Comparison of VVER-1000 benchmark calculations and improvements in hexagonal-Z diffusion methodology
The evolution of nuclear reactor technology is connected with increased requirements to core design and analysis methodology. An optimal balance with respect to accuracy and efficiency has been reached in the modern three-dimensional few-group diffusion codes, which, for VVER reactors, are designed to analyze hexagonal geometry. The qualification of core design codes involves comprehensive benchmark calculations, comparison to measured data, and analysis of results in order to evaluate the accuracy of the implemented neutronic model and the range of code applicability. Comprehensive comparisons between results from bench-mark calculations of the first three cycles of the VVER-1000 unit 5 at Kozloduy nuclear power plants (NPP) and experimental data have been performed. The corresponding differences have been analyzed statistically and examined against the values of experimental inaccuracy. Within the framework of the developed nonlinear high-order finite difference nodal neutronic model in hexagonal-z geometry, new expressions for correction coefficients are proposed and benchmarked.
- OSTI ID:
- 89288
- Report Number(s):
- CONF-941102-; ISSN 0003-018X; TRN: 95:004215-0365
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 71; Conference: Winter meeting of the American Nuclear Society (ANS), Washington, DC (United States), 13-18 Nov 1994; Other Information: PBD: 1994
- Country of Publication:
- United States
- Language:
- English
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