废树脂热态压实废物包自辐照产气的初步计算分析  

Preliminary Calculation and Analysis of Self-irradia-tion Gas Production for the Hot Resin Compaction Waste Package

作　　者：甘学英 徐春艳 张宇 李小龙 蒋婧 张春龙 Gan Xueying;Xu Chunyang;Zhang Yu;Li Xiaolong;Jiang Jing;Zhang Chunlong(Nuclear and Radiation Safety Center,MEE,Beijing 100082,China)

机构地区：[1]生态环境部核与辐射安全中心,北京100082

出　　处：《核安全》2022年第1期51-58,共8页Nuclear Safety

摘　　要：本文通过Microsheild软件和文献报道的气体辐射化学产额(G值),采用偏保守参数和模型计算了废树脂热态压实废物包的吸收剂量以及产气量。结果表明,废物包约100年后的吸收剂量趋于稳定,预期和最大累积吸收剂量分别约为3.6×10^(5)Gy和1.4×10^(6)Gy,累积压力分别约为1.0×10^(6)Pa和2.5×10^(6)Pa,氢气体积比为8%-12%。H_(2)浓度到达安全限值(4%)的预期和最快时间分别约为0.97年(354天)和0.22年(80天)。本文目的在于为废树脂废物包自辐照产气进程的评估提供一种新的方法。Absorbed dose and gas production of the hot resin compaction waste package were calculated and analyzed under a condition of choosing conservative parameters and models with Microsheild software and the gas radiation chemical yield(G value)reported in the literatures.The results showed that the absorbed dose of the resin waste package tends to be stable after about 100 years,and the expected and the maximum cumulative doses are about 3.6×10^(5)Gy and 1.4×10^(6)Gy respectively,and the corresponding cumulative pressures are 1.0×10^(6)Pa and 2.5×10^(6) Pa,and the hydrogen volume ratio is about 8%-12%.The expected and the fastest time for H2 concentration to reach the safety limit(4%)are about 0.97 years(354 days)and 0.22 years(80 days),respectively.It was intended to develop a new approach to access the gas production evolution of spent resin waste package resulting from self-irradiation in this study.

关 键 词：废树脂 废物包 辐解 产气 辐射化学产额 氢气 

分 类 号：X771[环境科学与工程—环境工程]