On the effect of temperature on the threshold stress intensity factor of delayed hydride cracking in light water reactor fuel cladding

Delayed hydride cracking (DHC) was first observed in pressure tubes in Canadian CANDU reactors. In light water reactors, DHC was not observed until the late 1990s in high-burnup boiling water reactor (BWR) fuel cladding. In recent years, the focus on DHC has resurfaced in light of the increased interest in the cladding integrity during interim conditions. In principle, all spent fuel in the wet pools has sufficient hydrogen content for DHC to operate below 300 degrees C. It is therefore of importance to establish the critical parameters for DHC to operate. This work studies the threshold stress intensity factor (K-IH) to initiate DHC as a function of temperature in Zry-4 for temperatures between 227 degrees C and 315 degrees C. The experimental technique used in this study was the pin-loading testing technique. To determine the KIH, an unloading method was used where the load was successively reduced in a stepwise manner until no cracking was observed during 24 hours. The results showed that there was moderate temperature behavior at lower temperatures. Around 300 degrees C, there was a sharp increase in KIH indicating the upper temperature limit for DHC. The value for KIH at 227 degrees C was determined to be 2.6 +/- 0.3 MPa root m. (C) 2017 Korean Nuclear Society, Published by Elsevier Korea LLC.