Scientific Basis for Nuclear Waste Management: Volume 3John G. Moore The third International Symposium on the Scientific Basis for Nuclear Waste Management was held in Boston, Massachusetts, on November 17-20, 1980, as part of the Annual Meeting of the Materials Research Society. The purpose of this Symposium was to provide an interdisciplinary forum for the discussion of scientific research dealing with all levels and types of radioactive wastes and their management. Since its inception in 1978, this annual Symposium has provided a unique opportunity for scientists of widely differing backgrounds to share in such discussions. The proceedings of the first two meetings were published as Volumes 1 and 2 in this series. The fourth Symposium is scheduled to be held in the autumn of 1981. The efforts of many people went into making this meeting a success. The scope of the 1980 Symposium was guided by the follow ing Steering Committee: K. J. Notz (Chairman), Oak Ridge National Laboratory, USA G. H. Daly, Department of Energy, USA D. E. Ferguson, Oak Ridge National Laboratory, USA R. H. Flowers, Atomic Energy Research Establishment, UK F. Girardi, Ispra Establishment, Italy T. Ishihara, Radioactive Waste Management Center, Japan R. W. Lynch, Sandia Laboratories, USA S. A. Mayman, Atomic Energy of Canada Ltd. , Canada G. J. McCarthy, North Dakota State University, USA E. Merz, Kernforschunganlage Jillich, FRG L. Nilsson, KBS Project, Sweden D. M. Rohrer, Nuclear Regulatory Commission, USA R. Roy, Pennsylvania State University, USA T. "E. Scott, Ames Laboratory, USA C. |
Contents
DEVELOPMENT OF REFERENCE CONDITIONS FOR GEOLOGIC | 1 |
BASALT WASTE ISOLATION PROJECT DATA PACKAGE | 11 |
EVALUATION OF PRODUCT SPECIFICATIONS WITH A SAFETY | 19 |
Copyright | |
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a-recoil actinide amorphous analysis backfill basalt batch bentonite borosilicate glass brine calculated canister ceramic cesium chemical CHLW clay coefficient column composition concentration containing corrosion crystal crystalline deionized water density diffusion dissolution dose effects elements elution Energy engineered barrier environment evaluated flow fluid formation fracture geologic granite groundwater Hanford heat hole hollandite hydration immobilization increase irradiation LaPO4 layer leach rates leach test leachability leachate loading materials measured metamict minerals ml/g monazite NaCl nepheline Nuclear Waste Nuclear Waste Management nuclides obtained oxide parameters particles perovskite phases pollucite porous pressure radiation radioactive waste radionuclides radiophase release repository rock salt samples shown shows silica simulated sintering sludge sodium solid solubility solution sorption spent fuel spinel stability storage structure studies surface SYNROC Table temperature thermal tion tracer tuff uranium values waste forms waste glass WIPP x-ray zeolite Zircaloy zirconolite