摘要
核级石墨在高温气冷堆中作为结构材料、慢化材料和反射层材料等被广泛应用,其氧化性能对高温气冷堆在进水或进气事故下材料的腐蚀行为有重要影响。初始孔隙率分布及孔隙率在氧化过程中的变化均对石墨氧化造成影响。本文以核级石墨IG-110、H-451、NBG-18和A3-3为例,以直径为6cm的石墨球为研究对象,在一维瞬态氧化模型的基础上,分析了初始孔隙率分别服从均匀分布、正态分布和对数正态分布时对石墨氧化的影响。从模型简化和高温气冷堆安全分析角度保守考虑,建立石墨氧化模型时,核级石墨初始孔隙率可取均匀分布,此时石墨的整体失重率最大。
Nuclear grade graphite is widely used as structure material,moderating material and reflector material in the high temperature gas-cooled reactor.The oxidation performance of nuclear grade graphite is important to the reactor material corrosion during water or air ingress accidents.The initial porosity distribution and porosity change during the oxidation process have an influence on the oxidation performance.The nuclear grade graphite IG-110,H-451,NBG-18 and A3-3were studied in this paper.Based on the one dimensional transient oxidation model,the oxidation of spherical nuclear grade graphite with a diameter of 6cm was researched.The effects of different initial porosity distributions on the graphite oxidation were analyzed as the initial porosity distribution was uniform,normal and lognormal respectively.For conservative consideration and simplifying the oxidation model in the safety analysis of high temperature gas-cooled reactor,the initial porosity distribution of nuclear grade graphite should be selected asuniform,which results a maximum overall weight loss ratio of graphite.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2016年第3期471-476,共6页
Atomic Energy Science and Technology
基金
国家科技重大专项资助项目(ZX069)
关键词
核级石墨
初始孔隙率分布
整体失重率
氧化模型
nuclear grade graphite
initial porosity distribution
overall weight loss ratio
oxidation model
