CN104335288A - 核电站的燃料元件存储池 - Google Patents

核电站的燃料元件存储池 Download PDF

Info

Publication number
CN104335288A
CN104335288A CN201380023574.4A CN201380023574A CN104335288A CN 104335288 A CN104335288 A CN 104335288A CN 201380023574 A CN201380023574 A CN 201380023574A CN 104335288 A CN104335288 A CN 104335288A
Authority
CN
China
Prior art keywords
fuel element
sluice
storage pool
gate
element storage
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN201380023574.4A
Other languages
English (en)
Inventor
马库斯·沃施集
埃哈德·穆勒
迈克尔·内梅切克
诺伯特·雅各布森
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Areva GmbH
Original Assignee
Areva NP GmbH
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Areva NP GmbH filed Critical Areva NP GmbH
Publication of CN104335288A publication Critical patent/CN104335288A/zh
Pending legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements 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
    • G21C19/02—Details of handling arrangements
    • G21C19/06—Magazines for holding fuel elements or control elements
    • G21C19/07—Storage racks; Storage pools
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/10—Means for preventing contamination in the event of leakage, e.g. double wall
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements 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
    • G21C19/32—Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements 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
    • G21C19/40—Arrangements for preventing occurrence of critical conditions, e.g. during storage
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements 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
    • G21C19/02—Details of handling arrangements
    • G21C19/08—Means for heating fuel elements before introduction into the core; Means for heating or cooling fuel elements after removal from the core
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements 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
    • G21C19/18—Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Other Liquid Machine Or Engine Such As Wave Power Use (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

在核电站中，燃料元件存储池(4)与反应堆坑(2)之间的水闸(10)配备有闸门(36)，通过该闸门，当燃料元件存储池(4)中的水平面(h)下降到预设的限位值(hG)以下时自动关闭水闸(10)。

Description

核电站的燃料元件存储池
本发明涉及一种核电站的燃料元件存储池，该存储池通过可关闭的水闸与布置在燃料元件存储池旁边的反应堆坑连接。
在核电站中，在反应堆坑旁边通常为注满的燃料元件存储池，其中乏燃料元件存储在燃料存储架中并通过位于燃料元件存储池中的池水的循环来冷却，直到其活性减弱，从而使得可将其运输到燃料元件存储池外面。在反应堆坑与燃料元件存储池之间为可用闸门关闭的水闸，该水闸在检修作业期间(此时反应堆坑被注满)可以打开，以便可以将借助燃料元件装料机从核中提取出来的乏燃料元件在反应堆坑的水下输送到燃料元件存储池并且将其存储在燃料元件存储架中。
如果反应堆坑中出现泄漏，例如给反应堆坑供水的线路的管路断裂，或对于沸水反应堆在通量补偿器中出现泄漏，则必须将被开启的水闸关闭，以防止燃料元件存储池中的水位下降。闸门的开启和关闭均是手动操作。
随着此类泄漏的出现，反应堆坑中的水位会下降，在存储池地面平台上的辐照度会相应地增加，因此，一旦出现所述泄漏要立即发出警报，而且此时在存储池地面平台上工作的人员必须立即离开建筑物。由于闸门的开启和关闭要手动操作，因此会出现这种情况，即将水闸关闭的闸门仍然开启着。这会导致的后果是，燃料元件存储池中的水位至少会降至水闸开口的下边处。如此一来，存储在燃料元件存储架中的燃料元件被水覆盖部分减少，其中在最不利的情况下燃料元件的上部会凸出超过水平面，从而使辐照度变得大得足以使燃料元件存储池周围环境中的区域不能再进入，而且很难或不可以再采取措施来冷却燃料元件。
因此，本发明的任务在于，提供一种核电站的燃料元件存储池，该存储池具有通往反应堆坑的水闸，在所述燃料元件存储池中避免了上述问题。
根据本发明，此任务通过具有权利要求1所述特征的燃料元件存储池来得以实现。根据这些特征，为通往反应堆坑的水闸配备了闸门，用于当燃料元件存储池中的水平面下降到预设的限位值以下时自动关闭水闸。通过这种措施来确保在当反应堆坑中的水平面因故障而低于预设的限位值的情况下有足够的水来覆盖存储在燃料元件存储池中的燃料元件。
此外，为了在自动关闭时驱动闸门而设置有被动驱动系统，该驱动系统具有独立于网络的储能装置，当核电站中的供电网全部断电时也能确保水闸关闭。此种独立于网络的存储器既可以是电储能装置，也可以是机械储能装置，例如可以是被增大的重量或预应力弹簧，或者还可以是气动储能装置，所述储能装置可直接地且不需要电驱动地与闸门连接。
当用于未达到限位值并用于触发闸门的闭合运动的信号发生器具有浮子时，则可实现特别高的功能可靠性。
参考附图中示出的实施例来进一步对本发明进行阐述。图中显示：
图1以示意性原理图示出了根据本发明的燃料元件存储池，其中该存储池布置在反应堆坑旁并通过闸门与反应堆坑液体连接，
图2为一个有利的实施形式，在此实施形式中浮子被设置成信号发生器，
图3至图6为适合于自动关闭水闸的闸门的有利实施形式。
根据图1，燃料元件存储池4位于核电站的反应堆坑2旁，乏燃料元件6(只有一个燃料元件被象征性地描述出来)直立地存储在同样只是示意性示出的燃料存储架8中。反应堆坑2和燃料存储池4通过可关闭的水闸10彼此液体连接。图1中描述了一种情况，在这种情况下，反应堆坑2用水注满，其中高度为h的水平面12仅略低于存储池地面平台14。
图1示出了核电站的一种状态，此时正在实施检修作业，例如正在更换燃料元件。位于反应堆坑4中的反应堆压力容器16开启并且也同样用水注满。在所示实施例中示出了沸水反应堆中的一种情况，其中位于反应堆压力容器16和反应堆坑2的壁18之间的中间区域20未被水注满。为了阻止水进入该中间区域20，在开始检修作业之前将所谓的通量补偿器24引入反应堆压力容器16和其旁边的存放区域22之间。
现在从图1可以看出，在所示实施例中，水闸10的底部26在燃料元件6或燃料元件存储架8的上边28以下。因此，在反应堆坑2空转的情况下水闸10打开时，例如当通量补偿器24破裂时，也可将燃料元件存储池4排空至底部26的水平。在这种情况下，存储在燃料元件存储架8中的燃料元件6凸出超过水平面12的调节高度hmin，即超出了Δh。
为了避免这一点，在燃料存储池4中布置有信号发生器30，当水平面12的高度h低于限位值hG时，所述信号发生器会生成信号S。借助所述信号S，通过独立于网络的储能装置30(例如蓄电池，机械、气动或液力储能装置)给驱动器34供给能量，所述驱动器会驱动被开启的闸门36，通过该闸门来关闭水闸10。换言之就是：当水平面12低于限位值hG时会自动地以及被动地将水闸10关闭，自动关闭是指无需手动操作，被动关闭是指通过外部网络独立于供给来关闭，从而使得燃料存储池中的水平面的进一步下降会被阻止并保证在存储架8中所存储的燃料元件6会有足够的水覆盖和冷却。
在根据图2的实施例中，信号发生器30具有浮子38，其操作开关40，用所述开关将储能装置32接通到驱动器34上。
在图3所示实施例中描述了水闸10，其中通过板52构成闸门36，其中在燃料元件存储池2壁上安装横向延伸的轨道50。闸门52可借助液压缸54在水闸10开启的位置和用虚线表示的水闸10关闭的位置之间来回运行。同样布置在燃料元件存储池2壁上的型材56被用作闸门52的上导向元件，以确保将水闸10牢牢地关闭。
在图4所示替代性的实施形式中，将可偏转地安装的板52(偏转闸门)设置成闸门36，所述闸门借助液压的、气动的或电力的驱动装置通过偏转运动来关闭水闸10。
为了替代其中闸门36基本上由板构成的图3和图4所示实施形式，在图5和图6设置了卷帘60形式的闸门36，所述卷帘卷绕到安装在水闸10底部26下方的滚轴62上并且可借助牵引索64卷起来以关闭水闸10。卷帘60由弹性橡胶膜组成，所述膜通过轮廓部68拉紧，所述轮廓部68平行于滚轴62的旋转轴66布置，此外其还用于将滚轴60引导至布置在水闸10旁边的导轨70中。
例如，也可设置所述卷帘60来补充图3示出的可移动的闸门。

Claims (3)

1.一种核电站的燃料元件存储池(4)，其具有通往反应堆坑(2)的水闸(10)，所述水闸(10)配备了闸门(36)，用于当所述燃料元件存储池(4)中的水平面(h)下降到预设的限位值(hG)以下时自动关闭所述水闸(10)。
2.如权利要求1所述的燃料元件存储池，其中为了在自动关闭时驱动闸门(36)，设置了被动驱动系统(34)，所述被动驱动系统(34)具有独立于网络的储能装置(32)。
3.如权利要求1或权利要求2所述的燃料元件存储池，其中用于低于限位值并用于触发闸门(36)的闭合运动的信号发生器(30)具有浮子(38)。
CN201380023574.4A 2012-05-04 2013-04-08 核电站的燃料元件存储池 Pending CN104335288A (zh)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
DE102012207473A DE102012207473A1 (de) 2012-05-04 2012-05-04 Brennelementlagerbecken eines Kernkraftwerks
DE102012207473.2 2012-05-04
PCT/EP2013/057289 WO2013164158A1 (de) 2012-05-04 2013-04-08 Brennelementlagerbecken eines kernkraftwerks

Publications (1)

Publication Number Publication Date
CN104335288A true CN104335288A (zh) 2015-02-04

Family

ID=48143261

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201380023574.4A Pending CN104335288A (zh) 2012-05-04 2013-04-08 核电站的燃料元件存储池

Country Status (9)

Country Link
US (1) US20150294746A1 (zh)
EP (1) EP2845199B1 (zh)
JP (1) JP2015517648A (zh)
KR (1) KR102090059B1 (zh)
CN (1) CN104335288A (zh)
DE (1) DE102012207473A1 (zh)
ES (1) ES2575853T3 (zh)
RU (1) RU2633701C2 (zh)
WO (1) WO2013164158A1 (zh)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE102013222280A1 (de) * 2013-11-01 2014-11-20 Areva Gmbh Brennelementlagerbecken eines Kernkraftwerks
JP2016017819A (ja) * 2014-07-08 2016-02-01 株式会社東芝 原子力プラントおよびその改造方法
KR102499160B1 (ko) 2019-11-12 2023-02-10 박승호 가죽 제품용 클리너 장치

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3020225A (en) * 1956-03-01 1962-02-06 Babcock & Wilcox Ltd Material handling plant
US3984282A (en) * 1970-08-05 1976-10-05 Nucledyne Engineering Corporation Passive containment system for a nuclear reactor
US4072559A (en) * 1972-11-30 1978-02-07 Siemens Aktiengesellschaft Method and apparatus for the zone-wise shuffling of nuclear reactor fuel elements
US4210614A (en) * 1970-08-05 1980-07-01 Nucledyne Engineering Corp. Passive containment system
US4649016A (en) * 1985-10-09 1987-03-10 Westinghouse Electric Corp. Remotely operable fuel transfer system for nuclear reactor
US5268942A (en) * 1992-09-10 1993-12-07 Pacific Nuclear Systems, Inc. Temporary cooling system and method for removing decay heat from a nuclear reactor
US20050100123A1 (en) * 1998-03-19 2005-05-12 Framatome Anp Gmbh Apparatus for transferring an article between fluid-filled vessels
CN102280155A (zh) * 2011-06-24 2011-12-14 华北电力大学 一种非能动乏燃料贮存池水位控制及余热排出装置

Family Cites Families (19)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2192963A (en) * 1937-05-22 1940-03-12 Atlas Valve Company Compensated valve
US3744593A (en) * 1971-04-13 1973-07-10 Transfer Systems Elevator for a reactor well and equipment storage area
JPS488046U (zh) * 1971-06-09 1973-01-29
JPS5829367B2 (ja) * 1973-11-29 1983-06-22 日本軽金属 （株） 自動開閉水門扉
DE7610898U1 (de) * 1976-04-08 1978-01-26 Interatom Internationale Atemreaktorbau Gmbh, 5060 Bensberg Gas- und strahlendichter verschluss
CA1121094A (en) * 1977-10-04 1982-03-30 Walter Brodowski Zinc chelates of terephthaloyl-terephthal/oxal copolyhydrazide
US4502245A (en) * 1981-05-18 1985-03-05 Gg. Noell Gmbh Means for controlling pivotal doors in nuclear plants
ATE30640T1 (de) * 1983-03-01 1987-11-15 Acec Dichtigkeitsanzeigegeraet fuer abdaemmung von nuklearbecken.
US4690795A (en) * 1985-10-07 1987-09-01 Westinghouse Electric Corp. Emergency transfer tube closure and process for sealing transfer tube under emergency conditions
JPS62245192A (ja) * 1986-04-16 1987-10-26 株式会社東芝 核燃料プ−ル用ゲ−ト装置
SU1497350A1 (ru) * 1987-08-03 1989-07-30 Украинский Филиал Центрального Научно-Исследовательского Института Комплексного Использования Водных Ресурсов Осушительно-увлажнительна система
JPH08304586A (ja) * 1995-05-12 1996-11-22 Toshiba Corp 使用済燃料貯蔵プール及び原子炉ウェルプール
JPH09138294A (ja) * 1995-11-14 1997-05-27 Toshiba Corp 使用済燃料貯蔵プール
RU2180764C2 (ru) * 1996-09-18 2002-03-20 Владимир Федотович Русинов Устройство для перегрузки топлива реакторов атомной станции
JP2002318296A (ja) * 2001-04-23 2002-10-31 Toshiba Plant Kensetsu Co Ltd 機器仮置きプールの間仕切りカーテン
DE102007033376B4 (de) * 2007-07-18 2012-04-26 Areva Np Gmbh Verfahren zum Rückbau einer nukleartechnischen Anlage
JP4922146B2 (ja) * 2007-12-19 2012-04-25 株式会社東芝 使用済燃料プール水監視装置
JP5826605B2 (ja) * 2011-11-10 2015-12-02 株式会社東芝 使用済み燃料貯蔵プールの水位検出装置及び方法
JP6270333B2 (ja) * 2013-04-16 2018-01-31 日立Ｇｅニュークリア・エナジー株式会社 原子炉水位計測装置

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3020225A (en) * 1956-03-01 1962-02-06 Babcock & Wilcox Ltd Material handling plant
US3984282A (en) * 1970-08-05 1976-10-05 Nucledyne Engineering Corporation Passive containment system for a nuclear reactor
US4210614A (en) * 1970-08-05 1980-07-01 Nucledyne Engineering Corp. Passive containment system
US4072559A (en) * 1972-11-30 1978-02-07 Siemens Aktiengesellschaft Method and apparatus for the zone-wise shuffling of nuclear reactor fuel elements
US4649016A (en) * 1985-10-09 1987-03-10 Westinghouse Electric Corp. Remotely operable fuel transfer system for nuclear reactor
US5268942A (en) * 1992-09-10 1993-12-07 Pacific Nuclear Systems, Inc. Temporary cooling system and method for removing decay heat from a nuclear reactor
US20050100123A1 (en) * 1998-03-19 2005-05-12 Framatome Anp Gmbh Apparatus for transferring an article between fluid-filled vessels
CN102280155A (zh) * 2011-06-24 2011-12-14 华北电力大学 一种非能动乏燃料贮存池水位控制及余热排出装置

Also Published As

Publication number Publication date
RU2014148917A (ru) 2016-06-27
DE102012207473A1 (de) 2013-11-07
US20150294746A1 (en) 2015-10-15
ES2575853T3 (es) 2016-07-01
KR102090059B1 (ko) 2020-03-17
KR20150004420A (ko) 2015-01-12
RU2633701C2 (ru) 2017-10-17
WO2013164158A1 (de) 2013-11-07
EP2845199B1 (de) 2016-03-30
EP2845199A1 (de) 2015-03-11
JP2015517648A (ja) 2015-06-22

Similar Documents

Publication Publication Date Title
US8559583B1 (en) Passive cooling and depressurization system and pressurized water nuclear power plant
KR101229953B1 (ko) 사용후핵연료 저장조 피동형 냉각장치
CN102903403B (zh) 一种能动与非能动相结合的堆芯注水热量导出装置
KR20140009835A (ko) 원자로의 피동안전계통
US20230073091A1 (en) Refueling water storage tank (rwst) with tailored passive emergency core cooling (ecc) flow
KR102243711B1 (ko) 원자로 장기 냉각 계통 및 이를 구비한 원전
KR101473377B1 (ko) 피동격납건물살수계통
KR101364646B1 (ko) 소형 안전보호용기를 적용한 피동안전 시스템 및 이를 구비하는 일체형 원자로
JPH0648473Y2 (ja) 原子炉装置
CN104335288A (zh) 核电站的燃料元件存储池
KR20150107855A (ko) 핵 원자로의 노심을 냉각시키기 위한 수동 시스템
JP5279325B2 (ja) 沸騰水型原子炉のハイブリッド安全系
CN107845434B (zh) 一种非能动反应堆堆芯辅助冷却系统
Chun et al. Safety evaluation of small-break LOCA with various locations and sizes for SMART adopting fully passive safety system using MARS code
EP2966651B1 (en) Nuclear power plant and remodeling method therefor
KR101191655B1 (ko) 2차 계통의 주증기 회수 및 증기발생기의 피동 재충수 장치
KR101504216B1 (ko) 방사성 물질 저감 설비 및 이를 구비하는 원전
US11120921B2 (en) In-containment spent fuel storage to limit spent fuel pool water makeup
US10079076B2 (en) Emergency core cooling system for a water-cooled reactor system
CN202887751U (zh) 一种能动与非能动相结合的堆芯注水热量导出装置
KR20180011201A (ko) 원자력 발전 플랜트의 취수 설비
KR20130083187A (ko) 원자로 외벽 공동 충수 시스템
Matsunaga Sato et al.

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
RJ01 Rejection of invention patent application after publication
RJ01 Rejection of invention patent application after publication

Application publication date: 20150204