MX2013010564A - Metodo y sistema para una trayectoria alternativa de remocion de energia rpv. - Google Patents

Metodo y sistema para una trayectoria alternativa de remocion de energia rpv.

Info

Publication number
MX2013010564A
MX2013010564A MX2013010564A MX2013010564A MX2013010564A MX 2013010564 A MX2013010564 A MX 2013010564A MX 2013010564 A MX2013010564 A MX 2013010564A MX 2013010564 A MX2013010564 A MX 2013010564A MX 2013010564 A MX2013010564 A MX 2013010564A
Authority
MX
Mexico
Prior art keywords
rpv
removal path
alternate
energy removal
heat sink
Prior art date
Application number
MX2013010564A
Other languages
English (en)
Other versions
MX349010B (es
Inventor
Robert J Ginsberg
John R Bass
Original Assignee
Ge Hitachi Nucl Energy America
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 Ge Hitachi Nucl Energy America filed Critical Ge Hitachi Nucl Energy America
Publication of MX2013010564A publication Critical patent/MX2013010564A/es
Publication of MX349010B publication Critical patent/MX349010B/es

Links

Classifications

    • 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
    • G21C9/004—Pressure suppression
    • 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
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004—Pressure suppression
    • G21C9/012—Pressure suppression by thermal accumulation or by steam condensation, e.g. ice condensers
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/02—Arrangements of auxiliary equipment
    • 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
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • 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

Un método y un sistema para una trayectoria para ¡a remoción de energía para un recipiente a presión del reactor (RPV) de un reactor de agua ligera. Un par de válvulas de aislamiento de contención operadas en forma manual, una ubicada dentro y una ubicada fuera de la contención primaria, se usan para abrir y cerrar la línea de extracción de vapor que está acoplada en comunicación de fluidos entre el RPV y el sumidero de calor. El sumidero de calor está ubicado fuera de la contención primaria. Una fuente de energía eléctrica externa no es requerida para operar el sistema o para llevar a cabo el método.
MX2013010564A 2012-09-13 2013-09-13 Metodo y sistema para una trayectoria alternativa de remocion de energia rpv. MX349010B (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US13/613,281 US20140072090A1 (en) 2012-09-13 2012-09-13 Method and system for an alternate rpv energy removal path

Publications (2)

Publication Number Publication Date
MX2013010564A true MX2013010564A (es) 2014-03-21
MX349010B MX349010B (es) 2017-07-06

Family

ID=49303699

Family Applications (1)

Application Number Title Priority Date Filing Date
MX2013010564A MX349010B (es) 2012-09-13 2013-09-13 Metodo y sistema para una trayectoria alternativa de remocion de energia rpv.

Country Status (5)

Country Link
US (1) US20140072090A1 (es)
EP (1) EP2709112B1 (es)
JP (1) JP6082677B2 (es)
MX (1) MX349010B (es)
TW (1) TWI598886B (es)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9738440B2 (en) 2012-12-20 2017-08-22 Ge-Hitachi Nuclear Energy Americas Llc Entrainment-reducing assembly, system including the assembly, and method of reducing entrainment of gases with the assembly

Family Cites Families (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6036987A (ja) * 1983-08-10 1985-02-26 株式会社東芝 原子炉の主蒸気バイパス装置
DE3643929C1 (en) * 1986-12-22 1988-04-28 Kernforschungsanlage Juelich Arrangement for residual heat removal for high-temperature reactors
JPS643594A (en) * 1987-06-26 1989-01-09 Hitachi Ltd Emergency reactor core cooler
JPH0762717B2 (ja) * 1988-09-21 1995-07-05 株式会社日立製作所 高温高圧容器への注液装置
US5106571A (en) * 1989-03-20 1992-04-21 Wade Gentry E Containment heat removal system
JPH03183995A (ja) * 1989-12-14 1991-08-09 Toshiba Corp 隔離時復水器
JPH05157877A (ja) * 1991-12-09 1993-06-25 Toshiba Corp 原子力発電所の冷却設備
JPH05264774A (ja) * 1992-03-17 1993-10-12 Toshiba Corp 非常時原子炉冷却装置
US5426681A (en) * 1994-01-04 1995-06-20 General Electric Company Boiling water reactor with combined active and passive safety systems
JPH11258378A (ja) * 1998-03-11 1999-09-24 Ishikawajima Harima Heavy Ind Co Ltd クエンチャサポートのアンカ構造
JP5676905B2 (ja) * 2010-04-09 2015-02-25 株式会社東芝 逃し安全弁の駆動システム
DE102010035510A1 (de) * 2010-08-25 2012-03-01 Areva Np Gmbh Verfahren zur Druckentlastung eines Kernkraftwerks, Druckentlastungssystem für ein Kernkraftwerk sowie zugehöriges Kernkraftwerk
US8848854B2 (en) * 2010-09-24 2014-09-30 Westinghouse Electric Company Llc Alternate feedwater injection system to mitigate the effects of aircraft impact on a nuclear power plant
US8638898B2 (en) * 2011-03-23 2014-01-28 Babcock & Wilcox Mpower, Inc. Emergency core cooling system for pressurized water reactor
TWM425370U (en) * 2011-10-18 2012-03-21 Iner Aec Executive Yuan A safety/relief valve discharge system in a BWR
JP5911762B2 (ja) * 2012-06-29 2016-04-27 株式会社東芝 原子力プラントおよび静的格納容器冷却系

Also Published As

Publication number Publication date
TW201421490A (zh) 2014-06-01
TWI598886B (zh) 2017-09-11
EP2709112B1 (en) 2017-11-15
EP2709112A2 (en) 2014-03-19
MX349010B (es) 2017-07-06
JP2014055951A (ja) 2014-03-27
EP2709112A3 (en) 2016-04-13
JP6082677B2 (ja) 2017-02-15
US20140072090A1 (en) 2014-03-13

Similar Documents

Publication Publication Date Title
CL2015002718A1 (es) Interfaz para sistema de energía renovable
EP3239274A4 (en) Carbonizing furnace, pyrolytic furnace, water gas generation system, hydrogen gas generation system, and power generation system
NZ596549A (en) Apparatus and method for processing biomass
GB201504121D0 (en) Secondary-side passive residual heat discharge system for nuclear power plant steam generator
GB2531190A8 (en) Passive concrete containment cooling system
GB2523949A8 (en) High-pressure safe injection system for nuclear power stations
IN2013MN00300A (es)
ZA202101622B (en) Acousto-optic leakage monitoring system for nuclear power plant main steam pipeline
ZA201802091B (en) Nuclear power plant spent fuel negative pressure unloading system
IN2014DN07449A (es)
WO2018204857A3 (en) Gas-cooled pressure tube reactor
GB2533735B (en) Apparatus for inspecting a reactor pressure vessel of a nuclear power plant
EP2884496A4 (en) NUCLEAR REACTOR MONITORING DEVICE, NUCLEAR REACTOR CONTROL DEVICE, AND NUCLEAR POWER GENERATION PLANT
WO2015142407A3 (en) Passively initiated depressurization valve for light water reactors
EP3631815A4 (en) VERY SIMPLIFIED BOILING WATER REACTORS FOR COMMERCIAL ELECTRICITY GENERATION
EP3100275A4 (en) Floating nuclear power reactor with a self-cooling containment structure and an emergency heat exchange system
MX2013010564A (es) Metodo y sistema para una trayectoria alternativa de remocion de energia rpv.
ZA201309394B (en) Steam power plant with an additional flexible solar system for the flexible integration of solar energy
GB2492958B (en) A distribution pipeline power plant
ZA201808123B (en) Method for ensuring hydrogen explosion safety at nuclear power plant
MX346155B (es) Metodo y sistema para el enfriamiento externo alternativo de una pila de supresion para un bwr.
PH12015500787A1 (en) Method for generating fresh water
GB202011406D0 (en) Nuclear power generation system
UA117057C2 (uk) Спосіб вилучення пробки і блока виймального при перевантаженні ядерного реактора
WO2015171187A3 (en) Floating nuclear power reactor with a self-cooling multiple component containment structure

Legal Events

Date Code Title Description
FG Grant or registration