Heejae Ju

ORCID: 0000-0002-3879-8770
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About
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Research Areas
  • Nuclear and radioactivity studies
  • Graphite, nuclear technology, radiation studies
  • Nuclear Materials and Properties
  • Corrosion Behavior and Inhibition
  • Risk and Safety Analysis
  • Nuclear reactor physics and engineering
  • Radioactive contamination and transfer
  • Enhanced Oil Recovery Techniques
  • Nuclear Engineering Thermal-Hydraulics
  • Molten salt chemistry and electrochemical processes
  • Hydrogen embrittlement and corrosion behaviors in metals
  • Radioactive element chemistry and processing
  • Electrodeposition and Electroless Coatings
  • Extraction and Separation Processes
  • Radioactivity and Radon Measurements
  • Groundwater flow and contamination studies
  • Anodic Oxide Films and Nanostructures
  • Rare-earth and actinide compounds
  • Laser-induced spectroscopy and plasma
  • Nuclear Physics and Applications

Korea Atomic Energy Research Institute
2019-2024

Korea Advanced Institute of Science and Technology
2018-2019

Seoul National University
2016-2017

To use nuclear energy sustainably, spent fuel, classified as high-level radioactive waste and inevitably discharged after electricity generation by power plants, must be managed safely isolated from the human environment. In Korea, land area is limited amount of waste, including fuels to disposed, relatively large. Thus, it particularly necessary maximize disposal efficiency. this study, a high-efficiency deep geological repository concept was developed enhance end, design strategies...

10.1016/j.net.2023.02.031 article EN cc-by-nc-nd Nuclear Engineering and Technology 2023-03-01

Based on the current high-level radioactive waste management basic plan and analysis results of spent nuclear fuel characteristics, such as dimensions decay heat, an improved geological disposal concept for from domestic power plants was proposed in this study. To end, container concepts two types reactors, pressurized water reactor (PWR) Canada deuterium uranium (CANDU), considering interim storage method, were derived. In addition, cooling time at disposal, according to plan-based...

10.7733/jnfcwt.2020.18.s.1 article EN cc-by-nc Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) 2020-11-30

This study developed a safety assessment tool for geological disposal systems called APro, systemically integrated modeling system based on modularizing and coupling the processes which need to be considered in system. Thermal, hydraulic, chemical, canister failure, radionuclide release transport were current version of APro. Each unit APro consists single Default Module, several Alternative Modules can increase flexibility model. As an initial stage developing modularization concept...

10.1016/j.net.2022.02.018 article EN cc-by-nc-nd Nuclear Engineering and Technology 2022-02-26

Abstract Canister performance is a major issue for constructing reliable deep geological repositories storing spent nuclear fuels, and corrosion resistance main the factor determining canister durability. We developed 2-D multiphysics model, which can predict both rate potential, simulating copper in repositories. found that canisters corroded through long-cell action repository, was quite limited, overall durability around 1.7 million years. Our results demonstrated exhibits sufficient...

10.1038/s41529-023-00345-6 article EN cc-by npj Materials Degradation 2023-04-08

Copper canisters are commonly employed to contain HLW for the long-term, making it crucial understand how corrosion affects canister. This study conducted a comparative analysis of two widely used calculation methods modeling canister within 3-D DGR domain. The first method, termed transport-limited corrosion, assumes an immediate sulfide-copper reaction and has been traditionally due its conservative nature. second known as potential-limited considers coupled redox reactions at surface...

10.1016/j.net.2024.03.039 article EN cc-by-nc-nd Nuclear Engineering and Technology 2024-03-30

We have conducted a long-term environmental assessment of geological repository for Intermediate Level Wastes (ILW) arising from PyroGreen processes that has been developed to decontaminate all HLW the pyrochemical partitioning spent nuclear fuels (SNF). process designed so final ILW can meet conservative acceptance criteria such as one established Waste Isolation Pilot Plant (WIPP) in U.S.A. The nuclide inventory vitrified waste is calculated using ORIGEN 2.1 based on design decontamination...

10.1016/j.proche.2016.10.059 article EN Procedia Chemistry 2016-01-01

The Korea Atomic Energy Research Institute (KAERI) has developed geological repository systems for the disposal of high-level wastes and spent nuclear fuels (SNFs) in South Korea. purpose most recently system, improved KAERI Reference Disposal System Plus (KRS+), is to dispose all SNFs with area efficiency. In this paper, a system-level safety assessment model KRS+ presented long-term results. A used evaluate overall performance system rather than simulating single component. Because site...

10.7733/jnfcwt.2020.18.s.75 article EN cc-by-nc Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) 2020-11-30

Abstract Canister performance is a major issue for constructing reliable deep geological repositories storing spent nuclear fuels, and corrosion resistance main the factor determining canister durability. We developed 2-D multiphysics model, which can predict both rate potential, simulating copper in repositories. found that canisters corroded through long-cell action repository, was quite limited, overall durability around 1.7 million years. Our results demonstrated exhibits sufficient...

10.21203/rs.3.rs-2133968/v1 preprint EN cc-by Research Square (Research Square) 2022-10-17
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