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Palmtag, Scott
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1

Advanced Liquid-Metal-Cooled Fast Reactor Core Design Using..:

Al-Dawood, Khaldoon ; Palmtag, Scott
Nuclear Science and Engineering.  , 2024
Link: https://doi.org/10.1080/..
 
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2

METAL: Methodology for liquid metal fast reactor core econo..:

Al-Dawood, Khaldoon ; Palmtag, Scott
Progress in Nuclear Energy.  173 (2024)  - p. 105232 , 2024
Link: https://doi.org/10.1016/..
 
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3

A Design and Optimization Methodology for Liquid Metal Fast..:

Al-Dawood, Khaldoon ; Palmtag, Scott ; Kuzmin, Andrey
International Journal of Energy Research.  2023 (2023)  - p. 1-15 , 2023
Link: https://doi.org/10.1155/..
 
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4

Fuel cycle cost comparison between lead and sodium cooled f..:

Al-Dawood, Khaldoon ; Palmtag, Scott
Nuclear Engineering and Design.  414 (2023)  - p. 112583 , 2023
Link: https://doi.org/10.1016/..
 
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5

Solving the Neutron Transport Equation for Microreactor Mod..:

Dawn, William C. ; Palmtag, Scott
Nuclear Science and Engineering.  197 (2023)  12 - p. 3138-3159 , 2023
Link: https://doi.org/10.1080/..
 
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6

CTF: A modernized, production-level, thermal hydraulic solv..:

Salko, Robert ; Wysocki, Aaron ; Blyth, Taylor...
Nuclear Engineering and Design.  397 (2022)  - p. 111927 , 2022
Link: https://doi.org/10.1016/..
 
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7

A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REAC..:

Dawn, William C. ; Palmtag, Scott ; Margulis, M..
EPJ Web of Conferences.  247 (2021)  - p. 06019 , 2021
Link: https://doi.org/10.1051/..
 
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8

VERA-CS VALIDATION OF CRITICAL EXPERIMENTS:

Novellino, Vincent ; Palmtag, Scott ; Margulis, M..
EPJ Web of Conferences.  247 (2021)  - p. 10014 , 2021
Link: https://doi.org/10.1051/..
 
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9

A multiphysics simulation suite for liquid metal-cooled fas..:

Dawn, William C. ; Palmtag, Scott
Annals of Nuclear Energy.  159 (2021)  - p. 108213 , 2021
Link: https://doi.org/10.1016/..
 
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10

QUANTIFICATION OF NUCLEAR DATA AND MANUFACTURING UNCERTAINT..:

Sedota, Christopher ; Palmtag, Scott ; Margulis, M..
EPJ Web of Conferences.  247 (2021)  - p. 15014 , 2021
Link: https://doi.org/10.1051/..
 
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11

Secondary-Source Core Reload Modeling with VERA:

Gentry, Cole ; Collins, Benjamin ; Davidson, Eva...
Nuclear Science and Engineering.  195 (2020)  3 - p. 320-337 , 2020
Link: https://doi.org/10.1080/..
 
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12

Simulation of the BEAVRS benchmark using VERA:

Collins, Benjamin ; Godfrey, Andrew ; Stimpson, Shane.
Annals of Nuclear Energy.  145 (2020)  - p. 107602 , 2020
Link: https://doi.org/10.1016/..
 
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13

Development of the multigroup cross section library for the..:

Kim, Kang Seog ; Gentry, Cole A. ; Godfrey, Andrew T...
Annals of Nuclear Energy.  132 (2019)  - p. 1-23 , 2019
Link: https://doi.org/10.1016/..
 
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14

VERA Core Simulator Methodology for Pressurized Water React..:

Kochunas, Brendan ; Collins, Benjamin ; Stimpson, Shane...
Nuclear Science and Engineering.  185 (2017)  1 - p. 217-231 , 2017
Link: https://doi.org/10.13182..
 
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15

An approach for coupled-code multiphysics core simulations ..:

Schmidt, Rodney ; Belcourt, Kenneth ; Hooper, Russell...
Annals of Nuclear Energy.  84 (2015)  - p. 140-152 , 2015
Link: https://doi.org/10.1016/..
 
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