Programme

FRIDAY, 3 October 08

8:30
- 9:00

Invited Lecture

WANO, Energy and Climate Change: The Role of Nuclear Safety, L. Mampaey (WANO)

9:00
- 10:30

l Parallel Sessions l

Area 4: Fuel Cycle Safety

A4-009 CRISTAL: A FRENCH CRITICALITY CODE PACKAGE TO ASSESS AREVA NP NUCLEAR INSTALLATION CRITICALITY SAFETY
M. Doucet, N. Comte, L. Durand-Terrasson, Ch. Faignet, M. Landrieu, S. Zheng

A4-010 OPTIMIZING TRANSPORT SECURITY: RISK ANALYSIS / EMERGENCY RESPONSE PREPAREDNES
P. Chollet

A4-012 COMPARISON OF THE SEVERE ACCIDENT BEHAVIOUR OF ADVANCED NUCLEAR FUEL ROD CLADDING MATERIALS
M. Grosse, L. Sepold, M. Steinbrueck, J. Stuckert

Area 1-1: Safety Assessment and Analysis

A1-107 INFLUENCE OF MODELLING OPTIONS IN RELAP5/SCDAPSIM AND MAAP4 COMPUTER CODES ON CORE MELT PROGRESSION AND REACTOR PRESSURE VESSEL INTEGRITY
S. Šadek, S. Špalj, B. Glaser

A1-084 MAIN RESULTS OF PHASE IV BEMUSE PROJECT. SIMULATION OF LBLOCA IN A NPP
M. Pérez, F. Reventós, L. Batet R. Pericas, P. Toth P. Bazin A. de Crécy, S. Borisov, H. Glaeser. T. Skorek , J. Joucla, P. Probst, A. Ui, B. Chung, D.Y-Oh, M. Kyncl, R. Pernica, A. Manera, F. D'Auria, A. Petruzzi, A. Del Nevo

A1-003 AN INNOVATIVE TRAINING PROGRAM TO INCREASE SAFETY CULTURE ON ELECTRABEL-SUEZ NUCLEAR POWER PLANTS
S. Powis, L. Maricq, K. Cauwenbergh, S. Crohain, K. De Keiser

10:30
- 11:00

Coffee Break

11:00
- 12:30

l Parallel Sessions l

Area 4: Fuel Cycle Safety

A4-020 AN EXAMPLE OF RISK INFORMED METHODOLOGIES FOR ACCIDENT ANALYSIS IN A FUEL FABRICATION PLANT THE JUZBADO INTEGRATED SAFETY ANALYSIS PROJECT
Óscar Zurrón-Cifuentes, Carolina Álvaro-Pérez

A4-058 SAFETY IMPROVEMENTS ON FUEL ROD BEHAVIOR BECAUSE OF AXIAL FISSION GAS TRANSPORT MODELING
M.T. del Barrio, L.E. Herranz

A4-072 AREVA-CERCA 10 YEARS LICENCE FOR FUEL FABRICATION
E. Torlini, T. Pin

Area 1-1: Safety assessment and analysis

A1-014 SARNET: SEVERE ACCIDENT RESEARCH NETWORK OF EXCELLENCE
T. Albiol, J-P. Van Dorsselaere, B. Chaumont, T. Haste, C.Journeau, L. Meyer, B. R. Sehgal, B. Schwinges, D. Beraha, A. Annunziato, R. Zeyen

A1-031 TWO NEW MODELS IN SCDAP FOR CANDU FUEL CHANNEL UNDER SEVERE ACCIDENTS
M. Mladin, D. Dupleac, I. Prisecaru

A1-052 PREDICTIONS OF POST-CHF HEAT TRANSFER IN HEATED TUBES USING THE TRACE SYSTEM CODE
B. Belhouachi, M. Ahmad, S.P. Walker, G.F. Hewitt

12:30
- 13:30

Lunch

13:30
- 14:30

Invited Lectures

Global Safety Regime, M. Modro (IAEA)
Towards European Regulation for Existing NPPs: Contribution of Nuclear Licensees, B. Fourest (EdF)

14:30
-15:30

Panel and Closure
Nuclear Safety Technology: Where We Are?
Panelists: F. D’Auria, N. Cavlina (Chairmen); N. Popov (Industry), M. Modro (International)