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dc.contributor.advisorNeil E. Todreas.en_US
dc.contributor.authorRomano, Antonino, 1972-en_US
dc.contributor.otherMassachusetts Institute of Technology. Dept. of Nuclear Engineering.en_US
dc.date.accessioned2005-06-02T16:31:46Z
dc.date.available2005-06-02T16:31:46Z
dc.date.copyright2003en_US
dc.date.issued2003en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/17643
dc.descriptionThesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2003.en_US
dc.descriptionIncludes bibliographical references (leaves 228-232).en_US
dc.description.abstractThe thesis investigates the potential of fertile free fast lead-cooled modular reactors as efficient incinerators of plutonium and minor actinides (MAs) for application to dedicated fuel cycles for transmutation. A methodology is developed that assesses the actinide incineration performance of several transmutation fuel cycles, both single and multi-tiered, on the basis of performance indicators related to the reduction of actinide mass at the repository and economics. Application of the methodology indicates that fast fertile-free critical reactors that bum plutonium and MAs applied to both one-tier and two-tier fuel cycles with fuel reprocessing have the potential to be more economical than other dedicated systems like the ATW. Hence the thesis studies two lead-cooled critical reactors that employ fertile-free fuel as possible candidates. The two designs proposed are: an actinide burner reactor (ABR), designed to incinerate mostly plutonium and some MAs from the spent fuel of the conventional LWR fleet, and a minor a ctinide buumer reactor (MABR), devoted to bum mostly minor actinides and some plutonium both recycled from the burner and produced by the LWR fleet that should be integrated in a two-tier fuel cycle where most of the plutonium is fed back to advanced thermal reactors or conventional fast reactors (first tier) for incineration. These designs incorporate several advanced technical solutions such as fuel assemblies with streaming elements, double-entry control rods and special absorbing materials that establish favorable neutronics characteristics and excellent self-controllability features, comparable to those of the Integral Fast Reactor (IFR) core.en_US
dc.description.abstract(cont.) Specifically, the designs achieve (a) negative reactivity feedbacks based on coolant voiding, Doppler and fuel and core structure thermal expansion effects; (b) satisfactory values for the effective delayed neutron fractions, comparable to those reported for the IFR; (c) proliferation resistance with dilution of the plutonium vector, which is practically unusable for nuclear weapons fabrication. The safety features of these designs is assessed by applying a thermal-hydraulic code that simulates the worst accident scenarios envisaged for the burners. Application of the fuel cycle methodology to both designs shows that a) deployment of the MABR as the burner in the two-tier fuel cycle is the most efficient strategy to manage actinides and that b) both designs yield lower fuel cycle costs compared to the subcritical reactors.en_US
dc.description.statementofresponsibilityby Antonino Romano.en_US
dc.format.extent269 leavesen_US
dc.format.extent14670504 bytes
dc.format.extent14713400 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.titleOptimization of actinide transmutation in innovative lead-cooled fast reactorsen_US
dc.typeThesisen_US
dc.description.degreePh.D.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.oclc54854710en_US


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