|
Name/Organization |
Title of presentation |
Printing version |
|
Josef Misak, IAEA
|
IAEA Activities in the Aria of WWER Reactor Nuclear Safety
|
slides
document |
|
Alexander Kolotov, REA
|
Rosenergoatom Safety Assessment Program for NPP Power Units
|
document(eng)
document(rus) |
|
Oleg Makhniouk, GAN
|
In-Depth Safety Assessment Results for Operating RBMK NPPs
|
abstract
document |
| Sandor Szirmai, HAEA |
The FSAR of the Paks NPP and its Safety Analysis Chapter |
document |
|
Gyozo Fejerdy, Paks NPP
|
Modeling of Overpressure Protection System Using APROS-5.11
|
abstract
slides |
|
Nicolay Fil,Podshibiakin A.K., Borisov L.N., Shchekoldin V.V., Gidropress
|
Sensitivity of VVER-1000 LB-LOCA Analysis to Initial/Boundary Conditions
|
document |
|
M. Modro, INEEL; S. Chakraborty, Switzerland;
M. Clemente, Germany;
J. E. Fisher, USA;
M.W. Jankowski, IAEA;
M. Khatib-Rahbar, USA;
E. Knoglinger, IAEA Consultant;
A. Krayushkin, Russia;
D.A. Mikhaylov, Russia;
J. Misak, IAEA;
|
Accidents Analysis and Associated Training Program for Kursk NPP #1 (Phase 1)
|
abstract |
|
M. Jankowski, IAEA; S. Chakraborty, Switzerland;
M. Clemente, Germany;
S. Dolganov, Russia;
J. E. Fisher, USA;
M. Khatib-Rahbar, USA;
E. Knoglinger, IAEA Consultant;
J. Misak, IAEA;
M. Modro, USA;
S. Neelov, Russia;
A.A. Potapov, Russia;
V.E. Radkevich, Russia;
M.I. Rozhdestvensky, Russia;
|
Accidents Analysis and Associated Training Program for Kursk NPP #1 (Phase 2)
|
slides |
|
Igor Karelov, M.L. Perepelitsa, EIS
|
Analysis of Feed and Bleed Regime for Modified PORVs on Z-NPP #5,6
|
abstract
document |
|
Eva Toth, Paks NPP
|
Bubble Condensor Experimental Qualification Project |
abstract
slides |
|
Sergey Kukhar, LNPP
|
Upgrading of Leningrad NPP Based on PSA Results |
slides |
|
Ihor Sergeyev, EIS
|
Overview of Internal Events PSA of Unit-1 of Khmelnitskiy NPP |
abstract |
|
Sergiy Krasnukha, S.Zhalilo, SUNPP
|
Main Results of Peer Review of PSA of SUNPP |
abstract
slides |
|
Heorhiy Balakan, A. Prokhodtsev, SUNPP
|
Management of the Risk of SUNPP based on PSA Level-1 Results |
abstract
slides
document |
|
A. Zhavrid, V.S. Boytchyuk, ZNPP
|
Zaporizhzhe NPP #5 PSA Level-1: Results and Review Comments |
abstract
slides
document |
|
K. Scherbinin, KhNPP; Sergey Vetchynkin, KIEP
|
In-Depth Safety Assessment of Khmelnitsky NPP #1, based on Non-Lead Plant |
abstract
slides
document |
|
Sergey Stashevsky, Vladlen Yarovoy, EIS
|
Evaluation of Equipment Replacements at ZNPP #5 Using SAPHIRE Code |
abstract
slides
document |
|
Michael Modro, R. Scott Hartley, Steven D. Novack, Kelly Reeves, INEEL
|
INEEL Probabilistic Risk Monitor Software for SAPHIRE |
abstract |
|
Bronislav Vinnikov, Kurchatov Institute; S.D. Novack, INEEL
|
Peer Review of a Risk Monitor based on the SAPHIRE Code |
abstract |
|
Miroslav Jakes, Czech Nucl. Safety Authority
|
Introduction to the PSA of Temelin NPP |
slides |
|
G. Samokhin, SEC-NRS
|
Defining Success Criteria and Acc. Sequence Analysis Tasks for VVER-440 PSA |
slides
document |
|
Lenard Saguidulin, D.Goma, ET&D
|
Peer Review of PSA Projects for Ukrainian NPPs |
abstract
slides |
|
Tatiana Berg, SEC-NRS
|
Development of Regulatory PSA Documents and PSA Review |
slides |
|
Bronislav Vinnikov, Kurchatov Institute
|
In-Depth Reliability Analysis of Kursk NPP #1 ECCS before Upgrading |
|
|
Natalia Istomina, Tatiana Tchoulkova, SEC-NRS
|
Use of Expert Methods for for Evaluation of Acc. Consequences |
abstract(eng)
abstract(rus)
slides
document |
|
V.E Kroshilin, S.D. Kalinitchenko, A.E. Kroshilin, VNIIAES
|
THA of NPP Primary and Secondary Circuits with BAGIRA Code |
abstract
document |
|
Bruce Schmitt, PNNL
|
Deterministic Analysis Support for the LNPP #2 In-Depth Safety Assessment |
slides |
|
Alexander Bolibok, Vasily Galkin, EIS
|
General Approach to EOIs; Analytical Justification for ZNPP #5 |
abstract
document(eng)
document(rus) |
|
Peter Matejovic, M. Bachraty, IVS Trnava; D. Svincak, J. Balazi, Bohunice NPP
|
Analysis of EOIs for Bohunice V-1 NPP |
slides
document |
|
Valeri Strizhov, V.Medvedev, F.Ulyanov, A.Kiselev, A.Kiselev, IBRAE
|
Assessment of Stress/Strain State of VVER-1000 Concrete Containment |
slides |
|
E. Uspuras (G. Dundulis), R. Kulak, A. Marchertas, LEI
|
Pipe Whip Transient Analysis of the Ignalina NPP |
abstract
document |
|
Sergey Boutorin, VNIPIET; A.G.Krayev, RMINSK; S.G.Shulman, SPBGTU
|
General Approach to Structural Analysis of NPPs |
slides
document |
|
E. Uspuras, A. Kaliatka, LEI
|
RBMK-1500 Acc. Management for Loss of Long-Term Cooling |
abstract
document |
|
Valeri Strizhov, V. Nosatov, IBRAE
|
Analyses of VVERs Using the MELCOR Code |
document |
|
N.V. Boukine, L.N.Borisov, A.L.Gromov, N.S.Fil, A.M.Shumsky, Gidropress
|
Effect of Passive Safety Systems on Beyond Design Basis Accidents for V-392 Plants |
abstract
slides
document |
|
L. Sabotinov, S.Cadet-Mercier, A.Amri, IPSN
|
Analysis of Total Loss of Steam Generator Feed Water in VVER NPPs |
abstract |
|
V. Peresadko, V.Berkovitch, G.Taranov, M.Maltsev, AEP; A.Podshibyakin, S.Zaytsev, A.Shumsky, Gidropress
|
VVER-1000 Core and Conainment Behaviour for LB-LOCA with Blackout |
abstract
document |
|
T.E. Kouznetsova, V.E. Nechetny, N.S. Fil, Gidropress
|
Acc. Anal. to Evaluate the Need and Effectiveness of VVER-440 Prot. System Mods |
document |
|
Yu. Kavun, AEP; A. Popykion, V.Ignatenko, SEC-NRS
|
RIA Calculation for VVER-440 with Radyga Code |
abstract
document |
|
F. D'Auria, G. Galassi, A. Spadoni, D. Mazzini, University of Pisa |
VVER-1000 and VVER-440 system transient analyses at University of Pisa |
slides |
|
Can Canavan, Data Systems & Solutions
|
PSA peer review |
abstract |
|
G.Gromov, I.Lola, S.Sholomitsky, D.Gumenyuk, V.Kouzan, Energorisk Ltd.
|
Evaluation of Maximum Press. and Temp. in VVER-440/213 for Sec. Pipe Breaks |
document |
|
J.Augutis, LEI
|
Assessment of Gas Gap evaluation for the Ignalina NPP RBMK-1500 |
slides
document |
