Published May 1976
| Version v1
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Thermal decladding of BOR-60 fuel elements
Description
Experimental results on thermal decladding of reactor BOR-60 fuel elements irradiated to >10% and cooling time - 6 and 3 months - are discussed. The direct yield of fuel is 99.9%; content of steel in fuel <5,4%; data on fission products distribution are also given
Availability note (English)
MF available from INIS under the Report Number.Files
9363489.pdf
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Additional details
Additional titles
- Original title (Russian)
- Термическое вскрытие облученных твэлов реактора BOR-60 проектного выгорания с выдержкой после облучения 6 и 3 месяца
Publishing Information
- Imprint Pagination
- 20 p.
- Report number
- IAEA-AG--63-16
Conference
- Title
- Advisory group meeting on reprocessing of Liquid Metal Fast Breeder Reactor fuels.
- Dates
- 17 - 21 May 1976.
- Place
- Leningrad, USSR.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 9363489
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOR-60 REACTOR; DECLADDING; FUEL ELEMENTS; MELTING; SPENT FUELS
- Descriptors DEC
- BREEDER REACTORS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; HEAD END PROCESSES; LIQUID METAL COOLED REACTORS; NUCLEAR FUELS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS