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- W4229575907 abstract "Sr). Irradiation with /sup 60/Co gamma does not entirely duplicate the exposure of dried zeolite loaded with radioactive Cs and Sr, but only small differences in gas yields would be expected. An upper limit to the hydrogen produced may be calculated using reported radiolysis hydrogen yields. Using a G/sub H/sub 2// value of 0.015 for zeolite loaded to 60,000 Ci of Cs and Sr and 3 wt. % water, calculations indicate the total H/sub 2/ generation in an unvented liner after 14 days (maximum shipping time from TMI to PNL) would be approx. 13 L. Based on these data, the system described for the in-situ drying of the zeolite contained in SDS liners is an acceptable method to prepare the zeolite for shipment under existing regulations. 4 figures, 4 tables." @default.
- W4229575907 created "2022-05-11" @default.
- W4229575907 date "1982-01-01" @default.
- W4229575907 modified "2023-09-28" @default.
- W4229575907 title "Risk assessment for the transportation of radioactive zeolite liners" @default.
- W4229575907 doi "https://doi.org/10.2172/5295817" @default.
- W4229575907 hasPublicationYear "1982" @default.
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