中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Evaluation of the radioactivity in concrete from accelerator facilities

文献类型:期刊论文

;
作者Wang QB(王庆斌); Wang, QB; Masumoto, K; Bessho, K; Matsumura, H; Miura, T; Shibata, T
刊名JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY ; JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
出版日期2007 ; 2007
卷号273期号:1页码:#REF!
DOI10.1007/s10967-007-0710-3
通讯作者Wang, QB (reprint author), Chinese Acad Sci, Inst High Energy Phys, Beijing 100039, Peoples R China. ; Wang, QB (reprint author), Chinese Acad Sci, Inst High Energy Phys, Beijing 100039, Peoples R China.
文献子类Article
英文摘要For evaluation of radioactivity induced in the concrete samples from accelerator facilities, the residual radioactivity in concrete sample, collected from seven accelerator facilities, was determined by gamma-ray spectrometry. The tritium was extracted by the heating method using an IR furnace, and measured with a liquid scintillation counter. It was found that the major radioisotopes activated mainly by neutrons in the concrete samples were Eu-152, Co-60, (CS)-C-134 and H-3. The concentrations of radioactivities induced by thermal neutron capture are the highest at a depth of 10 cm in the concrete wall. The correlation between tritium, Co-60 and Eu-152 activity was investigated by measuring many concrete samples for seven accelerator facilities. The results indicate that their activities are strongly correlated with each other. So it would also be concluded that the total activity in shielding concrete could be estimated on the basis of the activities of Co-60 and Eu-152.; For evaluation of radioactivity induced in the concrete samples from accelerator facilities, the residual radioactivity in concrete sample, collected from seven accelerator facilities, was determined by gamma-ray spectrometry. The tritium was extracted by the heating method using an IR furnace, and measured with a liquid scintillation counter. It was found that the major radioisotopes activated mainly by neutrons in the concrete samples were Eu-152, Co-60, (CS)-C-134 and H-3. The concentrations of radioactivities induced by thermal neutron capture are the highest at a depth of 10 cm in the concrete wall. The correlation between tritium, Co-60 and Eu-152 activity was investigated by measuring many concrete samples for seven accelerator facilities. The results indicate that their activities are strongly correlated with each other. So it would also be concluded that the total activity in shielding concrete could be estimated on the basis of the activities of Co-60 and Eu-152.
学科主题Chemistry; Nuclear Science & Technology ; Chemistry; Nuclear Science & Technology
类目[WOS]Chemistry, Analytical ; Chemistry, Inorganic & Nuclear ; Nuclear Science & Technology
收录类别SCI
WOS记录号WOS:000247427400010 ; WOS:000247427400010
公开日期2016-05-03
源URL[http://ir.ihep.ac.cn/handle/311005/225795]  
专题高能物理研究所_加速器中心
推荐引用方式
GB/T 7714
Wang QB,Wang, QB,Masumoto, K,et al. Evaluation of the radioactivity in concrete from accelerator facilities, Evaluation of the radioactivity in concrete from accelerator facilities[J]. JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY,2007, 2007,273, 273(1):#REF!, #REF!.
APA 王庆斌.,Wang, QB.,Masumoto, K.,Bessho, K.,Matsumura, H.,...&Shibata, T.(2007).Evaluation of the radioactivity in concrete from accelerator facilities.JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY,273(1),#REF!.
MLA 王庆斌,et al."Evaluation of the radioactivity in concrete from accelerator facilities".JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY 273.1(2007):#REF!.

入库方式: OAI收割

来源:高能物理研究所

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