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題 名 | On the Determination of Neutron Attenuation by Some Common Shielding Materials Using Exact and Simplified Solutions of the Diffusion Equation for the Group Neutrons=利用群中子擴散方程式之精密解與簡化解測定屏蔽村料之中子衰減效應 |
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作 者 | Rashed,R. A.; Ibrahim,M. A.; | 書刊名 | 核子科學 |
卷 期 | 36:3 1999.06[民88.06] |
頁 次 | 頁225-231 |
分類號 | 449.62 |
關鍵詞 | 擴散方程式; 精密解; 簡化解; Diffusion equation; Exact and simplified solutions; |
語 文 | 英文(English) |
英文摘要 | The subject of neutron attenuation by some common shielding materials (water, ordinary concrete, heavy concrete, paraffin wax, graphite and marble) is treated in this work. The fast neutrons are expressed by the removal cross-section concept, while the other two groups (epithermal and thermal)are expressed in two ways; using an exact expression with two arbitrary constants for solving the diffusion equation and a simplified one in which the second arbitrary is neglected. Calculations are carried out with increasing thicknesses up to 2.5 meter for each of the above materials expressing the group fluxes in the ways (double and single arbitrary constants) for each of the considered thicknesses. The total neutron dose rate distributions of the three groups are also calculated by using exact and simplified solutions and are compared with each other for the given materials. These results are also compared with some available theoretical data. The two solutions are found to be almost identical for certain characteristic thicknesses, which are determined for each of the given shield materials, at which the simplified solution can be applied without significant numerical errors in the calculations of the total neutron dose rate. |
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