不同冷却剂对铅冷快堆堆芯物理参数的影响与分析
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TL326

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国家自然基金资助项目(11965001),核技术应用教育部工程研究中心开放基金资助项目(HJSJYB2021-9),东华理工大学博士启动基金资助项目(DHBK2021005),江西省质谱科学与仪器重点实验室开放基金资助项目(JXMS202111)


The Impact and Analysis of Different Coolants on the Core Physics Parameters of Lead-Cooled Fast Reactors
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    摘要:

    随着我国能源结构深化改革的推进,积极发展核能已成为主要趋势。第四代核能系统代表着核电发展的趋势和技术前沿,因此铅冷快中子反应堆的研究在国际上备受关注。本文基于麻省理工学院开发的反应堆蒙特卡洛中子输运方程开源软件OpenMC,以铅冷快中子欧洲示范堆(Advanced Lead Fast Reactor European Demonstrator ,ALFRED)为研究对象,选取两种不同的堆芯冷却剂开展铅冷快堆堆芯物理计算。研究结果表明,在装载相同燃料的情况下,采用铅-铋冷却剂可以提高堆芯的初始反应性271pcm;堆芯在正常商运状态下具有更高的堆芯有效缓发中子份额;堆芯的中子能谱更宽、更硬;对于燃料中的239Pu核素,燃烧效果更好。因此,ALFRED堆芯采用铅-铋合金冷却剂时,具有更高的有效增殖因子,有望提高堆芯的控制性和燃耗性能,并有效减少放射性废物的产生,为铅冷快中子反应堆欧洲示范堆堆芯设计和性能优化提供了有益的参考。

    Abstract:

    The advancement of deepening reforms in the energy structure of the country has underscored the imperative for active development within the domain of nuclear energy, emerging as a predominant trajectory. Representing the forefront of nuclear power evolution, fourth-generation nuclear energy systems have garnered considerable international attention. Particularly, the research into lead-cooled fast neutron reactors has been highly acclaimed on a global scale. Leveraging the open-source reactor Monte Carlo neutron transport equation software OpenMC, developed by the esteemed institution of the Massachusetts Institute of Technology (MIT), this study centers its investigation on the Advanced Lead Fast Reactor European Demonstrator (ALFRED). Employing ALFRED as the focal point, the study meticulously selects and examines two distinct coolant materials for the reactor core, thereby elucidating essential insights into the physical dynamics of lead-cooled fast reactors. The findings delineate that, under identical fuel loading conditions, the utilization of lead-bismuth coolant yields a significant enhancement in the reactor core's initial reactivity by 271pcm. Moreover, the reactor core manifests a heightened proportion of effective delayed neutrons during normal commercial operation. Additionally, the neutron spectrum of the reactor core exhibits broader and harder characteristics, while also showcasing improved burning efficacy for the 239Pu nuclide within the fuel matrix. Consequently, the employment of lead-bismuth alloy coolant within the ALFRED reactor core culminates in a heightened effective multiplication factor. This augmentation holds promise for enhancing the controllability and burnup performance of the reactor core, while concurrently mitigating the generation of radioactive waste. In essence, this study furnishes valuable insights into the design and performance optimization of the reactor core for the lead-cooled fast neutron reactor European Demonstrator.

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李凯旋,张子雄,魏强林,等. 不同冷却剂对铅冷快堆堆芯物理参数的影响与分析[J]. 科学技术与工程, 2024, 24(28): 12152-12158.
LI Kai-xuan, ZHANG Zi-xiong, WEI Qiang-lin, et al. The Impact and Analysis of Different Coolants on the Core Physics Parameters of Lead-Cooled Fast Reactors[J]. Science Technology and Engineering,2024,24(28):12152-12158.

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  • 收稿日期:2023-12-22
  • 最后修改日期:2024-07-30
  • 录用日期:2024-03-21
  • 在线发布日期: 2024-11-05
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