CN112635083B - Molten salt reactor capable of online material changing and material changing method thereof - Google Patents
Molten salt reactor capable of online material changing and material changing method thereof Download PDFInfo
- Publication number
- CN112635083B CN112635083B CN202011403541.0A CN202011403541A CN112635083B CN 112635083 B CN112635083 B CN 112635083B CN 202011403541 A CN202011403541 A CN 202011403541A CN 112635083 B CN112635083 B CN 112635083B
- Authority
- CN
- China
- Prior art keywords
- fuel
- reactor
- molten salt
- coolant
- container
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- 150000003839 salts Chemical class 0.000 title claims abstract description 57
- 238000000034 method Methods 0.000 title claims abstract description 9
- 239000000463 material Substances 0.000 title description 7
- 239000000446 fuel Substances 0.000 claims abstract description 152
- 230000000712 assembly Effects 0.000 claims abstract description 32
- 238000000429 assembly Methods 0.000 claims abstract description 32
- 241000013033 Triso Species 0.000 claims abstract description 20
- 239000002826 coolant Substances 0.000 claims description 53
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 19
- 238000001816 cooling Methods 0.000 claims description 17
- 230000001681 protective effect Effects 0.000 claims description 6
- 238000009826 distribution Methods 0.000 claims description 3
- 230000004308 accommodation Effects 0.000 claims 1
- 239000003758 nuclear fuel Substances 0.000 description 9
- 230000004992 fission Effects 0.000 description 8
- 239000007788 liquid Substances 0.000 description 8
- 239000004449 solid propellant Substances 0.000 description 6
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 4
- 238000006243 chemical reaction Methods 0.000 description 4
- 239000007789 gas Substances 0.000 description 4
- 230000020169 heat generation Effects 0.000 description 4
- 230000000694 effects Effects 0.000 description 3
- 230000005855 radiation Effects 0.000 description 3
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 2
- 229910002092 carbon dioxide Inorganic materials 0.000 description 2
- 239000001569 carbon dioxide Substances 0.000 description 2
- 230000005611 electricity Effects 0.000 description 2
- 150000004673 fluoride salts Chemical class 0.000 description 2
- 239000001257 hydrogen Substances 0.000 description 2
- 229910052739 hydrogen Inorganic materials 0.000 description 2
- PQXKHYXIUOZZFA-UHFFFAOYSA-M lithium fluoride Chemical compound [Li+].[F-] PQXKHYXIUOZZFA-UHFFFAOYSA-M 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000010248 power generation Methods 0.000 description 2
- 230000000717 retained effect Effects 0.000 description 2
- PUZPDOWCWNUUKD-UHFFFAOYSA-M sodium fluoride Chemical compound [F-].[Na+] PUZPDOWCWNUUKD-UHFFFAOYSA-M 0.000 description 2
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 description 1
- KRHYYFGTRYWZRS-UHFFFAOYSA-M Fluoride anion Chemical compound [F-] KRHYYFGTRYWZRS-UHFFFAOYSA-M 0.000 description 1
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 1
- 229910052776 Thorium Inorganic materials 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 230000002411 adverse Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- JZKFIPKXQBZXMW-UHFFFAOYSA-L beryllium difluoride Chemical compound F[Be]F JZKFIPKXQBZXMW-UHFFFAOYSA-L 0.000 description 1
- 229910001633 beryllium fluoride Inorganic materials 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 230000017525 heat dissipation Effects 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 238000012432 intermediate storage Methods 0.000 description 1
- WABPQHHGFIMREM-UHFFFAOYSA-N lead(0) Chemical compound [Pb] WABPQHHGFIMREM-UHFFFAOYSA-N 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 238000010907 mechanical stirring Methods 0.000 description 1
- 238000009377 nuclear transmutation Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 230000000191 radiation effect Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 235000013024 sodium fluoride Nutrition 0.000 description 1
- 239000011775 sodium fluoride Substances 0.000 description 1
- 238000003860 storage Methods 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
- 238000009423 ventilation Methods 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- 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
- G21C3/44—Fluid or fluent reactor fuel
- G21C3/54—Fused salt, oxide or hydroxide compositions
-
- 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
-
- 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/33—Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses an online reloadable molten salt reactor and a reloading method thereof, wherein the online reloadable molten salt reactor comprises a protection container, a reactor container arranged in the protection container, a reactor core, a supporting mechanism and a hoisting mechanism; the support mechanism comprises a plurality of support rails which are spaced in parallel and transversely span the reactor vessel; the core includes a plurality of fuel assemblies arranged along a length of the support rail, each fuel assembly including a fuel grid, TRISO fuel spheres received therein along a height of the fuel grid; the top of the fuel grating is hung on the supporting rail; the hoisting mechanism is positioned above the supporting mechanism. According to the molten salt reactor capable of online refueling, the TRISO fuel balls are filled into the vertical fuel grids to form a single fuel assembly, the fuel assembly is arranged and moved in the reactor container by matching with the supporting mechanism and the hoisting mechanism above the fuel assembly, the online refueling of the molten salt reactor and the fine adjustment of the axial enrichment degree of the fuel assembly are realized, and the power is built and expanded in a modularized manner.
Description
Technical Field
The invention relates to the technical field of nuclear power, in particular to an online reloadable molten salt reactor and a reloading method thereof.
Background
Molten Salt Reactor (MSR) is the only liquid fuel reactor in six fourth generation nuclear energy systems, and can be used for power generation, nuclear waste transmutation, hydrogen production, nuclear fuel production and other aspects. The molten salt reactor comprises two technical directions, wherein the first type is a liquid fuel molten salt reactor, and fissile materials are dissolved in molten fluoride salt; the second type is a solid fuel molten salt stack, where the molten fluoride is simply used as a coolant, the fuel is coated with particles similar to the fuel of a pebble-bed HTR, and the solid fuel type of molten salt stack is commonly referred to as a fluoride-cooled solid fuel high temperature stack (FHR).
Taking a liquid fuel molten salt reactor as an example, the liquid fuel molten salt reactor adopts thorium or uranium fused in fluoride salts such as beryllium fluoride, sodium fluoride, lithium fluoride and the like as fuel, and a solid fuel assembly does not need to be specially manufactured. The liquid fuel determines that its operating principle is different from that of a conventional solid fuel reactor: the fuel fused salt containing fission and convertible materials flows into the reactor core with optimized design at the inlet temperature of more than 500 ℃ so as to reach the criticality, and only reaches the criticality at the reactor core, the fuel fused salt generates fission reaction at the reactor core to release heat and is absorbed and taken away by the reactor core, no additional coolant is needed, and the temperature of the fuel fused salt at the outlet of the reactor core can reach 700-800 ℃ (the boiling point temperature of the fuel fused salt is about 1400 ℃). The high-temperature fuel molten salt flowing out of the reactor core transfers heat to secondary side coolant molten salt through a primary side heat exchanger, and then is transferred to a three-loop through a secondary side heat exchanger, and in the past study of the three-loop system, the Rankine cycle is mainly considered, the steam turbine generator is driven by heated steam to generate electricity, and the two-loop heat exchanger is considered to heat helium or supercritical carbon dioxide to generate electricity or produce hydrogen. Therefore, the high-temperature fuel molten salt of the whole reactor core of the molten salt reactor is not only a heat carrier, but also a heat source for nuclear reaction, and is a brand new nuclear reactor fuel utilization technology completely different from other solid fuels.
Chinese patent CN201810089818.3 discloses a small modular flow pebble bed fluoro-salt cooled high temperature reactor comprising a nuclear fuel operating system, a nuclear heat generation system, a nuclear heat transfer system and a nuclear heat utilization system. The nuclear fuel operation system is used for storing nuclear fuel, loading the nuclear fuel into the nuclear heat generation system and unloading the nuclear fuel from the nuclear heat generation system, the nuclear heat generation system controls the fission of the nuclear fuel and generates nuclear heat, and the nuclear heat transmission system transmits the nuclear heat to the nuclear heat utilization system, and the nuclear heat utilization system utilizes the nuclear heat for power generation or other heat utilization. The nuclear fuel operating system feeds fuel balls from the lower part of the core, and new fuel balls enter the core from the bottom by buoyancy, burn for a period of time, rise to the top by buoyancy, and leave the core. However, the above patent has the following problems: the primary loop coolant is forced circulation, the system flow is complex, the technical difficulty of the molten salt pump of key equipment is high, the cost is high, and the molten salt pump is easy to damage, and once the molten salt pump is damaged or a primary loop pipeline leaks, the active area of the reactor core is lost to be cooled, so that serious nuclear accidents are caused. The core fuel distribution has uncertainty that will have an adverse effect on core power control.
Chinese patent 200880117773.0 discloses a nuclear reactor, particularly a pool-type nuclear reactor, having a new concept of fuel elements, comprising a main tank containing a core comprising a bundle of fuel assemblies and immersed in a main coolant circulating between the core and at least one heat exchanger; the reactor is characterized in that: the fuel assemblies extending along respective parallel longitudinal axes and having respective active portions disposed at bottom ends of the fuel assemblies and submerged in the primary coolant to form the core, and respective service portions extending above the active portions and emerging from the primary coolant; the reactor is a circular core. The fuel assemblies in the above patents are complex in structure and require shutdown refueling. Whether the fuel assembly has high temperature resistance, heat transfer characteristics and the like is not detailed.
Chinese patent 201480010226.8 discloses a practical molten salt fission reactor comprising a core, a pool of coolant liquid and a heat exchanger; the core comprises an array of hollow tubes of molten salt containing fissile isotopes. The tube array is at least partially submerged in a pool of coolant liquid; the tube array includes critical sections in which the density of fissile isotopes during operation of the reactor is sufficient to initiate a self-sustaining fission reaction. Heat transfer from the molten salt of the fissile isotope to the tube is achieved by any one or more of the following: natural convection of the molten salt; mechanical stirring of the molten salt; and oscillating molten salt flow within the tube. The molten salt of the fissile isotope is completely contained within the tube during reactor operation. In this patent, fissile fuel molten salt is contained in the fuel pipe, but the fuel molten salt is relatively strong in corrosiveness to the fuel pipe, once leaked, the whole loop coolant is polluted, the control of radioactive substances is unfavorable, and the collection and control of fissile gas are difficult. In addition, the fuel loading scheme is not described in this patent, and whether a shutdown refueling is required is not detailed.
Disclosure of Invention
The invention aims to solve the technical problem of providing an online reloadable molten salt reactor based on TRISO fuel balls and a reloading method thereof.
The technical scheme adopted for solving the technical problems is as follows: the molten salt reactor capable of online refueling comprises a closed protection container, a reactor container arranged in the protection container, a reactor core arranged in the reactor container, a supporting mechanism and a hoisting mechanism arranged in the protection container;
The support mechanism comprises a plurality of support rails spaced in parallel and spanning above the reactor vessel; the core includes a plurality of fuel assemblies arranged along a length of the support rails, each of the fuel assemblies including a fuel grid vertically immersed in coolant, TRISO fuel spheres received therein along a height of the fuel grid and immersed in coolant; the top of the fuel grid is exposed out of the coolant and hung on the support rail;
The lifting mechanism is positioned above the supporting mechanism and is used for lifting the fuel assembly and transversely moving the fuel assembly along the supporting rail.
Preferably, in the fuel grid, the TRISO fuel spheres form a single row or a plurality of rows.
Preferably, a support structure is provided in the reactor vessel, supported at the bottom of the fuel grid.
Preferably, the support rail comprises at least two transverse rails which are arranged in parallel at intervals; the top of the fuel grating is matched on at least two transverse rails.
Preferably, the hoisting mechanism comprises at least one cross beam positioned above the supporting mechanism and a hoisting piece which is arranged on the cross beam in a lifting manner.
Preferably, the on-line refuelable molten salt reactor further comprises at least one heat exchanger disposed within the reactor vessel;
And the coolant in the reactor vessel enters the heat exchanger from an inlet at the upper end of the heat exchanger, and returns to the reactor vessel and the reactor core from an outlet at the lower end of the heat exchanger after heat exchange, so that a coolant circulation loop is formed.
Preferably, the coolant circulates naturally between the heat exchanger and the core along a coolant circulation loop under the effect of a density difference caused by a temperature difference; or a circulating pump is arranged at the inlet of the heat exchanger to drive the coolant to flow in a coolant circulation loop in a forced circulation mode.
Preferably, the online reloadable molten salt reactor further comprises at least one passive air cooling flow passage arranged in the surrounding wall of the protection container, and an air inlet and an air outlet which are respectively communicated with the passive air cooling flow passage are arranged on the outer wall surface of the protection container.
Preferably, the passive air cooling flow passage is bent in the surrounding wall of the protection container to form an input flow passage and an output flow passage which are connected, and the output flow passage is closer to the inner wall surface of the protection container than the input flow passage;
The air inlet is communicated with the input flow channel, and the air outlet is communicated with the output flow channel.
Preferably, the passive air cooling flow passage extends in a plurality of bends in the enclosure wall of the protective container.
Preferably, the outer wall of the reactor vessel is provided with radiating fins.
The invention also provides a refueling method of the online refueling molten salt reactor, which comprises the following steps:
S1, after a spent fuel assembly is formed by the fuel assembly, the spent fuel assembly is lifted by a lifting mechanism, so that the top of a fuel grid of the spent fuel assembly is separated from a supporting rail;
S2, the lifted spent fuel assembly is moved to one end of the support rail along the support rail by the lifting mechanism;
S3, the hoisting mechanism sequentially moves the fuel assemblies hung on the support rail, fills the positions of the spent fuel assemblies, and loads new fuel assemblies from the other end of the support rail.
Preferably, one end of the support rail is used as a fuel assembly inlet end, and the opposite end is used as a fuel outlet end;
the fuel assembly inlet ends of two adjacent support rails are staggered.
The invention has the beneficial effects that: the TRISO fuel balls are filled into the vertical fuel grids to form a single fuel assembly, the fuel assembly is arranged in the reactor container by matching with the supporting mechanism and the hoisting mechanism which are arranged above the fuel assembly, and the online refueling of the molten salt reactor and the fine adjustment of the axial enrichment degree of the single fuel assembly are realized, so that the power is built and expanded in a modularized manner.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic cross-sectional view of an on-line refuelable molten salt reactor in accordance with an embodiment of the present invention;
FIG. 2 is a top view of a fuel assembly on a support mechanism in an in-line refuelable molten salt reactor in accordance with an embodiment of the present invention.
Detailed Description
For a clearer understanding of technical features, objects and effects of the present invention, a detailed description of embodiments of the present invention will be made with reference to the accompanying drawings.
As shown in fig. 1, an on-line refuelable molten salt reactor according to an embodiment of the present invention includes a closed protection vessel 10, a reactor vessel 20 disposed in the protection vessel 10, a core disposed in the reactor vessel 20, a support mechanism 30 disposed in the protection vessel 10, and a hoist mechanism 40.
The reactor vessel 20 is contained by the protective vessel 10 and is located in a reactor building which can withstand low pressure (positive and negative); the factory building is internally provided with an air filtering and purifying device for collecting radionuclide such as fission gas. The main circuit is located in a reactor vessel (pool stack) 20.
The coolant is contained within the reactor vessel 20, submerging the core within the reactor vessel 20. The core includes a plurality of fuel assemblies 50, each fuel assembly 50 including a fuel grid 51 and a plurality of TRISO fuel balls (isotropically coated fuel) 52 housed within the fuel grid 51.
In the present invention, the whole of the fuel grid 51 may be a hollow or net-shaped cylindrical structure, the fuel grid 51 is vertically arranged in the reactor vessel 20, the TRISO fuel balls 52 are accommodated therein along the height of the fuel grid 51 and immersed in the coolant, and the heat of the TRISO fuel balls 52 is taken away by the flow of the coolant. The TRISO fuel balls 52 form a single column or a plurality of columns in the height direction of the fuel grid 51, depending on the diameter size of the TRISO fuel balls 52.
The coolant can be molten salt coolant, or liquid metal coolant such as metallic lead base, sodium, etc. or other normal pressure liquid coolant compatible with TRISO fuel.
The support mechanism 30 is located above the reactor vessel 20 within the containment vessel 10 for suspending the fuel assemblies 50 that position the core. The support mechanism 30 may include a plurality of support rails 31 spaced in parallel and spanning above the reactor vessel 20, with a plurality of fuel assemblies 50 disposed along the length of the support rails 31, with the fuel grids 51 of the fuel assemblies 50 being immersed vertically in the coolant, as well as with TRISO fuel balls 52 contained in the fuel grids 51 being immersed in the coolant. The top of the fuel grid 51 is exposed to the coolant and is suspended from the support rail 31.
A matched buckle component, a locating pin component, a concave-convex structure or the like can be arranged between the top of the fuel grating 51 and the support rail 31, so that the top of the fuel grating 51 is located on the support rail 31 and is not easy to shift.
A square core may be formed by dividing the plurality of fuel assemblies 50 into a plurality of groups arranged and suspended on the plurality of support rails 31. Each fuel assembly 50 can adjust the height of the TRISO fuel sphere 52 to accommodate before loading as desired, thereby adjusting the fuel enrichment at different heights to adjust the core power distribution.
In addition, fissile gas and the like can be retained by the TRISO fuel balls 52, possible fission products released by molten salt coolant are retained, the reactor building is a micro negative pressure container, and a ventilation system removes possible radioactive gas.
In this embodiment, referring to fig. 1 and 2, the support rail 31 includes at least two transverse rails 311 disposed in parallel and spaced apart; the top of the fuel grid 51 mates with and is positioned on the rails 311. The peripheral dimension of the main body of the fuel grating 51 is smaller than the interval between two horizontal rods 311 which are horizontally adjacent to each other, so that the lifting and the material changing movement are facilitated; the top of the fuel grid 51 is then cooperatively positioned over the two rails 311.
To further secure the fuel assembly 50, a support structure 21 is provided within the reactor vessel 20, supported at the bottom of the fuel grid 51. The support structure 21 may be in the form of a support beam, a support screen, or the like.
Lifting mechanism 40 is located above support mechanism 30 within protective container 10 for lifting fuel assembly 50 and moving fuel assembly 50 laterally along support rail 31.
Alternatively, in this embodiment, the lifting mechanism 40 includes at least one beam 41 located above the supporting mechanism 30, and a lifting member 42 disposed on the beam 41 in a liftable manner. The lifting member 42 is adapted to cooperate with the top of the fuel grate 51 to raise or lower the fuel assembly 50. The lifting member 42 may be a hook or other structural member, and may specifically be configured to cooperate with the top structure of the fuel grid 51.
The molten salt reactor capable of online refueling of the invention also comprises a remote control terminal (not shown) for controlling the start and stop of the hoisting mechanism 40.
Further, the on-line refuelable molten salt reactor of the present invention further includes at least one heat exchanger 60 disposed within the reactor vessel 20.
The coolant in the reactor vessel 20 enters the heat exchanger 60 from an inlet at the upper end of the heat exchanger 60, exchanges heat with a medium passing through the heat exchanger 60 (the medium on the secondary side may be molten salt, water, carbon dioxide, or the like), and returns to the reactor vessel 20 and the reactor core from an outlet at the lower end of the heat exchanger 60, thereby forming a coolant circulation loop (as shown by an arrow in fig. 1).
Wherein, under the action of density difference caused by temperature difference of coolant approaching and separating from the reactor core, the coolant flows in a natural circulation mode in the coolant circulation loop; alternatively, a circulation pump may be provided at the inlet of the heat exchanger 60 to drive the coolant into the heat exchanger 60 to force the coolant to flow in a forced circulation manner in the coolant circulation loop. The core in the reactor vessel 10 is cooled by the continuous flow of coolant along the coolant circulation circuit, thereby achieving the primary and secondary energy exchange.
As shown in fig. 1, in this embodiment, two heat exchangers 60 are disposed within the reactor vessel 20 on opposite sides of the core.
The heat exchanger 60 may be formed as a module with the core and the number of modules may be expanded as desired within the reactor vessel 20.
The molten salt reactor capable of online refueling according to the present invention further comprises at least one passive air cooling flow passage 70 provided in the surrounding wall of the protection vessel 10, and an air inlet (not shown) and an air outlet (not shown) respectively communicating with the passive air cooling flow passage 70 are provided on the outer wall surface of the protection vessel 10. The air enters the passive air cooling flow passage 70 from the air inlet, flows along the passive air cooling flow passage 70, absorbs heat, and then heats up to discharge the passive air cooling flow passage 70 from the air outlet.
In the present embodiment, the passive air cooling flow path 70 is bent inside the surrounding wall of the protection container 10 to form an input flow path 71 and an output flow path 72 that are connected, and the output flow path 72 is closer to the inner wall surface of the protection container 10 or parallel to the inner wall surface than the input flow path 71. The air inlet communicates with the inlet flow passage 71 and the air outlet communicates with the outlet flow passage 72.
In other embodiments, the passive air cooling flow passage 70 may extend in multiple bends in the enclosure wall of the protective container 10, such as in a horizontal or vertical direction. The air inlet and air outlet may be located on opposite sides or the same side of the enclosure wall and the air outlet is located at a higher elevation than the air inlet.
The heat exchanger 60 and the passive air cooling flow passage 70 are arranged, and after shutdown, the heat after an accident is led out to the final heat trap-atmosphere by utilizing the characteristic of high temperature of the coolant and passive cooling such as heat radiation, convection heat transfer (enhanced heat transfer of the large-surface-area thin fins) and the like.
In addition, heat radiation fins may be provided on the outer wall of the reactor vessel 20 to enhance the heat radiation effect and to enhance heat radiation. The heat dissipation fins are preferably fins having a large surface area.
Referring to fig. 1 and 2, the method for reloading an online reloadable molten salt reactor according to the invention comprises the following steps:
s1, after the fuel assembly 50 forms a spent fuel assembly, the hoisting mechanism 40 hoistes the spent fuel assembly so that the top of the fuel grid 51 of the spent fuel assembly is separated from the supporting rail 31.
S2, the lifting mechanism 40 moves the lifted spent fuel assembly to one end of the support rail 31 along the support rail 31.
S3, the hoisting mechanism 40 sequentially moves the fuel assemblies 50 suspended on the support rail 31, fills the positions of the spent fuel assemblies, and loads new fuel assemblies 50 from the other ends of the support rail 31.
One end of the support rail 31 is taken as a fuel assembly inlet end, and the other end is taken as a fuel outlet end. The spent fuel assembly is moved to the fuel discharge end of the support rail 31 and out of the core. The new fuel assembly 50 is moved into the core from the fuel assembly entry end of the support rail 31.
The fuel assembly inlet ends of two adjacent support rails 31 are staggered, and better core power flattening is achieved by utilizing different fuel enrichment degrees in the transverse direction and the vertical direction.
In the core, among the plurality of rows of fuel assemblies formed by the plurality of support rail 31 rows, each row of fuel assemblies is loaded with a new fuel assembly 50 from one end of the support rail 31 where it is located, the spent fuel assemblies are taken out from the opposite end, and the old fuel assemblies 50 are moved to the spent fuel assemblies side in turn, and can be moved to the adjacent position only by slightly lifting the fuel assemblies 50 by the lifting mechanism 40, and the fuel assemblies 50 are always kept in the coolant.
After passing through the core, the spent fuel assemblies are moved to the perimeter of the reactor vessel 20 for storage until decay heat is reduced to a value and then moved to an intermediate storage facility. A new batch of fuel assemblies (maintained at a sufficient distance from the core to ensure minimal fission reactions) is pre-stored within the reactor vessel 20 to support intermittent non-shutdown refueling, meeting long refueling cycle requirements.
The foregoing description is only illustrative of the present invention and is not intended to limit the scope of the invention, and all equivalent structures or equivalent processes or direct or indirect application in other related technical fields are included in the scope of the present invention.
Claims (6)
1. The molten salt reactor capable of online refueling is characterized by comprising a closed protection container, a reactor container arranged in the protection container, a reactor core arranged in the reactor container, a supporting mechanism and a hoisting mechanism arranged in the protection container;
The support mechanism comprises a plurality of support rails spaced in parallel and spanning above the reactor vessel; the core includes a plurality of fuel assemblies arranged along a length of the support rails, each of the fuel assemblies including a fuel grid vertically immersed in coolant, TRISO fuel spheres received therein along a height of the fuel grid and immersed in coolant; the whole fuel grid is of a hollow or net-shaped barrel structure, the fuel grid is vertically arranged in the reactor container, the TRISO fuel balls are accommodated in the fuel grid along the height of the fuel grid and immersed in the coolant, and the heat of the TRISO fuel balls is taken away through the flow of the coolant;
In the fuel grid, the TRISO fuel balls form a single row or a plurality of rows, and each fuel assembly adjusts the height accommodation of the TRISO fuel balls before loading so as to adjust the fuel enrichment degree of different heights to adjust the reactor core power distribution; the support rail comprises at least two transverse rails which are arranged in parallel at intervals; the top of the fuel grating is matched with at least two transverse rails;
The top of the fuel grid is exposed out of the coolant and hung on the support rail; the lifting mechanism is positioned above the supporting mechanism and is used for lifting the fuel assembly and transversely moving the fuel assembly along the supporting rail;
The online reloadable molten salt reactor further comprises at least one passive air cooling flow passage arranged in the surrounding wall of the protection container, and an air inlet and an air outlet which are respectively communicated with the passive air cooling flow passage are arranged on the outer wall surface of the protection container;
The passive air cooling flow passage is bent in the surrounding wall of the protective container to form an input flow passage and an output flow passage which are connected, and the output flow passage is parallel to the inner wall surface of the protective container or is equidistant to the wall surface and bent for many times compared with the input flow passage;
The air inlet is communicated with the input flow channel, and the air outlet is communicated with the output flow channel;
The passive air cooling flow passage is bent and extended for a plurality of times in the surrounding wall of the protection container;
And the outer wall of the reactor container is provided with radiating fins.
2. The on-line refuelable molten salt reactor of claim 1 wherein a support structure is provided within the reactor vessel that is supported at the bottom of the fuel grid.
3. The molten salt reactor of claim 1 wherein said lifting means comprises at least one beam above said support means and lifting means arranged on said beam in a liftable manner.
4. The on-line refuelable molten salt reactor of claim 1 further comprising at least one heat exchanger disposed within the reactor vessel;
And the coolant in the reactor vessel enters the heat exchanger from an inlet at the upper end of the heat exchanger, and returns to the reactor vessel and the reactor core from an outlet at the lower end of the heat exchanger after heat exchange, so that a coolant circulation loop is formed.
5. The on-line refuelable molten salt reactor of claim 4 wherein coolant circulates naturally between the heat exchanger and the core along a coolant circulation loop under the influence of a density differential caused by a temperature differential; or a circulating pump is arranged at the inlet of the heat exchanger to drive the coolant to flow in a coolant circulation loop in a forced circulation mode.
6. A method of refuelling an on-line refuelable molten salt reactor as claimed in any one of claims 1 to 5 including the steps of:
S1, after a spent fuel assembly is formed by the fuel assembly, the spent fuel assembly is lifted by a lifting mechanism, so that the top of a fuel grid of the spent fuel assembly is separated from a supporting rail;
S2, the lifted spent fuel assembly is moved to one end of the support rail along the support rail by the lifting mechanism;
s3, sequentially moving the fuel assemblies hung on the support rail by the hoisting mechanism, filling the positions of the spent fuel assemblies, and loading new fuel assemblies from the other end of the support rail, wherein one end of the support rail is used as a fuel assembly inlet end, and the other end of the support rail is used as a fuel outlet end;
the fuel assembly inlet ends of two adjacent support rails are staggered.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011403541.0A CN112635083B (en) | 2020-12-04 | 2020-12-04 | Molten salt reactor capable of online material changing and material changing method thereof |
| PCT/CN2021/116591 WO2022116614A1 (en) | 2020-12-04 | 2021-09-06 | Molten salt reactor capable of realizing online refueling, and refueling method thereof |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011403541.0A CN112635083B (en) | 2020-12-04 | 2020-12-04 | Molten salt reactor capable of online material changing and material changing method thereof |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN112635083A CN112635083A (en) | 2021-04-09 |
| CN112635083B true CN112635083B (en) | 2024-05-10 |
Family
ID=75308229
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202011403541.0A Active CN112635083B (en) | 2020-12-04 | 2020-12-04 | Molten salt reactor capable of online material changing and material changing method thereof |
Country Status (2)
| Country | Link |
|---|---|
| CN (1) | CN112635083B (en) |
| WO (1) | WO2022116614A1 (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112635083B (en) * | 2020-12-04 | 2024-05-10 | 中广核工程有限公司 | Molten salt reactor capable of online material changing and material changing method thereof |
| CN113299409A (en) * | 2021-04-30 | 2021-08-24 | 西安交通大学 | Small-size villaumite of spiral cross fuel element cools off high temperature reactor core |
| CN113689963B (en) * | 2021-08-30 | 2022-12-09 | 西安交通大学 | Multipurpose heat transport system for small-sized villiaumite cooling high-temperature reactor |
Citations (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB935130A (en) * | 1961-09-12 | 1963-08-28 | Arthur Paul Pedrick | Improvements in fuel element arrangements for nuclear reactors |
| US3170843A (en) * | 1962-10-26 | 1965-02-23 | Hammond Roland Philip | Paste reactor |
| GB1281979A (en) * | 1969-12-16 | 1972-07-19 | Brown Boveri Krupp Reaktor | Low capacity nuclear reactor and fuel elements therefor |
| BE797291A (en) * | 1972-03-29 | 1973-07-16 | Euratom | NUCLEAR REACTOR AND METHOD FOR OPERATING SUCH REACTOR |
| JPS6438692A (en) * | 1987-08-03 | 1989-02-08 | Power Reactor & Nuclear Fuel | Fuel control autonomous safety type fast breeder |
| CN1700359A (en) * | 2005-03-18 | 2005-11-23 | 张育曼 | Supercritical water nuclear reactor utilizing sleeve fuel assembly |
| RU2348084C1 (en) * | 2007-08-17 | 2009-02-27 | Федеральное государственное унитарное предприятие "Всероссийский научно-иследовательский институт неорганических материалов имени академика А.А. Бочвара" | Device for withdrawal of spent fuel assemblies |
| CN101939793A (en) * | 2007-09-26 | 2011-01-05 | 德尔诺瓦维斯公司 | Nuclear reactor, in particular pool-type nuclear reactor, having new concept fuel elements |
| CN102623072A (en) * | 2012-03-30 | 2012-08-01 | 中国科学院合肥物质科学研究院 | Compound accident residual heat removal system for accelerator-driven sub-critical reactor |
| CN104269194A (en) * | 2014-10-13 | 2015-01-07 | 中国科学院合肥物质科学研究院 | Temperature-triggered passive accident residual heat removal system for pool type reactor |
| CN108369827A (en) * | 2015-12-06 | 2018-08-03 | 伊恩·理查德·斯科特 | Rectangle nuclear reactor core |
| CN109215809A (en) * | 2018-09-13 | 2019-01-15 | 中国核动力研究设计院 | A kind of supercritical carbon dioxide reactor microspheroidal fuel assembly |
| CN111627572A (en) * | 2020-06-04 | 2020-09-04 | 中国科学院上海应用物理研究所 | Modularized molten salt reactor core and molten salt reactor |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB964841A (en) * | 1962-02-14 | 1964-07-22 | Atomic Energy Authority Uk | Nuclear reactors cooled by liquid metal |
| EP1622168B1 (en) * | 2004-07-28 | 2011-06-22 | The European Atomic Energy Community (EURATOM), represented by the European Commission | Integral nuclear reactor |
| WO2018140117A2 (en) * | 2016-11-15 | 2018-08-02 | Terrapower, Llc | Thermal management of molten fuel nuclear reactors |
| CN209496626U (en) * | 2018-12-07 | 2019-10-15 | 中国科学院上海应用物理研究所 | Core structure and fused salt pebble bed reactor |
| CN109509562B (en) * | 2018-12-07 | 2023-09-19 | 中国科学院上海应用物理研究所 | Reactor core structure, molten salt pebble bed reactor, fuel management method of molten salt pebble bed reactor and reactor core loading method |
| CN112635083B (en) * | 2020-12-04 | 2024-05-10 | 中广核工程有限公司 | Molten salt reactor capable of online material changing and material changing method thereof |
-
2020
- 2020-12-04 CN CN202011403541.0A patent/CN112635083B/en active Active
-
2021
- 2021-09-06 WO PCT/CN2021/116591 patent/WO2022116614A1/en active Application Filing
Patent Citations (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB935130A (en) * | 1961-09-12 | 1963-08-28 | Arthur Paul Pedrick | Improvements in fuel element arrangements for nuclear reactors |
| US3170843A (en) * | 1962-10-26 | 1965-02-23 | Hammond Roland Philip | Paste reactor |
| GB1034870A (en) * | 1962-10-26 | 1966-07-06 | Atomic Energy Commission | Paste reactor |
| GB1281979A (en) * | 1969-12-16 | 1972-07-19 | Brown Boveri Krupp Reaktor | Low capacity nuclear reactor and fuel elements therefor |
| BE797291A (en) * | 1972-03-29 | 1973-07-16 | Euratom | NUCLEAR REACTOR AND METHOD FOR OPERATING SUCH REACTOR |
| JPS6438692A (en) * | 1987-08-03 | 1989-02-08 | Power Reactor & Nuclear Fuel | Fuel control autonomous safety type fast breeder |
| CN1700359A (en) * | 2005-03-18 | 2005-11-23 | 张育曼 | Supercritical water nuclear reactor utilizing sleeve fuel assembly |
| RU2348084C1 (en) * | 2007-08-17 | 2009-02-27 | Федеральное государственное унитарное предприятие "Всероссийский научно-иследовательский институт неорганических материалов имени академика А.А. Бочвара" | Device for withdrawal of spent fuel assemblies |
| CN101939793A (en) * | 2007-09-26 | 2011-01-05 | 德尔诺瓦维斯公司 | Nuclear reactor, in particular pool-type nuclear reactor, having new concept fuel elements |
| CN102623072A (en) * | 2012-03-30 | 2012-08-01 | 中国科学院合肥物质科学研究院 | Compound accident residual heat removal system for accelerator-driven sub-critical reactor |
| CN104269194A (en) * | 2014-10-13 | 2015-01-07 | 中国科学院合肥物质科学研究院 | Temperature-triggered passive accident residual heat removal system for pool type reactor |
| CN108369827A (en) * | 2015-12-06 | 2018-08-03 | 伊恩·理查德·斯科特 | Rectangle nuclear reactor core |
| CN109215809A (en) * | 2018-09-13 | 2019-01-15 | 中国核动力研究设计院 | A kind of supercritical carbon dioxide reactor microspheroidal fuel assembly |
| CN111627572A (en) * | 2020-06-04 | 2020-09-04 | 中国科学院上海应用物理研究所 | Modularized molten salt reactor core and molten salt reactor |
Non-Patent Citations (2)
| Title |
|---|
| 华明川.先进核电站辐射安全.中国原子能出版社,2012,第220页. * |
| 氟盐冷却高温堆在主要事故工况下对RVACS散热能力的需求;赵晶;中国优秀硕士学位论文全文数据库 工程科技II辑(第7期);第15页 * |
Also Published As
| Publication number | Publication date |
|---|---|
| WO2022116614A1 (en) | 2022-06-09 |
| CN112635083A (en) | 2021-04-09 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN112635083B (en) | Molten salt reactor capable of online material changing and material changing method thereof | |
| CN108417277B (en) | Integrated reactor body system and chloride reactor system | |
| Adamov et al. | The next generation of fast reactors | |
| US20090268860A1 (en) | Process for accelerating the breeding and conversion of fissile fuel in nuclear reactors | |
| Shin et al. | Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation | |
| EP2965323A2 (en) | Managing nuclear reactor spent fuel rods | |
| US20120051485A1 (en) | Corium cooling promoting apparatus and containment | |
| US5021211A (en) | Liquid metal cooled nuclear reactors with passive cooling system | |
| CN111508622A (en) | Reactor core and reactor | |
| CN108140433A (en) | Nuclear reactor | |
| EP0167069B1 (en) | Gas displacement spectral shift reactor | |
| Skoda et al. | TEPLATOR: nuclear district heating solution | |
| US3156625A (en) | Core for a supercritical pressure power reactor | |
| Zeman et al. | TEPLATOR DEMO: Basic design of the primary circuit | |
| US20230106712A1 (en) | Liquid metal cooled nuclear reactor incorporating a fully passive decay heat removal (dhr) system with a modular cold source | |
| JP2006343321A (en) | Fuel element for fast reactor, fast reactor and erection method of fast reactor facility | |
| Orlov et al. | Heavy liquid metal cooled fast reactors: peculiarities and development status of the major projects | |
| Ignat’ev et al. | Analysis of the Fuel-Loop Characteristics of a Molten-Salt Nuclear Reactor with a Cavity Core | |
| Proust et al. | Status of the design and feasibility assessment of the European helium cooled ceramic breeder inside tubes test blanket | |
| Modro et al. | Generation-IV multi-application small light water reactor (MASLWR) | |
| CN117174349A (en) | Gallium metal cooled megawatt-level small modular nuclear reactor | |
| JP4341876B2 (en) | Solid cooled reactor | |
| Filin et al. | Design features of BREST reactors and experimental work to advance the concept of BREST reactors | |
| US20240170168A1 (en) | Solid-state fluid thermal bonded heat pipe micro-reactor | |
| KR20090047186A (en) | Pascar : proliferation-resistant, accident-tolerant, secure and capsular autonomous reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |