| 混合堆增殖钍基燃料组件中子学分析 |
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| 引用本文： | 马续波,陈义学,全国萍,王悦,韩静茹,陆道纲.混合堆增殖钍基燃料组件中子学分析[J].核动力工程,2012,33(1):129-133. |
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| 作者姓名： | 马续波 陈义学 全国萍 王悦 韩静茹 陆道纲 |
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| 作者单位： | 华北电力大学核科学与工程学院,北京,102206 |
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| 基金项目： | 国家自然科学基金，中央高校基本科研业务费专项资金，长江学者和创新团队发展计划，先进核燃料循环863项目 |
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| 摘 要： | 采用压水堆17×17燃料组件模型,用燃料组件参数计算程序DRAGON分别对混合堆增殖钍燃料组件和全铀组件的中子学特性进行了研究,分析组件的燃料温度系数、慢化剂温度系数及其与燃耗的关系。计算结果表明,混合堆增殖钍燃料组件和全铀组件的中子特性相似,但钍燃料组件中的乏燃料组件中的次锕系核素(MA)的含量明显减少。
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| 关 键 词： | 混合堆增殖钍基燃料 中子学 温度系数 |
Neutronics Calculation of Fusion-Fission Hybrid Breeding Thorium Fuel Assembly |
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| MA Xu-bo
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CHEN Yi-xue
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QUAN Guo-ping
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WANG Yue
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HAN Jing-ru
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LU Dao-gang.Neutronics Calculation of Fusion-Fission Hybrid Breeding Thorium Fuel Assembly[J].Nuclear Power Engineering,2012,33(1):129-133. |
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| Authors: | MA Xu-bo CHEN Yi-xue QUAN Guo-ping WANG Yue HAN Jing-ru LU Dao-gang |
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| Affiliation: | School of Nuclear Science and Technology,North China Electric Power University,Beijing 102206,China |
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| Abstract: | A preliminary comparative study of the physical properties among 17×17 fuel assembly in PWRs for prototype between uranium assembly and hybrid breeding thorium-based assembly has been investigated respectively using the DRAGON software.The parameters such as fuel temperature coefficient,moderator temperature coefficient and that variation as a function of operation period have been investigated.Results show that the neutron properties of uranium-based assembly and hybrid breeding thorium-based assembly are similitude,but MA mass of hybrid breeding thorium-based assembly is evidently less than those of the uranium assembly. |
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| Keywords: | Fusion-fission hybrid breeding thorium fuel Neutronics Temperature coefficient |
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