GB202009909D0 - Method and device for evaluating degree of neutron irradiation embrittlement of nuclear power plant reactor pressure vessel - Google Patents
Method and device for evaluating degree of neutron irradiation embrittlement of nuclear power plant reactor pressure vesselInfo
- Publication number
- GB202009909D0 GB202009909D0 GBGB2009909.9A GB202009909A GB202009909D0 GB 202009909 D0 GB202009909 D0 GB 202009909D0 GB 202009909 A GB202009909 A GB 202009909A GB 202009909 D0 GB202009909 D0 GB 202009909D0
- Authority
- GB
- United Kingdom
- Prior art keywords
- power plant
- pressure vessel
- nuclear power
- reactor pressure
- neutron irradiation
- 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.)
- Granted
Links
Classifications
-
- 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
-
- 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)
- Testing Resistance To Weather, Investigating Materials By Mechanical Methods (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
PCT/CN2017/113491 WO2019104510A1 (en) | 2017-11-29 | 2017-11-29 | Method and device for evaluating degree of neutron irradiation embrittlement of nuclear power plant reactor pressure vessel |
Publications (4)
Publication Number | Publication Date |
---|---|
GB202009909D0 true GB202009909D0 (en) | 2020-08-12 |
GB2583292A GB2583292A (en) | 2020-10-21 |
GB2583292A8 GB2583292A8 (en) | 2020-12-16 |
GB2583292B GB2583292B (en) | 2023-03-08 |
Family
ID=66664375
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB2009909.9A Active GB2583292B (en) | 2017-11-29 | 2017-11-29 | Method and device for evaluating degree of neutron irradiation embrittlement of nuclear power plant reactor pressure vessel |
Country Status (2)
Country | Link |
---|---|
GB (1) | GB2583292B (en) |
WO (1) | WO2019104510A1 (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN115221457A (en) * | 2022-09-20 | 2022-10-21 | 哈尔滨工业大学(深圳)(哈尔滨工业大学深圳科技创新研究院) | Method for quantitatively calculating irradiation swelling capacity of control rod core |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN111899803B (en) * | 2020-07-03 | 2023-05-30 | 苏州热工研究院有限公司 | Method for establishing low Cu reactor pressure vessel steel irradiation embrittlement prediction model |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP2841917B1 (en) * | 2012-06-22 | 2020-10-07 | Korea Atomic Energy Research Institute | The method of non-destructive evaluation of intergranular stress corrosion cracking (igssc) in structural components made of metal alloys, and the method of lifetime evaluation of the structural components |
CN102930167B (en) * | 2012-11-05 | 2015-09-30 | 中国原子能科学研究院 | Reactor pressure vessel radiation embrittlement prediction and evaluation method |
CN102967507B (en) * | 2012-11-09 | 2016-03-02 | 华中科技大学 | A kind of material ions irradiation mechanic property test method |
CN103698236B (en) * | 2013-12-10 | 2016-09-14 | 中广核工程有限公司 | A kind of for method for estimating fatigue life of pipeline of nuclear power plant |
CN105489259B (en) * | 2014-09-18 | 2017-06-16 | 中国核动力研究设计院 | Reactor pressure vessel longevity phase irradiation method |
CN106128528B (en) * | 2016-07-28 | 2017-05-31 | 中广核工程有限公司 | A kind of method and apparatus for monitoring nuclear power plant reactor pressure vessel irradiation damage |
-
2017
- 2017-11-29 GB GB2009909.9A patent/GB2583292B/en active Active
- 2017-11-29 WO PCT/CN2017/113491 patent/WO2019104510A1/en active Application Filing
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN115221457A (en) * | 2022-09-20 | 2022-10-21 | 哈尔滨工业大学(深圳)(哈尔滨工业大学深圳科技创新研究院) | Method for quantitatively calculating irradiation swelling capacity of control rod core |
CN115221457B (en) * | 2022-09-20 | 2022-12-13 | 哈尔滨工业大学(深圳)(哈尔滨工业大学深圳科技创新研究院) | Method for quantitatively calculating irradiation swelling capacity of control rod core |
Also Published As
Publication number | Publication date |
---|---|
GB2583292A8 (en) | 2020-12-16 |
GB2583292A (en) | 2020-10-21 |
WO2019104510A1 (en) | 2019-06-06 |
GB2583292B (en) | 2023-03-08 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
789A | Request for publication of translation (sect. 89(a)/1977) |
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