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 201
... assessment and risk management must be clearly separated . The reduction in potential life expectancy ( RIPLE ) may ... assessment , as used by EPA , is significantly different with respect to exposure assess- ment as defined by ...
... assessment and risk management must be clearly separated . The reduction in potential life expectancy ( RIPLE ) may ... assessment , as used by EPA , is significantly different with respect to exposure assess- ment as defined by ...
Page 203
Risk Assessment Figure 2 describes the components of risk assessment ( 6 ) . The steps described in Fig . 1 are likely to become accepted by all U.S. agencies . The engineering profession , as represented by ASME and the American ...
Risk Assessment Figure 2 describes the components of risk assessment ( 6 ) . The steps described in Fig . 1 are likely to become accepted by all U.S. agencies . The engineering profession , as represented by ASME and the American ...
Page 217
... assessment used the SYVAC executive computer code coupled to repository assessment models based on those devel- oped to assess the disposal of spent CANDU fuel ( 8 ) and adapted to SNL AGR fuel . Assessment Model The repository assessment ...
... assessment used the SYVAC executive computer code coupled to repository assessment models based on those devel- oped to assess the disposal of spent CANDU fuel ( 8 ) and adapted to SNL AGR fuel . Assessment Model The repository assessment ...
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