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Showing results 1 to 20 of 38

Issue DateTitleAuthor(s)TypeView
2021-02A convolutional neural network model for abnormality diagnosis in a nuclear power plantLee, Gyumin; Lee, Seung Jun; Lee, ChangyongARTICLE62
2020-12A Multi-Physics Adaptive Time Step Coupling Algorithm for Light-Water Reactor Core Transient and Accident SimulationCherezov, Alexey; Park, Jinsu; Kim, Hanjoo; Choe, Jiwon; Lee, DeokjungARTICLE80
2020-10A PCA compression method for reactor core transient multiphysics simulationCherezov, Alexey; Jang, Jaerim; Lee, DeokjungARTICLE32
2020-11A Sensor Fault-Tolerant Accident Diagnosis SystemChoi, Jeonghun; Lee, Seung JunARTICLE75
2020-09Abnormal state diagnosis model tolerant to noise in plant dataShin, Ji Hyeon; Kim, Jae Min; Lee, Seung JunARTICLE55
2021-01Analysis of VVER-1000 mock-up criticality experiments with nuclear data library ENDF/B-VIII.0 and Monte Carlo code MCSSetiawan, Fathurrahman; Lemaire, Matthieu; Lee, DeokjungARTICLE41
2020-01Analytical local stress model for UMo/Al dispersion fuelJeong, Gwan Yoon; Kim, Yeon Soo; Park, JaeyeongARTICLE240
2021-03Composition-segmented BiSbTe thermoelectric generator fabricated by multimaterial 3D printingYang, Seong Eun; Kim, Fredrick; Ejaz, Faizan; Lee, Gi Seung; Ju, Hyejin; Choo, Seungjun; Lee, Jungsoo; Kim, Gyeonghun; Jung, Soo-ho; Ahn, Sangjoon; Chae, Han Gi; Kim, Kyung Tae; Kwon, Beomjin; Son, Jae SungARTICLE58
2020-06Conceptual design of long-cycle boron-free small modular pressurized water reactor with control rod operationJang, Jaerim; Choe, Jiwon; Choi, Sooyoung; Lemaire, Matthieu; Lee, Deokjung; Shin, Ho CheolARTICLE87
2021-02Criticality benchmark of Monte Carlo code MCS for light water reactor fuel in transportation and storage packagesLee, Hochul; Jang, Jaerim; Jang, Junkyung; Kang, Hyunwook; Kim, Wonkyeong; Lee, Deokjung; Lee, Hyun ChulARTICLE38
2020-12Deep learning-based procedure compliance check system for nuclear power plant emergency operationAhn, Jeeyea; Lee, Seung JunARTICLE110
2020-02Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactorKim, Wonkyeong; Hursin, Mathieu; Pautz, Andreas; Vincent, Lamirand; Pavel, Frajtag; Lee, DeokjungARTICLE257
2021-03Development of a multi-unit seismic conditional core damage probability model with uncertainty analysisHeo, Yunyeong; Lee, Seung JunARTICLE38
2020-06Development of mobile scanning system for effective in-situ spatial prediction of radioactive contamination at decommissioning sitesLee, Chanki; Park, Se-Won; Kim, Hee ReyoungARTICLE162
2021-02Effective energy management design of spent fuel dry storage based on hybrid controlrod-heatpipeKim, Kyung Mo; Bang, In CheolARTICLE46
2021-01Effects of plasma turbulence on the nonlinear evolution of magnetic island in tokamakChoi, Minjun J.; Bardoczi, Laszlo; Kwon, Jae-Min; Hahm, Taik Soo; Park, Hyeon Keo; Kim, Jayhyun; Woo, Minho; Park, Byung-Ho; Yun, Gunsu S.; Yoon, Eisung; McKee, GeorgeARTICLE22
2020-01Enhanced heat transfer and reduced pressure loss with U-pattern of helical wire spacer arrangement for liquid metal cooled-fast reactor fuel assemblyJeong, Yeong Shin; Kim, Ji Yong; Bang, In CheolARTICLE251
2020-01Exhaustive testing of safety-critical software for reactor protection systemLee, Sang Hun; Lee, Seung Jun; Shin, Sung Min; Lee, Eun-chan; Kang, Hyun GookARTICLE272
2020-08Extension of Monte Carlo code MCS to spent fuel cask shielding analysisMai, Nhan Nguyen Trong; Zhang, Peng; Lemaire, Matthieu; Ebiwonjumi, Bamidele; Kim, Wonkyeong; Lee, Hyunsuk; Lee, DeokjungARTICLE66
2021-02Fabrication and thermal conductivity of CeO2–Ce3Si2 compositeAhn, Jungsu; Kim, Gyeonghun; Jung, Yunsong; Ahn, SangjoonARTICLE89
Showing results 1 to 20 of 38

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