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TRANSURANUS is a computer program for the thermal and mechanical analysis of fuel rods in nuclear reactors and was developed at the European Institute for Transuranium Elements (TUI). 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 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 has a comprehensive material data bank for oxide, mixed oxide, carbide and nitride fuels, Zircaloy and steel claddings and different coolants. During its development great effort was spent on obtaining an extremely flexible tool which is easy to handle, exhibiting very fast running times. The total development effort is approximately 40 man-years. In recent years, interest in the use of this code has increased and it is in use in several organisations, in both research and private industry. The code is now available to all interested parties. The paper outlines the main features and capabilities of the TRANSURANUS code and its validation, and also considers some practical aspects.

Additional information

Authors: LASSMANN K, JRC Karlsruhe (DE)
Bibliographic Reference: Paper presented: E-MRS Symposium on Nuclear Materials for Fission Reactors, Strasbourg (FR), November 4-8, 1991
Availability: Available from (1) as Paper EN 36395 ORA
Record Number: 199210975 / Last updated on: 1994-12-02
Original language: en
Available languages: en