Enhancement of sub-thermal neutron flux through cold polyethylene

IF 1 Q3 NUCLEAR SCIENCE & TECHNOLOGY
D. Fritz, Y. Danon, E. Liu
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引用次数: 3

Abstract

Total thermal neutron cross section measurements serve as the primary means of validation for thermal neutron scattering kernels, an important quantity for neutron transport calculations. In an effort to improve the quality of thermal neutron scattering kernels, researchers at Rensselaer Polytechnic Institute (RPI) designed and constructed a polyethylene based cold moderation system to enhance neutron flux below 10 meV when coupled with the Enhanced Thermal Target (ETT) at the RPI Gaerttner LINAC. The final design yielded an increase in sub-thermal neutron flux (below 10 meV) by a factor of 4.5 for a moderator temperature of 37.5 K relative to the ETT alone. A further increase to a factor of 6 is expected after a minor geometry modification and decrease in polyethylene temperature to 25 K. This novel capability will be used to conduct total thermal neutron cross section measurements from 0.0005–10 eV for different materials including moderator materials.
通过冷聚乙烯增强亚热中子通量
热中子总截面测量是验证热中子散射核的主要手段,是中子输运计算的重要量。为了提高热中子散射核的质量,伦斯勒理工学院(RPI)的研究人员设计并构建了一个基于聚乙烯的冷调节系统,当与RPI Gaerttner LINAC的增强型热靶(ETT)耦合时,可以将中子通量提高到10 meV以下。最终设计产生的亚热中子通量(低于10 meV)在37.5 K的慢化剂温度下相对于ETT单独增加了4.5倍。在微小的几何形状修改和聚乙烯温度降低到25 K后,预计进一步增加到6倍。这种新能力将用于对包括慢化剂材料在内的不同材料进行0.0005-10 eV的总热中子截面测量。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Journal of Neutron Research
Journal of Neutron Research NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
2.30
自引率
9.10%
发文量
23
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