4Advances in Elastic-Plastic Fracture Analysis[R].EPRI Report NP-3607,Palo Alto,CA:Electric Power Research Institute,1984.
5Robert E.Henry.The Two-phase Critical Discharge of Initially Saturated or Subcooled Liquid[J].Nuclear Science and Engineering,1970,41:330-342.
6NUREG-0800,U.S.Nuclear Regulatory Commission,Standard Review Plan 3.6.3,Leak-Before-Break Evaluation Procedures[S].Revision 1,March,2007.
7Mechanical Fracture Predictions for Sensitized Steel Piping with Circumferential Cracks[R].EPRI Report NP-192,Palo Alto,CA:Electric Power Research Institute,1976.
8Yang Yaguang,Sydnor Russell.Reliability estimation for a digital instrument and control system[J].Nuclear Engineering and Technology,2012,44(4):405-414.
9Bjorn Axel Gran.The use of bayesian belief nets in safety assessment of software based systems[R].Norway:In Special Issues of International Journal on Intelligent Information Systems at FLINS'98 Int.J.General Systems,2000.