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

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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.