Preliminary evaluation of waste package releases using drift-scale thermo-hydrologic analyses
Creators
- 1. M ampersand O/INTERA, Austin, TX (United States)
Description
In a 1993 performance assessment, the uncertainty associated with using panel-scale thermo-hydrologic analyses to define the near-field environment in the vicinity of the waste packages was identified as one of the major factors impacting the predicted performance. This was because of the impact of the thermo-hydrologic regime on the initiation of aqueous corrosion as well as the rate of corrosion, rate of waste form dissolution (due to the uncertainty in the percent of the waste form surface covered by water film), solubility limits, and the effective diffusion through the waste package and engineered barrier. This document presents an initial attempt to incorporate, in a more representative fashion, the anticipated thermo-hydrologic response in the vicinity of in-drift emplaced waste packages into the post-closure performance assessment. It illustrates some of the issues which must be resolved prior to justifying the inclusion of these representations into the assessment
Additional details
Publishing Information
- Publisher
- American Nuclear Society, Inc.; American Society of Civil Engineers.
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Title
- High level radioactive waste management: Proceedings
- Imprint Pagination
- 811 p.
- Journal Page Range
- p. 319-322.
Conference
- Title
- 6. annual international conference on high level radioactive waste management.
- Dates
- 30 Apr - 5 May 1995.
- Place
- Las Vegas, NV (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27037405
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S58: GEOSCIENCES; S54: ENVIRONMENTAL SCIENCES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBON 14; CONTAINERS; CORROSION; FISSION PRODUCT RELEASE; HIGH-LEVEL RADIOACTIVE WASTES; LEAD 210; NEPTUNIUM 237; PERFORMANCE; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE FACILITIES; TECHNETIUM 99; UNDERGROUND FACILITIES; YUCCA MOUNTAIN
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CARBON ISOTOPES; CHEMICAL REACTIONS; EVEN-EVEN NUCLEI; HEAVY NUCLEI; HOURS LIVING RADIOISOTOPES; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; LEAD ISOTOPES; LIGHT NUCLEI; MANAGEMENT; MATERIALS; MOUNTAINS; NANOSEC LIVING RADIOISOTOPES; NEPTUNIUM ISOTOPES; NUCLEAR FACILITIES; NUCLEI; ODD-EVEN NUCLEI; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOISOTOPES; SPONTANEOUS FISSION RADIOISOTOPES; TECHNETIUM ISOTOPES; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- CONF-9504179--.