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 353
RECENT RESULTS OF THE CHARACTERIZATION OF BOROSILICATE GLASS PRODUCTS FOR WAK - HLLW VITRIFICATION A.K. De , W. Verachtert WAK , C / O Belgoprocess N.V. ... Borosilicate Glass Products for WAK-HLLW Vitrification A K De and W Verachtert.
RECENT RESULTS OF THE CHARACTERIZATION OF BOROSILICATE GLASS PRODUCTS FOR WAK - HLLW VITRIFICATION A.K. De , W. Verachtert WAK , C / O Belgoprocess N.V. ... Borosilicate Glass Products for WAK-HLLW Vitrification A K De and W Verachtert.
Page 570
... Borosilicate Glass Monoliths Glass Glass High Silica Glass Phosphate Glass Glass - Ceramic Monoliths Iron - enriched Basalt Metallic Alloys Ceramic in Concrete Ceramic Pellets in Metal Matrix Cermet Glass Glass - Ceramic Glass - Ceramic ...
... Borosilicate Glass Monoliths Glass Glass High Silica Glass Phosphate Glass Glass - Ceramic Monoliths Iron - enriched Basalt Metallic Alloys Ceramic in Concrete Ceramic Pellets in Metal Matrix Cermet Glass Glass - Ceramic Glass - Ceramic ...
Page 571
... Glass frit Recycle waste nuclear poison PuO2 Size reduction Metal oxidation Weld canister Off - gas treatment To ... borosilicate glass is shown in Fig . 4. In this process , the gamma 137 radiation field is assumed to be provided ...
... Glass frit Recycle waste nuclear poison PuO2 Size reduction Metal oxidation Weld canister Off - gas treatment To ... borosilicate glass is shown in Fig . 4. In this process , the gamma 137 radiation field is assumed to be provided ...
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