IT1263663B - Impianto a reattore nucleare includente mezzi per iniettare refrigerante addizionale nel circuito refrigerante del reattore - Google Patents

Impianto a reattore nucleare includente mezzi per iniettare refrigerante addizionale nel circuito refrigerante del reattore

Info

Publication number
IT1263663B
IT1263663B ITPD930106A ITPD930106A IT1263663B IT 1263663 B IT1263663 B IT 1263663B IT PD930106 A ITPD930106 A IT PD930106A IT PD930106 A ITPD930106 A IT PD930106A IT 1263663 B IT1263663 B IT 1263663B
Authority
IT
Italy
Prior art keywords
supply
refrigerant
refrigerant circuit
water
integration
Prior art date
Application number
ITPD930106A
Other languages
English (en)
Inventor
Michael Mario Corletti
Terry Lee Schulz
Original Assignee
Westinghouse Electric Corp
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 Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Publication of ITPD930106A0 publication Critical patent/ITPD930106A0/it
Publication of ITPD930106A1 publication Critical patent/ITPD930106A1/it
Application granted granted Critical
Publication of IT1263663B publication Critical patent/IT1263663B/it

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
    • 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)

Abstract

Un reattore nucleare a acqua pressurizzata impiega il suo impianto di rimozione di calore residuo per integrare acqua nel circuito refrigerante del reattore da una alimentazione d'acqua di rifornimento nel contenimento durante depressurizzazione e stadi portante a raffreddamento di emergenza passivo mediante alimentazione a gravità del serbatoio di immagazzinamento dell'acqua di rifornimento e allagamento dell'edificio di contenimento. Quando depressurizzazione inizia a causa di una perdita occidentale o controllabile, il sistema o impianto di rimozione di calore residuo viene attivato manualmente e impedisce allagamento del contenimento quando tale azione non è necessaria. Il funzionamento del sistema o impianto di raffreddamento passivo non è compromesso. Un serbatoio di immagazzinamento d'acqua di integrazione ad alta pressione è collegato al circuito refrigerante del reattore mantenendo refrigerante di integrazione o rincalzo alla pressione di funzionamento del reattore. Il sistema o impianto di depressurizzazione a stadi sfoga il circuito del refrigerante al contenimento, riducendo così l'alimentazione di refrigerante di integrazione. Il livello di refrigerante di integrazione può essere rilevato per innescare l'apertura di condotti di depressurizzazione successivi. Le pompe di rimozione del calore residuo spostano acqua del serbatoio di immagazzinamento dell'acqua di rifornimento nel circuito del refrigerante quando il circuito del refrigerante è depressurizzato, impedendo di raggiungere lo stadio di depressurizzazione finale a meno che il livello del refrigerante di integrazione non continui a diminuire. Il sistema di rimozione di calore residuo può pure essere collegato in un ciclo chiuso o anello con il serbatoio d'alimentazione dell'acqua di rifornimento o ricarica per un percorso di rimozione del calore ausiliare.
ITPD930106A 1992-06-24 1993-05-07 Impianto a reattore nucleare includente mezzi per iniettare refrigerante addizionale nel circuito refrigerante del reattore IT1263663B (it)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US07/903,635 US5268943A (en) 1992-06-24 1992-06-24 Nuclear reactor with makeup water assist from residual heat removal system

Publications (3)

Publication Number Publication Date
ITPD930106A0 ITPD930106A0 (it) 1993-05-07
ITPD930106A1 ITPD930106A1 (it) 1994-11-07
IT1263663B true IT1263663B (it) 1996-08-27

Family

ID=25417838

Family Applications (1)

Application Number Title Priority Date Filing Date
ITPD930106A IT1263663B (it) 1992-06-24 1993-05-07 Impianto a reattore nucleare includente mezzi per iniettare refrigerante addizionale nel circuito refrigerante del reattore

Country Status (6)

Country Link
US (1) US5268943A (it)
JP (1) JP3121475B2 (it)
KR (1) KR100294410B1 (it)
CN (1) CN1033726C (it)
GB (1) GB2268312B (it)
IT (1) IT1263663B (it)

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KR20010067010A (ko) * 2000-11-23 2001-07-12 이철상 후막형 전계발광소자용 바인더 조성물 및 이를 포함하는전계발광소자
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US8160197B2 (en) * 2007-03-06 2012-04-17 Areva Np Nuclear power plant using nanoparticies in closed circuits of emergency systems and related method
CN101447239B (zh) * 2008-12-22 2012-10-03 岭澳核电有限公司 核电站大修期间加快一回路排水的方法
US8559584B2 (en) * 2010-12-20 2013-10-15 Westinghouse Electric Company Llc Nuclear reactor automatic depressurization system
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KR101071415B1 (ko) 2011-04-15 2011-10-07 한국수력원자력 주식회사 Ｓｂｏ와 ｌｏｃａ 대처 피동 고압안전주입탱크 시스템
US9583221B2 (en) 2011-06-15 2017-02-28 Bwxt Nuclear Energy, Inc. Integrated emergency core cooling system condenser for pressurized water reactor
KR101229954B1 (ko) * 2011-09-08 2013-02-06 한전원자력연료 주식회사 원자력 발전소의 피동형 냉각 시스템
KR101229953B1 (ko) * 2011-09-08 2013-02-06 한전원자력연료 주식회사 사용후핵연료 저장조 피동형 냉각장치
KR101224023B1 (ko) * 2011-09-09 2013-01-21 한국수력원자력 주식회사 피동보조 급수계통을 이용한 경수로의 응급잔열제거 및 격납용기 냉각계통
US9312035B2 (en) * 2011-11-14 2016-04-12 Westinghouse Electric Company Llc Semi-portable emergency cooling system for removing decay heat from a nuclear reactor
KR101307744B1 (ko) * 2012-01-25 2013-09-11 한국수력원자력 주식회사 원자로 냉각재의 자동 보충 장치 및 방법
CN103295657A (zh) * 2012-02-29 2013-09-11 上海核工程研究设计院 核反应堆余热排出系统
US9208906B2 (en) * 2012-06-13 2015-12-08 Westinghouse Electric Company Llc Passive system for cooling the core of a nuclear reactor
US9748004B2 (en) * 2012-06-13 2017-08-29 Westinghouse Electric Company Llc Combined core makeup tank and heat removal system for a small modular pressurized water reactor
KR101434532B1 (ko) 2012-07-12 2014-08-27 한국원자력연구원 안전주입탱크를 이용한 피동안전주입계통
US9536629B2 (en) * 2012-07-24 2017-01-03 Westinghouse Electric Company Llc Passive power production during a nuclear station blackout
KR101373676B1 (ko) 2012-08-03 2014-03-13 한국원자력연구원 분리된 질소탱크로 가압되는 질소가스탱크 분리형 안전주입탱크 시스템
KR101343051B1 (ko) 2012-08-03 2013-12-18 한국원자력연구원 안전밸브를 이용한 혼합형 안전주입탱크 시스템
CN202887748U (zh) * 2012-08-20 2013-04-17 中国核电工程有限公司 一种应对全厂断电事故的非能动排热装置
MY187908A (en) * 2012-09-27 2021-10-28 China Nuclear Power Eng Co Ltd Combined active and passive secondary-side reactor core heat removal apparatus
US11373768B2 (en) * 2013-03-12 2022-06-28 Bwxt Mpower, Inc. Refueling water storage tank (RWST) with tailored passive emergency core cooling (ECC) flow
KR20150132510A (ko) 2013-03-15 2015-11-25 비더블유엑스티 엠파워, 인크. 장기간 반응기 냉각을 위한 수동형 기법
US9779840B2 (en) 2013-10-28 2017-10-03 Bwxt Mpower, Inc. PWR decay heat removal system in which steam from the pressurizer drives a turbine which drives a pump to inject water into the reactor pressure vessel
KR101446709B1 (ko) 2014-02-27 2014-10-06 한국원자력연구원 열혼합을 방지하는 피동고압안전주입 시스템
US9875817B2 (en) 2014-06-09 2018-01-23 Bwxt Mpower, Inc. Nuclear reactor support and seismic restraint with in-vessel core retention cooling features
US10529458B2 (en) 2014-07-22 2020-01-07 Bwxt Mpower, Inc. Integral isolation valve systems for loss of coolant accident protection
KR101963479B1 (ko) * 2016-09-12 2019-03-28 한국도로공사 콘크리트의 강도발현 확인장치를 포함하는 양생포
US20190326026A1 (en) * 2017-01-03 2019-10-24 Korea Hydro & Nuclear Power Co., Ltd Nuclear power plant having improved cooling performance and method for operating same

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Also Published As

Publication number Publication date
GB2268312A (en) 1994-01-05
US5268943A (en) 1993-12-07
ITPD930106A1 (it) 1994-11-07
CN1033726C (zh) 1997-01-01
CN1080772A (zh) 1994-01-12
GB9308466D0 (en) 1993-06-09
JPH0659075A (ja) 1994-03-04
GB2268312B (en) 1996-04-24
KR940001183A (ko) 1994-01-10
ITPD930106A0 (it) 1993-05-07
KR100294410B1 (ko) 2001-09-17
JP3121475B2 (ja) 2000-12-25

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