A study on the assessment criteria of DHC in PWR spent fuel
- LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, 34057 (Korea, Republic of)
One of the major degradation mechanisms of PWR spent fuel cladding is delayed hydride cracking (DHC), which can activate within a relatively low temperature range. Its maximum crack growth rate is estimated to be within the range of 10{sup -7} m/s, at which the cladding can rupture in 1 to 2 years during dry storage. For this reason, it is essential to prevent DHC crack growth itself, but most of the existing DHC studies have been focused on the crack growth rate. In this regard, the values and characteristics of the threshold stress intensity factor (K{sub IH}) for PWR Zircaloy-4 cladding were described. Based on the limited existing test results and analysis, the experimentally measured K{sub IH} were compared with the predicted K{sub IH}. The comparison shows that the predicted values are much lower than the measured ones and both theoretical estimation and measured values of K{sub IH} increase as the temperature increases. The possibilities of degradation by DHC were also discussed during long-term dry storage. For a more reliable analysis, additional information on a pre-existing crack of spent fuel is needed.
- Research Organization:
- American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 22764050
- Country of Publication:
- United States
- Language:
- English
Similar Records
Control of degradation of spent LWR (light-water reactor) fuel during dry storage in an inert atmosphere
Assessment of nitrogen as an atmosphere for dry storage of spent LWR fuel