| 2021-03 | Composition-segmented BiSbTe thermoelectric generator fabricated by multimaterial 3D printing | Yang, Seong Eun; Kim, Fredrick, et al | ARTICLE | 33 |
| 2021-02 | Criticality benchmark of Monte Carlo code MCS for light water reactor fuel in transportation and storage packages | Lee, Hochul; Jang, Jaerim, et al | ARTICLE | 21 |
| 2021-01 | Radiological safety assessment of lead shielded spent resin treatment facility with the treatment capacity of 1 ton/day | Byun, Jaehoon; Choi, Woo Nyun, et al | ARTICLE | 117 |
| 2020-12 | Neutronic simulation of China experimental fast reactor start-up tests- part II: MCS code Monte Carlo calculation | Tuan Quoc Tran; Choe, Jiwon, et al | ARTICLE | 60 |
| 2020-12 | Deep learning-based procedure compliance check system for nuclear power plant emergency operation | Ahn, Jeeyea; Lee, Seung Jun | ARTICLE | 89 |
| 2020-12 | Selective and efficient extraction of Nd from NdFeB magnets via ionization in LiCl-KCl-CdCl2 melt | Jeon, Younghwan; Hur, Jungho, et al | ARTICLE | 33 |
| 2020-12 | A Multi-Physics Adaptive Time Step Coupling Algorithm for Light-Water Reactor Core Transient and Accident Simulation | Cherezov, Alexey; Park, Jinsu, et al | ARTICLE | 20 |
| 2020-12 | Radiological safety evaluation of dismantled radioactive concrete from Kori Unit 1 in the disposal and recycling process | Lee, ChoongWie; Kim, Hee Reyoung | ARTICLE | 29 |
| 2020-11 | A Sensor Fault-Tolerant Accident Diagnosis System | Choi, Jeonghun; Lee, Seung Jun | ARTICLE | 62 |
| 2020-11 | Modelling and analysis of extra vessel electro magnetic pump for a small modular lead-bismuth fast reactor | Kwak, Jaesik; Kim, Hee Reyoung | ARTICLE | 52 |
| 2020-11 | Development of a multi-unit seismic conditional core damage probability model with uncertainty analysis | Heo, Yunyeong; Lee, Seung Jun | ARTICLE | 23 |
| 2020-11 | A convolutional neural network model for abnormality diagnosis in a nuclear power plant | Lee, Gyumin; Lee, Seung Jun, et al | ARTICLE | 46 |
| 2020-11 | Numerical Analysis of the Temperature Distribution of the EM Pump for the Sodium Thermo-hydraulic Test Loop of the GenIV PGSFR | Kwak, Jaesik; Kim, Hee Reyoung | ARTICLE | 26 |
| 2020-11 | RAST-K v2—Three-Dimensional Nodal Diffusion Code for Pressurized Water Reactor Core Analysis | Park, Jinsu; Jang, Jaerim, et al | ARTICLE | 50 |
| 2020-11 | Grain growth and densification of uranium mononitride during spark plasma sintering | Kim, Gyeonghun; Ahn, Jungsu, et al | ARTICLE | 22 |
| 2020-10 | Photoneutron reaction kinematics and error of commonly used approximations | Fynan, Douglas A. | ARTICLE | 83 |
| 2020-10 | Structural Stability Analysis of Waste Packages Containing Low- and Intermediate-Level Radioactive Waste in a Silo-type Repository | Byeon, Hyeongjin; Jeong, Gwan Yoon, et al | ARTICLE | 61 |
| 2020-10 | A PCA compression method for reactor core transient multiphysics simulation | Cherezov, Alexey; Jang, Jaerim, et al | ARTICLE | 21 |
| 2020-09 | Spectral resolution evaluation by MCNP simulation for airborne alpha detection system with a collimator | Kim, Min Ji; Sung, Si Hyeong, et al | ARTICLE | 43 |
| 2020-09 | Effective energy management design of spent fuel dry storage based on hybrid controlrod-heatpipe | Kim, Kyung Mo; Bang, In Cheol | ARTICLE | 32 |
