Speaker
Description
Two potential cladding degradation mechanisms have been the focus of regulatory authorities’ reviews when evaluating applications for storage and transportation of spent nuclear fuel under dry, inert atmosphere conditions: thermal creep and hydride re-orientation. A review of the thermal creep mechanisms in the low and high stress regions and their dependence on applied stress, as supported by experimental work, leads to the conclusion that creep failure is highly unlikely for internally pressurized spent fuel rods. Through a process of elimination, the formation of radial hydrides can be assessed to be minor or completely eliminated for several types of BWR and PWR claddings; claddings that would benefit from additional investigations include RX and pRX PWR claddings when hydride dissolution upon heating occurs in a temperature range sufficiently high for complete hydride dissolution, but too low for any significant radiation damage annealing.
| Country or International Organization | United States of America |
|---|---|
| Do you wish to enter the YGE SFM19 Challenge? | Yes |
