Realistic methods for calculating the release of radioactivity following steam generator tube rupture faults : A consensus document
The present report addresses the steam generator tube rupture (SGTR) fault of a PWR, which is a design basis fault considered by European licensing authorities. The same SGTR fault sequences are not considered in all countries for licensing purposes and, therefore, a selection of faults was considered which enabled the methods and data to be compared. The mechanisms which determine the retention of fission products in the steam generator are reviewed. A realistic model for predicting the release to the environment is proposed and used to predict the release for an SGTR fault sequence in which a relief valve fails to close. The results show that the nature of the transient is sensitive to factors such as the reactor design and the operating procedures. The resulting differences in the accident progression have a significant effect on the predicted level of fission product retention.
Bibliographic Reference: EUR 15615 EN (1994) 202 pp., FS, ECU 23
ISBN: ISBN 92-826-8667-1
Record Number: 199411339 / Last updated on: 1994-12-06
Original language: en
Available languages: en