Community Research and Development Information Service - CORDIS


TRANSURANUS is a sophisticated computer programme for the mechanical and thermal analysis of the fuel rod begaviour in power reactors during normal operation, off-normal operation and - with several restrictions- also during accidents.

Present interest is in the area of high burn-up phenomena and MOX fuel. The TRANSURANUS code is modular structured. For all properties and physical processes in the fuel, several options (models or correlations) exist that are programmed as separate program modules. Depending on the specific case, any option (correlation) for a given property or process can be called independently. This flexibility of the code allows the analusis of different fuel rod designs, special experimental set ups or carious reactor conditions. Created for Western type reactors, the standard TRANSURANUS code has been extended to miodel the behaviour of Russian WWER fuel rods in the nuclear reactors WWER-440 AND WWER-1000.

Additional information

Authors: ELENKOV D, Institute for Nuclear Research And Nuclear Energy, Sofia (BG);KASSMANN K, ITU, Karlsruhe, (DE)
Bibliographic Reference: Oral Report: 3rd International Seminar on WWER Fuel Performance, Pamporovo, (BG) 4-8 October, 1999
Availability: 1 as paper EN 60770 ORA
ISBN: 954-9820-03-3
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