| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 5475305 | Annals of Nuclear Energy | 2017 | 8 Pages |
Abstract
The two-stage core analysis method is widely used for BWR core analysis. The purpose of this study is to develop a core analysis model coupled with subchannel analysis within the two-stage calculation scheme using an assembly-based thermal-hydraulics calculation in the core analysis. The model changes the 2D lattice physics scheme, and couples with 3D subchannel analysis which evaluates the thermal-hydraulics characteristics within the coolant flow area divided as some subchannel regions. In order to couple with these two analyses, some BWR fuel assembly parameters are assumed and verified. The developed model is evaluated for the heterogeneous problem with and without a control rod. The present model is especially effective for the control rod inserted condition. The present model can incorporate the subchannel effect into the current two-stage core calculation method.
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Authors
Takeshi Mitsuyasu, Motoo Aoyama, Akio Yamamoto,