Proceedings of the ... International Conference on Radioactive Waste Management and Environmental Remediation, Volume 1American Society of Mechanical Engineers, 1995 - Nuclear facilities |
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Page 427
... cesium and strontium from wastes of Hanford Site and Idaho National Engineering Laboratory with the use of solvent on the basis of chlorinated cobalt dicarbollide are carried out . Linear and liquid - membrane cascade flowsheets are ...
... cesium and strontium from wastes of Hanford Site and Idaho National Engineering Laboratory with the use of solvent on the basis of chlorinated cobalt dicarbollide are carried out . Linear and liquid - membrane cascade flowsheets are ...
Page 428
... cesium and strontium in raffinate , i.a. to more efficient recovery of cesium and strontium . The calculations have shown that in the case of INEL wastes the increase of nitric acid concentration in stripping solution from 2 to 8 mol ...
... cesium and strontium in raffinate , i.a. to more efficient recovery of cesium and strontium . The calculations have shown that in the case of INEL wastes the increase of nitric acid concentration in stripping solution from 2 to 8 mol ...
Page 466
... cesium and strontium from the acidic liquid waste simulant using the ChCoDiC process was 99.9 % and 99.6 % , respectively . Decontamination factors of cesium and strontium from inert alkali metals were 830 for sodium and 90 for ...
... cesium and strontium from the acidic liquid waste simulant using the ChCoDiC process was 99.9 % and 99.6 % , respectively . Decontamination factors of cesium and strontium from inert alkali metals were 830 for sodium and 90 for ...
Contents
VOLUME | 1 |
Evaluation of Possible Treatment of Solid Raw Containing Polymer with High Frequency Heating | 5 |
Volume ReductionPellet Handling PressSystems for Supercompaction of Dry Solid Low and Intermediate | 10 |
Copyright | |
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acid actinides activities americium assessment BNFL boreholes borosilicate glass burnup calculated CANDU canister cask cesium chemical composition concentration containing cost developed disposal facility disposition dose rate Energy environment environmental evaluation fissile materials fission fission products fuel assemblies fuel cycle fuel elements geological glass Gorleben groundwater Hanford heat high level HLLW IAEA impact interim storage ions irradiated Laboratory leaching level waste licensing loading measured melt melter ment metal monitoring MOX fuel neptunium neutron nuclear fuel nuclear power nuclide operation options oxide Pantex parameters performed phase plant plutonium potential production radiation radionuclides radwaste reactor recycling regulatory release repository reprocessing requirements risk ruthenium safety salt salt dome samples scenario simulated solution spent fuel surface Table tank technical temperature tion transport tritium uranium vitrified Waste Management waste packages weapons