EA201691856A1 - Способ извлечения пробки и блока выемного при перегрузке ядерного реактора - Google Patents

Способ извлечения пробки и блока выемного при перегрузке ядерного реактора

Info

Publication number
EA201691856A1
EA201691856A1 EA201691856A EA201691856A EA201691856A1 EA 201691856 A1 EA201691856 A1 EA 201691856A1 EA 201691856 A EA201691856 A EA 201691856A EA 201691856 A EA201691856 A EA 201691856A EA 201691856 A1 EA201691856 A1 EA 201691856A1
Authority
EA
Eurasian Patent Office
Prior art keywords
cork
extracting
nuclear reactor
removable
reactor
Prior art date
Application number
EA201691856A
Other languages
English (en)
Other versions
EA029845B1 (ru
Inventor
Николай Дмитриевич ВАСИЛЬЕВ
Владимир Евгеньевич ОГУРЦОВ
Александр Иванович КУЗНЕЦОВ
Original Assignee
Открытое Акционерное Общество "Акмэ-Инжиниринг"
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 Открытое Акционерное Общество "Акмэ-Инжиниринг" filed Critical Открытое Акционерное Общество "Акмэ-Инжиниринг"
Publication of EA201691856A1 publication Critical patent/EA201691856A1/ru
Publication of EA029845B1 publication Critical patent/EA029845B1/ru

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
    • G21C19/105—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with grasping or spreading coupling elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/19—Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • G21C19/205—Interchanging of fuel elements in the core, i.e. fuel shuffling
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • 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
    • G21C15/24—Promoting flow of the coolant
    • G21C15/243—Promoting flow of the coolant for liquids
    • G21C15/247—Promoting flow of the coolant for liquids for liquid metals
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
  • Cleaning By Liquid Or Steam (AREA)
  • Extraction Or Liquid Replacement (AREA)

Abstract

Изобретение относится к атомной технике, в частности к способу извлечения пробки и блока выемного реактора на быстрых нейтронах с тяжелым жидкометаллическим теплоносителем. Технический результат заключается в извлечении из ядерного реактора пробки и блока выемного без тепловыделяющих сборок с помощью комплекса перегрузочного оборудования в радиационно-безопасных условиях. Способ извлечения пробки и блока выемного при перегрузке ядерного реактора заключается в предварительном монтаже перегрузочного оборудования, выемке пробки из реакторного моноблока, а также транспортировке и размещении пробки в шахте для пробки, выгрузке блока выемного, его транспортировке и размещении блока выемного в шахте для разборки блока выемного.
EA201691856A 2014-04-18 2015-04-17 Способ извлечения пробки и блока выемного при перегрузке ядерного реактора EA029845B1 (ru)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
RU2014115600/07A RU2558379C1 (ru) 2014-04-18 2014-04-18 Способ извлечения пробки и блока выемного при перегрузке ядерного реактора
PCT/RU2015/000250 WO2015160285A1 (ru) 2014-04-18 2015-04-17 Способ извлечения пробки и блока выемного при перегрузке ядерного реактора

Publications (2)

Publication Number Publication Date
EA201691856A1 true EA201691856A1 (ru) 2016-12-30
EA029845B1 EA029845B1 (ru) 2018-05-31

Family

ID=53795846

Family Applications (1)

Application Number Title Priority Date Filing Date
EA201691856A EA029845B1 (ru) 2014-04-18 2015-04-17 Способ извлечения пробки и блока выемного при перегрузке ядерного реактора

Country Status (13)

Country Link
US (1) US10290382B2 (ru)
EP (1) EP3133610B1 (ru)
JP (1) JP6321284B2 (ru)
KR (1) KR101809399B1 (ru)
CN (1) CN106663480B (ru)
BR (1) BR112016024195B1 (ru)
CA (1) CA2945750C (ru)
EA (1) EA029845B1 (ru)
HU (1) HUE045942T2 (ru)
MY (1) MY178376A (ru)
RU (1) RU2558379C1 (ru)
UA (1) UA117057C2 (ru)
WO (1) WO2015160285A1 (ru)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106816185B (zh) * 2015-11-27 2018-11-27 国核华清（北京）核电技术研发中心有限公司 用于核电站的安注容器
CN109545411A (zh) * 2018-11-20 2019-03-29 中国科学院合肥物质科学研究院 一种核反应堆的堆芯

Family Cites Families (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4705661A (en) * 1985-05-31 1987-11-10 Electricite De France Service National Fast neutron nuclear reactor equipped with a central handling cell and a boxed slab
JPH0820549B2 (ja) * 1987-10-30 1996-03-04 三菱重工業株式会社 プラグの脱着装置
JPH01313796A (ja) * 1988-06-13 1989-12-19 Fuji Electric Co Ltd 圧力管型原子炉のシールプラグ取外し装置
JPH0272883U (ru) * 1988-11-24 1990-06-04
JPH04268494A (ja) * 1991-02-25 1992-09-24 Toshiba Corp 高速増殖炉
JPH04353798A (ja) * 1991-05-31 1992-12-08 Toshiba Corp 高速増殖炉
JPH1062585A (ja) * 1996-08-13 1998-03-06 Fuji Electric Co Ltd 高速炉用炉外燃料貯蔵設備
JPH1116495A (ja) * 1997-06-25 1999-01-22 Hitachi Ltd 陰極線管の製造方法
JP3875374B2 (ja) * 1997-10-03 2007-01-31 株式会社東芝 高速増殖炉およびその炉心上部機構の引抜装置
RU2166808C1 (ru) * 1999-12-03 2001-05-10 Курская Атомная Электростанция Съемник пробки
JP2001264476A (ja) * 2000-03-17 2001-09-26 Toshiba Corp 重金属冷却炉
RU2224307C2 (ru) * 2002-01-08 2004-02-20 Закрытое акционерное общество Научно-производственное объединение "ГАММА-С" Способ перегрузки быстрого ядерного реактора и система перегрузки
KR100905375B1 (ko) * 2007-11-19 2009-07-01 한국원자력연구원 핵연료교환장치 및 핵연료교환방법
RU2399972C2 (ru) * 2008-11-07 2010-09-20 Открытое акционерное общество "Центральное конструкторское бюро машиностроения" (ОАО "ЦКБМ") Контейнер для выгрузки выемного блока с активной зоной или без нее
EP2497092B1 (en) * 2009-11-02 2018-08-29 TerraPower LLC Nuclear fission reactor and methods
JP6089195B2 (ja) * 2012-09-14 2017-03-08 国立研究開発法人日本原子力研究開発機構 炉心上部機構の交換工法

Also Published As

Publication number Publication date
WO2015160285A1 (ru) 2015-10-22
HUE045942T2 (hu) 2020-02-28
RU2558379C1 (ru) 2015-08-10
KR101809399B1 (ko) 2017-12-14
JP2017511493A (ja) 2017-04-20
KR20170002457A (ko) 2017-01-06
US10290382B2 (en) 2019-05-14
US20180033504A1 (en) 2018-02-01
CA2945750A1 (en) 2015-10-22
BR112016024195A2 (pt) 2017-08-15
CN106663480A (zh) 2017-05-10
CA2945750C (en) 2018-10-23
BR112016024195B1 (pt) 2022-02-08
EA029845B1 (ru) 2018-05-31
EP3133610A4 (en) 2017-11-29
EP3133610B1 (en) 2019-10-09
CN106663480B (zh) 2018-03-16
MY178376A (en) 2020-10-09
UA117057C2 (ru) 2018-06-11
JP6321284B2 (ja) 2018-05-09
EP3133610A1 (en) 2017-02-22

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Legal Events

Date Code Title Description
MM4A Lapse of a eurasian patent due to non-payment of renewal fees within the time limit in the following designated state(s)

Designated state(s): AZ KG TJ TM RU

TC4A Change in name of a patent proprietor in a eurasian patent