Community Research and Development Information Service - CORDIS


The present report deals with comparisons of acceptance criteria for flows of components of nuclear power plants (NPPs), which are applied during in-service inspection results evaluation. Two main codes have been included in the study: RSEM and ASME XI codes which are the French rules for monitoring and maintenance and the American code for inspection of operating plants respectively. The scope of the study is directed to significant weldments of the reactor coolant system of pressurized water reactor (PWR). Moreover, an analytical tool was used as an innovation in order to provide validation for criteria comparisons.

Additional information

Authors: ALICINO F, Ansaldo (IT);CAPURRO E, Ansaldo (IT);REALE S, Università di Firenze (IT);TOGNARELLI L, Università di Firenze (IT)
Bibliographic Reference: EUR 17573 EN (1998) 66pp., ECU 13.50
Availability: Available from the (2)
ISBN: ISBN 92-828-4192-8
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