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Half‐Space Neutron Transport with Linearly Anisotropic Scattering

dc.contributor.authorMcCormick, Norman J.en_US
dc.contributor.authorKuščer, I.en_US
dc.date.accessioned2010-05-06T21:56:22Z
dc.date.available2010-05-06T21:56:22Z
dc.date.issued1965-12en_US
dc.identifier.citationMcCormick, N. J.; Kuščer, I. (1965). "Half‐Space Neutron Transport with Linearly Anisotropic Scattering." Journal of Mathematical Physics 6(12): 1939-1945. <http://hdl.handle.net/2027.42/70296>en_US
dc.identifier.urihttps://hdl.handle.net/2027.42/70296
dc.description.abstractThe method developed by Case is used to solve four time‐independent, one‐speed problems for neutron transport in a homogeneous medium where the scattering function is linear in the cosine of the scattering angle. The solutions to the albedo, Milne, Green's function, and constant isotropic source problems for a half‐space are facilitated by the use of half‐range bi‐orthogonality relations between the eigenfunctions of the homogeneous transport equation. Expressions are also derived for the emerging angular densities and the densities and net currents on the surface of the half‐space.en_US
dc.format.extent3102 bytes
dc.format.extent360087 bytes
dc.format.mimetypetext/plain
dc.format.mimetypeapplication/pdf
dc.publisherThe American Institute of Physicsen_US
dc.rights© The American Institute of Physicsen_US
dc.titleHalf‐Space Neutron Transport with Linearly Anisotropic Scatteringen_US
dc.typeArticleen_US
dc.subject.hlbsecondlevelPhysicsen_US
dc.subject.hlbtoplevelScienceen_US
dc.description.peerreviewedPeer Revieweden_US
dc.contributor.affiliationumDepartment of Nuclear Engineering, The University of Michigan, Ann Arbor, Michiganen_US
dc.description.bitstreamurlhttp://deepblue.lib.umich.edu/bitstream/2027.42/70296/2/JMAPAQ-6-12-1939-1.pdf
dc.identifier.doi10.1063/1.1704744en_US
dc.identifier.sourceJournal of Mathematical Physicsen_US
dc.identifier.citedreferenceK. M. Case, Ann. Phys. (N.Y.) 9, 1 (1960).en_US
dc.identifier.citedreferenceK. M. Case, Recent Developments in Neutron Transport Theory, Michigan Memorial Phoenix Project Report, The University of Michigan (1961).en_US
dc.identifier.citedreferenceM. R. Mendelson and G. C. Summerfield, J. Math. Phys. 5, 668 (1964).en_US
dc.identifier.citedreferenceG. J. Mitsis, Nucl. Sci. Eng. 17, 55 (1963).en_US
dc.identifier.citedreferenceN. J. McCormick and M. R. Mendelson, Nucl. Sci. Eng. 20, 462 (1964).en_US
dc.identifier.citedreferenceJ. R. Mika, Nucl. Sci. Eng. 11, 415 (1961).en_US
dc.identifier.citedreferenceF. Shure and M. Natelson, Ann. Phys. (N.Y.) 26, 274 (1964).en_US
dc.identifier.citedreferenceI. Kuščer, N. J. McCormick, and G. C. Summerfield, Ann. Phys. 30, 411 (1964).en_US
dc.identifier.citedreferenceN. J. McCormick, “One‐Speed Neutron Transport Problems in Plane Geometry,” Ph.D. thesis, The University of Michigan (1964).en_US
dc.identifier.citedreferenceS. Chandrasekhar, Radiative Transfer (Dover Publications, Inc., New York, 1960).en_US
dc.identifier.citedreferenceK. M. Case, Rev. Mod. Phys. 29, 651 (1957).en_US
dc.owningcollnamePhysics, Department of


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