EA201501008A3 - DEVICE FOR THE CONTROL OF THE TIGHTNESS OF THE HEAT-BREAKING ASSEMBLY OF THE ATOMIC REACTOR AND THE METHOD OF IMPLEMENTING SUCH CONTROL - Google Patents

DEVICE FOR THE CONTROL OF THE TIGHTNESS OF THE HEAT-BREAKING ASSEMBLY OF THE ATOMIC REACTOR AND THE METHOD OF IMPLEMENTING SUCH CONTROL

Info

Publication number
EA201501008A3
EA201501008A3 EA201501008A EA201501008A EA201501008A3 EA 201501008 A3 EA201501008 A3 EA 201501008A3 EA 201501008 A EA201501008 A EA 201501008A EA 201501008 A EA201501008 A EA 201501008A EA 201501008 A3 EA201501008 A3 EA 201501008A3
Authority
EA
Eurasian Patent Office
Prior art keywords
control
tightness
fuel
working rod
implementing
Prior art date
Application number
EA201501008A
Other languages
Russian (ru)
Other versions
EA030889B1 (en
EA201501008A2 (en
Inventor
Сергей Андреевич АЛЕКСАНИН
Вадим Игоревич ДУНАЕВ
Михаил Евгеньевич ФЕДОСОВСКИЙ
Original Assignee
Закрытое Акционерное Общество "Диаконт"
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 Закрытое Акционерное Общество "Диаконт" filed Critical Закрытое Акционерное Общество "Диаконт"
Priority to EA201501008A priority Critical patent/EA030889B1/en
Publication of EA201501008A2 publication Critical patent/EA201501008A2/en
Publication of EA201501008A3 publication Critical patent/EA201501008A3/en
Priority to CN201680060526.6A priority patent/CN108463857B/en
Priority to PCT/RU2016/000550 priority patent/WO2017138835A1/en
Priority to HUP1800223 priority patent/HUP1800223A1/en
Priority to FI20185241A priority patent/FI128657B/en
Publication of EA030889B1 publication Critical patent/EA030889B1/en

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • G21C17/07—Leak testing
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • 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)

Abstract

Предложено устройство для контроля герметичности тепловыделяющих сборок атомного реактора и способ, реализуемый указанным устройством. Предложенное устройство размещается на рабочей штанге перегрузочной машины для перегрузки топлива реактора и осуществляет барботаж теплоносителя вблизи тепловыделяющей сборки, которая находится в рабочей штанге и в отношении которой осуществляется контроль герметичности. Устройство отличается тем, что форсунки подающего трубопровода обращены к центру рабочей штанги, что позволяет обеспечить подачу сжатого газа непосредственно под хвостовик тепловыделяющей сборки, обеспечив повышение интенсивности барботажа теплоносителя вблизи указанной сборки, и таким образом повысить эффективность контроля герметичности.A device is proposed for monitoring the tightness of fuel assemblies of an atomic reactor and a method implemented by said device. The proposed device is placed on the working rod of the reloading machine for reloading the fuel of the reactor and sparging coolant near the fuel assembly, which is located in the working rod and in relation to which the tightness control is carried out. The device differs in that the nozzles of the supply pipeline are facing the center of the working rod, which allows for the supply of compressed gas directly under the shank of the fuel assembly, increasing the intensity of bubbling coolant near the specified assembly, and thus increasing the efficiency of leakage control.

EA201501008A 2015-08-14 2015-08-14 Device for checking the hermeticity of a nuclear reactor fuel assembly and method for carrying out such control EA030889B1 (en)

Priority Applications (5)

Application Number Priority Date Filing Date Title
EA201501008A EA030889B1 (en) 2015-08-14 2015-08-14 Device for checking the hermeticity of a nuclear reactor fuel assembly and method for carrying out such control
CN201680060526.6A CN108463857B (en) 2015-08-14 2016-08-15 Apparatus and method for leak detection in nuclear fuel assemblies
PCT/RU2016/000550 WO2017138835A1 (en) 2015-08-14 2016-08-15 Device for checking the hermeticity of a nuclear reactor fuel assembly
HUP1800223 HUP1800223A1 (en) 2015-08-14 2016-08-15 Device for cheking the hermeticity of nuclear reactor fuel assemnly
FI20185241A FI128657B (en) 2015-08-14 2016-08-15 Apparatus and method for leak detection in a nuclear fuel assembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
EA201501008A EA030889B1 (en) 2015-08-14 2015-08-14 Device for checking the hermeticity of a nuclear reactor fuel assembly and method for carrying out such control

Publications (3)

Publication Number Publication Date
EA201501008A2 EA201501008A2 (en) 2016-02-29
EA201501008A3 true EA201501008A3 (en) 2016-04-29
EA030889B1 EA030889B1 (en) 2018-10-31

Family

ID=55404367

Family Applications (1)

Application Number Title Priority Date Filing Date
EA201501008A EA030889B1 (en) 2015-08-14 2015-08-14 Device for checking the hermeticity of a nuclear reactor fuel assembly and method for carrying out such control

Country Status (5)

Country Link
CN (1) CN108463857B (en)
EA (1) EA030889B1 (en)
FI (1) FI128657B (en)
HU (1) HUP1800223A1 (en)
WO (1) WO2017138835A1 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109973826B (en) * 2019-04-26 2020-05-15 西安交通大学 Experimental device and method for measuring leakage rate of nuclear reactor pipeline
JP2022126239A (en) 2021-02-18 2022-08-30 三菱重工コンプレッサ株式会社 gas expander

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN1016471B (en) * 1985-12-20 1992-04-29 法玛通公司 Monitoring method and device for shell fault in nuclear fuel components
JPS63266395A (en) * 1987-04-24 1988-11-02 Mitsubishi Atom Power Ind Inc Fuel leakage inspection device
US5414742A (en) * 1993-11-10 1995-05-09 Westinghouse Electric Corporation Leak-detection system and method for detecting a leaking container
US5570400A (en) * 1995-08-08 1996-10-29 B&W Fuel Company On line sipping air delivery system
US5754610A (en) * 1996-12-05 1998-05-19 Framatome Technologies, Inc. In-mast sipping modular mast modification
US6070453A (en) * 1998-08-12 2000-06-06 Tokheim Corporation Computerized dispenser tester
US6345082B1 (en) * 1999-06-03 2002-02-05 Thomas A. Galioto Fuel assembly mechanical flow restriction apparatus for detecting failure in situ of nuclear fuel rods in a fuel assembly during reactor shutdown
RU2186429C2 (en) * 2001-10-19 2002-07-27 Славягин Павел Дмитриевич Method and device for recharging fuel assembly of liquid-cooled reactor and for checking its tightness
EA016571B1 (en) * 2010-10-06 2012-05-30 Зао "Диаконт" Method for automated fuel leakage detection during reloading of reactor fuel assembly and system therefor
CN104361916B (en) * 2014-09-19 2017-02-15 武汉海王核能装备工程有限公司 Typical nuclide monitor of fuel element failure

Also Published As

Publication number Publication date
CN108463857A (en) 2018-08-28
HUP1800223A1 (en) 2019-04-29
CN108463857B (en) 2022-11-08
EA030889B1 (en) 2018-10-31
FI128657B (en) 2020-09-30
WO2017138835A1 (en) 2017-08-17
EA201501008A2 (en) 2016-02-29
FI20185241A (en) 2018-03-14

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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