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 24
... Gorleben 1 and Gorleben 2 in 1986. They have been sunken in the salt below the depth of 260 m and have now reached a depth of about 600 m . Beginning at a depth of 380 m , in a distance of ca. 100 m a special investigation program is ...
... Gorleben 1 and Gorleben 2 in 1986. They have been sunken in the salt below the depth of 260 m and have now reached a depth of about 600 m . Beginning at a depth of 380 m , in a distance of ca. 100 m a special investigation program is ...
Page 277
... Gorleben GmbH , Gorleben Federal Republic of Germany ABSTRACT The Status in 2/95 : The German back - end policy until mid '94 was primarily based on reprocessing . Direct disposal was an acceptable alternative only , when reprocessing ...
... Gorleben GmbH , Gorleben Federal Republic of Germany ABSTRACT The Status in 2/95 : The German back - end policy until mid '94 was primarily based on reprocessing . Direct disposal was an acceptable alternative only , when reprocessing ...
Page 768
... Gorleben working model . Boundaries of emplacement fields Boundaries of safety zones Anhydrite layers. safety zone to anhydrite / carnallitite , width 50m safety zone to anhydrite / carnallitite , width 100m shafts and safety pillars.r ...
... Gorleben working model . Boundaries of emplacement fields Boundaries of safety zones Anhydrite layers. safety zone to anhydrite / carnallitite , width 50m safety zone to anhydrite / carnallitite , width 100m shafts and safety pillars.r ...
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