CN1790552A - Fuel assembly changing, loading and unloading process for straight-moving nuclear reactor - Google Patents
Fuel assembly changing, loading and unloading process for straight-moving nuclear reactor Download PDFInfo
- Publication number
- CN1790552A CN1790552A CNA2004100988046A CN200410098804A CN1790552A CN 1790552 A CN1790552 A CN 1790552A CN A2004100988046 A CNA2004100988046 A CN A2004100988046A CN 200410098804 A CN200410098804 A CN 200410098804A CN 1790552 A CN1790552 A CN 1790552A
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- fuel
- nuclear
- reactor
- refueling
- loading
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- 239000000446 fuel Substances 0.000 title claims abstract description 56
- 238000000034 method Methods 0.000 title claims abstract description 15
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 16
- 230000005540 biological transmission Effects 0.000 claims abstract description 6
- 238000007689 inspection Methods 0.000 claims description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract description 8
- 238000004519 manufacturing process Methods 0.000 abstract description 3
- 238000011160 research Methods 0.000 abstract description 2
- 239000013535 sea water Substances 0.000 abstract description 2
- 238000012546 transfer Methods 0.000 abstract description 2
- 230000000712 assembly Effects 0.000 abstract 3
- 238000000429 assembly Methods 0.000 abstract 3
- 238000010612 desalination reaction Methods 0.000 abstract 1
- 238000011017 operating method Methods 0.000 description 5
- 238000005516 engineering process Methods 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 4
- 239000012141 concentrate Substances 0.000 description 1
- 238000011033 desalting Methods 0.000 description 1
- 230000007246 mechanism Effects 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
Classifications
-
- 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
- Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention belongs to an improvement of a fuel assembly refueling, loading and unloading process of a nuclear reactor, and discloses a straight-moving type fuel assembly refueling, loading and unloading process of the nuclear reactor. The method comprises the steps of receiving, checking and storing new fuel assemblies, exchanging reactor cores and storing and sending spent fuel assemblies, wherein the exchanging reactor cores and the storing and sending of the spent fuel assemblies are completed by a numerical control loading and unloading machine walking on magnetic slide rails arranged between a reactor plant and a fuel plant. The refueling loading and unloading process does not need underwater overturning of the fuel assembly, can save special equipment such as an underwater overturning machine, a nuclear fuel loader, a nuclear fuel transmission pipe, a transfer pool, a man-bridge crane for hoisting spent fuel and the like, and is simple, reliable, safe and quick in refueling operation process. The system can be directly used in nuclear power stations, nuclear heat supply reactors, nuclear seawater desalination plants, research reactors, nuclear power plants and production reactors, and can improve the refueling efficiency of nuclear reactors, reduce the manufacturing cost of refueling systems and the labor intensity of operators and improve the economy of reactors.
Description
Technical field
The invention belongs to a kind of improvement of nuclear reactor fuel assembly refueling, loading and unloading technique.
Background technology
The existing pressurized-water reactor nuclear power plant of China all adopts the technology of overturning to realize the transmission of fuel assembly between nuclear reactor factory building and fuel factory building under water as the nuclear reactor fuel assembly refueling, loading and unloading technique of Qinshan nuclear power plant and Daya Bay nuclear power plant.This technology and the set system complex thereof of reloading, poor reliability, the used time of reloading is long, and the probability of generation fuel assembly lifting accident is higher, threatens very big to nuclear safety.Gulf, field nuclear power plant does not then have the fuel factory building, and novel fuel assembly is stored in the top in solid waste storehouse, and irradiated fuel assembly then is stored in the spentnuclear fuel pond of reactor building.There is not the transshipment problem of new and old fuel assembly between heap factory building and fuel factory building in fuel handling and storage.It is to adopt to walk between the heap pond of numerical control fuel manipulator crane in reactor building and the spentnuclear fuel pond with the loading and unloading of finishing fuel assembly and in place.Its technology characteristics is that the overwhelming majority operation of reloading all concentrates on heap and carries out in the factory building.Adopt this operating procedure that reloads when reactor operation, can't operate to be positioned at the irradiated fuel assembly in the spentnuclear fuel pond of heap factory building, be unfavorable for piling the control of the temperature and humidity of factory building, increase heap factory building radioactive dosage level.
Summary of the invention:
The purpose of this invention is to provide the straight nuclear reactor fuel assembly refueling, loading and unloading technique that a kind of operating procedure that reloads is simple, the time is fast, safe and reliable.
The present invention is achieved in that a kind of straight nuclear reactor fuel assembly refueling, loading and unloading technique, it comprises reception, inspection and the storage of novel fuel assembly, the storage of reactor reloading pattern, irradiated fuel assembly and transmission, wherein, the storage of said reactor reloading pattern and irradiated fuel assembly and transmission are that magnetic slide rail between reactor building and the fuel factory building is up to be walked to finish being arranged at by the numerical control fuel manipulator crane.
Adopt straight nuclear reactor fuel assembly refueling, loading and unloading technique not need to carry out the upset under water of fuel assembly, can save a large amount of specialized equipments such as tipper, nuclear fuel carrier, nuclear fuel transfer tube, nuclear fuel transhipment pond, spentnuclear fuel lifting personnel selection bridge crane car under water, and the operating procedure that reloads is simple, reliable and secure, the time is fast.Can improve the efficient of reloading of nuclear reactor, reduce the cost and the labor intensity of operating personnel of refuelling system, improve the economy of reactor.
Description of drawings
Fig. 1 is a straight nuclear reactor fuel assembly refueling operating procedure factory building front view;
Fig. 2 is a straight nuclear reactor fuel assembly refueling operating procedure factory building vertical view.
Among the figure, 1 reactor pressure vessel, 2 in-pile components are deposited the pond, 3 digital display magnetic slide rail positioning numerical control fuel manipulator cranes, 4 irradiated fuel store ponds, 5 fuel tinning ponds, 6 magnetic slide rails, 7 reactor buildings, 8 fuel factory buildings, 9 reactor pits, 10 connect gate, 11 refuelling slot gates.
Embodiment
As depicted in figs. 1 and 2, a kind of straight nuclear reactor fuel assembly refueling, loading and unloading technique comprises following content of operation:
(1) the fuel transport container that contains novel fuel assembly is arrived fuel tinning pond 5 by the handling of 130 tons of fuel factory building cranes; The novel fuel assembly handling 12 is checked and stored to the fresh fuel inspection and between storing from jar by 5 tons of fuel factory building whiplines; Store the appointment screen work position that novel fuel assembly is transported to irradiated fuel store pond 4 before reloading.
(2) when the reactor shutdown, first removal reactor pressure vessel 1 top cover, control rod drive mechanisms (CRD), part in-pile component etc. leave in-pile component in and deposit pond 2 before the operation of reloading.Reactor pit 9 in refuelling slot gate 11 between reactor building 7 and the fuel factory building 8 and the reactor building 7 is opened with the gate 10 that is connected that in-pile component is deposited between the pond 2.From reactor core, grab out irradiated fuel assembly with numerical control fuel manipulator crane 3 when reloading and transport in the irradiated fuel store pond 4 temporaryly, from irradiated fuel store pond 4, adorn heap operation again with numerical control fuel manipulator crane 3 extracting novel fuel assembly to reactor pits 9.
(3) when reactor operation, reactor building 7 is all closed with the gate 10 that is connected that in-pile component is deposited between the pond 2 with refuelling slot gate 11 and reactor pit 9 between the spentnuclear fuel factory building 8.Numerical control fuel manipulator crane 3 can operation between the irradiated fuel store pond 4 of fuel factory building 8 and fuel tinning pond 5, takes out irradiated fuel assembly and transport to 5 tinnings of fuel tinning pond and send from irradiated fuel store pond 4.These operations do not influence normal reactor operation.
Aforesaid operations all carries out under TV monitoring and controlling.
Straight nuclear reactor fuel assembly refueling, loading and unloading technique provided by the present invention can directly apply on nuclear power station, nuclear heat supplying pile, nuclear heat supply seawater desalting plant, research reactor, nuclear power plant, the production heap.Can improve the nuclear reactor efficient of reloading, reduce the refuelling system cost, reduce labor intensity of operating staff, improve the economy of reactor.
Claims (1)
1. straight nuclear reactor fuel assembly refueling, loading and unloading technique, it comprises reception, inspection and the storage of novel fuel assembly, reactor reloading pattern, the storage of irradiated fuel assembly and transmission is characterized in that: the storage of said reactor reloading pattern and irradiated fuel assembly and transmission are that magnetic slide rail between reactor building and the fuel factory building is up to be walked to finish being arranged at by the numerical control fuel manipulator crane.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNB2004100988046A CN1323405C (en) | 2004-12-16 | 2004-12-16 | Material changing, loading and unloading process flow for fuel assembly of straight-moving nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNB2004100988046A CN1323405C (en) | 2004-12-16 | 2004-12-16 | Material changing, loading and unloading process flow for fuel assembly of straight-moving nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN1790552A true CN1790552A (en) | 2006-06-21 |
| CN1323405C CN1323405C (en) | 2007-06-27 |
Family
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CNB2004100988046A Active CN1323405C (en) | 2004-12-16 | 2004-12-16 | Material changing, loading and unloading process flow for fuel assembly of straight-moving nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN1323405C (en) |
Cited By (20)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102332315A (en) * | 2007-09-26 | 2012-01-25 | 大亚湾核电运营管理有限责任公司 | Refueling method for fuel assemblies of reactor core of PWR (pressurized water reactor) nuclear power plant |
| CN102509567A (en) * | 2011-11-15 | 2012-06-20 | 广东核电合营有限公司 | Process method and lifting gripping apparatus both for jam control rod of nuclear power station reactor |
| CN102568633A (en) * | 2010-12-23 | 2012-07-11 | 中国核动力研究设计院 | Dry-type hoisting method for fuel-lacking assembly |
| CN103489488A (en) * | 2012-06-11 | 2014-01-01 | 中国核动力研究设计院 | Module type pressurized water reactor |
| CN104272399A (en) * | 2012-05-02 | 2015-01-07 | 西屋电气有限责任公司 | A method of refueling a nuclear reactor |
| CN104347129A (en) * | 2013-07-31 | 2015-02-11 | 中科华核电技术研究院有限公司 | Fuel assembly loading and unloading method of pressurized water reactor nuclear power station |
| CN105679386A (en) * | 2016-03-25 | 2016-06-15 | 上海核工程研究设计院 | Refueling device outside nuclear power containment |
| CN102509567B (en) * | 2011-11-15 | 2016-12-14 | 广东核电合营有限公司 | The bite control rod processing method of nuclear power plant reactor and bite control rod lifting grab |
| CN106531253A (en) * | 2016-11-25 | 2017-03-22 | 福建福清核电有限公司 | Online appearance inspection method for fuel |
| CN106683725A (en) * | 2017-01-05 | 2017-05-17 | 中广核研究院有限公司 | Device for fuel transfer and corresponding nuclear power platform |
| CN106910541A (en) * | 2017-03-30 | 2017-06-30 | 上海核工程研究设计院 | A kind of close-coupled nuclear reaction stows technique of reloading |
| CN107833644A (en) * | 2017-09-26 | 2018-03-23 | 中国船舶重工集团公司第七〇九研究所 | The refuelling system and material-changing method of ocean nuclear power platform |
| CN108193906A (en) * | 2017-10-09 | 2018-06-22 | 中国核电工程有限公司 | A kind of nuclear island factory building arrangement |
| CN108689299A (en) * | 2018-05-22 | 2018-10-23 | 广东核电合营有限公司 | The dilatation of million kilowatt Spent Fuel Pool removes overturning technique with old screen work |
| CN109461512A (en) * | 2018-10-25 | 2019-03-12 | 清华大学天津高端装备研究院 | A kind of spentnuclear fuel central repository pond hoisting device |
| CN110246600A (en) * | 2019-07-11 | 2019-09-17 | 上海核工程研究设计院有限公司 | A kind of full underground type compact reactor refuling device |
| CN110993129A (en) * | 2019-11-28 | 2020-04-10 | 中广核研究院有限公司 | Passive cooling system and method for offshore floating nuclear power station |
| WO2020134076A1 (en) * | 2018-12-29 | 2020-07-02 | 清华大学 | Unloading temporary storage device |
| 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 |
| CN115417183A (en) * | 2022-09-19 | 2022-12-02 | 中广核工程有限公司 | Layout structure of spent fuel transportation factory building and hoisting method of spent fuel transportation container |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5369676A (en) * | 1993-08-19 | 1994-11-29 | General Electric Company | Reactor refueling mechanism |
| JPH07209479A (en) * | 1994-01-27 | 1995-08-11 | Toshiba Corp | Fuel handling device |
| FR2719697B1 (en) * | 1994-05-05 | 1996-08-02 | Framatome Sa | Loading machine for fuel assemblies at the heart of a nuclear reactor having removable guide beams. |
| FR2788628B1 (en) * | 1999-01-18 | 2001-04-06 | Framatome Sa | DEVICE AND METHOD FOR LOADING THE HEART OF A NUCLEAR REACTOR |
| US6404836B1 (en) * | 1999-02-12 | 2002-06-11 | Westinghouse Electric Company Llc | Removable spent fuel handling machine rail |
-
2004
- 2004-12-16 CN CNB2004100988046A patent/CN1323405C/en active Active
Cited By (27)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102332315B (en) * | 2007-09-26 | 2014-02-26 | 大亚湾核电运营管理有限责任公司 | Refueling method for fuel assemblies of reactor core of PWR (pressurized water reactor) nuclear power plant |
| CN102332315A (en) * | 2007-09-26 | 2012-01-25 | 大亚湾核电运营管理有限责任公司 | Refueling method for fuel assemblies of reactor core of PWR (pressurized water reactor) nuclear power plant |
| CN102568633A (en) * | 2010-12-23 | 2012-07-11 | 中国核动力研究设计院 | Dry-type hoisting method for fuel-lacking assembly |
| CN102509567B (en) * | 2011-11-15 | 2016-12-14 | 广东核电合营有限公司 | The bite control rod processing method of nuclear power plant reactor and bite control rod lifting grab |
| CN102509567A (en) * | 2011-11-15 | 2012-06-20 | 广东核电合营有限公司 | Process method and lifting gripping apparatus both for jam control rod of nuclear power station reactor |
| US10014083B2 (en) | 2012-05-02 | 2018-07-03 | Westinghouse Electric Company Llc | Method of refueling a nuclear reactor |
| CN104272399A (en) * | 2012-05-02 | 2015-01-07 | 西屋电气有限责任公司 | A method of refueling a nuclear reactor |
| CN103489488A (en) * | 2012-06-11 | 2014-01-01 | 中国核动力研究设计院 | Module type pressurized water reactor |
| CN103489488B (en) * | 2012-06-11 | 2016-04-13 | 中国核动力研究设计院 | Modular presurized water reactor |
| CN104347129B (en) * | 2013-07-31 | 2017-03-29 | 中广核研究院有限公司 | The fuel assembly handling method of pressurized-water reactor nuclear power plant |
| CN104347129A (en) * | 2013-07-31 | 2015-02-11 | 中科华核电技术研究院有限公司 | Fuel assembly loading and unloading method of pressurized water reactor nuclear power station |
| CN105679386A (en) * | 2016-03-25 | 2016-06-15 | 上海核工程研究设计院 | Refueling device outside nuclear power containment |
| CN106531253A (en) * | 2016-11-25 | 2017-03-22 | 福建福清核电有限公司 | Online appearance inspection method for fuel |
| CN106683725A (en) * | 2017-01-05 | 2017-05-17 | 中广核研究院有限公司 | Device for fuel transfer and corresponding nuclear power platform |
| CN106683725B (en) * | 2017-01-05 | 2018-02-02 | 中广核研究院有限公司 | A kind of device for fuel transhipment and corresponding nuclear power platform |
| CN106910541A (en) * | 2017-03-30 | 2017-06-30 | 上海核工程研究设计院 | A kind of close-coupled nuclear reaction stows technique of reloading |
| CN107833644A (en) * | 2017-09-26 | 2018-03-23 | 中国船舶重工集团公司第七〇九研究所 | The refuelling system and material-changing method of ocean nuclear power platform |
| CN107833644B (en) * | 2017-09-26 | 2024-03-19 | 中国船舶重工集团公司第七一九研究所 | Material changing system and material changing method of ocean nuclear power platform |
| CN108193906A (en) * | 2017-10-09 | 2018-06-22 | 中国核电工程有限公司 | A kind of nuclear island factory building arrangement |
| CN108689299A (en) * | 2018-05-22 | 2018-10-23 | 广东核电合营有限公司 | The dilatation of million kilowatt Spent Fuel Pool removes overturning technique with old screen work |
| CN109461512A (en) * | 2018-10-25 | 2019-03-12 | 清华大学天津高端装备研究院 | A kind of spentnuclear fuel central repository pond hoisting device |
| US11887740B2 (en) | 2018-12-29 | 2024-01-30 | Chinergy Co., Ltd. | Unloading and temporary storage device |
| WO2020134076A1 (en) * | 2018-12-29 | 2020-07-02 | 清华大学 | Unloading temporary storage device |
| CN110246600A (en) * | 2019-07-11 | 2019-09-17 | 上海核工程研究设计院有限公司 | A kind of full underground type compact reactor refuling device |
| CN110993129A (en) * | 2019-11-28 | 2020-04-10 | 中广核研究院有限公司 | Passive cooling system and method for offshore floating nuclear power station |
| 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 |
| CN115417183A (en) * | 2022-09-19 | 2022-12-02 | 中广核工程有限公司 | Layout structure of spent fuel transportation factory building and hoisting method of spent fuel transportation container |
Also Published As
| Publication number | Publication date |
|---|---|
| CN1323405C (en) | 2007-06-27 |
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