Proceedings of the International Symposium on the Management of Wastes from the LWR Fuel Cycle: Held at the Denver Hilton Hotel, Denver, Colorado, July 11-16, 1976National Technical Information Service, U.S. Department of Commerce, 1976 - Nuclear fuels - 759 pages |
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Page 610
... smectite , ~ 20 % ; mixed illite / montmorillonite layer , ~ 15 % ; vermiculite , ~ 30 % ; chlorite plus mixed chlorite / vermiculite layer , ~ 10 % . 3. The plasticity index is remarkably constant , between 40 and 45 % . 4. There is a ...
... smectite , ~ 20 % ; mixed illite / montmorillonite layer , ~ 15 % ; vermiculite , ~ 30 % ; chlorite plus mixed chlorite / vermiculite layer , ~ 10 % . 3. The plasticity index is remarkably constant , between 40 and 45 % . 4. There is a ...
Contents
RADIOACTIVE WASTE MANAGEMENT IN THE UNITED KINGDOM | 12 |
THE FRENCH PROGRAM | 18 |
WolfJ SchmidtKuster | 28 |
53 other sections not shown
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acceptable activity addition Administration Agency alternative application Atomic Energy calciner canisters capacity chemical concentration concept considered container continuous cost criteria decontamination demonstration discussed disposal dose effects elements Energy environment environmental equipment ERDA estimated evaluation existing experience exposure facility factors Federal filters final fission formations fuel cycle future geologic glass heat high-level waste important increase industry International Laboratory limited liquid materials measurements melting metal methods natural nuclear power operation organic packaging period planned plant plutonium possible potential present problem Protection radiation radioactive waste reactor regulations release removal Report repository reprocessing Research and Development rock safety salt separation shielding shipped solid solidified solution spent standards storage studies surface Table technical temperature transport treatment tritium United uranium volume waste management