Thursday

Friday

THURSDAY, 2 October 08

Invited Lectures
CIEMAT, Nuclear Safety Research: A "Sine-Que-Non" Of Nuclear Power Plant Performance,  L. Herranz (CIEMAT)

JNSC, Current Nuclear Reactor Safety R&Ds and Trends in Japan, H. Ninokata (JNSC)

l Parallel Sessions l

Area 2-1: Safety of Forthcoming Reactors

A2-007 EPR SAFETY CONCEPT
J. Wirkner, J. Czech

A2-023 EUROPEAN UTILITY REQUIREMENTS (EUR) VOLUME 3 ASSESSMENT FOR AP1000 AND EPP PHASE 2E PROGRAM
G. Saiu, M. Frogheri

A2-004 DEVELOPMENT OF NATIONAL INFRASTRUCTURE FOR SAFE AND RELIABLE NUCLEAR POWER
R.I. Facer, N. Pieroni, A. Starz

Area 1-2: Design Safety Issue

A1-099 APPLICATION OF CFD CODES IN NUCLEAR REACTOR SAFETY ANALYSIS
U. Rohde, T. Höhne, E. Krepper, S. Kliem

A1-104 SAFETY IMPROVEMENTS IN MOCHOVCE 3&4 DESIGN
E. Bianco, F. Peinetti, I. Tripputi

A1-066 ANALYSIS, BY RELAP5 CODE, OF BORON DILUTION PHENOMENA IN SMALL BREAK LOCA AND IN MID LOOP OPERATION TRANSIENTS, PERFORMED IN PKL III TEST FACILITY
F. Mascari, G. Vella, F.D’Auria

Area 1-3: Licensing and Harmonisation

A1-096 REGULATORY CHALLENGES POSED BY THE “BEST-ESTIMATE PLUS UNCERTAINTY” METHODOLOGIES
R. Mendizábal, F. Pelayo

A1-097 ACCIDENT MANAGEMENT GUIDANCE AND INDIVIDUAL PLANT ACCIDENT MANAGEMENT SUPPORT -RECENT IAEA ACTIVITIES
S. H. Lee, G. L. Vayssier

A1-026 THE SGTR (STEAM GENERATOR TUBE RUPTURE) LICENSING EVOLUTION AND THE ASSOCIATED MODIFICATIONS FOR NUCLEAR UNITS IN BELGIUM
F. Parmentier, J.-C. Delalleau

Coffee Break

Area 2-2: Safety of Future Reactor Designs

A2-113 A CRITICAL OVERVIEW ON DIFFERENT SOLUTIONS FOR IN-POOL CONDENSERS FOR PASSIVE SAFETY SYSTEMS
D. Papini, A. Cammi, D. Grgić

A2-022 ANSALDO RESEARCH ACTIVITIES ON CRITICAL AND SUB-CRITICAL LEAD FAST REACTORS
A. Alemberti, L. Mansani, M. Frogheri

A2-015 SLOW REACTIVITY INSERTION IN SUBCRITICAL REACTORS. APPLICATION TO ADS
C. Montalvo, A. García-Berrocal, M. Balbás, J. Blázquez

Area 1-2: Design Safety Issue

A1-051 INDUSTRIAL SAFETY AND NUCLEAR SAFETY CONNECTIONS
G. Petrangeli

A1-062 USE OF PSA IN THE DESIGN AND CONSTRUCTION PHASE OF NPPS IN FINLAND
R. Himanen

A1-101 SAFETY ASSURANCE AND GOALS OF GENERIC NPP DESIGNS
M. El-Shanawany, R. Pape, I. Kouzmina

Area 1-3: Licensing and Harmonisation

A1-089 NPP SAFETY IN UKRAINE: RECENT DEVELOPMENTS AND TREND
G. Gromov, O. Sevbo, S. Sholomitsky

A1-115 EXPLOITATION OF BEPU APPROACH FOR THE LICENSING PROCESS
C. Camargo, R. Galetti, F. D’Auria, O. Mazzantini

A1-048 CULTURAL AND ORGANISATIONAL FACTORS LEADING TO MAJOR EVENTS
L. G.A. van Wijk, R. H. Taylor, J. H.R. May

Lunch

Poster Session

l Parallel Sessions l

Area 1-1: Safety Assessment and Analysis

A1-028 ON THE ANALYSIS AND EVALUATION OF DIRECT CONTAINEMENT HEATING WITH THE MULTIDIMENSIONAL MULTIPHASE FLOW CODE MC3D
M. Renaud, J. Tanguy

A1-044 CATHARE MULTI-1D MODELING OF COOLANT MIXING IN VVER-1000 FOR RIA ANALYSIS
N.P. Kolev, I. Spasov, J.Donov, N.Petrov, L.Sabotinov

A1-063 CFD SIMULATIONS OF GIDROPRESS MIXING FACILITY EXPERIMENTS IN THE FRAMEWORK OF TACIS PROJECT R2.02/02
T. Höhne, U. Rohde, D. Melideo, F. Moretti, F. D’Auria, A. Shishov, E. Lisenkov

A1-064 UNCERTAINTY ANALYSIS OF MODELING (UAM) AND SAFETY IMPLICATIONS
K. Ivanov, M. Avramova, I. Kodeli, E. Sartori

Area 2: Safety of Future Reactor Designs

A2-008 CONCEPT OF A FUTURE HIGH PRESSURE-BOILING WATER REACTOR, HP-BWR
F. Reisch

A2-049 SUPERIOR SAFETY RESPONSE OF THE VERY HIGH TEMPERATURE PB REACTOR
D. Saphier

A2-119 EVALUATION OF A CORE MID-PLANE BLANKET FOR VOID EFFECT REDUCTION IN LEAD FAST REACTOR
R. Ghazy, M. E. Ricotti

Area 1-3: Licensing and Harmonisation?

A1-057 A NEW METHOD TO RESPECT THE REAL STATE OF KNOWLEDGE ON UNCERTAINTIES IN THE EVALUATION OF SAFEY MARGINS
J. Baccou and E. Chojnacki

A1-069 NUCLEAR SAFETY RISK-INFORMED DECISION MAKING
F. M. Reinhart

A1-078 CURRENT TREND IN NUCLEAR SAFETY IN BELGIUM
R. Ashley

Conference Dinner (co-sponsored by Westinghouse)