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The consequences of a nuclear power plant accident are dependent on the source term of radioactive fission products released, and this is largely determined by their behaviour within the containment building. Little attention has been paid to the adequacy of mathematical models in predicting the important phenomena which determine fission product behaviour. The objective of this report is to summarize an assessment of primary circuit fission product behaviour source term codes currently being used within the European Community and to pronounce on the fitness of these codes for their intended purpose. The work was organized into the two separate areas of model and code assessment, and plant studies. The code assessments have shown that apparently well known mechanisms are not well modelled under 'representative' reactor conditions. A series of practical modelling recommendations have been made, and important data requirements have been noted.

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Authors: WILLIAMS D A ET AL, AEA Technology, Winfrith (GB);JONES A V ET AL, JRC Ispra (IT);MAILLAT A ET AL, CEA, CEN Cadarache, Saint-Paul-lez-Durance (FR);PAROZZI F, ENEL Milan (IT)
Bibliographic Reference: EUR 16509 EN (1995) 35pp., FS, free of charge
Availability: Available from the European Commission, Mr G Cottone, DG XII-F-5, 200 rue de la Loi, B-1049 Bruxelles (BE)
ISBN: ISBN 92-827-5265-8
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