Repository simulation tests
Description
The repository simulation experiments described in this paper are designed to assess the performance of SRP waste glass under the most realistic repository conditions that can be obtained in the laboratory. These tests simulate the repository environment as closely as possible and introduce systematically the variability of the geology, groundwater chemistry, and waste package components during the leaching of the waste glass. The tests evaluate waste form performance under site-specific conditions, which differ for each of the geologic repositories under consideration. Data from these experiments will aid in the development of a realistic source term that can describe the release of radionuclides from SRP waste glass as a component of proposed waste packages. Hence, this information can be useful to optimize waste package design for SRP waste glass and to provide data for predicting long-term performance and subsequent conformance to regulations. The repository simulation tests also help to bridge the gap in interpreting results derived from tests performed under the control of the laboratory to the uncertainity and variability of field tests. In these experiments, site-specific repository components and conditions are emphasized and only the site specific materials contact the waste forms. An important feature of these tests is that both actual and simulated waste glasses are tested identically. 7 figures, 2 tables
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE84015770.
Files
Additional details
Publishing Information
- Imprint Pagination
- 17 p.
- Report number
- DP-MS--83-138
Conference
- Title
- 86. annual meeting and exposition of the American Ceramic Society.
- Dates
- 29 Apr - 3 May 1984.
- Place
- Pittsburgh, PA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16015222
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BORON; BOROSILICATE GLASS; EXPERIMENTAL DATA; HIGH-LEVEL RADIOACTIVE WASTES; LEACHING; LITHIUM; PERFORMANCE; RADIOACTIVE WASTE DISPOSAL; SIMULATION; TUFF; WASTE-ROCK INTERACTIONS
- Descriptors DEC
- ALKALI METALS; DATA; DISSOLUTION; ELEMENTS; GLASS; IGNEOUS ROCKS; INFORMATION; MANAGEMENT; MATERIALS; METALS; NUMERICAL DATA; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; ROCKS; SEMIMETALS; SEPARATION PROCESSES; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES
Optional Information
- Secondary number(s)
- CONF-840440--4.