Acceleration method for neutron transport equation with highly anisotropic scattering

Xing Guang Sun; Hong Chun Wu; Zhi Jun Shen

Acceleration method for neutron transport equation with highly anisotropic scattering

Xing Guang Sun
, Hong Chun Wu
, Zhi Jun Shen

能源与动力工程学院

Xi'an Jiaotong University
Beijing Applied Physics and Computation Mathematics Institute

科研成果: 期刊稿件 › 文章 › 同行评审

摘要

S_N method is wildly used to solve neutron transport equation, but S_N method is very slow with highly anisotropic scattering. In this paper, the modified P_N synthetic acceleration (MPSA) method is used to accelerate S_N method, and applied to the code of ANISN which is internationally used. MPSA method not only can accelerate the computation with low-order of angular flux moments, but also with high-order of angular flux moments. So MPSA method is more efficient than DSA method. Numerical results for the test problems demonstrate that MPSA method is quiet efficient and robust, especially for the problems with highly anisotropic scattering.

源语言	英语
页（从-至）	125-128
页数	4
期刊	Hedongli Gongcheng/Nuclear Power Engineering
卷	29
期	1
出版状态	已出版 - 2月 2008

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title = "Acceleration method for neutron transport equation with highly anisotropic scattering",

abstract = "SN method is wildly used to solve neutron transport equation, but SN method is very slow with highly anisotropic scattering. In this paper, the modified PN synthetic acceleration (MPSA) method is used to accelerate SN method, and applied to the code of ANISN which is internationally used. MPSA method not only can accelerate the computation with low-order of angular flux moments, but also with high-order of angular flux moments. So MPSA method is more efficient than DSA method. Numerical results for the test problems demonstrate that MPSA method is quiet efficient and robust, especially for the problems with highly anisotropic scattering.",

keywords = "Acceleration method, Highly anisotropic scattering, Neutron transport",

author = "Sun, \{Xing Guang\} and Wu, \{Hong Chun\} and Shen, \{Zhi Jun\}",

year = "2008",

month = feb,

language = "英语",

volume = "29",

pages = "125--128",

journal = "Hedongli Gongcheng/Nuclear Power Engineering",

issn = "0258-0926",

publisher = "Atomic Energy Press",

number = "1",

}

TY - JOUR

T1 - Acceleration method for neutron transport equation with highly anisotropic scattering

AU - Sun, Xing Guang

AU - Wu, Hong Chun

AU - Shen, Zhi Jun

PY - 2008/2

Y1 - 2008/2

N2 - SN method is wildly used to solve neutron transport equation, but SN method is very slow with highly anisotropic scattering. In this paper, the modified PN synthetic acceleration (MPSA) method is used to accelerate SN method, and applied to the code of ANISN which is internationally used. MPSA method not only can accelerate the computation with low-order of angular flux moments, but also with high-order of angular flux moments. So MPSA method is more efficient than DSA method. Numerical results for the test problems demonstrate that MPSA method is quiet efficient and robust, especially for the problems with highly anisotropic scattering.

AB - SN method is wildly used to solve neutron transport equation, but SN method is very slow with highly anisotropic scattering. In this paper, the modified PN synthetic acceleration (MPSA) method is used to accelerate SN method, and applied to the code of ANISN which is internationally used. MPSA method not only can accelerate the computation with low-order of angular flux moments, but also with high-order of angular flux moments. So MPSA method is more efficient than DSA method. Numerical results for the test problems demonstrate that MPSA method is quiet efficient and robust, especially for the problems with highly anisotropic scattering.

KW - Acceleration method

KW - Highly anisotropic scattering

KW - Neutron transport

UR - https://www.scopus.com/pages/publications/41649118296

M3 - 文章

AN - SCOPUS:41649118296

SN - 0258-0926

VL - 29

SP - 125

EP - 128

JO - Hedongli Gongcheng/Nuclear Power Engineering

JF - Hedongli Gongcheng/Nuclear Power Engineering

IS - 1

ER -

Acceleration method for neutron transport equation with highly anisotropic scattering

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