Optimal waste loading in high-level nuclear waste glass from high-burnup spent fuel for waste volume and geological disposal footprint reduction

被引:3
|
作者
Sakuragi, Tomofumi [1 ]
Okamura, Tomohiro [2 ]
Hamada, Ryo [1 ]
Asano, Hidekazu [1 ,2 ]
Minari, Eriko [2 ]
Nakase, Masahiko [2 ]
Takeshita, Kenji [2 ]
Oniki, Toshiro [3 ]
Uchiyama, Midori [3 ]
机构
[1] Radioact Waste Management Funding & Res Ctr, Akashicho 6-4, Chuo City, Tokyo 1040044, Japan
[2] Tokyo Inst Technol, Ookayama 2-12-1, Meguro, Tokyo 1528550, Japan
[3] IHI Corp, Isogo Ku, Shinnakahara Cho 1, Yokohama, Kanagawa 2358501, Japan
关键词
% reductions - Best estimates - Decay heat - Geological disposals - High level nuclear wastes - High-burn up - Nuclear waste glass - Optimisations - Volume reductions - Waste loadings;
D O I
10.1557/s43580-022-00232-3
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The effects of waste loading in vitrified high-level nuclear waste (HLW) from the reprocessing of high-burnup spent fuel (56 GWd/tHM) on waste volume reduction (i.e., number of HLW canisters produced) and decay heat generation were investigated to minimize the repository footprint. As the waste loading increases, the number of canisters produced decreases; however, the decay heat and subsequent footprint per canister increase. The best estimate waste loading observed was 23 wt% (including 10 wt% Na2O), wherein the repository footprint minimizes to 60.0 m(2)/tHM. These results are slightly higher than those for standard HLW (55.5 m(2)/tHM). However, upon comparing the repository footprint with electric power generation, the benefit of optimization was that the footprint for high-burnup HLW (131 m(2)/TWh) was 13% smaller than that of standard HLW (151 m(2)/TWh).
引用
收藏
页码:150 / 154
页数:5
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