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Title: Critical mass experiment using {sup 235}U foil-SiO{sub 2}-polyethylene plates

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:298317

Fissile material in waste is frequently encountered in decontamination and decommissioning activities. Thousands of drums containing radioactive waste are stored in storage facilities throughout the US Department of Energy (DOE) complex. The amount of fissile material in each drum is generally small because of the criticality safety limits that have been calculated using neutron transport computer codes such as MCNP, KENO, or ONEDANT. No experimental critical data are available to ensure the correctness of the calculations for those systems containing fissile material ({sup 235}U, {sup 233}U, and {sup 239}Pu) in contact with matrix material (Al{sub 2}O{sub 3}, CaO, MgO, and SiO{sub 2}) in the drums. The purpose of the {sup 235}U foil-SiO{sub 2}-polyethylene experiment is to provide experimental data to validate the computer transport codes and the cross-section data.

OSTI ID:
298317
Report Number(s):
CONF-981106-; ISSN 0003-018X; TRN: 99:001948
Journal Information:
Transactions of the American Nuclear Society, Vol. 79; Conference: American Nuclear Society winter meeting, Washington, DC (United States), 15-19 Nov 1998; Other Information: PBD: 1998
Country of Publication:
United States
Language:
English