Annual progress report on the NSRR experiments, (19)
Description
Fuel behavior studies in simulated reactivity initiated accident (RIA) conditions have been performed by utilizing Nuclear Safety Research Reactor (NSRR) since October 1975. This report describes the results obtained from experiments performed from January through December, 1987. A total of 38 tests was carried out during this period : those are 5 NSRR standard fuel test, 6 fuel design parameter tests (2 fuel tests with iodine, 3 tests with SUS claddings, and 1 for destructive force measurement test), 7 cooling parameter tests (3 test with flow tube and 4 bundle tests), 8 advanced type fuel tests (1 NRC tests, 5 PCI-resistant fuel tests, 2 pressurized hollow fuel tests), 1 high pressure / high temperature tests, 2 high temperature / high pressure loop tests, 3 high temperature flooding tests, 3 fuel motion observation tests, and 3 miscellaneous atmospheric pressure capsule tests (1 fuel damage test, 2 acceleration tests). The progress of computer code development is also described. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
23015078.pdf
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Additional details
Additional titles
- Subtitle (English)
- January 1987 through December 1987
Publishing Information
- Imprint Pagination
- 164 p.
- Report number
- JAERI-M--91-130
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 23015078
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- COOLING; DEFORMATION; FLOODS; FRETTING CORROSION; FUEL ELEMENT FAILURE; FUEL INTEGRITY; FUEL MOTION DETECTION; FUEL-CLADDING INTERACTIONS; HOLLOW FUEL RODS; N CODES; NSRR REACTOR; PROGRESS REPORT; REACTIVITY; REACTOR ACCIDENTS
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; COMPUTER CODES; CORROSION; DETECTION; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUEL RODS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MIXED SPECTRUM REACTORS; PULSED REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS