TY - JOUR
T1 - A design study of application of the CsI self-activation method to the neutron rem-counter technique
AU - Ueki, Taishi
AU - Nohtomi, Akihiro
AU - Wakabayashi, Genichiro
AU - Fukunaga, Junichi
AU - Kato, Toyoyuki
AU - Ohga, S.
N1 - Funding Information:
This study was performed in part under the Cooperative Research at Kindai University Reactor supported by the Graduate School of Engineering, Osaka University. The authors thank Mr. R. Kurihara and Ms. Y. Hanada of the Department of Health Sciences, Kyushu University, for their cooperation in the experiments, and also Mr. H. Ito of the HORIBA for his provision of information regarding Radi PA-1100.
Funding Information:
This study was performed in part under the Cooperative Research at Kindai University Reactor supported by the Graduate School of Engineering , Osaka University . The authors thank Mr. R. Kurihara and Ms. Y. Hanada of the Department of Health Sciences, Kyushu University, for their cooperation in the experiments, and also Mr. H. Ito of the HORIBA for his provision of information regarding Radi PA-1100.
Publisher Copyright:
© 2019 Elsevier Ltd
PY - 2019/9
Y1 - 2019/9
N2 - A design study of application of the CsI self-activation method to the “neutron rem-counter technique” was investigated. A CsI crystal served as both the main target material and 4π counter of neutron activation method in our proposed CsI self-activation method. A commercially available CsI gamma-ray dosimeter was selected as the neutron detector and surrounded with several neutron filters made of polyethylene and silicon rubber containing B4C. The geometric structure of these neutron filters was optimized by a Monte Carlo calculation to make the neutron response similar to the ICRP-74 rem-response. Optimization of this method, the residual sum of squares (RSS) of the calculated neutron response and the ICRP-74 rem-response were minimized by changing the thickness of each filter sequentially. In addition, experimental verification using a Pu–Be source and photoneutrons from a 10 MV-X medical linac has been conducted. From these results, it is concluded that it may be practical for evaluating neutron ambient dose-equivalent simply around medical linacs.
AB - A design study of application of the CsI self-activation method to the “neutron rem-counter technique” was investigated. A CsI crystal served as both the main target material and 4π counter of neutron activation method in our proposed CsI self-activation method. A commercially available CsI gamma-ray dosimeter was selected as the neutron detector and surrounded with several neutron filters made of polyethylene and silicon rubber containing B4C. The geometric structure of these neutron filters was optimized by a Monte Carlo calculation to make the neutron response similar to the ICRP-74 rem-response. Optimization of this method, the residual sum of squares (RSS) of the calculated neutron response and the ICRP-74 rem-response were minimized by changing the thickness of each filter sequentially. In addition, experimental verification using a Pu–Be source and photoneutrons from a 10 MV-X medical linac has been conducted. From these results, it is concluded that it may be practical for evaluating neutron ambient dose-equivalent simply around medical linacs.
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U2 - 10.1016/j.radmeas.2019.106181
DO - 10.1016/j.radmeas.2019.106181
M3 - Article
AN - SCOPUS:85071275531
SN - 1350-4487
VL - 128
JO - Radiation Measurements
JF - Radiation Measurements
M1 - 106181
ER -