AU2001276601A1 - Nuclear reactor plant - Google Patents

Nuclear reactor plant

Info

Publication number
AU2001276601A1
AU2001276601A1 AU2001276601A AU7660101A AU2001276601A1 AU 2001276601 A1 AU2001276601 A1 AU 2001276601A1 AU 2001276601 A AU2001276601 A AU 2001276601A AU 7660101 A AU7660101 A AU 7660101A AU 2001276601 A1 AU2001276601 A1 AU 2001276601A1
Authority
AU
Australia
Prior art keywords
coolant
nuclear reactor
coolant chamber
reactor plant
chamber
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.)
Abandoned
Application number
AU2001276601A
Inventor
Ivan Drodskie
David Richard Nicholls
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.)
Eskom
Original Assignee
Eskom
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 Eskom filed Critical Eskom
Publication of AU2001276601A1 publication Critical patent/AU2001276601A1/en
Abandoned legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • 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
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)

Abstract

The invention provides a cooling system which includes at least one and preferably a plurality of coolant chambers arranged around a heat source, typically a nuclear reactor. A coolant inlet pipe enters the or each coolant chamber at a high level and extends downwardly through the coolant chamber to a discharge end positioned at a low level within the coolant chamber. At least one anti-siphon bleed opening is provided in that portion of the coolant pipe which is positioned at the highest level within the coolant chamber.
AU2001276601A 2000-08-16 2001-08-08 Nuclear reactor plant Abandoned AU2001276601A1 (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
ZA200004187 2000-08-16
ZA2000/4187 2000-08-16
PCT/IB2001/001416 WO2002015197A2 (en) 2000-08-16 2001-08-08 Nuclear reactor plant

Publications (1)

Publication Number Publication Date
AU2001276601A1 true AU2001276601A1 (en) 2002-02-25

Family

ID=25588868

Family Applications (1)

Application Number Title Priority Date Filing Date
AU2001276601A Abandoned AU2001276601A1 (en) 2000-08-16 2001-08-08 Nuclear reactor plant

Country Status (9)

Country Link
US (1) US7136449B2 (en)
EP (1) EP1309974B1 (en)
JP (1) JP2004506910A (en)
KR (1) KR100810964B1 (en)
CN (1) CN1240078C (en)
AT (1) ATE527662T1 (en)
AU (1) AU2001276601A1 (en)
CA (1) CA2412863C (en)
WO (1) WO2002015197A2 (en)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1342245B1 (en) * 2000-12-14 2007-03-21 Pebble Bed Modular Reactor (Proprietary) Limited Cooling system
US8755438B2 (en) * 2010-11-29 2014-06-17 Ecole De Technologie Superieure Method and system for selectively performing multiple video transcoding operations
GB2488132A (en) * 2011-02-16 2012-08-22 Aspen Pumps Ltd Removal of condensate or other liquids from air conditioning systems or other installations
KR101445494B1 (en) 2013-07-18 2014-09-26 한국원자력연구원 Passive residual heat removal system of reserch reactor using gravity core cooling tank
KR101501457B1 (en) * 2013-08-27 2015-03-11 한국원자력연구원 Apparatus for breaking siphon effect of reactor pool and control method therefor
KR101651466B1 (en) * 2015-04-02 2016-08-29 한국원자력연구원 Verification test device for passive residual heat removal system of a research reactor
KR102107746B1 (en) * 2018-05-15 2020-05-07 한국원자력연구원 Heat transferring device with pumping structure

Family Cites Families (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3046403A (en) * 1959-04-17 1962-07-24 Babcock & Wilcox Co Device for the storage of a heat evolving material
US3621926A (en) * 1968-02-13 1971-11-23 Gen Electric Nuclear reactor coolant recirculation system
US3951164A (en) * 1975-02-07 1976-04-20 Jalco, Inc. Anti-siphon and backflow prevention valve
JPS5942999U (en) * 1982-09-16 1984-03-21 三菱重工業株式会社 Spent nuclear fuel storage facility
JPS59159092A (en) * 1983-02-28 1984-09-08 株式会社東芝 Thermal shield device of fast breeder
GB2157880B (en) * 1984-04-19 1988-02-10 Westinghouse Electric Corp An improved nuclear reactor plant construction
JPS6151594A (en) * 1984-08-22 1986-03-14 株式会社日立製作所 Loop type fast breeder reactor
FR2631484B1 (en) * 1988-05-13 1992-08-21 Framatome Sa NUCLEAR REACTOR WITH EMERGENCY COOLING WATER INJECTION DEVICE
JPH0792515B2 (en) * 1988-11-16 1995-10-09 株式会社日立製作所 Containment vessel
US5202084A (en) * 1990-07-10 1993-04-13 General Electric Company Bi-level reactor including steam separators
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
US5377242A (en) * 1993-11-15 1994-12-27 B&W Nuclear Service Company Method and system for emergency core cooling
JP2972162B2 (en) * 1997-04-17 1999-11-08 核燃料サイクル開発機構 Furnace wall cooling protection structure of fast reactor
US6269833B1 (en) * 1999-12-17 2001-08-07 Stp Nuclear Operating Company Spent fuel pool anti-siphon system

Also Published As

Publication number Publication date
ATE527662T1 (en) 2011-10-15
JP2004506910A (en) 2004-03-04
WO2002015197B1 (en) 2002-07-11
WO2002015197A2 (en) 2002-02-21
CN1240078C (en) 2006-02-01
CA2412863A1 (en) 2002-02-21
CA2412863C (en) 2009-12-22
CN1533576A (en) 2004-09-29
US20040028171A1 (en) 2004-02-12
KR20030029651A (en) 2003-04-14
EP1309974B1 (en) 2011-10-05
US7136449B2 (en) 2006-11-14
EP1309974A2 (en) 2003-05-14
WO2002015197A3 (en) 2002-05-10
KR100810964B1 (en) 2008-03-10

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