$sup 235$U DEPLETION AS A POTENTIAL INDEPENDENT CROSS-CHECK OF THE PLUTONIUM CONTENT OF SPENT POWER REACTOR FUELS.

Technical Report · Thu Jan 01 00:00:00 EST 1970

DOI:https://doi.org/10.2172/4088682· OSTI ID:4088682

Schneider, R. A.; Christensen, D. E.; Granquist, D. P.

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (United States)
• DOE Contract Number: AT(45-1)-1830
• NSA Number: NSA-25-004257
• OSTI ID: 4088682
• Report Number(s): BNWL-SA-3304; CONF-700541-1
• Resource Relation: Other Information: From 11th Annual Meeting of the Institute of Nuclear Materials Management, Gatlinburg, Tenn. UNCL. Orig. Receipt Date: 31-DEC-71
• Country of Publication: United States
• Language: English

Related Subjects

N24700* -Engineering-Radioactive Material Handling
BURNUP
CONTENT ANALYSIS
DEPLETED URANIUM
FISSIONABLE MATERIALS MANAGEMENT
FUELS
PLUTONIUM
URANIUM 235
YAEC
URANIUM ISOTOPES U-235/burnup in reactor fuels
use in determining plutonium content
PLUTONIUM/content in spent fuels
determination by uranium-235 depletion
REACTOR FUELS/plutonium content of spent
determinaton by uranium-235 depletion
NUCLEAR MATERIALS MANAGEMENT/method using uranium-235 depletion as cross-check on plutonium content of reactor fuels