Probabilistic safety analysis of a Greek Research Reactor
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[1] R. A. Bari,et al. Probabilistic safety analysis procedures guide , 1984 .
[2] Mohammad B. Ghofrani,et al. Determination of the safety importance of systems of the Tehran research reactor using a PSA method , 2002 .
[3] G. E. Apostolakis,et al. Experience with probabilistic risk assessment in the nuclear power industry , 1992 .
[4] C. Housiadas,et al. Thermal-hydraulic Calculations for the GRR-1 Research Reactor Core Conversion to Low Enriched Uranium Fuel , 2000 .
[5] Ensign Johnson,et al. certainly helpful, theimprovement realized byproper(5) Reactor Safety Study, "Appendix III -Failure data," USNuclear weighting isstill evident evenwhenthes-bias parameters Regulatory Commission Report WASH-1400, NUREG-75/014, , 1984 .
[6] Christos Housiadas,et al. Simulation of loss-of-flow transients in research reactors , 2000 .
[7] Ioannis A. Papazoglou,et al. Technical modeling in integrated risk assessment of chemical installations , 2002 .
[8] B. Mavko,et al. Influence of specific data on a research reactor probabilistic model , 1996 .