CN112366008A - Nuclear reactor for mobile plant power plant - Google Patents
Nuclear reactor for mobile plant power plant Download PDFInfo
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- CN112366008A CN112366008A CN202010653248.3A CN202010653248A CN112366008A CN 112366008 A CN112366008 A CN 112366008A CN 202010653248 A CN202010653248 A CN 202010653248A CN 112366008 A CN112366008 A CN 112366008A
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- propellant
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- 239000000446 fuel Substances 0.000 claims abstract description 92
- 239000003380 propellant Substances 0.000 claims abstract description 27
- 239000007789 gas Substances 0.000 claims abstract description 17
- 239000001307 helium Substances 0.000 claims abstract description 17
- 229910052734 helium Inorganic materials 0.000 claims abstract description 17
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims abstract description 17
- 238000005507 spraying Methods 0.000 claims abstract description 6
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 claims description 31
- 229910052751 metal Inorganic materials 0.000 claims description 27
- 239000002184 metal Substances 0.000 claims description 27
- 239000011159 matrix material Substances 0.000 claims description 22
- 239000000919 ceramic Substances 0.000 claims description 8
- OYPRJOBELJOOCE-UHFFFAOYSA-N Calcium Chemical compound [Ca] OYPRJOBELJOOCE-UHFFFAOYSA-N 0.000 claims description 7
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 claims description 7
- 229910052791 calcium Inorganic materials 0.000 claims description 7
- 239000011575 calcium Substances 0.000 claims description 7
- 229910000952 Be alloy Inorganic materials 0.000 claims description 4
- 230000000149 penetrating effect Effects 0.000 claims description 4
- 239000008188 pellet Substances 0.000 claims description 2
- 238000009826 distribution Methods 0.000 abstract description 3
- 239000010410 layer Substances 0.000 description 53
- 239000000463 material Substances 0.000 description 16
- 239000002245 particle Substances 0.000 description 14
- 229910052790 beryllium Inorganic materials 0.000 description 13
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 10
- 239000011258 core-shell material Substances 0.000 description 9
- 239000010439 graphite Substances 0.000 description 9
- 229910002804 graphite Inorganic materials 0.000 description 9
- 239000002296 pyrolytic carbon Substances 0.000 description 8
- 239000011449 brick Substances 0.000 description 6
- 239000002826 coolant Substances 0.000 description 6
- 239000003758 nuclear fuel Substances 0.000 description 6
- 239000011148 porous material Substances 0.000 description 6
- 239000011248 coating agent Substances 0.000 description 5
- 238000000576 coating method Methods 0.000 description 5
- 239000012798 spherical particle Substances 0.000 description 5
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 4
- 230000008901 benefit Effects 0.000 description 4
- 238000013461 design Methods 0.000 description 4
- 238000005516 engineering process Methods 0.000 description 4
- 230000004992 fission Effects 0.000 description 4
- 239000001257 hydrogen Substances 0.000 description 4
- 229910052739 hydrogen Inorganic materials 0.000 description 4
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 description 4
- 238000012546 transfer Methods 0.000 description 4
- 238000001816 cooling Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000005242 forging Methods 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 238000011160 research Methods 0.000 description 3
- 229910010271 silicon carbide Inorganic materials 0.000 description 3
- 229910052770 Uranium Inorganic materials 0.000 description 2
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 239000011247 coating layer Substances 0.000 description 2
- 239000000306 component Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 230000007246 mechanism Effects 0.000 description 2
- 239000004005 microsphere Substances 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 230000001141 propulsive effect Effects 0.000 description 2
- 230000009257 reactivity Effects 0.000 description 2
- 238000007789 sealing Methods 0.000 description 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 238000004804 winding Methods 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 1
- 241000013033 Triso Species 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
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- 239000011195 cermet Substances 0.000 description 1
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- 239000008358 core component Substances 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
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Images
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/044—Fuel elements with porous or capillary structure
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
- G21C3/623—Oxide fuels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/28—Control of nuclear reaction by displacement of the reflector or parts thereof
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention discloses a nuclear reactor for mobile device power equipment, which comprises an upper supporting plate, a lower supporting plate, a control rod assembly, a fuel assembly, a reflecting layer, a pressure container, a propellant supply pipeline, a propellant spraying pipeline, a plurality of cold air chambers, a plurality of hot air chambers and a plurality of cold helium gas channels, wherein the upper supporting plate is connected with the lower supporting plate through the control rod assembly; the axial direction of the center of the fuel element of the invention is from small to large to form a conical channel, so that the power distribution in all places in the nuclear reactor is kept uniform and constant.
Description
Technical Field
The invention belongs to the technical field of mobile devices, and particularly relates to a nuclear reactor for mobile device power equipment.
Background
The nuclear power moving device is equipment driven by nuclear power and capable of solving continuous and rapid moving. With the development of mobile devices in recent years, nuclear-powered mobile devices have come back into the field of view of many political, national defense and military families, researchers around the world. The countries having the nuclear power plant technology include the united states, russia, and england, and at present, france and japan are actively seeking the nuclear power plant technology and have conducted some research.
Currently, China is blank in the field of nuclear power mobile devices, is still in a starting stage of research, and is in an exploratory research stage for different heap types. The nuclear reactor is a source for energy generation of power equipment of the nuclear power mobile device, is a system which determines the most core of the field of the nuclear power mobile device, and can realize the field of the nuclear power mobile device meeting the requirements only if the reactor meeting the strategic requirements and reliable in performance is designed.
Disclosure of Invention
In view of the above, the invention provides a nuclear reactor for mobile plant power equipment, which can fill the blank in the field of mobile plant power equipment in China and solve the problem of mobile plant power.
The technical scheme for realizing the invention is as follows:
a nuclear reactor for a mobile plant power plant comprising an upper support plate, a lower support plate, a control rod assembly, a fuel assembly, a reflective layer, a pressure vessel, a propellant supply conduit, a propellant ejection conduit, a plurality of cold gas chambers, a plurality of hot gas chambers, and a plurality of cold helium gas ports;
the middle part in the pressure container cavity is fixedly connected with a fuel assembly, an upper supporting plate is horizontally arranged above the fuel assembly and fixedly connected with the pressure container, a lower supporting plate is horizontally arranged below the fuel assembly and fixedly connected with the pressure container, a propellant supply pipeline is led in from an opening at the top of the pressure container and is communicated with the top end of the fuel assembly after penetrating through the upper supporting plate, a propellant spraying pipeline is communicated with the bottom end of the fuel assembly and is led out from an opening at the bottom of the pressure container after penetrating through the lower supporting plate, a control rod assembly is vertically fixed on the side wall of the fuel assembly, a plurality of cold helium gas channels are vertically distributed between the wall of the pressure container and the fuel assembly, the upper end of each cold helium gas channel is communicated with a; the plurality of hot air chambers are arranged between the fuel assembly and the lower support plate, and a reflecting layer is filled in a cavity between the pressure container and the fuel assembly;
the fuel assembly is composed of a fuel element and a support element, a fuel area of the fuel element is a horn-shaped winding drum formed by sleeving 60 layers of metal ceramic thin plates together, and sequentially comprises a calcium metal matrix thin plate area, a molybdenum metal matrix thin plate area and a beryllium metal matrix thin plate area from inside to outside, and UO is uniformly coated among the metal ceramic thin plate layers in a dispersing way2Pellets of spherical fuel, UO2The outside of the ball is sequentially coated with a loose pyrolytic carbon layer, an inner compact pyrolytic carbon layer, a silicon carbide layer and an outer compact pyrolytic carbon layer.
Further, beryllium alloy pieces were pinned to form the reflective layer.
Further, the propellant supply pipe and the propellant ejection pipe are machined from beryllium alloy.
Has the advantages that:
1. the axial direction of the center of the fuel element of the invention is from small to large to form a conical channel, so that the power distribution in all places in the nuclear reactor is kept uniform and constant.
2. The beryllium metal block is used as a reflecting layer, so that the beryllium metal block has the advantages of low density, light weight, best heat conducting capacity per unit mass and highest specific ejection modulus in metal besides meeting the conditions of high strength, good toughness, good thermal stability and good corrosion resistance;
the beryllium blocks are connected in a pin key mode to form a whole, the structure is stable, and the effect of a common reflecting layer is met.
3. The fuel element of the invention adopts UO2As nuclear fuel, UO2The fuel has the advantages of mature processing and manufacturing technology, comprehensive performance data and the like, and is UO2Is spherical particles, effectively promotes the full contact with the propellant (liquid hydrogen/air), and improves the cooling effect. UO2The spherical particles are coated with three layers of pyrolytic carbon and one layer of silicon carbide to form ceramic fuel particles, the coating layer well restrains fission products and fuel in the fuel coating particles, and the heat exchange area is also improved.
4. The fuel assembly of the invention adopts high-concentration uranium fuel and high-temperature resistant materials, so that the power density of the reactor core and the temperature of the coolant at the outlet are improved, and the thrust-weight ratio of the reactor engine is improved.
Drawings
Fig. 1 is a view of a metal sheet according to an embodiment of the present invention.
Fig. 2 is a diagram of a fuel cell of a reactor according to an embodiment of the present invention.
Fig. 3 is a schematic diagram of a reactor structure according to an embodiment of the present invention.
The device comprises a groove 1, a working medium exhaust channel 2, a metal plate winding drum 3, a cold sleeve 4, a moderator 5, a beryllium pressure pipe 6, an upper supporting plate 7, a cold air chamber 8, a propellant supply pipeline 9, a fuel assembly 10, a pressure container 11, a control rod assembly 12, a cold helium channel 13, a reflecting layer 14, a hot air chamber 15, a propellant spraying pipeline 16 and a lower supporting plate 17.
Detailed Description
The invention is described in detail below by way of example with reference to the accompanying drawings.
The present invention provides a nuclear reactor for a mobile plant power plant, as shown in fig. 3, comprising an upper support plate 7, a lower support plate 17, a control rod assembly 12, a fuel assembly 10, a reflective layer 14, a pressure vessel 11, a propellant supply conduit 9, a propellant ejection conduit 16, a plurality of cold air chambers 8, a plurality of hot air chambers 15, and a plurality of cold helium gas ports 13;
the fuel region of pebble bed reactor fuel elements is a trumpet roll formed by nesting 60 layers of cermet sheet metal together. Ceramic fuel particles of a pebble bed reactor are dispersed on a metal matrix sheet by7LiH is used as a moderator, has small density and good moderating capability, can resist high temperature of about 1000K, and reduces the volume and the mass of a fuel assembly.
The coated fuel particles adopt a TRISO type structure, and the center is UO with a diameter of 0.35mm2Spherical particles, wherein the outer layer of the spherical particles is coated with a loose pyrolytic carbon layer, an inner compact pyrolytic carbon layer, a silicon carbide (SiC) layer and an outer compact pyrolytic carbon layer, the diameter of the coated particles is 0.89mm, the coated particles are uniformly dispersed on a metal ceramic thin plate (the thickness is about 0.32mm), and the enrichment degree of U-235 in a fuel element is 87% and the fuel particle coating layer is a microspheric pressure vessel, and the structure of the metal sheet is shown in figure 1.
The fuel element has an inner and outer diameter (mm) of 28.2/12 and a shell thickness of 5 mm.
The fuel area of the fuel element has three areas, namely three metal sheets, which have propellant working medium circulation pores with proper porosity (the porosity is determined according to the heat exchange requirement of the area) to coat UO2The fuel particles of the particles are uniformly dispersed among the layers of the metal sheets, and the three metal sheets are a calcium metal matrix sheet, a molybdenum metal matrix sheet and a beryllium metal matrix sheet from inside to outside in sequence. The calcium metal matrix sheet is a high temperature sintered sheet in a high temperature region, about 20 layers; the molybdenum metal matrix thin plate is a sintered plate in a higher temperature area, and is nearly 40 layers; the remainder is the beryllium metal base sheet located in the outer low temperature region. The fuel elements are centrally and axially tapered from smaller to larger to form a conical channel, each fuel element circumscribing a respective outlet nozzle. The housing of the fuel element is a beryllium pressure tube made of graphite base material and beryllium metal base material, wherein the coating particles are not arranged in the beryllium pressure tube, and a moderator is arranged between the housing and the fuel element. Three metal matrix materials of a calcium metal matrix material, a molybdenum metal matrix material and a beryllium metal matrix material and a graphite matrix are used as structural materials of the fuel element, so that the fuel is endowed with a certain geometric shape and a heat transfer environment; the shell of the fuel element is made of graphite base materials and beryllium metal base materials, a certain heat transfer environment and a certain geometric shape are provided for the fuel, and graphite is also a moderator for neutrons.
As shown in fig. 2, the fuel elements and the strut elements form a fuel assembly of a cylindrical structure. Reactor core outer diameter/reflector outer diameter (mm) 297/380. The pebble bed reactor core is composed of 56 hexagonal fuel elements, proper number of control rods outside, and reflecting layers (including a top reflecting layer, a side reflecting layer and a bottom reflecting layer according to the position relation with the fuel assembly area), wherein the periphery of the reflecting layer is a thermal insulation layer composed of carbon structures. The pillar member has the same outer dimension as the fuel member, and is also hexagonal and is keyed to the fuel member by a pin.
The reflective layer (beryllium metal base material) was free of coating particles and contained only moderator. The beryllium reflecting layer is mainly used as a neutron reflecting layer in the fuel assembly area, the side reflecting layer is of a straight cylinder structure, each layer is composed of fan-shaped beryllium bricks, and the layers are not layered any more in the radial direction. The whole beryllium reflecting layer structure is composed of a plurality of layers of beryllium metal blocks in the height direction, the beryllium metal blocks are connected through pin keys to play a role in positioning, and the beryllium metal blocks form an integral structure, and a sleeve ring with the height of 60mm is designed at the hole channel interface of the upper beryllium brick layer and the lower beryllium brick layer so as to reduce the bypass flow loss of the core coolant. Only a fit mounting gap is left between the reactor fuel assembly shell and the reflector layer to limit the total amount of circumferential gap.
The control rod assembly is arranged in a side reflecting layer pore path, a control rod assembly pore path is formed in the reflecting layer close to the side of the reactor core, and the control rod pore path respectively passes through structures and components such as a bottom reflecting layer, a side reflecting layer, a top reflecting layer and an upper supporting plate from bottom to top along the axial direction. The control rod pore canal of the top reflecting layer is provided with a horizontal lateral small hole which is connected with a cold helium gas chamber for allowing cold helium to enter the control rod pore canal and cooling the control rod. The number of control rods is determined from reactor neutrophical analysis. The control rod has the same structure size and material composition, belongs to safety-level non-bearing mechanical equipment, and has two main characteristics of control rod structure design, namely a multi-section hanging and telescoping structure. The so-called "telescoping structure", namely the control rod includes outer stick and inner stick, the main purpose is that when inserting the control rod, the control rod expansion length covers the whole core active area, improve the reactivity value of the control rod to the maximum extent; when the control rods are lifted out of the active area of the reactor core, the inner rods and the outer rods are completely overlapped, so that the length of the control rods is reduced, and the height of the reactor pressure vessel is reduced. The control rod limit adopts a screw-nut structure, and the full stroke of the control rod is reduced through a gear reduction mechanism so as to reduce the stroke distance of the nut.
The beryllium metal base material and the graphite base material form a propellant supply pipeline and a spraying pipeline. Propellant flows down through the upper portion into the core through the supply pipe and out of the core through the lower outlet pipe.
The outer layer of the fuel element area is a reactor core shell (beryllium metal base material), and the reactor core shell and the pressure vessel are in contact with cold helium gas in a reactor pressure vessel so as to ensure that a metal structure does not bear high temperature. The core shell mainly functions to support the internal fuel assembly structure and transmit the externally generated load to the barrel body of the pressure vessel through structures such as tenons, supporting rollers, various limit keys and the like, so that the stability of the core structure is maintained.
The fuel assembly shell is a thin-walled welded right cylinder structure. The lower end of the cylinder body is provided with a cylinder body bottom structure. In order to increase the rigidity of the reactor core shell, an upper flange is arranged at the upper end of the cylinder body, and a lower thickened section is arranged at the lower part of the cylinder body. The lower part of the reactor core shell body is provided with a hot gas guide pipe opening flange. The bottom plate of the cylinder is thick, and radial rib plates, an inner cylinder and an outer cylinder are welded at the lower part of the bottom plate to increase the bottom support rigidity. The whole reactor core container is supported on a support table at the lower part of a reactor pressure container barrel body through support roller assemblies which are uniformly distributed on the circumference, each group of support roller assemblies comprises two rollers, the support rollers are placed between an upper cover plate and a lower cover plate, and an adjusting base plate is arranged at the position of the cover plates to adjust the levelness of the bottom during installation. The upper flange is provided with four guide keys, and the lower thickened section is provided with four positioning bosses. And a regulating sheet is additionally arranged between the key and the key groove, so that the accurate positioning of the core shell assembly is ensured. The connection between the core shell and the upper supporting plate is ensured by screws. And the accurate positioning of dismouting again is guaranteed to the pin.
The reactor uses helium as a coolant. After being sent into a reactor pressure vessel, the cold helium enters the top of the reactor core from bottom to top through a coolant orifice in the metallic beryllium block of the side reflecting layer and then flows through the fuel assembly area of the reactor from top to bottom. The graphite reactor internals form a flow channel for the heat carrier helium.
The lower supporting plate is a device for directly supporting the internals. The lowermost beryllium brick is seated on the lower support plate. The lower support plate is provided with a propellant spraying pipeline. The lower support plate is composed of two kinds of sector plates, the lower support plate is divided into an inner ring and an outer ring, the outer ring is composed of sector plates, and each sector plate is supported by a supporting roller.
In order to position the beryllium brick on the lower supporting plate, the lower supporting plate is provided with a tenon for positioning the beryllium brick. At the same time, there are pipe connectors and connecting pipes on the lower bearing plate in order to connect the cold helium gas channel upwards. Three rings of supporting rollers are arranged below the lower supporting plate. The edge of the lower supporting plate is provided with evenly distributed key slots so as to be matched with the guide keys of the lower thickened section of the reactor core shell.
The upper bearing plate supports the control rod bore and the propellant supply conduit. Meanwhile, the upper supporting plate is also an upper cover of the reactor core shell and plays a role in distributing helium gas flow. The upper and lower bearing plates are made of low alloy forgings and are connected with the upper flange section of the core stack shell by bolts and pins at the joint of the upper flange section of the core stack shell.
The reactor pressure vessel is a cylindrical shell with the diameter of 450mm and the total height of 500mm, the top cover and the lower cylinder of the reactor pressure vessel adopt a bolt-flange connection structure, and a metal sealing ring is adopted for sealing. The top cover of the pressure vessel is provided with a connecting pipe structure of a control rod driving mechanism. The cylinder body of the reactor pressure vessel is formed by assembling and welding a cylinder body flange, a cylindrical cylinder body and a lower end enclosure. The upper section of the cylinder of the reactor pressure vessel is thinner and is formed by welding steel plates, the flange of the cylinder and the lower section of the cylinder are thicker and need to be forged by an integral forging piece, and the lower end enclosure is formed by hot stamping of the integral forging plate. The reactor pressure vessel is the benchmark for the installation and positioning of the various components in the reactor.
The pebble bed reactor body design has a reactor top cover and an outer pressure vessel besides a key core. The outer layer of the reactor is provided with a hydrogen fuel/air supply pipeline, a thrust chamber frame, a propulsion vector controller, a connecting section of a pressure container and a contraction section, a spray pipe and other structures as part of the power equipment of the mobile device.
Pebble bed reactor design size
(the size of the backpack is unit millimeter), the structure is simplified, the volume is greatly reduced, the occupied space is the size of the backpack, the design weight of the body is 100kg,effectively reduced emission quality, spherical bed reactor core adopts high enriched uranium fuel and high temperature resistant material simultaneously, makes reactor core power density and the coolant temperature of export improve, and the thrust-weight ratio of engine promotes. The large thrust-to-weight ratio allows the mobile device to be lifted at a very high speed in a very short time. By using7LiH is used as a moderator, has small density and good moderating capability, can resist high temperature of about 1000K, and reduces the volume and the mass of a reactor core.
The pebble bed reactor fuel element adopts UO2As nuclear fuel, UO2The fuel has the advantages of mature processing and manufacturing technology, comprehensive performance data and the like. UO2The diameter of the spherical particles is 0.35mm, so that the full contact with a propellant (liquid hydrogen/air) is effectively promoted, and the cooling effect is improved. The fuel particle coating is a microspheric pressure vessel, the fission product and the fuel are well restricted in the fuel particle coating, which is the most main barrier for blocking the release of the fission product, the heat exchange area is increased, and the power density of the fuel is increased. The center of the pebble bed reactor fuel element forms a conical passage from small to large in the axial direction, so that the power distribution in all parts of the nuclear reactor is kept uniform and constant.
Three metal matrix materials of a calcium metal matrix material, a molybdenum metal matrix material and a beryllium metal matrix material and a graphite matrix are used as structural materials of the fuel element, so that the fuel is endowed with a certain geometric shape and a heat transfer environment; the shell of the fuel element is made of graphite base materials and beryllium metal base materials, a certain heat transfer environment and a certain geometric shape are provided for the fuel, and graphite is also a moderator for neutrons.
Propellant (liquid hydrogen/air) enters a fuel assembly area (56 fuel elements) of the reactor from a reactor supply pipeline, passes through a beryllium metal base thin plate area, a molybdenum metal base thin plate area and a calcium metal base thin plate area in sequence in each fuel element, is heated to 3200K from 30K, and is sprayed out from a fuel element center expansion type channel. Each fuel element is externally connected with a respective outlet nozzle to form thrust independently, the thrust of 56 fuel elements is bundled together to form total propulsive power, and finally high-temperature and high-pressure propellant is ejected from the nozzle of the pebble bed reactor engine at high speed to generate very large specific impulse and propulsive power.
Good sources of safety: high heat capacity of the core components, high temperature resistance of the three-layer sheet metal region of the fuel element, UO2Compatibility and chemical stability among fuel, structural materials, coolant and moderator, good containment of fission products by three layers of pyrolytic carbon and one layer of silicon carbide coated by fuel particles, feedback of inherent negative temperature reactivity of a reactor core and large temperature rise margin.
In summary, the above description is only a preferred embodiment of the present invention, and is not intended to limit the scope of the present invention. Any modification, equivalent replacement, or improvement made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (3)
1. A nuclear reactor for a mobile plant power plant comprising an upper support plate, a lower support plate, a control rod assembly, a fuel assembly, a reflector layer, a pressure vessel, a propellant supply conduit, a propellant discharge conduit, a plurality of cold gas chambers, a plurality of hot gas chambers, and a plurality of cold helium gas ports;
the middle part in the pressure container cavity is fixedly connected with a fuel assembly, an upper supporting plate is horizontally arranged above the fuel assembly and fixedly connected with the pressure container, a lower supporting plate is horizontally arranged below the fuel assembly and fixedly connected with the pressure container, a propellant supply pipeline is led in from an opening at the top of the pressure container and is communicated with the top end of the fuel assembly after penetrating through the upper supporting plate, a propellant spraying pipeline is communicated with the bottom end of the fuel assembly and is led out from an opening at the bottom of the pressure container after penetrating through the lower supporting plate, a control rod assembly is vertically fixed on the side wall of the fuel assembly, a plurality of cold helium gas channels are vertically distributed between the wall of the pressure container and the fuel assembly, the upper end of each cold helium gas channel is communicated with a; the plurality of hot air chambers are arranged between the fuel assembly and the lower support plate, and a reflecting layer is filled in a cavity between the pressure container and the fuel assembly;
the fuel assembly is composed of fuel elements and strut elements, and the fuel area of the fuel elements is composed of 60 layers of metal ceramic sheetsThe trumpet-shaped reel formed by sleeving the metal ceramic sheets is sequentially provided with a calcium metal matrix sheet area, a molybdenum metal matrix sheet area and a beryllium metal matrix sheet area from inside to outside, and UO is uniformly coated among the metal ceramic sheets in a dispersing way2Pellets of fuel in the form of spheres.
2. A nuclear reactor for a mobile unit power plant as claimed in claim 1, in which the beryllium alloy pieces are pinned to form the reflective layer.
3. A nuclear reactor for a mobile plant power plant as claimed in claim 1, in which the propellant supply and propellant ejection conduits are machined from beryllium alloy.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010653248.3A CN112366008A (en) | 2020-07-08 | 2020-07-08 | Nuclear reactor for mobile plant power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010653248.3A CN112366008A (en) | 2020-07-08 | 2020-07-08 | Nuclear reactor for mobile plant power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN112366008A true CN112366008A (en) | 2021-02-12 |
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| CN114530264A (en) * | 2022-01-04 | 2022-05-24 | 中国原子能科学研究院 | Space heap |
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