GB1344308A - Method and system for condensing leaking steam in a nuclear reactor installation - Google Patents

Method and system for condensing leaking steam in a nuclear reactor installation

Info

Publication number
GB1344308A
GB1344308A GB5468671A GB5468671A GB1344308A GB 1344308 A GB1344308 A GB 1344308A GB 5468671 A GB5468671 A GB 5468671A GB 5468671 A GB5468671 A GB 5468671A GB 1344308 A GB1344308 A GB 1344308A
Authority
GB
United Kingdom
Prior art keywords
steam
nuclear reactor
chamber
plant
leakage
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.)
Expired
Application number
GB5468671A
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.)
Siemens AG
Original Assignee
Siemens AG
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 Siemens AG filed Critical Siemens AG
Publication of GB1344308A publication Critical patent/GB1344308A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004Pressure suppression
    • G21C9/012Pressure suppression by thermal accumulation or by steam condensation, e.g. ice condensers
    • 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

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)

Abstract

1344308 Reactors SIEMENS AG 24 Nov 1971 [24 Nov 1970] 54686/71 Heading G6C In a steam generating nuclear reactor power plant, leakage steam is condensed by a waterfree medium such as carbon dioxide and/or silver iodide. Leakage steam, in the event of a rupture of the coolant lines 6, connecting the steam generators 7 and the reactor 4, is sprayed with carbon dioxide and silver iodide from the conduits 12, 13 respectively in the annular chamber, 10. The condensate collects in the container 15 and is conveyed to the reactor pit 5. The air cushion formed in front of the escaping steam is released from the chamber, 10, through the valve 16. Spray conduits, 17, 18 may also be placed in the plant chamber, 9, when leaking steam is condensed directly at the leakage point and no air cushion is moved through the plant.
GB5468671A 1970-11-24 1971-11-24 Method and system for condensing leaking steam in a nuclear reactor installation Expired GB1344308A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19702057593 DE2057593A1 (en) 1970-11-24 1970-11-24 Safety procedures for nuclear reactors

Publications (1)

Publication Number Publication Date
GB1344308A true GB1344308A (en) 1974-01-23

Family

ID=5788907

Family Applications (1)

Application Number Title Priority Date Filing Date
GB5468671A Expired GB1344308A (en) 1970-11-24 1971-11-24 Method and system for condensing leaking steam in a nuclear reactor installation

Country Status (4)

Country Link
AT (1) AT319414B (en)
DE (1) DE2057593A1 (en)
GB (1) GB1344308A (en)
IT (1) IT943683B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1583105A3 (en) * 2004-03-26 2006-11-15 Kabushiki Kaisha Toshiba Pressure suppression and decontamination apparatus and method for reactor container
US8126107B2 (en) 2006-03-07 2012-02-28 Areva Np Gmbh Nuclear engineering plant and closure apparatus for its containment

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1583105A3 (en) * 2004-03-26 2006-11-15 Kabushiki Kaisha Toshiba Pressure suppression and decontamination apparatus and method for reactor container
US7813465B2 (en) 2004-03-26 2010-10-12 Kabushiki Kaisha Toshiba Pressure suppression and decontamination apparatus and method for reactor container
US8126107B2 (en) 2006-03-07 2012-02-28 Areva Np Gmbh Nuclear engineering plant and closure apparatus for its containment
US8509376B2 (en) 2006-03-07 2013-08-13 Areva Gmbh Nuclear engineering plant and closure apparatus for its containment

Also Published As

Publication number Publication date
AT319414B (en) 1974-12-27
IT943683B (en) 1973-04-10
DE2057593A1 (en) 1972-05-31

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Legal Events

Date Code Title Description
PS Patent sealed
PLNP Patent lapsed through nonpayment of renewal fees