TRANSURANUS: a fuel rod analysis code ready for use
- 21 February 2003
- journal article
- Published by Elsevier
- Vol. 188, 295-302
- https://doi.org/10.1016/0022-3115(92)90487-6
Abstract
No abstract availableKeywords
This publication has 9 references indexed in Scilit:
- Modelling of fuel rod behaviour and recent advances of the transuranus codeNuclear Engineering and Design, 1988
- The oxired model for redistribution of oxygen in nonstoichiometric uranium-plutonium oxidesJournal of Nuclear Materials, 1987
- The revised URGAP model to describe the gap conductance between fuel and claddingNuclear Engineering and Design, 1987
- A fast and simple iteration scheme for the temperature calculation in a fuel rodNuclear Engineering and Design, 1987
- An Advanced Method for Transient Temperature Calculation in Fuel Element Structural AnalysisNuclear Technology, 1983
- The structure of fuel element codesNuclear Engineering and Design, 1980
- URANUS — A computer programme for the thermal and mechanical analysis of the fuel rods in a nuclear reactorNuclear Engineering and Design, 1978
- Analytic solutions to mass transport equations for cylindrical nuclear fuel elementsJournal of Nuclear Materials, 1977
- Plutonium redistribution in fast reactor mixed oxide fuel pinsJournal of Nuclear Materials, 1973