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作 者:Shuai-Wei Zhao Mei-Lan Jia Xing-Qian Jiao Meng-Qi Qiu Hong-Hui Li Yu-Chen Liu Liang Mao Wei Liu Dong Liang
机构地区:[1]China Institute for Radiation Protection [2]Sichuan Environmental Protection and Engineering CO.,LTD., CNNC
出 处:《Nuclear Science and Techniques》2019年第4期35-43,共9页核技术(英文)
摘 要:To explore the behavior of radiolytically produced hydrogen release from the waste resin stored in a high integrated container(HIC), and the mechanism of hydrogen diffusion in a near-surface disposal facility, both experimental studies and numerical simulations were performed through an accelerated irradiation test and simulated disposal, respectively. Results indicated that,100 years after disposal, the highest hydrogen concentration appeared in the cell where the HICs were placed. The volume fraction for different scenarios postulated in the numerical simulation was 2.64% for Scenario 1, 2.28% for Scenario 2, and 3.965% for Scenario 3, all of which are lower than the hydrogen explosion limit of 4.1%. The results indicated that the simulated HIC disposal scheme is safe.To explore the behavior of radiolytically produced hydrogen release from the waste resin stored in a high integrated container(HIC), and the mechanism of hydrogen diffusion in a near-surface disposal facility, both experimental studies and numerical simulations were performed through an accelerated irradiation test and simulated disposal, respectively. Results indicated that,100 years after disposal, the highest hydrogen concentration appeared in the cell where the HICs were placed. The volume fraction for different scenarios postulated in the numerical simulation was 2.64% for Scenario 1, 2.28% for Scenario 2, and 3.965% for Scenario 3, all of which are lower than the hydrogen explosion limit of 4.1%. The results indicated that the simulated HIC disposal scheme is safe.
关 键 词:RADIOACTIVE WASTE RESIN High integrated container REPOSITORY RADIOLYSIS Hydrogen release
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