Annual progress report on the NSRR experiments, (15)
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
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 January through December, 1983. A total of 51 tests were carried out during this period; those are 4 standard fuel rod tests (4 high energy deposition tests), 5 fuel design parameter tests (1 pre-pressurized fuel rod test, 3 stainless steel cladding fuel rod tests and 1 pre-irradiated clad fuel rod test), 6 cooling condition parameter tests (2 coolant temperature parameter tests, 1 forced convection test and 3 bundle rod tests), 3 defected fuel rod tests (3 fretting corroded clad fuel rod tests), 8 severe fuel damage tests, 2 special fuel rod tests (2 HTGR fuel tests), 3 high temperature high pressure capsule tests, 2 high temperature high pressure loop tests, 6 fuel behavior observation tests, and 12 miscellaneous tests (acoustic measurement tests, pellet acceleration measurement tests, fuel rod deformation measurement tests, etc). (author)
Availability note (English)
MF available from INIS under the Report Number.Files
17007114.pdf
Files
(8.2 MB)
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Additional details
Additional titles
- Subtitle (English)
- January 1983 through December 1983
Publishing Information
- Imprint Pagination
- 255 p.
- Report number
- JAERI-M--84-168
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 17007114
- 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
- COMPUTER CODES; FORCED CONVECTION; FRETTING CORROSION; FUEL CANS; FUEL ELEMENT FAILURE; FUEL RODS; HEATING; IRRADIATION CAPSULES; MOTION; NSRR REACTOR; POST-IRRADIATION EXAMINATION; PRESSURE DEPENDENCE; REACTIVITY INSERTIONS; RESEARCH PROGRAMS; STRAINS; TEMPERATURE DEPENDENCE
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; CONVECTION; CORROSION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HEAT TRANSFER; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MIXED SPECTRUM REACTORS; PULSED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS