Overlapping Local/Global Iteration Framework for Whole-Core Transport Solution

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In current practice of nuclear reactor design analysis, the whole-core diffusion nodal method is used in which nodal parameters are provided by a single-assembly lattice physics calculation with the zero net current boundary condition. Thus, the whole-core solution is not transport, because the interassembly transport effect is not incorporated. In this paper, the overlapping local/global iteration framework that removes the limitation of the current method is described. It consists of two-level iterative computations: half-assembly overlapping local problems embedded in a global problem. The local problem can employ heterogeneous fine-group deterministic or continuous-energy stochastic (Monte Carlo) transport methods, while the global problem is a homogenized coarse-group transport-equivalent model based on partial current based coarse-mesh finite difference methodology. The method is tested on several highly heterogeneous multislab problems and a two-dimensional small core problem, with encouraging results.
Publisher
AMER NUCLEAR SOC
Issue Date
2013-11
Language
English
Article Type
Article; Proceedings Paper
Citation

NUCLEAR SCIENCE AND ENGINEERING, v.175, no.3, pp.227 - 238

ISSN
0029-5639
URI
http://hdl.handle.net/10203/188450
Appears in Collection
NE-Journal Papers(저널논문)
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