The nuclear fuel cycle: analysis and management

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American Nuclear Society, 1990 - Mathematics - 378 pages
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This presents a balanced overview of the major methods currently available for obtaining numerical solutions in neutron and gamma-ray transport. It focuses on methods particularly applicable to the complex problems encountered in the analysis of reactors, fusion devices, radiation shielding, and other nuclear systems. It will be valuable as a self-contained reference and text to practicing engineers involved in research and development, to users of large transport computer codes for engineering analysis, and to first-year graduate students.

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Nuclear Fuel Resources
Enrichment and Conversion
Reactor Fuel Design and Fabrication

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