![]() Typically, in neutronic calculations, a nuclear fuel assembly is axially divided into 20-30 slices and each slice is radially modelled as one to four regions. The mapping between the two solvers is far from trivial, since the averaging volumes used by each solver can be significantly different. ![]() The weighting factor thus defines how much of the fission power (and possibly gamma heating) from a neutronic volume contributes to the heat generated in a given thermal-hydraulic volume. The sum of the weighting factors of the neutronic volumes contributing to a given thermal-hydraulic volume should be equal to unity. The relative weight of a neutronic volume to a thermal-hydraulic volume for the neutronic to thermal-hydraulic coupling. The weighting factor thus defines how much of the fuel temperature and the moderator temperature and/or density from a thermal-hydraulic volume should be used for retrieving the corresponding nuclear material data for a given neutronic volume. The sum of the weighting factors of the thermal-hydraulic volumes contributing to a given neutronic volume should be equal to unity. The relative weight of a thermal-hydraulic volume contributing to a neutronic volume for the thermal-hydraulic to neutronic coupling. A coupling coefficient can be seen as follows: ![]()
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