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The primary response system of a prototype pool liquid-metal fast breeder reactor to a hypothetical core disruptive accident this project is submitted in partial fulfillment ... /Zeuch, Wayne R. January 1900 (has links)
Thesis (M.S.)--University of Michigan, 1976.
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Fuel motion in loss-of-flow accidentsLal, Dhunjishaw 12 1900 (has links)
No description available.
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Modeling of unscrammed loss-of-flow accidents in fast reactors with the DSNP simulation codeRubio, Reuben A. January 1985 (has links)
Thesis (M.S.)--University of Michigan, 1985.
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Application of liquid metal magnetohydrodynamic generators to liquid metal fast breeder reactorsChow, Stanley 08 1900 (has links)
No description available.
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Temperature and velocity profile functions in a free convective liquid metal system with volume heat sourceSkavdahl, Richard E. January 1957 (has links)
Thesis (M.S.)--University of Michigan, 1957.
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A three region steam drum model for a nuclear power plant simulator (Brenda)Slovik, Gregory Charles January 1980 (has links)
No description available.
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A conceptual design of a uranyl nitrate fueled reactor for the destructive testing of liquid metal fast breeder reactor fuel subassembliesRamsower, Steven Earl January 1979 (has links)
No description available.
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Safety implications of a sensitivity analysis of the reactor kinetics parameters for fast breeder reactorsFlorian, Robert Joseph January 1982 (has links)
The delayed neutron spectra for LMFBRs are not as well known as those for LWRs. These spectra are necessary for kinetics calculations which play an important role in safety and accident analyses. In this study, a sensitivity analysis was performed to study the sensitivity of the reactor power and power density to uncertainties in the delayed neutron spectra during a rod ejection accident.
The generalised methodology, developed by Cacuci et. al., was used to derive a set of sensitivity derivatives. This method is based on the use of adjoints so that it is not necessary to repeatedly solve the governing (kinetics) equations to obtain the sensitivity derivatives. This is of particular importance when large systems of equations are used.
A two-energy multigroup and two precursor group model was formulated for the INFCE reference design MOX-fuelled LMFBR. The accidents studied were central control rod ejections with ejection times of 2, 10, and 30 seconds.
The power and power density responses were found to be most sensitive to uncertainties in the spectrum of the second delayed neutron precursor group, resulting from the fission of U-238, producing neutrons in the first energy group. It was found, for example, that for a rod ejection time of 30 seconds, an uncertainty of 7.2% in the fast components of the spectra resulted in a 24% uncertainty in the predicted power and power density. These responses were recalculated by repeatedly solving the kinetics equations. The maximum discrepancy was only 1.6%.
The versatility and accuracy of Cacuci’s methodology has been demonstrated. The results of the sensitivity analysis indicates the need for improved delayed neutron spectral data in order to reduce the uncertainties in the accident analyses.
The model can be extended by using more energy groups, more precursor groups, and more spatial dimensions. Other important responses that may be studied are the linear power density, linear heat rate, and reactivity worths. / Ph. D.
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Fluid mixing studies in a hexagonal 37-pin, wire wrap rod bundleChiu, King-Wo Thomas January 1980 (has links)
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / by King-Wo Thomas Chiu. / M.S.
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Heat transfer and fluid flow aspects of fuel-coolant interactions.Corradini, M. L January 1979 (has links)
Thesis. 1979. Ph.D. cn--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / Ph.D.cn
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