EXPERIMENTAL STUDY OF THE DISSOLUTION RATES OF A SIMULATED BOROSILICATE WASTE GLASS AS A FUNCTION OF pH AND TEMPERATURE

摘要

The Hanford Site in southeastern Washington state has been used extensively to produce nuclear materials for the U.S.strategic defense arsenal by the U.S.Department of Energy(DOE).A large inventory of radioactive waste has been accumulated in 177 buried single and double-shell tanks.Currently,DOE plans to immobilize a portion of the high-level and low-activity radioactive waste being stored at the Hanford Site into a vitrified matrix(i.e.,glass).The glasses made from the waste at Hanford will be disposed of at two U.S.locations:(1)the low-activity waste glass will be stored on site at the integrated disposal facility and(2)the high-level waste glass will be disposed of at the proposed mined geologic repository in Yucca Mountain,Nevada.