|
[1]
|
Wilson, G.E. and Boyack, B.E. (1998) The Role of the PIRT Process in Experiments, Code Development and Code Ap-plications Associated with Reactor Safety Analysis. Nuclear Engineering and Design, 186, 23-37. [Google Scholar] [CrossRef]
|
|
[2]
|
USNRC (2005) Regulatory Guide 1.203. U.S. Nuclear Reg-ulatory Commission.
|
|
[3]
|
Deng, C., Zhang, X., Yang, Y. and Yang, J. (2019) Research on Scaling Design and Ap-plicability Evaluation of Integral Thermal-Hydraulic Test Facilities: A Review. Annals of Nuclear Energy, 131, 273-290. [Google Scholar] [CrossRef]
|
|
[4]
|
陈炳德. 安全评审程序用CSAU法[J]. 核动力工程, 1992,13(5): 22-26.
|
|
[5]
|
Diamond, D.J. (2006) Experience Using Phenomena Identification and Ranking Technique (PIRT) for Nuclear Analysis. PHYSOR-2006 Topical Meeting, Vancouver, 10-14 September 2006, 3-10.
|
|
[6]
|
Ortiz, M.G. and Ghan, L.S. (1992) Uncertainty Analysis of Minimum Vessel Liquid Inventory during a Small-Break LOCA in a BW Plant: An Application of the CSAU Methodology Using the RELAP5/MOD3 Computer Code. NUREG/CR-5818. [Google Scholar] [CrossRef]
|
|
[7]
|
Hanson, R.G., Wilson, G.E., Ortiz, M.G., et al. (1992) Development of a Phenomena Identification and Ranking Table (PIRT) for a Postulated Double-Ended Guillotine Break in a Production Reactor. Nuclear Engineering and Design, 136, 335-346. [Google Scholar] [CrossRef]
|
|
[8]
|
Aoki, T., Takagi, T., Komura, I., et al. (2014) Study of a Methodology of Identifying Important Research Problems by the PIRT Process. Nuclear Science and Technology, 51, 832-844. [Google Scholar] [CrossRef]
|
|
[9]
|
Boyack, B.E., Motta, A.T., Peddicord, K.L., et al. (2001) PIRTs for Rod Ejection Accidents in PWR Containing High Burnup Fuel. U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research, Washington DC.
|
|
[10]
|
Suehiro, S., Sugimoto, J., Hidaka, A., et al. (2015) De-velopment of the Source Term PIRT Based on Findings during Fukushima Daiichi NPPs Accident. Nuclear Engineering and Design, 286, 163-174. [Google Scholar] [CrossRef]
|
|
[11]
|
Lin, H.-C., Zhang, S., Diamond, D., et al. (2019) Phenomena Identification and Ranking Table Study for Thermal Hydraulics for Advanced High Temperature Reactor. Annals of Nu-clear Energy, 124, 257-269. [Google Scholar] [CrossRef]
|
|
[12]
|
第四代核能技术国际论坛(GIF). 第四代核能技术国际论坛(GIF)发布综合安全评估方法(ISAM) [Z]. 2014.
|
|
[13]
|
陈福冰, 陈志鹏, 郑艳华, 等. 现象识别与分级表在高温气冷堆程序验证中的应用[J]. 原子能科学技术, 2015, 49(S1): 415-419.
|
|
[14]
|
Yang, Y., Deng, C. and Yang, J. (2021) Best Estimate plus Uncertainty Analysis of a Small-Break LOCA on an Advanced Generation-III Pressurized Water Re-actor. International Journal of Energy Research, 45, 11916-11929. [Google Scholar] [CrossRef]
|
|
[15]
|
Luo, H. (2012) Quantified PIRT and Uncertainty Quantification for Computer Code Validation. Oregon State University, Corvallis.
|
|
[16]
|
Scarlat, R.O. (2012) Design of Complex Systems to Achieve Passive Safety: Natural Circulation Cooling of Liquid Salt Pebble Bed Reactors. University of California, Berke-ley.
|
|
[17]
|
Yao, Y., Peng, C., Deng, C. and Yang, J. (2022) The Development and Application of Visualized Phenomena Identification and Ranking Table Methodology. Proceedings of the NURETH-19, Brussels, 6-11 March 2022, 1-10.
|
|
[18]
|
Griffiths, M.J., Schlegel, J.P., Hibiki, T., et al. (2014) Phenomena Identification and Ranking Table for Thermal-Hydraulic Phenomena during a Small-Break LOCA with Loss of High Pressure Injection. Progress in Nuclear Energy, 73, 51-63. [Google Scholar] [CrossRef]
|
|
[19]
|
Kinoshita, I., Yamada, M., Torige, T., et al. (2013) Develop-ment of the PIRT for the Small-Break Loss-of-Coolant Accident with High Pressure Injection Failure. Proceedings of the ASME International Mechanical Engineering Congress and Exposition (IMECE2013), San Diego, 15-21 November 2013, 1-10. [Google Scholar] [CrossRef]
|
|
[20]
|
Larson, T.K., Moody, F.J., Wilson, G.E., et al. (2007) Iris Small Break Loca Phenomena Identification and Ranking Table (PIRT). Nuclear Engineering and Design, 237, 618-626. [Google Scholar] [CrossRef]
|
|
[21]
|
Westinghouse, IRIS Small Break LOCA Phenomena Identi-fication and Ranking Table (PIRT). WCAP-16318-NP, 2004.
|
|
[22]
|
刘宇生, 许超, 安婕铷, 等. 非能动核电厂全厂断电事故现象识别与排序研究[J]. 核安全, 2018, 17(1): 58-65.
|
|
[23]
|
Corletti, M.M. (2001) AP1000 PIRT and Scaling Assessment. Westinghouse Electric Company LLC, Washington DC.
|
|
[24]
|
Kang, K.-H., Bae, B.-U., Kim, J.-R., et al. (2015) Development of a Phenomena Identification Ranking Table for Simulating a Station Blackout Transient of a Pres-surized Water Reactor with a Thermal-Hydraulic Integral Effect Test Facility. Annals of Nuclear Energy, 75, 72-78. [Google Scholar] [CrossRef]
|
|
[25]
|
邓程程, 常华健. 非能动比例试验台架的最佳估算事故分析及不确定性研究[D]: [博士学位论文]. 北京: 清华大学, 2014.
|
|
[26]
|
Wilson, G.E., Fletcher, C.D., Davis, C.B., et al. (1997) PIRTs for Westinghouse AP600 SBLOCA, MSLB and SGTR Scenarios, NUREG/CR = 6541. Idaho National Engineering and Environmental Laboratory, Washington DC.
|
|
[27]
|
Zheng, M., Yan, J., Shentu, J., et al. (2016) The General Design and Technology Innovations of CAP1400. Engineering, 2, 206-217. [Google Scholar] [CrossRef]
|
|
[28]
|
叶潜. 小型堆小破口失水事故最佳估算及不确定性分析[D]: [硕士学位论文]. 武汉: 华中科技大学, 2019.
|