CN1323405C - Material changing, loading and unloading process flow for fuel assembly of straight-moving nuclear reactor - Google Patents
Material changing, loading and unloading process flow for fuel assembly of straight-moving nuclear reactor Download PDFInfo
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- CN1323405C CN1323405C CNB2004100988046A CN200410098804A CN1323405C CN 1323405 C CN1323405 C CN 1323405C CN B2004100988046 A CNB2004100988046 A CN B2004100988046A CN 200410098804 A CN200410098804 A CN 200410098804A CN 1323405 C CN1323405 C CN 1323405C
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- 239000000446 fuel Substances 0.000 title claims abstract description 65
- 238000000034 method Methods 0.000 title claims abstract description 20
- 239000000463 material Substances 0.000 title claims description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 claims abstract description 34
- 230000000712 assembly Effects 0.000 claims abstract description 27
- 238000000429 assembly Methods 0.000 claims abstract description 27
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 13
- 238000007689 inspection Methods 0.000 claims abstract description 10
- 230000032258 transport Effects 0.000 claims description 7
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 5
- 238000009924 canning Methods 0.000 claims description 2
- 238000010438 heat treatment Methods 0.000 abstract description 3
- 238000010612 desalination reaction Methods 0.000 abstract description 2
- 238000004519 manufacturing process Methods 0.000 abstract description 2
- 239000013535 sea water Substances 0.000 abstract description 2
- 230000005540 biological transmission Effects 0.000 abstract 1
- 239000000969 carrier Substances 0.000 description 1
- 239000002828 fuel tank Substances 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000002910 solid waste Substances 0.000 description 1
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- 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
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Abstract
本发明属于一种核反应堆燃料组件换料装卸,即一种直形式核反应堆燃料组件换料装卸工艺流程。它包括新燃料组件的接收、检查和贮存、堆芯换料、乏燃料组件的贮存和发送,所说的堆芯换料及乏燃料组件的贮存和发送是由数控装卸料机在设置于反应堆厂房与燃料厂房之间的磁性滑轨上行走完成的。本换料装卸工艺流程不需要进行燃料组件水下翻转,可省去水下翻转机、核燃料承载器、核燃料传输管和转运水池、乏燃料吊装用人桥吊车等专用设备,而且换料操作工艺简单、可靠安全、时间快。可直接用于核电站、核供热堆、核海水淡化厂、研究堆、核动力厂、生产堆上,可提高核反应堆换料效率、降低换料系统造价和操作人员劳动强度,提高反应堆的经济性。
The present invention belongs to a kind of nuclear reactor fuel assembly refueling loading and unloading, that is, a straight nuclear reactor fuel assembly refueling loading and unloading process. It includes the reception, inspection and storage of new fuel assemblies, core refueling, storage and delivery of spent fuel assemblies. The core refueling and storage and delivery of spent fuel assemblies are completed by a numerically controlled loading and unloading machine walking on a magnetic slide rail arranged between the reactor building and the fuel building. The refueling loading and unloading process does not require underwater turning of the fuel assembly, and can save special equipment such as underwater turning machine, nuclear fuel carrier, nuclear fuel transmission pipe and transfer pool, and man-bridge crane for spent fuel hoisting. In addition, the refueling operation process is simple, reliable, safe and fast. It can be directly used in nuclear power plants, nuclear heating reactors, nuclear seawater desalination plants, research reactors, nuclear power plants, and production reactors, and can improve the refueling efficiency of nuclear reactors, reduce the cost of the refueling system and the labor intensity of operators, and improve the economy of the reactor.
Description
技术领域technical field
本发明属于一种核反应堆燃料组件换料装卸工艺流程的改进。The invention belongs to the improvement of a nuclear reactor fuel assembly refueling loading and unloading process flow.
背景技术Background technique
我国现有的压水堆核电站,如秦山核电站和大亚湾核电站的核反应堆燃料组件换料装卸工艺均采用水下翻转工艺来实现燃料组件在核反应堆厂房与燃料厂房之间的传输。这种换料工艺及其所设的系统复杂,可靠性差,换料所用时间长,而且发生燃料组件吊装事故的概率较高,对核安全威胁很大。而田湾核电厂则无燃料厂房,新燃料组件贮存在固体废物库的上方,乏燃料组件则贮存在反应堆厂房的乏燃料水池内。燃料装卸及贮存不存在新旧燃料组件在堆厂房与燃料厂房之间的转运问题。它是采用数控装卸料机在反应堆厂房内的水池与乏燃料水池之间行走以完成燃料组件的装卸及就位。其工艺特征是绝大部分换料操作都集中在堆厂房内进行。采用这种换料操作工艺在反应堆运行时无法操作位于堆厂房内的乏燃料水池内的乏燃料组件,不利于堆厂房的温度和湿度的控制,增高堆厂房放射性剂量水平。The existing pressurized water reactor nuclear power plants in my country, such as Qinshan Nuclear Power Plant and Daya Bay Nuclear Power Plant, use the underwater turning process to realize the transfer of fuel components between the nuclear reactor building and the fuel building. This refueling process and its system are complicated, have poor reliability, take a long time for refueling, and have a high probability of fuel assembly hoisting accidents, which pose a great threat to nuclear safety. The Tianwan NPP has no fuel building, and new fuel assemblies are stored above the solid waste repository, while spent fuel assemblies are stored in the spent fuel pool of the reactor building. Fuel loading and unloading and storage do not have the problem of transshipment of old and new fuel assemblies between the stack building and the fuel building. It uses a numerically controlled loading and unloading machine to walk between the water pool in the reactor building and the spent fuel pool to complete the loading, unloading and placement of fuel assemblies. Its technological feature is that most of the refueling operations are concentrated in the reactor building. Using this refueling operation process cannot operate the spent fuel assemblies located in the spent fuel pool in the reactor building when the reactor is running, which is not conducive to the control of the temperature and humidity of the reactor building, and increases the radioactive dose level of the reactor building.
发明内容Contents of the invention
本发明的目的是提供一种换料操作工艺简单、时间快、安全可靠的直行式核反应堆燃料组件换料装卸工艺流程。The object of the present invention is to provide a refueling loading and unloading technological process for straight nuclear reactor fuel assemblies with simple refueling operation process, fast time, safety and reliability.
本发明是这样实现的:一种直行式核反应堆燃料组件换料装卸工艺流程,包括新燃料组件的接受、检查和贮存;堆芯换料;乏燃料组件的贮存和发送。其中,所说的堆芯换料及乏燃料组件的贮存和发送是由数控装卸料机在设置于反应堆厂房与燃料厂房之间的磁性滑轨上行走完成的。具体说:一种直行式核反应堆燃料组件换料装卸工艺流程,其特点是它包括:The invention is realized in the following way: a process flow for fuel assembly refueling and loading and unloading of a straight-running nuclear reactor, including acceptance, inspection and storage of new fuel assemblies; core refueling; storage and delivery of spent fuel assemblies. Wherein, the core refueling and the storage and delivery of spent fuel assemblies are completed by a numerically controlled loading and unloading machine walking on a magnetic slide rail set between the reactor building and the fuel building. Specifically: a kind of refueling loading and unloading technological process of straight nuclear reactor fuel assembly, it is characterized in that it comprises:
(1)新燃料组件的接受、检查和贮存,即含有新燃料组件的燃料运输容器被燃料厂房吊车吊运到燃料装罐池,由燃料厂房辅助吊车从罐中将新燃料组件吊运到新燃料组件检查及贮存间进行检查、贮存,在换料前将新燃料组件转运到乏燃料贮存池的指定格架位置贮存;(1) Acceptance, inspection and storage of new fuel assemblies, that is, the fuel transport container containing new fuel assemblies is hoisted by the fuel plant crane to the fuel tanking pool, and the new fuel assemblies are hoisted from the tank to the new fuel assembly pool by the auxiliary crane of the fuel plant. Check and store the fuel assembly inspection and storage room, and transfer the new fuel assembly to the designated rack position of the spent fuel storage pool before refueling;
(2)堆芯换料,在反应堆停堆时,打开反应堆厂房内的反应堆水池与堆内构件存放池之间的连接闸门,在进行换料操作前先拆除反应堆压力容器顶盖、控制棒驱动机构、部分堆内构件等,存放在堆内构件存放池,将反应堆厂房与燃料厂房之间的换料闸门打开,换料时用设置于反应堆厂房与燃料厂房之间的磁性滑轨上数控装卸料机从堆芯中抓出乏燃料组件运到乏燃料贮存池中暂存,再从乏燃料贮存池中用数控装卸料机抓取新燃料组件至反应堆水池进行装堆操作;(2) For core refueling, when the reactor is shut down, open the connecting gate between the reactor pool in the reactor building and the reactor internals storage pool, and remove the top cover of the reactor pressure vessel and the control rod drive mechanism before performing the refueling operation , some reactor internal components, etc., are stored in the reactor internal component storage pool, and the refueling gate between the reactor building and the fuel building is opened, and the material is loaded and unloaded by numerical control on the magnetic slide rail set between the reactor building and the fuel building when refueling The machine grabs the spent fuel assembly from the core and transports it to the spent fuel storage pool for temporary storage, and then uses the numerical control loading and unloading machine to grab the new fuel assembly from the spent fuel storage pool to the reactor pool for stacking operation;
(3)乏燃料组件的贮存和发送,在反应堆运行时,将反应堆厂房与燃料厂房之间的换料闸门及反应堆水池与堆内构件存放池之间的连接闸门都关闭,数控装卸料机从乏燃料贮存池中取出乏燃料组件运到燃料装罐池装罐发送。(3) For the storage and delivery of spent fuel assemblies, when the reactor is running, the refueling gate between the reactor building and the fuel building and the connecting gate between the reactor water pool and the reactor internals storage pool are closed, and the numerical control loading and unloading machine The spent fuel assemblies are taken from the fuel storage pool and transported to the fuel filling pool for canning and delivery.
采用直行式核反应堆燃料组件换料装卸工艺流程不需要进行燃料组件的水下翻转,可省去水下翻转机、核燃料承载器、核燃料传输管、核燃料转运水池、乏燃料吊装用人桥吊车等大量专用设备,不停堆也能进行乏燃料组件的贮存和发送,而且换料操作工艺简单、可靠安全、时间快。可提高核反应堆的换料效率,降低换料系统的造价和操作人员的劳动强度,提高反应堆的经济性。The refueling and loading and unloading process of the straight nuclear reactor fuel assembly does not require the underwater turning of the fuel assembly, which can save a large number of dedicated underwater turning machines, nuclear fuel carriers, nuclear fuel transfer pipes, nuclear fuel transfer pools, spent fuel hoisting bridge cranes, etc. The equipment can store and send spent fuel assemblies without stacking, and the refueling operation process is simple, reliable and safe, and the time is fast. The refueling efficiency of the nuclear reactor can be improved, the cost of the refueling system and the labor intensity of the operator can be reduced, and the economic efficiency of the reactor can be improved.
附图说明Description of drawings
图1为直行式核反应堆燃料组件换料操作工艺厂房主视图;Fig. 1 is a front view of the fuel assembly refueling operation process building of a straight-running nuclear reactor;
图2为直行式核反应堆燃料组件换料操作工艺厂房俯视图。Fig. 2 is a top view of the fuel assembly refueling operation process building of a straight-running nuclear reactor.
图中,1反应堆压力容器,2堆内构件存放池,3数显型磁性滑轨定位数控装卸料机,4乏燃料贮存池,5燃料装罐池,6磁性滑轨,7反应堆厂房,8燃料厂房,9反应堆水池,10连接闸门,11换料闸门,12新燃料检查及贮存间。In the figure, 1 reactor pressure vessel, 2 reactor internal component storage pool, 3 digital display type magnetic slide rail positioning numerical control loading and unloading machine, 4 spent fuel storage pool, 5 fuel tanking pool, 6 magnetic slide rail, 7 reactor building, 8 Fuel plant, 9 reactor pools, 10 connecting gates, 11 refueling gates, 12 new fuel inspection and storage rooms.
具体实施方式Detailed ways
如图1和图2所示,一种直行式核反应堆燃料组件换料装卸工艺流程,包括如下操作内容:As shown in Fig. 1 and Fig. 2, a process flow for refueling and loading and unloading of fuel assemblies of a straight nuclear reactor includes the following operations:
(1)有新燃料组件的燃料运输容器被130吨燃料厂房吊车吊运到燃料装罐池5;由5吨燃料厂房辅助吊车从罐中将新燃料组件吊运至新燃料检查及贮存间12进行检查及贮存;在换料前将新燃料组件转运到乏燃料贮存池4的指定格架位置贮存。(1) The fuel transport container with new fuel assemblies is hoisted by a 130-ton fuel plant crane to the fuel tank pool 5; the 5-ton fuel plant auxiliary crane lifts the new fuel assemblies from the tank to the new fuel inspection and storage room 12 Carry out inspection and storage; before refueling, transfer the new fuel assembly to the designated grid position of the spent fuel storage pool 4 for storage.
(2)反应堆停堆时,打开反应堆厂房7内的反应堆水池9与堆内构件存放池2之间的连接闸门10,在进行换料操作前先拆除反应堆压力容器1顶盖、控制棒驱动机构、部分堆内构件等,存放在堆内构件存放池2。将反应堆厂房7与燃料厂房8之间的换料闸门11打开。换料时用数控装卸料机3从堆芯中抓出乏燃料组件运到乏燃料贮存池4中暂存,再从乏燃料贮存池4中用数控装卸料机3抓取新燃料组件至反应堆水池9进行装堆操作。(2) When the reactor is shut down, open the connecting gate 10 between the reactor pool 9 in the reactor building 7 and the reactor internals storage pool 2, and remove the top cover of the reactor pressure vessel 1 and the control rod drive mechanism before performing the refueling operation , some stack internals, etc., are stored in the stack internals storage pool 2. The refueling gate 11 between the reactor building 7 and the fuel building 8 is opened. During refueling, the spent fuel assembly is grabbed from the core by the numerical control loading and unloading machine 3 and transported to the spent fuel storage pool 4 for temporary storage, and then the new fuel assembly is picked up by the numerical control loading and unloading machine 3 from the spent fuel storage pool 4 to the reactor Pool 9 carries out stacking operation.
(3)在反应堆运行时,将反应堆厂房7与乏燃料厂房9之间的换料闸门11及反应堆水池9与堆内构件存放池2之间的连接闸门10都关闭。数控装卸料机3可以在燃料厂房8的乏燃料贮存池4与燃料装罐池5之间操作,从乏燃料贮存池4中取出乏燃料组件运到燃料装罐池5装罐发送。这些操作不影响反应堆正常运行。(3) When the reactor is running, the refueling gate 11 between the reactor building 7 and the spent fuel building 9 and the connecting gate 10 between the reactor water pool 9 and the reactor internals storage pool 2 are all closed. The numerical control loading and unloading machine 3 can be operated between the spent fuel storage pool 4 and the fuel filling pool 5 of the fuel plant 8, and the spent fuel assemblies are taken out from the spent fuel storage pool 4 and transported to the fuel filling pool 5 for filling and sending. These operations do not affect the normal operation of the reactor.
上述操作均在电视监视下进行。All the above operations were carried out under TV monitoring.
本发明所提供的直行式核反应堆燃料组件换料装卸工艺流程可直接应用于核电站、核供热堆、核供热海水淡化厂、研究堆、核动力厂、生产堆上。可提高核反应堆换料效率,降低换料系统造价、降低操作人员劳工强度,提高反应堆的经济性。The refueling and loading and unloading process flow of the direct-running nuclear reactor fuel assembly provided by the present invention can be directly applied to nuclear power plants, nuclear heating reactors, nuclear heating seawater desalination plants, research reactors, nuclear power plants, and production reactors. The refueling efficiency of the nuclear reactor can be improved, the cost of the refueling system can be reduced, the labor intensity of operators can be reduced, and the economy of the reactor can be improved.
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| CNB2004100988046A CN1323405C (en) | 2004-12-16 | 2004-12-16 | Material changing, loading and unloading process flow for fuel assembly of straight-moving nuclear reactor |
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| CNB2004100988046A CN1323405C (en) | 2004-12-16 | 2004-12-16 | Material changing, loading and unloading process flow for fuel assembly of straight-moving nuclear reactor |
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| CN113284639A (en) * | 2020-12-31 | 2021-08-20 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Refueling system of multi-box transfer mode of marine nuclear power platform |
| CN115417183B (en) * | 2022-09-19 | 2025-02-25 | 中广核工程有限公司 | Spent fuel transport plant layout structure and spent fuel transport container hoisting method |
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| CN1112718A (en) * | 1994-05-05 | 1995-11-29 | 法玛通公司 | Fuelling machine for fuel assemblies for the core of a nuclear reactor, having removable guide beams |
| CN1261715A (en) * | 1999-01-18 | 2000-08-02 | 法玛通公司 | Loading device and method for hoisting nuclear reactor core |
| CN1264129A (en) * | 1999-02-12 | 2000-08-23 | Abb燃烧工程核力公司 | Dismountable waste fuel loader-unloader track |
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| CN1790552A (en) | 2006-06-21 |
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