Analysis demonstrates the development of a variance reduction scheme in neutron transport, suggesting broader applicability in reactor safety assessments.
The necessity of development of the variance reduction scheme for usage in MCSS program is well grounded. The criterions of nonanalog method selection are stated. The most important elements of the developed scheme are described. Opportunities of numerous problems solution by usage of this scheme and opportunities of expanding its applicability are shown.
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Grytsenko et al. (2002) studied this question.
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