NUE_Journal Papers

Issue DateTitleAuthor(s)TypeView
2023-12Experimental estimation of radiation damage induced by 10B(n, α)7Li reactions in Al-B4C neutron absorber discharged from spent nuclear fuel poolJung, Yunsong; Kim, Geon, et alARTICLE68
2023-12Safety analysis and evaluation of transport and storage container for very Low-Level liquid radioactive wasteChoi, Woo Nyun; Shin, Seung Hun, et alARTICLE316
2023-11Experimental investigation of thermal behavior of overfilled sodium heat pipeLee, Dong Hun; Bang, In CheolARTICLE94
2023-11Effects of Cr and Mo contents on the flow-accelerated corrosion behavior of low alloy steels in the secondary side of pressurized water reactorsKim, Seunghyun; Kim, Gidong, et alARTICLE30
2023-10Effects of yttrium on the oxidation behavior of Fe13Cr6AlY alloys under 1200 & DEG;C steamKim, Sungyu; Lee, Chang-Hoon, et alARTICLE224
2023-10Seismic Analysis of Waste Packages Stacked in Radioactive Waste Disposal SilosByeon, Hyeongin; Park, Jaeyeong, et alARTICLE428
2023-10Experimental characterization of the flowline of a lithium film formed using an electromagnetic thruster for a RAON prototype charge stripperKang, Tae Uk; Lee, Geunhyeong, et alARTICLE224
2023-09Experimental investigation of heat transfer limitations in concentric annular sodium heat pipes and thermosyphonLee, Dong Hun; Bang, In CheolARTICLE92
2023-09Experimental study on 3D printed heat pipes with hybrid screen-groove combined capillary wick structurePark, Ye Yeong; Bang, In CheolARTICLE92
2023-09High fidelity transient solver in STREAM based on multigroup coarse-mesh finite difference methodRahman, Anisur; Lee, Hyun Chul, et alARTICLE70
2023-09Dose analysis of nearby residents and workers due to the emission accident of gaseous radioactive material at the spent resin mixture treatment facilityByun, Jaehoon; Yoon, Seungbin, et alARTICLE86
2023-09The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operationKim, Ji Yong; Lee, Yunju, et alARTICLE52
2023-09Expedited spark plasma sintering of high‐density uranium mononitride pellet utilizing U2</sub>N3</sub> powderAhn, Jungsu; Kim, Geon, et alARTICLE80
2023-09Deep reinforcement learning for a multi-objective operation in a nuclear power plantBae, Junyong; Kim, Jae Min, et alARTICLE98
2023-08Stability of Cr oxide formed on Fe-20Cr-2Si alloy in 1200 degrees C steam or oxygenMoon, Joonho; Kim, Sungyu, et alARTICLE230
2023-08Beta-Ray-Bremsstrahlung Contributions to Short-Lived Delayed Photoneutron Groups in Heavy Water ReactorsSetiawan, Yanuar Ady; Sengar, Hemantika, et alARTICLE444
2023-08Leachability of Lead, Cadmium, and Antimony in Cement Solidified Waste in a Silo-Type Radioactive Waste Disposal Facility EnvironmentLee, Yulim; Byeon, Hyeongjin, et alARTICLE574
2023-08Deep learning-based label-free hematology analysis framework using optical diffraction tomographyRyu, Dongmin; Bak, Taeyoung, et alARTICLE58
2023-07Multi-Abnormality Attention Diagnosis Model Using One-vs-Rest Classifier in a Nuclear Power PlantCho, Seung Gyu; Choi, Jeonghun, et alARTICLE60
2023-06Development of an artificial neural network model for generating macroscopic cross-sections for RAST-AIDzianisau, Siarhei; Saeju, Korawit, et alARTICLE607