IN-PILE LOOP STUDY OF UO$sub 2$-NaK SLURRY

Journal Article · Wed Jun 01 04:00:00 EDT 1960 · Nuclear Sci. and Eng.

OSTI ID:4157013

Carlson, R D

The effect of fission on circulating a UO/sub 2/-NaK suspension was studied up to a total uranium burnup of 0.07%. A loop of one-half inch stainless steel tubing with a test volume of 250 cc was irradiated in the Argonne CP-5 reactor. The loop contained 5 vol.% (40 wt.%), 93.14% enriched UO/sub 2/ suspended in NaK alloy and was operated for 902 hr at temperatures above 350 deg C. No difficulty was encountered during the operation of the loop in the reactor. Examination of the slurry after irradiation showed extensive comminution of the UO/sub 2/ particles. Analytical results after termination of the experiment revealed the distribution of some fission products. 45.5% of the krypton and xenon fission gases were found in the cover gas. 82% of the cesium was found dissolved in the NaK. Cerium and zirconium were found with the UO/sub 2/. (auth)

• Research Organization: Argonne National Lab., Ill.
• NSA Number: NSA-14-018205
• OSTI ID: 4157013
• Journal Information: Nuclear Sci. and Eng., Journal Name: Nuclear Sci. and Eng. Vol. Vol: 7
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BURNUP
CERIUM
CESIUM
CP-5
DISTRIBUTION
FISSION PRODUCTS
FUEL SLURRIES
GRAIN SIZE
IN PILE LOOPS
IRRADIATION
KRYPTON
METALS, CERAMICS, AND OTHER MATERIALS
POTASSIUM ALLOYS
REACTORS
SODIUM ALLOYS
SOLUBILITY
STAINLESS STEELS
SUSPENSIONS
TEMPERATURE
TESTING
THICKNESS
TUBES
URANIUM
URANIUM DIOXIDE
VOLUME
XENON
ZIRCONIUM