Presentations from the Sixth International Information Exchange Forum


The Sixth International Exchange Forum on Safety Analysis for Nuclear Power (Forum-6) was held April  8-12, 2002 in Kyiv, Ukraine.  There were about 80 papers presented at the conference. The papers listed below include the ones that were presented in the International RELAP5 Users Group (IRUG) session, along with one paper from the poster session.

Click on one of the following titles to view a paper.

Paper Title

Authors

Organization

The Variant Analysis for Assessment of the Core Condition of Reactor Type WWER-440 (V-230) in case of Loop Guillotine Rupture

K. Avdjiev, 
E. Balabanov, 
A. Krastev

ENPRO Consult

RELAP5/MOD3.2 Assessment Using INSC SP-V7

Paul D. Bayless, 
Mikhail V. Davydov

INL 
EREC

Analysis of the Natural Circulation Standard Problem for Kozloduy NPP Unit 6

Nikolay A. Brus,
Oleg E. Ioussoupov

EREC

Analysis with RELAP5 Computer Code of Experiments for Investigation of Void Fraction Distribution in RBMK Fuel Channel Model

V. Borisenko, 
I. Kadenko

NUK

Use of Main Loop Valves Investigation in Case of SGTR

Pavlin P. Groudev, 
Rositsa V. Gencheva

INRNE

Deterministic Safety Analyses of the Armenian NPP #2

V.G.Petrosyan,
Natalya Hovakimova

Armatom

Small Break LOCA Analysis of MOCHOVCE NPP VVER-440/213 with Operator Action

Tomas Kliment, 
Boris Kvizda,  Tibor Zold

VUJE 
 Mochovce NPP

RELAP5/MOD3.2 Analysis of Trip of One MCP at Kozloduy NPP Unit 6

M. Pavlova,
P. Groudev,
V. Hadjiev

INRNE 

Kozloduy NPP

RMBK SP-2 Validation Results (KS PH Rupture Simulation)

Bruce Schmitt

PNNL

The Second Standard Problem of VVER Reflooding: Basic Results

V.V. Sergeev,
A.D. Efanov,
V.N. Vinogradov,
O.A. Sudnitsyn

IPPE

The Possibility of 3D-effects Prediction with 1D Thermohydraulic Codes and its Significance in the Frame of PWR Type Reactors Deterministic Safety Analysis

Dmitro Shevyelov

KIEP

The Analysis of the WWER-440 Primary Circuit Protection against Cold Overpressure with RELAP5/MOD3.2 Code

Dmitro Shevyelov
Yuriy Sapozhnikov

KIEP

Development of Coupled Thermohydraulics-Neutron Kinetics Models with RELAP5-3D Code for VVER Reactors

A. Shkarupa,
N. Trofimova,
I. Kadenko,
A. Kharitonov, 
R. Yermolenko,
T. Galatyuk

NUK

Experience in Modeling the Zaporizhzhya NPP Using RELAP5

V.V. Sverdlov,
A.V. Sverdlov

EIS

RELAP5/MOD3.2 Analyses of KS-1 Facility Experiments on Heat Transfer Processes in the Full-Length and Partially Uncovered Model

V. Vinogradov,
A.Yu. Balykin

KI