권호 표지

방사성폐기물학회지 (Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)) (Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT))

한국방사성폐기물학회 (Korean Radioactive Waste Society)

  • 계간
  • /
  • 1738-1894(pISSN)
  • /
  • 2288-5471(eISSN)

과학기술표준분류

  • 원자력 ＞ 핵연료주기/방사성폐기물 관리 기술

Aim & Scope

Journal of Nuclear Fuel Cycle and Waste Technology (JNFCWT) is a quarterly journal publishing peer-reviewed papers in various research areas associated with the nuclear fuel cycle and radioactive waste management. The journal is managed by the Korean Radioactive Waste Society. JNFCWT provides a forum for all stakeholders in the field of nuclear fuel cycle and radioactive waste management aiming at sharing and disseminating state of the art technical information, lessons learned from industrial experiences, and discussions on current socio-political issues. JNFCWT publishes the results of original research in the format of review articles, commentaries, and technical notes. From Volume 1 (2003) to Volume 11 (2013), this journal was published as the Journal of the Korean Radioactive Waste Society. It was renamed to the Journal of Nuclear Fuel Cycle and Waste Technology (JNFCWT) in 2013. As of 2019, the journal is listed in the SCOPUS of Elsevier. JNFCWT covers the following fields related to the nuclear fuel cycle and radioactive waste management as follows: 1. Policy, Safety, and Regulation of Nuclear Fuel Cycle / Non-proliferation, Safeguards, and Nuclear Security 2. Treatment, Transportation, and Storage of Spent Nuclear Fuel / Molten Salt Chemistry and Technology 3. High-Level Waste Immobilization and Disposal Technologies 4. Low- and Intermediate-Level Radioactive Waste Management 5. Decommissioning and Environmental Remediation 6. Radiation Protection, Shielding, and Environment 7. Radiochemistry and Nuclear Chemistry

http://www.krs.or.kr KSCI KCI SCOPUS

제17권S호

  1. Kim, Geon Young;Lee, Jae Owan;Cho, Won-Jin;Baik, Min-Hoon 1
    https://doi.org/10.7733/jnfcwt.2019.17.S.1 KSCI
    Engineering scale in-situ demonstration of engineered barrier system performance (In-DEBS) based on the advanced Korean reference repository system (A-KRS) was planned from 2012. The whole system was designed and manufactured by the Korea Atomic Energy Research Institute (KAERI) and installed in the KAERI Underground Research Tunnel (KURT) in May, 2016. Operation started in July, 2016 and quality thermal, hydro, and mechanical (THM) data have been produced. This is the first engineering scale in-situ test of a deep geological repository system performance for high level radioactive waste disposal in Korea. The main purpose of this test is the development of verification technology for engineered barrier system (EBS) performance of deep geological repository system by demonstration of manufacturing techniques for large scale disposal canisters and buffer, demonstration of installation of unit module of disposal system, acquisition of long-term THM behavior data around domestic bentonite EBS, validation of the modeling techniques for coupled THM behavior, and development and demonstration of monitoring techniques for major parameters in buffer. With the successful installation and operation of In-DEBS, we have secured demonstration and modeling techniques for coupled THM behavior of EBS using in-situ test data, which form the core of Research, Development, and Demonstration (RD&D) for High-level Radioactive Waste (HLW) disposal technology, as well as securing manufacturing and installation technology of engineering scale EBS. It is expected that the results of the In-DEBS test will provide important information for technology development of a future real scale experiments of Korean repository system.
  2. Ko, Nak-Youl;Cho, Wan Hyoung;Kim, Geon Young 15
    https://doi.org/10.7733/jnfcwt.2019.17.S.15 KSCI
    In order to understand behaviors of engineered barriers for geological disposal of high-level radioactive wastes, an In-DEBS (In-situ Demonstration of Engineered Barrier System) test was planned. Geological and hydrogeological data of KURT (KAERI Underground Research Tunnel) site were obtained and analyzed to select an appropriate position for the In-DEBS test. Proper research galleries in the extended section of KURT were decided on for the test using regional data of the KURT site. Borehole investigations were carried out to examine local properties of the research galleries in order to characterize groundwater flow and evaluate groundwater inflow at the research galleries. The data from the borehole investigations provided the basis for selecting the position of a large-diameter borehole for the In-DEBS test as well as other practical requirements for implementing the test in the KURT conditions. From in-situ investigation of a wall of the large-diameter borehole, groundwater inflow and distribution of hydraulic conductivity at the wall were evaluated. The hydrogeological data and analysis results in this study can be applied to understand and simulate the evolution of the behavior of In-DEBS and nearby rocks.
  3. Kim, Jin-Seop;Choi, Young-Chul;Lee, Minsoo;Lee, Changsoo;Yoon, Seok;Cho, Won-Jin;Kim, Geon Young 25
    https://doi.org/10.7733/jnfcwt.2019.17.S.25 KSCI
    The objective of this study is to propose a design for the In-DEBS (In-situ Demonstration of Engineered Barrier System) and suggest optimized conditions for manufacturing engineered barriers. The In-DEBS design was made from the AKRS (Advanced Korea Reference disposal System of HLW), based on performance experience carried out at KAERI (Korea Atomic Energy Research Institute) and from literature reviews. The optimal manufacturing conditions were derived from the test production with regard to the canister and the bentonite buffer. The performance of the manufactured engineered barriers was also evaluated in advance of in-situ application. In-DEBS was designed at 1/2.3 scale of AKRS. An aluminum mold-type heater of 4.2 kW was used to simulate the heating from nuclear fuel. A new methodology using a floating die press and CIP (Cold Isostatic Press) was introduced to fabricate a reliable engineering-scale buffer block for in-situ experiments, leading to a homogeneous and uniform distribution in the densities of the buffer blocks. From the test results, it was found that a floating die press of 40 MPa and CIP of 50 MPa are necessary to satisfy AKRS design premises for the buffer blocks (dry density > 1.6 kg·cm-3). With regard to the THM sensor installations, CNC (Computer Numerical Control) was applied to shape the sensor holes.
  4. Choi, Young-Chul;Kim, Jin-Seop;Yoon, Seok;Lee, Changsoo 45
    https://doi.org/10.7733/jnfcwt.2019.17.S.45 KSCI
    The paper describes the process of developing and implementing In-DEBS (In-situ Demonstration of Engineered Barrier System) for analyzing thermal-hydraulic-mechanical (THM) coupled behavior characteristics of an engineered barrier system in a high-level waste disposal system. The engineered barrier system is composed of a disposal canister, buffer, and near field rock. In-DEBS is designed to analyze the THM coupled behavior due to the inflow of underground water and the heat of disposal canisters in the buffer and near field rock. Since it is difficult to assemble the buffer block while installing sensors and heaters in a disposal hole, the buffer blocks were assembled from the outside. OBPA (One-Body Pre-Assembly) assembled with buffer blocks, sensors and heater requires special transport equipment to accurately insert it into the disposal hole because the total weight is about three tones. In this study, the fully assembled buffer block was inserted by developing a crane exclusively for In-DEBS, which can be moved into an accurate position by lifting more than five tones. To analyze the THM coupled behavior of the near field rock, 4 test holes were cored around In-DEBS and a total of 40 temperature sensors and 5 pore pressure sensors were installed in the test hole. A total of 185 sensors for temperature, relative humidity, pressure and displacement sensors were installed in the In-DEBS. All sensors were connected to a multichannel measuring system that stores field data in real time.
  5. Lee, Changsoo;Yoon, Seok;Cho, Won-Jin;Jo, Yeonguk;Lee, Sudeuk;Jeon, Seokwon;Kim, Geon Young 65
    https://doi.org/10.7733/jnfcwt.2019.17.S.65 KSCI
    In 2012, an in-situ Demonstration of Engineered Barrier System (In-DEBS) was planned with the aim of investigating the coupled thermohydro-mechanical (THM) behavior of both the engineered barrier system (EBS) and the natural barrier system (NBS) at the advanced Korean reference repository system (A-KRS). The relevant in-situ experiment has been in operation in Research Gallery 3 of the KAERI Underground Research Tunnel (KURT) since May 2016. For analysis of the in-situ experiment data and investigation of the THM coupled behavior, it is necessary to understand thermal, hydraulic, and mechanical properties of KURT granite and bentonite buffer material. This paper summarizes the thermal, hydraulic, and mechanical properties of KURT granite and Gyeongju bentonite presented in previous studies. Moreover, it suggests various models capable of providing input parameters for interpretative modeling of In-DEBS experiment or for predictive numerical simulations of In-DEBS or A-KRS.
  6. 최영철;조원진;이재완;김건영 81
    https://doi.org/10.7733/jnfcwt.2019.17.S.81 KSCI
    This paper is intended to describe the field experimental data obtained from the initial operation of In-DEBS (Engineering scale in-situ demonstration of engineered barrier system), which is installed to analyze the THM (thermal, hydro, and mechanical) coupled behavior of engineered barrier system. On the top, which is plugged with concrete, heat is generated during the curing process of concrete. The heat affects the buffer and the near-field rock. The temperature of the buffer and the near field rock becomes less and less farther away from the plugging. Sensors and measurement system were verified using these phenomena. To protect the measurement system, the heater temperature was gradually increased to 100°C over one week, and the temperature of the heater surface was maintained at the target temperature. After heater operation, the temperature of the buffer reached the steady state in about four days, and the relative humidity increased and gradually decreased after a certain period of time. Also, the total pressure of the buffer was increased by swelling due to groundwater saturation. After the heater was started, it was observed that the temperature and displacement of the near-field rock continued to increase.
  7. Lee, Changsoo;Lee, Jaewon;Lee, Jae Owan;Cho, Won-Jin;Kim, Geon Young 97
    https://doi.org/10.7733/jnfcwt.2019.17.S.97 KSCI
    Coupled thermo-hydraulic (TH) behavior is expected owing to a decay heat from high-level radioactive waste and water intake from rockmass in high-level radioactive waste disposal system. And coupled thermo-hydro-mechanical (THM) behavior is expected in high-level radioactive waste disposal system owing to thermal stress and swelling pressure generated by changes in temperature and saturation. Since 2016, an in-situ demonstration of an engineered barrier system (In-DEBS) at the KAERI Underground Research Tunnel (KURT) has been performed to investigate the coupled THM behavior in the high-level radioactive waste disposal system and nearby rockmass. In this study, a numerical simulation using TOUGH-MP/FLAC3D and an axisymmetric model was carried out to analyze the in-situ experimental data and estimate the coupled THM behavior. In addition, input parameters and THM models used in this study are evaluated and the practical applicability of TOUGH2-MP/FLAC3D to THM simulations is examined by comparison of in-situ data with calculation results. Temperature and relative humidity evolutions are well captured in the numerical simulation. In addition, even though the calculated displacement is relatively small, its evolution trend shows agreement with the in-situ data. The axisymmetric model was useful for analyzing coupled THM behavior in the In-DEBS experiment however, a 3D analysis including a consideration of the effect of KURT geometry is necessary to thoroughly investigate coupled THM behavior in the rockmass. The input parameters and the THM models in this study can be applied to predict the long-term behavior in the In-DEBS experiment and to carry out a performance assessment of the coupled THM behavior in a high-level radioactive waste disposal system.