首页> 外文期刊>International Journal of Nuclear Energy Science and Technology >Feasibility study for production of ~(99)Mo and ~(99m)Tc by the neutron activation of ~(98)Mo in the MNSR reactor
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Feasibility study for production of ~(99)Mo and ~(99m)Tc by the neutron activation of ~(98)Mo in the MNSR reactor

机译:在MNSR反应堆中通过中子活化〜(98)Mo产生〜(99)Mo和〜(99m)Tc的可行性研究

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摘要

The calculated weekly specific activities of~(99)Mo and~(99m)Tc produced from the irradiation of the MoO_(3)targets in the Miniature Neutron Source Reactor (MNSR) are presented in this paper. The productions of the~(99)Mo and~(99m)Tc were modelled and calculated through a set of differential equations using the Mathcad program. The resonance self-shielding factor (G_(res)) was calculated using the MATSSF and MCNP4C codes. The effects of the physical parameters such as the neutron flux and irradiation time on the weekly specific activities of~(99)Mo and~(99m)Tc have been analysed. It was found that the optimum irradiation scheme was achieved when the MNSR was operated for an extended period of 5 hours a day for 5 days a week at the neutron flux of 7.5×10~(11)n.cm~(‒2).s~(‒1). The weekly specific activities for the~(99)Mo and~(99m)Tc which can be produced in the MNSR, filling each of the five inner irradiation sites with 20 g of the MoO_(3)targets and using the regular natural convection method to cool the reactor, were 7.20 and 5.05 mCi.g~(‒1), respectively.
机译:本文介绍了在微型中子源反应堆(MNSR)中辐照MoO_(3)靶产生的〜(99)Mo和〜(99m)Tc的每周比活。使用Mathcad程序通过一组微分方程对〜(99)Mo和〜(99m)Tc的产量进行建模和计算。使用MATSSF和MCNP4C代码计算共振自屏蔽因子(G_(res))。分析了诸如中子通量和辐照时间等物理参数对〜(99)Mo和〜(99m)Tc每周比活的影响。研究发现,当中子通量为7.5×10〜(11)n.cm〜()2)的条件下,每周5天,每天延长5小时运行MNSR时,可获得最佳的辐照方案。 s〜(‒1)。可以在MNSR中产生的〜(99)Mo和〜(99m)Tc的每周特定活动,用20 g MoO_(3)靶填充五个内部辐照位点中的每个辐照位,并使用常规自然对流方法冷却反应器的温度分别为7.20和5.05 mCi.g〜(‒1)。

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