CN114883019A - High-temperature gas cooled reactor fuel loading and unloading system and method - Google Patents

High-temperature gas cooled reactor fuel loading and unloading system and method Download PDF

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Publication number
CN114883019A
CN114883019A CN202210561353.3A CN202210561353A CN114883019A CN 114883019 A CN114883019 A CN 114883019A CN 202210561353 A CN202210561353 A CN 202210561353A CN 114883019 A CN114883019 A CN 114883019A
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China
Prior art keywords
fuel
pressure vessel
temperature gas
fuel transfer
ball
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CN202210561353.3A
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Chinese (zh)
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吴郁龙
石琦
孙运轮
金东杰
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CHINERGY CO LTD
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CHINERGY CO LTD
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Priority to CN202210561353.3A priority Critical patent/CN114883019A/en
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/19Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/20Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • 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

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a high-temperature gas-cooled reactor fuel loading and unloading system which comprises a reactor pressure vessel, wherein an outlet of a discharge pipe of the reactor pressure vessel is communicated with an inlet of a first broken ball sorting device, a broken ball outlet of the first broken ball sorting device is communicated with a first broken ball tank, a non-broken ball outlet is communicated with a circulating fuel transfer tank, and the circulating fuel transfer tank is conveyed to a feed inlet of the reactor pressure vessel through a vertical conveying mechanism. The high-temperature gas cooled reactor fuel loading and unloading system avoids high-speed impact in the fuel ball lifting process, the fuel ball lifting operation is reliable, the lifting speed is adjustable, the broken ball amount is reduced, and the device is simple in structure. The invention also discloses a high-temperature gas cooled reactor fuel loading and unloading method.

Description

High-temperature gas cooled reactor fuel loading and unloading system and method
Technical Field
The invention relates to the technical field of nuclear fuel loading and unloading, in particular to a high-temperature gas cooled reactor fuel loading and unloading system and method.
Background
The pebble-bed high-temperature gas-cooled reactor adopts spherical fuel elements with the diameter of 60mm as fuel of the reactor. The spherical fuel elements are all ceramic coated granular spherical fuel elements. The thermal power of a single reactor in the high-temperature gas cooled reactor demonstration project is 250MW, 42 ten thousand spherical fuel elements are arranged in the reactor, the circulation frequency of the spherical fuel elements in the reactor is 15 times, and the circulation power is compressed helium.
Spherical fuel elements (fuel spheres for short) are discharged from the lower part of the reactor core through a discharging device, the fuel spheres reaching burn-up are conveyed to a spent fuel tank, the fuel spheres which do not reach burn-up are lifted to the top of the reactor core again to enter the reactor core, and the nuclear reaction is continued. Fresh fuel also enters the core from the top of the core through the lifting device. The high-temperature gas cooled reactor demonstration project adopts helium to lift fuel balls in a lifting pipeline, the fuel balls are lifted in the lifting pipeline by virtue of helium gas, the lifting process is influenced by helium gas characteristics, the lifting speed is limited to a certain extent, and when the speed is too high, vibration can be generated to influence lifting or damage the fuel balls, so that the ball crushing amount is increased.
Disclosure of Invention
In view of this, the invention provides a fuel handling system for a high temperature gas cooled reactor, which avoids high-speed impact during fuel ball lifting, and has the advantages of reliable fuel ball lifting operation, adjustable lifting speed, reduced ball breaking amount and simple device structure.
The invention also provides a fuel loading and unloading method of the high-temperature gas cooled reactor.
In order to achieve the purpose, the invention provides the following technical scheme:
the high-temperature gas cooled reactor fuel loading and unloading system comprises a reactor pressure vessel, wherein the outlet of a discharge pipe of the reactor pressure vessel is communicated with the inlet of a first broken ball sorting device, the broken ball outlet of the first broken ball sorting device is communicated with a first broken ball tank, the non-broken ball outlet is communicated with a circulating fuel transfer tank, and the circulating fuel transfer tank is conveyed to the feed inlet of the reactor pressure vessel through a vertical conveying mechanism.
Optionally, still include the fuel transfer well, be provided with in the fuel transfer well the perpendicular transport mechanism, the fuel transfer well bottom entry with be provided with first horizontal transport mechanism between the non-pellet outlet, the well head of fuel transfer well with be provided with second horizontal transport mechanism between the feed inlet of reactor pressure vessel.
Optionally, the non-broken ball outlet is communicated with an inlet of a burnup measurer, a first outlet of the burnup measurer is communicated with the circulating fuel transfer tank, and a second outlet of the burnup measurer is communicated with the spent fuel transfer tank.
Optionally, the vertical transportation mechanism comprises a crane arranged at the top end of the fuel transfer well, a hoisting end of the crane is connected with a steel wire rope, the steel wire rope is vertically arranged in the fuel transfer well, and one end of the steel wire rope, far away from the crane, is used for being connected with the circulating fuel transfer tank.
Optionally, a suction pump is arranged at the feed inlet of the reactor pressure vessel, one end of the suction pump is communicated with the ball outlet of the circulating fuel transfer tank through a ball inlet pipeline, and the other end of the suction pump is communicated with the feed inlet of the reactor pressure vessel through a ball outlet pipeline.
Optionally, a charging device is arranged at the position of the feed inlet of the reactor pressure vessel, an inlet end of the charging device is communicated with the ball outlet pipeline of the suction pump, one outlet of the charging device is communicated with the second ball crushing tank, and the other outlet of the charging device is communicated with the feed inlet of the reactor pressure vessel.
Optionally, a first isolation valve is arranged on a pipeline communicated with the second ball crushing tank, a second isolation valve is arranged on a communication pipeline communicated with a feed inlet of the reactor pressure vessel, and a third isolation valve is arranged at the feed inlet of the charging device.
Optionally, the feed ports of the reactor pressure vessel include a fresh fuel fill port and a recycled fuel fill port, the recycled fuel fill port being in communication with the recycled fuel transfer tank.
According to the technical scheme, the high-temperature gas cooled reactor fuel loading and unloading system provided by the invention has the advantages that the screened whole spheres are contained in the circulating fuel transfer tank, and the circulating fuel transfer tank is conveyed to the feed inlet of the reactor pressure vessel through the vertical conveying mechanism, so that the fuel spheres contained in the circulating fuel transfer tank are recycled. According to the invention, the circulating fuel transfer tank is lifted by adopting the vertical transportation mechanism, so that the lifting of the recycled fuel balls is realized, and compared with the transportation mode of lifting the fuel balls in a lifting pipeline by adopting helium gas in the prior art, the high-speed impact in the lifting process of the fuel balls is avoided, so that the damage caused by extrusion or collision in the lifting process of the fuel balls is avoided, the fuel balls are reliably lifted and run, the lifting speed is adjustable, the ball breaking amount is reduced, the device structure is simple, and the cost is lower.
The invention also provides a high-temperature gas cooled reactor fuel loading and unloading method, which uses the high-temperature gas cooled reactor fuel loading and unloading system, the fuel balls which are sorted by the first ball sorting device and can be recycled are contained in the circulating fuel transfer tank and are conveyed to the feed inlet of the reactor pressure vessel by the vertical conveying mechanism for recycling.
Optionally, the circulating fuel transfer tank is lifted via a fuel transfer well.
The fuel loading and unloading method of the high temperature gas cooled reactor of the invention uses the fuel loading and unloading system of the high temperature gas cooled reactor, thus having the advantages of the system and not being repeated herein.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the drawings without creative efforts.
FIG. 1 is a schematic structural diagram of a high temperature gas cooled reactor fuel handling system according to an embodiment of the present invention;
fig. 2 is a schematic structural diagram of a vertical transportation mechanism according to an embodiment of the present invention.
Wherein:
1. the reactor comprises a reactor pressure vessel, 2, a first broken ball sorting device, 3, a first broken ball tank, 4, a burnup measurer, 5, a fourth isolation valve, 6, a spent fuel transfer tank, 7, a circulating fuel transfer tank, 8, a fuel transfer well, 9, a crane, 10, a fuel suction device, 11, a charging device, 12, a fifth isolation valve, 13, a third isolation valve, 14, a first isolation valve, 15, a second broken ball tank, 16, a new fuel charging port, 17, a circulating fuel charging port, 18 and a second isolation valve.
Detailed Description
The invention discloses a fuel loading and unloading system of a high-temperature gas cooled reactor, which avoids high-speed impact in the fuel ball lifting process, ensures reliable lifting operation of fuel balls, is adjustable in lifting speed, reduces the ball breaking amount and has a simple device structure.
The invention also provides a fuel loading and unloading method of the high-temperature gas cooled reactor.
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
Referring to fig. 1 and 2, the high temperature gas cooled reactor fuel handling system of the present invention includes a reactor pressure vessel 1, an outlet of a discharge pipe of the reactor pressure vessel 1 is communicated with an inlet of a first broken ball sorting device 2, the first broken ball sorting device 2 includes two outlets, specifically, a broken ball outlet and a non-broken ball outlet, the broken ball outlet is communicated with a first broken ball tank 3, the non-broken ball outlet is communicated with a circulating fuel transfer tank 7, and the circulating fuel transfer tank 7 is conveyed to a feed inlet of the reactor pressure vessel 1 through a vertical conveying mechanism.
Wherein, the reactor pressure vessel 1 is filled with 42 ten thousand spherical fuels, and the first broken ball sorting device 2 is used for sorting the broken balls discharged from the reactor pressure vessel 1. First garrulous ball jar 3 is used for the garrulous ball that first garrulous ball sorting unit 2 of splendid attire were screened, and circulation fuel transports jar 7 is used for the whole ball that first garrulous ball sorting unit 2 of splendid attire were screened. The first crushed ball sorting apparatus 2 is a crushed ball sorting apparatus commonly used in the prior art, and is not limited herein.
According to the high-temperature gas cooled reactor fuel loading and unloading system, the screened whole spheres are contained in the circulating fuel transfer tank 7, and the circulating fuel transfer tank 7 is conveyed to the feed inlet of the reactor pressure vessel 1 through the vertical conveying mechanism, so that the fuel spheres contained in the circulating fuel transfer tank 7 can be recycled. According to the invention, the circulating fuel transfer tank 7 is lifted by adopting the vertical conveying mechanism, so that the lifting of the recycled fuel balls is realized, and compared with the conveying mode of lifting the fuel balls in a lifting pipeline by adopting helium gas in the prior art, the high-speed impact in the lifting process of the fuel balls is avoided, so that the damage caused by extrusion or collision in the lifting process of the fuel balls 1 is avoided, the lifting operation is reliable, the lifting speed is adjustable, the ball breaking amount is reduced, the device structure is simple, and the cost is lower.
Further, the high-temperature gas cooled reactor fuel handling system also comprises a fuel transfer well 8, wherein the vertical transportation mechanism is arranged in the fuel transfer well 8, a first horizontal transportation mechanism is arranged between a well bottom inlet of the fuel transfer well 8 and the non-broken ball outlet, and a second horizontal transportation mechanism is arranged between a well mouth of the fuel transfer well 8 and a feed inlet of the reactor pressure container 1. The vertical transportation mechanism is used for lifting a circulating fuel transfer tank 7 which is positioned at the bottom of a fuel transfer well 8 to the position of the well head of the fuel transfer well 8. The first horizontal transportation mechanism is used for transporting the circulating fuel transfer tank 7 at the position of the non-broken ball outlet to the position of a fuel transfer well 8. The second horizontal transportation mechanism is used for transporting the circulating fuel transfer tank 7 at the wellhead position of the fuel transfer well 8 to the reactor pressure vessel 1. The first horizontal transportation mechanism and the second horizontal transportation mechanism can be horizontal conveyors, and can also be other horizontal transportation devices commonly used by the technical personnel in the field.
Wherein, perpendicular transport mechanism is including setting up in the crane 9 on 8 tops of fuel transfer well, and the end of lifting by crane 9 is connected with wire rope, wire rope sets vertically in fuel transfer well 8, wire rope keeps away from the one end of crane 9 and is used for being connected with the circulating fuel transfer tank 7 that is located fuel transfer well 8. The inside residual heat is taken away by the ventilation system in the fuel carrying well 8. In order to facilitate the elimination of the sorted spent fuel balls, the non-crushed-ball outlet of the first crushed-ball sorting device 2 is communicated with the inlet of the burnup measurer 4, the first outlet of the burnup measurer 4 is communicated with the circulating fuel transfer tank 7, and the second outlet of the burnup measurer is communicated with the spent fuel transfer tank 6. The spent fuel transfer tank 6 is used for containing fuel balls for reaching the burn-up. A fourth isolation valve 5 is arranged on a pipeline for communicating the fuel consumption measurer 4 with the spent fuel transfer tank 6, and a fifth isolation valve 12 is arranged on a pipeline for communicating the fuel consumption measurer 4 with the circulating fuel transfer tank 7.
In order to facilitate the transportation of the fuel spheres in the circulating fuel transfer tank 7 to the feed inlet of the reactor pressure vessel 1, a fuel suction device 10 is arranged at the feed inlet of the reactor pressure vessel 1, and specifically, the fuel suction device 10 is a suction pump. One end of the suction pump is communicated with a ball outlet of the circulating fuel transfer tank 7 through a ball inlet pipeline, and the other end of the suction pump is communicated with a feed inlet of the reactor pressure vessel 1 through a ball outlet pipeline, so that fuel balls in the circulating fuel transfer tank 7 are conveyed to the feed inlet of the reactor pressure vessel 1.
Further, a charging device 11 is arranged at the position of the feed inlet of the reactor pressure vessel 1, the inlet end of the charging device 11 is communicated with the ball outlet pipeline of the suction pump, one outlet of the charging device 11 is communicated with the second ball crushing tank 15, and the other outlet is communicated with the feed inlet of the reactor pressure vessel 1. The charging device 11 is including setting up in the second broken ball sorting unit of ball jar and lower extreme of depositing of upper end, deposit the ball jar and be used for keeping in circulating fuel and new fuel, deposit the bottom export of ball jar with second broken ball sorting unit's entry intercommunication, the broken ball that second broken ball sorting unit divides the election gets into second broken ball jar 15, and good ball gets into reactor pressure vessel 1.
Wherein, a first isolation valve 14 is arranged on a pipeline for communicating the charging device 11 with the second ball crushing tank 15, a second isolation valve 18 is arranged on a communication pipeline for communicating the charging device 11 with the feed inlet of the reactor pressure vessel 1, and a third isolation valve 13 is arranged at the feed inlet of the charging device 11.
To accommodate different feeds, the feed ports of the reactor pressure vessel 1 include a fresh fuel feed port 16 and a recycle fuel feed port 17, the recycle fuel feed port 17 communicating with the recycle fuel transfer tank 7 for delivering recycled fuel pellets to the reactor pressure vessel 1.
Wherein, set up two fifth isolating valves 12 on the pipeline that burnup caliber 4 and empty circulating fuel transport tank 7 communicate, be convenient for carry out the atmosphere through setting up two valves and switch over empty circulating fuel transport tank 7 and partial communicating pipe, carry out the atmosphere of air helium to circulating fuel transport tank 7 and switch over. After the empty circulating fuel transfer tank 7 is installed back to the pipeline at the lower part of the burnup measurer 4, the fifth isolation valve 12 at the upper part of the pipeline is closed to avoid the influence of the vacuumizing process on the burnup measurer 4, the fifth isolation valve 12 at the lower part is opened to vacuumize the circulating fuel transfer tank 7, and then the fifth isolation valve 12 at the upper part is opened to enable the pipeline to be communicated, so that the fuel ball of the burnup measurer 4 is ensured to be in the helium atmosphere when entering the circulating fuel transfer tank 7.
The operation process of the high-temperature gas cooled reactor fuel loading and unloading system is as follows: the fuel balls enter a first broken ball sorting device 2 through a discharge pipe at the bottom end of a reactor pressure vessel 1, the sorted broken balls enter a first broken ball tank 3, and the complete fuel balls enter a burnup measurer 4 for online burnup measurement. The fuel balls reaching the burn-up enter a spent fuel transfer tank 6, and the fuel balls not reaching the burn-up enter a circulating fuel transfer tank 7. And when the spent fuel transfer tank 6 reaches the temporary storage amount of spent fuel balls, closing a fourth isolation valve 5 between the fuel consumption measurer 4 and the spent fuel transfer tank 6, releasing the pressure in the spent fuel transfer tank 6, and then transporting the spent fuel transfer tank 6 to a spent fuel warehouse through a rotating device to uniformly store the spent fuel in the nuclear power plant. And then, an empty spent fuel transfer tank 6 is installed, at the moment, two fourth isolation valves 5 between the burnup measurer 4 and the spent fuel transfer tank 6 are still in a closed state, and through the arrangement of the two fourth isolation valves 5, atmosphere switching of air and helium is performed on the spent fuel transfer tank 6 conveniently, the air atmosphere of the empty spent fuel transfer tank 6 is switched to the helium atmosphere, and the specific process refers to the operation process of switching the atmosphere by the two fifth isolation valves 12. And opening two fourth isolating valves 5 to perform online temporary storage of the spent fuel.
The fuel spheres which do not reach the burnup are detected by the burnup measurer 4 and need to return to the reactor pressure vessel 1 to continue the fission reaction, the fuel spheres which do not reach the burnup enter the circulating fuel transfer tank 7, when the circulating fuel transfer tank 7 reaches the temporary storage amount of the circulating fuel spheres, the fifth isolation valve 12 between the burnup measurer 4 and the circulating fuel transfer tank 7 is closed, the pressure in the circulating fuel transfer tank 7 is relieved and then is conveyed to the fuel transfer well 8 through the first horizontal conveying mechanism, the circulating fuel transfer well is lifted to the wellhead position by the crane 9, and then the circulating fuel transfer well is conveyed to the top cabin of the reactor pressure vessel 1 through the second horizontal conveying mechanism. The circulating fuel balls in the circulating fuel transfer tank 7 pass through the fuel suction device 10 and enter the charging device 11 from the circulating fuel charging port 17. Fresh fuel enters the charging device 11 through the fresh fuel charging port 16. When the circulating fuel or new fuel is charged into the charging device 11, the atmosphere is air atmosphere, and the second isolation valve on the pipeline connecting the charging device 11 and the reactor pressure vessel 1 is closed. When the charging device 11 is filled with fuel, the third isolation valve 13 is closed, and then the atmosphere is switched, and after the atmosphere inside the charging device 11 is switched to the helium atmosphere, the second isolation valve 18 is opened. When the charging device 11 works, single ball feeding and sorting of fuel balls are carried out, the crushed balls enter the second crushed ball tank 15, and the good balls enter the reactor pressure vessel 1, so that the circulation of fuel and the charging of new fuel are realized.
It can be understood that in the high temperature gas cooled reactor fuel handling system of the present invention, the circulating fuel transfer tank 7 communicated with the burnup measurer 4 is a tank not filled with fuel pellets, the circulating fuel transfer tank 7 located in the fuel transfer well 8 is a tank filled with fuel pellets, and the circulating fuel transfer tank 7 communicated with the fuel suction device 10 is a tank filled with fuel pellets.
The invention also provides a high-temperature gas cooled reactor fuel loading and unloading method, by using the high-temperature gas cooled reactor fuel loading and unloading system, the fuel balls which are sorted by the first broken ball sorting device 2 and can be recycled are contained in the circulating fuel transfer tank 7 and are conveyed to the feed inlet of the reactor pressure vessel 1 by the vertical conveying mechanism for recycling, so that the extrusion or collision in the lifting process of the fuel balls is avoided. Wherein the circulating fuel transfer tank 7 is lifted via a fuel transfer well 8.
According to the method for loading and unloading the fuel of the high-temperature gas cooled reactor, the circulating fuel ball is integrally lifted, so that the lifting speed of the fuel ball is ensured, and the fuel ball is prevented from being damaged by collision. Compared with the prior art that spent fuel is lifted by the gravity and the air force of a fuel ball and transferred to the spent fuel storage, the device is simple.
The fuel loading and unloading system of the high-temperature gas cooled reactor has the advantages of simple structure, controllable lifting speed of the fuel ball, wide application range, good economy and high reliability, and can be applied to the fuel loading and unloading of the ball bed module type high-temperature gas cooled reactor.
In the description of the present solution, it is to be understood that the terms "upper", "lower", "vertical", "inside", "outside", and the like indicate orientations or positional relationships based on those shown in the drawings, and are only for convenience of describing the present invention and simplifying the description, but do not indicate or imply that the referred device or element must have a specific orientation, be constructed in a specific orientation, and be operated, and thus should not be construed as limiting the present solution.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or to implicitly indicate the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of that feature. In the description of the present application, "a plurality" means two or more unless specifically limited otherwise.
The embodiments in the present description are described in a progressive manner, each embodiment focuses on differences from other embodiments, and the same and similar parts among the embodiments are referred to each other.
The previous description of the disclosed embodiments is provided to enable any person skilled in the art to make or use the present invention. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the generic principles defined herein may be applied to other embodiments without departing from the spirit or scope of the invention. Thus, the present invention is not intended to be limited to the embodiments shown herein but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.

Claims (10)

1. The high-temperature gas cooled reactor fuel loading and unloading system is characterized by comprising a reactor pressure vessel, wherein an outlet of a discharge pipe of the reactor pressure vessel is communicated with an inlet of a first broken ball sorting device, a broken ball outlet of the first broken ball sorting device is communicated with a first broken ball tank, a non-broken ball outlet is communicated with a circulating fuel transfer tank, and the circulating fuel transfer tank is conveyed to a feed inlet of the reactor pressure vessel through a vertical conveying mechanism.
2. The high temperature gas cooled reactor fuel handling system of claim 1, further comprising a fuel transfer well, wherein the vertical transportation mechanism is disposed in the fuel transfer well, a first horizontal transportation mechanism is disposed between a well bottom inlet of the fuel transfer well and the non-broken-ball outlet, and a second horizontal transportation mechanism is disposed between a well head of the fuel transfer well and the feed inlet of the reactor pressure vessel.
3. The high temperature gas cooled reactor fuel handling system of claim 1, wherein the non-pellet outlet is in communication with an inlet of a burnup measurer, a first outlet of the burnup measurer is in communication with the circulating fuel transfer tank, and a second outlet of the burnup measurer is in communication with the spent fuel transfer tank.
4. The high temperature gas cooled reactor fuel handling system of claim 2, wherein the vertical transport mechanism comprises a crane disposed at the top end of the fuel transfer well, a steel cable is connected to a hoisting end of the crane, the steel cable is vertically disposed in the fuel transfer well, and an end of the steel cable away from the crane is used for connecting with the circulating fuel transfer tank.
5. The system for loading and unloading the fuel in the high temperature gas cooled reactor according to claim 1, wherein a suction pump is arranged at the feed inlet of the reactor pressure vessel, one end of the suction pump is communicated with the ball outlet of the circulating fuel transfer tank through a ball inlet pipeline, and the other end of the suction pump is communicated with the feed inlet of the reactor pressure vessel through a ball outlet pipeline.
6. The high temperature gas cooled reactor fuel handling system of claim 5, wherein a charging device is disposed at the feed inlet of the reactor pressure vessel, an inlet end of the charging device is communicated with the ball outlet pipeline of the suction pump, one outlet of the charging device is communicated with the second ball crushing tank, and the other outlet of the charging device is communicated with the feed inlet of the reactor pressure vessel.
7. The high temperature gas cooled reactor fuel handling system of claim 6, wherein a first isolation valve is arranged on a pipeline connecting the charging device and the second ball crushing tank, a second isolation valve is arranged on a pipeline connecting the charging device and a feed inlet of the reactor pressure vessel, and a third isolation valve is arranged on a feed inlet of the charging device.
8. The high temperature gas cooled reactor fuel handling system of claim 1, wherein the feed ports of the reactor pressure vessel include a fresh fuel fill port and a recycled fuel fill port, the recycled fuel fill port being in communication with the recycled fuel transfer tank.
9. A method for loading and unloading fuel into and from a high-temperature gas-cooled reactor, which is characterized in that the system for loading and unloading fuel into and from a high-temperature gas-cooled reactor according to any one of claims 1 to 8 is used, and fuel balls which are sorted out by the first ball sorting device and can be recycled are contained in a circulating fuel transfer tank and are conveyed to a feed port of a reactor pressure vessel by a vertical conveying mechanism for recycling.
10. The method for loading and unloading the fuel into and out of the high temperature gas cooled reactor according to claim 9, wherein the circulating fuel transfer tank is lifted via a fuel transfer well.
CN202210561353.3A 2022-05-23 2022-05-23 High-temperature gas cooled reactor fuel loading and unloading system and method Pending CN114883019A (en)

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Application Number Priority Date Filing Date Title
CN202210561353.3A CN114883019A (en) 2022-05-23 2022-05-23 High-temperature gas cooled reactor fuel loading and unloading system and method

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Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115424752A (en) * 2022-09-06 2022-12-02 华能山东石岛湾核电有限公司 Spherical element single conveying device
CN116344086A (en) * 2023-03-29 2023-06-27 华能山东石岛湾核电有限公司 Reactor core feeding pipe blocking on-line treatment system and method of fuel loading and unloading system

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115424752A (en) * 2022-09-06 2022-12-02 华能山东石岛湾核电有限公司 Spherical element single conveying device
CN116344086A (en) * 2023-03-29 2023-06-27 华能山东石岛湾核电有限公司 Reactor core feeding pipe blocking on-line treatment system and method of fuel loading and unloading system
CN116344086B (en) * 2023-03-29 2024-04-19 华能山东石岛湾核电有限公司 Reactor core feeding pipe blocking on-line treatment system and method of fuel loading and unloading system

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