Uranium and plutonium are required to be accounted in spent fuel head-end and major recovery area in pyro-process for safeguards purpose. The possibility of neutron resonance technique, as a non-destructive analysis, was simulated on isotopic fissile analysis for large scale process. Neutron resonance technique has advantage to distinguish uranium from plutonium directly in mixture. Simulation was performed on U235 and Pu239 assay in spent fuel and for scoping examination of assembly type. The resonance energies were determined for U235 and Pu239. The linearity in the neutron transmission was examined for the selected resonance energies. In addition, the limit for detection was examined by changing sample density, thickness and content for actual application. Several factors were proposed for neutron production and the moderated neutron source was simulated for effective and efficient transmission measurement. From the simulation results, neutron resonance technique is promising to analyze U235 and Pu239 for spent fuel assembly. An accurate fissile assay will contribute to an increased safeguards for the pyro-processing system and international credibility on the reuse of fissile materials in the fuel cycle.

出于保障目的，铀和钚必须计入乏燃料前端和高温工艺的主要回收区。中子共振技术作为一种无损分析的可能性，在同位素裂变分析中模拟了大规模过程。中子共振技术有利于在混合物中直接区分铀和钚。对乏燃料中的 U235 和 Pu239 分析以及组件类型的范围检查进行了模拟。确定了 U235 和 Pu239 的共振能量。针对选定的共振能量检查了中子传输的线性。此外，根据实际应用，通过改变样品密度、厚度和含量来检查检测限。提出了中子产生的几个因素，并对慢化中子源进行了模拟，以实现有效和高效的传输测量。从模拟结果来看，中子共振技术有望用于分析乏燃料组件中的U235和Pu239。准确的裂变分析将有助于加强对高温处理系统的保障，以及在燃料循环中再利用裂变材料的国际可信度。