Advanced Search
CHEN Yan, ZHANG Chun-ming, FU Zhi-wei, SONG Wei, LI Chao-jun, WANG Zhe, ZUO Jia-xu. Study on Safety Subsidiary Objective of Nuclear Power Plant in USA[J]. Atomic Energy Science and Technology, 2013, 47(4): 599-603. DOI: 10.7538/yzk.2013.47.04.0599
Citation: CHEN Yan, ZHANG Chun-ming, FU Zhi-wei, SONG Wei, LI Chao-jun, WANG Zhe, ZUO Jia-xu. Study on Safety Subsidiary Objective of Nuclear Power Plant in USA[J]. Atomic Energy Science and Technology, 2013, 47(4): 599-603. DOI: 10.7538/yzk.2013.47.04.0599
shu

Study on Safety Subsidiary Objective of Nuclear Power Plant in USA

  • Nuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing 100082, China

More Information
    Graphical Abstract
    • Abstract
  • This paper reviewed the development of the quantitative safety objective and subsidiary objective in USA. The expressions of CDF and LERF were obtained according to NUREG-1150. The relationship between the subsidiary objective and the quantitative safety objective was derived. The method was compared with that used in NUREG-1860. The requirements of safety objective for the future nuclear power plant and the development of probabilistic safety analysis （PSA） technology in USA were studied and can be used as reference in China.
    • FullText(HTML)
    • References (13)
  • [1]
    Proposed policy statement on safety goals for nuclear power plants, 47FR7023[R]. USA: NRC, 1983.
    [2]
    Safety goals for the operations of nuclear power plants,51FR28044[R]. USA: NRC, 1986.
    [3]
    Implementation of the safety goals, SECY-89-102[R]. USA: NRC, 1989.
    [4]
    Severe risks: An assessment for five US nuclear power plants,NUREG-1150[R]. USA: NRC, 1990.
    [5]
    An approach for using probabilistic risk assessment in risk-informed decisions on plant-specific changes to the licensing basis, DG-1061[R]. USA: NRC, 1997.
    [6]
    Quantitative guidelines from the framework for risk-informing, 10 CFR PART 50[R]. USA: NRC, 2002.
    [7]
    Study for a risk-informed and performance-based regulatory structure for future plant licensing, NUREG-1860[R]. USA: NRC, 2007.
    [8]
    Modified reactor safety goal policy statement, SECY-01-0009[R]. USA: NRC, 2001.
    [9]
    An approach for using probabilistic risk assessment in risk-informed decisions on plant specific changes to the licensing basis, RG 1.174[R]. USA: NRC, 2011.
    [10]
    Risk informed regulatory framework for new reactors, SECY-12-0081[R]. USA: NRC, 2012.
    [11]
    Evaluation of severe accident risks: Methodology for the containment, source term, consequence, and risk integration analyses, NUREG/CR-4551[R]. USA: NRC, 1993.
    [12]
    White paper on options for risk metrics for new reactors[R]. USA: NRC, 2009.
    [13]
    Advisory committee on reactor safeguards reliability and probabilistic risk assessment, NRC-877[R]. USA: ACRS, 2011.
    • Related Articles

  • Related Articles

    [1]FENG Bingchen, YANG Jianfeng, ZHANG Xiaoming, WANG Zhao. Research on Correlation Analysis Method for Seismic PSA Based on Separation of Variables[J]. Atomic Energy Science and Technology, 2021, 55(3): 488-493. DOI: 10.7538/yzk.2020.youxian.0250
    [2]WANG Zhao, YANG Jianfeng, FENG Bingchen. PSA of CPR1000 SBO Accident Based on Monte Carlo Accident Process Analysis[J]. Atomic Energy Science and Technology, 2020, 54(11): 2098-2106. DOI: 10.7538/yzk.2019.youxian.0707
    [3]YANG Peng, YU Hong, HU Wenjun. Probabilistic Safety Assessment Event Tree Analysis of Radioactive Release Risk for Pool Type Sodium-cooled Fast Reactor[J]. Atomic Energy Science and Technology, 2020, 54(7): 1228-1234. DOI: 10.7538/yzk.2019.youxian.0445
    [4]YU Xin-li, ZHU Wen-tao, YANG Xiao-qing, ZHENG Xiang-yang, ZHAN Jia-shuo. Probabilistic Assessment of Creep Induced RCS Rupture in Severe Accident[J]. Atomic Energy Science and Technology, 2016, 50(6): 1072-1077. DOI: 10.7538/yzk.2016.50.06.1072
    [5]HE Jie, LIU Tao, ZHANG Min-jun, TONG Jie-juan. Study on Level-1 PSA Approach of Integrated Risk of Multi-unit NPP[J]. Atomic Energy Science and Technology, 2014, 48(5): 867-871. DOI: 10.7538/yzk.2014.48.05.0867
    [6]ZHAN Wen-hui, YAN Zhen. Application of PSA in Sanmen and Haiyang NPPs SWS Pumps Configuration Effect Analysis[J]. Atomic Energy Science and Technology, 2013, 47(3): 449-452. DOI: 10.7538/yzk.2013.47.03.0449
    [7]HU Wen-jun. Strategy for Fault Tree Conversion to Binary Decision Diagram[J]. Atomic Energy Science and Technology, 2010, 44(3): 289-293. DOI: 10.7538/yzk.2010.44.03.0289
    [8]ZHENG Yao-yao, XU Zhen, KE Xiao. ATWS Sensitivity Studies to Support PSA Success Criteria[J]. Atomic Energy Science and Technology, 2010, 44(增刊): 264-268. DOI: 10.7538/yzk.2010.44.suppl.0264
    [9]ZHANG Xue-feng, LIU Yi-bing, XU Wen-ge, LI Zi-ying, LIU Ting, HAN Shi-quan. Chemiluminescence Immunoassay for Free Prostate-Specific Antigen[J]. Atomic Energy Science and Technology, 2008, 42(z1): 57-62. DOI: 10.7538/yzk.2008.42.z1.0057
    [10]WANG Hai-tao, WU Yi-can, DING Hou-ben, LIU Ping, HU Li-qin, ZHANG Shi-jie, LI Ya-zhou. Algorithms of Consequence Analysis for PSA in Nuclear Power Plant[J]. Atomic Energy Science and Technology, 2008, 42(8): 724-728. DOI: 10.7538/yzk.2008.42.08.0724

Catalog

    Get Citation
    PDF
    XML
    Article views (335) PDF downloads (1137) Cited by()
    Turn off MathJax
    Article Contents
    Abstract
    References
    Related Articles

    Website Copyright©2023 Atomic Energy Science and Technology  京ICP备12043220号-2

    Address：Box 65, P.O. Box 275, Beijing   Postal Code：102413

    Email：yznkxjs7285@163.com   Tel:（010）69357285,69358024

    Supported by: Beijing Renhe Information Technology Co., Ltd.  Baidu Analytics

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return