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Showing results 1 to 20 of 24

Issue DateTitleAuthor(s)TypeView
2015-05A Hybrid Monte Carlo/Method-of-Characteristics Method for Efficient Neutron Transport AnalysisLee, Hyunsuk; Choi, Sooyoung; Lee, DeokjungARTICLE610
2017-12A new approach to three-dimensional neutron transport solution based on the method of characteristics and linear axial approximationZheng, Youqi; Choi, Sooyoung; Lee, DeokjungARTICLE412
2015-05A New Equivalence theory Method for Treating Doubly Heterogeneous Fuel ? I: TheoryLee, Deokjung; Williams, Mark L.; Choi, SooyoungARTICLE730
2015-05A New Equivalence theory Method for Treating Doubly Heterogeneous Fuel? II: VerificationsLee, Deokjung; Choi, Sooyoung; Williams, Mark L.; Kong, ChidongARTICLE703
2019-12Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysisDu, Xianan; Choe, Jiwon; Choi, Sooyoung; Lee, Woonghee; Cherezov, Alexey; Lim, Jaeyong; Lee, Minjae; Lee, DeokjungARTICLE89
2019-02Comparative analysis of VERA depletion benchmark through consistent code-to-code comparisonPark, Jinsu; Khassenov, Azamat; Kim, Wonkyeong; Choi, Sooyoung; Lee, DeokjungARTICLE329
2020-04Conceptual 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 CheolARTICLE14
2019-01Depletion chain optimization of lattice code STREAM for LWR fuel assembly burnup analysisKhang Hoang Nhat Nguyen; Choi, Sooyoung; Lemaire, Matthieu; Lee, DeokjungARTICLE238
2017-01Extension of double heterogeneity treatment method for coated TRISO fuel particlesKim, Hanjoo; Choi, Sooyoung; Park, Minyong; Lee, Deokjung; Lee, Hyun ChulARTICLE426
2015-10Impact of inflow transport approximation on light water reactor analysisChoi, Sooyoung; Smith, Kord; Lee, Hyun Chul; Lee, DeokjungARTICLE535
2020-05MCS/TH1D analysis of VERA whole-core multi-cycle depletion problemsNguyen, Tung Dong Cao.; Lee, Hyunsuk; Choi, Sooyoung; Lee, DeokjungARTICLE68
2015-05New calculational model for self-powered neutron detector based on Monte Carlo simulationLee, Hyunsuk; Choi, Sooyoung; Cha, Kyoon-Ho; Lee, Kwangho; Lee, DeokjungARTICLE739
2017-03On the diffusion coefficient calculation in two-step light water reactor core analysisChoi, Sooyoung; Smith, Kord S.; Kim, Hanjoo; Tak, Taewoo; Lee, DeokjungARTICLE321
2019-02Performance evaluation of CMFD on inter-cycle correlation reduction of Monte Carlo simulationPark, Jinsu; Zhang, Peng; Lee, Hyunsuk; Choi, Sooyoung; Yu, Jiankai; Lee, DeokjungARTICLE224
2017-02Pin-based Pointwise Energy Slowing-down Method for Resonance Self-shielding CalculationLee, Deokjung; Choi, SooyoungDoctoral thesis622
2016-08Resonance Self-shielding Method Using Resonance Interference Factor Library for Practical Lattice Physics Computations of LWRsChoi, Sooyoung; Khassenov, Azamat; Lee, DeokjungARTICLE509
2015-09Resonance self-shielding methodology of new neutron transport code STREAMChoi, Sooyoung; Lee, Hyunsuk; Hong, Ser Gi; Lee, DeokjungARTICLE513
2017-02Resonance treatment using pin-based pointwise energy slowing-down methodChoi, Sooyoung; Lee, Changho; Lee, DeokjungARTICLE730
2018-10Validation of lattice physics code STREAM for predicting pressurized water reactor spent nuclear fuel isotopic inventoryEbiwonjumi, Bamidele; Choi, Sooyoung; Lemaire, Matthieu; Lee, Deokjung; Shin, Ho CheolARTICLE182
2019-03Validation of the MCNP6 code for SFR shielding design analysisTuan Quoc Tran; Jeong, Sanggeol; Khang Nhat Hoang Nguyen; Lee, Hyunsuk; Choi, Sooyoung; Zhang, Peng; Lee, Min Jae; Lim, Jae-Yong; Lee, DeokjungARTICLE253
Showing results 1 to 20 of 24

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