Analysis of Small Modular SMART Reactor Core Fuel Burn up using MCNPX code

Moustafa Aziz
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Abstract

SMART Nuclear reactor, which is conceptually developed by KAERI (Korea Atomic Energy Research Institute), is a Small modular reactor of 330 Mwth. MCNPX computer code Package which is based on Monte Carlo method is used to model the reactor core and evaluate neutronic characteristics of the core. Reactor multiplication factor is evaluated with time. Fuel burnup and depletion of fissile 235 U and breeding of plutonium are calculated with fuel burnup along the life cycle of the reactor core. Radial and axial Power and flux mapping distributions are calculated along all fuel assemblies of the core. Delayed neutron fraction, prompt neutron life time as well as fuel, moderator and void temperature coefficient of reactivity are evaluated and analysed. The results indicated that average core burnup extends to 27 GWd/T after 3 operation years which corresponds to 235 U burnup ratio of 71 %. Power distribution is compared to previously published results and satisfactory agreements were found
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使用 MCNPX 代码分析小型模块化 SMART 反应堆堆芯燃料燃烧情况
SMART 核反应堆由韩国原子能研究院(KAERI)开发,是一个 330 兆瓦的小型模块化反应堆。采用基于蒙特卡洛法的 MCNPX 计算机代码包对反应堆堆芯进行建模,并评估堆芯的中子特性。反应堆倍增因子随时间变化进行评估。根据反应堆堆芯生命周期的燃料燃烧情况,计算了燃料燃烧和裂变铀 235 的消耗情况以及钚的孕育情况。计算了堆芯所有燃料组件的径向和轴向功率及通量映射分布。对延迟中子分数、瞬发中子寿命以及燃料、慢化剂和空隙反应温度系数进行了评估和分析。结果表明,运行 3 年后,堆芯平均燃耗延长至 27 GWd/T,相当于 235 U 燃耗率为 71%。功率分布与之前公布的结果进行了比较,结果令人满意
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