Thursday

Friday

WEDNESDAY, 1 October 08

Opening

Invited Lectures
OECD/NEA, OECD/NEA Initiatives on Nuclear Safety, J. Reig, (OECD/NEA)

RC Petten, JRC IE Network Research Activities on NPP Operational Experience Feedback, V. Ranguelova (JRC-Petten)

Coffee Break

Poster Summary - Presenters Giovanni Bruna, Francesc Reventos and Estelle Sauvage

A1-1 Safety Assessment and Analysis

A1-042 VALIDATION OF TECH-M-97 CODE AGAINST RESULTS OF BEMUSE PROGRAM
S.L. Borisov, N.V. Bukin, N.S. Fil

A1-045 CATHARE ASSESSMENT OF PACTEL LOCA EXPERIMENTS WITH ACCIDENT MANAGEMENT
L. Sabotinov

A1-046 HEMERA: A 3D COUPLED CORE-PLANT SYSTEM FOR ACCIDENTAL REACTOR TRANSIENT SIMULATION
A. Sargeni, G.B. Bruna, B. Normand, F. Fouquet, E. Mury, F. Scarcelli, J.C. Le Pallec, R. Lenain, E. Hourcade, C. Poinot-Salanon,
E. Royer ,E. Richebois

A1-053 APPROACHES AND METHODS TO EVALUATE UNCERTAINTY IN SYSTEM THERMAL-HYDRAULICS CALCULATIONS. KEY APPLICATIONS BY CIAU METHOD
A. Petruzzi, F. D’Auria

A1-054 ADRESSING BORON DILUTION SCENARIO THROUGH RELAP5/3.3 ANALYSIS OF VVER-1000 SB LOCA
P. Pla, W. Giannotti, A. Del Nevo, N. Muellner, C. Parisi, F. D’Auria

A1-055 THE “CODE USER EFFECT” AND THE INTERNATIONAL TRAINING SEMINAR 3D S.UN.COP
A. Petruzzi, F. D’Auria, T. Bajs, F. Reventos

A1-060 INTERNATIONAL ACTIVITIES IN THE FIELD OF THERMAL-HYDRAULICS PERFORMED BY THE EC JRC IE IN THE FRAMEWORK OF THE TACIS AND PHARE PROGRAMMES
A., M. Biéth

A1-082 CYCLON-EFFECT IN PWR DOWNCOMER DURING BLOWDOWN SCENARIOS
F. Montenegro, J. Fradera, E. Mas de les Valls, O. Lozano, L. Batet, F. Reventós

A1-083 CODE VALIDATION AND SCALING OF THE ROSA/LSTF TEST 3-1 EXPERIMENT
V. M. Martínez, F. Reventós, C. Pretel, L. Batet

A1-2 Design safety issues

A1-006 FIRST EXPERIENCE WITH THE CONSOLIDATION OF WWER REACTOR PRESSURE VESSEL KNOWLEDGE THROUGH A NEW METHOD
U. von Estorff, L. Debarberis, M. Brumovsky, T. Williams

A1-032 COMPUTATIONAL FLUID DYNAMICS (CFD) AS A TOOL FOR PREDICTION OF THERMAL FATIQUE IN T-JUNCTIONS
B. Niceno, B. L. Smith, H-M. Prasser

A1-085 DESIGN PROCEDURES FOR AVOIDING INSTABILITY IN TWO-PHASE NATURAL CIRCULATION SYSTEMS
P. K. Vijayan, M.R. Gartia, A.K. Nayak, D. Saha, R.K. Sinha

A1-3 Licensing and Harmonisation

A1-034 SIMULATOR TRAINING AND NUCLEAR SAFETY IN KOZLODUY NPP PLC
K. D. Stoychev

A1-036 IBERDROLA NEW FUEL DESIGN LICENSING PROCESS
P. Mata

A1-068 APROS SIMULATION MODEL FOR OLKILUOTO-3 EPR APPLICATIONS
K.. Porkholm, H. Kontio, H. Plit, K.. Söderholm

A1-076 LICENSING PROCESS FOR POWER UPRATE- MEXICAN EXPERIENCE
Y.R. Mamani-Alegria, J.R. Salgado-Gonzalez, J. Miranda-Aldaco

A1-4 Operational safety

A1-017 NEUTRONICS AND THERMALHYDRAULICS COUPLED CALCULATIONS TO MODEL A LOCA FOR ADVANCED CANDU FUEL PROJECTS
I. Prodea

A1-018 SOURCE TERM EVALUATION FOR A SEVERE ACCIDENT IN CANDU TYPE REACTOR BY ASTEC CODE
M. Constantin, A. Rizoiu, I.. Turcu, C. Margeanu

A1-079 INTERNATIONAL EFFORTS TOWARDS GROUNDING OF NUCLEAR CONCEPTS SAFETY (SURVEY OF ISTC PROGRAMS RESULTS)
L.V. Tocheny

A1-080 PRESSURE DROP AND DRYOUT BEHAVIORS OF A VOLUMETRICALLY HEATED IRREGULAR PARTICLE BED
Y. Chen, P. P. Kulkarni, R. Kulenovic, M. Rashid, A. K. Nayak

A1-086 A STUDY OF THE INFLUENCE OF PLANT CONDITION ON THE HEAT REMOVAL FEASIBILITY AFTER A FAILURE OF THE RHRS
J.F. Villanueva, S. Carlos, V. Serradell, S. Martorell, F. Pelayo, R. Mendizábal

A1-108 INFLUENCE OF NPP KRSKO CORE NUCLEAR CHARACTERISTICS ON RCCA EJECTION ACCIDENT
I. Ivekovic, D. Grgic, D. Pevec, J. Vukovic

A1-110 APPLICATION OF THE SYSTEM THERMAL-HYDRAULICS CODES FOR THE EVALUATION OF THE OPERATING PWR PLANT SAFETY IN THE SHUTDOWN CONDITIONS
N. Čavlina, N. Debrecin, T. Bajs, V. Benčik

A1-114 PROBABILISTIC EVALUATION OF POTENTIAL PTS SCENARIOS
I.Bašić, I. Vrbanić

A1-116 PSA QUANTIFICATION COMPARISON BETWEEN BDD AND CONVENTIONAL APPROACH
Z. Šimić, R. Banov, V. Mikuličić

A1-124 SLOVENIAN POWER SYSTEM RELIABILITY ANALYSIS
A. Volkanovski, B. Mavko, M. Čepin

A1-125 INFLUENCE OF CONTINUOUS CORIUM FIELD ON STEAM EXPLOSION SIMULATION RESULTS
M. Uršič, M. Leskovar

A2 Safety of Future Reactor Designs

A2-112 EXPERIMENTAL CHARACTERISATION OF A TWO PHASE NATURAL CIRCULATION LOOP SIMULATING A PASSIVE EMERGENCY HEAT REMOVAL SYSTEM
Lorenzo Santini, Davide Papini, Marco E. Ricotti, Davor Grgić

A3 Research Reactors

A3-047 SAFETY ISSUES OF COLD NEUTRON SOURCES IN RESEARCH REACTORS
K. H. Gobrecht O. A. Scheuer

A3-100 NEURAL NETWORK APPLICATION TO ON-LINE MONITORING OF CRDM AND THERMO-HYDRAULIC CONDITION
M. Sepielli, M. Palomba, A. Ratto, R. Rosa, M. Bernabucci

A3-002 ANALYSIS OF THE EFFECT OF INTERNAL FIRE ON THE SAFETY OPERATION OF TEHRAN RESEARCH REACTOR
S. S. Arshi, M. R. Nematollahi, K. Sepanloo

A4 Fuel Cycle Safety

A4-037 ORGANIZATION FOR NUCLEAR SAFETY IN NUCLEAR FUEL PLANT PITESTI ROMANIA
Gh. Epure, T. Ivana

Lunch

Poster Session

l Parallel Sessions l

Area 1-1: Safety Assessment and Analysis

A1-016 EVALUATION OF THE IMPACT THAT PARS HAVE ON THE HYDROGEN RISK IN THE REACTOR CONTAINMENT: METHODOLOGY AND APPLICATION TO PSA LEVEL 2
A. Bentaib, C. Caroli, B. Chaumont, K. Chevalier-Jabet

A1-071 COMPARATIVE ANALYSIS OF GRAPHITE STACK BEHAVIOUR IN TKR-TESTS AND KURSK-5 REACTOR BY COMPLEX CODE U_STACK
O.Yu. Novoselsky, A.A. Semchenkov, L.M. Parafilo, D.V. Kryuchkov

A1-091 A GENERIC ASSESSMENT OF THE RIA INTERIM CRITERIA IN A TYPICAL 3 LOOP 12 FEET PWR WITH 3D METHODS
J. Riverola, T. Nuñez

Area 3: Research Reactors

A3-013 THE BORAX ACCIDENT IN THE JHR
B. Maugard, J-P.Elie, D. Iracane, P. Trémodeux, F. Witters

A3-021 GAMMA HEATING DEPENDENCE ON FUEL ENRICHMENT: A NUMERICAL EXPERIMENT
M. Varvayanni, P. Savva, N. Catsaros

A3-024 DATA COLLECTION COMPUTERIZED SYSTEM FOR TRIGA RESEARCH REACTOR
D. Mladin

Area 2-1: Safety of Forthcoming Reactors

A1-127 AP1000: THE PWR REVISITED
P. Gaio

A1-128 THE SAFETY CONCEPT OF THE SWR 1000 WITH ACTIVE AND PASSIVE SAFETY SYSTEMS
W. Brettschuh, D. Pasler

A1-094 ACR-1000©: ADVANCED CANDU BASED ON PROVEN SAFETY OF CANDU REACTORS,
N. Popov, R. Ion, M. Cormier, P. Santamaura, S. Yu, R. Duffey

Coffee Break

l Parallel Sessions l

Area 1-4: Operational Safety

A1-103 STATE-OF-THE-ART OF THE IGNALINA RBMK-1500 SAFETY
E. Uspuras

A1-120 TOOLS TO SUPPORT IMPORTANT TECHNICAL DECISIONS DURING ACCIDENT CONDITIONS
J. Tenschert, C. Bergiers

A1-123 AN ESTIMATION OF OPERATOR ACTION SUCCESS CRITERIA TIME WINDOWS WITH BEST ESTIMATE CODE
A. Prošek, B. Mavko

A1-126 AN EVALUATION ON THE EMERGENCY OPERATION STRATEGY FOR THE RECIRCULATION SUMP BLOCKAGE AT KORI UNITS 3&4
C. G. Lee, C. S. Lee, S. H. Shin, E. K. Kim

Area 3: Research Reactors

A3-029 SAFETY BARRIERS OF THE HANARO RESEARCH REACTOR
H. S. Jung, I.C. Lim

A3-035 TRANSIENT BEHAVIOUR OF LOW ENRICHED URANIUM SILICIDE PLATE-TYPE FUEL FOR RESEARCH REACTORS
K. Yanagisawa

A3-038 REEVALUATION OF BDBA CONSEQUENCES OF RESEARCH REACTORS
G. Biaut, T. Bourgois, G. Bruna

A3-050 SIMULATING A PARTIAL LOCA IN A NARROW CHANNEL USING THE DSNP SIMULATION SYSTEM
D. Saphier

Area 1-1: Safety Assessment and Analysis

A1-011 LARGE SCALE EXPERIMENTS ON GAS DISTRIBUTION IN THE CONTAINMENT
K. Fischer

A1-067 SPATIAL DISCRETIZATION IN LWR CELL CALCULATIONS WITH HELIOS 1.9: INFLUENCE ON KINF AND FLUX DISTRIBUTION
B. Merk, R. Koch

A1-088 THE ROLE OF ENTRAINED DROPLETS IN PRECURSURY  COOLING DURING PWR POST-LOCA REFLOOD
D. Chatzikyriakou, S.P. Walker, G.F. Hewitt

A1-122 ROLE OF RELAP/SCDAPSIM IN NUCLEAR SAFETY
C. Allison