引文
[1]Ellingwood B.Validation of seismic probabilistic risk assessments of nuclear power plants[R].NUREG/CR-0008,1994.
[2]Kennedy R P,Ravindra M K.Seismic fragilities for nuclear power plant studies[J].Nuclear Engineering and Design,1984,79(1):47-68.
[3]Park Y J,Hofmayer C H,Chokshi N C.Survey of seismic fragilities used in PRA studies of nuclear power plants[J].Reliability Engineering and System Safety,1998,62:185-195.
[4]Reed J W,Kennedy R P.Methodology for developing seismic fragilities[R].Report TR-103959,Electric Power Research Institute,1994.
[5]Budnitz R J.Current status of methodologies for seismic probabilistic safety analysis[J].Reliability Engineering and System Safety,1998,62:71-88.
[6]EQE.Summary of the seismic adequacy of twenty classes of equipment required for safe shutdown of nuclear plants[R].Report EPRI NP-7149-D,Electric Power Research Institute,1991.
[7]Tsai N C,Mochizuki G L,Holman G S.Componentfragility research program phase II development of seismic fragilities from high-level qualification data[R].NUREG/CR-5470,Lawrence Livermore National Laboratory,1989.
[8]Holman G S,Chou C K.Componentfragility research program phase I component prioritization[R].NUREG/CR-4899,Lawrence Livermore National Laboratory,1987.
[9]Ohtani K,Shibata H,Watabe M,et al.Seismic proving tests for nuclear power plant no.1[C]//Earthquake Engineering,Tenth World Conference,Balkema,Rotterdam,1992:3603-3608.
[10]Shimazaki Y,Kusumoto S,Akiyama H,et al.Seismic proving tests for nuclear power plant,no.2[C]//Earthquake Engineering,Tenth World Conference,Balkema Rotterdam,1992:3609-3614.
[11]Kennedy R,Nie J,Hofmayer C,et al.Evaluation of JNES equipment fragility tests for use in seismic probabilistic risk assessments for U.S.nuclear power plants[R].NUREG/CR-7040,Office of Nuclear Regulatory Research,2011.
[12]Iijima T,Abe H,Fujita T.Program outline of seismic fragility capacity tests on nuclear power plant equipment[C]//Proceedings of the 12th International Conference on Nuclear Engineering,ICONE12,Virginia,USA,2004,367-374.
[13]Iijima T,Abe H,Suzuki K.Seismic fragility capacity of equipment-horizontal shaft pump test[C]//Proceedings of the 18th International Conference on Structural Mechanics in Reactor Technology,SMiRT 18,Beijing,China,2005.
[14]Iijima T,Abe H,Suzuki K.Seismic fragility capacity of equipment-electric panel test[C]//Transactions of the 19th International Conference on Structural Mechanics in Reactor Technology,SMiRT 19,Toronto,Canada,2007.
[15]Fujita T,Sasaki Y,Abe H,et al.NUPEC project:seismic proving test on reactor shutdown cooling systems-(summary of results)[C]//K17/3,Transactions of the 14th International Conference on Structural Mechanics in Reactor Technology,SMiRT 14,Lyon,France,1997.
[16]Hirama T,Goto M,Hasegawa T,et al.Seismic proof test of a reinforced concrete containment vessel(RCCV)Part 1:Test model and pressure test[J].Nuclear Engineering and Design,2005,235:1335-1348.
[17]Hirama T,Goto M,Shiba K,et al.Seismic proof test of a reinforced concrete containment vessel(RCCV)Part 2:Results of shaking table tests[J].Nuclear Engineering and Design,2005,235:1349-1371.
[18]Hirama T,Goto M,Kumagai H,et al.Seismic proof test of a reinforced concrete containment vessel(RCCV)Part 3.Evaluation of seismic safety margin[J].Nuclear Engineering and Design,2007,237:1128-1139.
[19]Bandyopadhyay K K,Hofmayer C H.Seismic fragility of nuclear plant components(phase I)[R].NUREG/CR-4659,BNL-NUREG-52007,Vol.1,July 1986.
[20]Bandyopadhyay K K,Hofmayer C H,Kassir M K,et al.Seismic fragility of nuclear power plant components(phase II)a fragility handbook on eighteen components[R].NUREG/CR-4659,BNL-NUREG-52007,Vol.4,August 1991.
[21]王晓磊,侯钢领,吕大刚.某核电站安全壳1:15模型振动台试验[J].工程力学,2014,31(增刊):249-252.WANGXiaolei,HOU Gangling,LDagang.Shaking table tests of a 1:15 reinforced concrete containment vessel model for a nuclear power plant[J].Engineering Mechanics,2014,31(Suppl):249-252.(in Chinese)
[22]Cover L E,Bohn M P,Campbell R D,et al.Handbook of nuclear power plant seismic fragilities[R].NUREG/CR-3558,Lawrence Livermore National Laboratory,June 1985.
[23]Newmark N M,Cornell C A.On the seismic reliability of nuclear power plants[C]//ANS Topical Meeting on Probabilistic Reactor Safety,Newport Beach,CA,May 1978.
[24]Campbell R,Hardy G,Merz K.Seismic fragility application guide[R].EPRI 1002988,Palo Alto,California,December 2002.
[25]Newmark N M.Inelastic design of nuclear reactor structures and its implications on design of critical equipment[C]//Transactions of the 4th International Conference on Structural Mechanics in Reactor Technology,San Francisco,CA,1977.
[26]Riddell R,Newmark N M.Statistical analysis of the response of nonlinear systems subjected to earthquakes[R].University of Illinois Civil Engineering Department Report UILU 79-2016,August 1979.
[27]Kennedy R P,Murray R C,Ravindra M K,et al.Assessment of seismic margin calculation methods[R].NUREG/CR-5270,Lawrence Livermore National Laboratory,March 1989.
[28]Shinozuka M,Hwang H,Reich M.Reliability assessment of reinforced concrete containment structures[J].Nuclear Engineering and Design,1984,80:247-267.
[29]Ellingwood B,Bhattacharya B,Zheng R.Reliability-based condition assessment of steel containment and liners[R].NUREG/CR-5442,ORNL/TM-13244,Oak Ridge National Laboratory,1996.
[30]Klamerus E W.Structural seismic fragility analysis of the Surry containment[R].NUREG/CR-6783,SAND2002-1996P,Sandia National Laboratories,2002.
[31]International Atomic Energy Agency.Earthquake experience and seismic qualification by indirect methods in nuclear installations[R].IAEA-TECDOC-1333,Vienna,Austria,January 2003.
[32]Kennedy R P,vonRiesemann W A,Wyllie L A,et al.Use of seismic experience and test data to show ruggedness of equipment in nuclear power plants[R].Sandia National Laboratories,June,1992.
[33]Baughman P,Sumodobila B N.SQUG electronic earthquakes experience database users guide[R].EPRI TR-113705,EPRI,Palo Alto,CA,1999.
[34]Cummings G E.The use of data and judgment in determining seismic hazard and fragilities[C]//8thInternational Conference on Structural Mechanics in Reactor Technology,Brussels,Belgium,August 19-23,1985.
[35]George LL,Mensing R W.Using subjective percentiles and test data for estimating fragility functions[C]//DOE Statistical Symposium,sponsored by the Department of Energy,Berkeley,CA,January 15,1981.
[36]Bandyopadhyay K K,Hofmayer C H,Kassir M K,et al.Seismic fragility of nuclear power plant components(phaseⅡ)[R].NUREG/CR-4659,BNL-NUREG-52007,Vol.3,1990.
[37]USNRC.Reactor safety study[R].WASH 1400,NUREG-73/041,1975.
[38]Hwang H H M.Fragility assessment for seismic PRA studies[R].BNL-NUREG-36344,TI85 012506,Brookhaven National Laboratory,NY,USA,1985.
[39]Kennedy R P,Ravindra M K.Seismic fragilities for nuclear power plant risk studies[J].Nuclear Engineering and Design,1984(79):47-68.
[40]Smith P D,Dong R G,Bernreuter D L,et al.Seismic safety margins research program phase I final report-overview[R].NUREG/CR-2015,Vol.1,Lawrence Livermore Laboratory,1981.
[41]Hwang H,Reich M,Shinozuka M.Structural reliability analysis and seismic risk assessment[R].BNL-NUREG-34502,Brookhaven National Laboratory,1984.
[42]Kennedy R P,Murray R C,Ravindra M K,et al.Assessment of seismic margin calculation methods[R].NUREG/CR-5270,Lawrence Livermore National Laboratory,1989.
[43]Kennedy R P.Overview of methods for seismic PRA and margins analysis including recent innovations[C]//Proceedings of OECD/NEA Workshop on Seismic Risk,Tokyo,Japan,Aug.10-12,1999.
[44]Lee N H,Song K B.Seismic capability evaluation of theprestressed/reinforced concrete containment,Yonggwang nuclear power plant Units 5 and6[J].Nuclear Engineering and Design,1999,192:189-203.