CN112635083A - Molten salt pile capable of changing materials online and material changing method thereof - Google Patents

Molten salt pile capable of changing materials online and material changing method thereof Download PDF

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Publication number
CN112635083A
CN112635083A CN202011403541.0A CN202011403541A CN112635083A CN 112635083 A CN112635083 A CN 112635083A CN 202011403541 A CN202011403541 A CN 202011403541A CN 112635083 A CN112635083 A CN 112635083A
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CN
China
Prior art keywords
fuel
molten salt
reactor
coolant
flow channel
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Pending
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CN202011403541.0A
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Chinese (zh)
Inventor
郑华
张辉
何国伟
魏淑虹
张勋
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China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
CGN Power Co Ltd
Shenzhen China Guangdong Nuclear Engineering Design Co Ltd
Original Assignee
China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
CGN Power Co Ltd
Shenzhen China Guangdong Nuclear Engineering Design Co Ltd
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Application filed by China General Nuclear Power Corp, China Nuclear Power Engineering Co Ltd, CGN Power Co Ltd, Shenzhen China Guangdong Nuclear Engineering Design Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN202011403541.0A priority Critical patent/CN112635083A/en
Publication of CN112635083A publication Critical patent/CN112635083A/en
Priority to PCT/CN2021/116591 priority patent/WO2022116614A1/en
Pending legal-status Critical Current

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/44Fluid or fluent reactor fuel
    • G21C3/54Fused salt, oxide or hydroxide compositions
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/33Supporting 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
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

The invention discloses an online refueling molten salt reactor and a refueling method thereof, wherein the online refueling molten salt reactor comprises a protection container, a reactor container arranged in the protection container, a reactor core, a support mechanism and a hoisting mechanism; the supporting mechanism comprises a plurality of supporting rails which are parallel and spaced and span above 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 grate, a TRISO fuel sphere housed therein along a height of the fuel grate; the top of the fuel grid is hung on the support rail; the hoisting mechanism is positioned above the supporting mechanism. According to the online refueling molten salt reactor, the TRISO fuel balls are filled into the vertical fuel grids to form a single fuel assembly, the fuel assemblies are arranged and moved in the reactor container by matching with the supporting mechanism and the hoisting mechanism above the fuel assemblies, online refueling of the molten salt reactor is realized, the axial enrichment degree of the fuel assemblies is finely adjusted, and the molten salt reactor is modularly constructed and expands power.

Description

Molten salt pile capable of changing materials online and material changing method thereof
Technical Field
The invention relates to the technical field of nuclear power, in particular to a molten salt pile capable of realizing online refueling and a refueling method thereof.
Background
The 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 the like. The molten salt reactor comprises two technical directions, the first type is a liquid fuel molten salt reactor, and fissile materials are dissolved in molten fluoride; the second type is a solid fuel molten salt stack, where the molten fluoride salt acts only as a coolant, and the fuel uses coated particles, similar to the fuel of the pebble bed HTR, which is a type of solid fuel molten salt stack 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 liquid fusion of thorium or uranium dissolved in fluoride salt such as beryllium fluoride, sodium fluoride and lithium fluoride as fuel, and does not need to specially manufacture a solid fuel assembly. The liquid fuel determines that the working principle of the liquid fuel 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 the reactor core of more than 500 ℃ so as to reach the critical state, and only reaches the critical state at the reactor core, the fuel fused salt has fission reaction at the reactor core to release heat and is absorbed and taken away by the fuel fused salt, 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 temperature is about 1400 ℃). The high-temperature fuel fused salt flowing out of the reactor core transfers heat to the secondary side coolant fused salt through the primary side heat exchanger and then transfers the heat to the three-loop through the secondary side heat exchanger, in the past research of the three-loop system, Rankine cycle is mainly considered, a steam turbine generator is pushed by heated steam to generate electricity, and at present, a 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 transfer agent, but also a heat source of 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 ball bed fluoride salt cooled high temperature reactor, which comprises a nuclear fuel operation system, a nuclear heat generation system, a nuclear heat transmission system and a nuclear heat utilization system. The nuclear fuel operating system stores and loads and unloads nuclear fuel into and from a nuclear heat generating system, the nuclear heat generating system controls fission of the nuclear fuel and generates nuclear heat, the nuclear heat transmitting system transmits the nuclear heat to a nuclear heat utilizing system, and the nuclear heat utilizing system utilizes the nuclear heat for power generation or other heat utilization. The nuclear fuel handling system feeds fuel spheres from the lower portion of the core, and fresh fuel spheres enter the core from the bottom by buoyancy, rise to the top by buoyancy after a period of combustion, and leave the core. However, the above patent has the following problems: one loop coolant is forced circulation, the system flow is complex, the key equipment molten salt pump is large in technical difficulty, high in manufacturing cost and easy to damage, and once the molten salt pump is damaged or a loop pipeline leaks, the core active area is lost to be cooled, so that serious nuclear accidents are caused. The core fuel distribution has uncertainty that will adversely affect core power control.
Chinese patent 200880117773.0 discloses a nuclear reactor with new concept of fuel elements, in particular a pool-type nuclear reactor, comprising a main tank with a containment core comprising a bundle of fuel assemblies and immersed in a primary 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 constitute 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 assembly in the above patent is complex in structure and requires shutdown for 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 containing a molten salt of a fissile isotope. The tube array is at least partially submerged in a pool of coolant liquid; the tube array includes a critical zone in which a density of the fissile isotopes during reactor operation 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 means: natural convection of the molten salt; mechanical stirring of the molten salt; and an oscillating molten salt flow within the tube. The molten salt of the fissile isotope is contained entirely within the tube during reactor operation. In the patent, the fuel pipe is loaded with fission fuel molten salt, but the fuel molten salt has strong corrosivity to the fuel pipe, once leakage happens, the whole primary circuit coolant is polluted, the radioactive substance is not controlled, and the collection and control of fission gas are difficult. In addition, the fuel loading scheme is not described in this patent, and whether a shutdown refueling is required is not described.
Disclosure of Invention
The invention aims to provide a TRISO fuel sphere-based online refueling molten salt reactor and a refueling method thereof.
The technical scheme adopted by the invention for solving the technical problems is as follows: the online refueling molten salt reactor 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 which are spaced in parallel and span above the reactor vessel; the core comprises a plurality of fuel assemblies arranged along the length direction of the support rail, each fuel assembly comprises a fuel grid vertically immersed in coolant, a TRISO fuel ball accommodated therein along the height of the fuel grid and immersed in the coolant; the top of the fuel grid is exposed to the coolant and hung on the support rail;
the hoisting mechanism is positioned above the supporting mechanism and used for hoisting 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 that is supported at the bottom of the fuel grid.
Preferably, the support rail comprises at least two transverse rails arranged in parallel at intervals; the top of the fuel grid fits over at least two of the cross rails.
Preferably, the hoisting mechanism comprises at least one beam positioned above the supporting mechanism and a hoisting piece arranged on the beam in a lifting manner.
Preferably, the on-line refuelable molten salt stack 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 to form a coolant circulation loop.
Preferably, the coolant circulates naturally between the heat exchanger and the core along the coolant circulation circuit, under the effect of the density difference caused by the temperature difference; alternatively, a circulating pump is arranged at the inlet of the heat exchanger, and the coolant is driven to flow in the coolant circulating loop in a forced circulation mode.
Preferably, the online refueling molten salt reactor further comprises at least one passive air cooling flow channel arranged in the surrounding wall of the protection container, and the outer wall surface of the protection container is provided with an air inlet and an air outlet which are respectively communicated with the passive air cooling flow channel.
Preferably, the passive air cooling flow channel is bent in the surrounding wall of the protection container to form an input flow channel and an output flow channel which are connected, and the output flow channel is closer to the inner wall surface of the protection container than the input flow channel;
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 channel extends in the surrounding wall of the protective container in a plurality of bending ways.
Preferably, the reactor vessel outer wall is provided with heat radiating fins.
The invention also provides a refueling method of the online refueling molten salt reactor, which comprises the following steps:
s1, after the fuel assembly forms a spent fuel assembly, the hoisting mechanism hoists the spent fuel assembly to separate the top of the fuel grid from the support rail;
s2, moving the lifted spent fuel assembly to one end of the support rail along the support rail by a hoisting mechanism;
and S3, sequentially moving the fuel assemblies suspended 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.
Preferably, one end of the support rail serves as a fuel assembly inlet end, and the other end of the support rail serves as a fuel outlet end;
the fuel assembly inlet ends of two adjacent support rails are arranged in a staggered mode.
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 arrangement of the fuel assemblies in a reactor container is realized by matching with a supporting mechanism and a hoisting mechanism which are arranged above the fuel assemblies, the online refueling of a molten salt reactor and the fine adjustment of the axial enrichment degree of the single fuel assembly are realized, and the modular construction and the power expansion are realized.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic cross-sectional structure diagram of an on-line refueling molten salt pile according to an embodiment of the invention;
FIG. 2 is a top view of a fuel assembly on a support mechanism in an online refueling molten salt reactor according to an embodiment of the invention.
Detailed Description
For a more clear understanding of the technical features, objects and effects of the present invention, embodiments of the present invention will now be described in detail with reference to the accompanying drawings.
As shown in fig. 1, the online refueling molten salt reactor according to an embodiment of the present invention includes a sealed protection container 10, a reactor container 20 disposed in the protection container 10, a core disposed in the reactor container 20, a support mechanism 30 disposed in the protection container 10, and a hoisting mechanism 40.
The reactor vessel 20 is contained by the protective vessel 10 and is located in a reactor plant capable of withstanding low pressures (positive and negative); an air filtering and purifying device is arranged in the plant to collect radioactive nuclides such as fission gas and the like. The primary loop is located in a reactor vessel (pool stack) 20.
The coolant is contained within the reactor vessel 20 and submerges 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 spheres (isotropically clad fuel) 52 housed within the fuel grid 51.
In the invention, the fuel grid 51 can be a hollow or net-shaped cylinder structure, the fuel grid 51 is vertically arranged in the reactor vessel 20, the TRISO fuel spheres 52 are accommodated in the fuel grid 51 along the height of the fuel grid and immersed in the coolant, and the heat of the TRISO fuel spheres 52 is taken away through the flow of the coolant. The diameter of the TRISO fuel spheres 52 is set so that the TRISO fuel spheres 52 form a single row or a plurality of rows in the height direction of the fuel grid 51.
The coolant can be molten salt coolant, and can also be selected from liquid metal coolant such as metal lead base, sodium and the like 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, a plurality of fuel assemblies 50 arranged along the length of the support rails 31, fuel grids 51 of the fuel assemblies 50 vertically immersed in coolant, and TRISO fuel spheres 52 contained in the fuel grids 51 also immersed in the coolant. The top of the fuel grid 51 is exposed to the coolant and is suspended from the support rails 31.
A snap assembly, a dowel assembly, a concave-convex structure, or the like may be disposed between the top of the fuel grate 51 and the support rail 31, so that the top of the fuel grate 51 is positioned on the support rail 31 and is not easily displaced.
A square core may be formed by arranging a plurality of fuel assemblies 50 in groups and suspending them on a plurality of support rails 31. Each fuel assembly 50 can adjust the height accommodation of the TRISO fuel spheres 52 before loading as required, thereby adjusting the fuel enrichment at different heights to adjust the core power distribution.
In addition, the TRISO fuel sphere 52 can retain fission gas and the like, the molten salt coolant can retain fission products which can be released, a reactor factory is a micro negative pressure containing body, and a ventilation system removes radioactive gases which can exist.
In this embodiment, referring to fig. 1 and 2, the support rail 31 includes at least two transverse rails 311 arranged in parallel and spaced apart from each other; the top of the fuel grate 51 fits and is positioned on the cross rail 311. The general outer circumference size of the fuel grid 51 is smaller than the interval between two horizontally adjacent cross rods 311, so that the lifting and the material changing movement are convenient; the top of the fuel grate 51 is then positioned over the two rails 311.
To further secure the fuel assemblies 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.
The lifting mechanism 40 is located above the support mechanism 30 within the containment vessel 10 for lifting the fuel assemblies 50 and moving the fuel assemblies 50 laterally along the support rails 31.
Alternatively, in the present embodiment, the hoisting mechanism 40 includes at least one beam 41 located above the supporting mechanism 30, and a hoisting member 42 arranged on the beam 41 in a liftable manner. The lifting element 42 is adapted to engage the top of the fuel grate 51 to lift or lower the fuel assembly 50. The lifting member 42 may be a hook or other structure, and may be specifically configured to fit on the top of the fuel grate 51.
The online refueling molten salt reactor further comprises a remote control terminal (not shown) for controlling the hoisting mechanism 40 to start and stop.
Further, the on-line refuelable molten salt stack of the present invention further comprises 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 (the medium on the secondary side may be molten salt, water, carbon dioxide, or the like) passing through the heat exchanger 60, and then returns to the reactor vessel 20 and the core from an outlet at the lower end of the heat exchanger 60 to form a coolant circulation loop (as shown by an arrow in fig. 1).
Wherein the coolant flows in the coolant circulation circuit in a natural circulation manner according to a density difference caused by a temperature difference between the coolant approaching and departing the core; 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 loop, achieving a one-loop and two-loop energy exchange.
As shown in fig. 1, in this embodiment, two heat exchangers 60 are provided in 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 online refueling molten salt reactor further comprises at least one passive air cooling flow channel 70 arranged in the surrounding wall of the protection container 10, and the outer wall surface of the protection container 10 is provided with an air inlet (not shown) and an air outlet (not shown) which are respectively communicated with the passive air cooling flow channel 70. The air enters the passive air cooling flow channel 70 from the air inlet, flows along the passive air cooling flow channel 70, absorbs heat, is heated, and is discharged out of the passive air cooling flow channel 70 from the air outlet.
In this embodiment, the passive air cooling flow passage 70 is bent in the surrounding wall of the protective container 10 to form an input flow passage 71 and an output flow passage 72 that are connected, and the output flow passage 72 is closer to the inner wall surface of the protective container 10 than the input flow passage 71 or is parallel to the inner wall surface. 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 channel 70 extends in the surrounding wall of the protective container 10 by bending for multiple times, and may extend in multiple times along the horizontal direction or the vertical direction. The air inlet and the 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 channel 70 are arranged, and the post-accident heat is led out to the final heat sink-atmosphere by utilizing the high-temperature characteristic of the coolant after shutdown and utilizing passive cooling such as thermal radiation, convective heat transfer (large-surface-area thin fins for enhanced heat exchange) and the like.
In addition, the outer wall of the reactor vessel 20 may be provided with heat dissipation fins to enhance the heat dissipation effect and realize enhanced heat dissipation. The heat sink fins are preferably fins having a large surface area.
Referring to fig. 1 and 2, the refueling method of the online refueling molten salt pile can comprise the following steps:
s1, after the fuel assembly 50 forms the spent fuel assembly, the hoisting mechanism 40 hoists the spent fuel assembly to separate the top of the fuel grid 51 from the support rail 31.
S2, the hoisting mechanism 40 moves the hoisted 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 hung on the support rail 31, fills the positions of the spent fuel assemblies, and loads new fuel assemblies 50 from the other end of the support rail 31.
One end of the support rail 31 serves as a fuel assembly inlet end, and the other end serves as a fuel outlet end. The spent fuel assemblies are moved to the fuel discharge end of the support rail 31, out of the core. A 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 arranged in a staggered mode, and better core power flattening is achieved by utilizing different fuel enrichment degrees in the horizontal direction and the vertical direction.
In the core, in a plurality of rows of fuel assemblies formed by arranging a plurality of support rails 31, each row of fuel assemblies is loaded with a new fuel assembly 50 from one end of the support rail 31, a spent fuel assembly is taken out from the opposite end, and the old fuel assembly 50 is moved to the spent fuel assembly side in sequence, and the fuel assemblies 50 can be moved to adjacent positions only by slightly lifting the fuel assemblies 50 through 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 periphery of the reactor vessel 20 for storage until the decay heat is reduced to a certain value, and then moved to an intermediate storage facility. A fresh batch of fuel assemblies (maintained at a sufficient distance from the core to ensure minimal fission reactions) is pre-stored in the reactor vessel 20 to support intermittent refueling without stopping the reactor, meeting long refueling cycle requirements.
The above description is only an embodiment of the present invention, and not intended to limit the scope of the present invention, and all modifications of equivalent structures and equivalent processes performed by the present specification and drawings, or directly or indirectly applied to other related technical fields, are included in the scope of the present invention.

Claims (13)

1. The online refueling molten salt reactor is characterized by comprising a closed protective container, a reactor container arranged in the protective container, a reactor core arranged in the reactor container, a supporting mechanism and a hoisting mechanism arranged in the protective container;
the support mechanism comprises a plurality of support rails which are spaced in parallel and span above the reactor vessel; the core comprises a plurality of fuel assemblies arranged along the length direction of the support rail, each fuel assembly comprises a fuel grid vertically immersed in coolant, a TRISO fuel ball accommodated therein along the height of the fuel grid and immersed in the coolant; the top of the fuel grid is exposed to the coolant and hung on the support rail;
the hoisting mechanism is positioned above the supporting mechanism and used for hoisting the fuel assembly and transversely moving the fuel assembly along the supporting rail.
2. The on-line refuelable molten salt stack of claim 1, wherein the TRISO fuel spheres form a single or multiple rows in the fuel grid.
3. The on-line refuelable molten salt stack of claim 1, wherein a support structure is provided within the reactor vessel that is supported at the bottom of the fuel grid.
4. The on-line refuelable molten salt stack of claim 1, wherein the support rails comprise at least two transverse rails arranged in parallel and spaced apart; the top of the fuel grid fits over at least two of the cross rails.
5. The molten salt reactor capable of being reloaded online as claimed in claim 1, wherein the hoisting mechanism comprises at least one cross beam located above the supporting mechanism and a hoisting piece arranged on the cross beam in a lifting manner.
6. The on-line refuelable molten salt stack 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 to form a coolant circulation loop.
7. The on-line refuelable molten salt reactor of claim 6, wherein coolant naturally circulates between the heat exchanger and the core along a coolant circulation loop under the effect of density differences caused by temperature differences; alternatively, a circulating pump is arranged at the inlet of the heat exchanger, and the coolant is driven to flow in the coolant circulating loop in a forced circulation mode.
8. The on-line refuelable molten salt reactor according to claim 1, further comprising at least one passive air cooling flow channel arranged in the surrounding wall of the protection container, wherein the outer wall surface of the protection container is provided with an air inlet and an air outlet which are respectively communicated with the passive air cooling flow channel.
9. The on-line refueling molten salt reactor according to claim 8, wherein the passive air cooling flow channel is bent in a surrounding wall of the protection container to form an input flow channel and an output flow channel which are connected, and the output flow channel is closer to the inner wall surface of the protection container than the input flow channel or is parallel to the inner wall surface at equal distance and is bent for multiple times;
the air inlet is communicated with the input flow channel, and the air outlet is communicated with the output flow channel.
10. The on-line refuelable molten salt stack of claim 8, wherein the passive air cooling flow channel extends in a plurality of bends within a surrounding wall of the protection vessel.
11. The on-line refuelable molten salt stack of any one of claims 1 to 10, wherein the reactor vessel outer wall is provided with heat dissipating fins.
12. A method for refueling a molten salt pile capable of being recharged online as claimed in any one of claims 1 to 11, comprising the steps of:
s1, after the fuel assembly forms a spent fuel assembly, the hoisting mechanism hoists the spent fuel assembly to separate the top of the fuel grid from the support rail;
s2, moving the lifted spent fuel assembly to one end of the support rail along the support rail by a hoisting mechanism;
and S3, sequentially moving the fuel assemblies suspended 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.
13. The method for refueling a molten salt reactor capable of being refueled online as claimed in claim 12, wherein one end of the support rail serves as a fuel assembly inlet end, and the opposite end serves as a fuel outlet end;
the fuel assembly inlet ends of two adjacent support rails are arranged in a staggered mode.
CN202011403541.0A 2020-12-04 2020-12-04 Molten salt pile capable of changing materials online and material changing method thereof Pending CN112635083A (en)

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CN202011403541.0A CN112635083A (en) 2020-12-04 2020-12-04 Molten salt pile capable of changing materials online 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

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Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
CN113689963A (en) * 2021-08-30 2021-11-23 西安交通大学 Multipurpose heat transport system for small-sized villiaumite cooling high-temperature reactor
WO2022116614A1 (en) * 2020-12-04 2022-06-09 中广核工程有限公司 Molten salt reactor capable of realizing online refueling, and refueling method thereof

Citations (13)

* Cited by examiner, † Cited by third party
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)

* Cited by examiner, † Cited by third party
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
EA039692B8 (en) * 2016-11-15 2022-03-21 ТерраПауэр, ЭлЭлСи Thermal management of molten fuel
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
CN112635083A (en) * 2020-12-04 2021-04-09 中广核工程有限公司 Molten salt pile capable of changing materials online and material changing method thereof

Patent Citations (14)

* Cited by examiner, † Cited by third party
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 (1)

* Cited by examiner, † Cited by third party
Title
赵晶: "氟盐冷却高温堆在主要事故工况下对RVACS散热能力的需求", 中国优秀硕士学位论文全文数据库 工程科技II辑, no. 7, pages 220 *

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2022116614A1 (en) * 2020-12-04 2022-06-09 中广核工程有限公司 Molten salt reactor capable of realizing online refueling, and refueling 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
CN113689963A (en) * 2021-08-30 2021-11-23 西安交通大学 Multipurpose heat transport system for small-sized villiaumite cooling high-temperature reactor

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