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Showing results 1 to 6 of 6

Issue DateTitleAuthor(s)TypeView
2019-05-13Application of Monte Carlo Neutronics and Fuel Performance Coupled Codes to Whole-core Depletion of OPR-1000Tran, Tuan Quoc; Lee, Hyunsuk; Choe, Jiwon; Cherezov, Alexey; Yu, Jiankai; Shin, Ho Cheol; Lee, DeokjungCONFERENCE32
2019-10-07Development of Hexagonal-Z Geometry Capability in RAST-K for Fast Reactor AnalysisTran, Tuan Quoc; Cherezov, Alexey; Du, Xianan; Park, Jinsu; Lee, DeokjungCONFERENCE14
2019-12-03MCS Multi-group Cross Sections Generation for Fast Reactor AnalysisNguyen, Tung Dong Cao; Lee, Hyunsuk; Du, Xianan; Dos, Vutheam; Tran, Tuan Quoc; Lee, DeokjungCONFERENCE25
2020-02Neutronic simulation of China Experimental Fast Reactor start-up tests. Part I: SARAX code deterministic calculationDu, Xianan; Choe, Jiwon; Tran, Tuan Quoc; Lee, DeokjungARTICLE185
2019-08-26Preliminary CEFR analysis by Monte Carlo codesTran, Tuan Quoc; Choe, Jiwon; Du, Xianan; Cherezov, Alexey; Lee, Hyunsuk; Lee, DeokjungCONFERENCE22
2019-05-24Recent Progress on Fast Reactor Analysis in UNIST CORE LaboratoryDu, Xianan; Choe, Jiwon; Choi, Sooyoung; Cherezov, Alexey; Lee, Woonghee; Tran, Tuan Quoc; Park, Jinsu; Lee, DeokjungCONFERENCE10
Showing results 1 to 6 of 6