CN104464851B - 一种用于核电站一回路高温管道热疲劳原型的监测方法 - Google Patents
一种用于核电站一回路高温管道热疲劳原型的监测方法 Download PDFInfo
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- CN104464851B CN104464851B CN201410788725.1A CN201410788725A CN104464851B CN 104464851 B CN104464851 B CN 104464851B CN 201410788725 A CN201410788725 A CN 201410788725A CN 104464851 B CN104464851 B CN 104464851B
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- 238000012544 monitoring process Methods 0.000 title claims abstract description 39
- 206010019332 Heat exhaustion Diseases 0.000 title claims abstract description 23
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/112—Measuring temperature
-
- 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
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- 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)
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CN201410788725.1A CN104464851B (zh) | 2014-12-19 | 2014-12-19 | 一种用于核电站一回路高温管道热疲劳原型的监测方法 |
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CN201410788725.1A CN104464851B (zh) | 2014-12-19 | 2014-12-19 | 一种用于核电站一回路高温管道热疲劳原型的监测方法 |
Publications (2)
Publication Number | Publication Date |
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CN104464851A CN104464851A (zh) | 2015-03-25 |
CN104464851B true CN104464851B (zh) | 2016-08-17 |
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CN201410788725.1A Expired - Fee Related CN104464851B (zh) | 2014-12-19 | 2014-12-19 | 一种用于核电站一回路高温管道热疲劳原型的监测方法 |
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Families Citing this family (13)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104376882B (zh) * | 2014-11-11 | 2017-03-22 | 中广核研究院有限公司 | 热管道 |
CN105448359B (zh) * | 2015-12-07 | 2017-09-01 | 中广核工程有限公司 | 一种核电厂疲劳监测***及方法 |
CN106680001B (zh) * | 2016-10-25 | 2019-09-17 | 核动力运行研究所 | 一种管道三通区域在线疲劳寿命监测装置及方法 |
CN108268675B (zh) * | 2016-12-30 | 2021-09-07 | 北京金风科创风电设备有限公司 | 疲劳损伤确定方法以及疲劳损伤确定装置 |
CN109979622B (zh) * | 2017-12-27 | 2021-02-09 | 核动力运行研究所 | 核电厂稳压器疲劳寿命在线监测评估***与方法 |
GB2581407B (en) * | 2018-07-03 | 2022-12-07 | China Nuclear Power Technology Res Inst Co Ltd | Temperature measuring device in a nuclear reactor loop |
CN208400506U (zh) * | 2018-07-03 | 2019-01-18 | 中广核研究院有限公司 | 核反应堆回路测温热管道及测温装置 |
CN112649460B (zh) * | 2019-10-10 | 2023-10-20 | 国核电站运行服务技术有限公司 | 稳压器波动管热分层试验方法 |
CN110828011B (zh) * | 2019-11-04 | 2021-11-23 | 广东核电合营有限公司 | 核电厂管道热疲劳监测*** |
CN111141400B (zh) * | 2019-12-04 | 2021-08-24 | 深圳中广核工程设计有限公司 | 核电站弯管热疲劳敏感区管壁温度测量方法 |
CN112699514B (zh) * | 2020-12-31 | 2022-06-17 | 河北工业大学 | 热分层管道瞬态热应力快速计算方法 |
DE102021128132B3 (de) | 2021-10-28 | 2022-06-30 | Framatome Gmbh | Überwachungssystem zum Überwachen einer mechanischen Ermüdung eines Metallrohrs eines Kraftwerks, Kraftwerk, Benutzung und zugehöriges Verfahren |
CN114777368B (zh) * | 2022-04-08 | 2024-06-18 | 青岛海尔空调器有限总公司 | 用于监控循环***管路风险的方法、装置和循环*** |
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DE3314181A1 (de) * | 1983-04-19 | 1984-10-25 | Kraftwerk Union AG, 4330 Mülheim | Verfahren zur ueberwachung der ermuedung von bauteilen, z.b. in kernkraftwerken |
JPH03180724A (ja) * | 1989-12-11 | 1991-08-06 | Toshiba Corp | 配管疲労監視用振動積算装置 |
JPH1114782A (ja) * | 1997-06-19 | 1999-01-22 | Shikoku Electric Power Co Inc | 配管劣化評価方法及び装置 |
JP2006194782A (ja) * | 2005-01-14 | 2006-07-27 | Toshiba Corp | 構造物の欠陥評価方法 |
JP2007225387A (ja) * | 2006-02-22 | 2007-09-06 | Toshiba Corp | 原子炉構造物の溶接部における疲労特性予測の方法、そのシステムおよびそのプログラム |
JP4705066B2 (ja) * | 2007-03-30 | 2011-06-22 | 株式会社日立製作所 | 原子力プラント、給水ノズルの熱疲労監視方法及び原子力プラントの運転方法 |
CN204651011U (zh) * | 2014-12-19 | 2015-09-16 | 大连理工大学 | 一种用于核电站一回路高温管道热疲劳原型监测装置 |
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Inventor after: Wu Wenhua Inventor after: Zhang Guoxun Inventor before: Wu Wenhua Inventor before: Gao Kunyue Inventor before: Gao Nan Inventor before: Qie Chaoyang Inventor before: Xu Hong Inventor before: Xu Xiaozhen Inventor before: Wei Wei Inventor before: Hou Huaqing Inventor before: Li Fuliang Inventor before: Xie Chenping |
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Free format text: CORRECT: INVENTOR; FROM: WU WENHUA GAO NAN QIE CHAOYANG XU HONG XU XIAOZHEN WEI WEI HOU HUAQING LI FULIANG XIE CHENPING GAO KUNYUE TO: WU WENHUA ZHANG GUOXUN |
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