The accurate determination of the neutron distribution and multiplication factor in a commercial power reactor appears at first to be an extremely challenging problem that would tax the largest supercomputers. However, years of development and refinement of computational methods for this problem have resulted in modern methods that are incredibly computationally efficient. In this talk I will describe these methods, give examples of how efficient they are, and point out how they take advantage of the physics of the problem. Perhaps this will lead to discussions of how to employ similar strategies in other transport problems.
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