期刊文献+

水溶液堆中子学优化和提取方式对^(99)Mo生产效率的影响研究 被引量:1

Effect of neutronics optimization and extraction method on the production efficiency of ^(99)Mo in an aqueous reactor
原文传递
导出
摘要 医用同位素生产水溶液堆(Medical Isotope Production aqueous Reactor,MIPR)具有尺寸小、功率低和固有安全性高等优点,是^(99)Mo和其他医用同位素生产的较佳候选堆型之一。本文重点研究低富集铀启堆模式下的提取方式以及处理能力对MIPR生产^(99)Mo效率的影响。采用SCALE6.1蒙特卡罗程序、ENDF/B-Ⅶ238群数据库进行计算。首先,根据已有的实验数据对MIPR中子学计算方法进行了验证,并对堆芯设计进行了中子学优化。然后,根据优化的堆芯模型对不同提取方式以及处理能力下的^(99)Mo生产效率进行了研究,确定了可实现临界的铀浓度与富集度范围。结果表明:在不同富集度下存在最小临界质量,且随235U富集度的增加,最小临界铀质量时的铀浓度减小;有效倍增因子随硝酸浓度增加线性减小,相应的硝酸反应性系数约为-1.400×10^(-2)L·mol^(-1);随着铀浓度的增加,空泡和温度反应性系数减小,对应反应性系数分别约在(-100~-250)×10-3℃^(−1)和(-18~-30)×10-5℃^(−1)范围。MIPR生产^(99)Mo的效率在线提取方式略高于离线批处理方式,5 d生产周期下,生产效率提高约16%。后处理能力对在线提取方式的生产效率影响较大,5 d生产周期下,后处理速率提高5倍,生产效率提高约113%。 [Background]The medical isotope production aqueous reactor(MIPR)has advantages of small size,low power,and high inherent safety,hence is one of better candidate reactor types for the production of^(99)Mo and other medical isotopes.[Purpose]This study aims at the effects of extraction methods and reprocessing capacity on the production efficiency of^(99)Mo based on low-enriched uranium MIPR designed with neutronic optimization.[Methods]First,the calculation method was verified according to existing experimental data,and the neutronic optimization of the MIPR was performed for core design by using SCALE6.1 code and ENDF/B-VII database with 238 groups.Then,the^(99)Mo production efficiency under different extraction methods as well as processing capacities was investigated based on the optimized core structure.The range of achievable critical uranium concentration and enrichment was determined.[Results]There is a minimum critical mass under different enrichment,and with the increase of 235U enrichment,the uranium concentration at the minimum critical uranium mass decreases.The effective multiplication factor decreases linearly with an increase in nitric acid concentration,and the corresponding nitric acid reactivity coefficient is approximately−1.400×10^(-2)L·mol^(-1).With an increase in uranium concentration,the void and temperature reactivity coefficients decrease,and the corresponding reactivity coefficients are approximately(−100~−250)×10−3℃^(−1)and(−18~−30)×10−5℃^(−1).[Conclusion]The production efficiency of the MIPR production of the^(99)Mo online extraction method is slightly greater than that of the offline batch processing method with an increment of about 16%under a five-day production cycle.The reprocessing capability has a greater impact on the production efficiency of the online extraction method.If the reprocessing rate is increased five times,the increment of production efficiency is about 113%under a five-day production cycle.
作者 郁长清 朱贵凤 严睿 邹杨 YU Changqing;ZHU Guifeng;YAN Rui;ZOU Yang(Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China;University of Chinese Academy of Sciences,Beijing 100049,China)
出处 《核技术》 CAS CSCD 北大核心 2023年第9期125-134,共10页 Nuclear Techniques
基金 国家自然科学基金(No.12005290) 中国科学院青年创新促进会(No.2020261) 中国科学院上海分院"基础研究特区计划"(No.JCYJ-SHFY-2021-003)资助。
关键词 水溶液堆 医用同位素 铀质量 ^(99)Mo 反应性系数 Aqueous reactor Medical isotopes Uranium mass ^(99)Mo Reactivity coefficient
  • 相关文献

参考文献8

二级参考文献38

  • 1邓启民,李茂良,程作用.医用同位素生产堆(MIPR)生产^(99)Mo的应用前景[J].核科学与工程,2006,26(2):165-167. 被引量:13
  • 2Maria Lyra. Alternative production methods to face global molybdenum-99 supply shortage[J]. Hellenic Journal of Nuclear Medicine, 2011, 14(1): 49-55. 被引量:1
  • 3Steven C, van der Marck & Arjan J, Koning & Kevin E. Charltun. The options for the future production of the medical isotope 99Mo[J]. European Journal of Nuclear Medicine and Molecular Imaging, 2010, 37:1817-1820. 被引量:1
  • 4Health and Consumers Directorate-general, European Commission. Preliminary report on supply of radio- isotopes for medical use and current developments in nuclear medicine[C]. SANCO/C/3/HW D(2009) Rev. 8, Luxembourg, 30 October 2009. 被引量:1
  • 5OECD Nuclear Energy Agency (NEA). The path to a reliable supply of medical radioisotopes[C]. Nuclear Energy in Perspective. June, 2011. 被引量:1
  • 6International Atomic Energy Agency. Production technologies for molybdenum-99 and technetium-99m[C]. IAEA-TECDOC-1065. February 1999. 被引量:1
  • 7Sayed M Qaim. The present and future of medical radionuclide production[C]. Radiochimica Acta. A special Golden Jubilee Issue in August/September 2012. 被引量:1
  • 8Lambrechta R M, Sekine T, Vera R H. Alice predictions on the accelerator production of molybdenum-99[J]. Applied Radiation and Isotopes 1999, 51:177-182. 被引量:1
  • 9Scholten B, Lambrecht R M, Cogneauc M, et al. Excitation functions for the cyclotron production of 99mTC and 99Mo[J]. Applied Radiation and Isotopes 1999, 51: 69-80. 被引量:1
  • 10Gagnona K, Bdnardb F, Kovacsc M, et al Cyclotron production of 99mTc: Experimental measurement of the 100Mo(p,x)99Mo, 99mTc and 99gTc excitation functions from 8 to 18 MeV[J]. Nuclear Medicine and Biology, 2011, 38:907-916. 被引量:1

共引文献37

同被引文献9

引证文献1

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部