CEFR反射层区批量辐照生产同位素89Sr和63Ni可行性分析

Feasibility Analysis on Batch Irradiation Production of Isotopes 89Sr and 63Ni in CEFR Reflector

  • 摘要: 中国实验快堆(CEFR)中子通量高、中子能谱硬,是我国重要的研究堆辐照平台。为验证利用快中子(n,p)阈反应在CEFR反射层区批量辐照生产同位素的可行性,本研究采用蒙特卡罗程序进行堆芯中子学建模与分析,并结合中国原子能科学研究院自主研发的多群点燃耗程序开展堆芯物理与热工耦合计算,在堆芯外围反射层区批量布置天然丰度Y2O3与天然铜靶,对辐照组件的产能、品质进行计算评估,并对生产方案进行初步安全分析。结果表明,在堆芯燃料装载不发生改变的情况下,CEFR具备作为快中子辐照平台生产89Sr与63Ni同位素的能力;此类“搭车”辐照生产同位素的模式对其他辐照考验任务影响较小,同时可保证CEFR反应性控制,燃料组件功率,组件释热、源项等各项指标,满足CEFR安全运行要求。

     

    Abstract: The China Experimental Fast Reactor (CEFR) has a high neutron flux and a hard neutron energy spectrum, making it an important research reactor irradiation platform. To verify the feasibility of batch irradiation production of isotopes using the fast neutron (n,p) threshold reaction on the CEFR, this study employs the Monte Carlo program for core neutron modeling and analysis. This is combined the multi-group burnup calculation code independently developed by China Institute of Atomic Energy to perform coupled neutronics and thermal-hydraulic calculations. This study designed an irradiation scheme for batch placement of naturally abundant Y2O3 and natural copper targets in the reflector region. The production capacity and product quality were evaluated. Furthermore, a preliminary safety analysis of the production plan was completed. The results show that, without changing the fuel loading of the core, the CEFR has the ability to produce isotope 89Sr and isotope 63Ni as a fast neutron irradiation platform. The isotopes production mode has relatively little impact on other irradiation test tasks. Meanwhile, it can ensure various parameters of CEFR, including reactivity control, fuel assembly power, component heat release, and source term, thereby meeting the safety operation requirements of the CEFR.

     

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