A. Bakshi, S. Chatterjee, S. Dawn, Mudit Beck, T. Selvam
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引用次数: 0
摘要
在蒙特卡罗程序FLUKA的模拟基础上，设计并制作了1 Ci 241Am-Be源的中子源外壳屏蔽。使用FLUKA模拟计算了壳体表面和距离壳体表面1 m处的中子和光子剂量当量率，并使用伽马和中子剂量率计进行了测量。计算和测量的伽马和中子剂量当量率吻合良好。利用FLUKA模拟生成了源壳外的中子能谱，并用ROSPEC +简易闪烁光谱仪中子能谱系统进行了测量，结果也吻合较好。通过模拟得到了源外壳外的伽马能谱以及由于不锈钢和外壳中铅的活化产物而产生的剩余活度。
Shielding designing of 241Am-Be neutron source housing experiment and Monte Carlo simulation
Shielding of a neutron source housing for 1 Ci 241Am-Be source has been designed and fabricated based on the simulation carried out using Monte Carlo code FLUKA. Neutron and photon dose equivalent rates at the surface and at 1 m distance from the surface of the housing were calculated using FLUKA simulation and measured using gamma and neutron dose rate meters. The calculated and measured gamma and neutron dose equivalent rates agree well. Neutron spectra outside the source housing were generated using FLUKA simulation and measured with the ROSPEC + simple scintillation spectrometer neutron spectrometry system and also agree reasonably well. Gamma spectra outside the source housing and residual activity due to activation products in stainless steel and lead of the housing were also generated through simulation.
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