Temperature field of multi-barrier with gap layer in nuclear waste repository

被引：3
作者：
Sun, De'an [1 ,2 ]
He, Luqiang [2 ]
Zhou, Xiangyun [3 ]
Qin, Yongjun [1 ]
机构：
[1] Xinjiang Univ, Coll Civil Engn & Architecture, Urumqi 830047, Peoples R China
[2] Shanghai Univ, Dept Civil Engn, Shanghai 200444, Peoples R China
[3] Nanjing Inst Technol, Inst Civil Engn & Intelligent Management, Nanjing 211167, Peoples R China
来源：
NUCLEAR ENGINEERING AND DESIGN | 2023年 / 414卷
基金：
中国国家自然科学基金;
关键词：
Nuclear waste repository; Disposal; Bentonite buffer layer; Analytical solution; Temperature evolution; Construction gap; THERMAL-ANALYSIS; DISPOSAL; DESIGN; BUFFER; ROCK;
D O I：
10.1016/j.nucengdes.2023.112588
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
A three-dimensional four-layer thermal conduction model including an air layer was developed to analyze temperature evolution in nuclear waste repository. Laplace-domain temperature solutions for each layer were obtained using finite Fourier transform and Laplace transform. The Laplace-domain solutions were transformed into time-domain semi-analytical solutions by numerical inversion. The surface temperature of central canister was obtained by superimposing the temperature increments of air and buffer layers on rock wall temperature caused by every canister in one disposal panel. The effects of the geometrical parameters, thermal parameters and nuclear waste parameters on surface temperature of canister were studied based on the obtained semi-analytical solution. The results indicate that the presence of air layer has little effect on temperature distribution in bentonite while its effect on temperature at surface of canister is significant. Thickness of air layer has a greater effect on temperature than that of its thermal conductivity. The burn-up value and cooling time also have significant influence on the temperature. Finally, the influences of repository's geometric size on temperature in this model were analyzed.
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页数：12
相关论文
共 35 条
[21]   Numerical analysis of the effect of gap-filling options on the maximum peak temperature of a buffer in an HLW repository [J].
Lee, Jae Owan ;
Choi, Heui-Joo ;
Kim, Geon Young ;
Cho, Dong-Keun .
PROGRESS IN NUCLEAR ENERGY, 2019, 111 :138-149
[22]   Thermo-hydro-mechanical properties of bentonite-sand-graphite-polypropylene fiber mixtures as buffer materials for a high-level radioactive waste repository [J].
Liu, Xiaoyan ;
Cai, Guojun ;
Liu, Lulu ;
Liu, Songyu ;
Puppala, Anand J. .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2019, 141 :981-994
[23]   Investigation of the hydro-mechanical behaviour of GMZ bentonite pellet mixtures [J].
Liu, Zhang-Rong ;
Cui, Yu-Jun ;
Ye, Wei-Min ;
Chen, Bao ;
Wang, Qiong ;
Chen, Yong-Gui .
ACTA GEOTECHNICA, 2020, 15 (10) :2865-2875
[24]   Thermal, Mechanical and Thermo-Mechanical Assessment of the Rock Mass Surrounding SKB's Prototype Repository at A"spo HRL [J].
Lonnqvist, Margareta ;
Hokmark, Harald .
ROCK MECHANICS AND ROCK ENGINEERING, 2016, 49 (04) :1123-1142
[25]   Thermal conductivity of bentonite-graphite mixture and its prediction for high-level radioactive waste repository [J].
Peng, Fan ;
Tan, Yunzhi ;
Sun, De'an .
ANNALS OF NUCLEAR ENERGY, 2021, 154
[26]   Thermal Analysis of Spent Nuclear Fuels Repository [J].
Pereira, Fernando ;
Salome, Jean ;
Viana, Cristiane ;
Cardoso, Fabiano ;
Velasquez, Carlos E. ;
Barros, G. P. ;
Pereira, Claubia .
ATALANTE 2016 INTERNATIONAL CONFERENCE ON NUCLEAR CHEMISTRY FOR SUSTAINABLE FUEL CYCLES, 2016, 21 :386-393
[27]  
Posiva and SKB, 2017, Posiva SKB Report 01
[28]   The Swedish nuclear waste program and the long-term corrosion behaviour of copper [J].
Rosborg, B. ;
Werme, L. .
JOURNAL OF NUCLEAR MATERIALS, 2008, 379 (1-3) :142-153
[29]  
SKB, 2006, Tech. Rep. TR-06-18
[30]   NUMERICAL INVERSION OF LAPLACE TRANSFORMS [J].
STEHFEST, H .
COMMUNICATIONS OF THE ACM, 1970, 13 (01) :47-&
1234