0
Research Papers

Risk Analysis of Spent Fuel Pool Caused by Seismic Events

[+] Author and Article Information
Ming Wang

State Key Laboratory of Nuclear Power Safety
Monitoring Technology and Equipment,
China Nuclear Power Engineering Co., Ltd.,
Shenzhen 518172, Guangdong Province, China
e-mail: wangming_2010@cgnpc.com.cn

Modi Lin

China Nuclear Power Engineering Co., Ltd.,
Shenzhen 518172, Guangdong Province, China
e-mail: LinMoDi@cgnpc.com.cn

Jinkai Wang

China Nuclear Power Design Co., Ltd.,
Shenzhen 518172, Guangdong Province, China
e-mail: wangjinkai@cgnpc.com.cn

Manuscript received October 31, 2017; final manuscript received May 13, 2018; published online September 10, 2018. Assoc. Editor: Jovica R. Riznic.

ASME J of Nuclear Rad Sci 4(4), 041012 (Sep 10, 2018) (5 pages) Paper No: NERS-17-1273; doi: 10.1115/1.4040367 History: Received October 31, 2017; Revised May 13, 2018

Spent fuel pool (SFP) stores fuel assemblies removed from the reactor over the years. SFP and its accident mitigation measures may fail simultaneously at the time of the earthquake, which may cause serious accident consequences. This paper uses probabilistic safety assessment (PSA) method to quantitatively evaluate the risk of SFP for a CPR1000 unit caused by seismic events. Quantitative analysis results show that seismic events' risk is the highest in all internal events and external events for SFP. In order to reduce the risk of SFP, more attention should be paid to improve seismic capacity or reduce the common failure for systems and components associated with SFP under the earthquake situation.

FIGURES IN THIS ARTICLE
<>
Copyright © 2018 by ASME
Your Session has timed out. Please sign back in to continue.

References

Wang, Y. , Gong, A. , Xu, J. , and Zeng, J. , 2013, “ Modifications for Improving Safety Feature of Spent Fuel Pool in CPR1000 Nuclear Power Units,” Nucl. Power Eng., 34(1), pp. 77–80.
Electric Power Research Institute, 2013, “ Seismic Probabilistic Risk Assessment Implementation Guide,” Electric Power Research Institute, Palo Alto, CA, Report No. TR-3002000709. https://www.epri.com/#/pages/product/3002000709/?lang=en
Electric Power Research Institute, 1988, “ A Methodology for Assessment of Nuclear Power Plant Seismic Margin,” Electric Power Research Institute, Palo Alto, CA, Report No. EPRI-NP-6041. https://www.osti.gov/biblio/6823102
Electric Power Research Institute, 2001, “ Methodology for Developing Seismic Fragilities,” Electric Power Research Institute, Palo Alto, CA, Report No. EPRI-TR-103959. https://www.epri.com/#/pages/product/TR-103959/?lang=en
Nuclear Regulatory Commission, 2000, “ Loss of Spent Fuel Pool Cooling PRA: Model and Results,” Nuclear Regulatory Commission, Washington, DC, Report No. INEL-98/0334. https://inis.iaea.org/search/search.aspx?orig_q=RN:29040048
Nuclear Regulatory Commission, 2000, “ Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants,” Nuclear Regulatory Commission, Washington, DC, Report No. NUREG-1738. https://www.nrc.gov/docs/ML0104/ML010430066.pdf
Nuclear Regulatory Commission, 1997, “ Operating Experience Feedback Report: Assessment of Spent Fuel Cooling,” Nuclear Regulatory Commission, Washington, DC, Report No. NUREG-1275. https://www.osti.gov/biblio/453755
Wang, M. , Sang, H. , and Yang, C. , 2016, “ Risk Analysis of Spent Fuel Pool,” Nucl. Sci. Eng., 36, pp. 256–260.

Figures

Grahic Jump Location
Fig. 1

Initiating events tree for the SFP under seismic conditions

Grahic Jump Location
Fig. 2

An example of system fault tree modeling under seismic conditions

Grahic Jump Location
Fig. 3

Distribution of the detailed results about SFP FDF caused by seismic events

Tables

Errata

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In