Critical mass experiment using U-235 foils-SiO{sub 2}-polyethylene plates

Technical Report · Thu Dec 31 00:00:00 EST 1998

DOI:https://doi.org/10.2172/334338· OSTI ID:334338

Sanchez, R; Kimpland, R; Butterfield, K; Jaegers, P; Casson, W

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 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 assure the correctiveness of the calculations for those systems containing fissile material (U-235, U-233, and Pu-239) in contact with matrix material (Al{sub 2}O{sub 3}, CaO, MgO, and SiO{sub 2}) in the drums. The purpose of the U-235 foil-SiO{sub 2}-polyethylene experiment is to provide experimental data to validate the computer transport codes and the cross section data.

• Research Organization: Los Alamos National Lab., NM (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 334338
• Report Number(s): LA-UR--98-3297; CONF-981106--; ON: DE99002274
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
42 ENGINEERING
ALUMINIUM OXIDES
CALCIUM OXIDES
COMPUTER CODES
CRITICAL MASS
CRITICALITY
EXPERIMENTAL DATA
MAGNESIUM OXIDES
MATRIX MATERIALS
Nuclear Criticality Safety Program (NCSP)
PLUTONIUM 239
POLYETHYLENES
RADIOACTIVE WASTES
SILICON OXIDES
STORAGE FACILITIES
URANIUM 233
URANIUM 235
VALIDATION