2023 Publications:
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).
Friederike Bostelmann, Germina Ilas, and William A. Wieselquist, "Key nuclear data for non-LWR reactivity analysis," Frontiers in Energy Research, 11:1159478 (April 2023).
2022 Publications:
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)
F. Bostelmann, D. Wiarda, G. Arbanas, and W. A. Wieselquist, “Extension of SCALE/Sampler’s sensitivity analysis,” Annals of Nuclear Energy, 165, 108641 (January 2022).
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), UT-Battelle, LLC, Oak Ridge National Laboratory (December 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).
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).
2020 Publications:
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).
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).
D. Wiarda, et al, Specifications for the Generalised Nuclear Database Structure (GNDS), Nuclear Energy Agency Organisation for Economic Co-operation and Development (2020).
Prior Year Publications:
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. 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).
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).
D. Wiarda, M. Pigni, V. Sobes, and B. T. Rearden, “Dr. Mark Williams’ Three Contributions to Nuclear Data Covariance,” Transactions of the American Nuclear Society, 121, 1496–1498 (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).
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.
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 ICNC 2019 – 11th International Conference on Nuclear Criticality Safety, Paris, France, September 15–20, 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 the International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering, pp. 2836–2845, Portland, Oregon August 25–29, 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).
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).
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 (2019).
W. J. Marshall and A. M. Holcomb, “A Testing Trifecta: Data, Codes, and Evaluations,” Transactions of the American Nuclear Society, 119, 724–727 (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 (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 (2018).
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).
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).
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 (2014).
I. C. Gauld, M. T. Pigni, and G. Ilas, "Validation and testing of ENDF/B-VII decay data,” Nuclear Data Sheets, 120, 33–36 (2014).
C. McGraw and G. Ilas, "PWR ENDF/B-VII cross-section libraries for ORIGEN-ARP,” Nuclear Technology, 183(3), 436–445 (2013).
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).
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 ASTM International, 9(5) (2012).
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 (2011).
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).
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).