Published March 1980 | Version v1
Report Open

Semiannual progress report in the NSRR experiments, (8)

Creators

Description

Fuel behavior studies with simulated reactivity-initiated accident (RIA) conditions have been performed using Nuclear Safety Research Reactor (NSRR) since October 1975. This report describes the results obtained from January to June 1979. Forty-seven tests were carried out during the period; which are 3 standard rod tests, 7 fuel design parameter tests 3 autoclaved cladding tests, 2 gap gas parameter tests and others, 3 cooling environment variation tests (forced convection tests), 16 USNRC fuel rod tests, 5 defective fuel rod tests (waterlogged rod tests), 2 high pressure capsule tests, and 11 miscellaneous tests (fuel rod meltdown test and others). (author)

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Additional titles

Subtitle (English)
January to June, 1979

Publishing Information

Imprint Pagination
75 p.
Report number
JAERI-M--8779

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
12596715
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Numerical Data, Progress Report
Descriptors DEI
EXPERIMENTAL DATA; FORCED CONVECTION; FUEL ELEMENT FAILURE; FUEL-CLADDING INTERACTIONS; IRRADIATION CAPSULES; MELTDOWN; METALLOGRAPHY; NSRR REACTOR; RESEARCH PROGRAMS; SUBCOOLING; TEMPERATURE DEPENDENCE; WATER
Descriptors DEC
ACCIDENTS; CONVECTION; COOLING; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; HYDROGEN COMPOUNDS; INFORMATION; MIXED SPECTRUM REACTORS; NUMERICAL DATA; OXYGEN COMPOUNDS; PULSED REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS