Stress intensity factor at the tip of cladding incipient crack in RIA-simulating experiments for high-burnup PWR fuels
- 1. Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan)
Description
RIA-simulating experiments for high-burnup PWR fuels have been performed in the NSRR, and the stress intensity factor K1 at the tip of cladding incipient crack has been evaluated in order to investigate its validity as a PCMI failure threshold under RIA conditions. An incipient crack depth was determined by observation of metallographs. The maximum hydride-rim thickness in the cladding of the test fuel rod was regarded as the incipient crack depth in each test case. Hoop stress in the cladding periphery during the pulse power transient was calculated by the RANNS code. K1 was calculated based on crack depth and hoop stress. According to the RANNS calculation, PCMI failure cases can be divided into two groups: failure in the elastic phase and failure in the plastic phase. In the former case, elastic deformation was predominant around the incipient crack at failure time. K1 is available only in this case. In the latter, plastic deformation was predominant around the incipient crack at failure time. Failure in the elastic phase never occurred when K1 was less than 17 MPa m1/2. For failure in the plastic phase, the plastic hoop strain of the cladding periphery at failure time clearly showed a tendency to decrease with incipient crack depth. The combination of K1, for failure in the elastic phase, and plastic hoop strain at failure, for failure in the plastic phase, can be an effective index of PCMI failure under RIA conditions. (author)
Availability note (English)
Available from http://dx.doi.org/10.3327/jnst.46.1012Additional details
Identifiers
- DOI
- 10.3327/jnst.46.1012;
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 46
- Journal Issue
- 10
- Journal Page Range
- p. 1012-2021
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 41027046
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP EXTENSION; FAILURES; FUEL CANS; FUEL-CLADDING INTERACTIONS; HYDRIDES; NSRR REACTOR; PWR TYPE REACTORS; REACTIVITY INSERTIONS; ROD EJECTION ACCIDENTS; STRESS INTENSITY FACTORS; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; BURNUP; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; HYDROGEN COMPOUNDS; MIXED SPECTRUM REACTORS; POWER REACTORS; PULSED REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 19 refs., 10 figs., 2 tabs.