Modeling of reflood constitutes a challenging problem in nuclear thermal-hydraulics. The modeling idea of the Japanese scientist, Yamanouchi 1968, is still utilized in current modeling: two dimensional axial and radial solution to the conduction heat transfer problem inside the (thin) nuclear fuel clad is utilized to set up a model and to derive (typically, a very) large HTC (Heat Transfer Coefficient) at the location of the quench front. The model is continuously updated in code versions. In this paper application of different code versions to one selected experiment condition is tested.
Study of Top-Down Reflood with different Relap5 Code Versions
D'Auria F.
Primo
Conceptualization
;
1995-01-01
Abstract
Modeling of reflood constitutes a challenging problem in nuclear thermal-hydraulics. The modeling idea of the Japanese scientist, Yamanouchi 1968, is still utilized in current modeling: two dimensional axial and radial solution to the conduction heat transfer problem inside the (thin) nuclear fuel clad is utilized to set up a model and to derive (typically, a very) large HTC (Heat Transfer Coefficient) at the location of the quench front. The model is continuously updated in code versions. In this paper application of different code versions to one selected experiment condition is tested.File in questo prodotto:
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