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This paper describes the main concepts and purposes of fuel rod performance modelling and its contribution to the general improvement of nuclear fuel elements. Any such model must include a solution of the heat conduction equation and the principal mechanical equations i.e. for equilibrium and compatability, together with constitutive equations. The main source of uncertainty lies in the input data for local processes, since it is not known how local quantities such as pores, grain structure and stresses evolve during irradiation. The problem of determining fission gas release and swelling is particularly sensitive to changes in crack structure.

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Authors: LASSMANN K, JRC Karlsruhe (DE);O'CARROLL C, JRC Karlsruhe (DE);VAN DE LAAR J, JRC Karlsruhe (DE);RAY I, JRC Karlsruhe (DE);STEFANOVA S, Bulgarian Academy of Sciences, Institute for Nuclear Research and Nuclear Energy, Sofia (BG);CHANTOIN P, International Atomic Energy Agency, Division of Nuclear Fuel Cycle and Waste Management, Wien (AT)
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 38804 ORA
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