KR870008334A - 가압수 원자로용 수동안전 시스템 - Google Patents

가압수 원자로용 수동안전 시스템 Download PDF

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Publication number
KR870008334A
KR870008334A KR870000905A KR870000905A KR870008334A KR 870008334 A KR870008334 A KR 870008334A KR 870000905 A KR870000905 A KR 870000905A KR 870000905 A KR870000905 A KR 870000905A KR 870008334 A KR870008334 A KR 870008334A
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reactor
vessel
water
containment vessel
reactor containment
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KR870000905A
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KR950011978B1 (ko
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로렌스 에드워드 콘웨이
테리 리 슐츠
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혹스 제이. 에이취.
웨스팅하우스 일렉트릭 코오포레이숀
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • 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
    • 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

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  • 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)
  • Safety Devices In Control Systems (AREA)

Abstract

내용 없음

Description

기압수 원자로용 수동안전 시스템
본 내용은 요부공개 건이므로 전문내용을 수록하지 않았음
제 1 도는 본 발명의 양호한 실시예의 구성요소들을 나타내는 원자로 격납용기의 개략 상부평면도.
제 2 도는 양호한 실시예의 개략도표.
제 3 도는 양호한 실시예의 구성요소의 개략측면도.

Claims (3)

  1. 방호구조물(1), 방호구조물(1) 내에 위치되어 원자로 격납용기통을 둘러싸서 그와 환형공간을 한정해 주는 방열용 원자로 격납용기통(32), 원자로 격납용기통(32) 내에 위치되는 원자로용기(3), 원자로 격납용기통내에 위치되는 증기발생기(4), 상기 원자로 용기(3)으로부터 상기 증기발생기로 가열된 물을 안내하는 제 1 수로(5) 및 상기 증기발생기(4)로부터 상기 원자로 용기(3)으로 냉각된 물을 안내하는 제 2 수로(6)를 갖는 원자로 냉매회로, 상기 회로내에서 물순환을 유지시키기 위해 상기 원자로 냉매회로에 연결되는 원자로 냉매펌프(10), 그리고 상기 회로내의 물을 예정된 압력으로 유지시키기 위해 상기 원자로 냉매회로에 연결되는 가압기(7)를 포함하는 원자로용 수동 유체 안전시스템에 있어서,
    (가) 상기 원자로 냉매회로로부터 붕괴열을 제거하기 위해 상기 증기발생기를 어떤 압력으로 우회시킴과 더불어 상기 제 1 수로(5)로부터 상기 제 2 수로(6)으로 단지 자연 환류에 의해 물을 순환시키기 위한 제 1 수단(12)으로서,
    (1) 상기 제 1 수로로부터 흘러나오는 물을 상기 제 2 수로로 들어가기 전에 냉각시키기 위한 열교환기 수단(15)와,
    (2) 안전동작에 관계되는 파라메터값에 응답하여 상기 제 1 수로로부터 상기 제 2 수로로만 물이 흐르도록 하기위한 제 1 발브수단을 포함하는 상기 제 1 수단과,
    (나) 상기 원자로 냉매회로내의 손실된 물을 어떤 압력으로 보충하기 위해 상기 원자로 용기속으로 단지 중력에 의해서 저장된 냉수를 도입하기 위한 제 2 수단(22)으로서, 안전동작에 관계되는 파라메터값에 응답하여 단지 상기 원자로 용기속으로만 저장된 냉수가 도입되도록 해주기 위한 제 2 발브수단을 포함하는 상기 제 2 수단과,
    (다) 상기 원자로 냉매회로의 상기 제 1 및 제 2 수로들보다 높은 높이까지 원자로 격납용기통을 범람시키기 위해, 원자로 냉매회로내의 압력의 원자로 격납용기통에서와 동일한 압력에 거의 근사한 압력으로 감소될 때 상기 원자로 용기내로 단지 중력에 의해 저장된 냉수를 도입하기 위한 제 3 수단(34)으로서, 안전 동작에 관계되는 파라메터값에 응답하여 상기 원자로 냉매회로를 감압하기 위한 제 3 발브수단(36)을 포함하는 상기 제 3 수단과, 그리고
    (라) 상기 원자로 격납용기통을 둘러싸는 공기의 자연순환에 의해서만 상기 원자로 격납용기통으로부터 열을 제거하도록 유체와 상기 원자로 격납용기통간의 상기 환형 공간내에서 열교환 접촉을 행하기 위한 제 4 수단을 포함하는 것이 특징인 가압수 원자로용 수동안전시스템.
  2. 제 1 항에서, 상기 제 4 수단은 자연순환에 의해서만 상기 방호구조물이 상부로부터 상기 하부에서 상기 하부에서 접촉시키시 위해 자연순환에 의해서만 상기 방호구조물의 상부로부터 그의 하부로 경사지도록 상기 환형공간내에 냉기를 안내하고 또한 상기 원자로 격납용기통에 연하여 열교환접촉상태로 자연순환에 의해서만 상기 하부로부터 그의 상부에 있는 상기 방호구조물의 출구로 상승하도록 상기 환형 공간내의 공기를 안내하기 위한 수단을 포함하는 것이 특징인 가압수 원자로용 수동안전시스템.
  3. 제 2 항에서, 상기 원자로 격납용기통의 상부에 지지된 다수의 분무헤드들과, 가압된 분무유체를 담는 원자로 격납용기 분무축압탱크와, 상기 분무헤드들과 상기 원자로 격납용기분무 축압탱크를 연결하는 도관수단과, 그리고 상기 도관수단내에 설비되어 안전동작에 관계되는 파라메터값에 응답하여 개방되도록 배열된 차단발브를 더 포함하는 것이 특징인 가압수 원자로용 수동안전시스템.
    ※ 참고사항 : 최초출원 내용에 의하여 공개하는 것임.
KR1019870000905A 1986-02-07 1987-02-05 가입수형 원자로의 수동적 유체 안전장치 KR950011978B1 (ko)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
US827115 1986-02-07
US06/827,115 US4753771A (en) 1986-02-07 1986-02-07 Passive safety system for a pressurized water nuclear reactor
US86-827115 1986-02-07

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KR870008334A true KR870008334A (ko) 1987-09-25
KR950011978B1 KR950011978B1 (ko) 1995-10-13

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US (1) US4753771A (ko)
EP (1) EP0232186B1 (ko)
JP (1) JPH0715507B2 (ko)
KR (1) KR950011978B1 (ko)
ES (1) ES2021355B3 (ko)

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US4753771A (en) 1988-06-28
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