Benchmarking of activation reaction distribution in an intermediate energy neutron field using 3-D Monte Carlo Codes

Benchmarking of activation reaction distribution in an intermediate energy neutron field using 3-D Monte Carlo Codes
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使用 3-D 蒙特卡罗代码对中能中子场中的活化反应分布进行基准测试

DOI:
10.1093/rpd/ncr188
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发表时间:
2011
影响因子:
1
通讯作者:
T.Kosako
T.Kosako
中科院分区:
环境科学与生态学4区
文献类型:
--
作者:
T.Ogawa;M.N.Morev;M.Hirota;T.Abe;Y.Koike;S.Iwai;T.Iimoto;T.Kosako

文献摘要

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利用蒙特-卡罗程序计算了中能中子辐照混凝土屏蔽层内中子反应速率深度分布,并与实验结果进行了比较。在千叶的重离子医用加速器上,设置了一个由400 MeV核子-1碳离子轰击厚靶(停止长度)产生的正向中间中子照射场。在铁靶下游50厘米处安装了90厘米厚的普通混凝土屏蔽。铝、金和覆盖有镉的金的活化探测器被插入不同的深度。在暴露后提取辐照样品,并对每个样品进行伽马射线光谱测定。计算结果与实验结果的比较表明,除了表面的27 Al(n,X)24 Na反应外,低能和高能中子诱发反应的计算值与实验值吻合较好。
Neutron-induced reaction rate depth profiles inside concrete shield irradiated by intermediate energy neutron were calculated using a Monte-Carlo code and compared with an experiment. An irradiation field of intermediate neutron produced in the forward direction from a thick (stopping length) target bombarded by 400 MeV nucleon−1carbon ions was arranged at the heavy ion medical accelerator in Chiba. Ordinary concrete shield of 90 cm thickness was installed 50 cm downstream the iron target. Activation detectors of aluminum, gold and gold covered with cadmium were inserted at various depths. Irradiated samples were extracted after exposure and gamma-ray spectrometry was performed for each sample. Comparison of experimental and calculated shows good agreement for both low- and high-energy neutron-induced reaction except for27Al(n,X)24Na reaction at the surface.