A study on the assessment criteria of DHC in PWR spent fuel
Creators
- 1. LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, 34057 (Korea, Republic of)
Description
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 10-7 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 (KIH) for PWR Zircaloy-4 cladding were described. Based on the limited existing test results and analysis, the experimentally measured KIH were compared with the predicted KIH. The comparison shows that the predicted values are much lower than the measured ones and both theoretical estimation and measured values of KIH 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
Availability note (English)
Available from: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US), also available in CD-RomAdditional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 978-0-89448-734-7
- Imprint Title
- TOP FUEL 2016 Proceedings
- Imprint Pagination
- 1670 p.
- Journal Page Range
- p. 557-561
Conference
- Title
- LWR fuels with enhanced safety and performance
- Acronym
- TOP FUEL 2016
- Dates
- 11-15 Sep 2016
- Place
- Boise, ID (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 50007196
- Subject category
- S42: ENGINEERING; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; COMPARATIVE EVALUATIONS; CRACK PROPAGATION; CRACKING; CRACKS; DRY STORAGE; HYDRIDES; MECHANICAL TESTS; PWR TYPE REACTORS; SPENT FUELS; STRESS INTENSITY FACTORS; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0065-0273 K; ZIRCALOY 4
- Descriptors DEC
- ALLOYS; ALLOY-ZR98SN-4; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DECOMPOSITION; DEPOSITION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EVALUATION; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HYDROGEN COMPOUNDS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; MATERIALS TESTING; NUCLEAR FUELS; POWER REACTORS; PYROLYSIS; REACTOR MATERIALS; REACTORS; STORAGE; SURFACE COATING; TEMPERATURE RANGE; TESTING; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 7 refs.