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1	DEPLESYN : a three dimensional, discontinuous synthesis, diffusion-depletion code. Chin, Ronald Joseph. January 1977 (has links) Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Engineering, 1977 / Vita. / Includes bibliographical references. / Ph. D. / Ph. D. Massachusetts Institute of Technology, Department of Nuclear Engineering Nuclear Engineering
2	Optimization of the axial power shape in pressurized water reactors Melik, M. A January 1982 (has links) Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE / Bibliography: leaves 112-114. / by Mushtaq Ahmad Malik. / M.S. Nuclear Engineering. Pressurized water reactors Nuclear fuel elements Computer programs
3	Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores. Masterson, Robert Edward. January 1977 (has links) Thesis: Sc. D., Massachusetts Institute of Technology, Department of Nuclear Engineering, 1977 / Includes bibliographical references. / Sc. D. / Sc. D. Massachusetts Institute of Technology, Department of Nuclear Engineering Nuclear Engineering
4	Application of nodal equivalence theory to the neutronic analysis of PWRS Hoxie, Christopher Lloyd January 1982 (has links) Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / by Christopher Lloyd Hoxie. / Ph.D. Nuclear Engineering. Pressurized water reactors Neutron flux Nuclear fuel elements Computer programs
5	Development of a method for BWR subchannel analysis. Faya, Artur José Goncalves January 1980 (has links) Thesis. 1980. Ph.D.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Bibliography : leaves 138-146. / Ph.D. Nuclear Engineering Nuclear fuel elements Computer programs Boiling water reactors
6	MITR-II fuel management, core depletion, and analysis : codes developed for the diffusion theory program CITATION Bernard, John Albert January 1979 (has links) Thesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1979. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / by John A. Bernard, Jr. / Nucl.E. Nuclear Engineering Nuclear fuel elements Computer programs Neutron transport theory Nuclear fuels
7	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
8	Comparison of conservative and best estimate heat transfer packages with COBRA-IV-I. Massoud, Mahmoud January 1978 (has links) Thesis. 1978. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICOFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / Nucl.E. Nuclear Engineering Nuclear fuel elements Computer programs Pressurized water reactors Nuclear fuel elements Thermal properties Heat Transmission
9	Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients Rodack, Thomas January 1977 (has links) Thesis (Nucl. E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering; and, (M.S.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1977. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / by Thomas Rodack. / M.S. / Nucl.E. Mechanical Engineering. Nuclear Engineering. Nuclear fuel elements Computer programs Nuclear fuel elements Thermal properties Nuclear reactors Fluid dynamics
10	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

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