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51	Estudo e aplicacao dos codigos nucleares ANISN e DOT-II em problemas de fisica de reatores DIAS, ARTUR F. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:29:01Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:02:24Z (GMT). No. of bitstreams: 1 00965.pdf: 1750630 bytes, checksum: e69ee5985ba23aa96db338a0d9813c17 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP programming a codes d codes transport theory boltzmann equation neutron transport theory transport theory
52	O Metodo das ordenadas discretas na solucao da equacao de transporte em geometria plana com dependencia azimutal CHALHOUB, EZZAT S. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:42:57Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:08:16Z (GMT). No. of bitstreams: 1 06145.pdf: 4965019 bytes, checksum: afa11bbe0d27b123a27cffcd90fa9286 (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP neutron transport theory albedo finite difference method discrete ordinate method a codes computer codes programming computer calculations
53	Estudo e aplicacao dos codigos nucleares ANISN e DOT-II em problemas de fisica de reatores DIAS, ARTUR F. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:29:01Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:02:24Z (GMT). No. of bitstreams: 1 00965.pdf: 1750630 bytes, checksum: e69ee5985ba23aa96db338a0d9813c17 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP programming a codes d codes transport theory boltzmann equation neutron transport theory transport theory
54	O Metodo das ordenadas discretas na solucao da equacao de transporte em geometria plana com dependencia azimutal CHALHOUB, EZZAT S. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:42:57Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:08:16Z (GMT). No. of bitstreams: 1 06145.pdf: 4965019 bytes, checksum: afa11bbe0d27b123a27cffcd90fa9286 (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP neutron transport theory albedo finite difference method discrete ordinate method a codes computer codes programming computer calculations
55	Spatial homogenization methods for light water reactor analysis Smith, Kord Sterling January 1980 (has links) Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Vita. / Includes bibliographical references. / by Kord Sterling Smith. / Ph.D. Nuclear Engineering. Light water reactors Neutron transport theory Nuclear reactors Tables
56	Homogenization of BWR assemblies by response matrix methods Cheng, Alexander Y. C January 1981 (has links) Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1981. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Vita. / Includes bibliographical references. / by Alexander Y.C. Cheng. / Ph.D. Nuclear Engineering. Boiling water reactors Nuclear reactors Tables Neutron transport theory
57	The replacement of reflectors by Albedo-type boundary conditions. Kalambokas, Panagiotis Constantinos January 1976 (has links) Thesis. 1976. Sc.D.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / Microfiche copy available in Archives and Science. / Bibliography: leaves 221-224. / Sc.D. Nuclear Engineering Nuclear fuel elements Neutron transport theory Nuclear reactors Tables
58	Nonlinear methods for solving the diffusion equation. Shober, Robert Anthony January 1977 (has links) Thesis. 1977. Ph.D.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Vita. / Includes bibliographical references. / Ph.D. Nuclear Engineering Nuclear reactors Tables Finite element method Neutron transport theory
59	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
60	Multigroup transport equations with nondiagonal cross section matrices Willis, Barton L. January 1985 (has links) It is shown that multigroup transport equations with nondiagonal cross section matrices arise when the modal approximation is applied to energy dependent transport equations. This work is a study of such equations for the case that the cross section matrix is nondiagonalizable. For the special case of a two-group problem with a noninvertible scattering matrix, the problem is solved completely via the Wiener-Hopf method. For more general problems, generalized Chandrasekhar H equations are derived. A numerical method for their solution is proposed. Also, the exit distribution is written in terms of the H functions. / Ph. D. / incomplete_metadata LD5655.V856 1985.W548 Neutron transport theory Wiener-Hopf equations Wiener-Hopf operators Functional analysis

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