SCALE References

The current SCALE 6.3.2 manual can be cited with the following: 

W. A. Wieselquist, R. A. Lefebvre, Eds., SCALE 6.3.2 User Manual, ORNL/TM-2024/3386, UT-Battelle, Oak Ridge National Laboratory (February 2024).

Find below the SCALE team’s publications, additionally grouped into categories below.

2025 Publications:

Friederike Bostelmann, Steven E. Skutnik, and William A. Wieselquist, "Introducing the SLICE Method for estimating pebble-bed reactor inventories at equilibrium operation with SCALE," Annals of Nuclear Energy, 224 (December 2025). DOI: 10.1016/j.anucene.2025.111684.

Steven E. Skutnik, Friederike Bostelmann, Donny Hartanto, and William A. Wieselquist, "New capabilities for rapid depletion analysis of pebble-bed reactors in SCALE," Annals of Nuclear Energy, 223 (December 2025). DOI: 10.1016/j.anucene.2025.111564.

D. Hartanto, G. Redulescu, F. Bostelmann, W. Wieselquist, E. Duchnowski, B. Beeny, M. Christian, and D. L. Luxat, “SCALE & MELCOR non-LWR Fuel Cycle Demonstration Project – Heat Pipe Microreactor,” NRC Public Workshop, presented virtually from Oak Ridge, Tennessee, March 26, 2025.

Friederike Bostelmann, Benjamin R. Betzler, Donny Hartanto, and  William A. Wieselquist, "SCALE inventory and reactivity analysis as part of the Hermes 2021 PSAR review," Annals of Nuclear Energy, 212 (March 2025).  DOI: 10.1016/j.anucene.2024.111063.

Donny Hartanto, Georgeta Redulescu, Friederike Bostelmann, and William Wieselquist, SCALE Analyses of Scenarios in the Molten Salt Reactor Fuel Cycle, ORNL/TM-2024/3659, UT-Battelle, LLC, Oak Ridge National Laboratory (February 2025).

2024 Publications:

Dimitri Rochman, Alejandro Algora, Francisco Alvarez velarde, Aurelie Bardelay, Oystein Bremnes, Oscar Cabellos, Daniel Cano otto, Luigi Capponi, Coralie Carmouze, Stefano Caruso, Andrew Cummings, Ron Dagan, Muriel Fallot, Luca Fiorito, Lydie Giot, Kevin Govers, Silja Haakkinen, Volker Hannstein, Axel Hoefer, Tan Huynh, Raphaelle Ichou,Germaina Ilas, Pauli Juutilainen, Lukasz Koszuk, Marjan Kromar, Sebastien Lahaye, James Lam, Frederic Laugier, Agnes Launay, Vincent Leger, David Lecarpentier, Jaakko Leppanen, Fadhel Malouch, Julie-Fiona Martin, David McGinnes, Robert Mills, Futoshi Minato, Yasushi Nauchi, Pedro Ortego, Plamen Petkov, Pablo Romojaro, Shunsuke Sato, Marcus Seidl, Ahmed Shama, Teodosi Simeonov, Anders Sjoland, Virginie Solans, Fabian Sommer, Sven Tittelbach, Aime Tsilanizara, Efstathios Vlassopoulos, Vanessa Vallet, Alexander Vasiliev, Tomoaki Watanabe, and Gasper Zerovnik, "An introduction to Spent Nuclear Fuel decay heat for Light Water Reactors: a review from the NEA WPNCS," EPJ Nuclear Sci. Technol., 10, 9 (2024).

Tara Pandya, Tarek Ghaddar, Friederike Bostelmann, Nicholas Luciano, Steven Hamilton, Matthew Jessee, Donny Hartanto, Modeling Enhancements, Cross-Section Generation Updates, and Benchmarking with Shift, ORNL/TM-2024/3572, UT-Battelle, LLC, Oak Ridge National Laboratory (October 2024).

Arzu Alpan, Cihangir Celik, Mathieu Dupont, and Douglas Peplow, SCALE 6.3.0 Validation: Radiation Shielding, ORNL/TM-2023/2884/v4, UT-Battelle, LLC, Oak Ridge National Laboratory (October 2024).

Rabab Elzohery, Donny Hartanto, Friederike Bostelmann, and William Wieselquist, SCALE Analyses of Scenarios in the High-Temperature Gas-Cooled Reactor Fuel Cycle, ORNL/TM-2024/3536, UT-Battelle, LLC, Oak Ridge National Laboratory (October 2024).

Kang Seog Kim, Byoung-Kyu Jeon, Andrew Ward, Ugur Mertyurek, Matthew Jessee, William Wieselquist, "Validation of the SCALE/Polaris-PARCS Code Procedure with the ENDF/B-VII.1 AMPX 56-Group Library: Pressurized Water Reactor," Journal of Nuclear Engineering, 5(3), 246-259 (July 2024).

Kang Seog Kim, Andrew Ward, Ugur Mertyurek, Mehdi Asgari, William Wieselquist, "Validation of the SCALE/Polaris-PARCS Code Procedure with the ENDF/B-VII.1 AMPX 56-Group Library: Boiling Water Reactor," Journal of Nuclear Engineering, 5(3), 260-273 (July 2024).

D. Hartanto, G. Redulescu, F. Bostelmann, W. Wieselquist, E. Duchnowski, B. Beeny, M. Christian, and D. L. Luxat, “SCALE & MELCOR non-LWR Fuel Cycle Demonstration Project – Molten Salt Reactor,” NRC Public Workshop, presented virtually from Oak Ridge, Tennessee, July 11, 2024. 

Annie Berens, Friederike Bostelmann, and Nicholas R. Brown, "Equilibrium core modeling of a pebble bed reactor similar to the Xe-100 with SCALE," Progress in Nuclear Energy, 171(1) (June 2024). DOI: 10.1016/j.pnucene.2024.105187.

Thomas Evans, Seth Johnson, Shane Hart, Elliott Biondo, and Amanda Bachmann, "Investigation of Doppler Broadening Methods Within the Shift Monte Carlo Radiation Transport Code," Transactions of the American Nuclear Society, 130, 470-473 (June 2024).

A. M. Shaw, W. A. Metwally, M. N. Dupont, William (B.J.) Marshall, Cihangir Celik, Veronica Karriem, Alex Lang, and Lisa Fassino, "Effect of Decay Time on Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels," Transactions of the American Nuclear Society, 130, 794-797 (June 2024).

Kang Seog Kim, William Gurecky, Matthew Jessee, and William Wieselquist, "Sensitivity Analysis of the SCALE/Polaris-PARCS Code Procedure for Watts Bar Unit 1 and Peach Bottom Unit 2," Transactions of the American Nuclear Society, 130, 1001-1004 (June 2024).

Kang Seog Kim, Matthew A. Jessee, Andrew M. Holcomb, and William Wieselquist, "Dancoff-Based Wigner-Seitz Approximation for the Embedded Self-Shielding Method in SCALE/Polaris," Transactions of the American Nuclear Society, 130, 1030-1033 (June 2024).

B.K. Jeon, K.S. Kim, U. Mertyurek, A. Ward, M.A. Jessee, and W. Wieselquist, "Benchmark Calculations for Turkey Point Unit 3 and Surry Unit 1 Using the SCALE/Polaris-PARCS Procedure," Transactions of the American Nuclear Society, 130, 1104-1107 (June 2024).

D. Chandler, D. Hartanto, J. W. Bae, K. M. Burg, and Y. E. Robert, "Sensitivity and Validation Studies of Plutonium-238 Production with Shift and ORIGEN," Transactions of the American Nuclear Society, 130, 1108-1111 (June 2024).

Rike Bostelmann, Steve Skutnik, Alex Shaw, Donny Hartanto, and William Wieselquist, SCALE 6.3 Modeling Strategies for Reactivity, Nuclide Inventory, and Decay Heat of Non-LWRs, ORNL/TM-2024/3213, UT-Battelle, LLC, Oak Ridge National Laboratory (May 2024).

Alex Shaw, Hypothetical Sodium-Cooled Fast Reactor Fuel Transport Using the Existing ES-3100, ORNL/TM-2024/3366, UT-Battelle, LLC, Oak Ridge National Laboratory (May 2024).

Alex M. Shaw, Walid A. Metwally, and William J. Marshall, Scoping Studies on the Impacts of Increased Enrichment on Nuclear Criticality Safety, ORNL/TM-2024/3350, UT-Battelle, LLC, Oak Ridge National Laboratory (May 2024).

G. Radulescu, D. Hartanto, F. Bostelmann, and W. Wieselquist, "SCALE 6.3.1 Radiation Source Terms and Shielding Analysis for a Postulated Sodium-Cooled Fast Reactor Accident Scenario," Proceedings of International Conference on Physics of Reactors 2024 (PHYSOR 2024), pp. 360-369, San Francisco, California, April 21-24, 2024.

Germina Procop and Jesse Brown, "Nuclide Inventory Validation: Effect of Nuclear Data Libraries," Proceedings of International Conference on Physics of Reactors (PHYSOR 2024), pp. 1122-1130,  San Francisco, California, April 21-24, 2024.

Ugur Mertyurek, Riley Cumberland, and William Wieselquist, "Core Physics Characteristics of Extended Enrichment and Higher Burnup Boiling Water Reactor Fuel," Proceedings of International Conference on Physics of Reactors 2024 (PHYSOR 2024), pp. 2194-2203, San Francisco, California, April 21-24, 2024.

Donny Hartanto, Georgeta Radulescu, Rike Bostelmann, Rabab Elzohery, and William Wieselquist, SCALE Demonstration for Sodium-cooled Fast Reactor Fuel Cycle Analysis, ORNL/TM-2023/3214, UT-Battelle, LLC, Oak Ridge National Laboratory (April 2024).

W. A. Wieselquist and R. A. Lefebvre, SCALE 6.3.2 User Manual, UT-Battelle, LLC, Oak Ridge National Laboratory (February 2024).

Robert Lefebvre, Jesse Brown, Cihangir Celik, Thomas Evans, Bk Jeon, Jordan McDonnell, Katherine Royston, Dorothea Wiarda, and William Wieselquist, Photonuclear Physics in SCALE, ORNL/TM-2023/3201, UT-Battelle, Oak Ridge National Laboratory (January 2024).

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 (December 2023).

Kang Seog Kim, Dorothea Wiarda, Chris Chapman, Jordan McDonnell, and William A. Wieselquist, "Improvement of the SCALE-6.3/XSProc Pointwise Slowing-Down Capability with the Bound Thermal Scattering Data Including High Forward Peaks," Transactions of the American Nuclear Society, 129, 817–820 (November 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 (2024) (available online November 2023). DOI:10.1016/j.anucene.2023.110236.

C. Carmouze, R. Ichou, G. Ilas, F. Alvarez-Velarde, M. Chernykh, R. García Baonza, L. Giot, K. Govers, F. Grimaldi, V. Hannstein, A. Hoefer, P. Juutilainen, J. Lams, P. Martínez-Moreno, D. Mennerdahl, U. Mertyurek, Y. Molla, S. Richards, D. Rochman, P. Romojaro, D. Schulze Grachtrup, A. Shama, N. Slosse, P. Smith, F. Sommer, M. Stefanowska Skrodzka, S. Tittelbach, T. Wakanabe, G Žerovnik, "Overview of Spent Nuclear Fuel Inventory Results for the Ariane Gu3 Sample," Proceedings of ICNC 2023 – The 12th International Conference on Nuclear Criticality Safety, Sendai, Miyagi, Japan, October 1–6, 2023. 

Alex Shaw, Nicholas Kucinski, and Briana Hiscox, "Criticality Safety Recommendations for the Treatment Of Extended Enrichment And High Burnup Fuel for Storage and Transportation Systems," Proceedings of ICNC 2023 – The 12th International Conference on Nuclear Criticality Safety, Sendai, Miyagi, Japan, October 1–6, 2023. 

Tara Pandya, Tarek Ghaddar, Friederike Bostelmann, Matthew Jessee, and Philip Brit, Modeling Enhancements and Demonstration of Shift Capabilities for PBR and MSR, ORNL/TM-2023/3072, UT-Battelle, LLC, Oak Ridge National Laboratory (October 2023).

Nolan E. Goth, Jesse M. Brown, Tarek Ghaddar, Logan Scott, Jin Whan Bae, and Phillip Britt, Optimal Chloride Salt Mixture for a Fusion Blanket, ORNL/TM-2023/3052, UT-Battelle, LLC, Oak Ridge National Laboratory (September 2023).  

Germina Ilas and Rabab Elzohery, Validating Actinides and Fission Products for Burnup Credit Criticality Safety Analyses – Nuclide Compositions Prediction with Extended Validation Basis, NUREG/CR-7303(ORNL/SPR-2023/2885), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (September 2023).

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.

Ugur Mertyurek and William A. Wieselquist, Assessment of Core Physics Characteristics of Extended Enrichment and Higher Burnup LWR Fuels using the Polaris/PARCS Two-Step Approach Vol. 2: BWR Fuel, ORNL/TM-2022/2444, UT-Battelle, LLC, Oak Ridge National Laboratory (August 2023). [supporting files]

Steve E. Skutnik, Ugur Mertyurek, Muhammad Rizki Oktavian, and William A. Wieselquist, Transition Core Modeling for Extended Enrichment & Accident-Tolerant Fuels Using Polaris/PARCS, ORNL/TM-2023/2834, UT-Battelle, LLC, Oak Ridge National Laboratory (July 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).

Rabab Elzohery and Germina Ilas, "Impact of Cross Section Libraries on Loading Curves for Burnup Credit Criticality Safety Analysis Models," Transactions of the American Nuclear Society, 128, 494–496 (June 2023).

D. Hartanto, J. W. Bae, B. R. Betzler, J. R. Burns, D. Chandler, and C. Sizemore, “Nuclear Data Uncertainty Quantification of High Flux Isotope Reactor Low-Enriched Uranium Design,” Transactions of the American Nuclear Society, 128, 792–795 (June 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).

Kang Seog Kim, Ugur Mertyurek, Andrew M. Ward, Matthew A. Jessee, and William A. Wieselquist, "Benchmark Calculations for Peach Bottom Unit 2 and Hatch Unit 1 Using the SCALE-6.3.0/Polaris-PARCS v3.4.2 Code Package," Transactions of the American Nuclear Society, 128, 800–803 (June 2023).

Kang Seog Kim, Ugur Mertyurek, Andrew M. Ward, Matthew A. Jessee, and William A. Wieselquist, "Benchmark Calculations for BEAVRS and Watt Bar Unit 1 Using the SCALE-6.3.0/Polaris-PARCS v3.4.2 code Package," Transactions of the American Nuclear Society, 128, 804–807 (June 2023).

Shane W. D. Hart, Seth R. Johnson, Robert A. Lefebvre, and William A. Wieselquist, “Improvement of SCALE Infrastructure on Microsoft Windows,” Transactions of the American Nuclear Society, 128, 808–810 (June 2023).

Jeongwon Seo, Hany S. Abdel-Khalik, Ugur Mertyurek, Goran Arbanas, William Marshall, and William Wieselquist, “Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety,” Nuclear Science and Engineering, 198(3), 673–701 (June 2023, online). DOI: 10.1080/00295639.2023.2211202.

Georgeta Radulescu, Updated Recommendations Related to Spent Fuel Transport and Dry Storage Shielding Analyses, NUREG/CR-7302 (ORNL/TM-2023/2679), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (May 2023).

Friederike Bostelmann, Germina Ilas, and William A. Wieselquist, "Key nuclear data for non-LWR reactivity analysis," Frontiers in Energy Research, 11 (April 2023). DOI: 10.3389/fenrg.2023.1159478.

Hany Abdel-Khalik, Jeongwon Seo, Ugur Mertyurek, Goran Arbanas, William Marshall, and William Wieselquist, Comparative Analysis of Confidence Metrics for Nuclear Criticality Safety. ORNL/TM-2022/2772, UT-Battelle, LLC, Oak Ridge National Laboratory (March 2023).

R. Elzohery, F. Bostelmann, D. Hartanto, E. Davidson, W. Wieselquist, L. Albright, and D. Luxat, "SCALE & MELCOR non-LWR Fuel Cycle Demonstration Project – High Temperature Gas-Cooled Reactors," NRC Public Workshop, presented virtually from Oak Ridge, Tennessee, February 28, 2023.

2022 Publications:

Germina Ilas, Bruce Bevard, Joseph Giaquinto, Cole Hexel, and Benjamin Roach, "New Radiochemical Assay Experiments to Improve the Validation Basis for High Burnup Fuel," Proceedings of International High-Level Radioactive Waste Management (IHLRWM), pp. 568–571, Phoenix, Arizona, November 13–17, 2022.

Cihangir Celik, Douglas E. Peplow, Mathieu N. Dupont, and Georgeta Radulescu, SCALE 6.2.4 Validation: Radiation Shielding, UT-Battelle, LLC, Oak Ridge National Laboratory, ORNL/TM-2020/1500/v4 (November 2022). Web. DOI: 10.2172/1902814.

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.

Travis M. Greene and William J. Marshall, SCALE 6.2.4 Validation: Nuclear Criticality Safety, ORNL/TM-2020/1500/v2, UT-Battelle, LLC, Oak Ridge National Laboratory (November 2022).

William A. Wieselquist and  Benjamin R. Betzler, SCALE 6.2.4 Validation: Overview,  ORNL/TM-2020/1500/v1, UT-Battelle, LLC, Oak Ridge National Laboratory (November 2022).

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).

Georgeta Radulescu, Cihangir Celik, and Peter Stevanovic, "Overview of ORNL SCALE Shielding Analyses for Spent Nuclear Fuel Transportation and Storage Applications," Proceedings of  ICRS 14/RPSD 2022: 14th International Conference on Radiation Shielding and 21st Topical Meeting of the Radiation Protection and Shielding Division, pp. 54–57, Seattle, Washington, September 25–29, 2022.

Douglas E. Peplow, Daniel E. Archer, James M. Ghawaly, Jr., Tenzing H. Y. Joshi, Mark S. Bandstra, and Brian J. Quiter, "Threat Sources for Detection Algorithm Testing Developed with SCALE," Proceedings of  ICRS 14/RPSD 2022: 14th International Conference on Radiation Shielding and 21st Topical Meeting of the Radiation Protection and Shielding Division, pp. 136–139, Seattle, Washington, September 25–29, 2022.

Douglas E. Peplow, Daniel E. Archer, James M. Ghawaly, Jr., Tenzing H. Y. Joshi, Mark S. Bandstra, Brian J. Quiter, and Abigael C. Nachtsheim, "Detection Algorithm Virtual Testbed for Urban Search with SCALE," Proceedings of  ICRS 14/RPSD 2022: 14th International Conference on Radiation Shielding and 21st Topical Meeting of the Radiation Protection and Shielding Division, pp. 140–143, Seattle, Washington, September 25–29, 2022.

Noel B. Nelson, Michael B. R. Smith, Lawrence H. Heilbronn, Harrison L. Line, Douglas E. Peplow, and Mathew W. Swinney, "The Sensitivity of Three Terrestrial Bacteria to a Multi-Mission Radioisotope Thermoelectric Generator," Proceedings of  ICRS 14/RPSD 2022: 14th International Conference on Radiation Shielding and 21st Topical Meeting of the Radiation Protection and Shielding Division, pp. 292–295, Seattle, Washington, September 25–29, 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]

Jin Whan Bae, Ugur Mertyurek, and Mehdi Asgari, Light Water Reactor LEU+ Lattice Optimization, ORNL/TM-2021/2366, UT-Battelle, LLC, Oak Ridge National Laboratory (September 2022).

Peter Janssona, Martin Bengtsson, Francisco Álvarez-Velarde, Dušan Čalič, Stefano Caruso, Ron Dagan, Luca Fiorito, Lydie Giot, Kevin Govers, Augusto Hernandez Solis, Volker Hannstein, Germina Ilas, Marjan Kromar, Jaakko Leppänen, Marita Mosconi, Pedro Ortego, Rita Plukienė, Arturas Plukis, Anssu Ranta-Aho, Dimitri Rochman, Linus Ros, Shunsuke Sato, Peter Schillebeeckx, Ahmed Shama, Teodosi Simeonov, Alexey Stankovskiy, Holly Trellue, Stefano Vaccaro, Vanessa Vallet, Marc Verwerft, Gašper Žerovnik, and Anders Sjöland, "Benchmark Exercise for Spent Nuclear Fuel Decay Heat," Nuclear Science and Engineering, 196(9), 1125–1145 (September 2022).

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).

J. Eysermans, M. Verwerft, K. Govers, R. Ichou, G. Ilas, U. Meryturek, N. Messaoudi, P. Romojaro and N. Slosse, “REGAL International Program: Analysis of Experimental Data for Depletion Code Validation,” Annals of Nuclear Energy, 172 (July 2022). 

W. J. Marshall, M. N. Dupont, T. M. Greene, A. Lang, A. M. Shaw, J. B. Clarity, and E. M. Saylor, “Expansion of the ORNL VALID Library,” Proceedings of Nuclear Criticality Division Topical Meeting (NCSD 2022), pp. 228–237, Anaheim, California, June 12–16, 2022.

W.J. Marshall, A. Lang, E. M. Saylor, and R. A. Hall, “Recent Assessments of Existing Transportation Packages for use with HALEU Material,” Proceedings of Nuclear Criticality Division Topical Meeting (NCSD 2022), pp. 325–334, Anaheim, California, June 12–16, 2022.

A. M. Shaw and J. B. Clarity "Criticality Safety Implications of Extended-Enrichment and Accident-Tolerant Fuel for Fresh Fuel Storage,"  Proceedings of Nuclear Criticality Safety Division Topical Meeting (NCSD 2022), pp. 335-344, Anaheim, California, June 12-16, 2022.

W. J. Marshall and T. M. Greene, “Applicability of ORCEF UF4/CF2 Experiments to Validation of 30-Inch UF6 Cylinders,” Proceedings of Nuclear Criticality Division Topical Meeting (NCSD 2022), pp. 648–657, Anaheim, California, June 12–16, 2022.

A. M. Shaw and W. J. Marshall, "Analysis of SCALE Criticality and Sensitivity Calculations for Reflected HEU Cylinders,"  Proceedings of Nuclear Criticality Safety Division Topical Meeting (NCSD 2022), pp. 666-674, Anaheim, California, June 12-16, 2022.

W. J. Marshall and T. M. Greene, “Performance of the Initial Implementation of the Shift Monte Carlo Code,” Proceedings of Nuclear Criticality Division Topical Meeting (NCSD 2022), pp. 754–763, Anaheim, California, June 12–16, 2022.

Michael B. R. Smith, M. Scott Greenwood, Noel B. Nelson, Nicholas A. Thompson, and Douglas E. Peplow, "Virtual Interaction with Physics Enhanced Reality (VIPER): Using Augmented Reality to Visualize and Interact with Ionizing Radiation Data," Transactions of the American Nuclear Society, 126, 805–808 (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]

Jianwei Hu, Ugur Mertyurek, and William A. Wieselquist, Assessment of Core Physics Characteristics of Extended Enrichment and Higher Burnup LWR Fuels using the Polaris/PARCS Two-Step Approach. Vol. I: PWR Fuel, ORNL/TM-2022/1831, UT-Battelle, LLC, Oak Ridge National Laboratory (June 2022).

Georgeta Radulescu and Peter Stefanovic, A Study on the Characteristics of the Radiation Source Terms of Spent Fuel and Various Non-Fuel Hardware for Shielding Applications, ORNL-SPR-2021/2373, UT-Battelle, LLC, Oak Ridge National Laboratory (May 2022).

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.

William A. Wieselquist, Friederike Bostelmann, Robert Kile, Austin Lo, Ugur Mertyurek, Alex Shaw, Steve Skutnik, and Erik Walker, "Overview of Recent SCALE Activities for Non-LWR Inventory and Decay Heat Analysis," Proceedings of International Conference on Physics of Reactors 2022 (PHYSOR 2022), pp. 2072-2081, Pittsburgh, Pennsylvania, May 15–20, 2022.

Joseph R. Burns, Germina Ilas, Ugur Mertyurek, and William  Wieselquist, "Comparison of LWR Decay Heat Calculations Using ANSI/ANS-5.1-2014 Standard and SCALE," Proceedings of  International Conference on Physics of Reactors 2022 (PHYSOR 2022), pp. 3562–3571, Pittsburgh, Pennsylvania, May 15-20, 2022.

Tara M. Pandya, Friederike Bostelmann, Matthew Jessee, and Javier Ortensi, "Two-step neutronics calculations with Shift and Griffin for advanced reactor systems," Annals of Nuclear Energy, 173 (May 2022). DOI: 10.1016/j.anucene.2022.109131.

Jesse M. Brown, Goran Arbanas, Dorothea Wiarda, and Andrew Holcomb, Bayesian Optimization Framework for Imperfect Data or Models, ORNL/TM-2022/2448, UT-Battelle, LLC, Oak Ridge National Laboratory (April 2022).

Nicholas Kucinski, Peter Stefanovic, Justin Clarity, and William Wieselquist, Impacts of LEU+ and HBU Fuel on Decay Heat and Radiation Source Term, ORNL/TM-2022/1841, UT-Battelle, LLC, Oak Ridge National Laboratory (April 2022).

Germina Ilas and Joseph R. Burns, "SCALE 6.2.4 Validation for Light Water Reactor Decay Heat Analysis," Nuclear Technology, 208, 403–413 (March 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]

A. M. Shaw and J. B. Clarity, Impacts of LEU+ and ATF on Fresh Fuel Storage Criticality Safety, ORNL/TM-2021/2330,  UT-Battelle, LLC, Oak Ridge National Laboratory (February 2022).

Ugur Mertyurek and Germina Ilas, "Nuclide Inventory Benchmark for BWR Spent Nuclear Fuel: Challenges in Evaluation of Modeling Data Assumptions and Uncertainties," Journal of Nuclear Engineering, 3(1), 18–36, (February 2022).

F. Bostelmann, D. Wiarda, G. Arbanas, and W. A. Wieselquist, “Extension of SCALE/Sampler’s sensitivity analysis,” Annals of Nuclear Energy, 165 (January 2022). DOI: 10.1016/j.anucene.2021.108641.

Prior Year 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]

Georgeta Radulescu, Kaushik Banerjee, Thomas M. Miller, and Douglas E. Peplow, "Skyshine Calculations for a Large Spent Nuclear Fuel Storage Facility with SCALE 6.2.3," Nuclear Technology, 207(11), 1768–1783 (November 2021).

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).

Germina Ilas and Joseph R. Burns, "LWR Decay Heat Analysis with SCALE 6.3 and ENDF/B-VIII.0 Nuclear Data Libraries," Presented at TopFuel2021 (virtually from Oak Ridge, Tennessee), October 24–28, 2021, Santander, Spain.

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, presented virtually from Oak Ridge, Tennessee, September 14, 2021.  [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).

Kang-Seog Kim and William A. Wieselquist, "Neutronic Characteristics of ENDF/B-VIII.0 Compared to ENDF/B-VII.1 for Light-Water Reactor Analysis," Journal of Nuclear Energy, 2(4), 318–335, (September 2021).

Germina Ilas and Joseph R. Burns, "SCALE 6.2.4 Validation for Light Water Reactor Decay Heat Analysis," Nuclear Technology, 203(3), 403–413 (August 2021).

Georgeta Radulescu, Thomas Miller, Kaushik Banerjee, Douglas E. Peplow, Dose Rate Analysis of the WCS Consolidated Interim Storage Facility, ORNL/SPR-2019/1070, UT-Battelle, LLC, Oak Ridge National Laboratory (August 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]

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).

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 29, 2021. [supporting files].

Douglas E. Peplow, Gregory G. Davidson, Cihangir Celik, Elliot D. Biondo, Alexadra C. Hackett, William R. Ray, Daniel E. Archer, James M. Ghawaly, Jr., Andrew D. Nicholson, Michael J. Willis, Brian J. Quister, Mark S. Bandstra, Ross E. Meyer, Chun Ho Chow, Ian R. Steward, and Jeffrey O. Johnson, Monte Carlo Simulation of Background and Source Measurements with CSG and CAD Geometries, ORNL/TM-2021/2078, UT-Battelle, LLC, Oak Ridge National Laboratory (June 2021).

G. Ilas and B. Hiscox, "Validation of SCALE 6.2.4 and ENDF/B-VII.1 Data Libraries for Nuclide Inventory Analysis in PWR Used Fuel," Transactions of the American Nuclear Society, 124, 552–554 (June 2021).

Mathieu N. Dupont, Douglas E. Peplow, Cihangir Celik, Georgeta Radulescu, William A. Wieselquist, "Overview of the 2020 SCALE 6.2.4 Validation Report for Radiation Shielding Applications," Transactions of the American Nuclear Society, 124, 639–642 (June 2021).

Robert Hall, Ryan Sweet, Randy Belles, and William A. Wieselquist, Extended-Enrichment Accident-Tolerant LWR Fuel Isotopic and Lattice Parameter Trends, ORNL/TM-2021/1961, UT-Battelle, LLC, Oak Ridge National Laboratory (March 2021). [supporting files]

Riley Cumberland, Ryan Sweet, Ugur Mertyurek, Robert Hall, and William A. Wieselquist, Isotopic and Fuel Lattice Parameter Trends in Extended Enrichment and Higher Burnup LWR Fuel Vol. II: BWR Fuel, ORNL/TM-2020/1835, UT-Battelle, LLC, Oak Ridge National Laboratory (March 2021). [supporting files]

Robert Hall, Riley Cumberland, Ryan Sweet, and William A. Wieselquist, Isotopic and Fuel Lattice Parameter Trends in Extended Enrichment and Higher Burnup LWR Fuel Vol. I: PWR Fuel, ORNL/TM-2020/1833, UT-Battelle, LLC, Oak Ridge National Laboratory (February 2021). [supporting files]

Ugur Mertyurek, Matthew Jessee, and Benjamin Betzler, "Lattice physics calculations using the embedded self-shielding method in Polaris, Part II: Benchmark assessment," Annals of Nuclear Energy, 150 (January 2021). DOI: 10.1016/j.anucene.2020.107829.

Matthew Jessee, William Wieselquist, Ugur Mertyurek, Kang Seog Kim, Thomas Evans, Steven Hamilton, and Cole Gentry, "Lattice physics calculations using the embedded self-shielding method in Polaris, Part I: Methods and implementation," Annals of Nuclear Energy, 150 (January 2021). DOI: 10.1016/j.anucene.2020.107830. 

J. Hu, G. Ilas, and I. C. Gauld, Analysis of PNAR spent fuel safeguards measurements using the ORIGEN data analysis module, ORNL/TM-2020/1834, UT-Battelle, LLC, Oak Ridge National Laboratory (2020). 

Kursat Bekar, Justin Clarity, Mathieu Dupont, Robert Lefebvre, William Marshall, and Ellen Saylor, KENO-VI Primer: Performing Calculations using SCALE’s Criticality Safety Analysis Sequence (CSAS6) with Fulcrum, ORNL/TM-2020/1601, UT-Battelle, LLC, Oak Ridge National Laboratory (December 2020). [supporting files]

Kursat Bekar, Justin Clarity, Mathieu Dupont, Robert Lefebvre, William Marshall, and Ellen Saylor, KENO V.a Primer: Performing Calculations using SCALE’s Criticality Safety Analysis Sequence (CSAS5) with Fulcrum, ORNL/TM-2020/1664, UT-Battelle, LLC, Oak Ridge National Laboratory (December 2020) .[supporting files]

A. Rivas, J. Hou, and G. Ilas, “Preliminary Benchmark Calculations of Spent Nuclear Fuel Isotopic Compositions Using BWR Assay Data,” Transactions of the American Nuclear Society, 123, 1365–1368 (November 2020). 

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 (November 2020).  DOI: 10.1016/j.anucene.2020.107673.

Robert Hall, B.J. Marshall, and William A. Wieselquist, Assessment of Existing Transportation Packages for Use with HALEU, ORNL/TM-2020/1725, UT-Battelle, LLC, Oak Ridge National Laboratory (September 2020). [supporting files]

Georgeta Radulescu and Kaushik Banerjee, Best Practices for Shielding Analyses of Activated Metals and Spent Resins from Reactor Operation, ORNL/SPR-2020/1586, UT-Battelle, LLC, Oak Ridge National Laboratory (September 2020).

Andrew D. Nicholson, Douglas E. Peplow, James M. Ghawaly, Michael J. Willis, and Daniel E. Archer, "Generation of Synthetic Data for a Radiation Detection Algorithm Competition," IEEE Transactions on Nuclear Science, 67(8), 1968–1975 (August 2020).

H. Akkurt, H. Liljenfeldt, G. Ilas, S. Baker, and K. Fuhr, Phenomena Identification and Ranking Table (PIRT) for Decay Heat: Review of Current Status and Recommendations for Future Needs, Product ID 3002018440, Electric Power Research Institute (July 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 (June 2020). DOI: 10.1016/j.anucene.2019.107102.

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).

J. Hu, I.C. Gauld, S. Vaccaro, T. Honkamaa, and G. Ilas, "Validation of ORIGEN for VVER-440 Spent Fuel with Application to Fork Detector Safeguards Measurements,” ESARDA Bulletin, No.60, p. 28–43 (June 2020).

W. A. Wieselquist, R. A. Lefebvre, and M. A. Jessee, Eds., SCALE Code System, ORNL/TM-2005/39, Version 6.2.4, UT-Battelle, LLC, Oak Ridge National Laboratory (April 2020). Available from Radiation Safety Information Computational Center as CCC-834.

Briana Hiscox, Benjamin Betzler, Vladimir Sobes, and William J. Marshall, "Neutronic Benchmarking of Small Gas-Cooled Systems," Proceedings of the PHYSOR 2020, Cambridge, United Kingdom, March 29–April 2, 2020.  

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  Cambridge, United Kingdom, March 29–April 2 2020. 

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). 

Michael B. R. Smith and Douglas E. Peplow, "Official Release of The Radioisotope Power System Dose Estimation Tool (RPS-DET)," Proceedings of the 2020 IEEE Aerospace Conference, pp. 1–6, Big Sky, Montana, March 7–14, 2020.

Dongli Huang, Ugur Mertyurek, and Hany Abdel-Khalik, "Verification of the Sensitivity and Uncertainty-based criticality Safety Validation Techniques: ORNL’s SCALE Case Study," Nuclear Engineering and Design, 361 (February 2020). DOI: 10.1016/j.nucengdes.2020.110571.

D. Wiarda, et al, Specifications for the Generalised Nuclear Database Structure (GNDS), Nuclear Energy Agency Organisation for Economic Co-operation and Development (2020).

James M. Ghawaly Jr., Andrew D. Nicholson, Douglas E. Peplow, Christine M. Anderson-Cook, Kary L. Myers, Daniel E. Archer, Michael J. Willis, and Brian J. Quitter, "Data for training and testing radiation detection algorithms in an urban environment," Scientific Data, 7, 328 (2020).

K. Bekar, S. Johnson, C. Perfetti, B. Langley, T. Greene, W. Marshall, W. Wieselquist, M. Jessee, and B. Rearden, Iterated Fission Probability Sensitivity Capability in SCALE via Shift, ORNL/TM-2020/4, UT-Battelle, LLC, Oak Ridge National Laboratory (December 2019).

I. Duhamel, J. L. Alwin, F. B. Brown, M. E. Rising, K. Y. Spencer, D. Heinrichs, S. Kim, W. J. Marshall, and E. M. Saylor, “International Criticality Benchmark Comparison for Nuclear Data Validation,” Transactions of the American Nuclear Society, 121, 873–876 (November 2019). [pdf]

W. A. Wieselquist, “Recent SCALE Activities Within the Nuclear Criticality Safety Program,” Transactions of the American Nuclear Society, 121, 877–880 (November 2019).  

W. J. Marshall, “Bias Between ENDF/B-VIII.0 and ENDF/B-VII.1 for LEU Pin Array Systems,” Transactions of the American Nuclear Society, 121, 952–955 (November 2019). 

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.  

V. Sobes, W. J. Marshall, D. Wiarda, F. Bostelmann, A. Holcomb, and B. T. Rearden, “ENDF/B-VIII.0 Augmented Covariance Data: The First Iteration,” Transactions of the American Nuclear Society, 121, 1365–1368 (November 2019).  [pdf]

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).  

K. Bledsoe, G. Ilas and S. Hogle, “Application of Depletion Perturbation Theory for Sensitivity Analysis in the High Flux Isotope Reactor,” Transactions of the American Nuclear Society, 121, 1453–1456 (November 2019). [pdf]

B. T. Rearden, “Some Innovations of Dr. Mark Williams for the Practical Application of Sensitivity and Uncertainty Analysis to Reactor Analysis and Criticality Safety,” Transactions of the American Nuclear Society, 121, 1479–1483 (November 2019). [pdf]

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. 

C. M. Perfetti and B. T. Rearden, “Estimating Code Biases for Criticality Safety Applications with Few Relevant Benchmarks,” Nuclear Science Engineering 193(10), 1090–1128 (October 2019). 

B. R. Betzler, D. Chandler, D. H. Cook, E. E. Davidson, and G. Ilas, “Design Optimization Methods for High-Performance Research Reactor Core Design,” Nuclear Engineering and Design, 352 (October 2019). DOI: 10.1016/j.nucengdes.2019.110167. 

Kaushik Banerjee, Cihangir Celik, Gregory Davidson, Thomas M. Evans, Bradley T. Rearden, and William A. Wieselquist, The MAVRIC-Shift Sequence in SCALE for Radiation Transport and Shielding Calculations with Automated Variance Reduction and Parallel Computing, ORNL/TM-2019/1358, UT-Battelle, LLC, Oak Ridge National Laboratory (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, Seattle, Washington, September 22–26, 2019.

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, Seattle, Washington, September 22–26, 2019.

W. J. Marshall, J. B. Clarity, J. Yang, U. Mertyurek, M. A. Jessee, and B. T. Rearden, “Initial Application of TSUNAMI for Validation of Advanced Fuel Systems,” Proceedings of ICNC 2019 – 11th International Conference on Nuclear Criticality Safety, Paris, France, September 15–20, 2019. 

W. J. Marshall, E. M. Saylor, A. M. Holcomb, D. Wiarda, and T. M. Greene, “Validation of KENO V.a and KENO-VI in SCALE 6.3 Beta 3 Using ENDF/B-VII.1 and ENDF/B-VIII Libraries,” Proceedings of 11th International Conference on Nuclear Criticality Safety (ICNC 2019), Paris, France, September 15–20, 2019. 

F. Sommer, W. J. Marshall, and M. Stuke, “Correlation of HST-001 due to Uncertain Technical Parameters – Comparison of Results from SUnCISTT, Sampler, and DICE,” Proceedings of ICNC 2019 – 11th International Conference on Nuclear Criticality Safety, Paris, France, September 15–20, 2019.

W. J. Marshall, B. J. Ade, I. C. Gauld, G. Ilas, U. Mertyurek, J. B. Clarity, G. Radulescu, B. R. Betzler, S. M. Bowman, and J. S. Martinez-Gonzalez, “Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory,” Proceedings of 11th International Conference on Nuclear Criticality Safety 2019 (ICNC 2019), Paris, France, September 15–20, 2019.

M. Stuke, A. Hoefer, O. Buss, M. Chernykh, G. Dobson, J. Dyrda, T. Ivanova, N. Leclaire, W. J. Marshall, D. Mennerdahl, B. T. Rearden, P. Smith, F. Sommer, and S. Tittelbach, “UACSA Phase IV: Role of Integral Experiment Covariance Data for Criticality Safety Validation – Summary of Selected Results,” Proceedings of 11th International Conference on Nuclear Criticality Safety 2019 (ICNC 2019), Paris, France, September 15–20, 2019.

I. Duhamel, J. L. Alwin, F. B. Brown, M. E. Rising, K. Y. Spencer, D. Heinrichs, S. Kim, W. J. Marshall, and E. M. Saylor, “International Benchmarks Intercomparison Study for Codes and Nuclear Data Validation,” Proceedings of ICNC 2019 – 11th International Conference on Nuclear Criticality Safety, Paris, France, September 15–20, 2019.

I. Variansyah, B. R. Betzler, D. Chandler, G. Ilas, and W. R. Martin, “A Metaheuristic Optimization Tool for High Flux Isotope Reactor Low-Enriched Uranium Core Design,” Proceedings of International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering, Portland, Oregon, August 25–29, 2019. 

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, Portland, Oregon, August 25–29, 2019.

F. Bostelmann, D. Wiarda, W. A. Wieselquist, and B. T. Rearden, “SCALE/Sampler Sensitivity Indices,” Proceedings of International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering, pp. 2371–2380, Portland, Oregon, August 25–29, 2019

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, Portland, Oregon, August 25–29, 2019. 

S. Simunovic, J. W. McMurray, T. M. Besmann, E. E. Moore, K. T. Clarno, W. A. Wieselquist, and M. H. A. Piro, Depletion, Chemical Reaction and Transport in High Burnup Nuclear Fuel, ORNL/SPR-2019/1104, UT-Battelle, LLC, Oak Ridge National Laboratory (August 2019).

Michael B. R. Smith, Douglas E. Peplow, Robert A. Lefebvre, and William A. Wieselquist, Radioisotope Power System Dose Estimation Tool (RPS-DET) User Manual, ORNL/TM-2019/1249, UT-Battelle, LLC, Oak Ridge National Laboratory (August 2019).

D. Chandler, B. Betzler, D. Cook, G. Ilas, and D. Renfro, “Neutronic and Thermal-Hydraulic Feasibility Studies for High Flux Isotope Reactor Conversion to Low-Enriched Uranium Silicide Dispersion Fuel,” Annals of Nuclear Energy, 130, 277–292 (August 2019). 

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, Palm Desert, California, July 14–18, 2019. 

Mathew W. Swinney and Jackson N. Wagner, "Preliminary Validation of the Shift Monte Carlo Code for Fixed-Source Radiation Transport Problems," Nuclear Technology, 206(1), 107–125 (July 2019). 

Cihangir Celik, Douglas E. Peplow, Gregory G. Davidson, and Mathew W. Swinney, "A Directional Detector Response Function for Anisotropic Detectors," Nuclear Science and Engineering, 193(12), 1355–1370 (July 2019).

W. J. Marshall, J. Yang, U. Mertyurek, and M. A. Jessee, “Preliminary TSUNAMI Assessment of the Impact of Accident Tolerant Fuel Concepts on Reactor Physics Validation,” Transactions of the American Nuclear Society, 120, 500–503 (June 2019). 

B. T. Rearden, W. J. Marshall, J. B. Clarity, A. M. Holcomb, F. Bostelmann, and J. M. Scaglione, “Initial Investigations of the Criticality Safety Validation Basis for HA-LEU Transportation,” Transactions of the American Nuclear Society, 120, 517–520 (June 2019).

W. J. Marshall, J. B. Clarity, and S. M. Bowman, “Validation of keff Calculations for Extended BWR Burnup Credit Calculations,” Transactions of the American Nuclear Society, 120, 554–557 (June 2019). 

Jackson N. Wagner and Douglas E. Peplow, "Validation of the Shift Monte Carlo Code – Neutron Field Measurements in a Concrete Labyrinth," Transactions of the American Nuclear Society, 120, 763–766 (2019).

B. T. Rearden, F. Bostelmann, V. Sobes, and A. M. Holcomb, “Overview of Nuclear Data Needs for Nuclear Energy Applications,” Transactions of the American Nuclear Society, 120, 989–992 (June 2019). 

Majdi I. Radaideh, William A. Wieselquist, Tomasz Kozlowski, "A new framework for sampling-based uncertainty quantification of the six-group reactor kinetic parameters," Annals of Nuclear Energy, 127, 1–11 (May 2019).

Majdi I. Radaideh, Tomasz Kozlowski, William A. Wieselquist, and Matthew A. Jessee, "Data-Driven and Precursor-Group Uncertainty Propagation of Lattice Kinetic Parameters in UAM Benchmark," Hindawi (May 2019). DOI: 10.1155/2019/3702014.

K. Zeng, J. Hou, K. Ivanov, and M. Jessee, “Uncertainty Quantification on Pressurized Water Reactor Coupled Core Simulation Using Stochastic Sampling Method,” Proceedings of ANS Best Estimate Plus Uncertainty International Conference (BEPU 2018), Real Collegio, Lucca, Italy, May 13–19, 2019. 

I. C. Gauld and U. Mertyurek, "Validation of BWR Spent Nuclear Fuel Isotopic Predictions with Applications to Burnup Credit," Nuclear Engineering and Design, 345, 110–124 (April 2019).

Germina Ilas, Review of Experimental Assay Data for PWR Spent Fuel, ORNL/SPR-2019/1143, UT-Battelle, LLC, Oak Ridge National Laboratory (April 2019). 

I.C. Gauld and U. Mertyurek, "Validation of BWR Spent Nuclear Fuel Isotopic Predictions with Applications to Burnup Credit," Nuclear Engineering and Design, 345, 110–124 (April 2019).

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). 

M. B. R. Smith, C. Whiting and C. Barklay, “Nuclear Considerations for the Application of Lanthanum Telluride in Future Radioisotope Power Systems,” Proceedings of 2019 IEEE Aerospace Conference, pp. 1–11, Big Sky, Montana, March 2–9, 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).

W. Wieselquist, M. Williams, D. Wiarda, M. Pigni, and U. Mertyurek, Overview of Nuclear Data Uncertainty in Scale and Application to Light Water Reactor Uncertainty Analysis, NUREG/CR-7249 (ORNL/TM-2017/706), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (December 2018). 

W. J. Marshall, J. B. Clarity, and S. M. Bowman, Validation of keff Calculations for Extended BWR Burnup Credit, NUREG/CR-7252 (ORNL/TM-2018/797), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, (December 2018). 

I. Gauld and U. Mertyurek, Margins for Uncertainty in the Predicted Spent Fuel Isotopic Inventories for BWR Burnup Credit, NUREG/CR-7251 (ORNL/TM-2018/782), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, (December 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). 

W. J. Marshall and A. M. Holcomb, “A Testing Trifecta: Data, Codes, and Evaluations,” Transactions of the American Nuclear Society, 119, 724–727  (November 2018). 

W. J. Marshall, J. B. Clarity, and E. M. Saylor, “Sensitivity Calculations for Systems with Fissionable Reflector Materials Using TSUNAMI,” Transactions of the American Nuclear Society, 119, 787–790 (2018). 

E. L. Jones, J. B. Clarity, W. J. Marshall, B. T. Rearden, and G. I. Maldonado, “A Case Study in the Application of TSUNAMI-3D – Part 3, Continuous Energy – Iterative Fission Probability Method,” Transactions of  the American Nuclear Society, 119, 845–848 (2018).  

C. M. Perfetti, V. Sobes, A. M. Holcomb, D. Wiarda, M. L. Williams, and B. T. Rearden, “SCALE Resonance Parameter Sensitivity Coefficient Calculations,” Transactions of the American Nuclear Society, 119, 849–851 (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).   

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).

E. M. Saylor, W. J. Marshall, J. B. Clarity, Z. J. Clifton, and B. T. Rearden, Criticality Safety Validation of SCALE 6.2.2, ORNL/TM-2018/884, UT-Battelle, LLC, Oak Ridge National Laboratory (September 2018).

William Wieselquist, Ian Gauld, and Maro Pigni, "Prioritizing Nuclear Data Needs Using Uncertainty Analysis," Proceedings of INMM  59th Annual Meeting, Baltimore, Maryland, July 2018.

E. M. Saylor, W. J. Marshall, Z. J. Clifton, J. B. Clarity, and B. T. Rearden, “Validation of KENO V.A and KENO-VI in SCALE 6.2.2 Using ENDF/B-VII.0 and ENDF/B-VII.1 Libraries,” Transactions of the American Nuclear Society, 118, 571–574 (June 2018). 

Georgeta Radulescu, Thomas M. Miller, Kaushik Banerjee, and Douglas E. Peplow, "Detailed SCALE Dose Rate Evaluations for a Consolidated Interim Spent Nuclear Fuel Storage Facility," Transactions of the American Nuclear Society, 118, 765–768 (June 2018).

W. J. Marshall and E. M. Saylor, “Enhanced Engineering Analyses with Visualization of Geometry and Mesh-Based Data in Fulcrum,” Transactions of the American Nuclear Society, 118, 987–990 (June 2018).

C. A. Gentry, M. A. Jessee, and K. S. Kim, “Improvements in the Polaris Implementation of the Embedded Self-Shielding Method,” Proceedings of PHYSOR 2018 - Reactor Physics Paving the Way Toward More Efficient Systems, pp. 1503–1513, Cancun, Mexico, April 22–26, 2018.

D. Chandler, B. Betzler, D. Cook, G. Ilas, and D. Renfro, “Neutronic and Thermal-Hydraulic Feasibility Studies for High Flux Isotope Reactor Conversion to Low-Enriched Uranium U3SI2-AL Fuel,” Proceedings of PHYSOR 2018 - Physics Paving the Way Toward More Efficient Systems, pp. 2406–2417, Cancun, Mexico, April 22–26, 2018. 

B. R. Betzler, D. Chandler, D. H. Cook, E. E. Davidson, and G. Ilas, “High Flux Isotope Reactor Low-Enriched Uranium Core Design Optimization Studies,” Proceedings of PHYSOR 2018 -  Reactor Physics Paving the Way Toward More Efficient Systems, Cancun, Mexico, April 22–26, 2018. 

G. G. Davidson, T. M. Pandya, S. R. Johnson, T. M. Evans, A. E. Isotalo, C. A. Gentry, and W. A. Wieselquist, “Nuclide Depletion Capabilities in the Shift Monte Carlo Code,” Annals of Nuclear Energy, 114, 259–276 (April 2018). 

S. W. D. Hart, A. M. Holcomb, W. Wieselquist, and D. Wiarda, Improvements in ORIGEN Resource Readers, ORNL/LTR-2018/489, UT-Battelle, LLC, Oak Ridge National Laboratory Report (March 2018).

B. J. Ade, B. J. Marshall, G. Ilas, B. R. Betzler, and S. M. Bowman, Impact of Reactor Operating Parameters on Extended BWR Burnup Credit, NUREG/CR-7240 (ORNL/TM - 2017/46), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (January 2018). 

Matthew A. Jessee, William A. Wieselquist, Cole A. Gentry, and Ugur Mertyurek, "BWR Geometry Enhancements for the Polaris Lattice Physics Code," Transactions of the American Nuclear Society, 117, 1301–1305 (November 2017).

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).

Ian C. Gauld, Mark L. Williams, Franco Michel-Sendis, and James S. Martinez, "Integral nuclear data validation using experimental spent nuclear fuel compositions," Nuclear Engineering and Technology, 49(6) 1226–1233 (September 2017).

Brian J. Ade, William (B.J.) Marshall, and Stephen M. Bowman, ”Impact of Assembly-Specific Conditions on BWR Burnup Credit,” Proceedings of ANS 2017 Nuclear Criticality Safety Division Topical Meeting, Carlsbad, New Mexico, September 2017.

J. Hu, J. M. Giaquinto, I. C. Gauld, G. Ilas, and T. J. Keever, "Analysis of new measurements of Calvert Cliffs spent fuel samples using SCALE 6.2," Annals of Nuclear Energy, 106, 221–234 (August 2017). 

G. Ilas and H. Liljenfeldt, "Decay heat uncertainty for BWR used fuel due to modeling and nuclear data uncertainties,” Nuclear Engineering and Design, 319, 176–184 (August 2017).

D. E. Peplow, "A Comparison of the FW-CADIS and MR-CADIS Variance Reduction Methods," Transactions of the American Nuclear Society, 116, 540–543 (June 2017). [pdf]

D. E. Peplow, M. W. Swinney, G. G. Davidson, A. D. Nicholson and B. W. Patton, "Initial Modeling of Urban Search Measurements," Transactions of the American Nuclear Society, 116, 913–916 (June 2017). [pdf]

Brian J. Ade, William (B.J.) Marshall, Germina Ilas, Benjamin R. Betzler, and Stephen M. Bowman, Impact of Operating Parameters on Extended BWR Burnup Credit, NUREG/CR-7240 (ORNL/TM-2017/46), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (June 2017).

K. S. Kim, M. L. Williams, D. Wiarda, and U. Mertyurek, "Automatic Coarse Energy Group Structure Optimization by Minimizing Reaction Rate Differences for the SCALE and CASL Code Systems," Proceedings of M&C 2017 - International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Jeju, South Korea, April 16–20, 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). 

Ryan N. Bratton, Matt A. Jessee, William A. Wieselquist, and Kostadin N. Ivanov, "Rod Internal Pressure Distribution and Uncertainty Analysis Using FRAPCON," Nuclear Technology, 197(1), 47–63 (February 2017).

A. E. Isotalo, G. G. Davidson, T. M. Pandya, W. A. Wieselquist, and S. R. Johnson, "Flux Renormalization in Contant Power Burnup Calculations," Annals of Nuclear Energy, 96, 148–157 (October 2016). 

G. Ilas, B. Betzler, and B. Ade, “Impact of Reactor Operating Parameters on Cask Reactivity in BWR Burnup Credit”, Proceedings of the 18th International Symposium on the  Packaging and Transportation of Radioactive Materials (PATRAM 2016), Kobe, Japan, September 18–22, 2016. [pdf]

William (B.J.) Marshall, Brian J. Ade, Stephen Bowman, and Jesus S. Martinez-Gonzalez, Axial Moderator Density Distributions, Control Blade Usage, and Axial Burnup Distributions for Extended BWR Burnup Credit, NUREG/CR-7224 (ORNL/TM-2015/544), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (August 2016).

K. S. Kim, SUBGR: A Program to Generate Subgroup Data for the Subgroup Resonance Self-Shielding Calculation, ORNL/TM-2016/154, UT-Battelle, LLC, Oak Ridge National Laboratory (June 2016). 

Brian Ade, Andrew Worrall, Jeffrey Powers, and Steve Bowman, "Analysis of Key Safety Metrics of Thorium Utilization in LWRs," Nuclear Technology, 194, 162–177 (May 2016).

Joshua Peterson, Eva Sunny, William Wieselquist, and Andrew Worrall, "Generating Cross Sections for ORION Fuel Cycle Models," Proceedings of PHYSOR 2016, Sun Valley, Idaho, May 1–5, 2016. [pdf]

William A. Wieselquist, Ian C. Gauld, Shane W. Hart, Mark L. Williams, Dorothea A. Wiarda, and Aarno E. Isotalo, "New Features of the ORIGEN Transmutation Code in SCALE 6.2," Proceedings of PHYSOR 2016, Sun Valley, Idaho, May 1–5, 2016. [pdf]

K. S. Kim, J. Hu, and C. A. Gentry, "Embedded Self-Shielding Method Applied To Doubly Heterogeneous Fully Ceramic Micro-Encapsulated Fuels," Proceedings of PHYSOR 2016, Sun Valley, Idaho, May 1–5, 2016. [pdf]

M. L. Williams, D. Wiarda, K. S. Kim, and M. A. Jessee, "Multigroup Data Processing for the Embedded Self-Shielding Method in SCALE," Proceedings of PHYSOR 2016, Sun Valley, Idaho, May 1–5, 2016.[pdf]

Brian J. Ade, William J. Marshall, and Jesus S. Martinez, "Effect of Control Blade History, and Axial Coolant Density and Burnup Profiles on BWR Burnup Credit," Proceedings of PHYSOR 2016, Sun Valley, Idaho, May 1–5, 2016. 

Brian J. Ade, William J. Marshall, Stephen Bowman, and Jesus S. Martinez, "Effects of Control Blade History, Axial Coolant Density Profiles, and Axial Burnup Profiles on BWR Burnup Credit," Proceedings of PHYSOR 2016, Sun Valley, Idaho, May 1–5, 2016. [pdf]

Brian J. Ade, "Radial Variation of Burnup anda Source Terms in High Burnup LWR Fuel," Proceedings of PHYSOR 2016, Sun Valley, Idaho, May 1–5, 2016. 

D. Wiarda, M. E. Dunn, N. M. Greene, C. Celik, and L. M. Petrie, AMPX-6: A Modular Code System for Processing ENDF/B, ORNL/TM-2016/43, UT-Battelle, LLC, Oak Ridge National Laboratory (April 2016). Available from Radiation Safety Information Computational Center as CCC-834.

W. A. Wieselquist, A. B. Thompson, J. L. Peterson, and S. M. Bowman, ORIGAMI Automator Primer: Automated ORIGEN Source Terms and Spent Fuel Storage Pool Analysis, ORNL/TM-2015/409, UT-Battelle, LLC, Oak Ridge National Laboratory (April 2016).

Ugur Mertyurek and Ian C. Gauld, "Development of ORIGEN Libraries for Mixed Oxide (MOX) Fuel Assembly Designs," Nuclear Engineering and Design, 297, 220–230 (February 2016).

I. C. Gauld, J. M. Giaquinto, J. S. Delashmitt, J. Hu, G. Ilas, T.J. Haverlock, and C. Romano, "Re-evaluation of Spent Nuclear Fuel Assay Data for the Three Mile Island Unit 1 Reactor and Application to Code Validation," Annals of Nuclear Energy, 87, 267–281 (January 2016).

A. E. Isotalo and W. A. Wieselquist, "A method for including external feed in depletion calculations with CRAM and implementation into ORIGEN," Annals of Nuclear Energy, 85, 68–77 (November 2015).

B. T. Rearden, K. B. Bekar, C. Celik, K. T. Clarno, M. E. Dunn, S. W. D. Hart, A. M. Ibrahim, S. R. Johnson, B. R. Langley, J. P. Lefebvre, R. A. Lefebvre, W. J. Marshall, U. Mertyurek, D. E. Mueller, D. E. Peplow, C. M. Perfetti, L. M. Petrie, Jr., A. B. Thompson, D. Wiarda, W. A. Wieselquist, and M. L. Williams, "Criticality Safety Enhancements For Scale 6.2 and Beyond," Proceedings of International Cooperation in Nuclear Criticality Safety (ICNC 2015), pp. 1255–1269, Charlotte, North Carolina, September 13–17, 2015.

B. J. Ade, W. J. Marshall, S. M. Bowman, I. C. Gauld, G. Ilas, and J. S. Martinez, "Coolant Density and Control Blade History Effects in Extended BWR Burnup Credit", Proceedings of International Cooperation in Nuclear Criticality Safety (ICNC 2015), Charlotte, North Carolina, September 13–17, 2015.

B. T. Rearden, L. M. Petrie, D. E. Peplow, K. B. Bekar, D. Wiarda, C. Celik, C. M. Perfetti, A. M. Ibrahim, S. W. D. Hart, M. E. Dunn, and W. J. Marshall, “Monte Carlo Capabilities of the SCALE Code System,” Annals of Nuclear Energy, 82, 130–141 (2015).  

B. J. Marshall, B. J. Ade, S. M. Bowman, I. C. Gauld, G. Ilas, U. Mertyurek, and G. Radulescu, Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems, NUREG/CR-7194 (ORNL/TM-2014/240), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (April 2015). 

Brian Ade, Andrew Worrall, Jeffrey Powers, and Steve Bowman, "Safety Issues of Thorium Utilization in Commercial LWRs," Transactions of the American Nuclear Society, 111, 277–279 (November 2014).

B. T. Rearden, L. M. Petrie, D. E. Peplow, K. B. Bekar, D. Wiarda, C. Celik, C. M. Perfetti, M. E.  Dunn and S. W. D. Hart, “Enhancements In Continuous-Energy Monte Carlo Capabilities for SCALE 6.2,” Proceedings of PHYSOR 2014 - The Role of Reactor Physics toward a Sustainable Future September 28–October 3, 2014, Kyoto, Japan.

Matthew A. Jessee, William A. Wieselquist, Thomas M. Evans, Steven P. Hamilton, Joshua A. Jarrell, Kang Seog Kim, Jordan P. Lefebvre, Robert A. Lefebvre, Ugur Mertyurek, Adam B. Thompson, and Mark L. Williams, "POLARIS: A New Two-Dimensional Lattice Physics Analysis Capability for the SCALE Code System," Proceedings of PHYSOR 2014 - The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, September 28–October 3, 2014.

Ryan N. Bratton, Kostadin Ivanov, Matthew A. Jessee, William A. Wieselquist, "Bias and Uncertainty Assessment of Pressurized Water Reactor Fuel Isotopics," Proceedings of PHYSOR 2014 - The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, September 28–October 3, 2014.

G. Radulescu, D. E. Peplow, Mark L. Williams, and J. M. Scaglione, “Dose Rate Analysis of As-Loaded Spent Nuclear Fuel Casks,” Proceedings of the American Nuclear Society Topical Meeting of the Radiation Protection and Shielding Division, Knoxville, Tennessee, September 14–18, 2014, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2014). [pdf]

D. E. Peplow, G. Radulescu, M. L. Williams, and R. A. Lefebvre, “SCALE Enhancements for Detailed Cask Dose Rate Analysis,” Proceedings of the American Nuclear Society Topical Meeting of the Radiation Protection and Shielding Division, Knoxville, Tennessee, September 14–18, 2014, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2014). [pdf]

G. Radulescu, R. A. Lefebvre, D. E. Peplow, M. L. Williams, and J. M. Scaglione, "Dose Rate Analysis Capability for Actual Spent Fuel Transportation Cask Contents,"Proceedings of the Institute of Nuclear Materials Management (INMM) 55th Annual Meeting, Atlanta, Georgia, July 20–24, 2014. [pdf]

I. C. Gauld, M. T. Pigni, and G. Ilas, "Validation and testing of ENDF/B-VII decay data,” Nuclear Data Sheets, 120, 33–36 (June 2014).

M. L. Williams, G. Ilas, W.J. Marshall, and B.T. Rearden, "Applications of nuclear data covariances to criticality safety and spent fuel characterization,” Nuclear Data Sheets, 118, 341–345 (April 2014).

J. C. Wagner, D. E. Peplow, and S. W. Mosher, “FW-CADIS Method for Global and Semi-Global Variance Reduction of Monte Carlo Radiation Transport Calculations,” Nuclear Science and Engineering, 176(1), 37–57 (March 2014).  

G. Radulescu, I. C. Gauld, G. Ilas, and J. C. Wagner, “Approach for validating actinide and fission product compositions for burnup credit criticality safety analyses,” Nuclear Technology, 188(2), 154–171 (February 2014).

Brian Ade, Andrew Worrall, Jeffrey Powers, Steve Bowman, George Flanagan, and Jess Gehin, Safety and Regulatory Issues of the Thorium Fuel Cycle, NUREG/CR-7176 (ORNL/TM-2013/543), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (February 2014).

G. Ilas, I. C. Gauld, and H. Liljenfeldt, "Validation of ORIGEN for LWR used fuel decay heat analysis with SCALE,” Nuclear Engineering and Design, 273, 58–67 (2014).

B. T. Rearden, M. E. Dunn, D. Wiarda, C. Celik, K. B. Bekar, M. L. Williams, D. E. Peplow, C. M. Perfetti, J. P. Lefebvre, F. Havluj, and K. J. Dugan, “SCALE and AMPX Advancements to Support NCS Applications,” Transactions of the American Nuclear Society, 109, 907–910 (November 2013).

W. A. Wieselquist, K. S. Kim, G. Ilas, and I. C. Gauld, “Comparison of burnup credit uncertainty quantification methods,” Proceedings of Topical Meeting on Nuclear Criticality Safety (NCSD 2013), Wilmington, North Carolina, September 29–October 3, 2013. [pdf]

K. B. Bekar, C. Celik, D. Wiarda, D. E. Peplow, B. T. Rearden, and M. E. Dunn, “Enhancements in Continuous-Energy Monte Carlo Capabilities in SCALE,” Proceedings of Topical Meeting on Nuclear Criticality Safety (NCSD 2013), Wilmington, North Carolina, September 29–October 3, 2013. [pdf]

T. M. Miller and D. E. Peplow, “Guidance Detailing Methods to Calculate Criticality Accident Alarm Detector Response and Coverage,” Proceedings of Topical Meeting on Nuclear Criticality Safety (NCSD 2013), Wilmington, North Carolina, September 29–October 3, 2013. [pdf]

B. T. Rearden, M. E. Dunn, D. Wiarda, C. Celik, K. Bekar, M. L. Williams, D. E. Peplow, C. M. Perfetti, I. C. Gauld, W. A. Wieselquist, J. P. Lefebvre, R. A. Lefebvre, F. Havlůj, S. E. Skutnik, and K. J. Dugan, “Overview of SCALE 6.2,” Proceedings of Topical Meeting on Nuclear Criticality Safety (NCSD 2013), Wilmington, North Carolina, September 29–October 3, 2013. [pdf]

C. McGraw and G. Ilas, "PWR ENDF/B-VII cross-section libraries for ORIGEN-ARP,” Nuclear Technology, 183(3), 436–445 (September 2013).

T. M. Miller and D. E. Peplow, Guide to Performing Computational Analysis of Criticality Accident Alarm Systems, ORNL/TM-2013/211, UT-Battelle, LLC, Oak Ridge National Laboratory (August 2013). [supporting files]

T. M. Miller and D. E. Peplow, “Corrected User Guidance to Perform Three-Dimensional Criticality Accident Alarm System Modeling with SCALE,” Transactions of the American Nuclear Society, 108, 498–501 (June 2013).

D. E. Peplow, “Comparison of Hybrid Methods for Global Variance Reduction in Shielding Calculations,” Proceedings of the 2013 International Conference on Mathematics & Computational Methods Applied to Nuclear Science and Engineering (M&C 2013), Sun Valley, Idaho, May 5–9, 2013. [pdf]

Dean Wang, Brian Ade, and Andrew Ward, Cross Section Generation Guidelines for TRACE-PARCS, NUREG/CR-7164 (ORNL/TM-2012/518), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (May 2013).

D. E. Peplow, T. M. Miller, B. W. Patton, and J. C. Wagner, “Hybrid Monte Carlo/Deterministic Methods for Accelerating Active Interrogation Modeling,” Nuclear Technology, 182(1), 63–74 (March 2013). 

M. Williams, G. Ilas, M. A. Jessee, B. T. Rearden, D. Wiarda, W. Zwermann, L. Gallner, M. Klein, B. Krzykacz-Hausmann, and A. Pautz, "A statistical sampling method for uncertainty analysis with SCALE and XSUSA,” Nuclear Technology, 183(3), 515–526 (2013).

W. J. Marshall and B.T. Rearden, Criticality Safety Validation of SCALE 6.1, ORNL/TM-2011/450, UT-Battelle, LLC, Oak Ridge National Laboratory (January 2013 Revised). [supporting files]

B. J. Ade, SCALE/TRITON Primer: A Primer for Light Water Reactor Lattice Physics Calculations, NUREG/CR-7041 (ORNL/TM-2011/21), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (November 2012). [TRITON Primer Sample Input Files]

K. S. Kim and M. L. Williams, "Preliminary Assessment of Resonance Interference Treatment by Using 0-D Slowing Down Calculation in the Embedded Self-Shielding Method,"  Transactions of the American Nuclear Society, 107, 1128–1131 (November 2012). [pdf]

G. Ilas, I. C. Gauld, and G. Radulescu, "Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE,” Annals of Nuclear Energy, 46, 43–55 (August 2012).

D. E. Peplow, S. W. Mosher, and T. M. Evans, Consistent Adjoint Driven Importance Sampling using Space, Energy and Angle, ORNL/TM-2012/7, UT-Battelle, LLC, Oak Ridge National Laboratory (August 2012).

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).

D. E. Peplow and L. L. Wetzel, “Methods for Detector Placement and Analysis of Criticality Accident Alarm System,” Transactions of the American Nuclear Society 106, 497–500 (June 2012). [pdf]

J. M. Risner, D. Wiarda, T. M. Miller, D. E. Peplow, B. W. Patton, M. E. Dunn, and B. T. Parks, “Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries,” Journal of AASTM International, 9(5), (May 2012).

J. M. Scaglione, D. E. Mueller, J. C. Wagner, and W. J. Marshall, An Approach for Validating Actinide and Fission Product Burnup Credit Credit Criticality Safety Analyses - Criticality (Keff) Predictions, NUREG/CR-7109 (ORNL/TM-2011/514), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (April 2012).  [supporting files] 

G. Radulescu, I.C. Gauld, G. Ilas, and J.C. Wagner, An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses - Isotopic Composition Predictions, NUREG/CR-7108 (ORNL/TM-2011/509), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (April 2012). 

B. T. Rearden, L. M. Petrie, D. E. Peplow, M. A. Jessee, D. Wiarda, M. L. Williams, R. A. Lefebvre, J. P. Lefebvre, I. C. Gauld, and S. Goluoglu, “Enhancements in SCALE 6.1,” Proceedings of PHYSOR 2012, Knoxville, Tennessee, April 15–20, 2012. [pdf]

A. M. Ibrahim, D. E. Peplow, J. C. Wagner, S. W. Mosher, and T. M. Evans, “Acceleration of Monte Carlo Criticality Calculations Using Deterministic-Based Starting Sources,” Proceedings of PHYSOR 2012, Knoxville, Tennessee, April 15–20, 2012. [pdf]

M. L. Williams and K. S. Kim, "The Embedded Self-Shielding Method," Proceedings of PHYSOR 2012, Knoxville, Tennessee, April 15–20, 2012. [pdf]

K. S. Kim and M. L. Williams, "The Method of Characteristics For 2-D Multigroup and Pointwise Transport Calculation in SCALE/CENTRM," Proceedings of PHYSOR 2012, Knoxville, Tennessee, April 15–20, 2012. [pdf]

J. M. Risner, D. Wiarda, M. E. Dunn, T. M. Miller, D. E. Peplow, and B. W. Patton, Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data, NUREG/CR-7045 (ORNL/TM 2011/12), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (September 2011).

Brian Ade and Ian Gauld, Decay Heat Calculations for PWR and BWR Assemblies Fueled with Uranium and Plutonium Mixed Oxide Fuel using SCALE, ORNL/TM-2011/290, UT-Battelle, LLC, Oak Ridge National Laboratory (September 2011).

J. C. Wagner, D. E. Peplow, S. W. Mosher, and T. M. Evans, “Review of Hybrid (Deterministic/Monte Carlo) Radiation Transport Methods, Codes, and Applications at Oak Ridge National Laboratory,” Progress in Nuclear Science and Technology, 2, 808–814 (2011).  

I. C. Gauld, G. Radulescu, G. Ilas, B. D. Murphy, M. L. Williams, and D. Wiarda, "Isotopic depletion and decay methods and analysis capabilities in SCALE," Nuclear Technology, 174, 69 (May 2011).

D. E. Peplow, “Monte Carlo Shielding Analysis Capabilities with MAVRIC,” Nuclear Technology, 174(2), 289–313 (May 2011).  

G. Ilas and I. C. Gauld, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - Vandellos II Reactor, NUREG/CR-7013 (ORNLITM-2009/321), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (January 2011).

I. C. Gauld, G. Ilas and G. Radulescu, Uncertainties in Predicted Isotopic Compositions for High Burnup PWR Spent Nuclear Fuel, NUREG/CR-7012 (ORNL/TM-2010/41), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (January 2011).

G. Ilas and R.T. Primm, III, "Methodology for simulating the irradiation of the control elements in HFIR,” Transactions of the American Nuclear Society, 103, 696 (November 2010). [pdf]

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, Czech Republic, October 2010. [pdf]

D. E. Peplow and L. M. Petrie, Jr., “Criticality Accident Alarm System Modeling Made Easy With SCALE 6.1,” Transactions of the American Nuclear Society 102, 297–299 (June 2010).

G. Ilas, "On SCALE validation for PBR analysis," Proceedings of PHYSOR 2010 – Advances in Reactor Physics to Power the Nuclear Renaissance, Pittsburgh, Pennsylvania, May 9–14, 2010. [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, Pittsburgh, Pennsylvania,  May 9–14, 2010.

S. M. Bowman and I. C. Gauld, OrigenARP Primer: How to Perform Isotopic Depletion and Decay Calculations with SCALE/ORIGEN, ORNL/TM-2010/43, UT-Battelle, LLC, Oak Ridge National Laboratory (April 2010).

J. C. Wagner, E. D. Blakeman, and D. E. Peplow, “FW-CADIS Method for Variance Reduction of Monte Carlo Calculations of Detailed Distributions and Multiple Localized Quantities,” Proceedings of the 2009 International Conference on Advances in Mathematics, Computational Methods, and Reactor Physics (M&C 2009), Saratoga Springs, New York, May 3–7, 2009.

D. E. Peplow, S.W. Mosher, and T. M. Evans, “Hybrid Monte Carlo/Deterministic Methods for Streaming/Beam Problems,”  Proceedings of the American Nuclear Society Joint Topical Meeting of the Radiation Protection and Shielding Division, Las Vegas, Nevada, April 19–23, 2010.

G. Radulescu, I. C. Gauld, and G. Ilas, SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions, ORNL/TM-2010/44, UT-Battelle, LLC, Oak Ridge National Laboratory (March 2010).  [supporting files]

I. C. Gauld and B. D. Murphy, Technical Basis for a Proposed Expansion of Regulatory Guide 3.54—Decay Heat Generation in an Independent Spent Fuel Storage Installation, NUREG/CR-6999 (ORNL/TM-2007/231), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory  (February 2010).

B. D. Murphy and I. C. Gauld, Spent Fuel Decay Heat Measurements Performed at the Swedish Central Interim Storage Facility, NUREG/CR-6971 (ORNL/TM-2008/016), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (February 2010).

G. Ilas, I. C. Gauld, and B. D. Murphy, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation—ARIANE and REBUS Programs (UO2 Fuel), NUREG/CR-6969 (ORNL/TM-2008/072), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (February 2010).

G. Ilas, I. C. Gauld, F. C. Difilippo, and M. B. Emmett, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation—Calvert Cliffs, Takahama, and Three Mile Island , Reactors, NUREG/CR-6968 (ORNL/TM-2008/071), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (February 2010).

I. C. Gauld, G. Ilas, B. D. Murphy, and C. F. Weber, Validation of SCALE 5 Decay Heat Predictions for LWR Spent Nuclear Fuel, NUREG/CR-6972 (ORNL/TM-2008/015), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (February 2010).

D. E. Peplow and L. M. Petrie, Jr., “Criticality Accident Alarm System Modeling With SCALE,” Proceedings of the 2009 International Conference on Advances in Mathematics, Computational Methods, and Reactor Physics (M&C 2009), May 3–7, 2009, Saratoga Springs, New York. [pdf]

D. Wiarda, M. E. Dunn, D. E. Peplow, T. M. Miller and H. Akkurt, Development and Testing of ENDF/B-VI.8 and ENDF/B-VII.0 Coupled Neutron-Gamma Libraries for SCALE 6, NUREG/CR-6990 (ORNL/TM-2008/047), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (February 2009).

B. T. Rearden, D. E. Mueller, S. M. Bowman, R. D. Busch, and S. J. Emerson, TSUNAMI Primer: A Primer for Sensitivity/Uncertainty Calculations with SCALE, ORNL/TM-2009/027, UT-Battelle, LLC, Oak Ridge National Laboratory (January 2009).

D. E. Peplow, T. M. Evans and J. C. Wagner, “Simultaneous Optimization of Tallies in Difficult Shielding Problems,” Nuclear Technology, 168(3), 785–792 (2009). 

J. C. Wagner, D. E. Peplow and T. M. Evans, “Automated Variance Reduction Applied to Nuclear Well-Logging Problems,” Nuclear Technology, 168(3), 799–809 (2009). 

G. Ilas, B. D. Murphy, and I. C. Gauld, “Overview of ORIGEN-ARP and its application to VVER and RBMK,” Transactions of the American Nuclear Society, 97 (November 2007). [pdf]

D. E. Peplow, E. D. Blakeman and J. C. Wagner, “Advanced Variance Reduction Strategies for Optimizing Mesh Tallies in MAVRIC,” Transactions of the American Nuclear Society, 97, 595–597 (2007). [pdf]

J. C. Wagner, E. D. Blakeman and D. E. Peplow, “Forward-Weighted CADIS Method for Global Variance Reduction,” Transactions of the American Nuclear Society, 97, 630–633 (2007).

G. Ilas, I.C. Gauld, and B.M. Murphy, "VVER and RBMK cross section libraries for ORIGEN-ARP," Proceedings of International Conference on Nuclear Criticality Safety ICNC’07, St. Petersburg, Russia (2007)

D. E. Peplow and J. C. Wagner, “Automated Variance Reduction for SCALE Shielding Calculations,” Proceedings of the American Nuclear Society’s 14th Biennial Topical Meeting of the Radiation Protection and Shielding Division, pp. 391–393, Carlsbad, New Mexico, April 2–6, 2006.

D. E. Peplow, S. M. Bowman, J. E. Horwedel and J. C. Wagner, “Monaco/MAVRIC: Computational Resources for Radiation Protection and Shielding in SCALE,” Transactions of the American Nuclear Society, 95, 669–671 (2006).

D. F. Hollenbach and P. B. Fox, CENTRM Validation, ORNL/TM-2004/66, UT-Battelle, LLC, Oak Ridge National Laboratory (May 2005).   [supporting files]

P. B. Fox and D. F. Hollenbach, KENO-VI Validation, ORNL/TM-2004/60, UT-Battelle, LLC, Oak Ridge National Laboratory (May 2005).   [supporting files]

I.C. Gauld, MOX Cross-Section Libraries for ORIGEN-ARP, ORNL/TM-2003/2, UT-Battelle, LLC, Oak Ridge National Laboratory (July 2003).

I.C. Gauld, Strategies for Application of Isotopic Uncertainties in Burnup Credit, ORNL/TM-2001/257, UT-Battelle, LLC, Oak Ridge National Laboratory (June 2003).

P. B. Fox and L. M. Petrie, Validation and Comparison of KENO V.a and KENO-VI, ORNL/TM-2001/110, UT-Battelle, LLC, Oak Ridge National Laboratory (May 2002).

S. M. Bowman, W. C. Jordan, J. F. Mincey, C. V. Parks, and L. M. Petrie, Experience with the SCALE Criticality Safety Cross-Section Libraries, NUREG/CR-6686 (ORNL/TM-1999/322), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (October 2000).

L. C. Leal, O. W. Hermann, S. M. Bowman, and C. V. Parks, ARP: Automatic Rapid Process for the Generation of Problem-Dependent SAS2H/ORIGEN-S Cross-Section Libraries, ORNL/TM-13584, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory (April 1998).

J. J. Lichtenwalter, S. M. Bowman, M. D. DeHart, and C. M. Hopper, Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages, NUREG/CR-6361 (ORNL/TM-13211), U.S. Nuclear Regulatory Commission, UT-Battelle, LLC, Oak Ridge National Laboratory (March 1997)  [supporting files]