Multigroup Diffusion Theory Formulation of the Calculation of the Mean Square Slowing Down Distance in an Infinite Medium PDF Download
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Author: B. J. Toppel
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 30
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Book Description
Simple expressions for the mean square distance from a point fission source for slowing down past a given energy and for the mean square distance of neutrons that belong to a given energy group are derived within the framework of multigroup diffusion theory. The expressions may be applied to systems having arbitrary group transfer cross sections.
Author: B. J. Toppel
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 30
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Book Description
Simple expressions for the mean square distance from a point fission source for slowing down past a given energy and for the mean square distance of neutrons that belong to a given energy group are derived within the framework of multigroup diffusion theory. The expressions may be applied to systems having arbitrary group transfer cross sections.
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1038
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Book Description
Author: Joel H. Ferziger
Publisher: Elsevier
ISBN: 1483154998
Category : Science
Languages : en
Pages : 321
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Book Description
The Theory of Neutron Slowing Down in Nuclear Reactors focuses on one facet of nuclear reactor design: the slowing down (or moderation) of neutrons from the high energies with which they are born in fission to the energies at which they are ultimately absorbed. In conjunction with the study of neutron moderation, calculations of reactor criticality are presented. A mathematical description of the slowing-down process is given, with particular emphasis on the problems encountered in the design of thermal reactors. This volume is comprised of four chapters and begins by considering the problems of neutron moderation and their importance in all types of reactors. An asymptotic reactor model is described, and the calculation of the elastic scattering frequency is explained. Subsequent chapters focus on the process of slowing down in finite and infinite medium by analyzing capture by individual resonances; resonance integrals in heterogeneous systems; the slowing-down kernels; the spherical harmonics method; statistical methods; and small source theory. The final chapter presents numerical solutions of the Boltzmann equation and covers topics such as the multigroup approach, group constants, and solution of the multigroup equations. This book will be a useful resource for nuclear physicists and engineers.
Author: C. D. Petrie
Publisher:
ISBN:
Category : Hydrogen
Languages : en
Pages : 46
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Book Description
A one-dimensional multigroup program for the IBM 650, under the code name SLAG, is presented for the calculation of neutron fluxes, ages, and slowing-down densities in a homogenous medium containing hydrogen.
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 78
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Book Description
Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1288
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Book Description
Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 400
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Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 332
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Book Description
Author: Robert Vartan Meghreblian
Publisher:
ISBN:
Category : Mathematical physics
Languages : en
Pages : 826
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Book Description
Author: American Mathematical Society
Publisher:
ISBN:
Category : Mathematical physics
Languages : en
Pages : 360
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Book Description
