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Showing results 12 to 31 of 96

Issue DateTitleAuthor(s)TypeView
2016-12Boron-free small modular pressurized water reactor design with new burnable absorberCheo, Jiwon; Zheng, Youqi; Lee, Deokjung; Shin, Ho CheolARTICLE473
2017-02Calculation of Degenerated Eigenmodes with Modified Power MethodZhang, Peng; Lee, Hyunsuk; Lee, DeokjungARTICLE521
2011-09Cell Homogenization Method for Pin-by-Pin Neutron Transport CalculationsKozlowski, Tomasz; Xu, Yunlin; Downar, Thomas J.; Lee, DeokjungARTICLE531
2014-03Coarse mesh finite difference formulation for accelerated Monte Carlo eigenvalue calculationLee, Min Jae; Joo, Han Gyu; Lee, Deokjung; Smith, KordARTICLE670
2018-05Comment on "Vanadium, rhodium, silver and cobalt self-powered neutron detector calculations by RAST-K v2.0" ReplyKhoshahval, Farrokh; Zhang, Peng; Lemaire, Matthieu; Lee, DeokjungARTICLE261
2019-02Comparative analysis of VERA depletion benchmark through consistent code-to-code comparisonPark, Jinsu; Khassenov, Azamat; Kim, Wonkyeong; Choi, Sooyoung; Lee, DeokjungARTICLE275
2015-06Comparative Neutronics Analysis of DIMPLE S06 Criticality Benchmark with Contemporary Reactor Core Analysis Computer Code SystemsKim, Wonkyeong; Park, Jinsu; Kozlowski, Tomasz; Lee, Hyun Chul; Lee, DeokjungARTICLE516
2017-03Comparisons of SN and Monte-Carlo methods in PWR ex-core detector response simulationZheng, Youqi; Lee, Deokjung; Zhang, Peng; Lee, Eunki; Shin, Ho-cheolARTICLE531
2012-09Convergence analysis of coarse mesh finite difference method applied to two-group three-dimensional neutron diffusion problemLee, DeokjungARTICLE539
2004-06Convergence analysis of the nonlinear coarse-mesh finite difference method for one-dimensional fixed-source neutron diffusion problemLee, Deokjung; Downar, TJ; Kim, YARTICLE570
2015-12Convergence analysis of two-node CMFD method for two-group neutron diffusion eigenvalue problemJeong, Yongjin; Park, Jinsu; Lee, Hyun Chul; Lee, DeokjungARTICLE756
2019-01Core design of long-cycle small modular lead-cooled fast reactorTung Dong Cao Nguyen; Choe, Jiwon; Ebiwonjumi, Bamidele; Lemaire, Matthieu; Lee, DeokjungARTICLE207
2019-11Coupled Neutronics-Thermal-Hydraulic Simulation of BEAVRS Cycle 1 Depletion by the MCS/CTF Code SystemYu, Jiankai; Lee, Hyunsuk; Kim, Hanjoo; Zhang, Peng; Lee, DeokjungARTICLE39
2019-03Coupling of FRAPCON for fuel performance analysis in the Monte Carlo code MCSYu, Jiankai; Lee, Hyunsuk; Kim, Hanjoo; Zhang, Peng; Lee, DeokjungARTICLE83
2019-01Depletion chain optimization of lattice code STREAM for LWR fuel assembly burnup analysisKhang Hoang Nhat Nguyen; Choi, Sooyoung; Lemaire, Matthieu; Lee, DeokjungARTICLE203
2018-08Design of High Density Spent Fuel Storage Rack Applying Burnup CreditLee, Deokjung; Jeong, SanggeolMaster's thesis224
2013-09Design of ultralong-cycle fast reactor employing breed-and-burn strategyTak, Taewoo; Lee, Deokjung; Kim, T. K.ARTICLE684
2017-01Design study of long-life small modular sodium-cooled fast reactorPark, Jinsu; Tak, Taewoo; Kim, T.K.; Choe. Jiwon; Jeong, Yongjin; Zhang, Peng; Lee, DeokjungARTICLE433
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, DeokjungARTICLE97
2019-02Development of a New Monte Carlo Code for High-Fidelity Power Reactor AnalysisLee, Deokjung; Lee, HyunsukDoctoral thesis149
Showing results 12 to 31 of 96