An evaluation of the feasibility of disposal of nuclear waste in very deep boreholes
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.
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Format: | Thesis |
Language: | eng |
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Massachusetts Institute of Technology
2006
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Online Access: | http://hdl.handle.net/1721.1/33638 |
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author | Anderson, Victoria Katherine, 1980- |
author2 | Michael J. Driscoll. |
author_facet | Michael J. Driscoll. Anderson, Victoria Katherine, 1980- |
author_sort | Anderson, Victoria Katherine, 1980- |
collection | MIT |
description | Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004. |
first_indexed | 2024-09-23T13:20:03Z |
format | Thesis |
id | mit-1721.1/33638 |
institution | Massachusetts Institute of Technology |
language | eng |
last_indexed | 2024-09-23T13:20:03Z |
publishDate | 2006 |
publisher | Massachusetts Institute of Technology |
record_format | dspace |
spelling | mit-1721.1/336382022-01-25T21:37:25Z An evaluation of the feasibility of disposal of nuclear waste in very deep boreholes Anderson, Victoria Katherine, 1980- Michael J. Driscoll. Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Massachusetts Institute of Technology. Department of Nuclear Engineering Massachusetts Institute of Technology. Department of Nuclear Science and Engineering Nuclear Engineering. Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004. Includes bibliographical references (leaves 117-119). Deep boreholes, 3 to 5 km into igneous rock, such as granite, are evaluated for next- generation repository use in the disposal of spent nuclear fuel and other high level waste. The primary focus is on the stability and solubility of waste species, waste forms, and canister materials in saline, anoxic water, which is the most severe potential downhole environment given the sparse data available. Pourbaix (Eh-pH) diagrams and solubility products were calculated for 20 materials of interest. In general, extremely low dissolved concentrations were estimated. Copper was identified as the best canister material. Wall-to-far-field temperature increases were estimated to be about 20⁰ C for canisters containing two PWR assemblies, which is quite tolerable. Aspects requiring further work in the near term are detailed canister interior design to withstand crushing under a 1 km stack of same, and development of a borehole plug concept having a comparable or better impermeability and radionuclide holdup than the surrounding granite bedrock. by Victoria Katherine Anderson. S.M. 2006-07-31T15:19:08Z 2006-07-31T15:19:08Z 2004 2004 Thesis http://hdl.handle.net/1721.1/33638 64393821 eng M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission. http://dspace.mit.edu/handle/1721.1/7582 119 leaves 4209629 bytes 4214589 bytes application/pdf application/pdf application/pdf Massachusetts Institute of Technology |
spellingShingle | Nuclear Engineering. Anderson, Victoria Katherine, 1980- An evaluation of the feasibility of disposal of nuclear waste in very deep boreholes |
title | An evaluation of the feasibility of disposal of nuclear waste in very deep boreholes |
title_full | An evaluation of the feasibility of disposal of nuclear waste in very deep boreholes |
title_fullStr | An evaluation of the feasibility of disposal of nuclear waste in very deep boreholes |
title_full_unstemmed | An evaluation of the feasibility of disposal of nuclear waste in very deep boreholes |
title_short | An evaluation of the feasibility of disposal of nuclear waste in very deep boreholes |
title_sort | evaluation of the feasibility of disposal of nuclear waste in very deep boreholes |
topic | Nuclear Engineering. |
url | http://hdl.handle.net/1721.1/33638 |
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