Ogawara R, Suda M, Hagihara T, Kodaira S, Hamano T
National Institute of Radiological Sciences, National Institute for Quantum and Radiological Science and Technology, Chiba, Japan.
Radiat Prot Dosimetry. 2019 May 1;183(1-2):280-284. doi: 10.1093/rpd/ncz002.
Neutron fields produced by an accelerator-driven neutron source are generally mixed radiation fields that consist of fast neutrons and gamma rays. To estimate the biological effects of fast neutrons precisely, the gamma ray dose contamination must be evaluated in neutron fields. In this work, we developed a discrimination technique for absorbed doses (60Co gamma-ray equivalent) of fast neutrons and gamma rays using an ionization chamber. The filter thickness dependences of the absorbed doses of fast neutrons and gamma rays are different for a given filter material. Thus, the absorbed doses of each type of radiation were distinguished by fitting the dose attenuation curve, which was measured with an ionization chamber and attenuation filters, with a two-component exponential function. The absorbed dose of fast neutrons and gamma rays with no attenuation filter was evaluated from the y-intercept of the fitting function. This technique was demonstrated in two neutron fields produced by 4 MeV proton and deuteron bombardment of a 9Be target. The thicknesses of the polyethylene attenuation filters were 0-350 mm. The dose attenuation coefficients of fast neutrons obtained by the two-component exponential fitting function for the 9Be(p,n)9 and 9Be(d,n) reactions showed differences of 1.5 and 1.7%, respectively, from the reference measurements using a CR-39 plastic nuclear track detector. The absorbed dose contributions of gamma rays in neutrons fields of the 9Be(p,n)9B and 9Be(d,n) reactions were evaluated as 30.2 ± 3.24% and 20.4 ± 5.16%, respectively, without polyethylene filters.
由加速器驱动的中子源产生的中子场通常是由快中子和伽马射线组成的混合辐射场。为了精确估计快中子的生物效应,必须在中子场中评估伽马射线剂量污染。在这项工作中,我们使用电离室开发了一种区分快中子和伽马射线吸收剂量(60Co伽马射线当量)的技术。对于给定的过滤材料,快中子和伽马射线吸收剂量的过滤厚度依赖性是不同的。因此,通过将用电离室和衰减过滤器测量的剂量衰减曲线与双组分指数函数拟合,来区分每种辐射类型的吸收剂量。根据拟合函数的y轴截距评估无衰减过滤器时快中子和伽马射线的吸收剂量。该技术在由4 MeV质子和氘核轰击9Be靶产生的两个中子场中得到了验证。聚乙烯衰减过滤器的厚度为0 - 350 mm。通过双组分指数拟合函数获得的9Be(p,n)9和9Be(d,n)反应的快中子剂量衰减系数与使用CR - 39塑料核径迹探测器的参考测量结果相比,分别相差1.5%和1.7%。在没有聚乙烯过滤器的情况下,9Be(p,n)9B和9Be(d,n)反应的中子场中伽马射线的吸收剂量贡献分别评估为30.2 ± 3.24%和20.4 ± 5.16%。