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dc.contributor.advisorMichael J. Driscoll.en_US
dc.contributor.authorDozier, Frances Elizabethen_US
dc.contributor.otherMassachusetts Institute of Technology. Dept. of Nuclear Science and Engineering.en_US
dc.date.accessioned2013-02-14T15:20:18Z
dc.date.available2013-02-14T15:20:18Z
dc.date.copyright2011en_US
dc.date.issued2011en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/76944
dc.descriptionThesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2011.en_US
dc.descriptionCataloged from PDF version of thesis.en_US
dc.descriptionIncludes bibliographical references (p. 171-176).en_US
dc.description.abstractThis thesis analyzes the feasibility of emplacing DOE-owned defense nuclear waste from weapons production into a permanent borehole repository drilled ~4 km into granite basement rock. Two canister options were analyzed throughout the thesis: the canister currently used by the DOE for vitrified defense waste and a reference canister with a smaller diameter. In a thermal analysis, the maximum temperatures attained by the rock surrounding the waste, waste form, canister, liner, and gaps during the post-emplacement period were calculated. From this data, simple analytic equations were formed that can be used to calculate the maximum temperature differences for both defense waste and spent fuel when one does not want to repeat the analysis. Canister corrosion and waste form dissolution analyses were performed using Pourbaix diagrams. Finally, the cost and time for drilling the borehole and emplacing the defense waste were calculated. The temperature change in the granite is 15.1°C for the reference canister and 45.7°C for the DOE Canister. The resulting maximum temperature at the bottom of the borehole is 135.1°C (reference canister) and 165.7°C (DOE canister) for the bounding defense waste. The centerline temperature for the borosilicate glass waste package is approximately 150°C for the reference canister and 207°C for the DOE canister. Because of the thermodynamic properties, overall corrosion resistance, and reasonable cost, pure copper was shown to be the best borehole outer canister material. High-chromium stainless steel could also be a good option for borehole canisters because it has been shown to be highly corrosion-resistant in environments similar to predicted borehole environments. Cesium ion was found to have the highest concentration in the borehole environment. However, the relatively low half life of the most abundant cesium isotope suggests that the cesium would decay before the canister is breached. For the reference canister, the drilling and emplacement costs are not expected to exceed $46/kg of vitrified waste and the total disposal cost was found to be $153/kg of vitrified waste. The total cost of disposal of defense waste in DOE containers is not expected to exceed $53/kg of vitrified waste. Based on these analyses, disposal of vitrified defense waste in deep boreholes is expected to be technically and economically feasible.en_US
dc.description.statementofresponsibilityby Frances Elizabeth Dozier.en_US
dc.format.extent176 p.en_US
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/1721.1/7582en_US
dc.subjectNuclear Science and Engineering.en_US
dc.titleFeasibility of very deep borehole disposal of US nuclear defense wastesen_US
dc.typeThesisen_US
dc.description.degreeS.M.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineering
dc.identifier.oclc824565095en_US


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