool;

Figure 42 Schematic diagram of the neutron source mechanism at the top of the slowing pool;

Figure 43 Schematic diagram of the emergency passive residual heat removal system;

Figure _{44 is a} flow chart of the extraction and separation of the insoluble proliferation fuel;

Figure 45 Flow chart for extraction and separation of soluble and proliferating fuel.

[0112] In the figure, the label is compared with the name: 101 main container casing; 132 skin; 133 frame; 142 thin wall; 143 rib plate; 150 container side wall; 151 container top cover; 152 annular groove; 153 annular skirt Plate; 154 sealant; 155 locking device; 175 connecting sleeve; 176 fixed pipe head; 177 detachable pipe head; 178 upper pipe head; 179 lower pipe head; 180 pipe head; 201 fission pool; Cover; 203 fission pool sidewall; 205 fission pool floor; 209 insulation; 211 sidewall insulation; 212 load-bearing insulation; 221 fission pool gas chamber; 222 fission basin upper chamber; Coolant inlet; 232 main coolant outlet; 233 diversion tube; 234 deflector; 235 main circulation pump; 236 main circulation tube; 250 core; 251 core base; 255 core top grid; Grid; 258 shielding zone; 281 gas mixing chamber; 282 gas diffusion device; 283 gas pump; 285 mass exchanger; 286 oxide solid particles; 287 thermostat; 289 flow controller; 301 slowing pool; 302 internal slowing Pool; 303 external slowing pool; 305 slowing pool top cover; 306 slowing pool side wall 307 slowing pool bottom plate; 365 proliferation rod; 366 proliferation rod sleeve; 367 casing grid; 400 neutron source; 401 neutron source mechanism; 411 neutron source component; 413 neutron source driver; 415 neutron source set Tube; 426 sliding sleeve; 427 sealing sleeve; 429 coolant pump; 431 neutron source cold 501 heat exchange cell sidewall; 502 heat exchange cell; 503 heat transfer wall; 504 heat transfer tube; 505 heat sink; 507 current collector; 508 exhaust tube; 509 burst valve; 511 inlet pipe; 512 outlet pipe 553 moderator driver; 555 center guide; 558 spring; 601 reservoir; 602 slow solution cooler; 605 flow controller; 611 shutdown valve; 631 injector; 632 infusion pump; 633 infusion tube 635 return tube; 638 gas balance tube; 655 upper infusion tube; 656 upper infusion valve; 661 lower infusion tube; 662 lower infusion valve; 663 upper return tube; 665 lower return tube; 666 lower return valve; 681 barrier screen; Barrier screen drive; 683 drive belt; 685 upper guide rod; 691 seal ring; 695 lower guide rod; 696 lower duct; 700 open fuel rod; 703 fuel tank; 705 inner tube; 707 bottom plug; 708 top plug; Air vent; 710 gas injection pipe; 711 protective cover; 712 down conversion zone; 713 fuel zone; 714 upshift zone; 717 air cavity; 721 compression spring; 722 filler; 725 lower end plug; 726 upper end plug; 728 cladding tube; 729 exhaust pipe; 731 exhaust pipe bundle; 732 seal Tube; 734 boss; 735 groove; 737 screw; 738 screw hole; 742 slot; 743 solder joint; 747 keyway; 751 constraint; 752 retention gas; 753 sealing head; 754 claw connection; 756 gas injection hole; 757 pressure relief valve; 759 coolant outlet; 761 restraint receiving plate; 765 adsorption body; 766 adsorption body positioner; 767 adsorption body compression spring; 771 open fuel rod; 772 rod bundle top grid 773 bar beam bottom grid; 774 upper header; 775 lower header; 776 skeleton tube; 777 positioning grid; 778 top positioning grid; 779 bottom positioning grid; 781 fixing screw; 782 positioning pin; 785 pin 786 coolant inlet; 787 seal; 788 fixed thread; 789 main sleeve; 791 spacer; 795 closed fuel rod; 811 valve housing; 812 lower valve body; 813 upper valve body; 814 spring; Positioning head; 816 compression screw; 818 vent; 822 cap; 825 fusible heavy metal; 827 anti-deblocking head; 831 central air pipe; 912 air pump; 913 gas purification cooling room; 914 gas mixing room; ; 916 exhaust gas tank; 917 air pump; 918 gas Flow control valve; hydrothermal carrier tank 931; 932 cooling water tank; condenser 933; 934 a vacuum chamber; suction pipe 935; 936 drain pipe; flow rate control valve 937; 938 starting valve; steam pipe 939.

detailed description

[0113] The present invention will be further described in detail below in conjunction with the drawings and specific embodiments.

Embodiment 1: Implementation method of fast reactor type coupled nuclear reaction

As shown in Figure 9 and Figure 10:

The reactor main container is divided into a fission pool 201 and a moderated pool 301 which are completely isolated from each other. The core 250 is disposed in the fission pool, the core has a fast neutron core characteristic, and the slowing tank 301 has a slowing agent built therein.

[0115] The fission pool 201 and the slowing pool 301 are inlaid or movably combined with each other to couple the structure and function thereof, and a heat insulation layer is disposed between the fission pool 201 and the slowing pool 301 to block heat exchange between the two. The slowing tank 301 can be controlled to be close to the normal temperature and normal pressure state; the moderator is separated from the main coolant, the two are no longer tied in structure and function, and the fission pool 201 and the core 250 have no moderator, the main The coolant passes through the fission pool 201 without passing through the slowing tank 301; the neutron is allowed to pass through the fission pool 201 The structure between the slowing pool 301 and the slowing pool 301 enables neutron exchange and coupled nuclear reaction, and the fast neutron generated by the core and the slow reflection from the slowing pool 301 into the fission pool 201 are slow. The neutrons allow the core to simultaneously perform a coupled nuclear reaction initiated by fast neutrons and slowed neutrons (including thermal neutrons and mesenchytrons). The fission pool 201 has the characteristics and functions of a fast neutron reactor, and the slowing pool 301 A thermal neutron nuclear reaction (such as a thermal neutron capture reaction) can be performed.

[0116] A coupling nuclear control system is set in the slowing pool 301, and the coupled nuclear control and the passive shutdown are implemented by the coupled nuclear reaction; the moderated neutron function of the moderator and the controllability of the moderator or the slowing pool are utilized. The controllable displacement controls the reactivity of the core 250 by changing the neutron exchange between the fission pool 201 and the slowing pool 301; when the shutdown, the slowing pool 301 loses the neutron moderating function, and the slowing pool 301 is terminated. The core 250 transports the slowed neutrons, and the rapid decline of the core reactivity causes the chain fission reaction to be unsuccessful, thereby achieving passive shutdown.

[0117] utilizing the high efficiency of the thermal neutron nuclear reaction, performing on-line extraction of nuclear fuel proliferation and proliferating fuel under the condition that the slowing pool is close to normal temperature and pressure, realizing Pa-233/U-233 conversion and Th-232 outside the reactor / U-233 separation; In the slowing tank 301, a proliferating fuel system capable of online fuel replacement is provided. The initial proliferating fuel material contains only one species of radionuclide Th-232, and only the Th-232 thermal neutron capture nuclear reaction is avoided or avoided. Reduce the double loss of neutrons and effective nuclear fuel caused by Pa-233 and U-233 capture neutrons, and improve the proliferation efficiency and high neutron utilization rate. The slow-tempering pool has mild physical conditions, and it is not difficult to extract the proliferating fuel online. The subsequent separation of the nuclide is simple, and only a simple separation of the two elements of Th-232/U-233 is required.

[0118] Optimize fuel element and core design (eg, using a candle core design) to increase nuclear reaction efficiency and fuel efficiency.

[0119] As shown in FIG. 4 and FIG. 5, the reactor main vessel material and structure are optimized, and a large-area thin-walled neutron exchange window is disposed on the side wall of the reactor main vessel to increase the neutron exchange efficiency while ensuring the structural strength.

[0120] The reactor main container is reduced in height, simplification, cost reduction and modularization, and the overall replacement of the fission pool or the implementation of the fission pool module decommissioning once (the fission pool is decommissioned with the core replacement) improves the maintenance efficiency and Overall security. The main components of the reactor are modularized to allow the reactor to be split and combined.

[0121] The difficulty in splitting and reorganizing the reactor module is mainly reflected in the splitting and reorganization of the pipeline. The easy-to-reassemble casing connection and splitting method simplifies the splitting and recombination of the reactor module. The casing connection and splitting method is vertical socket or non-vertical or non-vertical to vertical socket.

[0122] As shown in FIG. 1, the vertical socket: the connecting sleeve 175 can be reused many times, the lower tube head is a fixed tube head 176, and the upper tube head is a detachable tube head 177, and the two tube heads are On the same vertical axis, the installation is carried out in vertical lifting; before the initial connection, the connecting sleeve 175 is welded to the lower tube head 179 in advance, and the upper tube head 178 is aligned and slightly inserted into the connecting sleeve 175 after welding, and the welding surface faces. The upper operation is simple and the welding effect is optimal; when splitting, it is only necessary to cut and separate under the welded portion of the upper end of the connecting sleeve 175, and the connecting sleeve 175 is slightly shortened; the residue in the connecting sleeve 175 is cleaned during reorganization, the upper tube head Repeat the previous connection process compared to the previous lengthening. [0123] As shown in FIG. 2, the non-vertical sleeve: the non-vertical sleeve is mainly connected by a horizontal pipe, and is installed by vertical lifting. The pipe head connected to the split module is a detachable pipe head 177, corresponding to The other tube head is a fixed tube head 176, and the connecting sleeve 175 is shorter as a disposable component, and then the connecting sleeve 175 or the appropriate length of the detachable tube head 177 is sequentially lengthened as needed; The upper sleeve 175 is connected but not welded, and the sliding joint sleeve 175 is exposed to the fixed pipe head 176. After the two pipe ends are aligned, the connecting sleeve 175 is sleeved, and then the two ends are welded separately; the entire connecting sleeve 175 is cut off during the splitting. When reassembling, replace the new connection sleeve 175 with the appropriate length, and repeat the previous connection process; the non-vertical sleeve is difficult to weld and the welding effect is not easy to guarantee.

[0124] As shown in FIG. 3, the non-vertical turn vertical socket: the two pipes connected are non-vertical pipes, and the two pipe heads to be connected are respectively converted into concentric vertical pipe heads by the elbows, and the fixed pipe is fixed. The head 176 is below, the detachable tube head 177 is on, and the subsequent joining, splitting and recombining methods are the same as the vertical socket.

Example 2: Double Moderate Pool Coupled Nuclear Reactor

As shown in Figure 7 and Figure 8, the double-moderated pool coupled nuclear reactor is a medium-sized fixed-type reactor suitable for power stations, heating, and desalination. The reactor main container is a double moderation pool coupling structure, and the main container is a detachable combined structure having a main container casing 101. The reactor has internal and external double slowing pools, the internal slowing pool 302 is located in the center of the reactor as a barrel-shaped structure, and the outer slowing pool 303 is located in the outer side of the reactor as an annular pool structure; the fission pool 201 is located in the middle of the two slowing pools. Pool structure. The inner and outer sidewalls of the fission cell 201 are each provided with a large-area thin-walled neutron exchange window. The fissile pool top cover is sealed with a metal sealant, the metal sealant is a fusible heavy metal alloy, and the fission pool top cover is made of a high-strength lightweight top cover. The slower tank top cover is sealed with a sealed silicone. The main coolant is lead or lead-bismuth alloy, the core is the fuel rod core, the fuel assembly can be an open fuel rod assembly or a closed fuel rod assembly, and the open fuel assembly is superior to the closed fuel rod assembly, which can reduce the fission pool height. The moderator is heavy water, and the slowing tank is provided with a slow solution circuit. The external slowing pool 303 specializes in fuel proliferation and is set up as a proliferation rod system, which can extract the proliferating fuel online and produce U-233 nuclear fuel. The internal slowing pool 302 is specially controlled by the company, which is set as the slowing pool level nuclear control system. At the time of shutdown, the double slowing pool at the same time quickly discharges the slowing liquid, and the reactor is shut down due to the lack of slowing function.

[0126] Embodiment 3: Fixed single slowing pool externally coupled nuclear reactor

As shown in Fig. 9 and Fig. 10, the fixed single slowing tank externally coupled nuclear reactor is a small to large reactor suitable for power station, heat supply and seawater desalination. The main container is of a detachable modular construction with a main container housing 101. The main reactor of the reactor is a single moderation pool external coupling structure, the fission pool is located at the center of the barrel-shaped structure, and the moderated pool is located outside the fission pool with an annular pool structure. The outer side wall of the fission pool 201 is provided with a large-area thin-walled neutron exchange window. The fissile pool top cover is sealed with a metal sealant, the metal sealant is a fusible heavy metal alloy, and the fission pool top cover is made of a high-strength lightweight top cover. The slowing tank top cover is sealed with a sealed silicone. The main coolant is lead or lead-bismuth alloy, the core is the fuel rod core, the fuel assembly can be an open fuel rod assembly or a closed fuel rod assembly, and the open fuel rod assembly is superior to the closed fuel rod assembly, which can reduce fission Pool height. slow The chemical agent is heavy water, the slowing liquid circuit is a one-way slowing liquid circuit, and the nuclear control system is a slowing liquid level nuclear control system; when the reactor is stopped, the slowing pool quickly discharges the slowing liquid, and the reactor stops due to the lack of slowing function. stack. The slowing tank is provided with a proliferation rod system, which can extract the proliferating fuel online and produce U-233 nuclear fuel.

Embodiment 4: Mobile single slowing pool externally coupled nuclear reactor

As shown in Fig. 9 and Fig. 10, the mobile single slowering tank external fast reactor type coupled nuclear reactor is a miniature or small nuclear power plant, such as ship power. The same as the sixth embodiment, the difference is: the fuel assembly is a closed fuel rod assembly; the slowing tank 301 is provided with a variable direction slowing liquid circuit, and the nuclear control system is a barrier screen nuclear control system.

Embodiment 5: Single Moderation Pool Built-in Coupling Nuclear Reactor

As shown in Figure 11 and Figure 12, the single moderator has a built-in coupled nuclear reactor for the simplified small or micro nuclear reactor, and the heat exchanger is integrated with the reactor. The main reactor of the reactor is a built-in coupling structure of the single slowing tank, and the slowing tank 301 is located in the center of the reactor as a barrel-shaped structure, and the moderator is heavy water or light water. The fission pool 201 is located outside the slowing pool 301 in an annular pool structure. The inner wall 203 of the fission pool is provided with a neutron exchange window having a large-area thin-wall structure. The main coolant is lead or lead-bismuth alloy, and the fission pool can be provided with a fission cell chamber; the core is a solid fuel rod core, and a conversion fuel zone can be arranged outside the core, and a shield region 258 is disposed outside the core. The slowing pool is set to the slow pool level nuclear control system (fixed stack) or the barrier screen nuclear control system (mobile stack); the neutron source mechanism 401 is set in the fission pool or the moderated pool. A heat exchange pool 502 is disposed outside the reactor, a heat transfer wall 503 is shared on the inner side of the heat exchange pool and outside the fission pool, and a heat transfer tube 504 is disposed outside the heat transfer wall 503, and the main coolant circulates in the heat transfer tube 504 and the fission pool 201. A heat sink 505 is disposed on the heat transfer tube 504 and the heat transfer wall 503, and the heat transfer tube 504 and the heat transfer wall 503 collectively derive core heat. The heat exchange tank 502 is equivalent to the first and second circuit heat exchangers, and the second circuit coolant is water; the first circuit is provided with the squib 508 and the blast valve 509, when water leakage enters the heat transfer tube 504 and enters the collecting chamber 507, The water vaporizes into steam, and the light-heavy steam enters the blast tube 508 upwards, and the blasting valve 509 is compressed by the membrane to discharge water vapor, which prevents water or steam from entering the core; when the water leaks into the fission pool chamber 221, the fission pool top The squib 508 and the blast valve 509 provided on the cover 202 can also discharge water vapor. The deflector can be equipped with a baffle 234; - the circuit is set or not equipped with a main circulation pump; the primary circuit is provided with a primary circulation pump 235: the primary coolant is forced to circulate; the primary circuit is not provided with a primary circulation pump: the primary coolant is self-circulating.

Embodiment 6: Space-Coupled Nuclear Reactor

As shown in Fig. 13 and Fig. 14, the reactor is a micro or small space nuclear power unit having no main container casing, and the reactor has a shield structure in the radial direction to reduce the weight. The main container is a single slowing pool external coupling structure, the fission pool 201 is in the center of the barrel shape, the slowing pool 301 is located in the outer annular tube shape, the moderator is graphite, and is filled in the cylindrical slowing pool; the reactor is slow In the cell displacement control system, the moderation cell 301 does not contact the fission cell 201, and the moderation cell 301 moves axially around the fission cell 201. The main coolant is a liquid metal, especially a liquid alkali metal, such as lithium-7, and the core 250 is composed of a closed fuel rod assembly. The fission cell can be provided with a draft tube 233. The thermal energy of the fission pool 201 is conducted from the liquid metal to the thermoelectric conversion device. The slowing pool displacement nuclear control system performs neutron moderation and nuclear control functions, and the slowing pool displacement nuclear control system includes a slowing pool 301 and a slowing pool driving mechanism. The slowing pool drive mechanism body includes a slowering pool driver 553, a clutch, a center guide 555, and a rebounding device; the center guide rod 555 is axially fixed at the center of the fission pool floor 205. The slowing pool driver 553 is a stepping or rotating motor, the center guiding rod 555 is a screw, the rotor core of the motor is hollow, the center guiding rod 555 passes through the shaft of the motor rotor, and the rotor of the motor rotates around the center guiding rod 555. In normal operation, the clutch engages with the center guide 555, and the motor pushes the slowing pool drive mechanism to move and position along the center guide 555; when the reactor is stopped, the clutch is separated from the center guide 555, and the rebound device pulls the slowing pool 301 Returning or pushing back to the distal end, that is, the slowing pool 301 is away from the fission pool 201, and the core is shut down due to a lack of slowing neutron reactivity.

Embodiment 7: Nuclear reactor fission pool with a large area neutron exchange window disposed on the side wall

There is only one main reactor main container, and the main container does not have a neutron exchange window, but a shield is provided to prevent the neutron from leaking outward, and the main container structure adopts a uniform thick structure. The large-area neutron exchange window described in the above embodiment is a non-uniform structure, which will be described in detail in this embodiment.

As shown in FIGS. 4 and 5, the main body side wall 203 of the fast reactor type coupled nuclear reactor may be provided with a large area neutron exchange window to increase the neutron exchange amount, and the neutron exchange window is generally disposed at the side wall 203 of the fission basin. The area where the neutron exchange is performed on the side wall of the fission pool is set to a thin-walled structure to form a neutron exchange window. The thin-walled structure adopts a frame skin structure or a thin-walled rib structure. The frame skin structure is provided with a frame 133 at a side wall portion of the neutron exchange region, and a thin plate skin 132 is disposed on the frame, and the fissile pool portion other than the frame skin structure may adopt a non-thin wall structure such as a bottom plate, near the bottom and the top portion. The side walls are constructed in a thick wall. The thin-walled rib structure is such that the side wall is mainly made of a thin wall 142, and the thin wall 142 is reinforced with a rib 143. The frame skin structure or the thin stud structure can be constructed in one piece. The main frame or the main rib is placed vertically symmetrically on the side wall of the fission pool, and the hoisting load is borne by the main frame or the main rib. A special reinforcement structure is provided at a position where the fission pool has a large bearing capacity, such as a reinforcing frame or a reinforcing rib at the outlet of the main coolant. The upper edge of the side wall of the fission pool is arranged in a sealed configuration to seal against the top of the fissile pool to form a closed fission tank 201 main vessel.

Example 8: Fuel tank built into the fuel rod

The fast reactor type coupled nuclear reactor uses a fuel rod assembly core, and the conventional fuel rod is a fuel directly filled into the fuel rod. The fuel liner 703 is an inclusion of fuel that is filled into the fuel rod in a unitary form to isolate the fuel from the fuel rod. The fuel liner 703 is first subjected to fuel stress and corrosion to protect the fuel rod cladding tube 728. The fuel liner 703 is a seal that can be stored separately for long periods of time.

[0133] As shown in FIGS. 15, 16, and 17, the fuel tank 703 body includes a bladder tube 705, a bottom plug 707, a top plug 708, a filler 722, a compression spring 721, a gas injection hole 709, or a gas injection tube 710. The outer diameter of the fuel tank 703 is slightly smaller than the inner diameter of the fuel rod cladding tube 728, and a fuel expansion space is reserved. The inner tube 705 is a cladding of the fuel inner liner 703, and the inner end of the inner tube 705 is bottomed Plug 707 and top plug 708 are sealed. The top plug 708 is provided with a gas injection hole 709 or a gas injection pipe 710. A filler (including a fuel) and a compression spring 721 are provided in the fuel tank, and the gas injection hole 709 or the gas injection pipe 710 is used for pumping or injecting or exhausting; the gas injection hole 709 is in the shape of a hole, and the gas injection pipe 710 is a short tubular shape. The gas injection hole 709 or the gas injection pipe 710 may be provided as a self-opening sealing structure, and sealed after the gas injection is completed. After the fuel tank 703 is heated or boosted or heated and pressurized, the gas injection hole 709 or the gas injection pipe 710 is opened and exhausted by itself, and the self-opening sealing structure is a burstable structure or a meltable sealing plug. Burst structure: The gas injection pipe 710 can burst, and the burst type is burst of low-strength material or burst of low-strength structure. The low-strength material is a material in which the gas injection pipe 710 is made of a low-strength material or has a low strength after being heated. When the temperature of the fuel tank 703 is increased, the internal air pressure is increased, and the gas injection pipe 710 is subjected to pressure bursting to open the air by itself; the low-strength structure is a gas injection pipe. A blasting groove is provided on the 710, and the gas injection pipe wall is thin at the blasting groove, and the air pressure difference causes the blasting groove to form a crack, and the gas injection pipe 710 cracks and vents. Fusible sealing plug: The fusible sealing plug can be melted after heating, and can be composed of a single sealing agent or a plurality of sealing agents. The various sealing agents are a plurality of sealing agents having different melting points, and the sealing plug has a lower melting point than the inner layer, and is sealed. The outer sealant is equivalent to the brazing material. After the core is started to warm up, the sealing plug is completely melted by heat, and the gas injection hole 709 is opened for exhaust. A protective cover 711 may be added to the top of the fuel tank 703. The protective cover 711 refers to a sleeve shape or a cap shape. The protective cover 711 is provided with a hole for gas communication, and the protective cover 711 is disposed outside the gas injection hole 709 or the gas injection pipe 710. After the fuel tank 703 completes the gas injection sealing, the sleeve-like shield 711 is directly welded to the top end of the top plug 708; when the fuel tank 703 is filled into the fuel rod, the cap-shaped shield 711 is fixed by the fuel rod pressing spring Above the top plug 708. The shield 711 prevents the blast or splash from contacting the fuel rod cladding tube 728; the fuel rod or fuel bladder 703 can be filled with a heat transfer medium such as helium or sodium.

[0134] The fuel tank 703 is more suitable for directly filling the particulate fuel, and can solve the problem that the advanced ceramic fuel is not easily sintered, and the fuel tank 703 can restrain the pellet fuel from sintering. The fuel particles are in close contact with the inner tube 705, and the inner tube 705 is subjected to the first expansion stress. When the fuel is gradually expanded to the maximum diameter, the fuel inner liner 703 and the cladding tube 728 are pressed together, and the heat transfer efficiency is increased. The thermal efficiency is better than the pellet fuel, which is beneficial to lower the fuel rod temperature. The initial heat transfer can rely on a gas or liquid heat transfer medium such as helium or sodium. The fuel liner 703 isolates the fuel from the cladding tube 728, alleviating the stress and corrosion of the cladding tube 728, and the cladding tube 728 is not easily broken, thereby prolonging the life of the fuel rod. The fuel liner 703 protects the inner wall of the fuel rod cladding tube 728 from being isolated. Depending on the function and environment of the inner tube 705 and the cladding tube 728, the two materials can be optimized in different directions using different materials.

Example 9: Open Fuel Rod

The fission pool of the simplified fast reactor-type coupled nuclear reactor is only equivalent to the core basket. The fission pool chamber 221 can be arranged in the upper part of the fission pool. The core can be an open fuel rod assembly, and the exhaust port of the fuel assembly can be extended to fission. In the cell plenum 221, the discharged fission gas may not contact the main coolant.

[0136] As shown in FIG. 17 and FIG. 18, the open fuel rod assembly is composed of an open type fuel rod 700; the open fuel rod 700 has a main structure of a bottom end closed and a top open rod-shaped cladding tube structure, and the top opening is An exhaust pipe 729 is provided. [0137] The body of the open fuel rod 700 includes a lower end plug 725, a cladding tube 728, a compression spring 721, an upper end plug 726, an exhaust capillary 729, a filler 722, or a fuel bladder 703. The ends of the fuel rod are respectively welded with end plugs, the bottom end is sealed by the lower end plug 725, the upper end plug 726 is provided with an opening, the exhaust pipe 729 is welded to the opening, and the fissile gas is discharged by the exhaust thin tube 729, and the open fuel rod 700 There is no air chamber or a short upper air chamber 717, a filler spring 721 is provided on the filler 722 or the fuel tank 703; the filler 722 in the fuel rod or fuel tank 703 is set the same, and the nuclide segment in the filler 722 It can be divided into three zones, from bottom to top, respectively, a down-conversion zone 712, a fuel zone 713 and an up-conversion zone 714. The up-down conversion zone is only initially loaded with a convertible nuclide, and the fuel zone 713 is initially provided with a fissile nuclide. One or two shielding zones are added to the fuel rod filling, and the shielding zone is provided with a neutron absorber to shield the remaining neutrons, thereby increasing the axial shielding function of the core. Set a shield area: Set an upper shield area at the top of the fill. Set two shield zones: Set the lower shield zone at the bottom of the filler and the upper shield zone at the top. The fuel rod filling 722 is provided with an adsorption zone filled with a honeycomb solid adsorbent to adsorb fission volatiles, and the adsorption zone is located between the up-conversion zone 714 and the upper shielding zone or at the uppermost end of the filler 722, and the adsorption zone and the upper shielding zone may Exchange location. The fuel rod packing has six basic partition combinations from bottom to top: down conversion zone - fuel zone - upconversion zone; downconversion zone - fuel zone - upshift zone - adsorption zone; downconversion zone - fuel zone - upconversion zone - Upper shield area; Down conversion area - Fuel area - Up conversion area - Adsorption area - Upper shield area; Lower shield area - Down conversion area - Fuel area - Up conversion area - Upper shield area; Lower shield area - Down conversion area - Fuel zone - upconversion zone - adsorption zone - upper shield zone.

Example 10: Open Fuel Rod Assembly

The open fuel rod assembly is composed of an open fuel rod assembly, which is a bundle open fuel assembly or a sleeve open fuel assembly; the bundle open fuel assembly has no main sleeve, and the sleeve open fuel The assembly has a main sleeve 789. An upper portion of the open fuel assembly is provided with an exhaust member.

[0139] As shown in FIG. 22, the bundle open fuel assembly: the bundle open fuel assembly includes a lower header 775, a bundle bottom grid 773, a skeleton tube 776, a positioning grid 777, an open fuel rod 700, The upper header 774 and the exhaust member; the skeleton tube 776, the positioning grid 777 and the upper and lower sockets together form a skeleton of the fuel assembly, and a plurality of positioning grids are fixed on the skeleton tube bundle, and both ends of the skeleton tube 776 are fixed to the upper and lower tube holders. The skeleton tube 776 is divided into two types. The first type is a through-tube, which can be used as a guide tube (such as a guide tube for nuclear measurement); the second type is a solid tube, and the end of the tube is welded with an end plug, through the end plug and up and down The tube seat is fixed, and the real tube is provided with a convertible fuel, a compression spring and a short air chamber, and the solid tube is equivalent to the conversion fuel rod. The fuel rod passes through the positioning grid 777 and is constrained to position. The lower end of the fuel rod is fixed to the bottom beam grid 773 of the bundle, and the bottom grid 773 of the bundle is fixed to the upper end of the lower header 775 or to the skeleton tube 776.

[0140] As shown in FIG. 23, a cannulated open fuel assembly: The cannulated open fuel assembly includes a pin 785, a bundle bottom grid 773, a main sleeve 789, an open fuel rod 700, and an exhaust member. The pin 785 is provided with a sealed structure to prevent leakage, and the pin 785 is also provided with a fixed structure (such as a bolt structure) fixed to the core bottom grid 256, and a plurality of coolant inlet holes 786 are provided on the pin 785. And the structure that controls the leakage flow. The bottom end of the fuel rod is fixed to the bottom layer of the beam bundle 773, and the bottom layer of the bundle bottom 773 is fixed to the lower end of the main sleeve 789 or the upper end of the pin 785.

[0141] The liquid heavy metal primary coolant has a large buoyancy, and both the fuel rod and the fuel assembly must be fixed at the lower end.

[0142] As shown in FIG. 18, FIG. 19, FIG. 20 and FIG. 21, the bottom of the fuel rod is fixed: a lower portion of the fuel assembly is provided with a bundle bottom grid 773, and the fuel rod is fixed on the bottom layer 773 of the bundle, and the fixing manner is Threaded or welded or inlaid. Threading: The end plug 725 end and the beam bottom grid 773 are provided with a boss 734 for positioning, a groove 735 and a screw hole 738 for fixing, first inlaid with the boss 734 and the groove 735 (to prevent fuel The rod is loosely rotated and then screwed with a screw 737; the other configuration is that the end of the fuel rod lower end plug 725 and the rod bottom grid 773 are screwed together and screwed 738 for screwing. Soldering and fixing: The bottom end plug of the fuel rod 725 is provided with a notch 742 at the end, and the strip grid of the bottom layer of the bundle 773 is inserted into the notch 742 of the lower end plug 725 and then fixed by welding. Inlaid fixing: The bottom end of the fuel rod 725 is provided with a keyway 747 at the end, and the corresponding beam guide is arranged on the bottom of the beam, and the beam guide slides into the keyway 747 for inlay fixing.

[0143] Fuel rod tip positioning: The open fuel rod assembly may be provided with a rod bundle top grid 772 for fuel rod tip positioning, and the rod bundle top grid plate 772 is fixed at the upper end of the fuel assembly body, ie, the upper tube holder 774 or the main sleeve The upper end of the tube 789; the top beam plate 772 of the bundle is provided with a positioning hole and a coolant hole, and the exhaust pipe 729 passes through the positioning hole on the top plate 772 of the beam to position the fuel rod, and the upper plug 726 and the rod of the fuel rod An anti-vibration spring is disposed between the bundle top grid plates 772, and the anti-vibration spring sleeve is sleeved at the base of the exhaust capillary tube 729. The fuel rod exhaust pipe that requires the top positioning can be thickened and thickened at the base to enhance the strength against external forces.

[0144] Fuel Assembly Mounting: The lower header 775 or pin 785 of the fuel rod assembly is secured to the core bottom grid 256 (eg, bolt construction).

[0145] The top of the fuel assembly can be positioned using a core top grid 255 that is positioned with the upper end of the exhaust main 755 passing through the locating holes of the core top grid 255.

[0146] Exhaust member: An upper portion of the open fuel rod assembly is provided with an exhaust member, and the exhaust member main body includes a restraining portion 751 and an exhaust main pipe 755. The restraining portion 751 is located at a lower portion of the exhaust member and is coupled to the fuel assembly main body, and the restraining portion 751 is sleeve-shaped or flared or claw-shaped. The upper part of the exhaust member is an exhaust main pipe 755, and the top of the exhaust main pipe 755 may be provided with a pressure relief valve 757 or a pressure relief valve; the exhaust member of the pressure relief valve 757 is provided with a valve exhaust member, and no pressure relief valve is provided. The exhaust member is a valveless exhaust member.

[0147] As shown in FIG. 24, the valveless exhaust member: the valveless exhaust member includes a restraining portion 751, an exhaust thin tube bundle 731, and an exhaust main pipe 755, which are simply constrained into a tight exhaust gas. After the thin tube bundle 731 is directly inserted into the exhaust main pipe 755, the exhaust thin pipe 729 can be expanded and contracted in the exhaust main pipe 755, and a lifting operation head can be disposed outside the exhaust main pipe 755.

[0148] As shown in FIG. 26, the valve exhaust member: the valve exhaust member body includes a restraining portion 751, a seal sleeve 732, an exhaust capillary bundle 731, a seal head 753, an exhaust main pipe 755, and a pressure relief valve. 757. Pressure relief valve 757 is set at exhaust main 755 At the top end, the exhaust pipe 729 in the valve exhaust member is firstly subjected to a rotationally constrained constraint at the restraining portion 751, and the upper end portion thereof is constrained into a tight exhaust pipe bundle 731, that is, the exhaust pipe 729 is in the restraint portion 751 region. The segment is in a loosely rotating state, and the twisted exhaust pipe 729 has a spring-like function, and has a certain flexing and extension function to buffer the fuel bar deformation stress and meet the requirements of the fuel rod irradiation elongation. The lower end of the sealing sleeve 732 is fixed to the upper end of the restraining portion 751, and the sealing sleeve 732 is sleeved with the exhaust capillary bundle 731, and the two are integrally sealed (such as brazed seal) to form an exhaustable sealing head 753, exhausting The main tube 755 is then sealed to the sealing sleeve 732 so that the fissile gas can only be discharged through the exhaust main 755 and the pressure relief valve 757. Brazing solder is generally difficult to meet the high requirements of high temperature resistance and corrosion resistance. The sealing head 753 of the brazed seal needs to be isolated from the main coolant, and the sealing sleeve 732 is appropriately lengthened, and the retained gas is retained in the sealing sleeve 732 when the main coolant is poured. 752, this portion of the trapped gas 752 that cannot be discharged becomes a barrier layer between the sealing head 753 and the main coolant. The exhaust main pipe 755 is provided with a gas injection hole 756 or a gas injection pipe. After the fuel assembly is manufactured, vacuuming and gas injection processing are performed, and the gas injection hole 756 or the gas injection pipe is closed.

[0149] The sealing head 753 is brazed and sealed, and the process flow is as follows: After the fuel rod is completed, the vacuum is closed and the end of the exhaust pipe is closed (such as mechanical sealing after induction heating), and the exhaust pipe 729 can be closed before being closed. Injecting the detection gas, the length of the exhaust pipe 729 is preferably slightly longer than the top end of the sealing sleeve 732 → completing the fuel rod airtightness and flaw detection inspection → completing the main assembly of the fuel rod assembly → annealing and swirling the exhaust capillary 729 The upper part of the re-constraint exhaust pipe 729 forms a tight exhaust pipe bundle 731 → the joint of the welding constraint portion 751 and the seal sleeve 732 → the connection constraint portion and the fuel assembly main body and the exhaust pipe bundle 731 Insert the sealing sleeve 732 → plug the gap between the exhaust pipe with a wire → surface treatment at the seal → heat the solder pool to melt the solder (the melting point of the solder is higher than the maximum operating temperature of the main coolant) → inverted fuel rod assembly Insert the seal into the solder bath at a suitable depth. After the solder is fully immersed, take it out and cool it into a sealing head 753. → Finish the polished sealing sleeve 732 → Cut off At the end of the sealing head 753, honour the exhaust pipe 729 port to ensure that each exhaust pipe 729 is unblocked.

[0150] Pressure relief valve: a pressure relief valve 757 is provided at the top of the valve exhausting member, and the pressure relief valve 757 is a spring type pressure relief valve or a fusible heavy metal pressure relief valve or a double pressure relief valve; An exhaust adsorption zone may be disposed in the main pipe 755, and the exhaust adsorption zone includes an adsorption body positioner 766, an adsorption body 765, and an adsorption body compression spring 767. The adsorbent 765 is a rod-shaped cartridge provided with a mesh hole filled with an adsorbent. The sorbent body positioner 766 is a positioning spring or an elastic clamp to prevent displacement of the absorbing body 765. The sorbent body compression spring 767 compresses the sorbent body 765 against airflow shock and displacement.

[0151] As shown in FIG. 27, the spring type pressure relief valve: the spring type pressure relief valve is cylindrical, and includes a valve housing 811, a lower valve body 812, an upper valve body 813, a spring 814, a spring positioning head 815, and a pressure. The screw 816; the valve housing is cylindrical, and the side of the lower valve body 812 is fixed to the valve housing 811 and sealed. The lower valve body 812 and the upper valve body 813 have a valve structure corresponding to the convex and concave surface, and the convex and concave surfaces can be closely attached to achieve sealing, and the convex and concave surfaces can be separated to realize exhaust pressure relief; the corresponding structure of the lower convex and concave concave is favorable for the gas to wash away the condensation. , the valve body is not easy to scale. A vent hole 818 is disposed in the middle of the lower valve body 812, and a vent hole 818 is disposed on the side of the upper valve body 813. Upper valve body The upper end of the 813 is connected to the spring, the upper end of the spring is connected with a spring positioning head 815, the pressing screw 816 presses down the spring positioning head 815, the pressing screw 816 and the upper end of the valve housing 811 are screwed, the spring positioning head 815 and the pressing screw 816 is provided with a vent 818 for gas discharge.

[0152] As shown in FIG. 28, the fusible heavy metal type pressure relief valve: the valve function of the fusible heavy metal type pressure relief valve is replaced by liquid heavy metal, and the fusible heavy metal type pressure relief valve includes an annular groove, a cap 822, and a fusible Heavy metal 825 and anti-deblocking head 827. The cap 822 is an upper valve body, which is a blind tube shape, the annular groove is a lower valve body, the cap 822 and the annular groove form a mosaic structure with a gap, and the gap of the annular groove is filled with a fusible heavy metal 825, which is fusible. The heavy metal 825 is a sealant, and the anti-deblocking head 827 prevents the cap 822 from being washed away by the internal high pressure airflow, such as a retaining screw. The working temperature of the fusible heavy metal type pressure relief valve is above the melting point of the fusible heavy metal. The heavy metal solidified below the working temperature is equivalent to the fixing and sealing action of the solder. When the pressure is released, the differential pressure pushes the gas through the heavy metal liquid 825. The U-shaped channel formed, the pressure difference is determined by the specific gravity and height of the heavy metal liquid, the annular groove is a single member or a composite member, and the annular groove of the single member, that is, the lower valve body is an annular groove-like whole, the composite member The annular groove is formed by welding and sealing the valve housing 811, the lower valve body 812 and the central air tube 831.

[0153] As shown in FIG. 29, the double pressure relief valve: the double pressure relief valve is an open type fuel assembly with two pressure relief valves connected in series at the top, the lower pressure relief valve is a fusible heavy metal type pressure relief valve, and the upper is a spring type pressure relief valve. The valve, the lower valve body 812 can be used as the anti-deblocking head 827 of the fusible heavy metal type pressure relief valve. The advantages of the double pressure relief valve are good sealing effect. The heavy metal solidified at low temperature can be completely sealed. The double pressure relief valve can double protect the oil at high temperature. The heavy metal liquid can also absorb the volatile matter in the fission gas to prevent the valve body from scaling and increase. The reliability of the spring type pressure relief valve.

Claims

Claim

A method for implementing a fast reactor-type coupled nuclear reaction, characterized in that: the reactor main container is split into a fission pool (201) and a moderated pool (301) that are completely isolated from each other, and the slowing pool (301) is internally moderated. a core (250) in the fission pool, the core has a fast neutron core characteristic; the fission pool (201) and the slowing pool (301) are inlaid or movably combined to couple the structure and function of the two, In the fission pool (201) and the slowing pool

An insulation layer is provided between (301) to block the heat exchange between the two; the moderator is separated from the main coolant, the fission pool (201) and the core (250) are free of moderator, and the main coolant passes through the fission pool ( 201) without passing through the slowing pool (301); allowing the neutron to pass through the configuration between the fission pool (201) and the slowing pool (301), making the fission pool

(201) and the slowing pool (301) can perform neutron exchange and perform a coupled nuclear reaction, and the fast neutron generated by the core and the slowed neutron reflected from the slowing pool (301) into the fission pool (201) can Core (250) simultaneous coupling of nuclear reactions induced by fast neutrons and slowed neutrons (including thermal neutrons and mesenchytrons), fission pool

(201) has the characteristics and functions of a fast neutron reactor, and the thermal neutron nuclear reaction can be performed in the slowing pool (301)

(such as thermal neutron capture reaction).

2. The method for implementing a fast reactor type coupled nuclear reaction according to claim 1, characterized in that: optimizing the material and structure of the main vessel of the reactor, and providing a large-area thin-walled neutron exchange window on the side wall of the main vessel of the reactor, The neutron exchange efficiency is increased while ensuring the structural strength; the coupled nuclear control system is set in the slowing pool (301), the coupled nuclear control and the passive shutdown are implemented by the coupled nuclear reaction; the slowing neutron function and slow using the moderator The controllability of the chemical or the controlled displacement of the moderated pool, the reactivity of the core (250) is controlled by changing the neutron exchange between the fission pool (201) and the slower tank (301); The slowing pool (301) loses the neutron moderating function, terminates the slowing pool (301) and transports the slowed neutrons to the core (250), and the core reactivity is rapidly decreased, so that the chain fission reaction cannot be maintained, thereby achieving passive operation. Shutdown; using the high efficiency of thermal neutron nuclear reaction, implementing on-line extraction of nuclear fuel proliferation and proliferating fuel, realizing Pa-233/U-233 conversion and Th-232/U-233 separation outside the reactor; 301) Settings can be changed online The fuel-proliferating fuel system, the initial proliferating fuel feedstock contains only one species of nuclides, Th-232, and only undergoes a Th-232 thermal neutron capture nuclear reaction, avoiding or reducing the neutrons caused by Pa-233 and U-233 capture neutrons. Double loss of effective nuclear fuel; Optimize fuel element and core design (such as candle core design) to improve nuclear reaction efficiency and fuel consumption rate; Reduce reactor simplification, simplification, cost reduction and modularization The overall replacement of the fission pool or the implementation of the fission pool module decommissioning once (the fission pool is decommissioned with the core replacement); modularizing the main components of the reactor to enable the reactor to be split and combined; using an easy-to-reassemble casing connection and split method , simplifying the splitting and recombination of the reactor module, the casing connection and splitting method is vertical socket or non-vertical socket or non-vertical rotation vertical Socket; Vertical Socket: Connection sleeve (175) can be reused many times longer, the lower tube head is fixed tube head

(176), the upper tube head is a detachable tube head (177), and the two tube heads are mounted on the same vertical axis with vertical lifting; before the initial connection, the connecting sleeve (175) is welded to the lower tube head in advance. (179), when connecting, the upper tube head (178) is aligned and slightly inserted into the connecting sleeve (175) and welded. The welding surface is facing upwards and the welding effect is the best; the splitting is only required in the connecting sleeve (175) The upper end of the weld is cut and separated, and the connecting sleeve (175) is slightly shortened; the residue in the connecting sleeve (175) is cleaned during recombination, and the upper tube head is appropriately lengthened compared with the previous one, and the previous connection process is repeated. Non-vertical splicing: Non-vertical splicing is mainly based on horizontal pipe connection, installed in vertical hoisting, and the pipe head connected to the split module is detachable pipe head

(177), the corresponding other tube head is the fixed tube head (176), the connecting sleeve (175) is shorter as a disposable part, and then the connecting sleeve (175) is lengthened as needed or the length is long and the detachable tube head is extended. (177); When connecting, pre-set the connecting sleeve (175) on the fixed pipe head (176) but not welding, and slide the connecting sleeve (175) to expose the fixed pipe head (176). Connect the sleeve (175) and weld the ends separately; cut the entire joint sleeve (175) when splitting, and replace it with a new joint sleeve of the appropriate length.

( 175), repeat the previous connection process; non-vertical sleeve welding is difficult, the welding effect is not easy to guarantee; non-vertical to vertical socket: the two pipes connected are non-vertical pipes, the two to be connected The tube head is converted into a concentric vertical tube head with elbows, the fixed tube head (176) is below, the detachable tube head (177) is on, and the subsequent connection, splitting and recombination methods are the same as vertical sockets. .

3. A fast reactor type coupled nuclear reactor, characterized in that: a reactor main vessel comprises a fission pool (201) and a slower tank (301) coupled to each other and completely isolated from each other, and the fission pool (201) has a built-in core (250), The core has the characteristics of a fast neutron core, the slowing tank (301) has a built-in moderator, the moderator is separated from the main coolant, the moderator does not enter the fission pool, and the main coolant does not enter the slow tank (301) An insulating layer is provided between the fission pool (201) and the slowing tank (301), the heat insulating layer is a vacuum structure or a filling heat insulating material, and the fission pool (201) and the slowing pool (301) are capable of neutron exchange but Heat exchange is blocked; main coolant is liquid metal or molten salt; moderator is solid moderator or liquid moderator; solid moderator is graphite or carbide or barium compound, especially graphite; liquid moderator a heavy water or heavy aqueous solution or a light or light aqueous solution, especially heavy water; a moderator tank filled with a liquid moderator; a fission pool (201) and a slower tank (301) combined to form a main vessel coupling structure, The main container coupling is constructed as a single slowing pool built-in coupling Structure or single moderation pool external coupling structure or double moderation pool coupling structure; single slowing pool built-in coupling structure is slowing pool (301) located in the center of the reactor is a barrel-shaped structure, and the fission pool (201) is located in the slowing The outer side of the pool (301) has an annular pool structure; The externally coupled structure of the single slowing pool is a fission pool (201) located in the center of the reactor as a barrel-shaped structure, and the slowing pool (301) is located outside the fission pool (201) in an annular pool structure or a cylindrical structure; The coupling structure of the chemical pool is that the internal slowing pool (302) is a barrel-shaped structure at the center of the reactor, and the outer slowing pool (303) is located at the outer side of the annular pool structure, and the fission pool (201) is located between the inner and outer slowing pools. The annular container structure; the main container coupling structure is a detachable combined structure or a non-detachable fixed structure; the main container casing (101) may be disposed on the outer periphery of the reactor main container, and the main container casing (101) is a thickened The pool type metal casing, the fission pool (201) and the moderated tank (301) are placed and fixed within the main vessel casing (101).

4. A nuclear reactor main vessel provided with a large-area neutron exchange window, characterized in that: a large-area neutron exchange window can be arranged on the side wall of the main container of the fast reactor-type coupled nuclear reactor, and the neutron exchange window is a thin-walled structure, thin-walled Constructed as a frame skin structure or a thin-walled rib structure; the frame skin structure is provided with a frame (133) on a side wall portion of the neutron exchange area, and a thin plate skin (132) is disposed on the frame, and the main body other than the frame skin structure The container part may adopt a non-thin wall structure, such as a bottom plate, a side wall near the bottom and the top, and a thick wall structure; the thin wall rib structure is a side wall with a thin wall (142) as a main body, and a thin wall (142) is provided with a rib plate. (143) Reinforcement; frame skin structure or thin-walled ribbed structure can be constructed in one piece; the main frame or main rib can be placed in the vertical symmetrical position of the main container side wall, and the hoisting bearing capacity is borne by the main frame or the main rib; A special reinforcement structure can be set at a large bearing position, such as a reinforcing frame or a stiffener at the main coolant outlet.

5. The fast reactor type coupled nuclear reactor according to claim 3, wherein: the fissile pool side wall (203) can be provided with a large-area thin-walled structure as a neutron exchange window, and the thin-walled structure is a frame skin structure or a thin wall. a rib structure; a sidewall insulation layer (211) is disposed between the fission pool side wall (203) and the slowing tank side wall (306), the side wall insulation layer material is solid particles, and the fission pool side wall (203) is The slowing pool side wall (306) transmits lateral pressure through the side wall insulation layer (211) to form mutual lateral support; the bottom of the fission pool may be provided with a load-bearing heat insulation layer (212), and the load-bearing heat insulation layer (212) is block-shaped Solid, such as insulated ceramic blocks.

6. The fast reactor type coupled nuclear reactor according to claim 5, wherein: the fission pool top cover (202) or the slowing tank top cover (305) is sealed by a sealant (154); a sealant (154) Metal sealant or sealant, metal sealant is fusible metal or fusible alloy, such as tin, tin-bismuth alloy, lead, lead-bismuth alloy, lead-tin alloy, lead-bismuth alloy; sealant is temperature and corrosion resistant Sealant, such as sealed silicone, sealant is suitable for low temperature type containers (such as slowing tank); the upper edge of the container side wall (150) is provided with an annular groove (152), and the outer edge of the container top cover (151) is arranged downwardly. The skirt plate (153); the sealing structure of the top cover and the side wall may be provided with a locking device (155), the locking device is a thread structure or a bolt structure or a spring clamp; The groove (152) is uniformly filled with an appropriate amount of liquid sealant (154), and the annular skirt is inserted into the annular groove before the sealant solidifies, and then the locking device (155) is fastened, and the sealant (154) is solidified. That is, the sealing structure is formed; the solidification of the metal sealant forms a firm sealing structure between the top cover and the side wall, and the metal sealing agent can be melted by heating the sealing structure during separation; the heating device can be arranged by the sealing structure of the fusible metal; The inner edge of the annular groove (152) may be higher than the outer edge to prevent the sealant from falling into the container.

7. The fast reactor type coupled nuclear reactor according to claim 3, wherein: the material of the slowing tank (301) is a metal having high neutron transparency, such as aluminum, aluminum alloy, zirconium alloy, aluminum zirconium alloy, aluminum titanium alloy. Zirconium-niobium alloy, nickel-aluminum alloy; The surface of the slowing tank with aluminum or aluminum alloy can be plated with water-resistant metal, and the water-resistant metal is zirconium or nickel or titanium.

8. A fuel tank built into a fuel rod, characterized in that: a fast reactor type coupled nuclear reactor uses a fuel rod assembly core, and a fuel tank (703) can be disposed in the fuel rod to wrap the filler (722), that is, a filler. (722) Filled into the fuel tank (703), the filler (722) does not directly contact the fuel rod cladding tube (728), the filler (722) includes fuel, and the fuel bladder (703) has a rod-shaped cladding configuration.

9. The fuel liner of claim 8, wherein: the fuel bladder (703) body comprises a bladder tube (705), a bottom plug (707), a top plug (708), a filler (722), and a pressure. a tight spring (721), a gas injection hole (709) or a gas injection pipe (710); the outer diameter of the fuel tank (703) is slightly smaller than the inner diameter of the fuel rod cladding tube (728), the fuel expansion space is reserved, and the inner tube (705) is The casing of the fuel tank (703), the inner tube (705) is sealed at both ends by a bottom plug (707) and a top plug (708), and the top plug (708) is provided with a gas injection hole (709) or a gas injection pipe.

(710), a filler (722) and a compression spring (721) are provided in the fuel tank, and the gas injection hole (709) or the gas injection pipe (710) is used for pumping or injecting or exhausting, and the gas injection hole (709) In the shape of a hole, the gas injection pipe (710) is a short tubular shape, and the gas injection hole (709) or the gas injection pipe (710) can be set as a self-opening sealing structure, and the gas injection hole (709) or the gas injection pipe (710) is performed after the gas injection is completed. After the fuel tank (703) is heated or boosted or heated up and boosted, the gas injection hole (709) or the gas injection pipe (710) is opened and exhausted by itself, and the self-opening sealing structure is a burstable structure or a meltable sealing plug. Explosive structure: The gas injection pipe (710) can be bursted, the burst type is burst of low-strength material or burst of low-strength structure, and the low-strength material is material of low-strength material or low-strength material after heating. Fuel tank (703) temperature rises, internal air pressure increases, gas injection pipe

(710) The pressure bursts and opens the air by itself; the low-strength structure is provided with a bursting groove on the gas injection pipe (710), the gas injection pipe wall is thin at the bursting groove, the air pressure difference causes the cracking groove to form a crack, and the gas injection pipe (710) cracks the exhaust gas; Fusible sealing plug: The fusible sealing plug can be melted after heating, and can be composed of a single sealing agent or a plurality of sealing agents, The sealant is a kind of sealant with different melting points. The outer layer of the sealing plug has a lower melting point than the inner layer. When sealing, the outer layer sealant is equivalent to the brazing material. After the core starts to heat up, the sealing plug is completely melted by heat, and the gas injection hole (709) is opened. Exhaust; a protective cover (711) may be added to the top of the fuel tank (703). The shield (711) refers to a sleeve shape or a cap shape, and the shield (711) is provided with a hole for gas communication, and the shield (711) is disposed. In the gas injection hole (709) or the gas injection pipe (710), the casing-like shield (711) is directly welded to the top end of the top plug (708) after the fuel liner (703) is insufflated, and the cap-shaped shield ( 711) is fixed on the top plug (708) by a fuel rod pressing spring, and the shield (711) prevents the explosion or splash from contacting the fuel rod cladding tube (728); the fuel rod or the fuel tank (703) can be Fill the heat transfer medium, such as helium and sodium.

10. An open type fuel rod and its components, characterized in that: a core of a fast reactor type coupled nuclear reactor may adopt an open fuel rod assembly; an open type fuel rod assembly is composed of an open type fuel rod (700); The fuel rod (700) has a main structure of a bottom-end closed and a top open-ended rod-shaped cladding tube structure, and a top end opening is provided with an exhaust capillary tube (729); an upper portion of the fuel assembly using the open fuel rod (700) is provided with an exhaust gas The open fuel rod (700) constitutes an open fuel rod assembly, the open fuel rod assembly is a bundle open fuel assembly or a sleeve open fuel assembly; the bundle open fuel assembly has no main sleeve, the sleeve opening The fuel assembly has a main casing (789).

11. The open fuel rod and assembly thereof according to claim 10, wherein the open fuel rod (700) body comprises a lower end plug (725), a cladding tube (728), a compression spring (721), The upper end plug (726), the exhaust capillary tube (729), the filler (722) or the fuel inner tank (703), the end of the fuel rod is welded with an end plug, the bottom end is sealed by the lower end plug (725), and the upper end plug ( 726) an opening is provided, and an exhaust pipe is welded at the opening

(729), the fission gas is discharged by the exhaust pipe (729), the open fuel rod (700) has no air chamber or has a short upper air chamber (717), a filler (722) or a fuel tank (703) The compression spring (721) is disposed on the top; the filler (722) in the fuel rod or the fuel tank (703) is set in the same manner, and the nuclide segment in the filler (722) can be divided into three zones, from bottom to top respectively. The conversion zone (712), the fuel zone (713) and the up-conversion zone (714), the up-down conversion zone is only initially loaded with a convertible nuclide, and the fuel zone (713) is initially provided with a fissile nuclide; the filler (722) can be added. One or two shielding zones, the shielding zone is provided with a neutron absorber shielding the remaining neutrons, increasing the core axial shielding function; setting a shielding zone: an upper shielding zone is arranged at the uppermost portion of the filling; two shielding zones are provided: the filler (722) The lowermost shielding area and the upper part of the filler (722) are provided with an upper shielding area; the filling (722) may be provided with an adsorption area, the adsorption area is filled with a honeycomb solid adsorbent to adsorb fission volatiles, and the adsorption area is located up-conversion Between zone (714) and upper shield or between fillers (722) End, the adsorption zone The position can be exchanged with the upper shield zone; the fuel rod filler (722) has six basic zone combinations from bottom to top: downconversion zone - fuel zone - upconversion zone, downconversion zone - fuel zone - upconversion zone - adsorption zone , down conversion zone - fuel zone - upconversion zone - upper shield zone, down conversion zone - fuel zone - upconversion zone - adsorption zone - upper shield zone, lower shield zone - down conversion zone - fuel zone - up conversion zone - Shielding zone, lower shielding zone - down conversion zone - fuel zone - upconversion zone - adsorption zone - upper shielding zone.

12. The open fuel rod of claim 11 and an assembly thereof, wherein: the bundle open fuel assembly comprises a lower header (775), a bundle bottom grid (773), a skeleton tube (776), Positioning grid (777), open fuel rod (700), upper header (774) and exhaust member; skeleton tube (776), positioning grid (777) and upper and lower headers together form the skeleton of the fuel assembly, The positioning grid is fixed on the skeleton tube bundle, and the skeleton tube

(776) Both ends are fixed with the upper and lower tube holders; the skeleton tube (776) is divided into two types, the first type is a through-hole tube, which can be used as a guide tube (such as a guide tube for nuclear measurement), and the second type is a real tube. The end of the tube is welded with an end plug, which is fixed by the end plug and the upper and lower tube seat. The real tube is provided with a convertible fuel, a compression spring and a short air chamber, and the solid tube is equivalent to the conversion fuel rod; the fuel rod is from the positioning grid ( The 777 is passed through and constrained. The lower end of the fuel rod is fixed to the bottom of the bundle (773), and the bottom of the bundle (773) is fixed to the upper end of the lower header (775) or to the skeleton tube (776). The casing open fuel assembly includes a pin (785), a bundle bottom grid (773), a main casing (789), an open fuel rod (700), and an exhaust member, and the pin (785) is provided with a seal The leakage prevention structure is constructed, and the pin (785) is also provided with a fixed structure (such as a bolt structure) fixed to the core bottom grid plate (256), a plurality of coolant inlet holes (786) on the pin (785) and a control leak. The structure of the flow, the bottom end of the fuel rod is fixed to the bottom of the rod bundle (773), and the bottom of the rod bundle (773) Set at the lower end of the main bushing (789) or the upper end of the pin (785), the upper part of the main bushing (789) can be set with the distance between the spacers to maintain the assembly; the open fuel rod assembly is provided with or without the bundle top grid Set the top beam of the bundle: The top of the bundle (772) is fixed at the upper end of the fuel assembly body, that is, in the upper header (774) or the upper end of the main sleeve (789), on the top of the bundle (772) Positioning holes and coolant holes are provided, and the exhaust pipe (729) passes through the positioning holes on the top plate of the beam (772) to position the fuel rod, the upper plug of the fuel rod (726) and the top plate of the bundle ( 772) An anti-vibration spring is arranged between the anti-vibration springs at the base of the exhaust pipe (729); the base of the exhaust pipe (729) that needs to be positioned at the top can be thickened and thickened to enhance the strength against external forces.

13. The open-ended fuel rod and assembly thereof according to claim 12, wherein: an upper portion of the open fuel rod assembly is provided with an exhaust member, and the exhaust member main body includes a restraining portion (751) and an exhaust main pipe (755) The restraining portion (751) is located at a lower portion of the exhaust member and connected to the fuel assembly main body, and the restraining portion (751) is a sleeve a shape or a horn or a claw shape, and a coolant outlet hole is disposed thereon; a constraining portion receiving plate (761) may be disposed at an upper end of the sleeve-shaped restraining portion, and the restraining portion receiving plate (761) may be provided with a fixing structure for engaging other components, such as Connection sleeve, threaded configuration; upper part of the exhaust member is the exhaust main pipe (755), the top of the exhaust main pipe (755) is provided with a pressure relief valve (757) or no relief valve is provided; the exhaust of the pressure relief valve (757) is set The component is a valve exhaust member, the exhaust member not provided with the pressure relief valve is a valveless exhaust member; a lifting operation head may be disposed outside the exhaust member; the valveless exhaust member: the valveless exhaust member includes a restraining portion (751 ), the exhaust pipe bundle (731) and the exhaust pipe (755), the exhaust pipe (729) is simply restrained into a tight exhaust pipe bundle (731) and directly inserted into the exhaust pipe (755), The exhaust pipe (729) can be extended and retracted in the exhaust main (755).

14. The open fuel rod of claim 13 and an assembly thereof, wherein: the valved exhaust member body comprises a restraining portion (751), a sealing sleeve (732), an exhaust capillary bundle (731), The sealing head (753), the exhaust main pipe (755) and the pressure relief valve (757), the pressure relief valve (757) are disposed at the top of the exhaust main pipe (755), and the exhaust pipe (729) in the valve exhausting member is After the constraint portion (751) is firstly subjected to the rotatory constraint, the upper end portion is constrained into a tight exhaust pipe bundle (731), that is, the exhaust pipe (729) is loosely rotated in the constraint portion (751). In the curved state, and satisfying the requirement of the elongation of the fuel rod, the lower end of the sealing sleeve (732) is fixed to the upper end of the restraining portion (751), and the sealing sleeve (732) is fitted with the exhaust thin tube bundle (731), both After the integral sealing (such as brazing seal), the venting sealing head (753) is formed, and the exhaust main pipe (755) is sealed with the sealing sleeve (732) so that the fissile gas can only pass through the exhaust main pipe (755). And pressure relief valve

(757) Discharge, the sealing sleeve (732) can be lengthened appropriately. When the main coolant is poured, the trapping gas (752) will remain in the sealing sleeve (732). This part of the trapped gas (752) that cannot be discharged becomes the sealing head (753). The isolation layer of the main coolant, the exhaust main pipe (755) is provided with a gas injection hole (756) or a gas injection pipe, after the fuel assembly is manufactured, vacuuming and gas injection processing is performed, and the gas injection hole (756) or the gas injection pipe is closed; Seal head

(753) Brazing seal can be used. The process flow is as follows: After the fuel rod is finished, vacuum and close the end of the exhaust pipe (such as mechanical seal after induction heating), before closing the exhaust pipe (729), as needed Perfusion detection gas, the length of the exhaust pipe (729) is slightly longer at the top end than the top of the sealing sleeve (732) → complete the fuel rod air tightness and flaw detection → complete the main assembly of the fuel rod assembly → the exhaust pipe ( 729) Annealing and twirling constraining the lower part → reconstraining the exhaust pipe (729) to form a tight exhaust pipe bundle at the upper part

(731) → The joint of the welding constraint (751) and the sealing sleeve (732) → the connection constraint and the fuel assembly body and the bundle of the exhaust pipe (731) into the sealing sleeve (732) → with a wire plug Close the gap between the exhaust pipe → surface treatment at the seal → heat the solder pool to melt the solder (the melting point of the solder is higher than the main cold The maximum operating temperature of the agent)→Inverted fuel rod assembly, insert the sealing part into the solder tank at a suitable depth, and after the soldering liquid is fully immersed, take it out and cool it into a sealing head (753) → Finish the polished sealing sleeve (732) → Cut off the seal At the very end of the head (753), tidy the exhaust pipe (729) port to ensure that each exhaust pipe (729) is unobstructed.

15. The open fuel rod and assembly thereof according to claim 14, wherein: a valve relief member has a pressure relief valve (757) at the top end, and a pressure relief valve (757) is a spring type pressure relief valve or fusible valve. Heavy metal pressure relief valve or double pressure relief valve; spring type pressure relief valve: spring type pressure relief valve is cylindrical, including valve housing (811), lower valve body

(812), upper valve body (813), spring (814), spring positioning head (815) and compression screw (816), the valve housing is cylindrical, the side of the lower valve body (812) and the valve housing ( 811) fixed and sealed, the lower valve body (812) and the upper valve body (813) are convex and concave corresponding valve structure, the convex and concave surface is close to the seal, the convex and concave surfaces can be separated to achieve exhaust pressure relief, the lower valve body ( 812) A vent hole (818) is arranged in the middle, a vent hole (818) is arranged on the side of the upper valve body (813), an upper end of the upper valve body (813) is connected with the spring, and a spring positioning head (815) is connected to the upper end of the spring, and the screw is tightened. (816) Press down on the spring positioning head (815), the compression screw (816) and the upper end of the valve housing (811) are threaded, and the spring positioning head (815) and compression screw (816) are provided with venting holes (818). Gas supply; fusible heavy metal pressure relief valve: The valve function of the fusible heavy metal pressure relief valve is replaced by liquid heavy metal. The fusible heavy metal pressure relief valve includes annular groove, cap (822), and fusible heavy metal ( 825) and the anti-deblocking head (827), the cap (822) is the upper valve body In the shape of a blind tube, the annular groove is a lower valve body, and the cap (822) and the annular groove form a mosaic structure with a gap. The gap of the annular groove is filled with a fusible heavy metal (825), and the fusible heavy metal (825) is Sealant, anti-deblocking head (827) anti-closure cap

(822) is washed away by the internal high-pressure airflow, such as anti-off screws, the annular groove is a single member or a composite member, and the annular groove of the single member, that is, the lower valve body is an annular groove-like whole, and the ring of the composite member Groove by valve housing

(811), the lower valve body (812) and the central air pipe (831) are welded and sealed; the double pressure relief valve: the double pressure relief valve is an open fuel assembly with two pressure relief valves in series, and the lower pressure relief valve is fusible Heavy metal type pressure relief valve, spring type pressure relief valve, spring type pressure relief valve lower valve body (812) can be used as fusible heavy metal type pressure relief valve anti-deblocking head (827); valve exhaust member An exhaust adsorption zone may be disposed in the exhaust main pipe (755), and the exhaust adsorption zone includes a adsorbent body positioner (766), an adsorbent body (765), and a sorbent body compression spring (767); the sorbent body (765) is clothed a rod-shaped box with a mesh hole filled with an adsorbent; a sorbent body positioner (766) is a positioning spring or an elastic clamp to prevent displacement of the absorbing body (765); and a sorbent body pressing spring (767) presses the absorbing body (765) ), against air impact and displacement.

16. The fast reactor type coupled nuclear reactor according to claim 3, wherein: the core (250) is a solid core, and the core can be provided with radial partitioning of two or three characteristics; Partition: The area near the slowing pool is the coupling area, and the slow spectrum area is the fast spectrum area; the radial partitioning of the three characteristics: adding a buffer between the coupling area and the fast spectrum area to enhance the core safety; At the same time, the thermal neutron and fast neutron nuclear reactions are carried out, and the fuel distribution ratio is close to that of the thermal neutron core; the fast spectrum region performs the fast neutron nuclear reaction, and the fuel distribution ratio is close to the fast neutron core; The distribution ratio characteristic is determined by the core safety design; a proliferation zone or a shielding zone (258) may be added to the periphery of the core; the core is composed of a fuel component, the fuel component is composed of a fuel rod, and the fuel rod is an open fuel rod (700) or Closed fuel rod (795); the fuel assembly is a rod bundle fuel assembly or a casing fuel assembly, the bundle fuel assembly has no main casing, the casing fuel assembly has a main casing (789); and the closed fuel rod (795) constitutes Rod bundle closed fuel Component or casing closed fuel assembly; open fuel rod

(700) constituting a bundle open fuel assembly or a sleeve open fuel assembly; the fuel assembly is bottom fixed, the bottom fixing method may be a core bottom grid (256) fixed, and the lower stem of the fuel rod assembly (775) Or the pin (785) is fixed to the core bottom plate (256) (such as the bolt structure); the top of the fuel assembly can be positioned by the core top grid (255), and the positioning pin (782) of the upper end of the closed fuel rod assembly is The core top grid plate (255) is positioned, and the open fuel rod assembly passes through the core top grid plate with the upper end of the exhaust gas main pipe (755)

The positioning hole of (255) is positioned; the lower part of the fuel assembly is provided with a bottom beam plate (773), and the fuel rod is fixed on the bottom plate (773) of the beam bundle, and the fixing manner can be screw fixing or welding fixing or mosaic fixing. Threading: The lower end plug (725) end and the beam bottom grid (773) are provided with a boss (734) for positioning, a groove (735) and a screw hole (738) for fixing, first inlaid convex The table (734) and the groove (735) are positioned and screwed with a screw (737), and the other configuration is a screw corresponding to the end of the lower end plug (725) of the fuel rod and the bottom plate of the bundle (773). The screw hole (738) is screwed; the welding is fixed: the fuel rod lower end plug (725) is provided with a notch (742) at the end, and the strip grid of the bottom beam (773) of the rod bundle is inserted into the notch of the lower end plug (725) (742) Re-welding and fixing; Inlaid fixing: The fuel rod lower end plug (725) is provided with a keyway (747) at the end, and the corresponding bundle guide rail is arranged on the bottom of the bundle beam, and the bundle guide slides into the keyway.

(747) Perform a mosaic mount.

17. The fast reactor type coupled nuclear reactor according to claim 16, wherein: the main structure of the closed fuel rod (795) is a rod-shaped cladding tube structure closed at both ends, and the closed fuel rod (795) includes a lower end plug. (725), cladding tube (728), air chamber (717), compression spring (721), upper end plug (726), filler (722) or fuel tank (703), upper end plug (726) and lower end Plug (725) seals the shell tube (728) at both ends, The cladding tube (728) has a long air chamber (717), the air chamber is located at the upper or lower portion, and a compression spring (721) is disposed on the filler (722) or the fuel tank (703); the fuel rod or the fuel tank The filling (722) in (703) is set the same, and the nuclide segment of the filling is divided into three zones, from bottom to top: down conversion zone (712), fuel zone (713) and upconversion zone (714). The conversion zone is only initially loaded with convertible nuclide, the fuel zone (713) is initially equipped with fissile nuclide; the closed fuel rod assembly is a rod bundle closed fuel assembly or a casing closed fuel assembly; the rod bundle closed fuel assembly : Rod bundle closed fuel assembly includes lower header (775), bundle bottom grid (773), skeleton tube

(776), a positioning grid (777), a closed fuel rod (795), and an upper header (774); the skeleton tube (776), the positioning grid (777), and the upper and lower headers together constitute a skeleton of the fuel rod assembly, A plurality of positioning grids (777) are fixed on the skeleton tube bundle, and both ends of the skeleton tube (776) are fixed to the upper and lower tube holders; the skeleton tube (776) is of two types, and the first type is a through-hole tube, which can be used as a guiding tube ( For example, the measuring guide tube); the second type is a solid tube, the end of the solid tube is welded with an end plug, and the end plug is fixed with the upper and lower tube seat (775), and the tube is provided with a convertible fuel, a compression spring and a short air chamber. The solid tube is equivalent to the conversion fuel rod; the fuel rod passes through the positioning grid (777) and is constrained and positioned; the fuel rod is fixed on the bottom layer of the rod bundle (773), and the bottom layer of the rod bundle (773) is fixed under The upper end of the socket (775) is either fixed to the skeleton tube (776); the lower header (775) is provided with a positioning pin

(782) or the pin hole is positioned with the core bottom grid plate (256), and the lower tube seat (775) is provided with a fixed structure (such as a bolt structure) to fix the assembly on the core bottom grid plate (256); the upper tube seat ( 774) Positioning pin (782) and pin hole positioning on the core top grid (255); casing closed fuel assembly: casing closed fuel assembly including pin (785), rod bundle bottom grid (773 ), the main casing (789) and the closed fuel rod (795), the pin (785) is provided with a sealed structure to prevent leakage, and the pin (785) is also provided with a fixed structure (such as a bolt structure) and a core bottom grid. The plate (256) is fixed, the pin (785) has a plurality of coolant inlet holes (786) and a structure for controlling leakage flow, the lower end of the main casing (789) is connected to the pin (785), and the fuel rod is located at the main casing. (789), an upper shield may be added on the fuel rod, and the middle portion of the fuel rod is positioned by grid positioning or wire winding, and the bottom end of the fuel rod is fixed with the bottom layer of the bundle (773), and the bottom of the rod bundle (773) ) fixed at the lower end of the main bushing (789) or the upper end of the pin (785), and the top of the main bushing (789) is provided with a lifting operation The head and the coolant outlet, the upper part of the outer side of the main sleeve can be provided with a spacer (791) to maintain the distance between the components.

18. The fast reactor type coupled nuclear reactor according to claim 17, wherein: a fission cell air chamber (221) is disposed at a top of the fission pool, and a gas generated by the fission pool is discharged into the fission pool air chamber (221); The fission cell (201) of the fuel rod assembly may be provided with a double-layer fission cell chamber; a double-layer fission chamber chamber is provided: an exhaust main pipe (755) of the open fuel rod assembly passes through the core top grid (255), the pile Core top grid (255) will The fission cell chamber (221) is divided into a fission cell upper chamber (222) and a fission pool lower chamber (223); the reactor is provided with a fission gas purification system, and the fission gas purification system is a gas circulation purification system, functioning of cooling components and removal with chemistry Active and nuclear activating fission gas components, such as iodine, cesium, bromine, cesium; fission gas purification system is a closed gas circulation circuit, fission gas purification system including fission pool gas chamber (221), air pump (912), gas purification Cooling chamber (913), exhaust gas tank (916), gas distribution tank (915), gas mixing chamber (914), air supply pump (917), flow control valve (937) and monitoring device; fission gas in gas purification cooling chamber ( 913) is purified, excess purified gas is injected into the exhaust gas tank, and the gas mixing chamber (914) will pick up the gas in the gas distribution tank (such as oxygen tank, hydrogen tank, argon tank) as needed to make the formulated gas The composition meets special requirements, such as oxygen content; the gas flow in the double-layer fission cell gas chamber is that the circulating gas first enters the lower chamber of the fission pool (223), and then passes between the two gas chambers. Entering the upper chamber of the fission pool (222), and then discharging the fission pool, the circulating gas flowing from bottom to top takes off the fission gas and blocks the fission gas from contacting the main coolant to prevent harmful gas from polluting the main coolant; Work flow of the fission gas purification system It is: fission pool air chamber → air pump → gas purification cooling chamber → gas mixing room → air supply pump → gas flow control valve → fission pool air chamber.

19. The fast reactor type coupled nuclear reactor of claim 16, characterized by: a rod bundle closed fuel assembly, a casing closed fuel assembly, a bundle open fuel assembly or a casing open fuel assembly The component may have a corresponding semi-shaped component or a special-shaped component, and the semi-shaped component or the special-shaped component fills the nick of the core edge, so that the coupling zone structure of the core edge approaches the complete; the cross-section of the half-shaped component is the corresponding component. Half of the diagonal cut of the cross section, the cross section of the profiled component can be any shape, and the choice of shape depends on the fill effect.

20. The fast reactor type coupled nuclear reactor according to claim 16, wherein: the core is a candle core, and the candle core is gradually burned from bottom to top, and the initial fissile nuclide is mainly distributed in the core. Below the fuel zone, the concentration ladder is lower and higher, and the upper fuel is accumulated by the proliferative reaction. The cumulative velocity is adapted to the upward velocity of the combustion zone, and the core fuel consumption rate is higher toward the lower part.

21. The fast reactor type coupled nuclear reactor according to claim 16, wherein: a core base (251) is disposed under the core (250), and the core (250) is fixed on the core base (251), and the core The base (251) is attached to the fissile pool floor (205).

22. The fast reactor type coupled nuclear reactor according to claim 5, wherein: the slowing tank (301) is filled with a liquid moderator, the slowing tank is provided with a slowing liquid circuit, and the slowing liquid is provided by a slowing liquid cooler. (602) cooling; The reactor is equipped with a nuclear control system to regulate the core power and perform the shutdown operation. The nuclear control system is a slower tank level nuclear control system or a barrier screen nuclear control system or a slower tank displacement nuclear control system or a control rod nuclear control system; The pool liquid level nuclear control system is set in the slow liquid circuit, the slow liquid circulation circuit is a one-way slow liquid circulation circuit, and the slowing liquid is always input from the top of the slowing tank (301); the slowing liquid level nuclear control system passes Adjusting the liquid level height of the moderator in the slowing tank to change the neutron exchange and neutron energy spectrum, thereby achieving the purpose of regulating the core reactivity, and automatically performing the passive shutdown in an emergency; the one-way slowing liquid circuit The medium slowing liquid is not filled with the slowing tank, the reactor movement can cause the slowing liquid to fluctuate, and the slowing tank liquid level nuclear control system is not suitable for the mobile reactor; the barrier screen nuclear control system also has a slowing liquid circuit, which includes the slowing liquid The circuit and the barrier screen mechanism, the slowing liquid circuit is a variable direction slowing liquid circuit. During normal operation, the slowing liquid is input to the top output from the bottom of the slowing tank (301), and the slowing tank (301) is filled with the slowing liquid, Affected by reactor movement During the shutdown period, the slowing liquid is changed from the top of the slowing tank (301), and the slowing tank (301) does not accumulate the slowing liquid; the barrier screen nuclear control system regulates the core reactivity by blocking the neutron exchange. It has no slowing fluid fluctuations, is suitable for mobile reactors, and can also be used for stationary reactors; the slower tank displacement nuclear control system is the overall mobile slowing pool (301), by changing the slowing pool (301) and the fission pool (201) The coupling structure changes the neutron exchange and coupled nuclear reactions to regulate core reactivity. The slower cell displacement nuclear control system is suitable for micro or small nuclear reactors, especially space nuclear reactors.

23. The fast reactor type coupled nuclear reactor according to claim 22, wherein: the one-way slowing liquid circuit inputs the slowing liquid from the top of the slowing tank (301), and the main body thereof includes the slowing pool (301) and the liquid storage. Pool (601), slow solution, infusion pump (632), infusion tube (633), spray (631), return tube (635) and slow solution cooler (602), one-way slow solution loop The infusion pump (632) is driven, and its circulation path is: reservoir → infusion pump → sprayer → slowing pool → return tube → slow solution cooler → reservoir; reservoir (601) is lower than slow In the chemical pool (301), the slowing liquid relies on gravity reflux, and the larger the difference between the liquid storage tank (601) and the slowing tank (301), the greater the backflow potential energy; the infusion tube (633) is provided with an infusion pump (632), infusion The pump (632) quantitatively supplies the slowing liquid to the slowing tank, the infusion tube (633) is connected to the bottom of the liquid storage tank (601), and the other end is connected to the liquid sprayer (631) in the upper part of the slowing tank (301), and the liquid is sprayed. The main body of the device (631) is a container or tube member provided with a nozzle (such as a hollow grid plate container or a mesh tube or a branch tube) ), the function is to spray or spray the slowing liquid to the surface of each device in the slowing tank, the slowing liquid flows from top to bottom to take away the heat on the device; the return pipe (635) is a large diameter pipe, Meet the requirements of fast shutdown; the slow solution cooler (602) is the cooling and temperature control device of the slowing liquid, which is set inside or outside the liquid storage tank; the surface of the parts to be cooled in the slowing tank can be provided with a wire mesh. The surface of the cooling component is covered with wire mesh, and the wire mesh is slowed down. Slowing the flow rate of the liquid, helping the slowing liquid to evenly distribute on the surface of the part and preventing the slowing liquid from splashing.

24. The fast reactor type coupled nuclear reactor according to claim 23, wherein: the main body of the moderated pool level nuclear control system comprises a one-way slowing liquid circuit, a gas equalizing tube (638) and a liquid flow control mechanism; tube

(638) Connect the top of the slowing tank (301) and the top of the reservoir (601) to balance the pressure of the two tanks; the flow control mechanism includes the flow controller (605), the shutdown valve (611), the monitoring device and the control The flow controller (605) is a single electric regulating valve or consists of a plurality of electric regulating valves whose function is to precisely adjust the level of the slowing pool; the shutdown valve (611) is normally closed and is opened during shutdown. The shutdown valve (611) may be one or more large-diameter normally-closed electric valves connected in series; the monitoring device includes a moderator liquid level monitoring device and a temperature sensor; and the infusion pump is used during the normal operation of the slowing pool level nuclear control system ( 632) pumping the slowing liquid into the slowing tank (301), and dispersing the slowing liquid to the surface of each device to flow down and accumulating in the slowing tank, and the slowing liquid passes the gravity flow controller by gravity ( 605) returning to the liquid storage tank (601) through a return pipe (635) at a certain flow rate, and being cooled and controlled by the slow solution liquid cooler (602); when the reactor is shut down, the shutdown program is started or the shutdown valve is shut off ( 611) power supply, normally closed shutdown valve (611) automatically opens, slows down The slowing liquid in the tank is quickly returned to the liquid storage tank (601) through the large-diameter shutdown valve (611), and the slowing liquid pool does not accumulate the slowing liquid; the slowing liquid circuit continues to perform the cooling function during the shutdown; the reactor power control Workflow: Execution by the flow controller, first adjust the level of the moderator liquid in the slower pool, and then change the neutron exchange and neutron energy spectrum, and finally achieve the purpose of regulating the core power; the workflow of the shutdown operation: Start the shutdown program or cut off the power to the shutdown valve → Shutdown valve

(611) Automatic opening → slowing liquid is quickly returned to the liquid storage tank (601) through the large-diameter shutdown valve (611) → the slowing tank lacks the slowing liquid and loses the neutron moderation function → the thermal neutron fission reaction is terminated →The core can not maintain the chain reaction and stop the reactor; Shutdown cooling process: The shutdown valve (611) is in the open state → The infusion pump (632) continues to run → The slowing liquid circuit continues to circulate → The sprayer (631) is slow The components in the chemical pool are sprayed with a slowing agent and cooled. The slowing liquid is quickly returned to the liquid storage tank (601) through the shutdown valve (611) → the slowing liquid cannot accumulate in the slowing tank; the slowing pool liquid level nuclear control system Recovery process: shut down the shutdown operation or resume the shutdown valve

(611) Power supply → Shutdown valve (611) is off → Slowing liquid is returned to the reservoir via the flow controller (605) (601) → Regulate the flow controller (605) to make the tank level Keep at the right height.

25. The fast reactor type coupled nuclear reactor according to claim 22, wherein: the variable direction slowing liquid circuit body comprises a slowing tank (301), a liquid storage tank (601), a slowing liquid, and an infusion tube (633). , infusion pump (632), upper infusion tube (655), upper infusion valve (656), lower infusion tube (661), lower infusion valve (662), sprayer

(631), upper return pipe (663), lower return pipe (665), lower return valve (666), and slower liquid cooler (602); The slowing fluid of the variable direction slowing liquid circuit is transported by the infusion pump (632), and the normal operation period is controlled by the infusion pump.

(632) Provide all the power to transport the slow solution; increase the gravity return during the shutdown period, and the larger the difference of the return potential between the reservoir (601) and the slower pool (301); the lower end of the infusion tube (633) At the bottom of the tank (601), an infusion pump (632) is arranged on the infusion tube (633), and an infusion tube is separated from the infusion pump (632).

(655) and the lower infusion tube (661); the upper infusion tube (655) is connected to the liquid ejecting device (631), and the main body of the liquid ejecting device (631) is a container or a tube member provided with a nozzle (such as a hollow grid plate shape) a container or a mesh pipe or a branched pipe), the slowing liquid is dispersed into the surface of each device in the slowing tank through the liquid sprayer (631), and the slowing liquid flows from the top to the bottom to take away the heat on the device; The lower infusion tube (661) is connected to the bottom of the slowing tank; the lower return tube (665) is a large diameter tube to meet the requirements of rapid shutdown; the lower infusion valve (662) is normally open, closed during shutdown, and infusion The valve (662) can be a normally open electric valve; the upper infusion valve (656) and the lower return valve (666) are normally closed, open during shutdown, and the upper infusion valve (656) and the lower return valve (666) can be common Closed electric valve; The circulation path during normal operation is: reservoir (601) → infusion tube (633) → infusion pump (632) → lower infusion valve (662) → lower infusion tube (661) → slowing pool (301 ) → Upper return pipe (663) → Slow solution cooler (602) → Reservoir (601) The circulation path during shutdown is: reservoir (601) → infusion tube (633) → infusion pump (632) → upper infusion valve (656) → upper infusion tube

(655) →sprayer (631)→slowering tank (301)→downflow return valve (666)→lower return pipe (665)→moderator cooler (602)→reservoir (601), shutdown During the period, the upper return pipe (663) function is converted into gas balance, and the pressure in the slowing tank (301) and the liquid storage tank (601) is balanced; the surface of the component to be cooled in the slowing tank can be provided with a screen, and the surface of the component needs to be cooled. Set the screen cover, the screen reduces the slowing liquid flow rate, helps the slow solution to evenly distribute on the surface of the part, and prevents the slowing liquid from splashing.

26. The fast reactor type coupled nuclear reactor according to claim 25, wherein: the main body of the barrier screen nuclear control system comprises a variable direction slowing liquid circuit and a blocking screen mechanism; and the main body of the blocking screen mechanism comprises a barrier screen driver (682) and a transmission belt. (683), upper guide rod (685), sealing sleeve (427), sealing ring (691), barrier screen (681), lower guide rod (695) and lower guide tube (696); barrier screen (681) setting On the side of the slowing pool (301) near the fission pool, the barrier screen (681) is a cylindrical or curved plate body of the lower fork, and the lower guide is provided with a lower guide rod (695), and the upper part of the barrier screen (681) is disposed. Upper guide rod (685); sealing sleeve (427) is arranged on the slowing tank top cover (305) or on the slowing tank upper deck, and a sealing ring (691) and a sliding structure are arranged in the sealing sleeve (427). The guide rod (685) slides within the sealing sleeve (427); the lower guide rod (695) slides and is positioned in the lower guide tube (696), and the lower guide tube (696) is provided with a leak hole; the barrier screen (681) ) with thermal barrier neutron Or the function of all neutrons, the barrier screen driver (682) drives the barrier screen (681) to move up and down, and the moving barrier screen (681) changes the neutron distribution and neutron exchange in the main container, thereby changing the core reactivity and regulating the reactor. Core power; Shutdown operation is performed by the variable direction slowing liquid circuit, starting the shutdown program or shutting off the power supply of the valve, the normally open lower infusion valve (662) is closed, the normally closed upper infusion valve (656) and the lower return valve ( 666) Automatically open, the slow solution flows rapidly into the reservoir (601) through the lower return pipe (665), and the gas in the reservoir (601) passes through the upper return pipe (663) into the slower pool to balance the two pools of gas, slowing down The pool (301) can not accumulate the slowing liquid, the thermal neutron and thermal neutron fission reaction disappears, and the core reactivity drops sharply, thus achieving the purpose of passive shutdown; during normal operation, the slowing liquid circulates from bottom to top, slow The chemical pool is filled with slowing liquid, and the cooling function is efficient; during the shutdown, the slowing liquid circuit changes direction from top to bottom, and the slowing liquid flows on the surface of each device to continue the cooling function.

27. The fast reactor type coupled nuclear reactor according to claim 5, wherein: the slowing tank (301) is filled with a liquid moderator, the slowing tank (301) is provided with a slowing liquid circuit, and the slowing liquid is slowed down. The liquid cooler (602) is cooled; the proliferative fuel system is set in the slowing tank (301), the proliferating fuel system is cooled by the slowing liquid; the proliferating fuel system is a immersed proliferating fuel system or an isolated propagating fuel system; the immersed proliferating fuel system The proliferating fuel raw material (convertible nuclides) is immersed in the slowing liquid, and the slowing liquid performs a solvent function to dissolve a part of the nuclide in the proliferating fuel, is taken out of the reactor through the slowing liquid circuit, and is separated online outside the main reactor of the reactor. Extraction; The isolated proliferating fuel system is a proliferative rod system, and the proliferating fuel is filled in the proliferative rod (365), and the proliferating fuel is isolated from the moderator.

28. The fast reactor type coupled nuclear reactor of claim 27, wherein: the main body of the proliferative rod system comprises a slowing fluid circuit, a proliferation rod (365), a proliferation rod sleeve (366), and a casing grid (367). , rod changing mechanism and auxiliary device; proliferation rod (365) is a rod-shaped shell tube structure sealed at both ends, filled with a proliferating fuel raw material (convertible nuclides); a proliferative rod sleeve (366) refers to a sleeve shape, Is a isolating sleeve between the proliferative rod (365) and the slowing tank (301), fixed on the slowing tank top cover (305) or the slowing tank upper deck or the moderated tank bottom plate, the open end of which is in the slowing pool In addition, the joint of the proliferative rod sleeve (366) and the fixed surface is a sealed structure; the proliferative rod sleeve (366) is isolated from the proliferative rod (365) and the slowing liquid, facilitating the online replacement of the proliferative rod, its length and cross-sectional shape and proliferation. Rods (365) adapt to each other; casing grid (367) reinforced proliferative rod casing

(366) to prevent deformation; the tube part of the proliferative rod (365) and the proliferative rod sleeve (366) is made of a material with high transparency to the neutron, such as an aluminum- or zirconium-based metal material; the rod-changing mechanism is a proliferation rod (365) Online replacement facility, the bar changing mechanism can be set above or below the slowing pool (301), blocking above the slowing pool For the obstacle area of the object (such as pipeline), choose the bar replacement method below or replace the proliferation rod with the substitute; the substitute does not need to be replaced online, only need to be replaced when the slowing pool is opened, and the substitute can be a secondary neutron. Source component or reflection rod or reaction rod, secondary neutron source assembly for reactor next start or new reactor start, reaction rod for artificial elements; accessory device including temperature detection device, temperature sensor built in proliferation rod (365) Inside, when the temperature in the proliferative rod (365) is higher than the normal value, it indicates that a fission reaction occurs in the proliferative rod, and the content of U-233 has reached the extractable range, and the rod must be replaced.

29. The fast reactor type coupled nuclear reactor of claim 28, wherein: the proliferation rod (365) comprises a bottom plug or bottom plate, a cladding tube, a filler, a temperature sensor and a tip portion; the lower end is closed by a bottom plug or The bottom plate is sealed, the upper end is sealed by the top end portion, and the operation head is provided on the top end portion for the rod changing mechanism to be grasped, the initial filling material (proliferation fuel raw material) is a bismuth compound, and the temperature sensor is placed in the filling; the proliferation rod is a repetitive use member or The disposable member, the repetitive growth rod can be used multiple times, the bottom plug and the top end can be separated from the cladding tube, the cladding tube is screwed and sealed with the bottom end plug and the top end portion; the rod changing mechanism of the proliferation rod system The positioning function and automatic bar changing function of the proliferation rod (365) can be set.

30. The fast reactor type coupled nuclear reactor according to claim 29, wherein: the separation and purification of the proliferating fuel adopts a separation process of a poorly soluble compound: separating a certain type of cerium compound from the inert property of the uranium compound, and proliferating the fuel raw material. In the case of a poorly soluble cerium compound, the uranium compound converted by the poorly soluble cerium compound is soluble; the poorly soluble compound is specific to a specific solvent, so that there are many kinds of poorly soluble cerium compounds; the solvent may be water or Acid or lye or organic solvent, insoluble bismuth compound is crystalline cerium oxide or cerium hydroxide or cerium or ceric acid or organic cerium compound; separation process of insoluble cerium compound: insoluble rod The sub-radiation→on-line extraction of the proliferative rod is placed in the storage room (9-11 months) until Pa-233 is fully degraded to U-233—the proliferative fuel is taken out from the proliferative rod and pulverized→the pulverized proliferated fuel is put into the dissolution tank. After thorough stirring, clarify → separate the solution and precipitate; the precipitate is dried to obtain a Th-232 compound; the separated solution is subjected to solute and solvent separation, The solute isolate is dried to give the U-233 compound.

31. The fast reactor type coupled nuclear reactor according to claim 29, wherein: the separation and purification of the proliferating fuel adopts a soluble compound separation process: the proliferating fuel raw material is a soluble cerium compound, and the soluble cerium compound is converted. The uranium compound is also soluble; the soluble compound is for a specific solvent, so there are various soluble hydrazine compounds; the solvent may be water or acid or alkali or organic solvent, soluble hydrazine compound It is a non-crystalline cerium oxide or cerium hydroxide or cerium or cerium or an organic cerium compound; a separation process of soluble cerium compound: refractory bismuth compound in the proton bar accepts neutron radiation → on-line extraction of the proliferation rod In the storage room (9-11 months), the Pa-233 is fully degraded to U-233. The proliferating fuel is taken out from the proliferative rod and pulverized. The pulverized proliferated fuel is put into the dissolution tank, stirred and dissolved → the proliferated fuel solution is → from the solution. U-233 is extracted; the solute is separated from the extract and dried to obtain a U-233 compound; the solute is separated from the remaining liquid after extraction and dried to obtain a Th-232 compound.

32. The fast reactor type coupled nuclear reactor according to claim 5, wherein: the main container is provided with a sleeve or a sealing sleeve (427), and a plug-in device is disposed in the sleeve or the sealing sleeve (427), such as Neutron source component

(411), nuclear measuring device; refers to the outer end of the outer end of the sleeve is closed, the main container is inserted into the isolation sleeve to form an isolation sleeve; the sealing sleeve (427) is provided with a sealing member (such as a sealing ring), and the sealing sleeve (427) Sealed outside the main container, the insert in the sealing sleeve (427) is not isolated from the main container; the neutron source mechanism (401) can be placed at the bottom of the fission pool or at the top of the slowing pool.

33. The fast reactor type coupled nuclear reactor according to claim 32, wherein: a neutron source mechanism (401) is disposed at a bottom of the fission pool, and a neutron source mechanism (401) body includes a neutron source component (411) and a neutron. Source cooler (431), neutron source bushing (415), sliding sleeve (426) and neutron source driver (413); neutron source bushing (415) is the isolation of the neutron source component from the main coolant The casing, the neutron source casing (415) and the sliding casing (426) are in communication and are on the same centerline, both of which are fixed to the fission basin floor (205), the former being located in the fission pool (201), the latter Located outside the fission pool, except for the rest of the neutron source mechanism (401), which can be separated from the fission pool (201), the cross-sectional shape of the neutron source casing (415) can be combined with the core fuel assembly. Suitable for, for example, hexagonal; neutron source component (411) is a columnar seal structure, the base is a smooth sliding part, and the neutron source component (411) is internally provided with a neutron source (400) and a coolant circulation channel; Subsource cooler (431) cools neutron source component (411), neutron The cooler (431) is a gas or liquid cooling circuit. The coolant can flow from the center of the neutron source assembly (411) to the periphery. The function of the neutron source driver (413) is to drive the neutron source assembly (411) in the sliding sleeve. The tube (426) slides inside, the neutron source component (411) slides up and down, and the neutron source driver (413) can be a motor-driven simple lifting platform (such as hydraulic, screw, rack type) or Complex electromagnetic drive.

The fast reactor type coupled nuclear reactor according to claim 32, wherein: the sub-source mechanism (401) in the slowing pool is disposed at the top of the slowing pool (301), and the sub-source mechanism (401) of the slowing pool includes: Neutron source component

(411), sealing sleeve (427), sealing ring (691) and neutron source driver (413); sealing sleeve (427) is fixed on the slowing tank top cover (305), neutron source assembly (411) The outer casing is a smooth cylindrical sealed container with a neutron source (400); the neutron source assembly (411) and the sealing sleeve (427) form a slidable The sealed structure; the neutron source driver (413) drives the neutron source component (411) to move within the sealing sleeve (427), the neutron source driver (413) is a lifting device or an electromagnetic driving device; the neutron source component (411) The neutron source component can be filled with thermal fluid or heat-conducting gas to enhance the cooling effect; the neutron source component (411) releases the neutrons in the slower pool to become thermal neutrons, thermal neutron exchange Entering the fission pool triggers the core fission reaction.

35. The fast reactor type coupled nuclear reactor according to claim 3, wherein: the main coolant is a liquid heavy metal, in particular lead or lead-bismuth eutectic; the main circuit is a main coolant circuit, and the main circuit is provided with an oxygen control system, Protect the main circuit structure and functional materials; The oxygen control system is a gas phase oxygen control system or a solid phase oxygen control system; the main circuit can be provided with a main coolant auxiliary heating and insulation device, and the main coolant auxiliary heating and heat preservation device is arranged at the bottom of the fission pool and the circulation pipe Its function is to melt the solidified main coolant and prevent the main coolant from solidifying.

36. The fast reactor type coupled nuclear reactor of claim 35, wherein: the gas phase oxygen control system body comprises an oxygen controlled gas circuit, a gas diffusion device (282), a gas pump (283), and a prosecution device; the oxygen controlled gas circuit comprises a gas mixing chamber (281) and a circulation air passage, the gas mixing chamber (281) proportions the oxygen-control gas component to a suitable ratio; the gas diffusion device (282) is a pipe or a container through which the main coolant flows, and may include a stirring device. The gas diffusion device (282) may be replaced by a main circulation pump (235) or a main circulation pipe (236) or a fission cell gas chamber (221); the gas pump (283) blasts the oxygen-controlled gas into the gas diffusion device (282), the oxygen-controlled gas Disperse evenly into the main coolant, and a small amount of dissolved residual gas is returned to the gas mixing chamber (281) for re-distribution; the control device detects the oxygen content of the main circuit and the proportion of the gas component in the oxygen-controlled gas circuit and commands the gas mixing chamber ( 281) regulating each gas component; the solid phase oxygen control system body comprises a mass exchanger

(285) and the prosecution device; the mass exchanger (285) is a container-type device filled with oxide solid particles (286), which can be placed on the branch circuit of the main circuit, and the oxide solid particles can be dissolved in the main coolant in a small amount. , such as lead oxide PbO; the main coolant flows through the mass exchanger (285) to perform solute exchange on the oxide solid particles (286), ie, oxide dissolution and solute precipitation deposition; the control device includes a thermostat (287) and a flow controller (289) that detects and regulates the temperature or flow rate of the main coolant flowing through the oxide solid particles (286) or the branch opening time, and controls the main coolant by controlling the dissolution and precipitation process of the oxide. The oxygen content of the branch can be provided by the differential pressure of the main circuit jet.

37. The fast reactor type coupled nuclear reactor according to claim 36, wherein: the gas phase oxygen control system can adopt a ternary gas combination, and the ternary gas includes an oxidizing gas, a reducing gas and a carrier gas, and the oxidizing gas can be selected. Water vapor or oxygen or carbon dioxide, reducing gas can be hydrogen or carbon monoxide, carrier gas Argon gas can be used; ternary gas combination can be selected from 3⁄40/ 3⁄4/ Ar or 3⁄4/ Ar or C0 ₂ / CO/ Ar; solid phase oxygen control system can add a bypass setting hydride dissolution device to coordinate the regulation of oxygen content in the main circuit The hydride dissolving device may be disposed at the other end of the main circuit opposite to the mass exchanger (285); the oxygen measuring probe of the oxygen control system may be a zirconia oxygen sensor.

38. The fast reactor type coupled nuclear reactor according to claim 5, wherein: the reactor is provided with a small circulation pump residual heat discharge device and an emergency passive residual heat removal system, and after the shutdown, the small circulation pump residual heat discharge device replaces the main circulation system. The residual heat in the reactor is discharged; when the residual heat discharge device of the small circulation pump fails to work due to the failure during the shutdown, the reactor immediately activates the emergency passive residual heat removal system; the emergency passive residual heat removal system is located higher than the main container, and the initial operating power is gravity. Subsequent power is derived from steam; the main body of the emergency passive residual heat removal system includes a hot liquid tank (931), a cooling water tank (932), a vacuum chamber (934), a flow control valve (937), a start valve (938), and a pipe; The height is: the vacuum chamber (934) is the highest, the cooling water tank (932) is the second, followed by the heat carrier tank (931), and the fission pool (201) is the lowest; the heat carrier tank (931) stores the pure water or the aqueous solution, the aqueous solution. It may contain a neutron absorber such as a boron-containing aqueous solution; a cooling water tank (932) stores cooling water, and the amount of cooling water depends on the set residual heat output; The empty chamber (934) initially functions to absorb the gas in the main container and the circuit, and the vacuum chamber (934) is connected to an air suction tube (935) and a liquid discharge tube (936), the suction tube ( 935) Connect the end of the condenser (933), the drain pipe (936) is connected to the hot water tank (931); the flow control valve (937) is normally closed, usually set to a flow rate setting, or can be controlled The line regulation size, the flow control valve (937) can be a normally closed electric valve; the other valves are the starting valve (938), the starting valve (938) is in the closed state during normal operation, all channels are cut off, and the valve is activated in emergency (938) In the open state, the starting valve (938) can be a normally closed electric valve; after the starting valve (938) is fully opened, the reactor residual heat is passively discharged into the fission pool (201) in the form of water vapor; the entire system has two circuits: one circuit It is a gas circuit, the other circuit is a water-steam circuit; the starting procedure of the passive residual heat removal system: reactor shutdown → small circulation pump waste heat removal system can not work normally → cut off the power supply of emergency passive residual heat removal system Start by program → Emergency passive residual heat removal system starts automatically; Gas circuit workflow: Vacuum chamber (934) - Secondary suction of gas in main vessel and pipeline, fission chamber gas chamber (221 ) → Steam tube (939) → Condenser (933) → Vacuum chamber (934) - drain tube (936) - heat transfer tank (931); water-steam circuit work flow: heat carrier tank (931) → heat transfer liquid → flow control valve ( 937)→ fission cell gas chamber (221)→dispersed to the main coolant surface→water vapor→steam tube (939)→condensation tube (933)→condensed water→carrier liquid tank (931).

39. The fast reactor type coupled nuclear reactor according to claim 5, wherein: the reactor main container is a single slowing pool built-in coupling structure, and the slowing pool (301) is located in the center of the reactor as a barrel-shaped structure, a moderator It is heavy water or light water; the fission pool (201) is located in the annular pool structure outside the slowing tank (301), the main coolant is lead or lead-bismuth alloy, and the fission pool (201) can be provided with a fission pool air chamber (221) A heat exchange tank (502) is disposed outside the reactor, a heat transfer wall (503) is shared inside the heat exchange pool and outside the fission pool, and a heat transfer tube (504) is disposed outside the heat transfer wall (503), and the main coolant is in heat transfer The tube (504) and the fission pool (201) are internally circulated, and the heat transfer tube (504) and the heat transfer wall (503) are provided with a heat sink (505), a heat transfer tube (504) and a heat transfer wall.

(503) jointly derive core heat; the inner side wall (203) of the fission pool is provided with a large-area thin-walled neutron exchange window; the core adopts a solid fuel rod core, and the outer periphery of the core can be provided with a conversion fuel zone, the outer side of the core A shielding area (258) is provided; a slowing pool setting slowing pool level nuclear control system (fixed stack) or a barrier screen nuclear control system

(mobile stack); neutron source mechanism (401) is set in fission pool or slower pool; heat exchange tank (502) is equivalent to first and second loop heat exchanger, second loop coolant is water; (508) and the blasting valve (509), when a water leak enters the heat transfer tube (504) and enters the collecting chamber (507), the water vaporizes into steam, and the light-heavy steam flows upward into the blast tube (508). Blasting valve (509) The pressurized membrane discharges water vapor to prevent water or steam from entering the core; when water leaks into the fission chamber air chamber (221), the detonating tube (508) is provided on the fission tank top cover (202) And the blasting valve (509) can also discharge water vapor; the deflector can be provided with a baffle (234); - the circuit is set or not equipped with a main circulation pump;

(235): The main coolant is forced to circulate; the main circuit is not provided in the primary circuit: the main coolant is self-circulating.

40. The fast reactor type coupled nuclear reactor according to claim 3, wherein: the reactor is a small or micro nuclear power device without a main container casing, and the main container is a single moderator external coupling structure, and the fission pool (201) Located in the center of the barrel, the slowing tank (301) is located in the outer ring shape, the moderator is graphite, filled in the cylindrical slowing pool; the reactor uses the slowing pool displacement control system, the slowing pool (301) No contact with fission pool

(201), the slowing pool (301) moves axially around the fission pool (201).

41. The fast reactor type coupled nuclear reactor according to claim 40, wherein: the reactor is a space nuclear power plant, and the main coolant is a liquid metal, in particular a liquid alkali metal, such as lithium-7, a core (250) body. It is composed of a closed fuel rod assembly, and the fission pool can be provided with a draft tube (233); the fission pool (201) is transferred from liquid metal to the thermoelectric conversion device; the slowing pool displacement control system performs neutron moderation and nuclear control functions. The slowing pool displacement nuclear control system comprises a slowing pool (301) and a slowing pool driving mechanism; the slowing pool driving mechanism body comprises a slowing pool driver (553), a clutch, a central guiding rod (555) and a rebounding device; Center guide (555) The axial direction is fixed in the center of the fission pool bottom plate (205). During normal operation, the clutch engages with the central guide rod (555), and the slowed pool drive (553) moves and positions along the central guide rod (555); the clutch and the center when the reactor is stopped The guide rod (555) is separated, and the rebound device pulls back or pushes the slowing pool back to the distal end, that is, the slowing pool is away from the fission pool, and the spring force of the rebound device is provided by the spring (558).

42. The fast reactor type coupled nuclear reactor according to claim 41, wherein: the slowing pool driver (553) is a stepping or rotating motor, the center guiding rod (555) is a screw, and the rotor core of the motor is hollow. The center guide rod (555) passes through the shaft of the motor rotor, and the motor rotor rotates around the center guide rod (555); in normal operation, the clutch engages with the center guide rod (555), and the motor pushes the slowing pool drive mechanism along the center guide Rod (555) movement and positioning; when the reactor is shut down, the clutch is separated from the central guide (555), and the rebound device pulls back or pushes the slowing pool (301) back to the distal end, ie, the slowing pool (301) is far from the fission pool (201), the core was shut down due to a lack of slowing neutron reactivity.