Works (47)
Updated: November 1st, 2024 06:50
2024 article
Advanced Liquid-Metal-Cooled Fast Reactor Core Design Using Modern Optimization Algorithms
Al-Dawood, K., & Palmtag, S. (2024, May 22). NUCLEAR SCIENCE AND ENGINEERING, Vol. 5.
author keywords: Liquid-metal-cooled fast reactor (LMFR); sodium-cooled fast reactor (SFR); optimization fuel cycle cost; transuranium (TRU) fuel
UN Sustainable Development Goal Categories
11. Sustainable Cities and Communities
(Web of Science)
Sources: ORCID, Web Of Science, NC State University Libraries
Added: June 1, 2024
2024 journal article
METAL: Methodology for liquid metal fast reactor core economic design and fuel loading pattern optimization
PROGRESS IN NUCLEAR ENERGY, 173.
Contributors: K. Al-Dawood n & n
author keywords: Liquid Metal Fast Reactor (LMFR); Sodium Fast Reactor (SFR); Optimization methodology; Fuel cycle cost; Low Enriched Uranium (LEU); TRansUranium (TRU) fuel
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy
(OpenAlex)
Sources: ORCID, Web Of Science, NC State University Libraries
Added: May 1, 2024
2023 journal article
A Design and Optimization Methodology for Liquid Metal Fast Reactors
INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2023.
Contributors: K. Al-Dawood n & n
Ed(s): A. Kuzmin
open access via downloads.hindawi.com (publisher PDF)
UN Sustainable Development Goal Categories
11. Sustainable Cities and Communities
(Web of Science)
Sources: ORCID, Web Of Science, NC State University Libraries
Added: March 9, 2023
2023 journal article
Fuel cycle cost comparison between lead and sodium cooled fast reactors
NUCLEAR ENGINEERING AND DESIGN, 414.
Contributors: K. Al-Dawood n & n
author keywords: Constrained nuclear design; Uranium nitride; Levelized Fuel Cycle Cost; Optimization; Sodium-cooled Fast Reactor (SFR); Lead-cooled Fast Reactor (LFR)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy
(OpenAlex)
Sources: ORCID, Web Of Science, NC State University Libraries
Added: September 19, 2023
2023 article
Solving the Neutron Transport Equation for Microreactor Modeling Using Unstructured Meshes and Exascale Computing Architectures
Dawn, W. C., & Palmtag, S. (2023, May 11). NUCLEAR SCIENCE AND ENGINEERING, Vol. 5.
author keywords: Neutron transport; unstructured mesh; finite element method; Exascale Computing Project; microreactor
UN Sustainable Development Goal Categories
11. Sustainable Cities and Communities
(Web of Science)
Sources: ORCID, Web Of Science, NC State University Libraries
Added: May 11, 2023
2022 journal article
CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pressurized water reactors
NUCLEAR ENGINEERING AND DESIGN, 397.
author keywords: Subchannel; LWR; CTF; VERA
UN Sustainable Development Goal Categories
13. Climate Action
(Web of Science)
Sources: Web Of Science, NC State University Libraries
Added: September 26, 2022
2022 conference paper
Control rod modeling in liquid metal-cooled fast reactors
Kiefer, T. M., Dawn, W. C., Al-Dawood, K., & Palmtag, S. (2022, July). https://www.osti.gov/biblio/23178744
Source: ORCID
Added: March 21, 2023
2022 conference paper
LMFR design and optimization methodology
Al-Dawood, K. A., & Palmtag, S. P. (2022, July). https://www.osti.gov/biblio/23178727
Source: ORCID
Added: March 21, 2023
2022 conference paper
VERA BWR Progression Problems
Lawing, C. ; Palmtag, S. ; & Asgari, M. (2022, May). https://www.osti.gov/biblio/1890346
Source: ORCID
Added: March 21, 2023
2021 journal article
A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORS
EPJ Web of Conferences, 247, 06019.
Ed(s): M. Margulis & P. Blaise
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy
(OpenAlex)
Source: ORCID
Added: May 1, 2021
2021 journal article
A multiphysics simulation suite for liquid metal-cooled fast reactors
ANNALS OF NUCLEAR ENERGY, 159.
author keywords: Sodium-cooled Fast Reactor (SFR); Simplified P-N (SPN); Finite Element Method (FEM); Thermal hydraulics; Thermal expansion; Multiphysics
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy
(OpenAlex)
11. Sustainable Cities and Communities
(Web of Science)
Sources: Web Of Science, NC State University Libraries, ORCID
Added: June 28, 2021
2021 report
Analysis of Approximations in Modeling of BWR Bundle Void Distributions
Source: ORCID
Added: March 21, 2023
2021 report
BWR Progression Problems
Source: ORCID
Added: March 21, 2023
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, pp. 265–275.
author keywords: quantum annealing; noisy intermediate-scale quantum computing; topology graph embeddings
TL;DR:
Applying the technique to the problem of determining an effective fuel loading pattern for nuclear reactors shows that densely mapped quantum stencils result in higher fidelity solutions of optimization problems then the sparser default solutions.
(via Semantic Scholar)
Sources: Web Of Science, NC State University Libraries
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
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation
(OpenAlex)
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
In Idaho National Laboratory.
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.
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy
(OpenAlex)
Source: ORCID
Added: May 1, 2021
2020 journal article
Secondary-Source Core Reload Modeling with VERA
NUCLEAR SCIENCE AND ENGINEERING, 195(3), 320–337.
author keywords: CASL; VERA; secondary source; source range; detector response
TL;DR:
New capabilities in the CASL reactor simulation package VERA have been adapted to provide high-fidelity simulation capabilities for modeling source range detector response during subcritical reactor configurations and were found to demonstrate excellent agreement with the measured data.
(via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy
(OpenAlex)
11. Sustainable Cities and Communities
(Web of Science)
Sources: Web Of Science, NC State University Libraries
Added: December 11, 2020
2020 journal article
Simulation of the BEAVRS benchmark using VERA
ANNALS OF NUCLEAR ENERGY, 145.
author keywords: CASL; VERA; BEAVRS benchmark
UN Sustainable Development Goal Categories
11. Sustainable Cities and Communities
(Web of Science)
Sources: Web Of Science, NC State University Libraries
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.
author keywords: VERA; MPACT; Cross section library; Benchmark; Verification
TL;DR:
The code-to-code comparison for the benchmarks shows that the CASL neutronics simulator MPACT and its 51-group library are working reasonably, and the cross section library generation procedure,cross section library, and MPACT transport capability have been verified.
(via Semantic Scholar)
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation
(OpenAlex)
11. Sustainable Cities and Communities
(Web of Science)
Sources: Web Of Science, ORCID, NC State University Libraries
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.
author keywords: VERA; MPACT; CASL
Source: ORCID
Added: August 18, 2020
2016 report
Assessment of Thermal Hydraulic Feedback Models
https://www.osti.gov/scitech/biblio/1325432-assessment-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
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy
(OpenAlex)
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
https://www.osti.gov/scitech/biblio/1325433-simulation-crud-induced-power-shift-using-vera-core-simulator-mamba
Source: ORCID
Added: August 18, 2020
2016 report
VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12
https://www.osti.gov/scitech/biblio/1260079-vera-benchmarking-results-watts-bar-nuclear-plant-unit-cycles
Source: ORCID
Added: August 18, 2020
2015 report
Development of COBRA-TF for Modeling Full-Core Reactor Operating Cycles
https://www.osti.gov/scitech/biblio/1185922-development-cobra-tf-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
https://www.osti.gov/scitech/biblio/1215576-vera-core-simulator-methodology-pwr-cycle-depletion
Source: ORCID
Added: August 18, 2020
2015 report
Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS
https://www.osti.gov/scitech/biblio/1214019-validation-application-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).
author keywords: Couple-code; Multiphysics; Reactor core simulations
Source: ORCID
Added: August 18, 2020
2014 report
Coupled Neutronics Thermal-Hydraulic Solution of a Full-Core PWR Using VERA-CS
https://www.osti.gov/scitech/biblio/1154814-coupled-neutronics-thermal-hydraulic-solution-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. http://www.scopus.com/inward/record.url?eid=2-s2.0-84883365179&partnerID=MN8TOARS
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. http://www.scopus.com/inward/record.url?eid=2-s2.0-79952378953&partnerID=MN8TOARS
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. http://www.scopus.com/inward/record.url?eid=2-s2.0-79953837410&partnerID=MN8TOARS
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. http://www.scopus.com/inward/record.url?eid=2-s2.0-55349115707&partnerID=MN8TOARS
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. http://www.scopus.com/inward/record.url?eid=2-s2.0-33244479401&partnerID=MN8TOARS
Source: ORCID
Added: August 18, 2020
2005 conference paper
Microscopic depletion model in SIMULATE-4
Transactions of the American Nuclear Society, 92, 635–636. http://www.scopus.com/inward/record.url?eid=2-s2.0-33244493781&partnerID=MN8TOARS
Source: ORCID
Added: August 18, 2020
1995 report
A two-dimensional, semi-analytic expansion method for nodal calculations
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation
(OpenAlex)
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
https://www.osti.gov/scitech/biblio/204716-measurements-actinide-transmutation-hard-spectrum-fast-reactor
Source: ORCID
Added: August 18, 2020
Employment
Updated: June 10th, 2020 09:23
North Carolina State University Raleigh, NC, US
Research Professor
Nuclear Engineer
Education
Updated: July 20th, 2014 14:47
1994 - 1997
Massachusetts Institute of Technology Cambridge, MA, US
Ph.D.
Nuclear Engineering
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