of International Activities in Accident Management and Decision Making in the Nuclear Industry

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[1]  D. F. Williams,et al.  AN 8 , 1999 .

[2]  T. G. Theofanous,et al.  Application of the risk oriented accident analysis methodology (ROAAM) to severe accident management in the AP600 advanced light water reactor , 1998 .

[3]  I. Catton,et al.  Reactor cavity flooding as an accident management strategy , 1998 .

[4]  P. V. Varde,et al.  An operator support system for research reactor operations and fault diagnosis through a connectionist framework and PSA based knowledge based systems , 1998 .

[5]  Ola Svenson.  A decision theoretic approach to an accident sequence: when feedwater and auxiliary feedwater fail in a nuclear power plant , 1998 .

[6]  O. Kymäläinen,et al.  In-vessel coolability and retention of a core melt , 1997 .

[7]  M. Sanchez,et al.  Extending PSA to accident management (AM): The case of the steam generator tube rupture (SGTR) emergency operating procedures assessment , 1996 .

[8]  Ali Mosleh,et al.  The development and application of the accident dynamic simulator for dynamic probabilistic risk assessment of nuclear power plants , 1996 .

[9]  P. Schnyder,et al.  SWISS , 1995, Cuisine, Texas.

[10]  Soon Heung Chang,et al.  Development of severe accident management supporting systems using quantified containment event trees , 1995 .

[11]  T. G. Theofanous,et al.  A consistent approach to severe accident management , 1994 .

[12]  A. Feigel,et al.  Implementation of bleed and feed procedures in Siemens PWRs , 1994 .

[13]  S. A. Hodge,et al.  Assessment of two BWR accident management strategies , 1994 .

[14]  Moosung Jae,et al.  Sensitivity and uncertainty analysis of accident management strategies involving multiple decisions , 1993 .

[15]  Moosung Jae,et al.  The Use of Influence Diagrams for Evaluating Severe Accident Management Strategies , 1992 .

[16]  Ed M. Dougherty.  Credibility and uncertainty associated with accident management actions , 1992 .

[17]  A. D. Swain,et al.  Handbook of human-reliability analysis with emphasis on nuclear power plant applications. Final report , 1983 .