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Author:

Wu, Hongchun (Wu, Hongchun.) | Liu, Pingping (Liu, Pingping.) | Zhou, Yongqiang (Zhou, Yongqiang.) | Cao, Liangzhi (Cao, Liangzhi.)

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Scopus SCOPUS

Abstract:

The fuel assembly or core with unstructured geometry is frequently used in the advanced reactor. To calculate the fuel assembly, the transmission probability method (TPM) is widely used. However, the rectangular or hexagonal meshes are mainly used in the TPM codes for the normal core structure. The triangle meshes are most useful for expressing the complicated unstructured geometry. Even though the finite element method and Monte-Carlo method are well suited for solving the unstructured geometry problem, they are very time-consuming. Therefore, a TPM code based on the triangle meshes is developed here. This code was applied to the hybrid fuel geometry, and compared with the results of the MCNP code and other codes. The results of the comparison were consistent with each other. The TPM with triangle meshes can thus be applied to the two-dimensional arbitrary fuel assembly. © Higher Education Press 2007.

Keyword:

MCNP code Neutron integral transport equation Transmission probability method Triangle mesh Unstructured fuel geometry

Author Community:

  • [ 1 ] [Liu, Pingping;Zhou, Yongqiang]Xi'an Jiaotong University, Department of Nuclear Engineering,Xi'an,China
  • [ 2 ] [Cao, Liangzhi]Xi'an Jiaotong University, School of Nuclear Science and Technology,Xi'an,China
  • [ 3 ] [Wu, Hongchun]Xi'an Jiaotong University,Xi'an,China

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Source :

Frontiers of Energy and Power Engineering in China

ISSN: 1673-7393

Year: 2007

Issue: 2

Volume: 1

Page: 158-166

Cited Count:

WoS CC Cited Count: 0

SCOPUS Cited Count:

ESI Highly Cited Papers on the List: 0 Unfold All

WanFang Cited Count: -1

Chinese Cited Count: -1

30 Days PV: 15

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