GB202314377D0 - Design method and apparatus for containment integrity test of advanced pressurized water reactor nuclear power plant - Google Patents

Design method and apparatus for containment integrity test of advanced pressurized water reactor nuclear power plant

Info

Publication number
GB202314377D0
GB202314377D0 GBGB2314377.9A GB202314377A GB202314377D0 GB 202314377 D0 GB202314377 D0 GB 202314377D0 GB 202314377 A GB202314377 A GB 202314377A GB 202314377 D0 GB202314377 D0 GB 202314377D0
Authority
GB
United Kingdom
Prior art keywords
power plant
nuclear power
design method
pressurized water
water reactor
Prior art date
Legal status (The legal status 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 status listed.)
Pending
Application number
GBGB2314377.9A
Other versions
GB2619465A (en
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China Nuclear Power Engineering Co Ltd
Original Assignee
China Nuclear Power Engineering Co Ltd
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 China Nuclear Power Engineering Co Ltd filed Critical China Nuclear Power Engineering Co Ltd
Publication of GB202314377D0 publication Critical patent/GB202314377D0/en
Publication of GB2619465A publication Critical patent/GB2619465A/en
Pending legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/001—Computer implemented control
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/003—Remote inspection of vessels, e.g. pressure vessels
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
    • G01M3/00—Investigating fluid-tightness of structures
    • G01M3/02—Investigating fluid-tightness of structures by using fluid or vacuum
    • G01M3/26—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors
    • G01M3/28—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds
    • G01M3/2807—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds for pipes
    • G01M3/2815—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds for pipes using pressure measurements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/002—Detection of leaks
    • 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)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Physics & Mathematics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Examining Or Testing Airtightness (AREA)
GB2314377.9A 2021-03-24 2021-12-27 Design method and apparatus for containment integrity test of advanced pressurized water reactor nuclear power plant Pending GB2619465A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CN202110312538.6A CN113140340B (en) 2021-03-24 2021-03-24 Design method for integrity test of advanced pressurized water reactor nuclear power plant containment
PCT/CN2021/141566 WO2022199178A1 (en) 2021-03-24 2021-12-27 Design method and apparatus for containment integrity test of advanced pressurized water reactor nuclear power plant

Publications (2)

Publication Number Publication Date
GB202314377D0 true GB202314377D0 (en) 2023-11-01
GB2619465A GB2619465A (en) 2023-12-06

Family

ID=76810032

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2314377.9A Pending GB2619465A (en) 2021-03-24 2021-12-27 Design method and apparatus for containment integrity test of advanced pressurized water reactor nuclear power plant

Country Status (4)

Country Link
CN (1) CN113140340B (en)
AR (1) AR125571A1 (en)
GB (1) GB2619465A (en)
WO (1) WO2022199178A1 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113140340B (en) * 2021-03-24 2022-07-26 中国核电工程有限公司 Design method for integrity test of advanced pressurized water reactor nuclear power plant containment

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP4405036B2 (en) * 2000-04-24 2010-01-27 株式会社東芝 Test method for reactor containment vessel
EP1298675A1 (en) * 2001-09-28 2003-04-02 Paul Scherrer Institut Installation, sampling device and method for radioactivity measurement in a nuclear power plant
CA2727492C (en) * 2011-01-14 2014-09-09 Ge-Hitachi Nuclear Energy Canada Inc. Method for removal of pressure tubes and calandria tubes from a nuclear reactor
CN106093616A (en) * 2016-05-30 2016-11-09 中国核电工程有限公司 A kind of formulating method for advanced pressurized water reactor nuclear power plant debugging stage head heap pilot project
CN108007645B (en) * 2017-10-25 2021-07-27 中国核电工程有限公司 Sensor arrangement method for large pressurized water reactor containment overall tightness test
CN108010594A (en) * 2017-10-25 2018-05-08 中国核电工程有限公司 The formulating method of universal test directive/guide project and content is debugged by advanced pressurized water reactor nuclear power plant
CN211350119U (en) * 2019-09-20 2020-08-25 中国核电工程有限公司 Large pressurized water reactor containment overall tightness test measuring system
CN113140340B (en) * 2021-03-24 2022-07-26 中国核电工程有限公司 Design method for integrity test of advanced pressurized water reactor nuclear power plant containment

Also Published As

Publication number Publication date
WO2022199178A1 (en) 2022-09-29
AR125571A1 (en) 2023-07-26
GB2619465A (en) 2023-12-06
CN113140340B (en) 2022-07-26
CN113140340A (en) 2021-07-20

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