| 2023-12 | Experimental estimation of radiation damage induced by 10B(n, α)7Li reactions in Al-B4C neutron absorber discharged from spent nuclear fuel pool | Jung, Yunsong; Kim, Geon, et al | ARTICLE | 68 |
| 2023-12 | Safety analysis and evaluation of transport and storage container for very Low-Level liquid radioactive waste | Choi, Woo Nyun; Shin, Seung Hun, et al | ARTICLE | 316 |
| 2023-11 | Experimental investigation of thermal behavior of overfilled sodium heat pipe | Lee, Dong Hun; Bang, In Cheol | ARTICLE | 94 |
| 2023-11 | Effects of Cr and Mo contents on the flow-accelerated corrosion behavior of low alloy steels in the secondary side of pressurized water reactors | Kim, Seunghyun; Kim, Gidong, et al | ARTICLE | 30 |
| 2023-10 | Effects of yttrium on the oxidation behavior of Fe13Cr6AlY alloys under 1200 & DEG;C steam | Kim, Sungyu; Lee, Chang-Hoon, et al | ARTICLE | 224 |
| 2023-10 | Seismic Analysis of Waste Packages Stacked in Radioactive Waste Disposal Silos | Byeon, Hyeongin; Park, Jaeyeong, et al | ARTICLE | 428 |
| 2023-10 | Experimental characterization of the flowline of a lithium film formed using an electromagnetic thruster for a RAON prototype charge stripper | Kang, Tae Uk; Lee, Geunhyeong, et al | ARTICLE | 224 |
| 2023-09 | Experimental investigation of heat transfer limitations in concentric annular sodium heat pipes and thermosyphon | Lee, Dong Hun; Bang, In Cheol | ARTICLE | 92 |
| 2023-09 | Experimental study on 3D printed heat pipes with hybrid screen-groove combined capillary wick structure | Park, Ye Yeong; Bang, In Cheol | ARTICLE | 92 |
| 2023-09 | High fidelity transient solver in STREAM based on multigroup coarse-mesh finite difference method | Rahman, Anisur; Lee, Hyun Chul, et al | ARTICLE | 70 |
| 2023-09 | Dose analysis of nearby residents and workers due to the emission accident of gaseous radioactive material at the spent resin mixture treatment facility | Byun, Jaehoon; Yoon, Seungbin, et al | ARTICLE | 86 |
| 2023-09 | The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operation | Kim, Ji Yong; Lee, Yunju, et al | ARTICLE | 52 |
| 2023-09 | Expedited spark plasma sintering of high‐density uranium mononitride pellet utilizing U2</sub>N3</sub> powder | Ahn, Jungsu; Kim, Geon, et al | ARTICLE | 80 |
| 2023-09 | Deep reinforcement learning for a multi-objective operation in a nuclear power plant | Bae, Junyong; Kim, Jae Min, et al | ARTICLE | 98 |
| 2023-08 | Stability of Cr oxide formed on Fe-20Cr-2Si alloy in 1200 degrees C steam or oxygen | Moon, Joonho; Kim, Sungyu, et al | ARTICLE | 230 |
| 2023-08 | Beta-Ray-Bremsstrahlung Contributions to Short-Lived Delayed Photoneutron Groups in Heavy Water Reactors | Setiawan, Yanuar Ady; Sengar, Hemantika, et al | ARTICLE | 444 |
| 2023-08 | Leachability of Lead, Cadmium, and Antimony in Cement Solidified Waste in a Silo-Type Radioactive Waste Disposal Facility Environment | Lee, Yulim; Byeon, Hyeongjin, et al | ARTICLE | 574 |
| 2023-08 | Deep learning-based label-free hematology analysis framework using optical diffraction tomography | Ryu, Dongmin; Bak, Taeyoung, et al | ARTICLE | 58 |
| 2023-07 | Multi-Abnormality Attention Diagnosis Model Using One-vs-Rest Classifier in a Nuclear Power Plant | Cho, Seung Gyu; Choi, Jeonghun, et al | ARTICLE | 60 |
| 2023-06 | Development of an artificial neural network model for generating macroscopic cross-sections for RAST-AI | Dzianisau, Siarhei; Saeju, Korawit, et al | ARTICLE | 607 |
