GB1525020A - Removal of decay heat on failure of a pressurised-water reactor - Google Patents

Removal of decay heat on failure of a pressurised-water reactor

Info

Publication number
GB1525020A
GB1525020A GB51269/75A GB5126975A GB1525020A GB 1525020 A GB1525020 A GB 1525020A GB 51269/75 A GB51269/75 A GB 51269/75A GB 5126975 A GB5126975 A GB 5126975A GB 1525020 A GB1525020 A GB 1525020A
Authority
GB
United Kingdom
Prior art keywords
steam generator
steam
failure
emergency
main
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
GB51269/75A
Inventor
Dieter Bohm
Gottfried Dipl Ing Gess
Peter Dipl Ing Caspar
Hermann Dipl Ing Kley
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.)
ABB Reaktor GmbH
BBC Brown Boveri AG Germany
BBC Brown Boveri France SA
Original Assignee
Babcock Brown Boveri Reaktor GmbH
Brown Boveri und Cie AG Germany
BBC Brown Boveri France SA
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 Babcock Brown Boveri Reaktor GmbH, Brown Boveri und Cie AG Germany, BBC Brown Boveri France SA filed Critical Babcock Brown Boveri Reaktor GmbH
Publication of GB1525020A publication Critical patent/GB1525020A/en
Expired 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
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G21D3/06—Safety arrangements responsive to faults within the plant
    • 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
    • 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)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

In the event of operating leaks from the primary to the secondary side in the steam generator (5), of the failure of the main heat sink and/or of breakage of the main steam pipe, the amount of afterheat and steam still produced after shutdown of the reactor (3) is condensed using an emergency circuit (13, 14, 15, 16, 17) and the condensate is resupplied to the steam generator. The emergency circuit is connected via a controllable pressure-reducing valve (10) to the main steam pipes (7), which are connected to the steam generator. It has, inter alia, an afterheat removal heat exchanger (13) with an additional condensate cooler (17), and is connected to the steam generator (5) via an emergency feedwater pump (14), an emergency feedwater control valve (15) and a connecting piece (16). As a result, radioactive contamination of the environment is prevented even in the event of leaks in the steam generator. <IMAGE>
GB51269/75A 1974-12-14 1975-12-15 Removal of decay heat on failure of a pressurised-water reactor Expired GB1525020A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2459150A DE2459150C3 (en) 1974-12-14 1974-12-14 Method and circuit arrangement for removing the decay heat of a pressurized water reactor in the event of a malfunction

Publications (1)

Publication Number Publication Date
GB1525020A true GB1525020A (en) 1978-09-20

Family

ID=5933382

Family Applications (1)

Application Number Title Priority Date Filing Date
GB51269/75A Expired GB1525020A (en) 1974-12-14 1975-12-15 Removal of decay heat on failure of a pressurised-water reactor

Country Status (5)

Country Link
AT (1) AT380119B (en)
CH (1) CH618805A5 (en)
DE (1) DE2459150C3 (en)
FR (1) FR2294517A1 (en)
GB (1) GB1525020A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5428652A (en) * 1991-08-12 1995-06-27 Siemens Aktiengesellschaft Secondary-side residual-heat removal system for pressurized-water nuclear reactors
US8647582B2 (en) 2007-12-27 2014-02-11 Elcon Recycling Center (2003) Ltd. System for safely processing a fluid via monitoring and decreasing explosiveness
CN104952495A (en) * 2015-06-26 2015-09-30 上海核工程研究设计院 Secondary side residual heat removal system for twin-reactor nuclear power plant

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2700168C3 (en) * 1977-01-04 1981-11-12 Kraftwerk Union AG, 4330 Mülheim Device for the removal of decay heat in a steam power plant heated with nuclear energy
DE2809466C3 (en) * 1978-03-04 1986-05-28 Brown Boveri Reaktor GmbH, 6800 Mannheim Device for emergency cooling of a steam generator in a nuclear power plant
DE2842875C2 (en) * 1978-10-02 1984-01-12 Brown Boveri Reaktor GmbH, 6800 Mannheim Process and device for removing residual heat from a water-cooled nuclear reactor plant
DE2921694C2 (en) * 1979-05-29 1981-12-03 Babcock-Brown Boveri Reaktor Gmbh, 6800 Mannheim Device for removing the heat to be transferred in a steam generator of a pressurized water reactor system in the event of a brief failure of the emergency feed water pumps
FR2487563A1 (en) * 1980-07-25 1982-01-29 Framatome Sa METHOD AND DEVICE FOR COOLING EMERGENCY RESPONSE OF A NUCLEAR REACTOR
FR2515853A1 (en) * 1981-11-05 1983-05-06 Framatome Sa COOLING DEVICE FOR THE PRIMARY CIRCUIT OF A PRESSURE WATER NUCLEAR REACTOR
DE3248029C2 (en) * 1982-12-24 1987-04-09 Brown Boveri Reaktor GmbH, 6800 Mannheim Method for preventing consequential damage in the event of leaks occurring within a steam generator of a pressurized water reactor plant between the primary and secondary circuits
EP0362596B1 (en) * 1988-09-30 1993-12-01 Siemens Aktiengesellschaft Heat reactor system comprising a residual heat removal system and its use in boiling-water and pressurized-water reactors
DE4126630A1 (en) * 1991-08-12 1993-02-18 Siemens Ag SECOND-SIDED HEAT EXHAUST SYSTEM FOR PRESSURE WATER CORE REACTORS

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1290703A (en) * 1960-06-01 1962-04-13 Atomic Energy Authority Uk Steam generator installation powered by a nuclear reactor
FR1345085A (en) * 1962-10-24 1963-12-06 Cup safety device, especially for baby cups
GB1291706A (en) * 1969-01-16 1972-10-04 Atomic Energy Authority Uk Improvements in nuclear reactors
GB1297951A (en) * 1969-04-14 1972-11-29
BE795482A (en) * 1972-02-19 1973-05-29 Siemens Ag NUCLEAR REACTOR COOLING SYSTEM
DE2336146A1 (en) * 1973-07-16 1975-02-06 Kraftwerk Union Ag Compact V-form pressurised auxiliary condensers - dissipating excess steam and decay heat in PWR power plant

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5428652A (en) * 1991-08-12 1995-06-27 Siemens Aktiengesellschaft Secondary-side residual-heat removal system for pressurized-water nuclear reactors
US8647582B2 (en) 2007-12-27 2014-02-11 Elcon Recycling Center (2003) Ltd. System for safely processing a fluid via monitoring and decreasing explosiveness
US8920738B2 (en) 2007-12-27 2014-12-30 Elcon Recycling Center (2003) Ltd. Method for safely processing a fluid via monitoring and decreasing explosiveness
CN104952495A (en) * 2015-06-26 2015-09-30 上海核工程研究设计院 Secondary side residual heat removal system for twin-reactor nuclear power plant

Also Published As

Publication number Publication date
ATA930175A (en) 1980-02-15
AT380119B (en) 1986-04-10
FR2294517B1 (en) 1981-08-28
DE2459150C3 (en) 1988-07-07
DE2459150B2 (en) 1980-07-03
FR2294517A1 (en) 1976-07-09
CH618805A5 (en) 1980-08-15
DE2459150A1 (en) 1976-06-16

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Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PCNP Patent ceased through non-payment of renewal fee