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Nondestructive high-sensitivity measurement method for activation estimation in accelerator room concrete
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作者 Hiroshi Matsumura Go Yoshida +9 位作者 Akihiro Toyoda Kazuyoshi Masumoto Hajime Nakamura Taichi Miura Koichi Nishikawa Kotaro Bessho Kimikazu Sasa Tetsuaki Moriguchi Fumiyoshi Nobuhara Yoko Nagashima 《辐射防护》 CAS CSCD 北大核心 2020年第6期677-682,共6页
This study established a method for easily and quickly estimating the specific activity produced in the concrete walls and floors of accelerator rooms during long-term operation of accelerator,for advanced zoning of a... This study established a method for easily and quickly estimating the specific activity produced in the concrete walls and floors of accelerator rooms during long-term operation of accelerator,for advanced zoning of activated/nonactivated areas in planning the decommissioning of an accelerator.We propose a new,highly sensitive method for nondestructively estimating the specific activity in concrete that can be applied to activation zoning.In this method,instead of direct determination of the specific activities of important long-half-life radionuclides for decommissioning,such as 152 Eu and 60 Co,we determine the specific activities of short-half-life radionuclides,24 Na and 56 Mn,in situ to obtain neutron flux.The obtained neutron flux and accelerator operation history yield the specific activities of 152 Eu and 60 Co for the advance zoning of activated/non-activated concrete.This method is a powerful long-term prediction tool for concrete activation. 展开更多
关键词 ACCELERATOR ACTIVATION CONCRETE specific activity DECOMMISSIONING
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In-situ evaluation for activated concrete in accelerator facility with scintillation-type gamma-ray spectrometer
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作者 Go Yoshida Hiroshi Matsumura +5 位作者 Koichi Nishikawa Akihiro Toyoda Yoshiharu Miyazaki Kazuyoshi Masumoto Hajime Nakamura Taichi Miura 《辐射防护》 CAS CSCD 北大核心 2020年第6期545-549,共5页
The assessment of activated concrete is particularly difficult during the decommissioning of an accelerator facility.Destructive analysis by core boring is the only method of investigating the activity of concrete mat... The assessment of activated concrete is particularly difficult during the decommissioning of an accelerator facility.Destructive analysis by core boring is the only method of investigating the activity of concrete material.To address this problem,an in-situ and nondestructive analysis method was developed to determineγ-ray-emitting nuclides and their specific activities in the concrete walls and floor by using a portable germanium semiconductor detector.In this work,we examined a substitute for Ge detector to establish a simpler and more convenient method.As candidates,we focused on some scintillation type spectrometers,and the possibility of a substitute for a Ge detector was examined by both simulation and experiment.The detection limits were roughly estimated through Monte Carlo simulation for various scintillation crystals,and it was found that 1.5-inch LaBr3,CeBr3,and SrI2 could distinguish the clearance level.It was confirmed that the 1.5-inch LaBr3 could reproduce the calibration curve of the Ge detector in the experiment.The required thickness and length of the radiation shield for suppressing the background radiation during the measurement was also determined for the convenience of an actual decommissioning work. 展开更多
关键词 activation ACCELERATOR CONCRETE scintillation detector PHITS code
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使用活化探测器和成像盘技术相结合的方法测量混凝土屏蔽体内中子空间分布
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作者 王庆斌 李铁辉 +2 位作者 Masumoto K Matsumura H Shibta T 《原子能科学技术》 EI CAS CSCD 北大核心 2006年第6期650-653,共4页
描述了1种联合使用活化探测器和成像盘技术(IP)探测中子注量的方法。利用这种方法,测量了高能中子束线装置KENS(KEK spallation neutron source facility)中混凝土屏蔽体内中子的空间分布。高能中子注量衰减的实验结果与使用蒙特卡罗程... 描述了1种联合使用活化探测器和成像盘技术(IP)探测中子注量的方法。利用这种方法,测量了高能中子束线装置KENS(KEK spallation neutron source facility)中混凝土屏蔽体内中子的空间分布。高能中子注量衰减的实验结果与使用蒙特卡罗程序MARS14模拟计算的结果符合很好。结果表明,联合使用活化探测器和成像盘技术可以同时测量多个位置的中子注量,直观展现出混凝土屏蔽体内中子强度的分布。 展开更多
关键词 活化探测器 成像盘技术 中子注量 屏蔽混凝土 空间分布
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加速器屏蔽体中氚的提取和比活度测量
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作者 王庆斌 王芊 +4 位作者 K. Masumoto K. Bessho H. Matsumura T. Miura T. Shibata 《原子能科学技术》 EI CAS CSCD 北大核心 2008年第5期465-469,共5页
使用红外炉发展了一种从活化混凝土中提取氚的方法。通过研究氚的提取效率与加热温度、加热时间的关系,获得了氚的提取优化条件为在800℃下加热30 min,Ar气流量设置为200 mL/min。氚由两个冷凝管收集,然后装到1个小玻璃瓶中,与液体闪烁... 使用红外炉发展了一种从活化混凝土中提取氚的方法。通过研究氚的提取效率与加热温度、加热时间的关系,获得了氚的提取优化条件为在800℃下加热30 min,Ar气流量设置为200 mL/min。氚由两个冷凝管收集,然后装到1个小玻璃瓶中,与液体闪烁体混合,使用液体闪烁计数器计数。使用这种方法提取氚只需55 min。相对于使用电子炉提取氚的方法,氚的提取效率可达到100%。收集了两个加速器屏蔽体中的混凝土样品,测量了样品中的γ射线核素和氚的放射性比活度。结果显示,氚的比活度与152Eu和60Co的比活度有很强的相关性。可得出结论:氚主要产生于热中子俘获反应6Li(n,α)3H。因而,可使用60Co的放射性比活度简单估计活化的混凝土样品中氚的放射性比活度。 展开更多
关键词 混凝土样品 红外炉 液体闪烁计数器
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