Published April 1981 | Version v1
Report Restricted

Dissolution of COPRECAL mixed-oxide fuel

Description

Conclusions based on this investigation of continuous coprecipitation-calcination (COPRECAL) mixed oxide (MOX) dissolution are as follows: (1) A large fraction of the COPRECAL MOX dissolved very rapidly in nitric acid alone. Appeoximately 95% of the powder tested dissolved in the first 5 to 6 minutes in boiling 8 to 12M nitric acid. The remainder dissolved much more slowly, with greater than 99% dissolved after 8 hours. The dissolution rate increased slightly as the nitric concentration was increased from 8 to 12M. (2) Of the fuel fabrication operations investigated, only the sintering operation had a significant effect on the dissolution rate. In tests with samples from a fuel fabrication run, the sintered pellet samples had approximately one-tenth as much residue remaining at the end of 6- and 12-hour tests in 12M nitric acid compared to the MOX powder starting material. (3) The presence of Pu and U in the nitric acid dissolvent had very little effect on the dissolution rate. In tests with Pu-U nitrate-nitric acid solution as the dissolvent, the final 5% of the COPRECAL sample dissolved slightly slower than it had in tests with nitric acid only as the dissolvent. (4) The plutonium-uranium ratio was higher in the final residue than in the starting material. At the end of a 6-hour dissolution test in 10M nitric acid the Pu-U ratio in the residue was 4 vs 0.25 in the starting material. (5) A final residue of undissolved oxide can be expected in the Wet Scrap Development Laboratory (WSDL) dissolver. As a way to minimize the buildup of undissolved MOX powder in the continuous dissolver, all scrap material could be subjected to high temperature sintering (e.g., approx. 17000C) prior to processing through WSDL

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.

Files

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Additional details

Publishing Information

Imprint Pagination
23 p.
Report number
HEDL-SA--2327

Conference

Title
American Nuclear Society's annual meeting.
Dates
7 - 12 Jun 1981.
Place
Miami Beach, FL, USA.

Optional Information

Secondary number(s)
CONF-810606--93.