High Level Radioactive Waste Management: Proceedings of the International Topical Meeting, Bände 1-2American Nuclear Society, 1992 |
Inhalt
Design and Licensing of the VSC Dry Fuel Storage System | 1216 |
Universal StorageTransportDisposal Packages | 1231 |
ASME Pressure Vessel Code Application to Nuclear Waste Container Design | 1244 |
Urheberrecht | |
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Häufige Begriffe und Wortgruppen
accident actinides activities ALMR analysis calcite calculated canister cask Civilian Radioactive Waste components concept container corrosion cost Department of Energy diffusion effective engineering environment environmental estimated evaluation excavation facility Figure fission products function geologic glass human factors impact increase initial issues limited materials National Laboratory neutron Nevada nuclear power Nuclear Waste Nye County OCRWM operations oxidation parameters performance assessment phase planning potential Radioactive Waste Radioactive Waste Management radionuclides reactor regulatory release repository reprocessing requirements rock safety samples Sandia National Laboratories scenarios schedule shipments simulation solubility solution spent fuel spent nuclear fuel storage strategy surface Table technetium technical temperature throughput transuranics tuff U.S. Department uranium validation values waste containers waste form Waste Management waste package Yucca Mountain