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頁籤選單縮合
題 名 | Deduction of Some Neutron Shielding Parameters for Different Types of Concrete Made from Local Materials=數種不同形式混凝土之中子屏蔽參數之研討 |
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作 者 | Ibrahim,M. A.; Rashed,R. A.; | 書刊名 | 核子科學 |
卷 期 | 35:4 1998.08[民87.08] |
頁 次 | 頁245-250 |
分類號 | 449.1 |
關鍵詞 | 混凝土; 中子屏蔽參數; Neutron; Shielding; Parameters; Different concretes; |
語 文 | 英文(English) |
英文摘要 | In this study, some shielding parameters are obtained to be used in the theoretical determination of neutron fluxes and corresponding dose rates through different types of concrete shields constructed from local materials. The attenuation of thermal and epithermal neutrons could be evaluated using these deduced parameters. The total neutron doses inside these concretes could then be used in the estimation of the shield thickness needed to attenuate these doses to certain permissible values. The semi-empirical derivation used may also be applied for different hydrogeneous shield materials, assuming the presence of certain experimental measurements for these materials. |
本系統中英文摘要資訊取自各篇刊載內容。