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 295
... CANDU , some environmental benefits that would be anticipated from DUPIC fuel cycle are analyzed in terms of radwaste arisings , spent fuel arisings as well as radiotoxicity of spent fuel to be disposed of . For comparative purpose ...
... CANDU , some environmental benefits that would be anticipated from DUPIC fuel cycle are analyzed in terms of radwaste arisings , spent fuel arisings as well as radiotoxicity of spent fuel to be disposed of . For comparative purpose ...
Page 297
... CANDU c ) Reactor mix ratio of PWR to CANDU d ) Mass of heavy metal that contains in spent PWR fuel discharged from 1.7 units e ) Discharge burnup of natural U - CANDU fuel is 7.3 MWd / kgHM ( once - through ) PWR Fuel Rods Cut to Size ...
... CANDU c ) Reactor mix ratio of PWR to CANDU d ) Mass of heavy metal that contains in spent PWR fuel discharged from 1.7 units e ) Discharge burnup of natural U - CANDU fuel is 7.3 MWd / kgHM ( once - through ) PWR Fuel Rods Cut to Size ...
Page 477
... CANDU and LWR spent fuel are subject to the same stringent IAEA safeguard standards which are developed to recognize different shapes and sizes of fuel . The spent MOX fuel from a CANDU reactor has very similar characteristics as ...
... CANDU and LWR spent fuel are subject to the same stringent IAEA safeguard standards which are developed to recognize different shapes and sizes of fuel . The spent MOX fuel from a CANDU reactor has very similar characteristics as ...
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