Synopsis
A balanced overview of the computational methods currently available for the solution of neutron transport problems encountered in engineering analysis. The predominant theme is the numerical solution of the Boltzmann equation for neutrons in those situations where the most widely used approximation diffusion theory is inadequate. Seven chapters co
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Nuclear Fuel Cycle: Analysis and Management
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Nuclear Fuel Cycle: Analysis and Management
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LA Grange Park, Illinois, U.S.A.: Amer Nuclear Society, 1990
ISBN 10: 0894484524
ISBN 13: 9780894484520
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Nuclear Fuel Cycle: Analysis and Management
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Nuclear Fuel Cycle: Analysis and Management
Published by
American Nuclear Society,U.S., 1990
ISBN 10: 0894484524
ISBN 13: 9780894484520
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