Pressure evaluation of a gap space in the engineered barrier system in a high-level radioactive waste repository

被引:1
|
作者
Yoon, Seok [1 ]
Lee, Gi-Jun [1 ]
An, Sangjun [2 ]
机构
[1] KAERI, Disposal Safety Evaluat Res Div, Daejeon 34057, South Korea
[2] KAERI, SMART Reactor Dev Div, Daejeon 34057, South Korea
基金
新加坡国家研究基金会;
关键词
Air gap; Compacted bentonite buffer material; Pressure variations; TEMPERATURE; BUFFER;
D O I
10.1016/j.csite.2023.103458
中图分类号
O414.1 [热力学];
学科分类号
摘要
Disposal canisters and buffer materials are main components in an engineered barrier system designed for high-level radioactive waste disposal. The design temperature of the buffer material is below 100 degrees C in most countries, and many studies have been conducted to increase the design temperature of the buffer material to increase the disposal density of the repository. A 1-cm air gap exists between the canister and buffer material that can cause several variations in the thermal-hydraulic-mechanical performance of the compacted bentonite buffer material. Therefore, considering the air-gap effect under high-temperature conditions is necessary because high temperatures can cause pressure variations in the air gap and compacted bentonites. Therefore, an experimental system was developed to measure the pressure variations in a confined cell, which contained air and compacted bentonites from room temperature to 150 degrees C. The pressure of the confined cell increased with increasing water content of the compacted bentonite, and the pressure changes were similar up to 100 degrees C irrespective of the presence of the 1-cm air gaps. Moreover, the pressure values at 150 degrees C were 10-15% higher in samples without gaps.
引用
收藏
页数:9
相关论文
共 50 条
  • [1] Modeling the risk of U(VI) migration through an engineered barrier system at a proposed Chinese high-level radioactive waste repository
    Cao, Xiaoyuan
    Zheng, Liange
    Hou, Deyi
    O'Connor, David
    Hu, Litang
    Wu, Jin
    SCIENCE OF THE TOTAL ENVIRONMENT, 2020, 707
  • [2] Prediction Model for Saturated Hydraulic Conductivity of Bentonite Buffer Materials for an Engineered-Barrier System in a High-Level Radioactive Waste Repository
    Lee, Gi-Jun
    Yoon, Seok
    Kim, Bong-Ju
    JOURNAL OF NUCLEAR FUEL CYCLE AND WASTE TECHNOLOGY, 2023, 21 (02): : 225 - 234
  • [3] AN ANALYSIS OF THE THERMAL AND MECHANICAL BEHAVIOR OF ENGINEERED BARRIERS IN A HIGH-LEVEL RADIOACTIVE WASTE REPOSITORY
    Kwon, S.
    Cho, W. J.
    Lee, J. O.
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2013, 45 (01) : 41 - 52
  • [4] Analysis of thermo-hydro-mechanical process in the engineered barrier system of a high-level waste repository
    Cho, Won-Jin
    Lee, Jae-Owan
    Kwon, Sangki
    NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (06) : 1688 - 1698
  • [5] Evaluation on the buffer temperature by thermal conductivity of gap- filling material in a high-level radioactive waste repository
    Yoon, Seok
    Kim, Min -Jun
    Chang, Seeun
    Lee, Gi-Jun
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2022, 54 (11) : 4005 - 4012
  • [6] Study on the permeability of engineered barrier for the enhancement of a radioactive waste repository system
    Tashiro, S
    Fujiwara, A
    Senoo, M
    NUCLEAR TECHNOLOGY, 1998, 121 (01) : 14 - 23
  • [8] Modeling the solubility of zirconia in a repository for high-level radioactive waste
    Curti, E
    Hummel, W
    JOURNAL OF NUCLEAR MATERIALS, 1999, 274 (1-2) : 189 - 196
  • [9] Canister spacing in high-level radioactive nuclear waste repository
    Zhou, Xiang-yun
    Sun, De'an
    Tan, Yunzhi
    Zhou, Annan
    ANNALS OF NUCLEAR ENERGY, 2020, 141
  • [10] Probabilistic risk analysis for a high-level radioactive waste repository
    Cohen, BL
    RISK ANALYSIS, 2003, 23 (05) : 909 - 915