Evaluation of Uncertainties in Relation to Severe Accidents and
Level-2 Probabilistic Safety Analysis

Workshop Proceedings
Aix-en-Provence, France
7-9 November 2005

Uncertainty in relation to several severe accident phenomena plays a major role in probabilistic safety analyses involving beyond-design-basis accident scenarios for nuclear power plants. The technical papers presented herein will be valuable for nuclear safety analysts, nuclear power plant designers and R&D managers, especially with regard to unresolved severe accident issues or issues where risk uncertainty is high.

Session III: Applications to Uncertainty Assessment on Severe Accident Physical Phenomena

8. Christophe JOURNEAU and Pascal PILUSO, Commissariat à l'Energie Atomique (CEA), France. Uncertainties on Thermodynamic and physical properties DataBases for Severe Accidents and their Consequences on Safety Calculations. Presentation

9. Adolf RYDL, NRI (Nuclear Research Institute) Rez, Czech Republic. Simple Probabilistic Approach to Evaluate Radioiodine Behaviour at Severe Accidents: Application to PHEBUS Test FPT-1.
Presentation

10. Joelle FLEUROT and Georges REPETTO, Institut de Radioprotection et de Sûreté Nucléaire (IRSN), France. Sensitivity Studies of Main Uncertain Core Degradation Parameters on Severe Accident Consequences.
Presentation

11. Randall GAUNTT, Sandia National Laboratories, United States. Uncertainty Analyses Using the MELCOR Severe Accident Analysis Code
Presentation

12. Christine BALS et al, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Germany. Post-Test Calculation and Uncertainty Analysis of the Experiment QUENCH-07 with the System Code ATHLET-CD.
Presentation

13. Daniel MAGALLON et al, Commissariat à l'Energie Atomique (CEA), France. FCI Phenomena Uncertainties Impacting Predictability of Dynamic Loading of Reactor Structures (SERENA Programme).
Presentation

14. Hymie SHAPIRO, Atomic Energy of Canada Limited (AECL), Canada. Design Features of ACR in Severe Accident Prevention and Mitigation.

15. Seung J. OH, and H. T. KIM, Korea Hydro and Nuclear Power (KHNP), Korea. Effectiveness of External Reactor Vessel Cooling (ERVC) Strategy for APR1400 and Issues of Phenomenological Uncertainties.
Presentation

16. Fernando ROBLEDO SANZ et al., Consejo de Seguridad Nuclear (CSN), Spain. Development of a simple computer code to obtain relevant data on H2 and CO combustion in severe accident and to aid in PSA-2 assessments.
Presentation

17. Sudhamay BASU, USNRC, United States and M.T. FARMER, ANL, United States. Significance of the OECD-MCCI Program in Relation to Severe Accident Uncertainties Evaluation.
Presentation