Scott Palmtag Al-Dawood, K., & Palmtag, S. (2023). A Design and Optimization Methodology for Liquid Metal Fast Reactors. INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2023. https://doi.org/10.1155/2023/6846467 Al-Dawood, K., & Palmtag, S. (2023). Fuel cycle cost comparison between lead and sodium cooled fast reactors. NUCLEAR ENGINEERING AND DESIGN, 414. https://doi.org/10.1016/j.nucengdes.2023.112583 Dawn, W. C., & Palmtag, S. (2023, May 11). Solving the Neutron Transport Equation for Microreactor Modeling Using Unstructured Meshes and Exascale Computing Architectures. NUCLEAR SCIENCE AND ENGINEERING, Vol. 5. https://doi.org/10.1080/00295639.2023.2189510 Salko, R., Wysocki, A., Blyth, T., Toptan, A., Hu, J., Kumar, V., … Pilch, M. (2022). 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. https://doi.org/10.1016/j.nucengdes.2022.111927 Kiefer, T. M., Dawn, W. C., Al-Dawood, K., & Palmtag, S. (2022, July). Control rod modeling in liquid metal-cooled fast reactors. Retrieved from https://www.osti.gov/biblio/23178744 Al-Dawood, K. A., & Palmtag, S. P. (2022, July). LMFR design and optimization methodology. Retrieved from https://www.osti.gov/biblio/23178727 Lawing, C. ; Palmtag, S. ; & Asgari, M. (2022, May). VERA BWR Progression Problems. Retrieved from https://www.osti.gov/biblio/1890346 Dawn, W. C., & Palmtag, S. (2021). A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORS. EPJ Web of Conferences, 247, 06019. https://doi.org/10.1051/epjconf/202124706019 Dawn, W. C., & Palmtag, S. (2021). A multiphysics simulation suite for liquid metal-cooled fast reactors. ANNALS OF NUCLEAR ENERGY, 159. https://doi.org/10.1016/j.anucene.2021.108213 Lawing, C. ; Palmtag, S. ; & Kropaczek, D. J. (2021). Analysis of Approximations in Modeling of BWR Bundle Void Distributions. https://doi.org/10.2172/1845788 Lawing, C. ; Palmtag, S. ; & Asgari, M. (2021). BWR Progression Problems. https://doi.org/10.2172/1838995 Sedota, C., & Palmtag, S. (2021). QUANTIFICATION OF NUCLEAR DATA AND MANUFACTURING UNCERTAINTIES IN VERA. EPJ Web of Conferences, 247, 15014. https://doi.org/10.1051/epjconf/202124715014 Fustero, J., Palmtag, S., & Mueller, F. (2021). 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. https://doi.org/10.1109/QCE52317.2021.00044 Gentry, C., Collins, B., Davidson, E., Davidson, G., Evans, T., Godfrey, A., … Wolfram, G. (2021). Secondary-Source Core Reload Modeling with VERA. NUCLEAR SCIENCE AND ENGINEERING, 195(3), 320–337. https://doi.org/10.1080/00295639.2020.1820797 Novellino, V., & Palmtag, S. (2021). VERA-CS VALIDATION OF CRITICAL EXPERIMENTS. EPJ Web of Conferences, 247, 10014. https://doi.org/10.1051/epjconf/202124710014 Salko, R., Jr, Wysocki, A., Toptan, A., Porter, N., Zhao, X., Blyth, T., … Avramova, M. (2020). CTF Validation and Verification. https://doi.org/10.2172/1731045 Dawn, W., Ortensi, J., DeHart, M., & Palmtag, S. (2020). Comparison of Generation of Higher-Order Neutron Scattering Cross Sections. In Idaho National Laboratory. https://doi.org/10.2172/1593864 Verrico, L., Palmtag, S., Thompson, T., Novellino, V., & Goodman, C. (2020). Design of an Economical Low-Power Fast Spectrum Molten Chloride Reactor. Transactions of the American Nuclear Society - Volume 123. https://doi.org/10.13182/t123-32905 Collins, B., Godfrey, A., Stimpson, S., & Palmtag, S. (2020). Simulation of the BEAVRS benchmark using VERA. ANNALS OF NUCLEAR ENERGY, 145. https://doi.org/10.1016/j.anucene.2020.107602 Kim, K. S., Gentry, C. A., Godfrey, A. T., Liu, Y., & Palmtag, S. (2019). Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification. ANNALS OF NUCLEAR ENERGY, 132, 1–23. https://doi.org/10.1016/j.anucene.2019.03.041 Kim, K. S. ; Clarno, K. T. ; Gentry, C. ; Wiarda, D. ; Williams, M. L. ; Kochunas, B. ; … Godfrey, A. T. (2017). Development of the V4.2m5 and V5.0m0 Multigroup Cross Section Libraries for MPACT for PWR and BWR. https://doi.org/10.2172/1352789 Kochunas, B. ; Collins, B. ; Stimpson, S. ; Salko, R. ; Jabaay, D. ; Graham, A. ; … Gehin, J. (2017). VERA Core Simulator methodology for pressurized water reactor cycle depletion. In Nuclear Science and Engineering. https://doi.org/10.13182/NSE16-39 Graham, A. ; Downar, T. ; & Palmtag, S. (2016). Assessment of Thermal Hydraulic Feedback Models. Retrieved from https://www.osti.gov/scitech/biblio/1325432-assessment-thermal-hydraulic-feedback-models Salko, R. K. ; Blyth, T. S. ; Dances, C. A. ; Magedanz, J. W. ; Jernigan, C. ; Kelly, J. ; … Gehin, J. C. (2016). CTF Validation and Verification Manual. https://doi.org/10.2172/1342678 Collins, B. S. ; Hamilton, S. P. ; Jarrett, M. G. ; Kim, K. S. ; Kochunas, B. ; Liu, Y. ; … Yee, B. (2016). Demonstrate VERA Core Simulator Performance Improvements L2:PHI.P13.03. https://doi.org/10.2172/1338536 Collins, B. S. ; Downar, T. ; Fitzgerald, A. ; Gehin, J. C. ; Godfrey, A. T. ; Graham, A. ; … Zhu, A. (2016). MPACT Standard Input User s Manual, Version 2.2.0. https://doi.org/10.2172/1342674 Downar, T. ; Collins, B. S. ; Gehin, J. C. ; Godfrey, A. T. ; Jabaay, D. ; Kelley, B. W. ; … Zhu, A. (2016). MPACT Theory Manual, Version 2.2.0. https://doi.org/10.2172/1340449 Collins, B. S. ; Downar, T. ; Fitzgerald, A. ; Gehin, J. C. ; Godfrey, A. T. ; Graham, A. ; … Zhu, A. (2016). MPACT VERA Input User s Manual, Version 2.2.0. https://doi.org/10.2172/1342675 Clarno, K. T. ; Palmtag, S. ; Secker, J. ; Kendrick, B. ; & Montgomery, R. (2016). Simulation of CRUD Induced Power Shift using the VERA Core Simulator and MAMBA. Retrieved from https://www.osti.gov/scitech/biblio/1325433-simulation-crud-induced-power-shift-using-vera-core-simulator-mamba Godfrey, A. T. ; Collins, B. S. ; Kim, K. S. ; Montgomery, R. ; Powers, J. J. ; Salko, R. K. ; … Secker, J. (2016). VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12. Retrieved from https://www.osti.gov/scitech/biblio/1260079-vera-benchmarking-results-watts-bar-nuclear-plant-unit-cycles Salko, R. K. ; Lange, T. L. ; Kucukboyaci, V. ; Sung, Y. ; Palmtag, S. ; Gehin, J. C. ; & Avramova, M. (2015). Development of COBRA-TF for Modeling Full-Core Reactor Operating Cycles. Retrieved from https://www.osti.gov/scitech/biblio/1185922-development-cobra-tf-modeling-full-core-reactor-operating-cycles Salko, R. K. ; Palmtag, S. ; Collins, B. S. ; Kendrick, B. ; & Seker, J. (2015). L3.PHI.CTF.P10.02-rev2 Coupling of Subchannel T/H (CTF) and CRUD Chemistry (MAMBA1D). https://doi.org/10.2172/1344982 Kochunas, B. ; Collins, B. S. ; Jabaay, D. ; Kim, K. S. ; Graham, A. ; Stimpson, S. ; … Gehin, J. C. (2015). VERA Core Simulator Methodology for PWR Cycle Depletion. Retrieved from https://www.osti.gov/scitech/biblio/1215576-vera-core-simulator-methodology-pwr-cycle-depletion Kouchunas, B. ; Jabaay, D. ; Downar, T. ; Collins, B. S. ; Stimpson, S. G. ; Godfrey, A. T. ; … Franceschini, F. (2015). Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS. Retrieved from https://www.osti.gov/scitech/biblio/1214019-validation-application-neutron-transport-mpact-within-casl-vera-cs Schmidt, R. ; Belcourt, K. ; Hooper, R. ; Pawlowski, R. P. ; Clarno, K. T. ; Simunovic, S. ; … Palmtag, S. (2014). An approach for coupled-code multiphysics core simulations from a common input. In Annals of Nuclear Energy (Oxford). https://doi.org/10.1016/j.anucene.2014.11.015 Clarno, K. T. ; Palmtag, S. ; Davidson, G. G. ; Salko, R. K. ; Evans, T. M. ; Turner, J. A. ; … Schmidt, R. (2014). Coupled Neutronics Thermal-Hydraulic Solution of a Full-Core PWR Using VERA-CS. Retrieved from https://www.osti.gov/scitech/biblio/1154814-coupled-neutronics-thermal-hydraulic-solution-full-core-pwr-using-vera-cs Salko, R. K., Avramova, M. N., Hooper, R., Palmtag, S., Popov, E., & Turner, J. (2013). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84883365179&partnerID=MN8TOARS Mertyurek, U., Palmtag, S., Gert, G., & Finch, J. (2010). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-79952378953&partnerID=MN8TOARS Palmtag, S., Lamas, J., Finch, J., Godfrey, A., & Moore, B. R. (2008). The advanced BWR core simulator AETNA02. International Conference on the Physics of Reactors 2008, PHYSOR 08, 2, 1282–1289. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-79953837410&partnerID=MN8TOARS Palmtag, S., Mertyurek, U., Moore, B. R., Sugawara, M., & Toishigawa, A. (2007). Steady-state nuclear analysis methods at global nuclear fuel, invited. Transactions of the American Nuclear Society, 97, 557–558. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-55349115707&partnerID=MN8TOARS CASMO-4 and multigroup MCNP comparisons for MOX fuel assemblies. (2005). Transactions of the American Nuclear Society, 92, 508–509. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-33244479401&partnerID=MN8TOARS Bahadir, T., Lindahl, S.-Ö., & Palmtag, S. P. (2005). Microscopic depletion model in SIMULATE-4. Transactions of the American Nuclear Society, 92, 635–636. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-33244493781&partnerID=MN8TOARS Palmtag, S. P. (1995). A two-dimensional, semi-analytic expansion method for nodal calculations. https://doi.org/10.2172/505709 Wagner, J. C., Redmond, E. L. I. I., Palmtag, S. P., & Hendricks, J. S. (1994). MCNP: Multigroup/adjoint capabilities (Vol. 4). https://doi.org/10.2172/10145615 Trybus, C. L., Collins, P. J., Maddison, D. W., Bunde, K. A., Palmtag, S. ; & Palmiotti, G. (1994). Measurements of actinide transmutation in the hard spectrum of a fast reactor. Retrieved from https://www.osti.gov/scitech/biblio/204716-measurements-actinide-transmutation-hard-spectrum-fast-reactor