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An analytic nodal method for solving the two-group, multidimensional, static and transient neutron diffusion equations

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An analytic nodal method for solving the two-group, multidimensional, static and transient neutron diffusion equations

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Author: Smith, Kord Sterling
Department: Massachusetts Institute of Technology. Dept. of Nuclear Engineering
Publisher: Massachusetts Institute of Technology
Date Issued: 1979
Description:
Thesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1979.MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE.Includes bibliographical references.
URI: http://hdl.handle.net/1721.1/15979
Series/Report no.: Massachusetts Institute of Technology. Dept. of Nuclear Engineering.
Keywords: Nuclear Engineering, Neutron transport theory, Nuclear reactors Tables

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