2023 Publications:
Friederike Bostelmann, Eva E. Davidson, William A. Wieselquist, David Luxat, Kenneth C. Wagner, and Lucas I. Albright, Non-LWR Fuel Cycle Scenarios for SCALE and MELCOR Modeling Capability Demonstration, ORNL/TM-2023/2954, UT Battelle, LLC, Oak Ridge National Laboratory (2023).
Donny Hartanto, Friederike Bostelmann, Benjamin R. Betzler, Kursat B. Bekar, Shane W. Hart, and William A. Wieselquist, "SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems," Annals of Nuclear Energy, 196, 110236, 2024 (available online November 2023). DOI:10.1016/j.anucene.2023.110236
D. Hartanto, G. Redulescu, R. Elzohery, F. Bostelmann, W. Wieselquist, K.C. Wagner, and D. Luxat, “SCALE & MELCOR non-LWR Fuel Cycle Demonstration Project – Sodium-Cooled Fast Reactor,” NRC Public Workshop, presented virtually from Oak Ridge, Tennessee, September 20, 2023.
Alex Shaw, Friederike Bostelmann, Donny Hartanto, Erik Walker, and William A. Wieselquist, SCALE Modeling of the Sodium Cooled Fast-Spectrum Advanced Burner Test Reactor, ORNL/TM-2022/2758, UT-Battelle, LLC, Oak Ridge National Laboratory (July 2023).
Annie Berens, Friederike Bostelmann, and Nicholas R. Brown, “Equilibrium Cycle Modeling of a Generic mHTGR Similar to the Xe-100,” Transactions of the American Nuclear Society, 128, 796–799 (June 2023).
Friederike Bostelmann, Germina Ilas, and William A. Wieselquist, "Key nuclear data for non-LWR reactivity analysis," Frontiers in Energy Research, 11, 1159478 (April 2023).
R. Elzohery, F. Bostelmann, D. Hartanto, E. Davidson, W. Wieselquist, L. Albright, and D. Luxat, "SCALE & MELCOR non-LWR Fuel Cycle Demonstration Proj ect – High Temperature Gas-Cooled Reactors," NRC Public Workshop, presented virtually from Oak Ridge, Tennessee, February 28, 2023.
2022 Publications:
Germina Ilas, Joseph R. Burns, Briana D. Hiscox, and Ugur Mertyurek, SCALE 6.2.4 Validation: Reactor Physics, ORNL/TM-2020/1500v3, UT-Battelle, LLC, Oak Ridge National Laboratory (November 2022). Web, doi:10.2172/1902818
Austin Lo, Rike Bostelmann, Donny Hartanto, Benjamin Betzler, and William Wieselquist, Application of SCALE to Molten Salt Fueled Reactor Physics in Support of Severe Accident Analyses, ORNL/TM-2022/1844, UT-Battelle, LLC, Oak Ridge National Laboratory (November 2022). Web. doi:10.2172/1897864.
Friederike Bostelmann, Austin Lo, Benjamin R. Betzler, Donny Hartanto, and William A. Wieselquist, “MSR Reactivity, Power, and Inventory Simulations with SCALE,” Transactions of the American Nuclear Society, 127, 920–922 (November 2022).
Donny Hartanto, William A. Wieselquist, Steve Skutnik, Philip Gibbs, and Donald N. Kovacic, "Uncertainty Quantification of Pebble’s Discharge Burnup and Isotopic Inventory using SCALE,” Transactions of the American Nuclear Society, 127, 1040–1043 (November 2022).
A. Shaw, F. Bostelmann, E. Walker, W. Wieselquist, D. Luxat, K. C. Wagner, and J. Schaperow, "SCALE/MELCOR Non-LWR Source Term Demonstration Project – Sodium Fast Reactor," NRC Public Workshop, presented virtually from Oak Ridge, Tennessee, September 20, 2022.
F. Bostelmann, D. Hartanto, A. Lo, B. Betzler, W. Wieselquist, D. Luxat, K. C. Wagner, and J. Schaperow, "SCALE/MELCOR Non-LWR Source Term Demonstration Project – Molten Salt Reactor," NRC Public Workshop, presented virtually from Oak Ridge, Tennessee, September 13, 2022. [supporting files]
Robert F. Kile, Friederike Bostelmann, Steven E. Skutnik, William A. Wieselquist, and Nicholas R. Brown, "Assessment of SCALE and MELCOR for a generic pebble bed fluoride high-temperature reactor," Annals of Nuclear Energy, 173, 109107 (August 2022).
Erik Walker, Steven Skutnik, William Wieselquist, Alex Shaw, and Friederike Bostelmann, SCALE Modeling of the Fast Spectrum Heat Pipe Reactor, ORNL/TM-2021/2021, UT-Battelle, LLC, Oak Ridge National Laboratory (June 2022). [supporting files]
S. E. Skutnik, F. Bostelmann, and W. A. Wieselquist, "Rapid Depletion Analysis of Flowing-Pebble Reactor Systems at Equilibrium using SCALE,” Proceedings of International Conference on Physics of Reactors 2022 (PHYSOR 2022), pp. 1298–1307, Pittsburgh, Pennsylvania, May 15-20, 2022.
Friederike Bostelmann, Cihangir Celik, Robert F. Kile, and William A. Wieselquist, SCALE Analysis of a Fluoride Salt-Cooled High-Temperature Reactor in Support of Severe Accident Analysis, ORNL/TM-2021/2273, UT-Battelle, LLC, Oak Ridge National Laboratory (March 2022). [supporting files]
2021 Publications:
F. Bostelmann, G. Ilas, C. Celik, A. M. Holcomb, and W. A. Wieselquist, Nuclear Data Assessment for Advanced Reactors, NUREG/CR-7289 (ORNL/TM-2021/2002), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (December 2021). [supporting files]
F. Bostelmann, S. E. Skutnik, E. D. Walker, G. Ilas, and W. A. Wieselquist, "Modeling of the Molten Salt Reactor Experiment with SCALE," Nuclear Technology, 208(4), 603–624 (October 2021).
F. Bostelmann, R. Kile, W. Wieselquist, D. Luxat, K. C. Wagner, and J. Schaperow, "SCALE/MELCOR Non-LWR Source Term Demonstration Project – Fluoride‐Salt‐Cooled High-Temperature Reactor (FHR),” NRC Public Workshop, September 14, 2021, presented virtually from Oak Ridge, Tennessee. [supporting files]
Friederike Bostelmann, Germina Ilas, and William A. Wieselquist, "Nuclear Data Sensitivity Study for the EBR-II Fast Reactor Benchmark Using SCALE with ENDF/B-VII.1 and ENDF/B-VIII.0," Journal of Nuclear Engineering, 2(4), 345–367 (September 2021).
Steven Skutnik and William Wieselquist, Assessment of ORIGEN Reactor Library Development for Pebble-Bed Reactors Based on the PBMR-400 Benchmark, ORNL/TM-2020/1886, UT-Battelle, LLC, Oak Ridge National Laboratory (July 2021).
S. Skutnik, W. Wieselquist, D. Luxat, K. C. Wagner, and J. Schaperow, "SCALE/MELCOR Non-LWR Source Term Demonstration Project – High-Temperature Gas-Cooled Reactor," NRC Public Workshop, presented virtually from Oak Ridge, Tennessee, July 20, 2021. [supporting files]
E. Walker, W. Wieselquist, S. Skutnik, A. Shaw, D. Luxat, K. C. Wagner, and J. Schaperow, "SCALE/MELCOR Non-LWR Source Term Demonstration Project – Heat Pipe Reactor," NRC Public Workshop, presented virtually from Oak Ridge, Tennessee, June 2021. [supporting files]
2020 Publications:
F. Bostelmann, C. Celik, M. L. Williams, R. J. Ellis, G. Ilas, and W. A. Wieselquist, “SCALE capabilities for high temperature gas-cooled reactor analysis,” Annals of Nuclear Energy, 147, 107673 (November 2020).
F. Bostelmann, B. T. Rearden, W. Zwermann, and A. Pautz, “SCALE/AMPX Multigroup Libraries for Sodium-Cooled Fast Reactor Systems,” Annals of Nuclear Energy, 140, 107102 (June 2020).
F. Bostelmann, G. Ilas, and W. Wieselquist, Key Nuclear Data Impacting Reactivity in Advanced Reactors, ORNL/TM-2020/1557, UT-Battelle, LLC, Oak Ridge National Laboratory (June 2020).
Briana Hiscox, Benjamin Betzler, Vladimir Sobes, and William J. Marshall, "Neutronic Benchmarking of Small Gas-Cooled Systems," Proceedings of the PHYSOR 2020, March 29–April 2, 2020, Cambridge, United Kingdom.
Brian J. Ade, Benjamin R. Betzler, Aaron J. Wysocki, Michael S. Greenwood, Phillip C. Chesser, Kurt A. Terrani, Prashant K. Jain, Joseph R. Burns, Briana D. Hiscox, Jordan D. Rader, Jesse J. W. Heineman, Florent Heidet, Aurelien Bergeron, James W. Sterbentz, Tommy V. Holschuh, Nicholas R. Brown, and Robert F. Kile, "Candidate Core Designs for the Transformational Challenge Reactor," Proceedings of the PHYSOR 2020, March 29–April 2, 2020, Cambridge, United Kingdom.
P. J. Vicente Valdez, B. R. Betzler, W. A. Wieselquist, and M. Fratoni, Modeling Molten Salt Reactor Fission Product Removal with SCALE, ORNL/TM-2019/1418, UT-Battelle, LLC, Oak Ridge National Laboratory Report (March 2020).
Prior Year Publications:
J. W. Bae, B. R. Betzler, and A. Worrall, “Molten Salt Reactor Neutronic and Fuel Cycle Sensitivity and Uncertainty Analysis,” Transactions of the American Nuclear Society, 121, 1339–1342, November 2019.
F. Bostelmann, A. M. Holcomb, W. J. Marshall, V. Sobes, and B. T. Rearden, “Impact of the ENDF/B-VIII.0 Library on Advanced Reactor Simulations,” Transactions of the American Nuclear Society, 121, 1369–1372 (November 2019).
E. Davidson, B. Betzler, R. Gregg, and A. Worrall, “Modeling a Fast Spectrum Molten Salt Reactor in a Systems Dynamics Fuel Cycles Code,” Annals of Nuclear Energy, 133, 409–424, November 2019.
K. S. Kim, M. L. Williams, A. M. Holcomb, D. Wiarda, B. K. Jeon, and W. S. Yang, “The AMPX/SCALE Multigroup Cross Section Processing for Fast Reactor Analysis,” Annals of Nuclear Energy, 132, 161–171, October 2019.
B. R. Betzler, A. Rykhlevskii, A. Worrall, and K. D. Huff, “Impacts of Fast Spectrum Molten Salt Reactor Characteristics on Fuel Cycle Performance,” Proceedings of GLOBAL 2019 International Nuclear Fuel Cycle Conference, pp. 514–521, September 22–26, 2019, Seattle, Washington.
B. R. Betzler, K. B. Bekar, W. A. Wieselquist, S. W. Hart, and S. G. Stimpson, “Molten Salt Reactor Fuel Depletion Tools in SCALE,” Proceedings of GLOBAL 2019 International Nuclear Fuel Cycle Conference, pp. 956–967, September 22–26, 2019, Seattle, Washington.
A. Rykhlevskii, B. R. Betzler, A. Worrall, and K. D. Huff, “Fuel Cycle Performance of Fast Spectrum Molten Salt Reactor Designs,” Proceedings of International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering, August 25–29, 2019, Portland, Oregon.
K. S. Kim, F. Bostelmann, A. M. Holcomb, G. Ilas, and W. A. Wieselquist, “Verification of the ENDF/B-VII.1 and VIII.0 AMPX 1597-Group Libraries for Advanced Reactor Analysis,” Proceedings of International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering, pp. 2836–2845, August 25–29, 2019, Portland, Oregon.
A. Worrall, J. W. Bae, B. R. Betzler, M. S. Greenwood, and L. G. Worrall, “Molten Salt Reactor Safeguards: The Necessity of Advanced Modeling and Simulation to Inform on Fundamental Signatures,” Proceedings of Institute of Nuclear Materials Management 60th Annual Meeting, July 14–18, 2019, Palm Desert, California.
V. Sobes, W. J. Marshall, D. Wiarda, F. Bostelmann, A. M. Holcomb, and B. T. Rearden, ENDF/B-VIII.0 Covariance Data Development and Testing Report for Advanced Reactors, ORNL/TM-2018/1037, UT-Battelle, LLC, Oak Ridge National Laboratory (March 2019).
F. Bostelmann, A. M. Holcomb, J. B. Clarity, W. J. Marshall, V. Sobes, and B. T. Rearden, Nuclear Data Performance Assessment for Advanced Reactors, ORNL/TM-2018/1033, UT-Battelle, LLC, Oak Ridge National Laboratory (March 2019).
D. Shen, M. Fratoni, G. Ilas, and J. Powers, “Molten-Salt Reactor Experiment (MSRE) Zero-Power First Critical Experiment with 235U”, MSRE-MSR-EXP-001, International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE), Nuclear Energy Agency (2019).
E. Losa, M.Kostal, T. Czakoj, B. Jansky, E. Novak, V. Rypar, J.J. Powers, N.R. Brown, and D. Mueller, "Neutronic Experiments with Fluorine Rich Compounds at LR-0 Reactor," Annals of Nuclear Energy, 120, 286–295 (October 2018).
F. Bostelmann, B. T. Rearden, W. Zwermann, and A. Pautz, “Preliminary SCALE/TSUNAMI Results for the Sub-Exercises of the OECD/NEA Benchmark for Uncertainty Analysis in Modeling of Sodium-Cooled Fast Reactors,” Transactions of the American Nuclear Society, 119, 627–630 (November 2018).
F. Bostelmann, M. L. Williams, C. Celik, R. J. Ellis, G. Ilas, and B. T. Rearden, “Assessment of SCALE Capabilities for High Temperature Reactor Modeling and Simulation,” Transactions of the American Nuclear Society, 119, 1073–1076 (November 2018).
D. Shen, M. Fratoni, M. Aufiere, A. Bidaud, J. Powers, and G. Ilas, “Progress towards a Molten Salt Reactor Experiment Benchmark Evaluation," Transactions of the American Nuclear Society ,117, 1359–1361 (November 2017).
Benjamin R. Betzler, Jeffrey J. Powers, and Andrew Worrall, "Molten Salt Reactor Neutronics and Fuel Cycle Modeling and simulation with SCALE," Annals of Nuclear Energy, 101, 489–503 (March 2017).
Germina Ilas, Dan Ilas, Ryan Kelly, and Eva Sunny, Validation of SCALE for High Temperature Gas-Cooled Reactor Analysis, NUREG/CR-7107, ORNL/TM-2011/161, U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (July 2012).
J. Gehin, M. Jessee, M. Williams, D. Lee, S. Goluoglu, G. Ilas, D. Ilas and S. Bowman, "Development and validation of SCALE nuclear analysis methods for high temperature gas-cooled reactors,” Proceedings of 5th International Topical Meeting on High Temperature Reactor Technology, Prague, October 2010, Czech Republic. [pdf]
G. Ilas, "On SCALE validation for PBR analysis," Proceedings of PHYSOR 2010 – Advances in Reactor Physics to Power the Nuclear Renaissance, May 9–14, 2010, Pittsburgh, Pennsylvania. [pdf]
E. E. Sunny and G. Ilas, "SCALE 6 analysis of HTR-10 pebble-bed reactor for initial critical configuration," Proceedings of PHYSOR 2010 – Advances in Reactor Physics to Power the Nuclear Renaissance, May 9–14, 2010, Pittsburgh, Pennsylvania.