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AbstractAbstract
[en] The principles of management and disposal of highly radioactive wastes contained in spent fuel from nuclear power generation are described. The status of developments in spent fuel reprocessing, high-level waste solidificaton and geologic isolation is reviewed. Some generic studies on the possible range of annual radiological doses to individuals from waste repositories are discussed and compared with doses from some existing nuclear power and fuel cycle operations, and with the dose received annually from an average background of naturally occurring radiation
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Secondary Subject
Source
Oct 1982; 74 p
Record Type
Report
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BASALT, CLAYS, COST, GRANITES, HIGH-LEVEL RADIOACTIVE WASTES, LEACHING, MARINE DISPOSAL, NEPTUNIUM 237, RADIATION DOSES, RADIATION EFFECTS, RADIOACTIVE WASTE DISPOSAL, RADIOACTIVE WASTE PROCESSING, REPROCESSING, SAFETY, SALT DEPOSITS, SOLIDIFICATION, SPENT FUELS, STABILITY, SYNTHETIC ROCKS, UNDERGROUND DISPOSAL, VITRIFICATION, WASTE MANAGEMENT
ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, DISSOLUTION, ENERGY SOURCES, FUELS, GEOLOGIC DEPOSITS, HEAVY NUCLEI, IGNEOUS ROCKS, ISOTOPES, MANAGEMENT, MATERIALS, MINERALS, NEPTUNIUM ISOTOPES, NUCLEAR FUELS, NUCLEI, ODD-EVEN NUCLEI, RADIOACTIVE MATERIALS, RADIOACTIVE WASTES, RADIOISOTOPES, REACTOR MATERIALS, ROCKS, SEPARATION PROCESSES, WASTE DISPOSAL, WASTE PROCESSING, WASTES, YEARS LIVING RADIOISOTOPES
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