| 基于线性核素链的燃耗算法与蒙特卡罗程序耦合计算 |
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| 引用本文： | 吴明宇,王事喜,杨勇,张强.基于线性核素链的燃耗算法与蒙特卡罗程序耦合计算[J].强激光与粒子束,2013,25(1):248-252. |
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| 作者姓名： | 吴明宇 王事喜 杨勇 张强 |
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| 作者单位： | 1.中国原子能科学研究院, 北京 1 0241 3 |
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| 基金项目： | 国家高技术发展计划项目 |
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| 摘 要： | 根据线性核素链原理和反应堆燃耗的特点，建立相应核数据库并采用回溯算法生成自适应核素链，完成核素的遍历和计算，形成多群点燃耗计算程序，能够独立进行燃耗计算并具有完整的输出结果形式。同时将所开发的燃耗计算程序与蒙特卡罗程序进行耦合，完成接口模块的设计，形成可用于研究堆和核电站的燃耗-输运耦合计算工具。将所开发的输运-耦合计算程序应用于中国实验快堆首炉堆芯燃耗的计算，将计算结果与现有设计数据进行比较。经过初步分析表明:新的燃耗计算程序能够精确计算锕系核素含量，包括易裂变核素和生成量很小的次锕系核素。对某些锕系核素如Pu241的计算结果还存在较大偏差，这需要对计算结果进一步分析，来确认偏差是来自计算过程还是相关的截面数据。整个燃耗-输运耦合计算系统对裂变产物的处理和反应性变化的计算也与现有的设计数据符合良好。
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| 关 键 词： | 燃耗计算 核素链 图论 回溯算法 |
| 收稿时间： | 2012/6/10 |
Monte Carlo program coupling with depletion code based on linear nuclide chainWu Ming |
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| Wu Mingyu,Wang Shixi,Yang Yong,Zhang Qiang.Monte Carlo program coupling with depletion code based on linear nuclide chainWu Ming[J].High Power Laser and Particle Beams,2013,25(1):248-252. |
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| Authors: | Wu Mingyu Wang Shixi Yang Yong Zhang Qiang |
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| Affiliation: | 1.China Institute of Atomic Energy,Beijing 102413,China |
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| Abstract: | Based on the linear nuclide chain method and the burn up features of reactors, the depletion nuclide database is established and the densities of all the nuclides in the burn up system are calculated using the backtracking algorithm. The depletion code can solve the burn up problem independently and have integrated output form, which makes it convenient to couple with the Monte Carlo program by the interface module to do the coupling transport-depletion calculation for reactor systems. The benchmark burnup of the first core of China Experimental Fast Reactor(CEFR) is calculated with the transport-depletion code to verify the function correctness. The comparison with the results obtained already using other codes shows that the new depletion program can calculate the density of actinides with high fidelity, including fissionable nuclides and some minor actinides with puny yields. There is difference with the inventory of Pu241. This should be analyzed further to determinate whether the difference comes from the depletion program or from the related cross section data. The calculation results of fission products and reactivity tally with the designed results well. |
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| Keywords: | depletion calculation nuclide chain graph theory backtracking algorithm |
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