Development of 2-D/1-D fusion method for three-dimensional whole-core heterogeneous neutron transport calculations = 3차원 전노심 비균질 중성자 수송계산을 위한 2-D/1-D 퓨전방법 개발

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To describe power distribution and multiplication factor of a reactor core accurately, it is necessary to perform calculations based on neutron transport equation considering heterogeneous geometry and scattering angles. These calculations require very heavy calculations and were nearly impossible with computers of old days. From the limitation of computing power, traditional approach of reactor core design consists of heterogeneous transport calculation in fuel assembly level and whole core diffusion nodal calculation with assembly homogenized properties, resulting from fuel assembly transport calculation. This approach may be effective in computation time, but it gives less accurate results for highly heterogeneous problems. As potential for whole core heterogeneous transport calculation became more feasible owing to rapid development of computing power during last several years, the interests in two and three dimensional whole core heterogeneous transport calculations by deterministic method are increased. For two dimensional calculation, there were several successful approaches using even parity transport equation with triangular meshes, S_N method with refined rectangular meshes, the method of characteristics (MOC) with unstructured meshes, and so on. The work in this thesis originally started from the two dimensional whole core heterogeneous transport calculation by using MOC. After successful achievement in two dimensional calculation, there were efforts in three-dimensional whole-core heterogeneous transport calculation using MOC. Since direct extension to three dimensional calculation of MOC requires too much computing power, indirect approach to three dimensional calculation was considered.Thus, 2D/1D fusion method for three dimensional heterogeneous transport calculation was developed and successfully implemented in a computer code. The 2D/1D fusion method is synergistic combination of the MOC for radial 2-D calculation and S_N-like methods ...
Cho, Nam-Zinresearcher조남진researcher
한국과학기술원 : 원자력및양자공학과,
Issue Date
254258/325007  / 020005215

학위논문(박사) - 한국과학기술원 : 원자력및양자공학과, 2006.2, [ viii, 100 p. ]


Neutron transport; Heterogeneous; Three-dimensional; Fusion method; 퓨전방법; 중성자 수송; 비균질; 3차원; MOC

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