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Introductory Neutronics

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This text is intended to cover basic neutronics roughly equivalent to a first semester graduate level course in reactor theory. As of the time of this writing, this should include introduction and discussion of the Boltzmann transport equation with the associated diffusion approximation up to the three spatial dimension (energy dependent) case, perturbation approximation of theoretical reactor configurations, cross section analysis, and discussion of computer programs associated with nuclear studies.

The reader is expected to be competent in undergraduate level physics/nuclear engineering and to be acquainted with mathematical techniques including multi-dimensional vector calculus and differential equations.

This text is not intended to provide information useful for the design or construction of nuclear weapons and should not contain any material that is restricted by international agreement.

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