Published 1987 | Version v1
Journal article Metadata-only

Postirradiation examination of higher uranium density fuels at JAERI

Creators

Description

A reduced enrichment program for research and test reactor fuels at Japan Atomic Energy Research Institute (JAERI), in which the JRR-2 and Japan Material Testing Reactor (JMTR) are to be converted to the use of medium-enriched uranium (MEU) (45% enriched uranium) aluminide fuels and the JRR-3 and JRR-4 to the use of low-enriched uranium (LEU) (19.5% enriched uranium) aluminide fuels is in progress or has been completed. Further core conversion of the JMTR to the use of LEU silicide fuels with burnable poison is being studied

Additional details

Publishing Information

Journal Title
Trans. Am. Nucl. Soc.
Journal Volume
55
Series
Trans. Am. Nucl. Soc.
Journal Page Range
279-280
ISSN
0003-018X
CODEN
TANSA

Conference

Title
American Nuclear Society winter meeting.
Dates
15-19 Nov 1987.
Place
Los Angeles, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19106462
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNABLE POISONS; BURNUP; CRACKS; DEFORMATION; FUEL ELEMENTS; FUEL PLATES; JMTR REACTOR; JRR-2 REACTOR; JRR-3 REACTOR; JRR-4 REACTOR; METALLOGRAPHY; MODERATELY ENRICHED URANIUM; POST-IRRADIATION EXAMINATION; REACTOR CORES; REACTOR KINETICS; SCANNING ELECTRON MICROSCOPY; X-RAY RADIOGRAPHY
Descriptors DEC
ACTINIDES; ELECTRON MICROSCOPY; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; KINETICS; MATERIALS; MATERIALS TESTING REACTORS; METALS; MICROSCOPY; NATURAL URANIUM REACTORS; NEUTRON ABSORBERS; NUCLEAR POISONS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-8711195--.