Study on Method of Aging Management During Operation for High Flux Engineering Test Reactor

Zhao Peng; Pan Ruian; Liu Zhen; Han Liangwen; Gao Yedong; Lai lisi; Sun Biao

doi:10.13832/j.jnpe.2023.S1.0199

Volume 44 Issue S1

Jun. 2023

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2023 > 44(S1): 199-204

Zhao Peng, Pan Ruian, Liu Zhen, Han Liangwen, Gao Yedong, Lai lisi, Sun Biao. Study on Method of Aging Management During Operation for High Flux Engineering Test Reactor[J]. Nuclear Power Engineering, 2023, 44(S1): 199-204. doi: 10.13832/j.jnpe.2023.S1.0199

Citation:

Zhao Peng, Pan Ruian, Liu Zhen, Han Liangwen, Gao Yedong, Lai lisi, Sun Biao. Study on Method of Aging Management During Operation for High Flux Engineering Test Reactor[J]. Nuclear Power Engineering, 2023, 44(S1): 199-204. doi: 10.13832/j.jnpe.2023.S1.0199

Citation:

PDF( 3752 KB)

Study on Method of Aging Management During Operation for High Flux Engineering Test Reactor

doi: 10.13832/j.jnpe.2023.S1.0199

Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2023-02-06
Rev Recd Date: 2023-02-22
Publish Date: 2023-06-15

Abstract

Abstract

In order to effectively carry out aging management of High Flux Engineering Test Reactor (HFETR), it is necessary to implement aging management activities in accordance with effective aging management methods. Through research on aging management scope screening, aging recognition, and aging management activities implementation methods and strategies, and according to the aging management practice and experience of operation license extension (OLE) application for HFETR, a systematic aging management system based on Deming cycle "plan-implementation-inspection-action (PDCA)" has been established for the reactor operation stage. The aging management review of HFETR in the first operation license extension application shows that the aging management method of HFETR is effective and can provide reference for the aging management of research reactors.
- Aging management,
- Research reactor,
- Aging management system,
- Deming cycle

FullText(HTML)

References(8)

References

[1]	高泉源. 研究堆老化管理的法规依据、现状及建议[J]. 核安全,2006, 4(4): 1-8. doi: 10.3969/j.issn.1672-5360.2006.04.001
[2]	国家核安全局. 研究堆定期安全审查: 核安全导则: HAD 202/02—2017[S]. 北京: 国家核安全局, 2017: 1-20.
[3]	国防科学技术工业委员会. 研究堆老化管理: EJ/T 1176—2005[S]. 北京: 核工业标准化所, 2005: 6-7.
[4]	龚嶷,崔满满,窦一康,等. 核电厂运行许可证延续(OLE)安全监管的对策[J]. 核安全,2015, 14(1): 1-11. doi: 10.16432/j.cnki.1672-5360.2015.01.001
[5]	石文翔,陶钧,尚宪和,等. 秦山核电厂运行许可证延续研究与应用[J]. 中国核电,2021, 14(3): 312-316.
[6]	International Atomic Energy Agency. IAEA ageing management for research reactors: specific safety guide No. SSG-10[S]. IAEA, 2010. VIENNA: International Atomic Energy Agency, 2010: 1-61.
[7]	国家核安全局. 核动力厂老化管理: 核安全导则: HAD 103/12—2012[S]. 北京: 国家核安全局, 2012: 1-23.
[8]	U. S. NRC. Generic aging lessons learned (Gall) report: NUREG-1801[S]. Washington DC: U. S. NRC, 2010: 21-22.