Scientific basis for nuclear waste management XXX: symposium held November 27-December 1, 2006, Boston, Massachusetts, U.S.A.
Materials Research Society, Jan 1, 2007 - Technology & Engineering - 642 pages
Management of nuclear waste remains an important international topic that includes reprocessing of commercial nuclear fuel, waste-form design and development, storage and disposal packaging, the process of repository site selection, system design, and performance assessment. Requirements to manage and dispose of materials from the production of nuclear weapons, and the renewed interest in nuclear power, in particular through the Generation IV Forum and the Advanced Fuel Cycle Initiative, can be expected to increase the need for scientific advances in waste management. This book offers an interdisciplinary perspective on materials-related issues associated with nuclear waste management programs. Invited and contributed papers cover a wide range of topics including studies on: spent fuel; performance assessment and models; waste forms for low- and intermediate-level waste; ceramic and glass waste forms for plutonium and high-level waste; radionuclides; containers and engineered barriers; disposal environments and site characteristics; and partitioning and transmutation.
72 pages matching Laboratory in this book
Results 1-3 of 72
What people are saying - Write a review
We haven't found any reviews in the usual places.
Corrosion of Nuclear Fuel Inside a Failed Copper Nuclear
Alteration Behavior of High Burnup Spent Fuel in Salt
Chemical Effects at the Reaction Front in Corroding Spent
76 other sections not shown
2007 Materials Research actinides Alloy 22 alteration analysis aqueous atoms Basis for Nuclear bentonite Boom Clay bubbles calcium calculated cell ceramics cerium chemical chloride coffinite composition concentration containing crevice corrosion density diffusion coefficient disposal dissolution dose electron elements energy environment experimental experiments Figure fission products fluorite fraction geological glass groundwater Gubka helium immobilisation increase interface irradiation Laboratory leach rates Materials Research Society matrix minerals murataite neptunium Nucl nuclear fuel Nuclear Waste Nuclear Waste Management oxidation oxygen parameters particles pellets perovskite phases phosphate plutonium polytype pore porosity potential powder precipitation present Proc processes pyrochlore radioactive waste radionuclides ratio reactor redox release repository shows simulated sintered solid solubility solution specimens spent fuel structure studtite surface Symp Table temperature tests uranium uranyl values VHT samples waste form Waste Management waste packages X-ray Yucca Mountain zirconolite