使用同质和异质模型对高温热核反应堆组件进行堆芯物理分析。

Moustafa Aziz
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引用次数: 0

摘要

MCNPX 计算机代码基于蒙特卡洛方法,用于设计高温试验反应堆(HTTR)组件的计算机模型。分析中使用了两种模型,即均相模型和异相模型。反应堆使用 TRISO 燃料、石墨慢化剂和氦冷却剂。组件的倍增因子作为燃料燃耗和运行时间的函数确定。对轴向功率映射分布进行了评估。计算了锕系元素(铀 235 和钚 239)随燃料燃烧时间的变化情况。燃料和慢化剂的反应温度系数被确定为运行温度的函数。评估了氦冷却剂损失对反应堆临界状态的影响(假设氦密度降低到额定密度的百分之一)。计算表明,均质模型与异质模型的结果非常一致,平均差异约为 5%。这使得均质模型可用于全反应堆堆芯模拟。这将大大方便并节省建模和计算时间。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Core Physics Analysis of An Assembly of HTTR Reactor using Homogeneous and heterogeneous model.
MCNPX computer code based on Monte Carlo method is used to design a computer model for an assembly of high temperature testing reactor (HTTR). Two models are used in the analysis, namely homogeneous and heterogeneous models. The reactor uses TRISO fuel, Graphite moderator and helium coolant. The multiplication factor of the assembly is determined as a function of fuel burnup and operation time. Axial power mapping distributions are evaluated. Time evolution of actinides (U 235 and Pu 239 ) is calculated as a result of fuel burnup. Fuel and moderator temperature coefficient of reactivity are determined as a function of operating temperature. The effect of Helium coolant losses on reactor criticality is evaluated (by assuming reduction of helium density to one percent of its nominal density). Calculations indicated that homogenous model results are in good agreement with heterogeneous models with an average difference of approximately 5 %. This enable homogeneous model to be used in full reactor core simulations. This is much easier and saves modeling and computational time.
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