2023 Publications:
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).
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).
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.
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).
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.
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).
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).
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.
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.
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).
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, 108641, (January 2022).
2021 Publications:
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.
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).
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).
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, 150,107829 (January 2021).
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, 107830 (January 2021).
2020 Publications:
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).
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).
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).
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).
Prior Year Publications:
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]
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), September 15–20, 2019, Paris, France.
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).
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).
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).
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).
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).
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).
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, September 18–22, 2016, Kobe, Japan. [pdf]
Joshua Peterson, Eva Sunny, William Wieselquist, and Andrew Worrall, "Generating Cross Sections for ORION Fuel Cycle Models," Proceedings of PHYSOR 2016, May 1–5, 2016, Sun Valley, Idaho. [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, May 1–5, 2016, Sun Valley, Idaho. [pdf]
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, 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.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).
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).
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).
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).
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, U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (April 2012).
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).
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).
G. Ilas and I. C. Gauld, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - Vandellos II Reactor, NUREG/CR-7013, 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, U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (2011).
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).
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 (2010). [pdf]
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).
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 (2007). [pdf]
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).
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).
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).