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This paper describes TRANSURANUS a computer program for the thermal and mechanical analysis of fuel rods in nuclear reactors. It was developed at the European Institute for Transuranium Elements (ITU) based on an earlier development of the URANUS code. The TRANSURANUS code consists of a clearly defined mechanical-mathematical framework into which physical models can easily be incorporated. Besides its flexibility for different fuel rod designs the TRANSURANUS code can deal with very different situations, as given for instance in an experiment, under normal, off-normal and accident conditions. The time scale of the problems to be treated may range from milliseconds to years. The code can be employed in different versions (as a deterministic and a statistical code).

Additional information

Authors: LASSMANN K, JRC Karlsruhe (DE);LÖSÖNEN P, JRC Karlsruhe (DE);VAN DE LAAR J, JRC Karlsruhe (DE)
Bibliographic Reference: Paper presented : IAEA Research Coordination Meeting on Fuel Modelling at Extended Burnup, Bombay (IN), April 1-5, 1996
Availability: Available from (1) as Paper EN 39866 ORA
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