The design of copper-coating overpack for the high-level radioactive waste disposal concept in Japan

被引:5
作者
Suzuki, Satoru [1 ]
Ogawa, Yusuke [1 ]
Giallonardo, Jason [2 ]
Keech, Peter G. [2 ]
机构
[1] Nucl Waste Management Org Japan, Sci & Technol Dept, Tokyo, Japan
[2] Nucl Waste Management Org, Safety & Tech Res, Toronto, ON, Canada
来源
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION | 2021年 / 72卷 / 1-2期
关键词
copper-coating technology; copper-steel composite overpack; geological disposal; vitrified waste; CORROSION; FUEL; CONTAINERS; STEEL;
D O I
10.1002/maco.202011855
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
For the geological disposal system in Japan, a vitrified waste will be contained in a metal overpack, which, in turn, will be surrounded by a thick bentonite buffer. The overpack is aiming to prevent the contact of groundwater to vitrified waste during the high radioactivity and heat generation period of the first 1,000 years at least after emplacement. Within the Japanese program, consideration for overpack candidate materials has included carbon steel, copper-steel composite, and titanium-steel composite. Within the extensive safety assessment conducted in 2000, steel was selected. This selection was partly based on the manufacturability of carbon steel, as well as its well-understood corrosion behavior. However, the understanding of copper corrosion and welding/manufacturing technologies have greatly progressed over the past two decades. In this study, we focus on the copper-coated container developed by the Nuclear Waste Management Organization, because this technology is seemingly effective to maintain very long-term containment of hundreds of thousands of years, with a low cost of manufacturing within the Canadian program. We are investigating the applicability of the copper-coating technologies in terms of the corrosion allowance and mechanical design.
引用
收藏
页码:94 / 106
页数:13
相关论文
共 50 条
  • [31] DEVELOPMENT OF GEO-INFORMATION DATA MANAGEMENT SYSTEM AND APPLICATION TO GEOLOGICAL DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE IN CHINA
    Wang, Peng
    Huang, Shu-Tao
    Wang, Ju
    Zhao, Yong-An
    Gao, Min
    Wu, Lun
    Cai, Heng
    NUCLEAR TECHNOLOGY & RADIATION PROTECTION, 2017, 32 (03) : 294 - 301
  • [32] Corrosion of carbon steel components in the French high-level waste programme: evolution of disposal concept and selection of materials
    Crusset, Didier
    Deydier, Valerie
    Necib, Sophia
    Gras, Jean-Marie
    Combrade, Pierre
    Feron, Damien
    Burger, Emilien
    CORROSION ENGINEERING SCIENCE AND TECHNOLOGY, 2017, 52 : 17 - 24
  • [33] CORROSION OF HIGH-LEVEL WASTE PACKAGING MATERIALS IN DISPOSAL RELEVANT BRINES
    SMAILOS, E
    NUCLEAR TECHNOLOGY, 1993, 104 (03) : 343 - 350
  • [34] Thermal Performance Analysis of Geologic High-Level Radioactive Waste Packages
    Lee, Si Y.
    Hensel, Steve J.
    De Bock, Chris
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2011, 133 (06):
  • [35] A contribution to the analysis of equity associated with high-level radioactive waste management
    Kermisch, Celine
    Depaus, Christophe
    Labeau, Pierre-Etienne
    PROGRESS IN NUCLEAR ENERGY, 2016, 92 : 40 - 47
  • [36] Direct Shear Experimental Study on the Mobilized Dilation Behavior of Granite in Alxa Candidate Area for High-Level Radioactive Waste Disposal
    Cheng, Cheng
    Li, Xiao
    Xu, Nengxiong
    Zheng, Bo
    ENERGIES, 2020, 13 (01)
  • [37] Estimation of the corrosion thickness of a disposal container for high-level radioactive wastes in a wet blentonite
    Kim, Seung Soo
    Chun, Kwan Sik
    Kang, Kwang Cheol
    Baik, Min Hoon
    Kwon, Soo Han
    Choi, Jong Won
    JOURNAL OF INDUSTRIAL AND ENGINEERING CHEMISTRY, 2007, 13 (06) : 959 - 964
  • [38] Chemical and mineralogical characterizations of a low-pH cementitious material designed for the disposal cell of the high-level radioactive waste (HLW)
    Bonnet, J.
    Mosser-Ruck, R.
    Sterpenich, J.
    Bourdelle, F.
    Verron, H.
    Michau, N.
    Bourbon, X.
    Linard, Y.
    CEMENT AND CONCRETE RESEARCH, 2022, 162
  • [39] Temperature and tortuosity effect on gas migration in a high-level waste disposal tunnel
    Justinavicius, D.
    Poskas, P.
    MINERALOGICAL MAGAZINE, 2015, 79 (06) : 1317 - 1325
  • [40] Evaluation of the technical options of radioactive waste management for utilization of MOX fuel: thermal impact of minor actinide separation with geological disposal of high-level waste
    Minari, Eriko
    Okamura, Tomohiro
    Nakase, Masahiko
    Asano, Hidekazu
    Takeshita, Kenji
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2021, 58 (10) : 1123 - 1133