An assessment of overseas developments in methods for treatment and disposal of high-level radioactive wastes

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dc.contributor.authorCostello, JMen_AU
dc.contributor.authorWilson, EGen_AU
dc.date.accessioned2007-11-22T04:18:06Zen_AU
dc.date.accessioned2010-04-30T04:33:02Zen_AU
dc.date.available2007-11-22T04:18:06Zen_AU
dc.date.available2010-04-30T04:33:02Zen_AU
dc.date.issued1982-10en_AU
dc.description.abstractThe 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.en_AU
dc.identifierAAEC-E-550en_AU
dc.identifier.citationCostello, J. M., Wilson, E. G. (1982). An assessment of overseas developments in methods for treatment and disposal of high-level radioactive wastes. (AAEC/E550). Lucas Heights, NSW: Australian Atomic Energy Commission Research Establishment, Lucas Heights Research Laboratories.en_AU
dc.identifier.govdoc370en_AU
dc.identifier.isbn0642597529en_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/269en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectRadioactive waste disposalen_AU
dc.subjectRadioactive waste processingen_AU
dc.subjectRadioactive wastesen_AU
dc.subjectSolidificationen_AU
dc.subjectLeachingen_AU
dc.subjectSynthetic rocksen_AU
dc.titleAn assessment of overseas developments in methods for treatment and disposal of high-level radioactive wastesen_AU
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