TRANSURANUS : A fuel rod analysis code ready for use
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. As well as its flexibility for the fuel rod design, the TRANSURANUS code can deal with very different situations, for instance 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, carbide and nitride fuels, zircaloy and steel claddings and different coolants. The recently developed high burnup model TUBRNP is also outlined.
Bibliographic Reference: Paper presented: WWER Reactor Fuel Performance, Modelling and Experimental Support, Varna, St. Constantine (BG), November 7-11, 1994
Availability: Available from (1) as Paper EN 38803 ORA
Record Number: 199510131 / Last updated on: 1995-08-22
Original language: en
Available languages: en