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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
Seller: Upward Bound Books, VALRICO, FL, U.S.A.
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Condition: acceptable. Books may exhibit damage including dents, creases, and folded pages. Some volumes may contain annotations or highlighted sections. PLEASE NOTE that extras or accessories may not be included. Additionally, digital codes and CDs have not been verified for functionality and may be inoperative. Seller Inventory # 59WS4H001V6U_ns
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