Fourth
International Information Exchange Forum
"SAFETY ANALYSIS FOR NPPs OF
VVER AND RBMK TYPE"
Sponsored by: U.S. Department of Energy
In cooperation with: Institute of Physics and Power Engineering,
International Atomic Energy Agency,
Pacific Northwest National Laboratory, Argonne National Laboratory,
Swedish International Project on Nuclear Safety, OECD Nuclear Energy
Agency, Riskaudit
11-15 October 1999
Obninsk, Russian Federation
Table of Contents
Foreword
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Agenda
Attendees
Papers Presented in Plenary Sessions I
Papers 1-10, 11-20, 21-30, 31-40, 41-51
Papers Presented in Plenary Sessions II
Papers 52-62
Papers Presented in Plenary Sessions III
Papers 63-71
Volume I.
I. Papers Presented in Plenary Sessions
Listing of Papers
(Names in italics indicate presenters)
Paper 1 - page 1 in Volume I
About a Russian Strategy for Investigations in Support of Safety of Native Reactors,
by Boris G. Gordon (SEC)
Paper 2 - page 7 in Volume I
Tasks and Perspectives of the Scientific and Engineering Center of RF Gosatomnadzor,
by B. Gordon (SEC)Paper 3 - page 23 in Volume I
Regulatory Aspects of NPP Safety in Ukraine,
by A. Smyshlayev (SNRA), presented by S.V. Bobryakov (SNRA)Paper 4 - page 39 in Volume I
Overview of the DOE-INSP Safety Analysis Program
Walter F. Pasedag (DOE) and Jeffrey L. Binder (ANL)Paper 5 - page 53 in Volume I
IAEA Safety Report on Accident Analysis of Nuclear Power Plants
by Jozef Misak (IAEA)Paper 6 - page 65 in Volume I
The OECD/NEA Strategic Plan - A Contribution to Nuclear Safety World-Wide,
by Miroslav Hrehor (NEA)Paper 7 - page 87 in Volume I
RINSC Activity in Creating Data Bases and Preserving of Foreign Code Configurations,
by S.E. Bugaenko, I.N. Denisov and L.P. Kabanov (RINSC)Paper 8 - page 101 in Volume I
Status of the Work on Certification of Computer Codes used for Justification of the
Safety of Russian NPPs, by O.M. Kovalevich, I.R. Ougouleva, A.I. Popikin (SEC) and S.
Zaritski (KI)Paper 9 - page 113 in Volume I
Experience Gained in the Review of Safety Analyses in SARs of NPPs
by V. Antropov, N. Koslova, N. Rizhova (SEC)Paper 10 - page 117 in Volume I
Analysis of a DU200 Pipe Rupture Regime of the Armenian NPP,
by Sos Sargsyan (ANPP) and Tatyana Petrosyan (ANRA)Paper 11 - page 149 in Volume I
RELAP5/Mod3.2 Assessment Using an ISB 11% Upper Plenum Break Experiment,
by Paul D. Bayless (INEEL)
Paper 12 - page 165 in Volume I
Post-Test Analysis of ISB-VVER Test Facility Upper Plenum 11% Leak with ECCS
Operation using the Codes RELAP and ATHLET,
by E.Yu. Shchepetilnikov (EREC) and S.S. Pylev (KI)Paper 13 - page 175 in Volume I
Post-Test Analysis of 11% Upper Plenum Break LOCA Test at the Integral Test Facility
ISB-VVER using RELAP5/Mod3.2, by I.V. Gashenko, M.P. Gashenko, O.I. Melikhov and
V.N. Blinkov (EREC)Paper 14 - page 195 in Volume I
Experimental Results Obtained at the Integral Facility PSB-VVER,
by I.A. Lipatov, G.I. Dremin, S.A. Galchanskaya, S.V. Zevalkin (EREC) and I.V. Elkin (KI)Paper 15 - page 211 in Volume I
Assessment Study of ATHLET and RELAP5/Mod3.2 Based on the Kalinin NPP Unit-1
Stop of Feedwater Supply to Steam Generator No. 4,
by A.M. Moskalev, S. Pylev, V. Roginskaya, O. Korotina and I. Elkin (KI)Paper 16 - page 231 in Volume I
Assessment of Applicability of Foreign Best-Estimate Thermal Hydraulic Codes for VVER
Safety Analysis, by V.I. Dorofeev, and M.A. Podshibyakin (REAP)Paper 17 - page 247 in Volume I
Analysis of Rovno Unit #3 Loss of External Power with BRU-A Stuck Open Using
RELAP5, by D.V. Shevelev, A.A. Potravka and E.A. Aleksandrov (Kiev-EP)Paper 18 - page 263 in Volume I
Steam Generator Collector Rupture,
by Pavlin Groudev, Malinka Pavlova (INRE-BAS) and Vasil Hadjiev (Kozloduy NPP)Paper 19 - page 279 in Volume I
Uranium-Erbium Fuel Implementation Experience in RBMK-1500 Reactors at Ignalina NPP;
Safety Substantiation on the Basis of STEPAN Code,
by Boris Voroncov, Ignalina NPPPaper 20 - page 291 in Volume I
Licensing of Unit #1 of Ignalina NPP, Aleksandr Alejev, VATESIPaper 21 - page 383 in Volume I
Use of the TURBO-FLOW Code for Estimating of the Serviceability of VVER Reactor
Safety Systems, by S.I. Sherbakov (IPPE)
Paper 22 - page 393 in Volume IBack to top of the page
Analysis of Plant Black-Out for VVER-440/213 NPPs,
by Peter Matejovic, L. Vranka and M. Bachraty (IVS-Trnava)Paper 23 - page 407 in Volume I
LOCA Analyses for Bohunice V-1 NPP VVER-440/230 after Gradual Upgrading,
by Tomas Kliment, VUJEPaper 24 - page 421 in Volume I
Some Calculation Results and Thermal Hydraulic Special Features of Small-Break LOCA
Process for the Standard Problem SP-1, by Valeriy Zenov (INEI-Sevastopol)Paper 25 - page 435 in Volume I
The TIGR-1 Code for Analysis of Transients in VVERs,
by M.P. Lizorkin, S.A. Kryukov, G.L. Lunin, V.A. Bolnov, A.V. Bodnikov,
V.G. Demurov, V.I. Pechenkin and O.B. Samoylov (OKB-M)Paper 26 - page 459 in Volume I
Annular Critical Heat Flux Determination for Russian ADE Reactors,
by Georgi V. Tsiklauri, Richard T. Pagh and Vladimir Korolev (PNNL),
presented by Bruce E. Schmitt (PNNL)Paper 27 - page 481 in Volume II
Thermal Hydraulic Analysis of Accidents Leading to Local Flow Stagnation in
RBMK-1500, by Eugenijus Uspuras and Algirdas Kaliatka (LEI)Paper 28 - page 491 in Volume II
RELAP Analysis of Thermal Hydraulic Stability in RBMK Parallel Channels,
by N.A. Brus and O.E. Youssoupov (EREC)Paper 29 - page 509 in Volume II
Non-Linear Analysis of the Structural Integrity of the Accident Location System in the
Ignalina NPP, by G. Dundulis, E. Narvydas and E. Uspuras (LEI)Paper 30 - page 517 in Volume II
Prevention of Inadvertent Primary Circuit Dilution; Mixing Calculations and Boron
Dilution Scenarios, by Eva Toth (Paks NPP)Paper 31 - page 529 in Volume II
MCP Trips Safety Analysis for VVER-440 Dukovany NPP,
by Jiri Sommer (NRI-Rez)Paper 32 - page 555 in Volume II
Condensation Water-Hammer Events in Tubular Bends with Horizontal and Vertical
Sections in Piping Systems of VVER NPPs,
by Aleksandr D. Efanov and Yu.F. Selivanov ( IPPE)Paper 33 - page 569 in Volume II
Approaches and Some Results from the Fire PSA Study for Novovoronesh NPP Unit-5,
by Irina Kouzmina, Artour Lioubarski (SEC), Mardy Kazarians (K&A)\ and
Victor Smoutnev (N-NPP)Paper 34 - page 583 in Volume II
Deterministic Support for PSA of NPPs, by Gennadi Samokhin, Sergey Volkovitski,
Artour Lioubarski (SEC) and Yuri. Shvyriaev (Moscow AEP)Paper 35 - page 619 in Volume II
Failure Data Collection at Leningrad NPP, by E.V. Degtev (L-NPP)Paper 36 - page 641 in Volume II
New Emergency Procedures of Westinghouse Type from Point of View of Human Factors
and Human Reliability, by Jaroslav Holy (NRI-Rez)Paper 37 - page 657 in Volume II
Human Reliability Analysis and Human Factors Evaluation in Support of Safety
Assessment and Improvement at the Paks NPP,
by A. Bareith, E. Hollo, Z. Karsa (VEIKI) and A.J. Spurgin (Consultant)Paper 38 - page 669 in Volume II
Results and Current Status of PSA Level 1 for Unit 4 of Kola NPP
by S.M. Kuzin, M.Y. Lankin, I.V.Marakulin, V.K. Shevelev, V.I. Shutov (Kola NPP)Paper 39 - page 681 in Volume II
The Novisa Project for Upgrading of Novovoronesh NPP Units 3 & 4,
by V. Pankov and N. Sysoev (Novovoronesh NPP)Paper 40 - page 685 in Volume II
SwisRus Project Level-2 PSA Study for Novovoronesh NPP Unit 5,
by D. Noskov, A. Lioubarski, G. Samokhin (SEC),
E. Gazzoli, H. Esmaili and M. Khatib-Rahbar (Energy Research)Paper 41 - page 689 in Volume II
PSA Application for Estimation and Ranking of NPP Safety Problems,
by S. Krasnukha and A. Prokhodtsev (SU-NPP)Paper 42 - page 695 in Volume II
Comparison of some Results and Modeling Issues of PSAs of VVER-1000,
by Artour Lioubarski and Irina Kouzmina (SEC)Paper 43 - page 715 in Volume II
Use of Level 1 PSA for Evaluation of Proposed Safety Upgrades for RBMK-1000 NPPs
with Leningrad NPP as a Case Study, by N.A. Stebenev (Leningrad NPP)Paper 44 - page 737 in Volume II
Issues Related to the SAR for the South-Ukraine NPP Unit 1and Zaparozhe-NPP Unit 5,
by V.Z. Baidullin and V.V. Kvasilchuk ( Ka-EP)Paper 45 - page 747 in Volume II
Independent Peer Review and QA of NPP PSA Projects, by A. Polyzhuk, IBRAEPaper 46 - page 755 in Volume II
Status and Perspectives of NPP Operational Safety Monitoring in Russia and Abroad,
by B.I. Vinnikov, KIPaper 47 - page 763 in Volume II
Neutron Kinetics Model Development for VVER-1000,
by I. Kadenko (Kyiv National Taras Shevchenko University),
V. Borissenko, A. Shkarupa, N. Trofimova and V. Galchenko (OSI)Paper 48 - page 769 in Volume II
Comparison of Experimental and Calculational Results for the Neutronic Characteristics of
Ignalina NPP, by A. Balygin (KI) and R.B. Sehgal (KTH)Paper 49 - page 771 in Volume II
Code Package DYN3D/RELAP5 Based on 3D Neutron Kinetics Capability for Transient
Analysis of Water Cooled Reactors, by L. Elovskaya, Ya. Kozmenkov,
Yu. Orekhov (IPPE), U. Grundmann, U.Rohde and A. Seidel (FZR-Germany)Paper 50 - page 783 in Volume II
Safety Upgrades in Ukrainian NPPs,
by V. Vorontsov, EnergoAtomPaper 51 - page 805 in Volume II
VVER-440/1000 Mathematical Model and Algorithm for Automatic Control,
E.A. Lisenkov, A.A. Trybelev, M.A. Bykov, Yu.N. Olshevskiy, N.N. Boyko,
T.M. Afanasyeva (OKB-GP)
Volume III.
II. Papers Presented in Sessions of the International RELAP Users Group (IRUG)
Paper 52 - page 819 in Volume IIIBack to top of the page
LOCA Scaling Effects for ISB-VVER, PSB-VVER Test Facilities and VVER-1000,
by E.Yu. Shtchepetilnikov, O.I. Melikhov and V.I. Melikhov (EREC)Paper 53 - page 827 in Volume III
Verification of the Thermo-Hydraulic RELAP5/Mod3.2 Code with Reference to NPP ADE
Separate Physical Phenomena, by A.S. Devkin, A.A. Apresov, I.V. Elkin,
A.K. Kalugin, A.M. Moskalev, V.B. Proklov, S.S. Pylev, V.M. Fedulenko and
M.Yu. Shemanov (KI)Paper 54 - page 837 in Volume III
Classification of the Thermo-Hydraulic Processes and Phenomena in Commercial
Uranium-Graphite Reactors; Development of Verification Matrixes for the
RELAP5/Mod3.2 Code, by I.V. Elkin (KI)Paper 55 - page 843 in Volume III
Assessment Study of the ATHLET Code Based on the PNC Experimental Data Obtained
at HTL and SEL Facilities, by A.M. Moslalev (KI), A. Petry and W. Richter (GRS, Germany)Paper 56 - page 853 in Volume III
Deterministic Model for Uncertainty Estimates for VVER-440 RELAP Calculations,
by Rustam Islamov (IBRAE)Paper 57 - page 863 in Volume III
RELAP-3D Development Status, by Paul D. Bayless (INEEL)Paper 58 - page 875 in Volume III
RELAP-3D Code Validation for RBMK Phenomena, by James E. Fisher (INEEL);
presented by Paul D. Bayless (INEEL)Paper 59 - page 901 in Volume III
RELAP/MOD3.2 Analysis of INSC Standard Problem R5: Thermal Hydraulic Stability in
Parallel Boiling Channels, by Patrick L. Garner(ANL); presented by Jordi Roglans (ANL)Paper 60 - page 921 in Volume III
Characteristics of the Model of the RU-V320 Control System for Use in RELAP5/3.2 in
Connection with the PSA Project of Zaporozhe NPP Unit-5,
by V.V. Sverdlov and A.V. Sverdlov, EISPaper 61 - page 943 in Volume III
Application of the RELAP5/Mod3.2 Code to Large LOCA Experiments on SB-1 EDO
Gidropress, by Victoria Roginskaya (KI)Paper 62 - page 957 in Volume III
Uncertainty Evaluations of the RELAP5/Mod3.2 Application to the NPP ADE-5 Transient
Analysis, by S.S. Pylev and I.V. Elkin (KI)
III. Papers Presented in Poster Sessions
Paper 63 - page 999 in Volume IIIBack to top of the page
Development., Validation and Application of RBMK Reactor Physics Capability at KTH,
by Antanas Romas (KTH)Paper 64 - page 1013 in Volume III
Analytical Model for Estimating the Friction and Heat Transfer in Two-Phase Flow with
Saddle-Shape Void Fraction Profile, by Yu. Kornienko (IPPE)Paper 65 - page 1023 in Volume III
Modernization of Numerical Scheme and Calculational Algorithm for Accidental Regimes
in the Code TRAP-97,
by V.K. Artemyev, Yu.N. Kornienko (IPPE) and S.I. Zaitsev (OKB-GP)Paper 66 - page 1033 in Volume III
Advanced Methodology for Modeling Neutron-Physical Fields with the RADUGA-EU
Code, by O.Yu. Kavun, G.S. Taranov and V.V. Ignatenko (AEP)Paper 67 - page 1041 in Volume III
Concept for Developing Open Code Systems of Medium Class for Mathematical
Modeling of Nuclear Reactors, M.N. Zizin (KI)Paper 68 - page 1057 in Volume III
Characteristics of Testing Facilities for Dynamic Codes,
by O.Yu. Kavun, L.I Podlazov (AEP) and A.I. Popykin (SEC)Paper 69 - page 1065 in Volume III
Design Analysis Technique of Thermo Hydraulic Processes in Bilibino NPP with Lumped
Parameter Model,
by V.V. Petrov, V.I. Kashirin, A.V. Kalmykov (Izhorskie Zavody)Paper 70 - page 1077 in Volume III
Component Reliability Data Base for Use in the PSA Study of Zaporozhe NPP Unit #5,
by A.N. Makartchyev and A.N. Tsaryev (Zaporozhe NPP)Paper 71 - page 1085 in Volume III
Modeling of Analog Controllers in VVE R-1000 NPP for Use in RELAP/Mod5-3.2,
by A.A. Bolibok (Zaporozhe NPP)