Verification of a two-step code system MCS/RAST-F to fast reactor core analysis von Tran, Tuan Quoc, Cherezov, Alexey, Du, Xianan, Lee, Deokjung

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Acceleration of Nuclear Reactor Simulation and Uncertainty Quantification Using Low-Precision Arithmetic von Cherezov, Alexey, Vasiliev, Alexander, Ferroukhi, Hakim

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Machine learning of LWR spent nuclear fuel assembly decay heat measurements von Ebiwonjumi, Bamidele, Cherezov, Alexey, Dzianisau, Siarhei, Lee, Deokjung

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A Multi-Physics Adaptive Time Step Coupling Algorithm for Light-Water Reactor Core Transient and Accident Simulation von Cherezov, Alexey, Park, Jinsu, Kim, Hanjoo, Choe, Jiwon, Lee, Deokjung

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RAST-K v2—Three-Dimensional Nodal Diffusion Code for Pressurized Water Reactor Core Analysis von Park, Jinsu, Jang, Jaerim, Kim, Hanjoo, Choe, Jiwon, Yun, Dongmin, Zhang, Peng, Cherezov, Alexey, Lee, Deokjung

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Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K von Jang, Jaerim, Kong, Chidong, Ebiwonjumi, Bamidele, Cherezov, Alexey, Jo, Yunki, Lee, Deokjung

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Verification and validation of isotope inventory prediction for back-end cycle management using two-step method von Jang, Jaerim, Ebiwonjumi, Bamidele, Kim, Wonkyeong, Cherezov, Alexey, Park, Jinsu, Lee, Deokjung

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Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis von Du, Xianan, Choe, Jiwon, Choi, Sooyoung, Lee, Woonghee, Cherezov, Alexey, Lim, Jaeyong, Lee, Minjae, Lee, Deokjung

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Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters von Ebiwonjumi, Bamidele, Kong, Chidong, Zhang, Peng, Cherezov, Alexey, Lee, Deokjung

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DEVELOPMENT OF DECAY HEAT MODEL FOR RAST-K von Dzianisau, Siarhei, Park, Jinsu, Choi, Sooyoung, Cherezov, Alexey, Du, Xianan, Lee, Deokjung

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Towards high-fidelity high-resolution modeling of a BWR fuel assembly by CASMO-5 von Cherezov, Alexey, Vasiliev, Alexander, Ferroukhi, Hakim

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Application of Backward Differential Formula and Anderson’s method for multigroup diffusion transient equation von Cherezov, Alexey, Vasiliev, Alexander, Ferroukhi, Hakim

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Low precision preconditioning for solving neutron diffusion eigenvalue problem by finite element method von Cherezov, Alexey, Vasiliev, Alexander, Ferroukhi, Hakim

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Finding limiting rods for dry storage analyses von Konarski, Piotr, Cherezov, Alexey, Cozzo, Cedric, Khvostov, Grigori, Ferroukhi, Hakim

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A PCA compression method for reactor core transient multiphysics simulation von Cherezov, Alexey, Jang, Jaerim, Lee, Deokjung

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A reduced-basis element method for pin-by-pin reactor core calculations in diffusion and SP3 approximations von Cherezov, Alexey, Sanchez, Richard, Joo, Han Gyu

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A reduced-basis element method for pin-by-pin reactor core calculations in diffusion and SP 3 approximations von Cherezov, Alexey, Sanchez, Richard, Joo, Han Gyu

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Uncertainty quantifi cation in decay heat calculation of spent nuclear fuel by STREAM/RAST-K von 장재림, 공치동, Bamidele Ebiwonjumi, Alexey Cherezov(UNIST, 조윤기, 이덕중

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Verification and validation of isotope inventory prediction for back-end cycle management using twostep method von 장재림, Bamidele Ebiwonjumi, 김원경, Alexey Cherezov, 박진수, 이덕중

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Verification of a two-step code system MCS/RAST-F to fast reactor core analysis von Tran, Tuan Quoc, Cherezov, Alexey, Du, Xianan, Lee, Deokjung

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