Comparison of Calculated and Measured Neutron Fluence in Fuel/Cladding Irradiation Experiments in HFIR... Conference Paper November, 2011
Evaluation of Damage Tolerance of Advanced SiC/SiC Composites after Neutron Irradiation Conference Paper November, 2011
C5 Benchmark Problem with Discrete Ordinate Radiation Transport Code DENOVO... Journal November, 2011
Investigation of Backscatter X-ray imaging techniques for Uranium Dioxide Fuel Rods... Journal October, 2011
Measurement of the U-236(n, f) cross section from 170 meV to 2 MeV at the CERN n_TOF facility... Journal October, 2011