SNF Data Visualization on the Centralized Used Fuel Resource for Information Exchange (CURIE) Website... Conference Paper June, 2017
Analysis of New Measurements of Isotopic Compositions in Spent Fuel Samples from Calvert Cliffs Unit 1 Reactor using SCALE 6.2 Journal May, 2017
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: core design and safety analysis Journal May, 2017
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: motivation and overview... Journal May, 2017
Improving the Accuracy of the Chebyshev Rational Approximation Method (CRAM) by Using Substeps... Journal May, 2017
A Multigroup, Lumped Parameter MOC Method for Subgroup Self-Shielding in MPACT Conference Paper April, 2017
MC21/CTF and VERA-CS Mutiphysics Solutions to VERA Core Physics Benchmark Problems 6 and 7 Conference Paper April, 2017
Sensitivity Study of INDEPTH for Verification of Facility Spent Nuclear Fuel Declarations Conference Paper April, 2017
