Research program on conditions to failure of high burnup fuel
Creators
- 1. Japan Nuclear Energy Safety Organization, Nuclear Energy System Safety Division, Tokyo (Japan)
Description
A fuel failure initiating at the cladding outer surface and penetrating inwards (outside-in cracking) observed in the power ramp test on high burnup BWR fuel has been studied to clarify its onset conditions for the safety review on high burnup fuel integrity under transient conditions. Hydrogen thermal diffusion in the cladding tube radial direction was investigated in terms of radial hydride precipitation which has been considered to be a potential site for the crack initiation. Hydrogen diffusion analyses seemed to provide reasonable prediction of radial hydride initiation conditions in comparison with the hydrogen thermal diffusion test results. Conditions to cause incipient crack were assessed using results of the outside-in cracking simulation test in which irradiated cladding tube specimens were loaded by constant internal pressurization under condition of radial temperature gradient. Results indicated the minimum stress to cause incipient cracks at the cladding outer surface. Crack propagation behaviors were also investigated using estimated incipient crack length and calculated stress intensity factor. (author)
Additional details
Publishing Information
- Imprint Title
- Annual safety research report, JFY 2010
- Imprint Pagination
- 444 p.
- Journal Page Range
- p. 29-34
- Report number
- JNES-RE--2011-0001
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51066784
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BURNUP EXTENSION; BWR TYPE REACTORS; CRACK PROPAGATION; FAILURES; FUEL CANS; FUEL-CLADDING INTERACTIONS; HYDROGEN; NUCLEAR FUELS; STRESS INTENSITY FACTORS; THERMAL DIFFUSION; ZIRCONIUM
- Descriptors DEC
- BURNUP; DIFFUSION; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; METALS; NONMETALS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 figs.; This record replaces 46029570