ES456036A1 - Reactor emergency coolant discharge at fast and slow rates - according to position of primary circuit leak - Google Patents

Reactor emergency coolant discharge at fast and slow rates - according to position of primary circuit leak

Info

Publication number
ES456036A1
ES456036A1 ES456036A ES456036A ES456036A1 ES 456036 A1 ES456036 A1 ES 456036A1 ES 456036 A ES456036 A ES 456036A ES 456036 A ES456036 A ES 456036A ES 456036 A1 ES456036 A1 ES 456036A1
Authority
ES
Spain
Prior art keywords
pressure
leak
biological shield
space
primary
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
ES456036A
Other languages
Spanish (es)
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.)
Kraftwerk Union AG
Original Assignee
Kraftwerk Union 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 Kraftwerk Union AG filed Critical Kraftwerk Union AG
Publication of ES456036A1 publication Critical patent/ES456036A1/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
    • 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)
  • Examining Or Testing Airtightness (AREA)

Abstract

A nuclear reactor installation comprises a liquid-cooled, esp. pressurised water reactor, in which the main coolant circuit comprises a pressure vessel and ducting leading out through the surrounding concrete biological shield. The biological shield, together with the reactor pressure vessel, constitutes a close space in which the pressure is monitored in order to actuate equipment for initiating a rapid power reduction if a leak should occur in the main coolant circuit. Pressure measuring devices inside the close space between biological shield and pressure vessel actuate the rapid power reduction equipment only if a leak occurs within the main biological shield, but initiate a slower reduction of power if a leak should occur outside this closed space within the biological shield. Pref. the pressure measuring equipment provides a comparison between the pressure rise inside the closed space and that outside this space. More specifically, the pressure measuring equipment records the difference in pressure between these two spaces. A sudden reduction in pressure by discharge of primary coolant from the circuit is avoided except in the essential cases of a leak within the primary contained space around the vessel. Where a leak occurs in the primary circuit outside the biological shield, a much slower power reduction is possible, and thus the stress loading induced in the primary circuit components can be correspondingly reduced.
ES456036A 1976-02-18 1977-02-18 Reactor emergency coolant discharge at fast and slow rates - according to position of primary circuit leak Expired ES456036A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2606527A DE2606527C3 (en) 1976-02-18 1976-02-18 Relief device for a nuclear reactor facility

Publications (1)

Publication Number Publication Date
ES456036A1 true ES456036A1 (en) 1978-04-16

Family

ID=5970221

Family Applications (1)

Application Number Title Priority Date Filing Date
ES456036A Expired ES456036A1 (en) 1976-02-18 1977-02-18 Reactor emergency coolant discharge at fast and slow rates - according to position of primary circuit leak

Country Status (3)

Country Link
CH (1) CH600497A5 (en)
DE (1) DE2606527C3 (en)
ES (1) ES456036A1 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6039525A (en) * 1983-08-12 1985-03-01 Mitsubishi Electric Corp Estimating method of water leakage position

Also Published As

Publication number Publication date
DE2606527B2 (en) 1978-04-06
DE2606527A1 (en) 1977-09-01
CH600497A5 (en) 1978-06-15
DE2606527C3 (en) 1978-11-30

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