Development of `DUCRETE`
Author(s) -
Paul A. Lessing
Publication year - 1995
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/366558
Subject(s) - uranium , depleted uranium , interim , uranium oxide , waste management , radioactive waste , portland cement , spent nuclear fuel , electromagnetic shielding , environmental science , aggregate (composite) , high level waste , nuclear engineering , cement , engineering , materials science , metallurgy , composite material , archaeology , history
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
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