Validation of the MC2-3/TWODANT/DIF3D code system for control rod worth via BFS-75-1 and BFS-109-2A reactor physics experiments
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[1] Philip R. Page,et al. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology , 2006 .
[2] Won Sik Yang,et al. MC2-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis , 2013 .
[3] Jae-Yong Lim,et al. Validation of the axial expansion reactivity worth for a metal-fueled Sodium-cooled Fast Reactor via a physical experiment , 2017 .
[4] Yeong-Il Kim,et al. Performance of Up-to-Date Evaluated Nuclear Data Files on Predicted Integral Parameters of Metal Fueled Fast Critical Assemblies , 2011 .
[5] H. Shim,et al. Adjoint Sensitivity and Uncertainty Analyses in Monte Carlo Forward Calculations , 2011 .
[6] A. Koning,et al. Uncertainties for the Kalimer Sodium Fast Reactor: Void Reactivity Coefficient, k eff, βeff, Depletion and Radiotoxicity , 2011 .
[7] Dohee Hahn,et al. CONCEPTUAL DESIGN OF THE SODIUM-COOLED FAST REACTOR KALIMER-600 , 2007 .
[8] E. Lewis,et al. DIF3D-VARIANT 11.0: A Decade of Updates , 2014 .