The report summarizes the first practical experience obtained by fuel rod performance modelling at the Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Sciences. The results of application of the PIN-micro code and the code modification PINB1 for thermomechanical analysis of WWER-440 fuel assemblies (FAs) are presented. The aim of this analysis is to study the fuel rod behaviour of the operating WWER reactors. The performance of two FAs with maximal linear power and varying geometrical and technological parameters is analyzed. On the basis of recent publications on WWER fuel performance modelling at extended burnup, a modified PINB1 version of the standard PIN-micro code is shortly described and applied for the selected FAs. Comparison of the calculated results is performed. The PINB1 version predicts higher fuel temperatures and more adequate FGR rate, accounting for the extended burnup. The results presented in this paper prove the existence of sufficient safety margins, for the fuel performance limiting parameters during the whole considered period of core operation. (author). 8 refs, 16 figs, 1 tab.
Stefanova, S; Vitkova, M; Simeonova, V; Passage, G; Manolova, M;  Haralampieva, Z;  Scheglov, A; Proselkov, V 
- Institute for Nuclear Research and Nuclear Energy, Sofia (Bulgaria)
- National Electric Company Ltd., Kozloduy (Bulgaria)
- Institute of Nuclear Reactors, RSC Kurchatov Inst., Moscow (Russian Federation)