LT2016016A - Emergency core cooling system of nuclear power plant - Google Patents

Emergency core cooling system of nuclear power plant

Info

Publication number
LT2016016A
LT2016016A LT2016016A LT2016016A LT2016016A LT 2016016 A LT2016016 A LT 2016016A LT 2016016 A LT2016016 A LT 2016016A LT 2016016 A LT2016016 A LT 2016016A LT 2016016 A LT2016016 A LT 2016016A
Authority
LT
Lithuania
Prior art keywords
pipe
valve
lpfl
feedwater
fracture
Prior art date
Application number
LT2016016A
Other languages
Lithuanian (lt)
Other versions
LT6317B (en
Inventor
Yasunori Nagata
Tomohiro Nakamura
Masayoshi Matsuura
Kazuaki Kito
Yoshihiko Ishii
Original Assignee
Hitachi-Ge Nuclear Energy, Ltd.
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 Hitachi-Ge Nuclear Energy, Ltd. filed Critical Hitachi-Ge Nuclear Energy, Ltd.
Publication of LT2016016A publication Critical patent/LT2016016A/en
Publication of LT6317B publication Critical patent/LT6317B/en

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
    • G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/084—Boiling water reactors
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

To provide a reactor capable of achieving cold shutdown of a reactor core by each single system in a configuration of an Emergency Core Cooling System (ECCS) including a Reactor Core Isolation Cooling system (RCIC). In an ECCS of a nuclear power plant including ECCSs sectioned into at least three sections, in which a first section in the ECCSs has a RCIC having a high-pressure injection pump driven by a turbine, a Low Pressure Flooder system (LPFL) having a low-pressure injection pump driven by a motor and an emergency power source, water is supplied into a reactor pressure vessel (RPV) through a first pipe and a first feedwater pipe by the RCIC, and water is supplied into the RPV through a second pipe and a second feedwater pipe by the LPFL, and an Automatic Depressurization System (ADS) which is used in common by the ECCSs sectioned into three sections, the ECCS includes a fracture detector detecting a fracture in the first feedwater pipe or the second feedwater pipe, and a first valve provided in the second pipe of the LPFL and a tie-line connecting the first pipe and the second pipe through a second valve in an upstream side of the first valve, in which the fracture detector detects a fracture of the second feedwater pipe and operates the first valve and the second valve to supply water into the RPV from the LPFL through the tie line and the first feedwater pipe.
LT2016016A 2015-02-06 2016-02-05 NUCLEAR POWER ACTIVATED AREA EMERGENCY COOLING SYSTEM LT6317B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2015022207A JP6348855B2 (en) 2015-02-06 2015-02-06 Emergency core cooling system for nuclear power plants

Publications (2)

Publication Number Publication Date
LT2016016A true LT2016016A (en) 2016-08-10
LT6317B LT6317B (en) 2016-09-12

Family

ID=55641812

Family Applications (1)

Application Number Title Priority Date Filing Date
LT2016016A LT6317B (en) 2015-02-06 2016-02-05 NUCLEAR POWER ACTIVATED AREA EMERGENCY COOLING SYSTEM

Country Status (3)

Country Link
JP (1) JP6348855B2 (en)
GB (1) GB2537957B (en)
LT (1) LT6317B (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US10706973B2 (en) * 2017-05-02 2020-07-07 Ge-Hitachi Nuclear Energy Americas Llc Very simplified boiling water reactors for commercial electricity generation
US10867712B2 (en) 2017-06-28 2020-12-15 Ge-Hitachi Nuclear Energy Americas Llc Isolation condenser systems for nuclear reactor commercial electricity generation
US11380451B2 (en) 2017-08-15 2022-07-05 Ge-Hitachi Nuclear Energy Americas Llc Depressurization and coolant injection systems for very simplified boiling water reactors

Family Cites Families (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5860293A (en) * 1981-10-06 1983-04-09 株式会社東芝 Emergency core cooling system
JPS59184890A (en) * 1983-04-04 1984-10-20 株式会社日立製作所 Reactor cooling system facility
JPH0740073B2 (en) * 1986-01-09 1995-05-01 株式会社東芝 Automatic decompression system
JPS63191000A (en) * 1987-02-03 1988-08-08 Toshiba Corp Breaking position detecting method for pipeline
JPH01217297A (en) * 1988-02-26 1989-08-30 Hitachi Ltd Protecting device of nuclear reactor plant
JPH03296692A (en) * 1990-04-17 1991-12-27 Toshiba Corp Detecting device of fracture of piping of residual heat removing equipment
US5213755A (en) * 1991-04-01 1993-05-25 General Electric Company Low pressure coolant injection modification for boiling water reactors
JPH0587968A (en) * 1991-09-25 1993-04-09 Toshiba Corp Recircuration device of nuclear reactor
US5511102A (en) * 1995-03-15 1996-04-23 General Electric Company Apparatus for draining lower drywell pool water into suppresion pool in boiling water reactor
JP2004061192A (en) * 2002-07-25 2004-02-26 Toshiba Corp Nuclear power plant
JP2008185572A (en) * 2007-01-31 2008-08-14 Toshiba Corp Alternative cooling equipment for nuclear reactors
JP4956316B2 (en) * 2007-07-26 2012-06-20 株式会社東芝 Emergency core cooling system
EP2515309A4 (en) * 2009-12-14 2015-04-08 Toshiba Kk MITIGATION SYSTEM OF REACTOR DISTURBANCES
JP2011185741A (en) * 2010-03-09 2011-09-22 Hitachi-Ge Nuclear Energy Ltd Emergency core cooling system

Also Published As

Publication number Publication date
GB2537957A (en) 2016-11-02
LT6317B (en) 2016-09-12
GB2537957B (en) 2017-06-07
GB201602015D0 (en) 2016-03-23
JP2016145726A (en) 2016-08-12
JP6348855B2 (en) 2018-06-27

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Legal Events

Date Code Title Description
BB1A Patent application published

Effective date: 20160629

FG9A Patent granted

Effective date: 20160912

PD9A Change of patent owner

Owner name: HITACHI GE VERNOVA NUCLEAR ENERGY, LTD., 1-1, 3-CHOME, SAIWAI-CHO, HITACHI-SHI, IBARAKI, 317-0073, JP

Effective date: 20251201