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Measurement of effective neutron cross section of the reaction ~(98)Mo (n, γ) 'Mo in TRR nuclear reactor by using thermal neutrons

机译:用热中子测量TRR核反应堆中〜(98)Mo(n,γ)“ Mo反应的有效中子截面

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The effective cross section of ~(98)Mo was measured using Westcott s convention. Diluted samples of natural MoO_3 were irradiated for 15 min in the channel D_6 of the core of the Tehran research reactor (TRR). The neutron flux at irradiation position was measured using diluted Au_2O_3 and CO_3O_4. The effective cross section was deduced as 0.526 ± 0.02b obtained from thermal flux. Index in Westcott s convention, r(T/T_0)/(1/2) at the irradiation position was obtained as 0.0545 ± 0.001. The contribution of the epithermal neutrons in total neutron activity of "Mo was 69%. The necessary correction factors such as thermal neutron self-shielding (Cth) and epithermal neutron self-shielding (C_(epi)), and gamma-ray attenuation (F_g) were taken into account. The results were presented and compared with effective cross section in evaluated nuclear data laboratory such as JENDL-4, KAERI and evaluated data by Mughabghab.
机译:〜(98)Mo的有效截面使用Westcott的惯例进行测量。将天然MoO_3的稀释样品在德黑兰研究堆(TRR)堆芯的通道D_6中照射15分钟。使用稀释的Au_2O_3和CO_3O_4测量照射位置的中子通量。由热通量得出的有效截面为0.526±0.02b。在韦斯科特的惯例中,在照射位置处的r(T / T_0)/(1/2)的指数为0.0545±0.001。超热中子对“ Mo”的总中子活度的贡献为69%。必要的校正因子包括热中子自屏蔽(Cth)和超热中子自屏蔽(C_(epi))和伽马射线衰减( F_g),将结果提交给JENDL-4,KAERI等核数据实验室和Mughabghab评估的数据,并与有效横截面进行比较。

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