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題 名 | On the Determination of Attenuated Neutrons Through Some Reactor Shields Using Three Different Formulae for the Neutron Fluxes=經由一些反應器屏蔽使用中子通率三個不同公式測定衰減中子 |
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作 者 | Ibrahim,M. A.; | 書刊名 | 核子科學 |
卷 期 | 34:6 1997.12[民86.12] |
頁 次 | 頁437-441 |
分類號 | 449.1 |
關鍵詞 | 反應器; 中子通率; 衰減中子; Neutrons; Shield; Formulae; |
語 文 | 英文(English) |
英文摘要 | This work is a theoretical study of the fast neutron attenuation through a midplane of a reactor shield consisting of multiple layers. the shield materials studied here are water, ordinary concrete and iron; with different arrangements and thicknesses in which one or two air spaces may be included. three different formulae for the intermediate and thermal attenuated fluxes are applied for the different arrangements. The obtained fluxes are converted to dose rates using suitable average conversion factors. |
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