| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 6763296 | Nuclear Engineering and Design | 2013 | 13 Pages |
Abstract
Calculations were performed with the BGCore system, which consists of the MCNP code coupled with fuel depletion and thermo-hydraulic feedback modules. A single 3-dimensional fuel assembly having reflective radial boundaries was modeled applying simplified restrictions on the maximum centerline fuel temperature and the CPR. It was found that axially heterogeneous fuel assembly design with a single fissile zone can potentially achieve net breeding, while matching conventional BWR core power rating under certain restrictions to the core loading pattern design.
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Authors
Y. Shaposhnik, E. Shwageraus, E. Elias,