-
核反应堆的中子学模拟计算中，核数据的不确定度导致的积分量计算结果的不确定度，通常采用基于微扰理论的灵敏度与不确定度分析方法（简称灵敏度法）量化.灵敏度分析法原则上只适用于线性模型，且一般输运计算程序难以直接进行灵敏度分析.而抽样法直接抽样核数据输入中子学计算程序进行计算，通过对计算结果的统计分析评估计算量的不确定度.抽样法易于实现、计算精确、且适用性强.在灵敏度分析与不确定度量化程序SURE中，增加了抽样法不确定度的量化功能.为将抽样法不确定度量化应用于复杂问题的模拟计算，需对其进行细致的考核.为此，选取简单的临界基准实验模型，分别采用灵敏度分析法和抽样法进行不确定度量化，得到了各核素各反应道核数据导致的keff计算不确定度.对比显示，两种方法的不确定度计算结果有很好的符合，验证了SURE程序抽样法功能的正确性.抽样法计算的keff符合正态分布，说明在一般核数据的不确定度范围内，keff与核数据近似成线性关系，利用灵敏度分析法评估keff计算值的不确定度是适用的.
[1] USDOE 2002 A Technology Roadmap for Generation-IV Nuclear Energy Systems USDOE/GIF-002-00（Washington:USDOE) p1
[2] Salvatores M, Jacqmin R 2008 Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations NEA/WPEC-26（Paris:OECD/NEA) p1
[3] Marable J H, Weisbin C R 1979 Theory and Application of Sensitivity and Uncertainty Analysis（Oak Ridge:Oak Ridge National Laboratory) p16
[4] Gilli L, Lathouwers D, Kloosterman J L, van der Hagen T H J J 2013 Nucl. Sci. Eng. 175 172
[5] Kim D H, Gil C S, Lee Y O 2008 International Conference on Nuclear Data for Science and Technology Nice, France, April 22-27, 2007 p289
[6] Kodeli I 2008 Sci. Technol. Nucl. Instll. 2008 659861
[7] Pusa M 2012 Sci. Technol. Nucl. Instll. 2012 157029
[8] Williams M L, Rearden B T 2008 Nucl. Data Sheets 109 5
[9] Hu Z H, Wang J, Sun W L, Li M S 2013 Atom. Energy Sci. Technol. 47 25 （in Chinese)[胡泽华, 王佳, 孙伟力, 李茂生2013原子能科学技术47 25]
[10] Dossantos-Uzarralde P J, Guittet A 2008 Nucl. Data Sheets 109 2894
[11] Gilli L, Lathouwers D, Kloosterman J L, van der Hagen T H J J, Koning A J, Rochman D 2013 Ann. Nucl. Energy 56 71
[12] Williams M M R 2007 Nucl. Sci. Eng. 155 109
[13] Wieselquist W, Zhu T, Vasiliev A, Ferroukhi H 2013 Sci. Technol. Nucl. Instll. 2013 549793
[14] Zhu T, Vasiliev A, Ferroukhi H, Pautz A 2014 Nucl. Data Sheets 118 453
[15] Zhu T, Vasiliev A, Ferroukhi H, Pautz A 2015 Ann. Nucl. Energy 75 713
[16] Zhu T, Vasiliev A, Ferroukhi H, Pautz A, Tarantola S 2015 J. Nucl. Sci. Technol. 52 8
[17] Chadwick M B, Herman M, Oblozinsky P 2011 Nucl. Data Sheets 112 110
[18] Engle W W J 1967 A User's Manual for ANISN:A One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering（Oak Ridge:Oak Ridge Gaseous Diffusion Plant Computing Technology Center) p1
[19] Macfarlane R E, Muir D W, Boicourt R M, Kahler A C 2012 The NJOY Nuclear Data Processing System (Los Alamos:Los Alamos National Laboratory) p1
[20] Kiedrowski B C, Brown F B 2013 Nucl. Sci. Eng. 174 227
[21] Briggs J B 2004 International Handbook of Evaluated Criticality Safety Benchmark Experiments（Paris:Nuclear Energy Agency) p1
-
[1] USDOE 2002 A Technology Roadmap for Generation-IV Nuclear Energy Systems USDOE/GIF-002-00（Washington:USDOE) p1
[2] Salvatores M, Jacqmin R 2008 Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations NEA/WPEC-26（Paris:OECD/NEA) p1
[3] Marable J H, Weisbin C R 1979 Theory and Application of Sensitivity and Uncertainty Analysis（Oak Ridge:Oak Ridge National Laboratory) p16
[4] Gilli L, Lathouwers D, Kloosterman J L, van der Hagen T H J J 2013 Nucl. Sci. Eng. 175 172
[5] Kim D H, Gil C S, Lee Y O 2008 International Conference on Nuclear Data for Science and Technology Nice, France, April 22-27, 2007 p289
[6] Kodeli I 2008 Sci. Technol. Nucl. Instll. 2008 659861
[7] Pusa M 2012 Sci. Technol. Nucl. Instll. 2012 157029
[8] Williams M L, Rearden B T 2008 Nucl. Data Sheets 109 5
[9] Hu Z H, Wang J, Sun W L, Li M S 2013 Atom. Energy Sci. Technol. 47 25 （in Chinese)[胡泽华, 王佳, 孙伟力, 李茂生2013原子能科学技术47 25]
[10] Dossantos-Uzarralde P J, Guittet A 2008 Nucl. Data Sheets 109 2894
[11] Gilli L, Lathouwers D, Kloosterman J L, van der Hagen T H J J, Koning A J, Rochman D 2013 Ann. Nucl. Energy 56 71
[12] Williams M M R 2007 Nucl. Sci. Eng. 155 109
[13] Wieselquist W, Zhu T, Vasiliev A, Ferroukhi H 2013 Sci. Technol. Nucl. Instll. 2013 549793
[14] Zhu T, Vasiliev A, Ferroukhi H, Pautz A 2014 Nucl. Data Sheets 118 453
[15] Zhu T, Vasiliev A, Ferroukhi H, Pautz A 2015 Ann. Nucl. Energy 75 713
[16] Zhu T, Vasiliev A, Ferroukhi H, Pautz A, Tarantola S 2015 J. Nucl. Sci. Technol. 52 8
[17] Chadwick M B, Herman M, Oblozinsky P 2011 Nucl. Data Sheets 112 110
[18] Engle W W J 1967 A User's Manual for ANISN:A One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering（Oak Ridge:Oak Ridge Gaseous Diffusion Plant Computing Technology Center) p1
[19] Macfarlane R E, Muir D W, Boicourt R M, Kahler A C 2012 The NJOY Nuclear Data Processing System (Los Alamos:Los Alamos National Laboratory) p1
[20] Kiedrowski B C, Brown F B 2013 Nucl. Sci. Eng. 174 227
[21] Briggs J B 2004 International Handbook of Evaluated Criticality Safety Benchmark Experiments（Paris:Nuclear Energy Agency) p1
| 引用本文: |
|
| Citation: |
|
计量
- 文章访问数: 531
- PDF下载量: 173
- 被引次数: 0
下载: