Preliminary study on CAD-based method of characteristics for neutron transport calculation

Our new method makes use of a CAD-based automatic modeling tool, MCAM, for geometry modeling and ray tracing of particle transport in method of characteristics (MOC). It was found that it could considerably enhance the capability of MOC to deal with more complicated models for neutron transport calc...

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Published inChinese physics C Vol. 38; no. 5; pp. 114 - 120
Main Author 陈珍平 郑华庆 孙光耀 宋婧 郝丽娟 胡丽琴 吴宜灿
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Published 01.05.2014
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Abstract Our new method makes use of a CAD-based automatic modeling tool, MCAM, for geometry modeling and ray tracing of particle transport in method of characteristics (MOC). It was found that it could considerably enhance the capability of MOC to deal with more complicated models for neutron transport calculation. In our study, the diamond-difference scheme was applied to MOC to reduce the spatial discretization errors of the fiat flux approximation. Based on MCAM and MOC, a new 2D MOC code was developed and integrated into the SuperMC system, which is a Super Multi-function Computational system for neutronics and radiation simulation. The numerical results demonstrated the feasibility and effectiveness of the new method for neutron transport calculation in MOC.
AbstractList Our new method makes use of a CAD-based automatic modeling tool, MCAM, for geometry modeling and ray tracing of particle transport in method of characteristics (MOC). It was found that it could considerably enhance the capability of MOC to deal with more complicated models for neutron transport calculation. In our study, the diamond-difference scheme was applied to MOC to reduce the spatial discretization errors of the fiat flux approximation. Based on MCAM and MOC, a new 2D MOC code was developed and integrated into the SuperMC system, which is a Super Multi-function Computational system for neutronics and radiation simulation. The numerical results demonstrated the feasibility and effectiveness of the new method for neutron transport calculation in MOC.
Our new method makes use of a CAD-based automatic modeling tool, MCAM, for geometry modeling and ray tracing of particle transport in method of characteristics (MOC). It was found that it could considerably enhance the capability of MOC to deal with more complicated models for neutron transport calculation. In our study, the diamond-difference scheme was applied to MOC to reduce the spatial discretization errors of the flat flux approximation. Based on MCAM and MOC, a new 2D MOC code was developed and integrated into the SuperMC system, which is a Super Multi-function Computational system for neutronics and radiation simulation. The numerical results demonstrated the feasibility and effectiveness of the new method for neutron transport calculation in MOC.
Author 陈珍平 郑华庆 孙光耀 宋婧 郝丽娟 胡丽琴 吴宜灿
AuthorAffiliation University of Science and Technology of China, Hefei 230027, China Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
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Cites_doi 10.1016/j.anucene.2006.07.001
10.1016/S0306-4549(97)00113-8
10.1016/j.fusengdes.2007.02.022
10.1016/0149-1970(86)90031-4
10.1016/j.fusengdes.2005.09.057
10.2172/582265
10.1080/18811248.2010.9711931
10.1088/0029-5515/47/8/040
10.13182/NSE96-3
10.1016/j.nucengdes.2008.04.014
10.1016/j.fusengdes.2008.12.041
10.15669/pnst.2.821
10.1016/j.fusengdes.2006.07.068
10.1016/0306-4549(95)00058-5
10.1016/S0306-4549(00)00038-4
10.1016/j.nima.2009.03.216
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Our new method makes use of a CAD-based automatic modeling tool, MCAM, for geometry modeling and ray tracing of particle transport in method of characteristics (MOC). It was found that it could considerably enhance the capability of MOC to deal with more complicated models for neutron transport calculation. In our study, the diamond-difference scheme was applied to MOC to reduce the spatial discretization errors of the fiat flux approximation. Based on MCAM and MOC, a new 2D MOC code was developed and integrated into the SuperMC system, which is a Super Multi-function Computational system for neutronics and radiation simulation. The numerical results demonstrated the feasibility and effectiveness of the new method for neutron transport calculation in MOC.
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References 22
23
24
25
29
Cho N Z (2) 1998; 25
Wang G Z (20) 2011; 2
Ferrari A (18) 2011
Diop C M (16) 2007; 97
10
12
13
Askew R (1) 1972
19
Petrovic I (26) 1996; 122
Goldberg L (4) 1995; 73
Halsall M J (3) 1980
Wu Y C (11) 2007; 26
Wu Y C (9) 2007; 27
5
6
(27) 2003
7
8
Cavarec C (28) 1994
Briesmeister J F (14) 2000
Zhang J J (15) 2010; 3
(17) 2009
Zheng S (21) 2007; 47
References_xml – volume: 97
  start-page: 694
  year: 2007
  ident: 16
  publication-title: Trans. Am. Nucl. Society
  contributor:
    fullname: Diop C M
– year: 2003
  ident: 27
  publication-title: Benchmark on Deterministic Transport Calculations without Spatial Homogenization, a 2-D/3-D MOX Fuel Assembly Benchmark
– ident: 7
  doi: 10.1016/j.anucene.2006.07.001
– volume: 73
  start-page: 173
  year: 1995
  ident: 4
  publication-title: Trans. Am. Nucl. Society
  contributor:
    fullname: Goldberg L
– year: 1980
  ident: 3
  publication-title: A Characteristic Solution to the Neutron Transport Equation in Complicated Geometries
  contributor:
    fullname: Halsall M J
– ident: 10
– volume: 26
  start-page: 20
  year: 2007
  ident: 11
  publication-title: Chinese J. Nucl. Sci. Eng.
  contributor:
    fullname: Wu Y C
– volume: 3
  start-page: 272
  year: 2010
  ident: 15
  publication-title: Chinese J. Nucl. Sci. Eng.
  contributor:
    fullname: Zhang J J
– volume: 25
  start-page: 547
  issn: 0306-4549
  year: 1998
  ident: 2
  publication-title: Ann. Nucl. Energy
  doi: 10.1016/S0306-4549(97)00113-8
  contributor:
    fullname: Cho N Z
– ident: 12
  doi: 10.1016/j.fusengdes.2007.02.022
– ident: 24
  doi: 10.1016/0149-1970(86)90031-4
– year: 2000
  ident: 14
  publication-title: MCNP–A general Monte Carlo N-Particle Transport Code
  contributor:
    fullname: Briesmeister J F
– ident: 23
  doi: 10.1016/j.fusengdes.2005.09.057
– ident: 19
  doi: 10.2172/582265
– ident: 29
  doi: 10.1080/18811248.2010.9711931
– year: 1972
  ident: 1
  publication-title: A Characteristics Formulation of the Neutron Transport Equation in Complicated Geometries
  contributor:
    fullname: Askew R
– volume: 47
  start-page: 1053
  issn: 0029-5515
  year: 2007
  ident: 21
  publication-title: Nucl. Fusion
  doi: 10.1088/0029-5515/47/8/040
  contributor:
    fullname: Zheng S
– volume: 122
  start-page: 151
  issn: 0029-5639
  year: 1996
  ident: 26
  publication-title: Nucl. Sci. Eng.
  doi: 10.13182/NSE96-3
  contributor:
    fullname: Petrovic I
– ident: 5
  doi: 10.1016/j.nucengdes.2008.04.014
– ident: 8
  doi: 10.1016/j.fusengdes.2008.12.041
– year: 2009
  ident: 17
  publication-title: Geant4 User's Guide for Application Developers (Version 4.9.3)
– volume: 2
  start-page: 821
  year: 2011
  ident: 20
  publication-title: Prog. Nucl. Sci. Technol.
  doi: 10.15669/pnst.2.821
  contributor:
    fullname: Wang G Z
– ident: 22
  doi: 10.1016/j.fusengdes.2006.07.068
– ident: 25
  doi: 10.1016/0306-4549(95)00058-5
– year: 1994
  ident: 28
  publication-title: The OECD/NEA Benchmark Calculations of Power Distributions within Assemblies
  contributor:
    fullname: Cavarec C
– ident: 6
  doi: 10.1016/S0306-4549(00)00038-4
– volume: 27
  start-page: 365
  year: 2007
  ident: 9
  publication-title: Chinese J. Nucl. Sci. Eng.
  contributor:
    fullname: Wu Y C
– year: 2011
  ident: 18
  publication-title: Fluka: a Multi-Particle Transport Code
  contributor:
    fullname: Ferrari A
– ident: 13
  doi: 10.1016/j.nima.2009.03.216
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SubjectTerms Approximation
CAD
Diamonds
Discretization
Error analysis
Mathematical analysis
Mathematical models
Method of characteristics
Transport
中子输运计算
光线追踪
几何建模
商务部
建模工具
特性
粒子输运
Title Preliminary study on CAD-based method of characteristics for neutron transport calculation
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