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51	Thermal-hydraulic analysis of tight lattice light water reactors. Boyd, William Artis January 1977 (has links) Thesis. 1977. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibiliographical references. / M.S. Nuclear Engineering Nuclear fuel elements Thermal properties Nuclear reactors Computer programs
52	Experimental and analytical study of axial turbulent flows in an interior subchannel of a bare rod bundle. Carajilescov, Pedro January 1975 (has links) Thesis. 1975. Ph.D.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / Vita. / Includes bibliographical references. / Ph.D. Nuclear Engineering Nuclear fuel elements Turbulence Mathematical models Laser Doppler velocimeter Fluid dynamics
53	Fuel element performance maps for nuclear reactor operational decisions. Da Silva, Othon Luiz Pinheiro January 1978 (has links) Thesis. 1978. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / Nucl.E. Nuclear Engineering Nuclear fuel elements Pressurized water reactors Nuclear fuel claddings
54	Approximate methods for obtaining a one-group nodal solution with two-group parameters Hagemeier, Bruce William January 1982 (has links) Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE / Includes bibliographical references. / by Bruce William Hagemeier. / M.S. Nuclear Engineering. Pressurized water reactors Cores Boiling water reactors Nuclear fuel elements Computer programs
55	The use of burnable poison to improve uranium utilization in PWRS Loh, Wee Tee January 1982 (has links) Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Bibliography: leaves 247-249. / by Wee Tee Loh. / Ph.D. Nuclear Engineering. Pressurized water reactors Light water reactors Uranium Nuclear fuel elements
56	A hydrodynamic evaluation of the Sandia UO₂ equation of state experiment Smith, Mark Scott January 1981 (has links) No description available. Uranium dioxide. Vapor pressure -- Mathematical models. FARA (Computer program)
57	Development of a two-fluid, two-phase model for light water reactor subchannel analysis Kelly, J. E January 1980 (has links) Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE / Includes bibliographical references. / by John Edward Kelly. / Ph.D. Nuclear Engineering. Light water reactors Two-phase flow Mathematical models Nuclear reactors Computer programs Nuclear fuel elements
58	The F [subscript N] method for a bare critical cylinder Southers, Jack Daniel January 1982 (has links) The F<sub>N</sub> method, originated by C. E. Siewert, is developed for a bare, axially infinite critical cylinder. The full-range completeness and orthogonality properties of the singular eigenfunctions are used to derive an expression for the emerging angular flux, which is represented by a power series. The resulting equations are reduced to matrix form and computer solved. Examples of the results of this method for different parameters are presented. Comparisons with other models are made. A fourth order approximation was found to be sufficient to achieve up to four digit agreement with benchmark values. / Master of Science LD5655.V855 1982.S667 Nuclear fuel rods Criticality (Nuclear engineering) Neutron transport theory
59	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 Nuclear Engineering Nuclear fuel elements Two-phase flow Heat Transmission
60	Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT Loomis, James North January 1981 (has links) Thesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1981. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / by James North Loomis. / Nucl.E. Nuclear Engineering. Nuclear fuel elements Computer programs Boiling water reactors Fluid dynamics Light water reactors Fluid dynamics Light water reactors Thermal properties

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