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Development of a Graphical User Interface for In-Core Fuel Management Using MCODE
Free accessDSpace@MIT | 2009|Publisher: American Nuclear Society -
Opencg: A Combinatorial Geometry Modeling Tool for Data Processing and Code Verification
Free accessDSpace@MIT | 2015|Publisher: American Nuclear Society (ANS) -
Ray Effect Mitigation for the Discrete Ordinates Method Using Artificial Scattering
Free accessBASE | 2020|Publisher: American Nuclear Society, KITopen (Karlsruhe Institute of Technologie) -
Partial Cross-Section Calculations for PGNAA Based on a Deterministic Neutron Transport Solver
Free accessBASE | 2022|Publisher: American Nuclear Society, KITopen (Karlsruhe Institute of Technologie)
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