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Using of computer code GEFEST800 at the initial stage of NPP operation with BN-800

Jun 28, 2017, 5:50 PM
1h 10m
Yekaterinburg

Yekaterinburg

POSTER Track 2. Fast Reactor Operation and Decommissioning Poster Session 2

Speaker

Mr Evgeny Seleznev (NUCLEAR SAFETY INSTITUTE OF RUSSIAN ACADEMY OF SCIENCES)

Description

The GEFEST800 code has been developed to carry out neutronic calculations of nu-clear power plant operation for sodium cooled fast breeder reactor BN-800 (stationary and transient from minimum controllable power level to full reactor power with drive control rods and fuel burning). The code allows to calculate the following parameters: keff; maximum reac-tivity reserve; effective reactivity of control rods and control rod groups; full, specific and lin-ear power of energy release in fuel assemblies; unevenness coefficients of energy release in fuel assemblies and reactor core; damaging irradiation dose for fuel assemblies; burning; reac-tivity coefficients; effective fraction of delayed neutrons; transient processes characteristics; decay energy release and many other parameters. The code has diffusion, transport and Monte-Carlo modules. The CONSYST code with ABBN-93 library is used for constants' preparation. The code has thermomechanical module to take into account changes in the size of the cells. The presence of such module al-lows to consider these changes in calculations of reactivity coefficients at different power lev-els. Services such as calculated parameters control, graphics, data preparation, analysis of cal-culated results are provided in interactive mode using specially developed graphical shell. Some results of using the code at the initial stage of NPP operation with BN-800 are presented in the paper.

Country/Int. Organization

RUSSIAN FEDERATION

Primary author

Mr Evgeny Seleznev (NUCLEAR SAFETY INSTITUTE OF RUSSIAN ACADEMY OF SCIENCES)

Co-authors

Mr Alexander Belov (Nuclear Safety Institute of the Russian Academy of Sciences) Mr Alexey Ivanov (Belojarskaja nuclear power plant) Mr Anatoliy Tsibulya (State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering) Mr Anton Peregudov (State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering) Mr David Asatrjan (Nuclear Safety Institute of the Russian Academy of Sciences) Mr Dmitriy Maltsev (Belojarskaja nuclear power plant) Mr Evgeny Ljapin (Belojarskaja nuclear power plant) Mr Gennadiy Manturov (State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering) Mr Grigoriy Dubovoj (Belojarskaja nuclear power plant) Mr Igor Fedorov (All-Russian Research Institute for Nuclear Power Plants Operation JSC) Ms Irina Chernova (Nuclear Safety Institute of the Russian Academy of Sciences) Mr Michail Semenov (State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering) Mr Victor Belousov (Nuclear Safety Institute of the Russian Academy of Sciences) Mr Yrii Drobyshev (All-Russian Research Institute for Nuclear Power Plants Operation JSC)

Presentation materials