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Abstract

The design and operational performance of fuel rods for nuclear power stations has been the subject of detailed experimental research for over thirty years. In the last two decades the continuous demands for greater economy in conjunction with more stringent safety criteria have led to an increasing reliance on computer simulations. Conditions within a fuel rod must be calculated both for normal operation and for proposed reactor faults. It has thus been necessary to build up a reliable, theoretical understanding of the intricate physical, mechanical and chemical processes occurring under a wide range of conditions, to obtain a quantitative insight into the behaviour of the fuel. A prime requirement is to predict the conditions under which failure of the cladding might occur, particularly in fuel nearing the end of its useful life. In this paper the general requirements of a fuel performance code are discussed briefly and an account is given of the basic concepts of code construction. An overview is then given of recent progress at the European Institute for Transuranium Elements in the development of a fuel rod performance code for general application and of more detailed mechanistic models for fission product behaviour.

Additional information

Authors: LASSMANN K, JRC Karlsruhe, Institute for Transuranium Elements, Postfach 2340, D-7500 Karlsruhe (DE);RONCHI C, JRC Karlsruhe, Institute for Transuranium Elements, Postfach 2340, D-7500 Karlsruhe (DE);SMALL G J, JRC Karlsruhe, Institute for Transuranium Elements, Postfach 2340, D-7500 Karlsruhe (DE)
Bibliographic Reference: Paper presented: Transuranium Elements Today and Tomorrow, Karlsruhe (DE), Oct. 26-27, 1988
Availability: Available from (1) as Paper EN 35035 ORA
Record Number: 198911139 / Last updated on: 1994-12-01
Category: PUBLICATION
Original language: en
Available languages: en
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