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蒙特卡罗方法在中子测井屏蔽中的应用
引用本文:李王燕,马英杰,万志雄.蒙特卡罗方法在中子测井屏蔽中的应用[J].科技信息,2012(1):121-122.
作者姓名:李王燕  马英杰  万志雄
作者单位:成都理工大学核技术与自动化工程学院,四川成都610059
摘    要:利用蒙卡罗方法模拟研究了在套管中子测井条件下,铜、银、含硼聚乙烯(含10%B4C聚乙烯)、钨、镉、铝不同厚度对中子的屏蔽效果.以及中子源到屏蔽层距离对屏蔽效果的影响。结果表明:用不同屏蔽材料对中子进行屏蔽,得到的中子能量分布相差很大。相同厚度下,银做屏蔽材料时.总中子和小于0.1MeV能量范围内的中予计数最小,钨在14MeV~0.1MeV中子能量区的计数最小.

关 键 词:中子测井  中子屏蔽  MCNP

Monte Carlo Method in Neutron Log Shielding of Application
Abstract:With the use of Monte Carlo method, we had simulated and researched the shielding effectiveness of different thickness of Cu, Ag, B4C and polythene mixture. W, Cd and AI under the condition of and the influence of the distance from neutron source to shielding layer. The result shows that if we shiehl neutron with different shielding material, the neutron energy distribution differs greatly. On the same thickness, when taking Ag as the shielding material, the counts of integrated neutron, 0-0.1MeV neutron are the least, while the counts of B4C and polythene mixture and W are the least in fast neutron region.
Keywords:Neutron logging  Neutron shielding  MCNP
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