Affiliation:
1. Nuclear Research Centre “Kurchatov Institute” , 1, Akademika Kurchatova pl., Moscow, 123182 , Russian Federation
Abstract
Abstract
A brief description of the development history of engineering computer codes for VVER reactor calculations, which have been developed in the VVER physics department of NRC Kurchatov institute, since the end of 1950 s till now, are given in the report. The modern status of the basic codes of the Kurchatov institute for VVER fuel loadings design and safety analysis (TVS-M, KASKAD-BIPR-PERMAK, BIPR8, PERMAK-3D, SC1, TOPRA, ATHLET/BIPR-VVER, TIGR-1, etc.) is characterized from various points of view. Some specific problems which are shown during designing of fuel cycles, optimisation of fuel and technologies will be commented. They demand decisions within the complex of programs and, accordingly, demand the further development of a complex or working out and inclusion in a complex of new programs.
Subject
Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation
Reference4 articles.
1. Theoretical investigations of the physical properties of VVER-type uranium-water lattices;Final report of TIC,1994
2. Time Dependent Spatial Neutron Kinetic Algorithm for BIPR8 and its Verification,1992
3. The recovery procedure of pin-by-pin fields of power distribution in the core of VVER type of reactor for the program BIPR-8
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