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 254
... cask handling : Receipt of the incoming loaded or empty casks , dispatch of the outgoing casks and preparation of the casks for loading and unloading . Secondly preconditioning : Dry unloading of spent fuel from the cask at the lower ...
... cask handling : Receipt of the incoming loaded or empty casks , dispatch of the outgoing casks and preparation of the casks for loading and unloading . Secondly preconditioning : Dry unloading of spent fuel from the cask at the lower ...
Page 285
... casks of the type CASTOR BARRE were designed and fabricated to accommodate 12 such rods each . As a special feature , the cask is equipped with tritium getter material , so that in case of a possible release of tritium from the rods ...
... casks of the type CASTOR BARRE were designed and fabricated to accommodate 12 such rods each . As a special feature , the cask is equipped with tritium getter material , so that in case of a possible release of tritium from the rods ...
Page 335
... cask also incorporates a double - lid concept wherein the inner lid is identified as part of the cask containment or confinement shell . The outer lid provides an impact protector , shielding for operators , and a testable , monitorable ...
... cask also incorporates a double - lid concept wherein the inner lid is identified as part of the cask containment or confinement shell . The outer lid provides an impact protector , shielding for operators , and a testable , monitorable ...
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