Analytical calculations of neutron slowing down and transport in the constant-cross-section problem

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

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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.

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Call Number: E 1.99: coo--2509-7
E 1.99: coo--2509-7 Available

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