Analytical calculations of neutron slowing down and transport in the constant-cross-section problem [electronic resource]

Aspects of the problem of neutron slowing down and transport in an infinite medium consisting of a single nuclide that scatters elastically and isotropically and has energy-independent cross sections were investigated. The method of singular eigenfunctions was applied to the Boltzmann Equation gover...

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Bibliographic Details
Online Access:	Online Access
Corporate Author:	Oak Ridge National Laboratory (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Oak Ridge, Tenn. : Oak Ridge, Tenn. : Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1978.
Subjects:	Transport Theory. Scattering. Eigenfunctions. Polynomials. Functions. Elastic Scattering. Differential Equations. Boltzmann Equation. Equations. Neutron Transport Theory. Series Expansion. Legendre Polynomials. Neutron Slowing-down Theory. Green Function. Corrections. Fermi Age Theory. Nuclear Physics And Radiation Physics.

ANALYTICAL CALCULATIONS OF NEUTRON SLOWING DOWN AND TRANSPORT IN THE CONSTANT-CROSS-SECTION PROBLEM

Published 1978

Online Access

Government Document Electronic eBook

Analytical calculations of neutron slowing down and transport in the constant-cross-section problem [electronic resource]

ANALYTICAL CALCULATIONS OF NEUTRON SLOWING DOWN AND TRANSPORT IN THE CONSTANT-CROSS-SECTION PROBLEM

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