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Characterization of carbon fiber flocked cathode materialsVisosky, Mark Michael January 1996 (has links)
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1996. / Includes bibliographical references (leaves 67-69). / by Mark Michael Visosky. / M.S.
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Nonlinear digital computer control for the steam generator system in a pressurized water reactor plantChoi, Jung In January 1987 (has links)
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1987. / Bibliography: v. 2, leaves 316-318. / by Jung In Choi. / Ph.D.
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Engineering design of electron accelerator targets for the commercial production of isotopesTompot, Randy William January 1997 (has links)
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997. / Includes bibliographical references (leaf 83). / by Randy Wiliam Tompot. / M.S.
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The effects of the on-line maintenance work management strategy on nuclear plant performanceNielsen, Frederick Mitchell January 1997 (has links)
Thesis (M. Eng.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997. / Includes bibliographical references (p. 99-101). / by Frederick Mitchell Nielsen. / M.Eng.
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Full value estimation of electric utility optionsSchenler, Warren William January 1996 (has links)
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1996. / Includes bibliographical references. / by Warren W. Schenler. / Ph.D.
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Sensitivity studies of the neutronic design of a fission converter-based ephithermal beam for boron neutron capture therapySakamoto, Shuichi January 1997 (has links)
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997. / Includes bibliographical references. / by Shuichi Sakamoto. / M.S.
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Electrochemical studies of zinc injection to reduce corrosion of PWR primary systemsFriedman, David Marcel January 1997 (has links)
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997. / Includes bibliographical references. / by David Friedman. / M.S.
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Calculation of absorbed fraction for internal gamma-ray emitters.Lee, Chai Quay January 1974 (has links)
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1974. M.S. / Includes bibliographical references. / M.S.
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A quantitative assessment of nuclear weapons proliferation risk utilizing probabilistic methodsSentell, Dennis Shannon, 1971- January 2002 (has links)
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2002. / Includes bibliographical references. / A comparative quantitative assessment is made of the nuclear weapons proliferation risk between various nuclear reactor/fuel cycle concepts using a probabilistic method. The work presented details quantified proliferation resistance metrics of a pressurized water reactor (PWR), a PWR utilizing thorium as a fertile component of the nuclear fuel (Radkowsky Thorium Reactor-RTR) and a high temperature, gas cooled, reactor with a pebble bed core (PBMR). This probabilistic method permits integration of all aspects of fissile material proliferation in formulating an overall estimate of relative proliferation risk. The reactor/fuel cycle concepts are examined along a "weapons-useable plutonium diverted from spent reactor fuel" proliferation pathway in order to determine these values, and concepts with low values of this estimate are favorable for continued development in terms of lowered proliferation potential. A determination is also made of those reactor/fuel cycle technical features that contribute the most to minimizing the proliferation success within these risk estimates. Identification of areas affecting these "importance measures", (i.e., reactor/fuel cycle practices, technical features, safeguard practices and resource allocations) allows for further research into these vital areas. The example and results presented in this work are an illustration of an integrated analysis utilizing a probabilistic method. The subjectivity used in determining various factors and confidence levels for this analysis is based on the author's own reasoning, opinion and judgment in light of political, economic and technical considerations. The results, implications and conclusions concerning different reactor/fuel cycles are applicable only within the context of this subjectivity as applied within this methodology. / by Dennis Shannon Sentell, Jr. / S.M.
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Variational derivation of modal-nodal finite difference equations in spatial reactor physics.Bailey, Patrick Gage January 1972 (has links)
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1972. Ph.D. / Vita. / Includes bibliographical references. / Ph.D.
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