郝思佳, 张培升, 高永光, 刁均辉, 韩智杰. 钼锝靶件辐照装置堆外自然循环实验研究[J]. 原子能科学技术, 2024, 58(1): 103-111. DOI: 10.7538/yzk.2023.youxian.0103
引用本文: 郝思佳, 张培升, 高永光, 刁均辉, 韩智杰. 钼锝靶件辐照装置堆外自然循环实验研究[J]. 原子能科学技术, 2024, 58(1): 103-111. DOI: 10.7538/yzk.2023.youxian.0103
HAO Sijia, ZHANG Peisheng, GAO Yongguang, DIAO Junhui, HAN Zhijie. Experimental Study of Natural Circulation in Outside Reactor Radiation Device for Technetium Molybdenum Targets[J]. Atomic Energy Science and Technology, 2024, 58(1): 103-111. DOI: 10.7538/yzk.2023.youxian.0103
Citation: HAO Sijia, ZHANG Peisheng, GAO Yongguang, DIAO Junhui, HAN Zhijie. Experimental Study of Natural Circulation in Outside Reactor Radiation Device for Technetium Molybdenum Targets[J]. Atomic Energy Science and Technology, 2024, 58(1): 103-111. DOI: 10.7538/yzk.2023.youxian.0103

钼锝靶件辐照装置堆外自然循环实验研究

Experimental Study of Natural Circulation in Outside Reactor Radiation Device for Technetium Molybdenum Targets

  • 摘要: 钼锝同位素辐照装置的堆外热工水力研究,对于确定靶件的辐照参数和辐照安全具有重要意义,相关结果可为靶件的设计验证和入堆辐照提供技术支持。本文针对自主研发的钼得靶件辐照装置,设计了堆外传热实验台架,开展了钼锝靶件辐照装置堆外传热验证实验,对比分析了不同热流密度、不同模拟靶件外径、不同辐照装置结构等条件下实验段的温度分布。结果表明,辐照装置内导流管的设计可有效提高装置的自然循环能力,证明了所设计辐照装置的安全性。

     

    Abstract: Technetium molybdenum isotope is widely used in the field of nuclear medicine, and its demand accounts for about 80% of the world medical isotope demand. Irradiation in reactor is an important method for production of technetium molybdenum isotope, which is mainly produced and supplied by foreign reactors at present. Therefore, it is of great significance to realize independent production of technetium molybdenum isotope in China. Prior to the radiation study of technetium molybdenum target in reactor, an outside reactor heat transfer experiment should be conducted to verify the rationality of the irradiation device design and obtain its heat transfer characteristics, so as to ensure that the radiation of technetium molybdenum target in reactor will not endanger the safety of the target and reactor. At present, most of the studies on irradiation in reactors are not equipped with forced cooling conditions, and the design of radiation testing devices for natural cooling is rarely carried out. And there are few outside reactor verification experiments for irradiation devices. If necessary outside reactor heat transfer experiments can be carried out, it will provide important technical support for the safety review and subsequent design optimization of irradiation devices. The nuclear heat release generated by the target during irradiation in the reactor test needs to be dissipated by natural convection heat transfer. In order to verify the heat dissipation capacity of the target irradiation device, it is necessary to carry out the heat transfer verification test outside the reactor. In this paper, a natural cooling of technetium molybdenum target irradiation device was designed, and an outside reactor heat transfer test platform was designed to carry out an outside reactor heat transfer verification experiment. The temperature distribution of the experimental section under different heat fluxes, different simulated target diameters and different irradiation device structures was compared and analyzed. The analysis shows that the experiment covers the maximum heat flux of the actual situation inside the reactor, and there is no underheated boiling in this power range, which proves the safety of the designed irradiation device. The design of the diversion tube in the irradiation device can delay the underheated boiling point to 1.1 times of the original thermal power and improve the natural circulation capacity of the device. The increasing of ambient temperature in a certain range is conducive to the enhancement of natural convection heat transfer ability.

     

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