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Sponsored by: US-Department of Energy
In cooperation with: : IAEA, IPPE, PNNL, ANL, SIP, NEA, Riskaudit
| Paper # | Paper Titles and Authors | Day |
|---|---|---|
|
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) |
18 October
|
|
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 B. Khalymonchik (SSTC) |
|
|
S.3
|
Numerical Solution of Conservation Equations in the Transient
Modelfor the System Thermalhydraulics in the KORSAR Computer Code, |
|
|
S.4
|
Verification and Validation of Core Analysis Code System
"SAPFIR-VVR95&RC", |
|
|
S.5
|
Development of Implicit
Stabilization Method for Numerical Prediction of Accident NPP Regimes in
the TRAP-97, V.K. Artemyev, Yu.N. Kornienko, S.I. Zaitsev (IPPE) |
|
|
S.6
|
Development of the Containment Code KUPOL-M, |
|
|
S.7
|
Development of the 1D Drift Model of Non-Equilibrium
Two-Phase Flow in Simple and Sub-Channel Geometry for Accident Analysis
of NPP |
19 October
|
|
S.8
|
Software Tool for Plant Operation Safety Performance
Monitoring and Enhancement, |
|
|
S.9
|
KENTAVR for Monitoring RBMK Neutronic Parameters, |
|
|
S.10
|
Development of Methodological Document "Atlas of Accident
Analyses", |
|
|
S.11
|
Neutron Cross Section Data Base ATLAS of the Slavutych
International Chornobyl Center, |
|
|
S.12
|
The Approach to Study and Matrix of BDBA RBMK Accidents
(without corium), |
|
|
S.13
|
Simulation of the Hydrogen Distribution and Removal in
the Containment of VVER-1000 NPPs, |
|
|
S.14
|
Experimental Substantiation of Design Functions of HT-2
System for New Russian NPP Project, |
|
|
S.15
|
Investigation of the Mechanics and Thermo-Hydraulics
Coupled Processes for the RBMK Graphite Stack, |
|
|
S.16
|
Critical Heat Flux, Local Hydraulic Characteristics and
Verification of VVER Fuel Assembly Computer Codes, |
|
|
S.17
|
Calculation of Deformation and Integrity of RBMK Pressure
Tubes at DHG Partial Break Using KAPRAN1 Code, |
20 October
|
|
S.18
|
Nuclear Fuel Qualification Program in Ukraine, |
|
|
S.19
|
Safety Analysis Strategic Program for Cernavoda NPP Unit
1", |
|
|
S.20
|
Assessment Study of ATHLET12A Based on the KS Facility
in Kurchatov Institute Stop Fill Problem for RBMK |
|
|
S.21
|
Structural Approach to Safety Analysis of NPP on Base
of Coolant Oscillations Modeling and Forecasting of the NPP Fundamental
Equipment Reliability. |
|
|
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 |
|
|
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 of Nuclear Fuel in Ukraine,
|
|
|
S.26
|
Some RELAP5 Modeling Features of the ISB-VVER SP-2 Test, |
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