Error Assessment of Homogenized Cross Sections Generation for Whole Core Neutronic Calculation
- University of California at Berkeley, 3115 Etcheverry Hall, Berkeley CA (United States)
The objective of the work here was to assess the errors introduced by using 2D, few group homogenized cross sections to perform neutronic analysis of BWR problems with significant axial heterogeneities. The 3D method of characteristics code DeCART is used to generate 2-group assembly homogenized cross sections first using a conventional 2D lattice model and then using a full 3D solution of the assembly. A single BWR fuel assembly model based on an advanced BWR lattice design is used with a typical void distribution applied to the fuel channel coolant. This model is validated against an MCNP model. A comparison of the cross sections is performed for the assembly homogenized planar cross sections from the DeCART 3D and DeCART 2D solutions.
- OSTI ID:
- 21036065
- Journal Information:
- AIP Conference Proceedings, Vol. 947, Issue 1; Conference: 7. Latin American symposium on nuclear physics and applications, Cusco (Peru), 11-16 Jun 2007; Other Information: DOI: 10.1063/1.2813839; (c) 2007 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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