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 93
CLEARANCE OF SLIGHTLY RADIOACTIVE MATERIAL FROM RADIOLOGICAL CONTROL IN GERMANY S. Thierfeldt Brenk Systemplanung Aachen , Germany ABSTRACT - Clearance from radiological control of slightly radioactive material arising from operation or ...
CLEARANCE OF SLIGHTLY RADIOACTIVE MATERIAL FROM RADIOLOGICAL CONTROL IN GERMANY S. Thierfeldt Brenk Systemplanung Aachen , Germany ABSTRACT - Clearance from radiological control of slightly radioactive material arising from operation or ...
Page 223
... radiological exposure of the operators in charge of spent fuel unloading , the radiological exposure is limited to 0.33 mSv / year / operator . For the transport itself , carriers expo- sure is approximately 0.5 mSv / year / operator ...
... radiological exposure of the operators in charge of spent fuel unloading , the radiological exposure is limited to 0.33 mSv / year / operator . For the transport itself , carriers expo- sure is approximately 0.5 mSv / year / operator ...
Page 568
... radiological barriers reduce availability for weapons use ELIMINATION Materials almost completely removed from human access USE Reactors - No processing required LWR CANDU MHTGE etc. DISPOSAL Immobilization Deep boreholes Underground ...
... radiological barriers reduce availability for weapons use ELIMINATION Materials almost completely removed from human access USE Reactors - No processing required LWR CANDU MHTGE etc. DISPOSAL Immobilization Deep boreholes Underground ...
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