Works (36)
2021 journal article
A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORS
EPJ Web of Conferences, 247, 06019.
Ed(s): M. Margulis & P. Blaise
www.epj-conferences.org (publisher PDF)
Source: ORCID
Added: May 1, 2021
2021 journal article
A multiphysics simulation suite for liquid metal-cooled fast reactors
ANNALS OF NUCLEAR ENERGY, 9.
Sources: Web Of Science, ORCID
Added: June 28, 2021
2021 journal article
QUANTIFICATION OF NUCLEAR DATA AND MANUFACTURING UNCERTAINTIES IN VERA
EPJ Web of Conferences, 247, 15014.
Ed(s): M. Margulis & P. Blaise
Source: ORCID
Added: May 1, 2021
2021 article
Quantum Annealing Stencils with Applications to Fuel Loading of a Nuclear Reactor
2021 IEEE INTERNATIONAL CONFERENCE ON QUANTUM COMPUTING AND ENGINEERING (QCE 2021) / QUANTUM WEEK 2021.
Sources: Web Of Science, ORCID
Added: February 7, 2022
2021 journal article
VERA-CS VALIDATION OF CRITICAL EXPERIMENTS
EPJ Web of Conferences, 247, 10014.
Ed(s): M. Margulis & P. Blaise
Source: ORCID
Added: May 1, 2021
2020 report
CTF Validation and Verification
Source: ORCID
Added: May 1, 2021
2020 report
Comparison of Generation of Higher-Order Neutron Scattering Cross Sections
Source: ORCID
Added: August 18, 2020
2020 article
Design of an Economical Low-Power Fast Spectrum Molten Chloride Reactor
Transactions of the American Nuclear Society - Volume 123.
Source: ORCID
Added: May 1, 2021
2020 article
Secondary-Source Core Reload Modeling with VERA
NUCLEAR SCIENCE AND ENGINEERING.
Sources: Web Of Science, ORCID
Added: December 11, 2020
2020 journal article
Simulation of the BEAVRS benchmark using VERA
ANNALS OF NUCLEAR ENERGY, 145.
Sources: Web Of Science, ORCID
Added: July 13, 2020
2019 journal article
Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification
ANNALS OF NUCLEAR ENERGY, 132, 1–23.
Sources: Web Of Science, ORCID
Added: September 9, 2019
2017 report
Development of the V4.2m5 and V5.0m0 Multigroup Cross Section Libraries for MPACT for PWR and BWR
Source: ORCID
Added: August 18, 2020
2017 report
VERA Core Simulator methodology for pressurized water reactor cycle depletion
In Nuclear Science and Engineering.
Source: ORCID
Added: August 18, 2020
2016 report
Assessment of Thermal Hydraulic Feedback Models
Source: ORCID
Added: August 18, 2020
2016 report
CTF Validation and Verification Manual
Source: ORCID
Added: August 18, 2020
2016 report
Demonstrate VERA Core Simulator Performance Improvements L2:PHI.P13.03
Source: ORCID
Added: August 18, 2020
2016 report
MPACT Standard Input User s Manual, Version 2.2.0
Source: ORCID
Added: August 18, 2020
2016 report
MPACT Theory Manual, Version 2.2.0
Source: ORCID
Added: August 18, 2020
2016 report
MPACT VERA Input User s Manual, Version 2.2.0
Source: ORCID
Added: August 18, 2020
2016 report
Simulation of CRUD Induced Power Shift using the VERA Core Simulator and MAMBA
Source: ORCID
Added: August 18, 2020
2016 report
VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12
Source: ORCID
Added: August 18, 2020
2015 report
Development of COBRA-TF for Modeling Full-Core Reactor Operating Cycles
Source: ORCID
Added: August 18, 2020
2015 report
L3.PHI.CTF.P10.02-rev2 Coupling of Subchannel T/H (CTF) and CRUD Chemistry (MAMBA1D)
Source: ORCID
Added: August 18, 2020
2015 report
VERA Core Simulator Methodology for PWR Cycle Depletion
Source: ORCID
Added: August 18, 2020
2015 report
Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS
Source: ORCID
Added: August 18, 2020
2014 report
An approach for coupled-code multiphysics core simulations from a common input
In Annals of Nuclear Energy (Oxford).
Source: ORCID
Added: August 18, 2020
2014 report
Coupled Neutronics Thermal-Hydraulic Solution of a Full-Core PWR Using VERA-CS
Source: ORCID
Added: August 18, 2020
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.
Source: ORCID
Added: August 18, 2020
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.
Source: ORCID
Added: August 18, 2020
2008 conference paper
The advanced BWR core simulator AETNA02
International Conference on the Physics of Reactors 2008, PHYSOR 08, 2, 1282–1289.
Source: ORCID
Added: August 18, 2020
2007 conference paper
Steady-state nuclear analysis methods at global nuclear fuel, invited
Transactions of the American Nuclear Society, 97, 557–558.
Source: ORCID
Added: August 18, 2020
2005 conference paper
CASMO-4 and multigroup MCNP comparisons for MOX fuel assemblies
Transactions of the American Nuclear Society, 92, 508–509.
Source: ORCID
Added: August 18, 2020
2005 conference paper
Microscopic depletion model in SIMULATE-4
Transactions of the American Nuclear Society, 92, 635–636.
Source: ORCID
Added: August 18, 2020
1995 report
A two-dimensional, semi-analytic expansion method for nodal calculations
Source: ORCID
Added: August 18, 2020
1994 report
MCNP: Multigroup/adjoint capabilities
(Vol. 4).
Source: ORCID
Added: August 18, 2020
1994 report
Measurements of actinide transmutation in the hard spectrum of a fast reactor
Source: ORCID
Added: August 18, 2020
Employment
North Carolina State University Raleigh, NC, US
Research Professor
Nuclear Engineer
Education
1994 - 1997
Massachusetts Institute of Technology Cambridge, MA, US
Ph.D.
Nuclear Engineering
