CN109801719B - Double-pressure-vessel type integrated nuclear reactor structure - Google Patents
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Abstract
The invention discloses a double-pressure vessel type integrated nuclear reactor structure, which aims to reduce the number of openings on a single pressure vessel and improve the performance of an integrated structure; the upper grid plate, the nuclear reactor fuel bundle, the control rods and the lower grid plate are arranged in the inner pressure container from top to bottom, meanwhile, the inner pressure container is located inside the outer pressure container, the inner pressure container and the outer pressure container are coaxial, and a top sealing chamber and a side chamber are formed between the outer wall of the inner pressure container and the outer pressure container. The top seal chamber is mainly used for providing nuclear protection and poison collection for the double-pressure vessel type nuclear reactor; the spiral steam generator is arranged in the side cavity, and under the driving of a main pump or natural inertia, coolant flows between the cavity of the inner pressure container and the side cavity in a reciprocating circulating mode through a coolant channel of the top side wall and the bottom wall surface of the inner pressure container, and continuously exchanges heat with the spiral steam generator to generate high-temperature and high-pressure steam so as to convey high-energy steam power for the steam turbine.
Description
Technical Field
The invention relates to the technical field of nuclear reactors, in particular to a double-pressure-vessel type integrated nuclear reactor structure.
Background
Mankind is seeking for clean and efficient energy safety all the time, and has used nuclear power for many years, nuclear power system has played an indispensable role in energy structures at home and abroad, the size of the nuclear reactor of the present very mature nuclear power plant is large-scale, which is not beneficial to the nuclear reactor to be applied to island power supply, mobile nuclear power platform, space nuclear power, ship power station and the like; at present, all countries around the world are striving to develop miniaturized nuclear reactors and miniature nuclear reactors with smaller volume and higher power density, and the nuclear reactors and the steam generator, a main device such as a main pump, a control rod driving mechanism and the like are directly combined with a pressure vessel to form an integrated structure (namely, an integrated nuclear reactor), which is one of the key development directions of future nuclear reactors.
Various forms of integrated reactors have been proposed by international and domestic research and development institutions, and various types of integrated nuclear reactors are researched and developed in the united states, including IRIS reactors which are mainly researched and developed by westinghouse corporation, small MASLWR reactors which are jointly researched and developed by the united states department of energy, and Nu-Scale reactors which are being researched and developed by the united states company NuScale, SMART reactors are also researched and developed by the korean atomic energy research institute, MRX reactors are also researched and developed by the japan atomic energy research institute, and the like.
Along with diversification of the existing nuclear reactor coolant, different thermal properties of the working medium of the nuclear reactor core are different, different nuclear reactor core structures and nuclear fuel structures need to be designed, and the integrated nuclear reactor also plays a role in research in other aspects, a single pressure vessel type nuclear reactor has very limited core space, and has over-high core radiation intensity, over-high neutron irradiation and difficult horizontal diffusion of poisons, so that the integrated nuclear reactor is not beneficial to considering research and application in other aspects, for example, release of a large amount of radiation, fission neutrons, rays and poisons is applied to human public utilities such as biomedical research, chemical product research, nuclear material modification research and the like, and meanwhile, the single pressure vessel type integrated nuclear reactor is not beneficial to natural heat exchange circulation of the coolant in the pressure vessel and isolation and discharge of the poisons of the nuclear reactor, in order to relieve the contradiction, research and development engineers at home and abroad are also developing multi-opening single pressure vessel type integrated nuclear reactors (the integrated nuclear reactor pressure vessel is provided with 2 or more bolt/welding connectors).
The multi-opening single pressure vessel type integrated nuclear reactor is characterized in that: the pressure vessel of the integrated nuclear reactor is formed by hermetically connecting or welding a plurality of components, generally comprises an upper end cover, a core support chamber, a lower end cover and a bearing support, and the integral structural strength and safety of the pressure vessel are influenced by the strength and the air tightness of the sealing joints.
However, with the rapid development of nuclear energy, people not only increasingly weigh the nuclear energy, but also increasingly worry about the inherent safety, and most of integrated nuclear reactors may be applied to offshore emergency power supply, mobile platform or moving platform power supply, etc., except for earthquake or flood, the mobile platform vibration and movement need to be considered within the nuclear safety design load range, so it is particularly necessary to design a second nuclear pressure safety barrier in addition to the integrated nuclear reactor pressure vessel, and it is especially necessary to prevent the nuclear reactor core from melting, the first loop coolant circulation of the first nuclear pressure safety barrier cannot pass through the nuclear reactor core to take away the nuclear heating crack, at this time, the cavity between the second nuclear pressure barrier (outer pressure vessel) and the inner pressure vessel can continuously perform inner cooling circulation, so that the natural cooling vessel can take away the nuclear cracking heating in the core melting state, improving the inherent safety of the nuclear reactor.
Disclosure of Invention
In view of the above, the present invention is directed to overcoming the disadvantages of the prior art, adapting to the practical needs, and providing a dual pressure vessel type integrated nuclear reactor structure, so as to reduce the number of openings on a single pressure vessel, improve the performance of the integrated structure, increase the space of an additional nuclear reactor, and provide a research platform for nuclear materials, nuclear medicine, and nuclear agriculture.
In order to realize the purpose of the invention, the technical scheme adopted by the invention is as follows:
designing a double-pressure-vessel type integrated nuclear reactor structure, which comprises a nuclear reactor fuel bundle, a control rod, an upper grid plate and a lower grid plate, wherein the lower grid plate provides support and fixation for the nuclear reactor fuel bundle, and the upper grid plate is fixed with a control rod magnetic rod lifting mechanism; meanwhile, the double-pressure-vessel type integrated nuclear reactor structure further comprises an inner pressure vessel and an outer pressure vessel, the inner pressure vessel is located inside the outer pressure vessel, the inner pressure vessel and the outer pressure vessel are coaxially arranged and are provided with a unified upper opening, therefore, a side cavity and a top cavity are formed between the outer wall of the inner pressure vessel and the outer pressure vessel, and the tops of the inner pressure vessel and the outer pressure vessel are closed.
The upper grid plate, the nuclear reactor fuel rod bundle, the control rods and the lower grid plate are arranged in the inner pressure container from top to bottom, the bottom of the inner pressure container is provided with a coolant distributor, and the wall surface of the bottom of the inner pressure container is provided with reactor core coolant. Meanwhile, the magnetic rod lifting mechanism with the control rods is fixed on the upper grid plate, so that fixed support is provided for the magnetic rod lifting mechanism, and vibration noise and transverse torsion of the magnetic rod lifting mechanism are reduced.
A top sealing chamber and a side chamber are formed between the outer wall of the inner pressure vessel 2 and the outer pressure vessel 18; the top seal chamber is mainly used for providing secondary seal protection, nuclear leakage detection and other nuclear protection and poison collection for the double-pressure vessel type nuclear reactor.
And a coolant channel is formed in the side wall of the top of the inner pressure vessel, the inner cavity of the inner pressure vessel is communicated with the inner cavity of the outer pressure vessel through the coolant channel, and the coolant of the reactor core enters between the inner pressure vessel and the outer pressure vessel through the coolant channel.
A spiral steam generator is arranged in a side cavity between the inner pressure vessel and the outer pressure vessel and surrounds the outer wall of the inner pressure vessel.
The helical steam generator is disposed at the top of the inner pressure vessel and below the coolant channels. The side wall of the outer pressure vessel is provided with a cooling water inlet channel of the spiral steam generator, the steam outlet is positioned at the upper part of the side cavity of the outer pressure vessel, and the installation position of the steam output pipe is different from that of the current reactor core of the nuclear power plant in that the outer pressure vessel does not have a side wall steam output pipe.
The internal pressure container is in a necking bottle shape, meanwhile, the spiral steam generator tube bundle surrounds the bottleneck position of the internal pressure container in a grouping mode, and the external bottleneck position of the internal pressure container is directly formed by direct spiral winding of a straight pipe on an assembly site.
The wet motor main pump is installed at the top in the internal pressure container, and the motor hoist and mount are on the sealed apron lower surface of internal pressure container, and the main pump is located coolant passage below, and the motor passes through transmission bearing with the main pump to be connected, and simultaneously, the main pump is located the 2/5 positions of internal pressure container throat bottleneck height.
Set up the external connection head of 4 spiral steam generator cooling water inlets on the outer pressure vessel lateral wall, 4 external connection are in 360 degrees circumference evenly symmetric distributions, and the lateral wall opening on this outer pressure vessel is whole to be spiral steam generator's cooling water inlet, does not have the headspace at the side window and gives steam outlet.
4 cooling water inlets of the spiral steam generator are positioned at the bottom of the spiral steam generator and close to 4 windows on the side wall of the outer pressure vessel, and a steam output pipe on the spiral steam generator is positioned at the top of the spiral steam generator and penetrates through the top sealing cover of the outer pressure vessel to the outside.
The top of the outer pressure vessel is provided with a sealing cover with an open and closed top, the sealing cover is connected with the top of the outer pressure vessel through a bolt, and an o-shaped elastic sealing tube with the circumference ratio of 4/5 is arranged between the sealing cover and the top of the outer pressure vessel.
The spiral steam generator is arranged in the side cavity, coolant can flow between the inner pressure container cavity and the side cavity in a reciprocating circulating mode through the coolant channels on the top side wall and the bottom wall surface of the inner pressure container under the driving of the main pump, and continuously exchanges heat with the spiral steam generator to generate high-temperature and high-pressure steam, so that high-energy steam power is conveyed to the steam turbine.
The internal pressure vessel is positioned inside the external pressure vessel, is mainly used for resisting neutron irradiation and weakening pressure fluctuation impact and thermal shock of the coolant under high temperature and high pressure, and the external pressure vessel is mainly used for providing stable coolant pressure and providing an internal circulation cavity environment for the whole integrated nuclear reactor.
The invention has the beneficial effects that:
the double-pressure vessel type integrated nuclear reactor structure can improve the natural heat exchange circulation efficiency of the reactor core of the nuclear reactor and the natural cooling efficiency of the residual heat of the reactor core, a loop pipeline system is cancelled by the double-pressure vessel type integrated structure, the probability of the occurrence of a breach accident of the pipeline system is reduced, meanwhile, the top side wall and the bottom wall surface of the inner pressure vessel are provided with coolant channels communicated with the top of the outer pressure vessel, high-temperature and high-pressure coolant heated by nuclear fuel assemblies of the nuclear reactor can enter the top of the outer pressure vessel through the coolant channels on the top side wall of the inner pressure vessel under the driving of a motor main pump arranged on the top of the inner pressure vessel, and is cooled by a spiral steam generator tube bundle spirally wound between the outer surface of the inner pressure vessel and the inner surface gap of the outer pressure vessel, and secondary side cooling water in the spiral steam generator tube bundle is heated into high-temperature and high-pressure water steam, the steam turbine is pushed to do work to provide electric power or mechanical power for the power device, meanwhile, after being cooled, the coolant sinks downwards in the outer pressure container, the temperature is reduced, the density is increased, the coolant continuously flows to a coolant channel on the wall surface of the bottom of the inner pressure container to enter the inner pressure container, flows through the coolant distributor and returns to the nuclear reactor core of the inner pressure container again, and integrated internal circulation is achieved. The integrated internal circulation can keep certain inertia in a short time when a main pump failure accident happens, continuously and circularly flows through the steam generator, and carries out the waste heat of the reactor core of the internal pressure container nuclear reactor to the spiral heat exchanger, thereby promoting the natural heat exchange circulation in the double-pressure container type integrated nuclear reactor and improving the inherent safety of the integrated nuclear reactor.
The double-pressure-container type integrated nuclear reactor structure is mainly applied to nuclear power generation, ship nuclear power, seawater desalination, industrial hydrogen production, urban heating, space energy supply and nuclear reactor batteries, and can also be applied to nuclear power moving platforms such as nuclear power cars, nuclear reactor trains, nuclear power aircrafts and the like due to compact double-pressure-container type integrated structure and high power density.
Drawings
FIG. 1 is a schematic diagram of the principal structure of a dual pressure vessel-integrated nuclear reactor configuration of the present design;
FIG. 2 is a schematic structural view of the double pressure vessel type integral nuclear reactor according to the present design in the structural appearance and section state;
fig. 3 is a partial structural schematic diagram of the double pressure vessel type integrated nuclear reactor according to the present design in a structural cross-sectional state.
Detailed Description
The invention is further illustrated with reference to the following figures and examples:
example 1: a dual pressure vessel integrated nuclear reactor structure, see figures 1 to 3.
The existing nuclear reactor comprises a nuclear reactor fuel bundle, a control rod 6, an upper grid plate 7 and a lower grid plate 19, wherein the lower grid plate 19 provides support and fixation for the nuclear reactor fuel bundle, and a control rod magnetic rod lifting mechanism 8 (which is a necessary structure for the existing nuclear reaction and is the prior art) is fixed on the upper grid plate 7.
The double-pressure vessel type integrated nuclear reactor structure comprises an inner pressure vessel 2 and an outer pressure vessel 18, wherein the inner pressure vessel 2 is in a necking bottle shape, the outer pressure vessel 18 is in a test tube shape, the inner pressure vessel and the outer pressure vessel are both integrated structures, further, the inner pressure vessel 2 is positioned inside the outer pressure vessel 18 and is supported by a support member 3 positioned on the inner bottom of the outer pressure vessel 18, a side cavity is formed between the outer wall of the inner pressure vessel 18 and the outer pressure vessel 2, and the top of the inner pressure vessel is fixed to the bottom of an end cover 1 at the top of the outer pressure vessel through bolts; while the inner pressure vessel 2 and the outer pressure vessel 18 are closed at the top; for the outer pressure vessel 18, the top of the outer pressure vessel 18 is provided with a sealing cover 13 for closing the top opening of the outer pressure vessel, the sealing cover 13 is connected with the top of the outer pressure vessel 18 through a bolt, and an o-shaped elastic sealing tube S01 with the circumference ratio of 4/5 is arranged between the sealing cover and the top of the outer pressure vessel, so that the inner pressure vessel and the outer pressure vessel have independent bidirectional sealing characteristics.
The upper grid plate 7, the nuclear reactor fuel bundle and the control rods 6, and the lower grid plate 19, which are necessary for the nuclear reactor, are arranged in the inner pressure vessel 2 from top to bottom, the inner pressure vessel 2 is divided into an upper chamber B01, a middle chamber B02, and a lower chamber B03 from top to bottom, specifically, the upper grid plate 7, the nuclear fuel bundle and the control rods 6, and the control rod magnetic lifting rod mechanism 8 are positioned in the middle chamber, a coolant distributor 4 (prior art) is installed in the lower chamber B03 at the bottom of the inner pressure vessel 2, a reactor core coolant channel is arranged at the bottom of the inner pressure vessel 2, and a lifting mechanism in a nuclear reactor molten state can be placed at the bottom of the inner pressure vessel 2, so that the lifting mechanism can delay or reduce the contact time of the reactor core molten with the residual coolant in the lower chamber of the inner pressure vessel and the intensity of steam explosion.
Furthermore, the side wall of the top of the inner pressure vessel 2 is provided with a coolant channel S06, the inner cavity of the inner pressure vessel 2 and the inner cavity of the outer pressure vessel 18 are communicated through a coolant channel S06, the core coolant enters the space between the inner pressure vessel 2 and the outer pressure vessel 18 through the coolant channel S06 and flows downwards, and meanwhile, the top in the inner pressure vessel is provided with a wet motor main pump 17 which is positioned at the coolant channel S06 and is used for pumping out the coolant heated in the inner pressure vessel and sending the coolant into the space between the inner pressure vessel 2 and the outer pressure vessel 18 through a coolant channel S06.
Furthermore, the spiral steam generator 11 is arranged in a side cavity between the inner pressure vessel 2 and the outer pressure vessel 18, the spiral steam generator 11 is formed by directly spirally surrounding a pipeline without a welding structure, the spiral steam generator 11 is arranged around the outer wall of the inner pressure vessel 2, specifically, the spiral steam generator 11 is arranged at the top of the inner pressure vessel 2 and is positioned below the coolant channel S06, namely the spiral steam generator 11 surrounds the bottleneck of the inner pressure vessel 2, and the spiral steam generator 11 is positioned at 1/6-5/6 of the bottleneck height of the inner pressure vessel 2; the spiral steam generator all adopts the outer pressure vessel window straight tube to supply water, does not have the water supply ring, does not have steam output ring yet, and spiral steam generator mainly supports on inner pressure vessel surface through the bolt, is located the lateral part cavity of inner pressure vessel and outer pressure vessel, and when wet-type motor main pump 17, the coolant of inner pressure vessel is driven by wet-type motor main pump 17 and flows to outer pressure vessel in to heat into saturated steam, superheated steam through the cooling water in spiral pipe of spiral steam generator by spiral steam generator.
In the design, a cooling water inlet 16 communicated with a cooling water inlet of the spiral steam generator is further formed in the side wall 18 of the outer pressure container, the cooling water inlets of the spiral steam generator 11 are located at the bottom of the spiral steam generator, the four cooling water inlets 16 are symmetrically distributed on the side wall of the side wall 18 of the outer pressure container, and the cooling water inlets 16 provide a second loop cooling water loop for the spiral steam generator. While the output steam pipes 14 of the screw steam generator are located at the top of the screw steam generator and extend to the outside from the sealing cover 13 at the top of the outer pressure vessel 18.
Furthermore, the manufacturing process of the inner pressure vessel 2 and the outer pressure vessel 18 in the design is the same, the inner pressure vessel and the outer pressure vessel are integrally and precisely manufactured, the inner pressure vessel 2 is a complete whole except for the coolant channel S06 at the upper opening, the top part and the bottom part, no other welding joint or bolt sealing joint exists, the inner pressure vessel can bear the physical gas phase temperature of 1000-1300 ℃, and the lead, silver, beryllium, tungsten, beryllium and stainless steel composite coating is prepared on the wall surface of the inner pressure vessel by adopting a gas phase precipitation method, so that the heat conductivity, the expansion rate, the low irradiation performance and the corrosion resistance of the pressure vessel are improved, and the structural strength of the inner pressure vessel can be greatly improved by the design.
Furthermore, the potential capacity of the internal pressure container 2 is to absorb noise and pressure waves generated by heating the coolant of the reactor core of the integrated nuclear reactor, and simultaneously absorb a large amount of energy deposited by neutrons, ions and the like, besides the coolant channels on the top side wall and the bottom wall of the internal pressure container, the bottle-shaped upper necking is the only opening of the internal pressure container, so that the structural performance and the safety of the nuclear reactor are greatly enhanced, the volume of the internal pressure container is very compact, and the area of the integrated nuclear reactor needing coating technology treatment is greatly reduced.
Furthermore, a magnetic rod lifting mechanism 8 of a control rod is fixed on the upper grid plate 7, so that a fixed support is provided for the magnetic rod lifting mechanism 8, and meanwhile, the vibration noise and the transverse torsion of the magnetic rod lifting mechanism 8 are reduced.
Further, a top sealing chamber 22 and a side chamber 23 are formed between the outer wall of the inner pressure vessel 2 and the outer pressure vessel 18; the top seal chamber mainly provides secondary seal protection for the double-pressure-vessel nuclear reactor, and simultaneously also provides pressure stabilization and overpressure protection for the nuclear reactor, once the pressure of the pressure vessel 2 in the top seal chamber is too high, the pressure of the pressure vessel is far greater than that of the top seal chamber, the knife edge flange and the elastic metal pipe S01 can actively deform towards the outer side, the pressure of the nuclear reactor core is released, the pressure in the top chamber can rise, after being filtered by the radioactive filter screen, the emptying valve of the pressure stabilizer is triggered, the pressure of the top chamber is released, meanwhile, the water supply quantity of the spiral steam generator can be automatically increased, a safety injection system can actively add cooling water, and the temperature nuclear pressure of the nuclear reactor core is promoted to return to the normal design working condition range.
The installation steps of the double-pressure vessel type integrated nuclear reactor structure during installation are as follows:
1. mounting internal pressure vessel
The end cover 1 (also called a hanging scaffold) of the internal pressure container cylinder is temporarily fixed, the internal pressure container cylinder is installed after the hanging scaffold is installed and fixed, the connecting part of the hanging scaffold and the internal pressure container cylinder is fixed by bolts, and further, internal components of the internal pressure container are installed.
2. Mounting internal pressure vessel internal assembly
The components in the internal pressure container mainly comprise the following parts: the method comprises the following steps of installing a coolant distributor 4, a lower grid plate, a nuclear fuel rod assembly 5, control rods 6 and the like:
(1) the coolant distributor 4 and its fittings are first installed by hanging it into the internal pressure vessel, opening from the top of the internal pressure vessel.
(2) Installing a grid plate: the circumferential angle occupied by each grid plate is 30 degrees, the grid plates are assembled on site in the inner pressure container, 12 grid plates are assembled into a lower grid plate with 360 degrees of circumference, the difficulty that the grid plates are difficult to integrally assemble into the inner pressure container from the outside is avoided, and the whole grid plate does not have a welding joint.
(3) The nuclear fuel rod assembly 5 is installed after the lower grid plate is installed, and mainly comprises a nuclear fuel rod and a control rod 6, the fuel rod is connected with the lower grid plate at the lower part of the reactor core, and the control rod is positioned right above the reactor core when not inserted into the reactor core and is connected with a control rod driving mechanism (a magnetic rod lifting mechanism 8, the prior art).
(4) Installation of control rod drive mechanism (magnetic rod lifting mechanism): the crdm consists essentially of a crdm support (otherwise named: upper grid plate) and a crdm gripper disk (prior art). When the control rod driving mechanism is installed, the control rod grabbing disc is connected with the top of the control rod, and the magnetic rod lifting mechanism is suspended and the power supply cable provides damping and power supply for the control rod driving mechanism.
(5) After the installation is finished, the end cover 1 on the internal pressure container is installed, the wet motor main pump is fixedly hoisted on the bottom surface of the end cover, when the end cover is hoisted in the vertical direction, the wet motor main pump is also vertically hoisted into the internal pressure container together, the end cover is in bolt connection with the internal pressure container, and the knife edge flange and the elastic metal pipe are sealed in a double-layer mode.
3. Installing a spiral steam generator:
the spiral steam generator 11 is fixed on the outer surface of the internal pressure container, has no welding structure, completely adopts the straight pipe section of the window of the external pressure container to supply water, and has no water supply ring and no steam output ring.
4. Installing an outer pressure vessel:
integrally hoisting the installed inner pressure container and the internal parts thereof and the spiral steam generator 11 into an outer pressure container, installing an o-shaped elastic sealing pipe S01 with the circumference ratio of 4/5 at the upper flange opening of the outer pressure container, and then installing a steam output pipe; finally, the sealing cover of the outer pressure vessel is closed, and double sealing is carried out by using expansion bolts and an o-shaped elastic sealing pipe S01 with the circumference ratio of 4/5, so that a closed space is provided for toxic gas collection, and S04 in the figure 1 is a connecting expansion bolt hole between the inner pressure vessel and the upper sealing cover 21.
5. Finally, a nuclear reactor instrumentation & monitoring system 15 may be installed at the bottom and sides of the outer pressure vessel.
The working principle of the double-pressure vessel type integrated nuclear reactor structure is as follows:
the reactor core cooling heat exchange adopts a mode of taking forced circulation as main natural circulation as auxiliary natural circulation, and specifically comprises the following steps:
when the main pump of the wet motor main pump 17 works normally, the primary side liquid (core coolant) is driven to lift upwards in the inner pressure vessel 2, the primary side liquid flows into the upper chamber of the inner pressure vessel 2, after entering the upper chamber, the core coolant is driven by the main pump of the wet motor main pump 17, enters the outer pressure vessel 18 through the coolant channel S06 on the side wall of the top of the inner pressure vessel 2, then flows downwards along the outer sides of the heat exchange tubes in the spiral steam generator in the side chambers of the inner pressure vessel 2 and the outer pressure vessel 18, and in the process of flowing along the tube walls of the heat exchange tubes, the primary side liquid heats the heat exchange tubes 11, and the temperature of the primary side liquid (core coolant) is gradually reduced.
The primary liquid having a lowered temperature descends along the passage between the outer wall of the inner pressure vessel 2 and the inner wall of the outer pressure vessel 18 and then flows into the nuclear fuel rod assembly 5 through the coolant flow-through hole in the bottom of the inner pressure vessel 2. After the primary side liquid returns to the nuclear fuel rod assembly 5, the primary side liquid is heated by nuclear fission heat of the nuclear fuel rod assembly 5, flows from bottom to top in the inner pressure vessel 2, is continuously heated by the nuclear fuel rod assembly 5 at the same time, flows out of the nuclear fuel rod assembly 5, enters a main pump of a wet motor main pump 17, and completes the heating-cooling cycle process of the primary side liquid.
Under the accident condition (the main pump of wet motor main pump 17 is in under the non-operating condition), adopt natural circulation, specifically as follows: because the nuclear fuel rod assembly 5 is lower than the spiral steam generator 11, the nuclear fuel rod assembly and the spiral steam generator 11 generate a height difference, after the primary side liquid is heated in the nuclear fuel rod assembly 5, the density of the primary side liquid is reduced, the pressure is increased, under the combined action of the density difference and the pressure difference, the primary side liquid is lifted upwards against the action of gravity, the primary side liquid enters the upper chamber of the internal pressure vessel 2 under the action of natural density lifting force, enters the external pressure vessel 18 through the coolant channel on the side wall at the top of the internal pressure vessel 2, flows downwards along the primary side of the spiral steam generator 11 in the side chambers of the internal pressure vessel 2 and the external pressure vessel 18, in the flowing process along the tube wall of the spiral steam generator 11, the primary side liquid heats the water in the spiral steam generator 11, the temperature of the primary side liquid is gradually reduced, the density is increased, and the primary side liquid flows downwards along the outer wall of the internal pressure vessel 2 and the inner wall of the external pressure vessel 18 under the action of the gravity and the density difference .
Under normal working conditions and accident working conditions of a main pump of a wet motor main pump 17, secondary side liquid (water in the spiral steam generator) flows in from a cooling water inlet 16, is heated in the spiral steam generator 11 and then becomes superheated steam, flows out from a steam output pipe 14, and then pushes a steam turbine to generate electricity.
In the above process, the active shutdown and power regulation of the reactor are mainly realized by the control rod 6, the magnetic rod lifting mechanism 8 and the magnetic power supply system 10, and the nuclear fission reaction is completed by controlling the up-and-down movement of the electromagnetic rod lifting system to drive the control rod to be inserted into or lifted out of the reactor core assembly (the above process is the prior art, and this embodiment is not described in detail again).
Compared with the prior art, the double-pressure vessel type integrated nuclear reactor structure has the following advantages:
(1) in the molten state of the core of the nuclear reactor, the first loop coolant circulation (core coolant) of the first nuclear pressure safety barrier (inner pressure vessel) cannot penetrate through the core of the nuclear reactor to take away the nuclear fission heat, and at the moment, the cavity between the second nuclear pressure barrier (outer pressure vessel) and the inner pressure vessel can continuously carry out internal cooling circulation, so that the inner pressure vessel is naturally cooled and the nuclear fission heat in the molten state of the core is taken away, and the inherent safety of the nuclear reactor is improved.
(2) The inner and outer pressure vessels greatly reduce the number of openings on the pressure vessel (compared with a single pressure vessel type integrated nuclear reactor), and an additional nuclear reactor space is added, thereby providing a research platform for nuclear materials, nuclear medicine and nuclear agriculture.
(3) The shape of the inner pressure vessel is similar to that of a necking bottle, and the inner pressure vessel and the outer pressure vessel are integrally and precisely manufactured, except for the upper opening, the coolant hole channels at the bottom of the inner pressure vessel and the side wall of the top cavity, the inner pressure vessel is a complete whole without other welding joints and bolt sealing joints, and the structural strength of the inner pressure vessel is greatly improved.
(4) The lower end enclosure part of the pressure vessel is simplified and eliminated, and the pressure vessel of the nuclear reactor is manufactured and installed by adopting an integrated machine, so that the structural reliability of the pressure vessel of the nuclear reactor is greatly improved.
(5) The double-pressure-vessel type integrated nuclear reactor can be processed into formed parts by 100% disassembly in the process of hoisting and operating reloading of a reactor core, a welding structure of the whole nuclear reactor is completely eliminated, all the nuclear reactor adopts the linking modes of detachable bolts, sealing knife edges and the like, and the basic spirit and thought of modular design and maintenance of the nuclear reactor are increased.
The embodiments of the present invention are disclosed as the preferred embodiments, but not limited thereto, and those skilled in the art can easily understand the spirit of the present invention and make various extensions and changes without departing from the spirit of the present invention.
Claims (3)
1. A double-pressure container type integrated nuclear reactor structure comprises a nuclear reactor core fuel bundle, control rods, an upper grid plate and a lower grid plate, wherein the lower grid plate provides support and fixation for the nuclear reactor core fuel bundle, and a control rod magnetic rod lifting mechanism is fixed on the upper grid plate; the method is characterized in that: the double-pressure-vessel type nuclear reactor comprises an inner pressure vessel and an outer pressure vessel, wherein the inner pressure vessel is positioned in the outer pressure vessel, the inner pressure vessel and the outer pressure vessel are coaxial, a unified top seal is arranged between the inner pressure vessel and the outer pressure vessel, a top seal chamber and a side chamber are formed between the outer wall of the inner pressure vessel and the outer pressure vessel, the top seal chamber mainly provides secondary seal protection for the double-pressure-vessel type nuclear reactor, and meanwhile, pressure stabilization, overpressure protection, nuclear leakage detection and poison collection are provided for the nuclear reactor; a gap is formed between the outer wall of the inner pressure vessel and the outer pressure vessel;
the upper grid plate, the nuclear fuel bundle and control rods of the nuclear reactor core and the lower grid plate are arranged in the inner pressure container from top to bottom, the bottom of the inner pressure container is provided with a coolant distributor, the side walls of the bottom and the top of the inner pressure container are provided with coolant channels, the inner cavity of the inner pressure container is communicated with the inner cavity of the outer pressure container through the coolant channels, and the coolant of the reactor core enters between the inner pressure container and the outer pressure container through the coolant channels;
a spiral steam generator is arranged in a gap between the inner pressure vessel and the outer pressure vessel, and the spiral steam generator is directly spirally wound on the outer wall of the inner pressure vessel in an assembly site and is positioned in the outer pressure vessel; the spiral steam generator is arranged at the top of the inner pressure vessel and below the coolant channel, and is positioned outside the inner pressure vessel; the internal pressure container is in a necking bottle shape, and the spiral steam generator heat exchange tube is directly spirally wound on the bottleneck of the internal pressure container in an assembly site; a wet motor is arranged at the top in the internal pressure container and is positioned at the coolant channel; a cooling water inlet communicated with a cooling water inlet of the spiral steam generator is formed in the side wall of the outer pressure vessel;
under the normal operation state of a main pump of a wet motor main pump, reactor core coolant is lifted upwards in an inner pressure vessel, the reactor core coolant flows into an upper cavity of the inner pressure vessel and is driven by the main pump of the wet motor main pump to enter an outer pressure vessel through a coolant channel on the wall surface of the upper cavity of the inner pressure vessel, and flows downwards along the outer side of a heat exchange tube in a spiral steam generator positioned in a gap between the inner pressure vessel and the outer pressure vessel, the heat exchange tube is heated by the reactor core coolant, and the temperature of the reactor core coolant is gradually reduced; the reactor core coolant with the reduced temperature descends along a channel between the outer wall of the inner pressure vessel and the inner wall of the outer pressure vessel, then flows into the nuclear fuel rod assembly through a coolant flow through hole at the bottom of the inner pressure vessel, is heated by nuclear fission heat of the nuclear fuel rod assembly again after returning to the nuclear fuel rod assembly, flows from bottom to top in the inner pressure vessel until flowing out of the nuclear fuel rod assembly, and enters the main pump of the wet motor main pump again;
under the unable operating condition of main pump of wet-type motor main pump, the reactor core coolant is after nuclear fuel rod subassembly heating, the reactor core coolant gets into the upper cavity of internal pressure container under the effect of natural density lift, get into outer pressure vessel through the coolant passageway on the upper cavity wall surface of internal pressure container, flow downwards along the spiral steam generator outside that is located in the clearance of internal pressure container and outer pressure vessel, at the in-process that flows along the spiral steam generator pipe wall, the reactor core coolant heats the water in the spiral steam generator, the reactor core coolant temperature reduces gradually, the density increases, the reactor core coolant is along the downward flow of internal pressure container outer wall and outer pressure vessel inner wall under the effect of gravity and density difference.
2. The dual pressure vessel integral nuclear reactor structure of claim 1, wherein: and a cooling water inlet of the spiral steam generator is positioned at the bottom of the spiral steam generator, and a steam output pipe on the spiral steam generator is positioned at the top of the spiral steam generator and extends out of the top of the outer pressure vessel.
3. The dual pressure vessel integral nuclear reactor structure of claim 1, wherein: the top of the outer pressure vessel is provided with a sealing cover for sealing the top opening of the outer pressure vessel, the sealing cover is connected with the top of the outer pressure vessel through a bolt, and an o-shaped elastic sealing pipe is arranged between the sealing cover and the top of the outer pressure vessel.
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| US3322642A (en) * | 1964-06-29 | 1967-05-30 | Atomic Energy Authority Uk | Integrated nuclear reactor-steam generator |
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| KR20150022537A (en) * | 2013-08-23 | 2015-03-04 | 한국원자력연구원 | Reactor internal control rod drive mechanism and nuclear reactor with the same |
| CN207250153U (en) * | 2017-07-31 | 2018-04-17 | 清华大学天津高端装备研究院 | integrated nuclear reactor |
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| US3322642A (en) * | 1964-06-29 | 1967-05-30 | Atomic Energy Authority Uk | Integrated nuclear reactor-steam generator |
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