HK1202344A1 - Steam generator for a nuclear reactor - Google Patents

Steam generator for a nuclear reactor

Info

Publication number
HK1202344A1
HK1202344A1 HK15102785.8A HK15102785A HK1202344A1 HK 1202344 A1 HK1202344 A1 HK 1202344A1 HK 15102785 A HK15102785 A HK 15102785A HK 1202344 A1 HK1202344 A1 HK 1202344A1
Authority
HK
Hong Kong
Prior art keywords
steam generator
nuclear reactor
nuclear
reactor
steam
Prior art date
Application number
HK15102785.8A
Other languages
English (en)
Chinese (zh)
Inventor
John T Groome
Sooyun Joh
James Allan Nylander
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 HK1202344A1 publication Critical patent/HK1202344A1/xx

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
    • 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
    • G21C15/16—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants comprising means for separating liquid and steam
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00—Methods of steam generation characterised by form of heating method
    • F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/16—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour
    • F22B1/162—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour in combination with a nuclear installation
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • 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
    • 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
    • G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/006—Details of nuclear power plant primary side of steam generators
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/32—Integral 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
    • G21C1/322—Integral 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
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Sustainable Development (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Energy (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
HK15102785.8A 2012-04-20 2015-03-18 Steam generator for a nuclear reactor HK1202344A1 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US13/451,759 US9230697B2 (en) 2012-04-20 2012-04-20 Steam generator for a nuclear reactor
PCT/US2013/037292 WO2013158950A2 (en) 2012-04-20 2013-04-19 Steam generator for a nuclear reactor

Publications (1)

Publication Number Publication Date
HK1202344A1 true HK1202344A1 (en) 2015-09-25

Family

ID=49380114

Family Applications (1)

Application Number Title Priority Date Filing Date
HK15102785.8A HK1202344A1 (en) 2012-04-20 2015-03-18 Steam generator for a nuclear reactor

Country Status (9)

Country Link
US (2) US9230697B2 (ko)
EP (1) EP2859556B1 (ko)
JP (5) JP2015514995A (ko)
KR (2) KR102159794B1 (ko)
CN (1) CN104272397B (ko)
CA (2) CA2869901C (ko)
HK (1) HK1202344A1 (ko)
PL (1) PL2859556T3 (ko)
WO (1) WO2013158950A2 (ko)

Families Citing this family (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9230697B2 (en) 2012-04-20 2016-01-05 Nuscale Power, Llc Steam generator for a nuclear reactor
US9997262B2 (en) 2013-12-26 2018-06-12 Nuscale Power, Llc Integral reactor pressure vessel tube sheet
US9897308B2 (en) 2013-12-26 2018-02-20 Nuscale Power, Llc Steam generator with tube aligning orifice
GB2522881B (en) * 2014-02-07 2018-05-09 Rolls Royce Power Eng Plc Steam generator
WO2016106051A1 (en) * 2014-12-23 2016-06-30 Nuscale Power, Llc Light water reactor with condensing steam generator
US10685752B2 (en) * 2015-02-10 2020-06-16 Nuscale Power, Llc Steam generator with inclined tube sheet
US20170023305A1 (en) * 2015-07-22 2017-01-26 General Electric Company Steam generator having an integrated modular heat exchanger
CN107785084B (zh) * 2017-07-31 2023-10-27 清华大学天津高端装备研究院 一种自加压型的一体化冷容器型反应堆
US10755826B2 (en) 2017-11-10 2020-08-25 Nugen, Llc Integrated system for converting nuclear energy into electrical, rotational, and thermal energy
RU2725161C1 (ru) * 2019-11-29 2020-06-30 федеральное государственное бюджетное образовательное учреждение высшего образования "Национальный исследовательский университет "МЭИ" (ФГБОУ ВО "НИУ "МЭИ") Охлаждаемая стенка токамака
JP7321953B2 (ja) 2020-02-17 2023-08-07 株式会社神戸製鋼所 自動溶接システム、溶接方法、学習装置、学習済みモデルの生成方法、学習済みモデル、推定装置、推定方法、及びプログラム
US11421589B1 (en) 2021-05-18 2022-08-23 Nugen, Llc Integrated system for converting nuclear energy into electrical, mechanical, and thermal energy

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US4174123A (en) * 1971-07-14 1979-11-13 The Babcock & Wilcox Company Vessel penetration apparatus
US3941187A (en) 1971-07-14 1976-03-02 The Babcock & Wilcox Company Consolidated nuclear steam generator
BE786097A (fr) * 1971-07-14 1973-01-10 Babcock & Wilcox Co Perfectionnements aux generateurs de vapeur du type nucleaire
JPS5723761Y2 (ko) * 1972-10-16 1982-05-24
ZA74176B (en) * 1973-01-29 1974-12-24 Babcock & Wilcox Co Consolidated nuclear steam generator
JPS5127801A (ja) 1974-08-06 1976-03-09 Kubota Ltd Sakushonhetsudo
CA1122202A (en) * 1979-11-23 1982-04-20 Gordon M. Cameron Heat exchanger having improved tube layout
JPS62163994A (ja) * 1986-01-14 1987-07-20 株式会社東芝 高速増殖炉
US5263067A (en) * 1992-06-24 1993-11-16 Westinghouse Electric Corp. Locating hot and cold-legs in a nuclear powered steam generation system
JP3511531B2 (ja) * 1994-12-14 2004-03-29 株式会社東芝 蒸気発生器
JP2000346306A (ja) * 1999-06-03 2000-12-15 Ishikawajima Harima Heavy Ind Co Ltd 蒸気発生器の給水入口部
JP4101422B2 (ja) 1999-12-28 2008-06-18 株式会社東芝 液体金属冷却型原子炉および液体金属冷却型原子力プラント
JP3524884B2 (ja) * 2001-03-02 2004-05-10 三菱重工業株式会社 高速増殖炉
US6813328B2 (en) 2002-12-13 2004-11-02 Curtiss-Wright Electro-Mechanical Corporation Nuclear reactor submerged high temperature spool pump
JP2006162339A (ja) * 2004-12-03 2006-06-22 Mitsubishi Heavy Ind Ltd 熱交換器及び原子炉
CN101307897B (zh) * 2008-06-24 2010-06-23 清华大学 保证气冷堆一回路介质在蒸汽发生器内流动均匀性的装置
US8971477B2 (en) * 2009-06-10 2015-03-03 Babcock & Wilcox Mpower, Inc. Integral helical coil pressurized water nuclear reactor
JP5127801B2 (ja) 2009-09-30 2013-01-23 株式会社藤商事 遊技機
EP2534660A1 (en) 2010-02-05 2012-12-19 Smr, Llc Nuclear reactor system having natural circulation of primary coolant
US9336907B2 (en) * 2010-04-23 2016-05-10 Atomic Energy Of Canada Limited Pressure-tube reactor with coolant plenum
CA2796487C (en) * 2010-04-23 2021-06-08 Atomic Energy Of Canada Limited/Energie Atomique Du Canada Limitee Pressure-tube reactor with pressurised moderator
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US9230697B2 (en) 2012-04-20 2016-01-05 Nuscale Power, Llc Steam generator for a nuclear reactor

Also Published As

Publication number Publication date
JP2020024214A (ja) 2020-02-13
EP2859556A2 (en) 2015-04-15
EP2859556A4 (en) 2016-04-06
US10147507B2 (en) 2018-12-04
EP2859556B1 (en) 2020-12-16
CN104272397A (zh) 2015-01-07
WO2013158950A2 (en) 2013-10-24
JP2015514995A (ja) 2015-05-21
WO2013158950A3 (en) 2013-11-14
KR102220520B1 (ko) 2021-02-25
KR102159794B1 (ko) 2020-09-24
US20130279643A1 (en) 2013-10-24
US20150103967A1 (en) 2015-04-16
JP7514339B2 (ja) 2024-07-10
CA3178009A1 (en) 2013-10-24
PL2859556T3 (pl) 2021-06-14
JP2021119356A (ja) 2021-08-12
US9230697B2 (en) 2016-01-05
JP6882418B2 (ja) 2021-06-02
CA2869901C (en) 2023-01-17
CA2869901A1 (en) 2013-10-24
KR20200111284A (ko) 2020-09-28
JP2019032339A (ja) 2019-02-28
CN104272397B (zh) 2016-12-21
JP2023052220A (ja) 2023-04-11
KR20150003807A (ko) 2015-01-09

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