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DEVELOPMENT AND APPLICATION OF A HYBRID TRANSPORT METHODOLOGY FOR ACTIVE INTERROGATION SYSTEMS

机译:主动询问系统混合传输方法的发展与应用

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A hybrid Monte Carlo and deterministic methodology has been developed for application to active interrogation systems. The methodology consists of four steps: ⅰ) neutron flux distribution due to neutron source transport and subcritical multiplication; ⅱ) generation of gamma source distribution from (n, γ) interactions; ⅲ) determination of gamma current at a detector window; ⅳ) detection of gammas by the detector. This paper discusses the theory and results of the first three steps for the case of a cargo container with a sphere of HEU in third-density water cargo. To complete the first step, a response-function formulation has been developed to calculate the subcritical multiplication and neutron flux distribution. Response coefficients are pre-calculated using the MCNP5 Monte Carlo code. The second step uses the calculated neutron flux distribution and Bugle-96 (n, γ) cross sections to find the resulting gamma source distribution. In the third step the gamma source distribution is coupled with a pre-calculated adjoint function to determine the gamma current at a detector window. The AIMS (Active Interrogation for Monitoring Special-Nuclear-Materials) software has been written to output the gamma current for a source-detector assembly scanning across a cargo container using the pre-calculated values and taking significantly less time than a reference MCNP5 calculation.
机译:已经开发出一种混合的蒙特卡洛和确定性方法,用于主动询问系统。该方法包括四个步骤:ⅰ)由于中子源传输和亚临界倍增而产生的中子通量分布; ⅱ)由(n,γ)相互作用产生伽马射线源分布; ⅲ)在探测器窗口确定伽马电流; ⅳ)通过探测器探测伽玛。本文讨论了第三密度水货物中带有HEU球形的货柜的前三个步骤的理论和结果。为了完成第一步,已经开发了响应函数公式来计算亚临界乘积和中子通量分布。响应系数是使用MCNP5蒙特卡洛代码预先计算的。第二步使用计算出的中子通量分布和Bugle-96(n,γ)横截面来找到所得的伽马源分布。在第三步骤中,伽马源分布与预先计算的伴随函数耦合,以确定探测器窗口处的伽马电流。编写了AIMS(用于监视特殊核材料的主动询问)软件,可以使用预先计算的值输出伽马电流,以便使用预先计算的值跨货物集装箱扫描源检测器组件,并且比参考MCNP5计算花费的时间要少得多。

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