Community Research and Development Information Service - CORDIS


This spinning cylinder experiment, organised under the auspices of the Network for the Evaluation of Steel Components (NESC) is designed to address the cleavage initiation behaviour of axial subclad flaws in end of life reactor pressure vessel (RPV) material under pressurized thermal shock (PTS) transient conditions. Pre-test structural integrity assessments have been performed to assist in the detail design of the experiment and in particular the specification of initial defect sizes. The results presented offer an insight into the influences of experimental variables on the probability of realising a cleavage event during the transient.

Additional information

Authors: BHANDARI S, Framatome, Paris (FR);MCALLISTER S, JRC Petten (NL)
Bibliographic Reference: Article : Nuclear Engineering and Design (1995), pp. 1-15
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