Show simple item record

dc.contributor.advisorMichael J. Driscoll.en_US
dc.contributor.authorAnderson, Victoria Katherine, 1980-en_US
dc.contributor.otherMassachusetts Institute of Technology. Dept. of Nuclear Engineering.en_US
dc.date.accessioned2006-07-31T15:19:08Z
dc.date.available2006-07-31T15:19:08Z
dc.date.copyright2004en_US
dc.date.issued2004en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/33638
dc.descriptionThesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.en_US
dc.descriptionIncludes bibliographical references (leaves 117-119).en_US
dc.description.abstractDeep 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.en_US
dc.description.statementofresponsibilityby Victoria Katherine Anderson.en_US
dc.format.extent119 leavesen_US
dc.format.extent4209629 bytes
dc.format.extent4214589 bytes
dc.format.mimetypeapplication/pdf
dc.format.mimetypeapplication/pdf
dc.language.isoengen_US
dc.publisherMassachusetts Institute of Technologyen_US
dc.rightsM.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.en_US
dc.rights.urihttp://dspace.mit.edu/handle/1721.1/7582
dc.subjectNuclear Engineering.en_US
dc.titleAn evaluation of the feasibility of disposal of nuclear waste in very deep boreholesen_US
dc.typeThesisen_US
dc.description.degreeS.M.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineering
dc.identifier.oclc64393821en_US


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record