Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code BATAN-FUEL

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY
S. Pinem, D. Hartanto, Liem Peng Hong, W. Luthfi
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引用次数: 0

Abstract

This paper presents the generation and the verification of the few-group homogenized cross-sections for Batan-Fuel. This code is routinely used for fuel management in the RSG-GAS. The Monte Carlo code Serpent 2 code, in conjunction with the latest nuclear data library ENDF/B-VIII.0, was used. Calculations using the existing newly generated few-group cross-section data were carried out for the 88th core. The calculated core parameters such as excess reactivity and control rod worth are compared to the available experimental data. On the other hand, the fuel burnup fraction and radial power peaking factor (PPF) are compared to the results of Serpent 2. It was shown that the new cross-section data have more consistency and a better agreement excess reactivity and control rod worth compared to the experimental data. Similarly, the U-235 burnup fraction and radial power peaking factor by the new cross-section data are also shown to concur well with Serpent 2. The newly generated few-group cross-sections are recommended to replace the existing ones for the fuel management of RSG-GAS.
核心燃料管理规范BATAN-FUEL中RSG-GAS少组均质截面的改进
本文介绍了巴丹燃料少群均质截面的生成和验证。此代码通常用于RSG-GAS中的燃料管理。蒙特卡罗代码毒蛇2代码,结合最新的核数据库ENDF/B-VIII。0,被使用。利用现有的新生成的少数组截面数据对第88个岩心进行了计算。计算得到的堆芯参数如超反应性和控制棒值与现有实验数据进行了比较。另一方面,将燃油燃耗分数和径向功率峰值因子(PPF)与Serpent 2的结果进行了比较。结果表明,与实验数据相比,新截面数据具有更强的一致性和更好的超反应性与控制棒值的一致性。同样,通过新的截面数据,U-235燃耗分数和径向功率峰值系数也与Serpent 2相吻合。建议用新生成的少组截面代替现有的RSG-GAS燃料管理截面。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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