I. Papers Presented in
Plenary Sessions
|
A.
|
Papers of the IAEA Technical
Committee Meeting (TCM) on Status of Safety Reports of WWER and RBMK Nuclear
Power Plants
|
| Paper # |
Paper Titles and Authors |
|
T.1 |
Status of Regulatory Requirements
and Safety Justification Reports in Russia,
by M. Kouznetsov (SEC-GAN) |
|
T.2 |
Safety Assessment of SAR
in Ukraine ,
by A. Lukashyn, V.V. Ynyushev (UNRA) |
|
T.3 |
Status of Safety Reports
of Paks NPP,
by J. Zsoldos (HAEA) |
|
T.4 |
The Safety Analysis Report
ofIgnaliana NPP,
by A. Mereznikov, (INPP) |
|
T.5 |
Development of Ignalina's
Safety Analyses Reports,
by Eugenijus Uspuras (LEI) |
|
T.6 |
Development of the Safety
Substantiation Report of Kozloduy NPP Units # 1-4,
by Borislav Stanimirov (BNSA) |
|
T.7 |
Status of Safety Analysis
Reports in the Slovak Republic,
by J. Husarcek (UJD) |
|
T.8 |
Safety Analysis Reports:
Current Status in the Czech Republic,
by S. Svab (CNRA)Note: This paper was not available during Forum-2000 |
| T.9 |
Status of the Safety Analysis Reports of the Armenian NPP,
by A. Aleksanyan, V. Petrosyan, K. Poghosyan (ANPP)Note: This paper
was not available during Forum-2000 |
| |
B.
|
Other Invited and Contributed
Papers Presented in the Plenary Sessions
|
| Paper # |
Paper Titles and Authors |
|
P.1 |
Recent Developments in the
INSP Safety Analysis Program,
by Walter Pasedag (DOE) and Mark Petri (ANL) |
| P.2 |
Overview of US INSC Programs and Objectives,
by Jeffrey L. Binder (ANL) |
|
P.3 |
Overview of Russian INSC
Programs and Objectives,
by S. Bugaenko (RINSC) |
|
P.4 |
Support of the European Commission
funded PHARE and TACIS Nuclear Safety Programmes by the Joint Research Centre
(JRC),
by Hartmut U. Wider, G. Cojazzi, C. Kirchsteiger, A.V. Jones (JRC-Ispra)
and F. Sevini, M. Bieth, L. Fabbri, J.L. Monjaret (JRC-Petten) |
|
P.5 |
Requirements to the Composition
and Contents of the Software Verification Report Presented for Certification
by the Regulatory Authority of Russia,
by Inna Ougaleva and A.I. Popikin, V.S.Rubtsov (SEC-GAN) |
|
P.6 |
Severe Accident Management
for NPPs of VVER Type,
by Nikolai Ponomarev-Stepnoi, V. Asmolov and V. Sidorenko (KI) |
|
P.7 |
IAEA Project on Accident
Analysis and the Associated Training for Kursk NPP,
by M. Jankowski, Jozef Misak (IAEA) |
|
P.8 |
Experience with the Review
ofSafety Analysis Reports in Slovakia,
by Marian Kristof (UJD) |
|
P.9 |
Licensing of PRZ SV Replacement:
Independent Calculations Performed by the Regulatory Authority,
by A. Amirjanyan, Tatyana Petrosyan (ANRA) |
|
P.10 |
Experience in Safety Analysis
Document Development for ZNPP,
by I.V. Karelov (EIS) |
|
P.11 |
Peer review and QA of SafetyAnalysis
for LNPP #2, by Vladimir Vasekin (GAN), Bronislav Vinikov, Aleksandr
Kramerov (KI), Oleg Kovalevich, Evgenii K. Shubeiko (SEC-GAN) |
|
P.12 |
Current Status of the Development
of Safety Analysis Reports for Operating VVER-Type NPPs in Ukraine,
by V.V. Vorontsov, S. Kolesov, L. Nikolaeva (Energoatom) |
|
P.13 |
Some Results of Safety Analyses
for NPP Dukovany with WWER-440/213,
by J. Krhounkova (NRI-Rez) |
|
P.14 |
Summary of PSA Applications
at the Monticello NPP,
by Craig Nierode (Monticello NPP) |
|
P.15 |
Overview and Results of
FirePSA Study for Novovoronesh NPP #5,
by Irina Kouzmina (SEC-GAN), Mardy Kazarians (K&A), Victor Smoutnev
(NV-NPP |
|
P.16 |
Preliminary Results of Novovoronesh
NPP #6 External Events PSA at Power Operation,
by Artour Lioubarski, Dmitry Noskov, Boris Gordon (SEC-GAN) |
|
P.17 |
SWISRUS Project NovovoroneshNPP
#5 Level 2/3 PSA,
by Dmitry Noskov, A. Lubarsky, B. Gordon (SEC-GAN), I. Sokolova (GAN),E.
Cazzoli, H. Esmaili, M. Khatib-Rahbar (Energy Research) |
|
P.18 |
NOVISA Project on PSA of
NVNPP #3,
by V. Zarudaev, A. Rozin, A. Bodrov, Yu. Shviriaev, G. Tokmachev,E.
Baykova, V. Morozov (NV-NPP) |
|
P.19 |
Safety Analyses Supporting
Symptom Oriented EOPs at Paks NPP,
by Eva Toth (Paks NPP) |
|
P.20 |
Justfication of Symptom-Based
EOPs for Balakova NPP,
by V. Sevastyanov (BNPP) |
|
P.21 |
Specific TH Analyses for
Integrity Eval'n of VVER-440/V213,
by Branislav Hatala, Julius Filo, Tomas Kliment (VUJE) |
|
P.22 |
Application of RELAP5/Mod3.2.2
Gamma to an ATWS Test at PMK-2,
by L. Perneczky, Ivan Toth (KFKI) |
|
P.23 |
The In-Depth Safety Analysisof
Leningrad NPP,
by Yuriy Skok (L-NPP) |
|
P.24 |
Verification of Thermohydraulic
Codes on a Standard Problem of Reflooding,
by V.V. Sergeev (IPPE) |
|
P.25 |
Risk Management of Refuelling
Outages at Monticello NPP,
by Craig Nierode (MNPP) |
|
P.26 |
Risk Management of On-Line
Maintenance at Monticello NPP,
by Craig Nierode (MNPP) |
|
P.27 |
Application of PRA Technologies
- Risk Advisory Systems,
by T. Blackburn (PNNL) |
|
P.28 |
Level 1 PSA Internal Events
for Z-NPPP#5,
by Oleg Kocharyant (Z-NPP) |
|
P.29 |
Generic Common Cause FailureModel
,
by A. Volkov (IBREA)
Note: This paper was presented; no printed/electronic version was available |
|
P.30 |
Design Basis Accident Analyses
for South Ukraine NPP #1 and Rivne NPP #1,
by G. Gromov (Energorisk) |
|
P.31 |
Probabilistic Safety Assessment
Level 1 of South Ukraine NPP #1 and Rivne NPP #1,
by G. Gromov (Energorisk) |
|
P.32 |
Investigation of the Condensing
Pool Behavior in the Accident Localization System of Ignalina NPP,
by S. Rimkevicius (INPP) |
|
P.33 |
Codes and Main Results of
Safety Analysis of Kalinin NPP,
by A.A. Falkov, V.S. Kul, V.I. Pechenkin, O.B. Samoylov (OKBM), M.P.
Lyzorkin, G.L. Lunin, Yu. G. Nikiporets, V.B. Proklov (KI) |
|
P.34 |
Preliminary Verification
Results of Computer Analyzer for Investigation of Normal Operation, Transient
and Accident Conditions of the 1000 MW Reactor at at Kalinin NPP, based
on the Code "Hard-Nut",
by S.V. Vigovsky, A.A. Semenov, E.V. Tchernov, D.M. Baturin (MSEPI),
L.N. Bogachek, V.M. Chapaev (Ka-NPP) |
|
P.35 |
Loss of Non-Emergency AC
Power at SU-NPP,
by S. Krasnukha, S. Zhalilo, A. Prokhodtsev (SU-NPP) |
|
P.36 |
Peer Review Approach of
SUSAPSA Level 1,
by Lenar Sagidullin, D. Goma (ET&D) |
|
P.37 |
Reliability Data Bases,
by T. Blackburn (PNNL) |
|
P.38 |
PSA Model Features for Zaporozhe
NPP #5,
by I.V. Sergeev (ZNPP) |
|
P.39 |
Thermal Hydraulic Justification
of System Success Criteria for Z-NPP #5 PSA,
by A.A. Bolibok, V.V. Sverdlov, A.B. Sverdlov (EIS / Z-NPP) |
| P.40 |
Level 1 and 2 PSA Activitiesin
the Slovak Republic,
by Pavol Hlavac (RELKO) |
|
P.41 |
Results of PSA Level 1 for
Rostov NPP #1,
by A. Yaskin (AEP-NN) |
|
P.42 |
Optimum Management of NPP
Safety and Methodology of an Event Tree,
by V.I. Pampuro, V.I. Borisenko (OSI) |
|
P.43 |
Special Software "SS-PSA"
for Integrated Reliability and Safety Analysis of NPPs with RBMK Type Reactors
,
by B.I. Vinikov (KI) |
|
P.44 |
Some Remarks about In-Depth
Safety Assessment at South Ukraine NPP,
by S. Krasnukha, SUNPP (Note: This paper was not available in written
form) |
|
P.45 |
Limitations of the TH Allocated
Point Kinetics Model Implementation for the Analysis of Reactivity Accidents
,
by S. Krasnukha (SU-NPP) |
|
P.46 |
Development of Neutron Physics
Models for VVERs with NESTLE Code,
by A. Shkarupa, N. Trofimova, V. Galchenko, I. Kadenko, V. Borissenko
(Kyiv Univ.) |
II. Papers Presented in
Sessions of the International RELAP Users Group (IRUG), 19, 20 October
2000
|
| Paper # |
Paper Titles and
Authors |
| R.1 |
Preliminary Analysis of INSC
Standard Problem V4: Heat Transfer under Partly Uncovered Core Conditions,
Test Performed at KS-1 Facility at RRC-KI,
by J.W. Ahrens, A.M. Tentner (ANL), presented by Jordi Roglans (ANL)
|
|
R.2 |
Computational Modeling Using
RELAP5/MOD3.2 of Accident Conditions Simulated in an Experimental Facility,
by V.I. Schekoldin, Yu.A. Bezrukov, Yu. A. Mygrov, V.K. Efimov, A.N.
Gudoshnykov(OKB-GP) |
|
R.3 |
RELAP5 Analysis of Standard
Problem R2 on Kurchatov's KS Facillity,
by Victor A. Vinogradov, A.Yu. Balykin (KI) |
|
R.4 |
Analysis with RELAP5 ComputerCode
of Experiments for Investigation of Void Fraction Distribution in RBMKFuel
Channel Model,
by N.A. Brus, O.E. Ioussoupov (EREC) |
|
R.5 |
Analysis of ISP-33 Using
RELAP-3D ,
by Peter Matejovic, (IVS) |
|
R.6 |
Total Loss of Feed Water
for VVER 1000,
by Pavlin Groudev, Malinka Pavlova (INRE) |
|
R.7 |
Loss of Off-Site Power Transient
in VVER-1000 Reactors,
by Assia Ivanova (Enpro Consult) |
|
R.8 |
Analysis of Passive FeedwaterInjection
in the Case of VVER-440/V213 Plant Black-Out,
, by Peter Matejovic, L. Vranka, M. Bachrary (IVS) |
|
R.9 |
Preliminary Analyses of the
LOCA 200 mm for NPP Kozloduy Units 1-4,
by K. Avdjiev, M. Marinov, E. Popov, A. Krastev(EnergoProekt) |
|
R.10 |
Comparison of RELAP and
KOBRA TH Module for a Single RBMK Channel,
by Alexandr Krayushkin (KI) |
|
R.11 |
Overview of Recent RELAP
Development ,
by Paul D. Bayless (INEEL) |
|
R.12 |
RELAP5/MOD3.2 Analysis of
Natural Circulation Test at Kozloduy NPP #6,
by Malinka Pavlova, P. Groudev (INRE), V. Hadjiev (Ko-NPP), J. Roglans
(ANL) |
|
R.13 |
Modeling of Primary-to-Secondary
Leaks in VVER-440 NPPs Using RELAP5/MOD3.2,
by V. Borissenko, I. Kadenko, A. Krushinskiy, V. Mukoid (OSI) |
|
R.14 |
Additional RELAP5 Analysis
of Thermal-Hydraulic Stability in Parallel Channels of RBMK Primary CircuitModel
,
by N.A. Brus, O.E. Iousoupov (EREC) |
|
R.15 |
Development of Ignalina
NPP RBMK-1500 Reactor RELAP5-3D Model,
by E. Bubelis , A. Kaliatka, E. Uspuras (LEI) |
|
R.16 |
RELAP-3D Model for the Kursk#1
NPP,
by James E. Fisher (INEEL) |
|
R.17 |
KORSAR: A New-Generation
Computer Code for Numerically Modeling Dynamic Behavior of NPPs,
by Yu.A. Migrov, Yu.V. Yudov (NITI) |
III. Papers Presented
in Parallel PSA Sessions, 18, 19 October2000
|
| Paper # |
Paper Titles and
Authors |
|
N.1 |
PSA in Operations Training
atMonticello NPP,
Craig Nierode, M-NPP |
|
N.2 |
PSA Applications at Monticello
,
Craig Nierode, M-NPP |
IV. Papers Presented in
Poster Sessions, 18, 19 and 20 October2000
|
| Paper # |
Paper Titlesand Authors |
|
S.1 |
Universal Model of RBMK Reactor
Dynamics Originated Both for SafetyAnalysis and for Full Scope Simulators
by Andrey Zenkov, D. Yanushevich,S. Malkin, M. Babaytsev, A. Glembotsky,
A. Krayushkin, I. Rakitin (KI) |
|
S.2 |
On Usage of Coupled Neutron-Kinetic
and Thermal-Hydraulic Computer Code DYN3D+ATHLET to Study Safety of VVER-1000
Type Reactors under Transient and Emergency Operational Modes,
by U. Rohde, S. Kliem, A. Seidel, V. Khalymonchuk, A. Kuchin (SSTC) |
|
S.3 |
Numerical Solution of Conservation
Equations in the Transient Model for the System Thermalhydraulics in theKORSAR
Computer Code,
by Yu. Yudov (NITI) |
|
S.4 |
Verification and Validation
of Core Analysis Code System "SAPFIR-VVR95&RC",
by Aleksandr Elchine, A.S. Ivanov, A.V. Piskaryov, A. Karpov, V.G.
Artemov, V.V. Obuhov, Yu. P. Shemaev (NITI) |
|
S.5 |
Development of Implicit Stabilization
Method for Numerical Prediction of Accident NPP Regimes in the TRAP-97
,
by V.K. Artemyev, Yu.N. Kornienko, S.I. Zaitsev (IPPE) |
|
S.6 |
Development of the Containment
Code KUPOL-M,
by A.A. Loukianov, N.N. Shangin, A.A. Zaitsev, Yu.S. Yuriev (IPPE) |
|
S.7 |
Development of the 1D Drift
Model of Non-Equilibrium Two-Phase Flow in Simple and Sub-Channel Geometry
forAccident Analysis of NPP Regimes,
by Yu. Kornienko (IPPE) |
|
S.8 |
Software Tool for Plant Operation
Safety Performance Monitoring and Enhancement,
by S.D. Malkin, V.P. Syvokon, V.V. Pozniakov, M.E. Gladishev (KI) |
|
S.9 |
KENTAVR for Monitoring RBMK
Neutronic Parameters,
by A.N. Kuzmin, V.M. Kachanov, V.E. Jitarev(KI), G.N. Alexakov, V.P.
Alferov, A.V. Kudryavtsev, V.A. Federov (MEPhI), G.P. Kirichenko (Teploenergotehnika) |
|
S.10 |
Development of Methodological
Document "Atlas of Accident Analyses",
by Victor N. Antropov (SEC-GAN) |
|
S.11 |
Neutron Cross Section Data
Base ATLAS of the Slavutych International Chornobyl Center,
by Dmitry Bobro (SICC) |
|
S.12 |
The Approach to Study and
Matrix of BDBA RBMK Accidents (without corium),
by A.Ya. Kramerov, D. Mikhailov (KI) |
|
S.13 |
Simulation of the Hydrogen
Distribution and Removal in the Containment of VVER-1000 NPPs,
by N.N. Shangin, A.A. Loukianov, A.A. Zaitsev, Yu.G. Davydov (IPPE) |
|
S.14 |
Experimental Substantiation
of Design Functions of HT-2 System for New Russian NPP Project,
by V.M. Berkovich, A.D. Efanov, S.G. Kaliakin, A.B. Malyshev, O.V. Remizov,
G.S. Taranov, , (IPPE and AEP-Moscow) |
|
S.15 |
Investigation of the Mechanics
and Thermo-Hydraulics Coupled Processes for the RBMK Graphite Stack,
by L.M. Parafilo, D.V. Kruchkov (IPPE), B.A. Gabaraev, S.L. Soloview, O.Yu.
Novoselsky, V.N. Filinov (NT) |
|
S.16 |
Critical Heat Flux, Local
Hydraulic Characteristics and Verification of VVER Fuel Assembly Computer
Codes ,
by A.D. Efanov, A.P. Kolmakov, V.V. Lozhkin, A.M. Smirnov (IPPE),V.I.
Abramov, E.I. Levin (Gidropress) |
|
S.17 |
Calculation of Deformation
and Integrity of RBMK Pressure Tubes at DHG Partial Break Using KAPRAN1
Code ,
by O. Yu. Novoselsky, Vladimir N. Filinov (NT) |
|
S.18 |
Nuclear Fuel Qualification
Program in Ukraine,
by Vladimir Kvasilchuk (Kharkiv CRCD) |
|
S.19 |
Safety Analysis Strategic
Program for Cernavoda NPP Unit 1",
by Relu Istrate (Cernavoda NPP) |
|
S.20 |
Assessment Study of ATHLET12A
Based on the KS Facility in Kurchatov Institute Stop Fill Problem for RBMK
,
by A.Moskalev (KI) |
|
S.21 |
Structural Approach to Safety
Analysis of NPP on Base of Coolant Oscillations Modeling and Forecastingof
the NPP Fundamental Equipment Reliability,
by K.N. Proskouriakov, Yu. B. Vorobyov, V.D. Kuznetsov, M.Gholampour,
M.M. Kaverznev (Moscow Power Engineering Institute) |
|
S.22 |
Criterion of Steam Generating
Ducts Parametrical Similarity,
by K.N. Proskouriakov |
|
S.23 |
RBMK-1500 Reactor Void Reactivity
Factor Measurements at Low Power Level,
by B. Voroncov, G. Krivoshein, A. Kulko, A. Maekelov IgnalinaNPP |
|
S.24 |
Calculation of Equipment
Reliability Parameters, Common Cause Failure Probability and Event Frequencies
for the PSA of Zaporozhe ISA,
by I.A. Semenyuk (Novator-Kiev) |
|
S.25 |
Project for Qualification
ofNuclear Fuel in Ukraine,
by V.V. Kvasilchuk, V.R. Tararinov (CRCD-Kharkiv) |
