Design study on differential die-away technique in an integrated active neutron NDA system for non-nuclear proliferation

A. Ohzu, M. Maeda, M. Komeda, H. Tobita, M. Kureta, M. Koizumi, M. Seya
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引用次数: 1

Abstract

A specific Differential Die-away Analysis (DDA) system in an advanced non-destructive analysis (NDA) system using a compact pulsed neutron generator has been studied and designed for non-nuclear proliferation in the Japan Atomic Energy Agency (JAEA). The NDA system is composed mainly of combination of four active neutron analysis techniques, DDA, PGA (Prompt Gamma-ray Analysis), NRTA (Neutron Resonance Transmission Analysis) and DGS (Delayed Gamma Spectroscopy). The design study on the DDA section in the system has been performed with Monte Carlo simulation code (MCNP) to evaluate the performance of the DDA system. The simulation result shows that the 239Pu mass (contained in MOX fuel) of as low as 0.01 g is detectable. The dependence of the performance on the type of the inner wall material in the DDA section and the thickness of the cylindrical moderator placed to circumscribe the measurement sample are presented.
非核扩散综合有源中子NDA系统差分渐灭技术设计研究
日本原子能机构(JAEA)研究和设计了一种特殊的差分渐灭分析(DDA)系统,该系统是采用紧凑型脉冲中子发生器的先进无损分析(NDA)系统,用于防止核扩散。NDA系统主要由DDA、PGA(提示伽玛射线分析)、NRTA(中子共振透射分析)和DGS(延迟伽玛能谱分析)四种中子分析技术组合而成。利用蒙特卡罗仿真程序(MCNP)对系统中的DDA部分进行了设计研究,以评估DDA系统的性能。模拟结果表明,MOX燃料中含有的239Pu质量低至0.01 g。分析了DDA截面内壁材料的类型和用于限定测量样品的圆柱形慢化剂的厚度对性能的影响。
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