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Showing results 1 to 20 of 24

Issue DateTitleAuthor(s)TypeView
2017-08-24Boron-free SMPWR Analysis with MCS and STREAM codesJang, Jaerim; Choe, Jiwon; Choi, Sooyoung; Lee, Hyunsuk; Ebiwonjumi, Bamidele; Shin, Ho Cheol; Lee, DeokjungCONFERENCE46
2018-04-22Conceptual Core Design of a Small Modular Fast Reactor Cooled by Lead-Bismuth EutecticNguyen, Dong Cao Tung; Choe, Jiwon; Ebiwonjumi, Bamidele; Lemaire, Matthieu; Lee, DeokjungCONFERENCE39
2019-01Core design of long-cycle small modular lead-cooled fast reactorTung Dong Cao Nguyen; Choe, Jiwon; Ebiwonjumi, Bamidele; Lemaire, Matthieu; Lee, DeokjungARTICLE323
2019-10-24Development of AutoCASK Code System for PWR Spent Nuclear Fuel Cask Analysis at UNISTKim, Wonkyeong; Jang, Jaerim; Ebiwonjumi, Bamidele; Lee, Hyunsuk; Lemaire, Matthieu; Zhang, Peng; Kang, Seung-gu; Lee, DeokjungCONFERENCE46
2018-04-22Development of Photon-Transport Capability in UNIST Monte Carlo Code MCSLemaire, Matthieu; Lee, Hyunsuk; Ebiwonjumi, Bamidele; Kong, Chidong; Kim, Wonkyeong; Jo, Yunki; Park, Jinsu; Lee, DeokjungCONFERENCE49
2017-08-24Experimental Validation of STREAM for Spent Nuclear Fuel ApplicationsEbiwonjumi, Bamidele; Choi, Sooyoung; Lemaire, Matthieu; Lee, Deokjung; Shin, Ho CheolCONFERENCE38
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, DeokjungARTICLE75
2019-12-03Functional Expansion Tallies in Monte Carlo High Fidelity LWR AnalysisEbiwonjumi, Bamidele; Lee, Hyunsuk; Zhang, Peng; Lee, DeokjungCONFERENCE96
2017-08-24Implementation of On-The-Fly Energy Release per Fission Model in STREAMLee, Woonghee; Choi, Sooyoung; Ebiwonjumi, Bamidele; Lemaire, Matthieu; Lee, DeokjungCONFERENCE46
2017-08-24Introduction to UNIST Spent Nuclear Fuel Transportation Package Analysis Code SystemKong, Chidong; Lee, Hyunsuk; Lemaire, Matthieu; Kim, Wonkyeong; Jo, Yunki; Park, Jinsu; Choe, Jiwon; Ebiwonjumi, Bamidele; Lee, DeokjungCONFERENCE44
2018-04-22MCS Analysis of IAEA Lead-Cooled Fast Reactor Core Neutronics BenchmarkEbiwonjumi, Bamidele; Nguyen, Dong Cao Tung; Choe, Jiwon; Lemaire, Matthieu; Lee, DeokjungCONFERENCE46
2018-10-25MCS Analysis of Westinghouse 3-loop PWR Multi-cycle OperationEbiwonjumi, Bamidele; Lee, Hyunsuk; Choe, Jiwon; Lee, Deokjung; Shin, Ho CheolCONFERENCE49
2019-05-13MCS/FRAPCON Multi-physics Coupled Simulation of Westinghouse 3-loop PWR Wholecore AnalysisEbiwonjumi, Bamidele; Lee, Hyunsuk; Zhang, Peng; Cherezov, Alexey; Lee, Deokjung; Shin, Ho Cheol; Lee, Hwan SooCONFERENCE57
2018-09-30Monte Carlo Code MCS Multi-cycle Depletion Analysis of Westinghouse 3-loop PWREbiwonjumi, Bamidele; Lee, Hyunsuk; Choe, Jiwon; Lemaire, Matthieu; Lee, DeokjungCONFERENCE59
2019-05-24Recent Development Status of Neutron Transport Code STREAMChoi, Sooyoung; Choe, Jiwon; Nguyen, Khang Hoang Nhat; Lee, Woonghee; Kim, Wonkyeong; Kim, Hanjoo; Ebiwonjumi, Bamidele; Jeong, Eun; Lee, Hyunsuk; Kim, Kyeongwon; Kim, Kiho; Lee, DeokjungCONFERENCE55
2017-08-24Recent Work on Photon Transport with UNIST Monte Carlo Code MCSLemaire, Matthieu; Lee, Hyunsuk; Ebiwonjumi, Bamidele; Kong, Chidong; Kim, Wonkyeong; Jo, Yunki; Park, Jinsu; Lee, DeokjungCONFERENCE40
2021-03Uncertainty quanti fi cation of PWR spent fuel due to nuclear data and modeling parametersEbiwonjumi, Bamidele; Kong, Chidong; Zhang, Peng; Cherezov, Alexey; Lee, DeokjungARTICLE22
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 CheolARTICLE266
2020-09Validation of nuclide depletion capabilities in Monte Carlo code MCSEbiwonjumi, Bamidele; Lee, Hyunsuk; Kim, Wonkyeong; Lee, DeokjungARTICLE241
2019-08-26Validation of Nuclide Depletion Capabilities in Monte Carlo Code MCS using Spent Fuel Isotopic MeasurementsEbiwonjumi, Bamidele; Lee, Hyunsuk; Kim, Wonkyeong; Choi, Sooyoung; Lee, DeokjungCONFERENCE57
Showing results 1 to 20 of 24

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