Improvement of delayed hydride cracking assessment of PWR spent fuel during dry storage
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
In a previous study, delayed hydride cracking (DHC) assessment of pressurized water reactor (PWR) spent fuel during dry storage using the threshold stress intensity factor (KIH) was performed. However, there were a few limitations in the analysis of the cladding properties, such as oxide thickness and mechanical properties. In this study, those models were modified to include test data for irradiated materials, and the cladding creep model was introduced to improve the reliability of the DHC assessment. In this study, DHC susceptibility of PWR spent fuel during dry storage depending on the axial elevation was evaluated with the improved assessment methodology. In addition, the sensitivity of affecting parameters such as fuel burnup, hydride thickness, and crack aspect ratio are presented.
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Technology
- Journal Volume
- 52
- Journal Issue
- 3
- Series
- 25 refs, 12 figs, 1 tab
- Journal Page Range
- p. 614-620
- ISSN
- 1738-5733
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 51108543
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- ASPECT RATIO; BURNUP; CRACKING; DRY STORAGE; HYDRIDES; PWR TYPE REACTORS; RELIABILITY; SPENT FUELS; STRESS INTENSITY FACTORS
- Descriptors DEC
- CHEMICAL REACTIONS; DECOMPOSITION; DIMENSIONLESS NUMBERS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HYDROGEN COMPOUNDS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; PYROLYSIS; REACTOR MATERIALS; REACTORS; STORAGE; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; WATER COOLED REACTORS; WATER MODERATED REACTORS