Scientific basis for nuclear waste management XVII
- ed.; Catholic Univ. of America, Washington, DC (United States)
- ed.; Lawrence Livermore National Lab., CA (United States)
The 17th Materials Research Society Symposium on the Scientific Basis for Nuclear Waste Management included 17 sessions, during which 120 papers were presented by scientists from 16 countries. The nuclear waste glass overview surveyed achievements to date and identified issues requiring further research. The objectives and limitations session noted the progress that has been made in developing a scientific basis for nuclear waste management, but questioned whether regulations calling for detailed predictions over a period of 10,000 years are either necessary or capable of being satisfied. The other papers presented at the Symposium described the progress of studies in a broad array of areas of nuclear waste science and technology. These areas included radiation effects and gas generation, ceramic materials, cementitious materials, actinides spent fuel, glass processing and properties, glass leaching, dissolution and alteration, natural and ancient analogues, transuranic wastes and special topics, sorption mechanisms, repository studies, geochemistry and hydrology, containers, and backfill materials. Several novel experimental techniques were described, as well as advances in modeling. An encouraging feature of the progress in modeling is that the agreement between calculated results based on models developed, refined and tested in the US and in other countries on one hand, and experimental data on the other, shows considerable improvement. This reflects greater understanding of the mechanisms involved in the release of radionuclides from the various components of the waste repository system, including the wasteforms themselves. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.
- Sponsoring Organization:
- USDOE, Washington, DC (United States); Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 25014
- Report Number(s):
- CONF-931108-Vol.333; ISBN 1-55899-232-4; TRN: 95:007093
- Resource Relation:
- Conference: Fall meeting of the Materials Research Society (MRS), Boston, MA (United States), 29 Nov - 3 Dec 1993; Other Information: PBD: 1994; Related Information: Materials Research Society symposium proceedings, Volume 333
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
RADIOACTIVE WASTE DISPOSAL
MEETINGS
RADIOACTIVE WASTE PROCESSING
LEADING ABSTRACT
WASTE FORMS
PERFORMANCE TESTING
MATERIALS TESTING
RADIOLYSIS
SPENT FUELS
HIGH-LEVEL RADIOACTIVE WASTES
RADIONUCLIDE MIGRATION
RADIOACTIVE WASTE FACILITIES
UNDERGROUND DISPOSAL
SITE CHARACTERIZATION
MATHEMATICAL MODELS
VITRIFICATION
WEATHERING
CORROSION
SALT CAVERNS
WIPP
ZEOLITES
CEMENTS
DISSOLUTION
LEACHING
SORPTION
ION EXCHANGE
YUCCA MOUNTAIN
GROUND WATER
BACKFILLING
Yucca Mountain Project