核级石墨IG-110氧化模型研究

Research on Oxidation Model of Nuclear Grade Graphite IG-110

  • 摘要: 核级石墨IG-110在球床模块式高温气冷堆(HTR-PM)中作为结构材料被广泛应用。在正常运行工况及进气进水等严重事故工况下,核级石墨IG-110不可避免地与氧气等发生氧化反应,其氧化性能对反应堆的安全运行有着重要的作用。本文综合考虑核级石墨在氧化过程中局部孔隙率及氧化速率随失重率的变化,建立IG-110与氧气反应的氧化模型,得到氧化反应过程中各参数随空间和时间的变化。重点分析孔隙率变化和Knudsen扩散对有效扩散系数的影响,确定了在事故分析中较为适用的有效扩散系数形式。

     

    Abstract: Nuclear grade graphite IG-110 is widely used as structure materials in the high temperature gas-cooled reactor pebble-bed module (HTR-PM). Under normal operation condition, or air/water ingress accidents, nuclear grade graphite IG-110 is inevitably oxidized by oxygen and steam. The oxidation performance of IG-110 is important to the reactor safe operation. A new oxidation model, considering the local porosity and oxidation rate varying with weight loss ratio, was developed. Based on the oxidation model, the parameters trending over time and space could be obtained. The effect of porosity and Knudsen diffusion on the effective diffusion coefficient was mainly analyzed. The appropriate effective diffusion coefficient for the safety analysis could be determined based on the numerical results.

     

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