| 二维输运燃耗耦合程序开发与验证 |
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| 引用本文： | 胡小利,陈义学,杨寿海,吴军.二维输运燃耗耦合程序开发与验证[J].原子能科学技术,2013,47(Z1):360-364. |
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| 作者姓名： | 胡小利 陈义学 杨寿海 吴军 |
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| 作者单位： | 1.华北电力大学 核科学与工程学院，北京102206；2.深圳中广核工程设计有限公司，广东 深圳518057 |
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| 摘 要： | 为准确计算反应堆内燃耗问题，建立了基于二维离散纵标法及BATEMAN燃耗方法的输运燃耗耦合计算方法，并开发相应的计算程序。基于ENDF/B-Ⅶ评价库开发了175群中子和42群光子截面数据库MUSE-F1.0，采用OECD/NEA发布的MOX燃料快堆基准题对耦合计算方法及程序系统进行验证计算。结果表明，耦合计算程序结果与基准题吻合良好，误差在8%以内，初步验证了耦合计算程序在快堆嬗变工程应用中的可行性。
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| 关 键 词： | 输运计算 燃耗方法 离散纵标 截面数据库 |
Research and Validation on Two-Dimensional Transport-Depletion Program |
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| HU Xiao-li,CHEN Yi-xue,YANG Shou-hai,WU Jun.Research and Validation on Two-Dimensional Transport-Depletion Program[J].Atomic Energy Science and Technology,2013,47(Z1):360-364. |
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| Authors: | HU Xiao-li CHEN Yi-xue YANG Shou-hai WU Jun |
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| Affiliation: | 1.School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China;2.China Nuclear Power Engineering Design Limited Company, Shenzhen 518057, China |
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| Abstract: | To describe depletion problems in reactor precisely, the system based on two-dimensional discrete ordinates transport theory and BATEMAN burnup method was set up, and the corresponding code was developed. The matching 175-group neutron and 42-group photon cross section data MUSE-F1.0 was developed based on ENDF/B-Ⅶ. The code was validated with benchmark on MOX fuel fast reactor of OECD/NEA. The computed data are in accord with benchmark, and the error is less than 8%. The results prove that the couple system is feasible in fast reactor transmutation application. |
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| Keywords: | transport calculation depletion method discrete ordinates MUSE-F1 0 cross section library |
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