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 762
... boreholes ( Fig . 2 ) are differentiated as boreholes of type A and type B , respectively ( see gallery desig- nation ) . In the borehole of type A the annulus between the liner and the borehole wall was backfilled with ceramic alumina ...
... boreholes ( Fig . 2 ) are differentiated as boreholes of type A and type B , respectively ( see gallery desig- nation ) . In the borehole of type A the annulus between the liner and the borehole wall was backfilled with ceramic alumina ...
Page 763
... boreholes A1 and B1 . Figure 1 shows the tent drifts and the boreholes drifted for the installation of geotechnical measurement instruments . Though the radioactive canisters were never emplaced into the boreholes because of the ...
... boreholes A1 and B1 . Figure 1 shows the tent drifts and the boreholes drifted for the installation of geotechnical measurement instruments . Though the radioactive canisters were never emplaced into the boreholes because of the ...
Page 792
... borehole and / or in the surrounding rock mass provided a hydrau- lic short circuit in most boreholes . The 19 small diameter bore- holes ( 50 to 80 mm ) served only as observation and sampling boreholes . Three boreholes tapped and so ...
... borehole and / or in the surrounding rock mass provided a hydrau- lic short circuit in most boreholes . The 19 small diameter bore- holes ( 50 to 80 mm ) served only as observation and sampling boreholes . Three boreholes tapped and so ...
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