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AbstractAbstract
[en] The modelling of fuel behaviour during irradiation and the tailoring of an irradiation stable fuel require an accurate description of the stress free volume changes due to fuel densification and fuel swelling. The influence of fuel flows due to creep and hot pressing should be considered separately. This paper presents detailed densification models which describe the dependence of densification on time or burnup, temperature, density, pore size distribution, grain size, and fission rate. UO2 matrix swelling due to fission product accumulation and densification due to pore shrinkage are considered to operate simultaneously and are linearly superposed. Four temperature regions can be identified which describe the dependence of irradiation induced fuel densification on temperature. The shrinkage rate of small pores strongly controls the initial densification rate. Experimental verification of the densification models is obtained from numerous constant temperature thermal sinter tests conducted between 12000C and 19000C as well as in isothermal irradiation tests between 10000C and 12000C and around 7000C. Although the kinetics of thermal and in-reactor densification are different, standarized thermal resinter tests can be established and used to predict the in-reactor densification. (Auth.)
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Jaeger, T.A.; Boley, B.A. (eds.); International Association for Structural Mechanics in Reactor Technology; Commission of the European Communities, Brussels (Belgium); v. C p. C3/1 1-16; ISBN 0 444 85062 7;
; 1977; v. C p. C3/1 1-16; North-Holland; Amsterdam, Netherlands; 4. international conference on structural mechanics in reactor technology; San Francisco, USA; 15 - 19 Aug 1977

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Conference
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