Abstract
Samples of Boom Clay, a potential host formation for radioactive waste, have been irradiated either in the γ-field of spent fuel or by the α-radiation of 241Am. Hydrogen gas is released as well as an equivalent quantity of oxygen which is readily consumed by the reducing clay. Marked differences are observed though for the two radiations and the α radiolysis seems to be very dependent on the dose rate. Since Boom Clay undergoes deep alterations when exposed to air a question is raised concerning the consequences of a radiolytic oxidation on the sorptive properties of that clay and on its eventual acidification. Pu, Eu and even TC remain strongly sorbed under γ-irradiation. Recommendations are made about the manner to continue the study.
Original language | English |
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Pages (from-to) | 41-60 |
Number of pages | 20 |
Journal | Radioactive waste management and the nuclear fuel cycle |
Volume | 11 |
Issue number | 1 |
State | Published - 1988 |
ASJC Scopus subject areas
- General Medicine