Works (46)

Updated: May 2nd, 2024 05:02

2024 journal article

METAL: Methodology for liquid metal fast reactor core economic design and fuel loading pattern optimization

Progress in Nuclear Energy, 173.

By: K. Al-Dawood n & S. Palmtag n

Contributors: K. Al-Dawood n & S. Palmtag n

Source: ORCID
Added: May 1, 2024

2023 journal article

A Design and Optimization Methodology for Liquid Metal Fast Reactors

INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2023.

By: K. Al-Dawood n & S. Palmtag n

Contributors: K. Al-Dawood n & S. Palmtag n

Ed(s): A. Kuzmin

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.

By: K. Al-Dawood n & S. Palmtag n

Contributors: K. Al-Dawood n & S. Palmtag 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.

By: W. Dawn n & S. Palmtag n

author keywords: Neutron transport; unstructured mesh; finite element method; Exascale Computing Project; microreactor
UN Sustainable Development Goal Categories
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.

By: R. Salko*, A. Wysocki*, T. Blyth*, A. Toptan*, J. Hu*, V. Kumar*, C. Dances*, W. Dawn n ...

author keywords: Subchannel; LWR; CTF; VERA
UN Sustainable Development Goal Categories
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

By: T. Kiefer, W. Dawn, K. Al-Dawood & S. Palmtag

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

By: K. Al-Dawood & S. Palmtag

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

By: C. Lawing, S. Palmtag & M. Asgari

Source: ORCID
Added: March 21, 2023

2021 journal article

A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORS

EPJ Web of Conferences, 247, 06019.

By: W. Dawn n & S. Palmtag n

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.

By: W. Dawn n & S. Palmtag n

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)
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

By: C. Lawing n, S. Palmtag* & D. Kropaczek n

Source: ORCID
Added: March 21, 2023

2021 report

BWR Progression Problems

By: C. Lawing n, S. Palmtag n & M. Asgari*

Source: ORCID
Added: March 21, 2023

2021 journal article

QUANTIFICATION OF NUCLEAR DATA AND MANUFACTURING UNCERTAINTIES IN VERA

EPJ Web of Conferences, 247, 15014.

By: C. Sedota n & S. Palmtag n

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.

By: J. Fustero n, S. Palmtag n & F. Mueller n

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

Secondary-Source Core Reload Modeling with VERA

NUCLEAR SCIENCE AND ENGINEERING, 195(3), 320–337.

By: C. Gentry*, B. Collins*, E. Davidson*, G. Davidson*, T. Evans*, A. Godfrey*, S. Hart*, G. Ilas* ...

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)
Sources: Web Of Science, NC State University Libraries
Added: December 11, 2020

2021 journal article

VERA-CS VALIDATION OF CRITICAL EXPERIMENTS

EPJ Web of Conferences, 247, 10014.

By: V. Novellino n & S. Palmtag n

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

By: R. Salko, A. Wysocki, A. Toptan n, N. Porter n, X. Zhao, T. Blyth*, J. Magedanz*, C. Dances* ...

Source: ORCID
Added: May 1, 2021

2020 report

Comparison of Generation of Higher-Order Neutron Scattering Cross Sections

In Idaho National Laboratory.

By: W. Dawn n, J. Ortensi*, M. DeHart* & S. Palmtag n

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.

By: L. Verrico, S. Palmtag*, T. Thompson, V. Novellino & C. Goodman

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: May 1, 2021

2020 journal article

Simulation of the BEAVRS benchmark using VERA

ANNALS OF NUCLEAR ENERGY, 145.

By: B. Collins, A. Godfrey, S. Stimpson* & S. Palmtag*

author keywords: CASL; VERA; BEAVRS benchmark
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.

By: K. Kim*, C. Gentry*, A. Godfrey*, Y. Liu* & S. Palmtag n

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)
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.

By: B. Kochunas*, B. Collins*, S. Stimpson*, R. Salko*, D. Jabaay*, A. Graham*, Y. Liu*, K. Kim* ...

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

By: A. Graham, T. Downar & S. Palmtag

Source: ORCID
Added: August 18, 2020

2016 report

CTF Validation and Verification Manual

By: R. Salko*, T. Blyth*, C. Dances*, J. Magedanz*, C. Jernigan*, J. Kelly*, A. Toptan n, M. Gergar* ...

Source: ORCID
Added: August 18, 2020

2016 report

Demonstrate VERA Core Simulator Performance Improvements L2:PHI.P13.03

By: B. Collins*, S. Hamilton*, M. Jarrett*, K. Kim*, B. Kochunas*, Y. Liu*, S. Palmtag*, R. Salko* ...

Source: ORCID
Added: August 18, 2020

2016 report

MPACT Standard Input User s Manual, Version 2.2.0

By: B. Collins*, T. Downar*, A. Fitzgerald*, J. Gehin*, A. Godfrey*, A. Graham*, D. Jabaay*, B. Kelley* ...

Source: ORCID
Added: August 18, 2020

2016 report

MPACT Theory Manual, Version 2.2.0

By: T. Downar*, B. Collins*, J. Gehin*, A. Godfrey*, D. Jabaay*, B. Kelley*, K. Clarno*, K. Kim* ...

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

By: B. Collins*, T. Downar*, A. Fitzgerald*, J. Gehin*, A. Godfrey*, A. Graham*, D. Jabaay*, B. Kelley* ...

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

By: K. Clarno, S. Palmtag, J. Secker, B. Kendrick & R. Montgomery

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

By: A. Godfrey, B. Collins, K. Kim, R. Montgomery, J. Powers, R. Salko, S. Stimpson, W. Wieselquist ...

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

By: R. Salko, T. Lange, V. Kucukboyaci, Y. Sung, S. Palmtag, J. Gehin, M. Avramova

Source: ORCID
Added: August 18, 2020

2015 report

L3.PHI.CTF.P10.02-rev2 Coupling of Subchannel T/H (CTF) and CRUD Chemistry (MAMBA1D)

By: R. Salko*, S. Palmtag*, B. Collins*, B. Kendrick* & J. Seker*

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

By: B. Kochunas, B. Collins, D. Jabaay, K. Kim, A. Graham, S. Stimpson, W. Wieselquist, K. Clarno ...

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

By: B. Kouchunas, D. Jabaay, T. Downar, B. Collins, S. Stimpson, A. Godfrey, K. Kim, J. Gehin, S. Palmtag, F. Franceschini

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).

By: R. Schmidt*, K. Belcourt*, R. Hooper*, R. Pawlowski*, K. Clarno*, S. Simunovic*, S. Slattery*, J. Turner*, S. Palmtag*

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

By: K. Clarno, S. Palmtag, G. Davidson, R. Salko, T. Evans, J. Turner, K. Belcourt, R. Hooper, R. Schmidt

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

By: R. Salko, M. Avramova, R. Hooper, S. Palmtag, E. Popov & J. Turner

Contributors: R. Salko, M. Avramova, R. Hooper, S. Palmtag, E. Popov & J. Turner

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

By: U. Mertyurek, S. Palmtag, G. Gert & J. Finch

Contributors: U. Mertyurek, S. Palmtag, G. Gert & J. Finch

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

By: S. Palmtag, J. Lamas, J. Finch, A. Godfrey & B. Moore

Contributors: S. Palmtag, J. Lamas, J. Finch, A. Godfrey & B. Moore

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

By: S. Palmtag, U. Mertyurek, B. Moore, M. Sugawara & A. Toishigawa

Contributors: S. Palmtag, U. Mertyurek, B. Moore, M. Sugawara & A. Toishigawa

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

Contributors: S. Palmtag & J. Rhodes III

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

By: T. Bahadir, S. Lindahl & S. Palmtag

Contributors: T. Bahadir, S. Lindahl & S. Palmtag

Source: ORCID
Added: August 18, 2020

1995 report

A two-dimensional, semi-analytic expansion method for nodal calculations

By: S. Palmtag*

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).

By: J. Wagner, E. Redmond, S. Palmtag* & J. Hendricks

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

By: C. Trybus, P. Collins, D. Maddison, K. Bunde, S. Palmtag & G. Palmiotti

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

Citation Index includes data from a number of different sources. If you have questions about the sources of data in the Citation Index or need a set of data which is free to re-distribute, please contact us.

Certain data included herein are derived from the Web of Science© and InCites© (2024) of Clarivate Analytics. All rights reserved. You may not copy or re-distribute this material in whole or in part without the prior written consent of Clarivate Analytics.