Effect of supplementary cementitious materials on the degradation of cement-based barriers in radioactive waste repository: A case study in Korea

Kim, Min-Seok; Han, Sol-Chan; Yun, Jong-Il

doi:10.1016/j.net.2024.04.041

Effect of supplementary cementitious materials on the degradation of cement-based barriers in radioactive waste repository: A case study in Korea

Journal Article · Sat Apr 27 00:00:00 UTC 2024 · Nuclear Engineering and Technology

DOI:https://doi.org/10.1016/j.net.2024.04.041· OSTI ID:2476125

Kim, Min-Seok ^[1]; ^[2]; Yun, Jong-Il ^[3]

Korea Advanced Institute of Science and Technology (KAIST), Daejeon (Korea, Republic of); Korea Radioactive Waste Agency, Gyeongju, Gyeongsangbuk-do (Korea, Republic of)
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Korea Advanced Institute of Science and Technology (KAIST), Daejeon (Korea, Republic of)

This study focuses on investigating the chemical degradation characteristics of cementitious barriers used in low- and intermediate-level radioactive waste repository by reactive transport modeling. The impact of the blending with supplementary cementitious materials (SCMs) in the barriers on the chemical degradation was evaluated to find the optimum barrier design. A number of different barrier designs were examined by replacing ordinary Portland cement (OPC) by SCMs (i.e., fly ash, silica fume, and blast-furnace slag). The simulation results showed that silica fume blended barrier has better durability against chemical degradation by rainwater compared to fly ash or blast-furnace slag blended barriers. In addition, the chemical durability of silica fume-based barrier increased with increasing replacement level up to about 20 %. It seems that the amount of formed calcium silicate hydrate (CSH) in the initial cement-based barrier highly affects the overall chemical durability. The newly developed reactive transport model demonstrated its capability for understanding the barrier performance and investigating the optimal design of the barrier system.

View Accepted Manuscript (DOE)

Research Organization:: Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)

Sponsoring Organization:: Korea government, Ministry of Trade, Industry and Energy (MOTIE); USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: AC52-07NA27344

OSTI ID:: 2476125

Report Number(s):: LLNL--JRNL-854329; 1082131

Journal Information:: Nuclear Engineering and Technology, Journal Name: Nuclear Engineering and Technology Journal Issue: 9 Vol. 56; ISSN 1738-5733

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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