Effects of burnup on heat generation in vitrified waste from spent MOX fuel for geological disposal

被引：2

作者：

Hamada, Ryo ^{[1
]}

Sakuragi, Tomofumi ^{[1
]}

Asano, Hidekazu ^{[1
]}

Oniki, Toshiro ^{[2
]}

Uchiyama, Midori ^{[2
]}

机构：

[1] Radioact Waste Management Funding & Res Ctr, Akashicho 6-4, Chuo City, Tokyo 1040044, Japan

[2] IHI Corp, Isogo Ku, Shinnakahara Cho 1, Yokohama, Kanagawa 2358501, Japan

来源：

MRS ADVANCES | 2022年 / 7卷 / 7-8期

关键词：

Compendex;

D O I：

10.1557/s43580-022-00246-x

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

In this study, we evaluated the amount of decay heat generated in vitrified waste from MOX fuel and the bentonite buffer temperature after disposal under different burnup conditions, assuming the waste loading in the vitrified waste was constant. The effect of burnup was calculated for two cases: (1) the initial fissile Pu content in MOX fuel was constant and (2) the initial fissile Pu content increased as the burnup increased. In case (1), the amount of decay heat generated in vitrified waste (kW/canister) decreased as the burnup increased considering the content of Am-241 in the vitrified waste decreased owing to the significant increase in the number of fission products (FP). Conversely, in case (2), the amount of heat generated in vitrified waste (kW/canister) increased as the burnup increased. Furthermore, the waste loading, for which the maximum temperature of the bentonite buffer after disposal still complies with the current upper limit of 100 degrees C in Japan, was found to be approximately 13 wt% (including Na2O 10 wt%).

引用

页码：155 / 159

页数：5

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