A Monte Carlo simulation to study a design of a $$gamma$$-ray detector for neutron resonance densitometry
土屋 晴文; 原田 秀郎; 小泉 光生; 北谷 文人; 高峰 潤; 呉田 昌俊; 飯村 秀紀
Tsuchiya, Harufumi; Harada, Hideo; Koizumi, Mitsuo; Kitatani, Fumito; Takamine, Jun; Kureta, Masatoshi; Iimura, Hideki
Neutron resonance densitometry (NRD) has been proposed to quantify nuclear materials in melted fuel (MF) that will be removed from the Fukushima Daiichi Nuclear Power Plant. Those MFs probably involve impurities of non-nuclear materials, and would prevent us from accurately measuring nuclear materials. Thus, NRD is based on a combination of neutron resonance transmission analysis (NRTA) and neutron resonance capture analysis (NRCA). The latter would enable us to identify impurities with their prompt $$gamma$$ rays. Here, a design study of a $$gamma$$-ray detector for NRCA in NRD was performed with Geant4. In order to effectively detect the prompt $$gamma$$ rays, the $$gamma$$-ray detector has a well shape, consisting of a cylindrical and a tube type LaBr$$_{3}$$ scintillators. We show how the $$gamma$$-ray detector measures 478 keV $$gamma$$ rays derived from $$^{10}$$B in MF under a high radiation environment caused by $$^{137}$$Cs. It was found that the $$gamma$$-ray detector was able to well suppress the Compton edge derived from $$^{137}$$Cs by using the tube type scintillator as a back-catcher detector. Then, we demonstrate that with this ability, detection of 478-keV $$gamma$$ rays derived from $$^{10}$$B is accomplished in realistic measuring time, and that achievable statistical uncertainty strongly depends on boron concentration in MF.
使用言語 : English
掲載資料名 : Nuclear Instruments and Methods in Physics Research A
: 729
ページ数 : p.338 - 345
発行年月 : 2013/11
出版社名 : Elsevier
特許データ :
論文URL :
キーワード : 福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident
使用施設 :
広報プレスリリース :
受委託・共同研究相手機関 :
登録番号 : AA20120980
抄録集掲載番号 : 42000175
論文投稿番号 : 13722
Accesses  (From Jun. 2, 2014)
- Accesses
分野:Instruments & Instrumentation
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