C-14 in Geological Repositories: Source Terms and Transport Models

Abstract Spent fuel management is one of the key issues for the sustainable development of nuclear energy. The deep geological disposal of radioactive waste is a vital aspect of spent fuel management, aiming to isolate radioactive sources from humans and circulating groundwater as much as possible. Buffer materials, as a crucial part of the engineering barrier system, play an important role in preventing the infiltration of groundwater and the outward migration of radioactive nuclides. However, due to a variety of unforeseen circumstances, there remains a risk of leakage in geological repositories, potentially leading to the radioactive sources penetrating the engineering barrier system and causing environmental damage. Carbon-14 (C-14) is one of the significant radioactive elements in China’s geological repositories. In the event of repository damage, C-14 could enter the biosphere and infiltrate the human body through the food chain. It could pose internal radiation hazards to human tissues and organs, which becomes a major source of collective radiation dose for humans. In recent years, there has been significant progress in the study of buffer materials for high-level radioactive waste (HLW) geological repositories in China, including the development of GMZ01 type bentonite as a buffer material. Extensive research has been conducted on the basic physicochemical properties and nuclide adsorption characteristics of these materials. However, studies specifically related to C-14 in these repositories are less common. The methods for assessing the inventory of C-14 in the repositories need to be refined. Although some computational models for simulating the migration process of C-14 from the repositories to the environment have been proposed, there is a lack of comprehensive summaries. Additionally, the overall research framework for the migration process of C-14 in buffer materials is not clear. Therefore, the study of the C-14 source term in geological repositories and its migration and diffusion behavior in bentonite, such as GMZ01 type, is a crucial part of the radiation safety assessment in geological repositories in China. This paper focuses on C-14, which is a typical radionuclide in radioactive source terms in geological repositories, investigates the research progress on the C-14 source term in geological repositories both domestically and internationally, organizes the methods for assessing the inventory of C-14 in repositories and compiles computational models for the migration and diffusion behavior of C-14 in key buffer materials. This paper aims to provide theoretical support for the analysis of the C-14 source term in high-level radioactive waste geological repositories and the study of C-14 migration processes in buffer materials, which could provide an important research basis for the radiation safety evaluation of high-level waste geological repositories in China.

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Published
2024-08-04
DOI
https://doi.org/10.1115/icone31-134283
Primary Topic
Scientific Computing and Data Management
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C-14 in Geological Repositories: Source Terms and Transport Models

Mengjie Wu, Zhengzhe Qu, Jianzhu Cao, Jingni Guo et al.
Scientific Computing and Data Management
article

C-14 in Geological Repositories: Source Terms and Transport Models

Mengjie Wu, Zhengzhe Qu, Jianzhu Cao, Jingni Guo, Feng Xie, Qi Zhang, Liqiang Wei, Yu Wang
article en

Abstract

Abstract Spent fuel management is one of the key issues for the sustainable development of nuclear energy. The deep geological disposal of radioactive waste is a vital aspect of spent fuel management, aiming to isolate radioactive sources from humans and circulating groundwater as much as possible. Buffer materials, as a crucial part of the engineering barrier system, play an important role in preventing the infiltration of groundwater and the outward migration of radioactive nuclides. However, due to a variety of unforeseen circumstances, there remains a risk of leakage in geological repositories, potentially leading to the radioactive sources penetrating the engineering barrier system and causing environmental damage. Carbon-14 (C-14) is one of the significant radioactive elements in China’s geological repositories. In the event of repository damage, C-14 could enter the biosphere and infiltrate the human body through the food chain. It could pose internal radiation hazards to human tissues and organs, which becomes a major source of collective radiation dose for humans. In recent years, there has been significant progress in the study of buffer materials for high-level radioactive waste (HLW) geological repositories in China, including the development of GMZ01 type bentonite as a buffer material. Extensive research has been conducted on the basic physicochemical properties and nuclide adsorption characteristics of these materials. However, studies specifically related to C-14 in these repositories are less common. The methods for assessing the inventory of C-14 in the repositories need to be refined. Although some computational models for simulating the migration process of C-14 from the repositories to the environment have been proposed, there is a lack of comprehensive summaries. Additionally, the overall research framework for the migration process of C-14 in buffer materials is not clear. Therefore, the study of the C-14 source term in geological repositories and its migration and diffusion behavior in bentonite, such as GMZ01 type, is a crucial part of the radiation safety assessment in geological repositories in China. This paper focuses on C-14, which is a typical radionuclide in radioactive source terms in geological repositories, investigates the research progress on the C-14 source term in geological repositories both domestically and internationally, organizes the methods for assessing the inventory of C-14 in repositories and compiles computational models for the migration and diffusion behavior of C-14 in key buffer materials. This paper aims to provide theoretical support for the analysis of the C-14 source term in high-level radioactive waste geological repositories and the study of C-14 migration processes in buffer materials, which could provide an important research basis for the radiation safety evaluation of high-level waste geological repositories in China.

Beijing Research Institute of Uranium Geology (CN), Tsinghua University (CN)
Openalex Percentile: Top 78%
Scientific Computing and Data Management
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