Behavior of High-Burnup PWR Fuels with Low-Tin Zircaloy-4 Cladding Under Reactivity-Initiated-Accident Conditions
Journal Article
·
· Nuclear Technology
OSTI ID:20822233
- Japan Atomic Energy Research Institute (Japan)
Experimental programs on fuel behavior during simulated reactivity-initiated-accident (RIA) conditions at the Nuclear Safety Research Reactor (NSRR) in Japan and the CABRI test reactor in France appear to indicate that cladding failures may occur at enthalpy values lower than would be expected. Results from two experiments designated as HBO-1 in NSRR and REP Na-1 in CABRI indicate that the occurrence of fuel failure is strongly influenced by corrosion of cladding in the tested fuels. However, data had been limited to fuel rods with conventional (1.5% Sn) Zircaloy-4 cladding. Results are described from newly conducted NSRR experiments, TK test series, for 38 to 50 MWd/kg U pressurized water reactor fuels with low-tin (1.3% Sn) Zircaloy-4 cladding, and anticipated processes of fuel behavior during the transient are discussed.
- OSTI ID:
- 20822233
- Journal Information:
- Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 1 Vol. 133; ISSN 0029-5450; ISSN NUTYBB
- Country of Publication:
- United States
- Language:
- English
Similar Records
High-burnup Experiments in Reactivity Initiated Accidents (HERA)
Assessment of reactivity transient experiments with high burnup fuel
A review of cladding failure thresholds in RIA conditions based on transient reactor test data and the need for continued testing
Technical Report
·
Wed Jun 01 00:00:00 EDT 2022
·
OSTI ID:1874819
Assessment of reactivity transient experiments with high burnup fuel
Technical Report
·
Thu Feb 29 23:00:00 EST 1996
·
OSTI ID:269708
A review of cladding failure thresholds in RIA conditions based on transient reactor test data and the need for continued testing
Conference
·
Wed Jun 01 00:00:00 EDT 2022
·
OSTI ID:2202402