MCNP simulations for the n_TOF NEAR station

Sotiris Alexandros Kopanos
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Abstract

The NEAR station is the newest experimental area of the n_TOF facility at CERN, utilizing the spallation process to generate extremely high neutron flux within a broad energy spectrum. As part of the campaign for the determination of the neutron beam spectral features, numerous foils have been irradiated last year and the induced activities were measured implementing a HPGe detector. Experimental data analysis of the irradiated foil’s gamma-ray spectra, yielded the saturated activities for each material that can be used to unfold the characteristics of the neutron flux through data deconvolution using the SAND-II code. Since this process is mostly mathematical and does not account for geometry, shielding and scattering effects, correction factors need to be defined and applied to the measured activities in order to produce a more robust and accurate result. For this purpose Monte Carlo simulations using the MCNP code were performed to investigate the self-shielding of the foils and its effect on both the neutron flux and the gamma rays emitted. Also, a detailed simulation including the full geometry of the experimental setup was developed and used in order to investigate possible influence of the peripheral materials (cement, other foils, mylar as well as the aluminum sample holder and rails) to the total flux that reaches each individual foil through scattering of neutrons.
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n_TOF近站的MCNP仿真
NEAR站是欧洲核子研究中心n_TOF设施的最新实验区,利用散裂过程在广泛的能谱内产生极高的中子通量。作为确定中子束光谱特征活动的一部分,去年对许多箔进行了辐照,并使用HPGe探测器测量了诱导活度。对辐照箔的伽玛射线能谱进行实验数据分析,得出了每种材料的饱和活度,可用于通过使用SAND-II代码进行数据反褶积来揭示中子通量的特征。由于这一过程主要是数学的,不考虑几何、屏蔽和散射效应,因此需要确定校正因子并将其应用于测量的活动,以便产生更可靠和准确的结果。为此,利用MCNP程序进行了蒙特卡罗模拟,研究了金属箔的自屏蔽特性及其对中子通量和伽马射线发射的影响。此外,还开发了一个详细的模拟,包括实验装置的完整几何形状,并用于研究外围材料(水泥、其他箔、mylar以及铝样品支架和导轨)对通过中子散射到达每个箔的总通量的可能影响。
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