Simulation of groundwater and nuclide transport in the near-field of the high-level radioactive waste repository with TOUGHREACT

被引:3
作者
Li Xun [1 ,2 ]
Yang Zeping [2 ]
Zheng Zhihong [2 ]
Wu Hongmei [1 ]
机构
[1] Zhejiang Univ, Coll Engn & Architecture, Hangzhou 310027, Zhejiang, Peoples R China
[2] ECIT, Fuzhou 344000, Fujian, Peoples R China
关键词
liquid saturation; groundwater transport; geologic disposal; radioactive waste;
D O I
10.1007/s11631-008-0299-4
中图分类号
P3 [地球物理学]; P59 [地球化学];
学科分类号
0708 ; 070902 ;
摘要
In order to know the mechanism of groundwater transport and the variation of ion concentrations in the near-field of the high-level radioactive waste repository, the whole process was simulated by EOS3 module of TOUGHREACT. Generally, the pH and cation concentrations vary obviously in the near-field saturated zone due to interaction between groundwater and bentonite. Moreover, the simulated results showed that calcite precipitation could not cause obvious variations in the porosity of media in the near-filed if the chemical components and their concentrations of groundwater and bentonite pore water are similar to those used in this study.
引用
收藏
页码:299 / 305
页数:7
相关论文
共 49 条
[31]   SIMULATING THE POTENTIAL FOR RADIONUCLIDE TRANSPORT FROM A PROPOSED DEEP GEOLOGIC REPOSITORY IN CANADA FOR LOW AND INTERMEDIATE LEVEL RADIOACTIVE WASTE [J].
Sykes, Jonathan F. ;
Normani, Stefano D. ;
Yin, Yong .
PROCEEDINGS OF THE XVIII INTERNATIONAL CONFERENCE ON COMPUTATIONAL METHODS IN WATER RESOURCES (CMWR 2010), 2010, :421-431
[32]   Recovery of Metals from Simulated High-Level Radioactive Waste Glass through Phase Separation [J].
Uruga, Kazuyoshi ;
Doka, Kunio ;
Sawada, Kayo ;
Enokida, Youichi ;
Yamamoto, Ichiro .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2008, 45 (09) :889-898
[33]   INTERLABORATORY MODELING FOR PERFORMANCE ASSESSMENT OF ENGINEERED BARRIERS IN HIGH-LEVEL RADIOACTIVE-WASTE DISPOSAL [J].
NAKAYAMA, S ;
AHN, JH ;
IKEDA, T ;
OHE, T ;
KAWANISHI, M ;
TSUKAMOTO, M ;
KIMURA, H ;
MUNAKATA, M .
JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 1992, 34 (04) :342-364
[34]   A preliminary consideration for underground autocatalytic criticality by vitrified high-level waste in water-saturated geologic repository [J].
Ahn, J ;
Greenspan, E ;
Chambré, PL .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2000, 37 (05) :465-476
[35]   Progress in permanent geologic disposal of spent nuclear fuel and high-level radioactive waste in the United States [J].
Dyer, JR ;
Peters, MT .
PROCEEDINGS OF THE INSTITUTION OF MECHANICAL ENGINEERS PART A-JOURNAL OF POWER AND ENERGY, 2004, 218 (A5) :319-334
[36]   Two-phase reactive transport modeling of heterogeneous gas production in a low- and intermediate-level radioactive waste repository [J].
Vehling, Falko ;
Kosakowski, Georg ;
Shao, Haibing .
APPLIED GEOCHEMISTRY, 2025, 178
[37]   Advances in geochemical research for the underground disposal of high-level, long-lived radioactive waste in a clay formation [J].
Landais, P .
JOURNAL OF GEOCHEMICAL EXPLORATION, 2006, 88 (1-3) :32-36
[38]   The effect of organic retarders on grout thickening and setting during deep borehole disposal of high-level radioactive waste [J].
Collier, Nicholas C. ;
Milestone, Neil B. ;
Travis, Karl P. ;
Gibb, Fergus. G. F. .
PROGRESS IN NUCLEAR ENERGY, 2016, 90 :19-26
[39]   Stress corrosion cracking susceptibility of P285NH and API 5L X65 steel grades in the high-level radioactive waste repository cell concept [J].
Bulidon, Nicolas ;
Deydier, Valerie ;
Bumbieler, Frederic ;
Duret-Thual, Claude ;
Mendibide, Christophe ;
Crusset, Didier .
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION, 2021, 72 (1-2) :154-165
[40]   Scenario development for safety assessment in deep geologic disposal of high-level radioactive waste and spent nuclear fuel: A review [J].
Kuhlman, Kristopher L. ;
Bartol, Jeroen ;
Carter, Alexander ;
Lommerzheim, Andree ;
Wolf, Jens .
RISK ANALYSIS, 2024, 44 (08) :1850-1864