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Publications by C. H. M. Broeders
Global Comparison of TALYS and ALICE Code Calculations and Evaluated Data From ENDF/B, JENDL, FENDL, and JEFF Files With Measured Neutron Induced Reaction Cross-Sections at Energies Above 0.1 MeV
Journal of Nuclear and Radiochemical Sciences
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Evaluated Neutron-Interaction and Gamma-Ray-Production Cross Sections of $Sup 9$Be for ENDF/B-IV. MAT No. 1289
Calculations of (N,2n) Reaction Cross Sections For74,76,78,80,82Se Up to 20 MeV
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COMPARISONS OF THE WESTINGHOUSE 1000-MWe LMFBR REFERENCE DESIGN CALCULATIONS USING THE WESTINGHOUSE 6602-M DATA AND THE MC$sup 2$ CODE WITH NEUTRON CROSS-SECTION DATA FROM THE ENDF/B FILE.
Measurements of Activation Cross Sections on Spallation Reactions for 59Co and natCu at Incident Neutron Energies of 40 to 120 MeV
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Measurement of the Am242m Neutron-Induced Reaction Cross Sections
Physical Review C
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Measurements of Activation Cross Sections on Spallation Reactions for 59Co and natCu at Incident Neutron Energies of 40 to 120 MeV.
Journal of Nuclear Science and Technology
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Uncertainty Analyses Applied to the UAM/TMI-1 Lattice Calculations Using the DRAGON (Version 4.05) Code and Based on JENDL-4 and ENDF/B-VII.1 Covariance Data
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Template for Estimating Uncertainties of Measured Neutron-Induced Fission Cross-Sections
EPJ Nuclear Sciences & Technologies
