51313-02257-Hydrides Formation from Fuel Cladding Corrosion and Influence of Hydrides on Mechanical Behavior

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Product Number: 51313-02257-SG

ISBN: 02257 2013 CP

Author: Xihua He

Publication Date: 2013

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Zirconium-based cladding material exposed to coolant water during nuclear reactor operations could absorb hydrogen up to 800 ppm. During extended dry storage as the cladding cools with time the hydrogen inside the cladding couldprecipitate as hydrides; furthermore both existing and newly formed hydrides may reorient. Depending on size distribution and orientation these hydrides may lead to premature fracture as a result of hydride embrittlement or delayed hydride cracking. Because the U.S. is actively considering extended dry storage as an alternative approach to manage spent nuclear fuel and the amount of high burnup fuel with possibly high hydrogen concentration is increasing as a result of changes in plant operating conditions there is a need for data on hydride reorientation and its influence on mechanical behavior during extended storage. This work reports (i) methods to form hydrides ofvarious concentration levels in cladding (ii) conditions when hydrides reorient under stress and (iii) effectsof hydride concentration and their orientation on mechanical properties.Preliminary results on the work showed that the hydride content absorbed in the bulk material can be adjusted by controlling the annealing temperature and there is a stress threshold to reorient the hydrides.