BR112013020721A2 - sistema de remoção de calor e método para utilização com um reator nuclear - Google Patents

sistema de remoção de calor e método para utilização com um reator nuclear

Info

Publication number
BR112013020721A2
BR112013020721A2 BR112013020721A BR112013020721A BR112013020721A2 BR 112013020721 A2 BR112013020721 A2 BR 112013020721A2 BR 112013020721 A BR112013020721 A BR 112013020721A BR 112013020721 A BR112013020721 A BR 112013020721A BR 112013020721 A2 BR112013020721 A2 BR 112013020721A2
Authority
BR
Brazil
Prior art keywords
reactor
nuclear reactor
removal system
heat removal
vessel
Prior art date
Application number
BR112013020721A
Other languages
English (en)
Inventor
Colin Maxwell Sexton
John Harold Matonic
Jonathan James Arthur
Maurice Andrew Fountain
Richard Biasca
Zachary James Houghton
Original Assignee
Nuscale Power Llc
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 Nuscale Power Llc filed Critical Nuscale Power Llc
Publication of BR112013020721A2 publication Critical patent/BR112013020721A2/pt

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24Promoting flow of the coolant
    • G21C15/243Promoting flow of the coolant for liquids
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D1/00Details of nuclear power plant
    • G21D1/02Arrangements of auxiliary equipment
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/32Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
    • G21C1/322Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed above the core
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/02Devices or arrangements for monitoring coolant or moderator
    • G21C17/022Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear 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

sistema de remoção de calor e método para utilização com um reator nuclear a presente invenção refere-se a um reator nuclear que inclui um vaso de reator, um vaso de contenção que circunda o vaso de reator, e um condensador que recebe um refrigerante de dentro do vaso de reator. o vaso de contenção e o condensador estão pelo menos parcialmente submersos dentro de um tanque de líquido de reator comum.
BR112013020721A 2011-02-15 2012-02-14 sistema de remoção de calor e método para utilização com um reator nuclear BR112013020721A2 (pt)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
US201161463282P 2011-02-15 2011-02-15
US13/303,408 US8867689B2 (en) 2011-02-15 2011-11-23 Heat removal system and method for use with a nuclear reactor
PCT/US2012/025001 WO2012112509A2 (en) 2011-02-15 2012-02-14 Heat removal system and method for use with a nuclear reactor

Publications (1)

Publication Number Publication Date
BR112013020721A2 true BR112013020721A2 (pt) 2016-10-18

Family

ID=46636876

Family Applications (1)

Application Number Title Priority Date Filing Date
BR112013020721A BR112013020721A2 (pt) 2011-02-15 2012-02-14 sistema de remoção de calor e método para utilização com um reator nuclear

Country Status (10)

Country Link
US (1) US8867689B2 (pt)
EP (1) EP2676277B1 (pt)
JP (2) JP6411739B2 (pt)
KR (1) KR101940197B1 (pt)
CN (1) CN103477394B (pt)
BR (1) BR112013020721A2 (pt)
CA (1) CA2827493C (pt)
ES (1) ES2710347T3 (pt)
PL (1) PL2676277T3 (pt)
WO (1) WO2012112509A2 (pt)

Families Citing this family (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9583221B2 (en) 2011-06-15 2017-02-28 Bwxt Nuclear Energy, Inc. Integrated emergency core cooling system condenser for pressurized water reactor
US9589685B2 (en) * 2012-05-21 2017-03-07 Smr Inventec, Llc Passive reactor cooling system
US11901088B2 (en) 2012-05-04 2024-02-13 Smr Inventec, Llc Method of heating primary coolant outside of primary coolant loop during a reactor startup operation
US11935663B2 (en) 2012-05-21 2024-03-19 Smr Inventec, Llc Control rod drive system for nuclear reactor
US10096389B2 (en) 2012-05-21 2018-10-09 Smr Inventec, Llc Loss-of-coolant accident reactor cooling system
US11373768B2 (en) 2013-03-12 2022-06-28 Bwxt Mpower, Inc. Refueling water storage tank (RWST) with tailored passive emergency core cooling (ECC) flow
WO2014200600A2 (en) 2013-03-15 2014-12-18 Babcock & Wilcox Mpower, Inc. Passive techniques for long-term reactor cooling
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
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
KR102515866B1 (ko) * 2016-05-02 2023-03-29 테라파워, 엘엘씨 개선된 용융 연료 원자로 열 관리 구성
WO2018084940A2 (en) * 2016-09-16 2018-05-11 Elysium Industries Ltd. Reactor control
CN106531243B (zh) * 2016-11-03 2021-08-17 中国核电工程有限公司 一种模块化小型压水堆事故下余热排出系统及厂房
US10755826B2 (en) 2017-11-10 2020-08-25 Nugen, Llc Integrated system for converting nuclear energy into electrical, rotational, and thermal energy
CN111916232B (zh) * 2020-08-13 2022-03-01 中国核动力研究设计院 一种轻水核反应堆结构
US11421589B1 (en) 2021-05-18 2022-08-23 Nugen, Llc Integrated system for converting nuclear energy into electrical, mechanical, and thermal energy
CN113744899B (zh) * 2021-06-02 2024-06-18 上海核工程研究设计院股份有限公司 一种核反应堆的启动加热系统
CN114141397A (zh) * 2021-11-05 2022-03-04 中广核研究院有限公司 核反应装置及净化系统

Family Cites Families (20)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5011652A (en) * 1986-09-19 1991-04-30 Hitachi, Ltd. Nuclear power facilities
IT1225690B (it) * 1988-09-15 1990-11-22 Ansaldo Spa Reattore nucleare a sicurezza intrinseca del tipo ad acqua in pressione
US5247553A (en) * 1991-11-27 1993-09-21 The United States Of America As Represented By The United States Department Of Energy Submerged passively-safe power plant
KR100189168B1 (ko) * 1995-12-01 1999-06-01 윤덕용 원자로의 피동 격납용기 냉각장치
US6249561B1 (en) 1995-11-09 2001-06-19 General Electric Company Combination containment cooling and residual heat removal condenser system for nuclear reactors
EP1241323A1 (de) * 2001-03-15 2002-09-18 Siemens Aktiengesellschaft Verfahren zum Betrieb einer Dampfkraftanlage sowie Dampfkraftanlage
JP2003043176A (ja) * 2001-07-30 2003-02-13 Mitsubishi Heavy Ind Ltd 冷却系統一体型原子炉の崩壊熱除去装置
US7558360B1 (en) * 2003-12-31 2009-07-07 General Electric Company Core catcher cooling
JP2006138744A (ja) * 2004-11-12 2006-06-01 Mitsubishi Heavy Ind Ltd 原子炉の冷却装置
SE532185C2 (sv) * 2007-04-10 2009-11-10 Westinghouse Electric Sweden Förfarande för att driva en reaktor hos en kärnanläggning
US8170173B2 (en) * 2007-11-15 2012-05-01 The State Of Oregon Acting By And Through The State Board Of Higher Education On Behalf Of Oregon State University Passive emergency feedwater system
US8588360B2 (en) * 2007-11-15 2013-11-19 The State Of Oregon Acting By And Through The State Board Of Higher Education On Behalf Of Oregon State University Evacuated containment vessel for a nuclear reactor
US8891723B2 (en) * 2007-11-15 2014-11-18 State of Oregon Acting by and Through The State Board of Higher Education on Behalf or Oregon State University, The Oregon State University Stable startup system for a nuclear reactor
US8687759B2 (en) * 2007-11-15 2014-04-01 The State Of Oregon Acting By And Through The State Board Of Higher Education On Behalf Of Oregon State University Internal dry containment vessel for a nuclear reactor
JP4592773B2 (ja) 2008-02-29 2010-12-08 株式会社東芝 静的冷却減圧系および加圧水型原子力プラント
JP5235614B2 (ja) * 2008-11-05 2013-07-10 日立Geニュークリア・エナジー株式会社 原子力プラント及び制御方法
US8184762B2 (en) * 2008-11-06 2012-05-22 Iwatt, Inc. Digital phase lock loop with multi-phase master clock
US8848855B2 (en) * 2008-11-17 2014-09-30 Nuscale Power, Llc Seismically isolated containment vessel
US8437446B2 (en) * 2008-11-17 2013-05-07 Nuscale Power, Llc Steam generator flow by-pass system
US8744035B1 (en) * 2008-11-18 2014-06-03 Nuscale Power, Llc Reactor vessel coolant deflector shield

Also Published As

Publication number Publication date
CN103477394A (zh) 2013-12-25
WO2012112509A2 (en) 2012-08-23
EP2676277A2 (en) 2013-12-25
CA2827493A1 (en) 2012-08-23
JP2017194479A (ja) 2017-10-26
JP6349443B2 (ja) 2018-06-27
US8867689B2 (en) 2014-10-21
JP6411739B2 (ja) 2018-10-24
ES2710347T3 (es) 2019-04-24
US20120207260A1 (en) 2012-08-16
WO2012112509A3 (en) 2012-11-22
CN103477394B (zh) 2017-02-15
JP2014506998A (ja) 2014-03-20
CA2827493C (en) 2017-03-14
KR101940197B1 (ko) 2019-01-18
EP2676277B1 (en) 2018-11-21
PL2676277T3 (pl) 2019-04-30
EP2676277A4 (en) 2017-03-15
KR20140031199A (ko) 2014-03-12

Similar Documents

Publication Publication Date Title
BR112013020721A2 (pt) sistema de remoção de calor e método para utilização com um reator nuclear
EA201491488A1 (ru) Интегрированный жидкосолевой реактор
HK1216206A1 (zh) 管理核反應堆廢燃料棒
WO2013041085A3 (de) Dual fluid reaktor
EP3166114A4 (en) Cooling filter vent system for static containment vessel, and nuclear power plant
EP2924690A4 (en) CORE REACTOR WITH LIQUID METAL REFRIGERANT
GB2524922B (en) Cooling systems for spent nuclear fuel, casks including the cooling systems, and methods for cooling spent nuclear fuel
MY195237A (en) Process For The Preparation of a Zeolitic Material
BR112013021464A2 (pt) método para reduzir a demanda química de oxigênio recalcitrante de um líquido em um sistema de água.
ZA201400117B (en) Heat pipe based passive residual heat removal system for spent fuel pool
CR20140300A (es) Proceso para la preparación de una solucion acuosa que comprende al menos un carbonato acido alcalinoterreo y su uso
BR112012031266A2 (pt) método, aparelho, meio legível por computador para armazenar as instruções de programa e sistema.
EP2839480A4 (en) DEFENSE SAFETY PARADIGM IN DEPTH FOR NUCLEAR REACTOR
CL2013000832A1 (es) Metodo para tratar agua que contiene iones de mg, ca y na disuelto, que comprende contactar el agua con una resina de intercambio cationico para remover dichos iones, tratar dicha resina con acido nitrico para producir un eluyente que contenga los iones, agregar carbonato para precipitar los iones ca y mg como carbonatos, separarlos de la solucion y tratar el eluyente.
FI20126326A (fi) Ydinreaktorin suojasäiliö
ES2546928R1 (es) Sistema de inyección de hidrógeno de arranque/parada para reactores de agua en ebullición (BWRs), y procedimiento para el mismo
PL2834549T3 (pl) Samouszczelniający system przechowywania cieczy z wewnętrznym elementem pochłaniającym energię
AR101929A1 (es) Método para la recuperación de líquido iónico y su sistema
EP2577680A4 (en) LIQUID FUEL-FISSION REACTOR
SI2638546T1 (sl) Postopek za kondicioniranje odpadkov, izvirajoäśih iz dekomisioniranja nuklearnih elektrarn
ZA201208024B (en) Treatment of a heater tube intended for a pressurizer of the primary cooling system of a nuclear reactor
WO2014197068A3 (en) Upper vessel transport
SM201000065A (it) Impianto e metodo per la bonifica veloce di serbatoi interrati adibiti al contenimento di carburantiliquidi
EP2975613A4 (en) COOLING SYSTEM FOR STORED CORE FUEL
FR3015293B1 (fr) Cuve de traitement thermique d'un liquide contamine par des agents pathogenes, installation de decontamination comprenant une telle cuve et procede de decontamination associe

Legal Events

Date Code Title Description
B08F Application dismissed because of non-payment of annual fees [chapter 8.6 patent gazette]

Free format text: REFERENTE A 6A ANUIDADE.

B08K Patent lapsed as no evidence of payment of the annual fee has been furnished to inpi [chapter 8.11 patent gazette]