Development of `DUCRETE`

Technical Report · Tue Feb 28 23:00:00 EST 1995

DOI:https://doi.org/10.2172/366558· OSTI ID:366558

Lessing, P A

This interim report covers theoretical and experimental aspects of a series of scoping tests using depleted uranium oxide pieces as aggregate in portland cement to form concrete (DUCRETE). DUCRETE is expected to provide a high integrity material suitable for shielding in spent nuclear fuel containers or for direct disposal in a low- level waste repository. The uranium oxide would produced by conversion of depleted UF{sub 6} stored by the Department of Energy.

• Research Organization: Idaho National Engineering Lab., Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC07-94ID13223
• OSTI ID: 366558
• Report Number(s): INEL--94/0029; ON: DE96014148
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
36 MATERIALS SCIENCE
AGGLOMERATION
BASALT
CEMENTS
COMPRESSIBILITY
CONCRETES
CURING
DEPLETED URANIUM
EXPERIMENT PLANNING
EXPERIMENTAL DATA
LOW-LEVEL RADIOACTIVE WASTES
MATERIALS TESTING
RADIOACTIVE WASTE DISPOSAL
SHIELDING
SPENT FUEL CASKS
SPENT FUEL STORAGE
TENSILE PROPERTIES
URANIUM DIOXIDE
URANIUM HEXAFLUORIDE