Article ID Journal Published Year Pages File Type
1729636 Annals of Nuclear Energy 2010 9 Pages PDF
Abstract
The neutronics and thermal-hydraulics coupled code, ANDES/COBRA-IIIc, previously verified in Cartesian geometry core analysis, can also be applied now to full three-dimensional VVER core problems, as well as to other thermal and fast hexagonal core designs. Verification results are provided, corresponding to the different cases of the OECD/NEA-NSC VVER-1000 Coolant Transient Benchmarks.
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
Preview
Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis
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