Benchmarking Studies of Probabilistic Fracture Mechanics Analysis Code, PROFMAC-II, for Assessing Pressurized Thermal Shock Events of Reactor Pressure Vessel Integrity Issues

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    • SONEDA Naoki
    • Komae Research Laboratory, Central Research Institute of Electric Power Industry
    • ONCHI Takeo
    • Komae Research Laboratory, Central Research Institute of Electric Power Industry


The probabilistic fracture mechanics analysis code, PROFMAC-II, was developed and benchmarked for postulated pressurized thermal shock (PTS) events of pressurized water reactor pressure vessel integrity issues by participating the PTS benchmarking activities organized and managed jointly by U.S. Nuclear Regulatory Commission (USNRC) and Electric Power Research Institute (EPRI). Three different sets of benchmarking problems were assigned to participants for the studies in sequence. The initial and second sets were preparatory to the third set. Results from the sequential benchmarking activities were that for axial flaw analyses probabilities of crack initiation were identical to those for vessel failure and the scatter of probabilities among four participating codes was small, while for circumferential flaw analyses probabilities varied widely. It was eventually verified that the same probabilities were achievable by unifying procedures for simulating material properties. Performance of the PROFMAC-II code was excellent in terms of consistency and adequacy among the four codes and the eight organizations which took part in the studies. Several issues relevant to analysis techniques and input variables were pointed out for further improvement of the codes.


  • Journal of Nuclear Science and Technology  

    Journal of Nuclear Science and Technology 33(1), p.87-98, 1996-01-25 

    Atomic Energy Society of Japan

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