Demonstration of a performance assessment methodology for high-level radioactive waste disposal in basalt formations
Description
This document describes a performance assessment methodology developed for a high-level radioactive waste repository mined in deep basalt formations. This methodology is an extension of an earlier one applicable to bedded salt. The differences between the two methodologies arise primarily in the modeling of round-water flow and radionuclide transport. Bedded salt was assumed to be a porous medium, whereas basalt formations contain fractured zones. Therefore, mathematical models and associated computer codes were developed to simulate the aforementioned phenomena in fractured media. The use of the methodology is demonstrated at a hypothetical basalt site by analyzing seven scenarios: (1) thermohydrological effects caused by heat released from the repository, (2) mechanohydrological effects caused by an advancing and receding glacier, (3) normal ground-water flow, (4) pumping of ground water from a confined aquifer, (5) rerouting of a river near the repository, (6) drilling of a borehole through the repository, and (7) formation of a new fault intersecting the repository. The normal ground-water flow was considered the base-case scenario. This scenario was used to perform uncertainty and sensitivity analyses and to demonstrate the existing capabilities for assessing compliance with the ground-water travel time criterion and the containment requirements. Most of the other scenarios were considered perturbations of the base case, and a few were studied in terms of changes with respect to initial conditions. The potential impact of these scenarios on the long-term performance of the disposal system was ascertained through comparison with the base-case scenario or the undisturbed initial conditions. 66 refs., 106 figs., 27 tabs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A09/MF A01 - US Govt. Printing Office. - OSTI as TI89014153.
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Additional details
Publishing Information
- Imprint Pagination
- 180 p.
- Report number
- NUREG/CR--4759
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20072625
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- BASALT; EVALUATION; FLOW RATE; GROUND WATER; HIGH-LEVEL RADIOACTIVE WASTES; MATHEMATICAL MODELS; PERFORMANCE TESTING; PLANNING; RADIOACTIVE WASTES; UNDERGROUND DISPOSAL; WASTE MANAGEMENT
- Descriptors DEC
- HYDROGEN COMPOUNDS; IGNEOUS ROCKS; MANAGEMENT; MATERIALS; OXYGEN COMPOUNDS; POLAR SOLVENTS; RADIOACTIVE MATERIALS; ROCKS; SOLVENTS; TESTING; WASTE DISPOSAL; WASTES; WATER
Optional Information
- Secondary number(s)
- SAND--86-2325.