Power ramp testing of fresh fuel rods with added iodine
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
In order to study the relationship between the power ramp failure, which has been mainly an issue of BWR fuel integrity, and the out-pile iodine stress corrosion (SCC) experiments, a series of power ramp experiments was performed using fresh fuel rods enriched with iodine. By adopting narrow fuel-clad gap and other measures, cladding stress condition was set to a level somewhat lower than the prototypic condition in irradiated fuels. Iodine atmosphere was adjusted by mixing UO2+x or MoO3 with CsI powder. Three rods were ramp-tested one by one, in which conditions leading to SCC failure were gradually strengthened. No fuel failure occurred, however, even under iodine partial pressure as high as about 1 atm.. From this result and a survey of past in-pile stress corrosion experiments, it was concluded that contribution of iodine to power ramp failure is actually small, vast number of iodine SCC experiments not simulating the actual fuel conditions. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
24047727.pdf
Files
(1.6 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 44 p.
- Report number
- JAERI-M--92-177
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 24047727
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CESIUM IODIDES; FUEL ELEMENT FAILURE; FUEL INTEGRITY; FUEL RODS; IODINE; MIXTURES; MOLYBDENUM OXIDES; POWER GENERATION; STRESS CORROSION; TEMPERATURE DEPENDENCE; TIME DEPENDENCE; TRANSIENTS; URANIUM DIOXIDE; VAPOR PRESSURE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALKALI METAL COMPOUNDS; CESIUM COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; CORROSION; DISPERSIONS; ELEMENTS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HALIDES; HALOGEN COMPOUNDS; HALOGENS; IODIDES; IODINE COMPOUNDS; MOLYBDENUM COMPOUNDS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS