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The paper presents the TRANSURANUS-WWER version, which models the fuel rod behaviour of Russian WWER nuclear power reactors. It is an extension of the TRANSURANUS code developed and continuously improved at ITU - Karlsruhe, Germany. The development has been performed by a joint team within the frame of a PHARE project of the European Union. Material properties of the cladding alloy Zr1Nb have been carefully analysed and incorporated into the code as WWER-specific subroutines. The verification is based on the SOFIT and the KOLA-3 data sets from the international IFPE database. The TRANSURANUS-WWER version predicts reasonably well the experimental findings available. Any further development needs to access to Russian data, which have not been published yet. Especially, irradiation data of WWER-1000 fuel rods are needed as well as further information on the behavior of WWER fuel rods during transients.

Additional information

Authors: ELENKOV D, Institute for Nuclear Research and Nuclear Energy, Sofia (BU);LASSMANN K, Institute for Transuranium, Karlsruhe (DE)
Bibliographic Reference: Paper presented: 3rd International Seminar on WWER Fuel Performance, Pamparovo (BU), 4-8th November (1999)
Availability: Available from Public Relations and Publications Unit, Ispra (IT)
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