2020 report
Comparison of Generation of Higher-Order Neutron Scattering Cross Sections
2020 article
Secondary-Source Core Reload Modeling with VERA
NUCLEAR SCIENCE AND ENGINEERING.
2020 journal article
Simulation of the BEAVRS benchmark using VERA
ANNALS OF NUCLEAR ENERGY, 145.
2019 journal article
Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification
ANNALS OF NUCLEAR ENERGY, 132, 1–23.
2017 report
Development of the V4.2m5 and V5.0m0 Multigroup Cross Section Libraries for MPACT for PWR and BWR
2017 report
VERA Core Simulator methodology for pressurized water reactor cycle depletion
In Nuclear Science and Engineering.
2016 report
Assessment of Thermal Hydraulic Feedback Models
2016 report
CTF Validation and Verification Manual
2016 report
Demonstrate VERA Core Simulator Performance Improvements L2:PHI.P13.03
2016 report
MPACT Standard Input User s Manual, Version 2.2.0
2016 report
MPACT Theory Manual, Version 2.2.0
2016 report
MPACT VERA Input User s Manual, Version 2.2.0
2016 report
Simulation of CRUD Induced Power Shift using the VERA Core Simulator and MAMBA
2016 report
VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12
2015 report
Development of COBRA-TF for Modeling Full-Core Reactor Operating Cycles
2015 report
L3.PHI.CTF.P10.02-rev2 Coupling of Subchannel T/H (CTF) and CRUD Chemistry (MAMBA1D)
2015 report
VERA Core Simulator Methodology for PWR Cycle Depletion
2015 report
Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS
2014 report
An approach for coupled-code multiphysics core simulations from a common input
In Annals of Nuclear Energy (Oxford).
2014 report
Coupled Neutronics Thermal-Hydraulic Solution of a Full-Core PWR Using VERA-CS
2013 conference paper
Improvements, enhancements, and optimizations of COBRA-TF
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013, 3, 2170–2181.
2010 conference paper
Validation of the lattice physics code LANCER02 with ENDF/B-VII library
International Conference on the Physics of Reactors 2010, PHYSOR 2010, 2, 1130–1139.
2008 conference paper
The advanced BWR core simulator AETNA02
International Conference on the Physics of Reactors 2008, PHYSOR 08, 2, 1282–1289.
2007 conference paper
Steady-state nuclear analysis methods at global nuclear fuel, invited
Transactions of the American Nuclear Society, 97, 557–558.
2005 conference paper
CASMO-4 and multigroup MCNP comparisons for MOX fuel assemblies
Transactions of the American Nuclear Society, 92, 508–509.
2005 conference paper
Microscopic depletion model in SIMULATE-4
Transactions of the American Nuclear Society, 92, 635–636.
1995 report
A two-dimensional, semi-analytic expansion method for nodal calculations
1994 report
MCNP: Multigroup/adjoint capabilities
(Vol. 4).
1994 report
Measurements of actinide transmutation in the hard spectrum of a fast reactor
1994 - 1997