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This report describes a calculational route to predict realistic radiological consequences for a successfully terminated large-loss-of-coolant accident (LOCA) at a pressurised-water reactor (PWR). All steps in the calculational route are considered. For each, a brief comment is made on the significant differences between the methods of calculation identified in the benchmark studies, and recommendations are made for methods and data for carrying out realistic calculations. The behaviour of inorganic iodine and the removal of aerosols from the atmosphere of the reactor building are identified as areas of particular importance. Where the retention of radioactivity is sensitive to design features, these are identified and, for the most important features, the impact of different designs on the release of activity is indicated. The predictions of the proposed model are calculated for each stage and compared with the releases of activity predicted by the licensing methods that were used in the earlier benchmark studies. Methods and data are also presented for calculating the resulting doses to members of the public.

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Authors: STEPHENSON W, NNC Limited, Knutsford (GB);DUTTON L M C, NNC Limited, Knutsford (GB);HANDY B J, NNC Limited, Knutsford (GB);SMEDLEY C, NNC Limited, Knutsford (GB)
Bibliographic Reference: EUR 14179 EN (1992) 235 pp., FS, ECU 24
Availability: (2)
ISBN: ISBN 92-826-4632-7
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