| Polaris: a new two-dimensional lattice physics analysis capability for the SCALE code system MA Jessee, WA Wieselquist, TM Evans, SP Hamilton, JJ Jarrell, KS Kim, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2014 | 47 | 2014 |
| Technical basis for peak reactivity burnup credit for BWR spent nuclear fuel in storage and transportation systems WBJ Marshall, BJ Ade, SM Bowman, IC Gauld, G Ilas, U Mertyurek, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2015 | 44 | 2015 |
| Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit IC Gauld, U Mertyurek Nuclear Engineering and Design 345, 110-124, 2019 | 28 | 2019 |
| SCALE 5 Analysis of BWR Spent Nuclear Fuel Isotopic Compositions Safety Studies U Mertyurek, MW Francis, IC Gauld Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2011 | 27 | 2011 |
| Lattice physics calculations using the embedded self-shielding method in Polaris, Part I: Methods and implementation MA Jessee, WA Wieselquist, U Mertyurek, KS Kim, TM Evans, ... Annals of Nuclear Energy 150, 107830, 2021 | 20 | 2021 |
| Margins for Uncertainty in the Predicted Spent Fuel Isotopic Inventories for BWR Burnup Credit IC Gauld, U Mertyurek, M Aissa United States Nuclear Regulatory Commission, Office of Nuclear Regulatory …, 2018 | 17 | 2018 |
| Isotopic and Fuel Lattice Parameter Trends in Extended Enrichment and Higher Burnup LWR Fuel Vol I: PWR fuel R Hall, R Cumberland, R Sweet, WA Wieselquist Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 13 | 2021 |
| Lattice physics calculations using the embedded self-shielding method in polaris, Part II: Benchmark assessment U Mertyurek, MA Jessee, BR Betzler Annals of Nuclear Energy 150, 107829, 2021 | 12 | 2021 |
| Overview of Nuclear Data Uncertainty in Scale and Application to Light Water Reactor Uncertainty Analysis W Wieselquist, ML Williams, D Wiarda, MT Pigni, U Mertyurek, M Aissa United States Nuclear Regulatory Commission, Office of Nuclear Regulatory …, 2018 | 12 | 2018 |
| Development of ORIGEN libraries for mixed oxide (MOX) fuel assembly designs U Mertyurek, IC Gauld Nuclear Engineering and Design 297, 220-230, 2016 | 12 | 2016 |
| Modernization enhancements in SCALE 6.2 BT Rearden, RA Lefebvre, JP Lefebvre, KT Clarno, ML Williams, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2014 | 12 | 2014 |
| Analysis of Experimental Data for High Burnup BWR Spent Fuel Isotopic Validation--SVEA-96 and GE14 Assembly Designs HJ Smith, IC Gauld, U Mertyurek US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2013 | 11 | 2013 |
| Generation of a broad-Group HTGR library for use with SCALE RJ Ellis, D Lee, D Wiarda, ML Williams, U Mertyurek Oak Ridge National Laboratory (United States). Funding organisation: US …, 2012 | 10 | 2012 |
| Systems and methods of predicting a critical effective k for a nuclear reactor U Mertyurek, DJ Kropaczek, AA Karve, AP Chopelas US Patent 7,532,698, 2009 | 8 | 2009 |
| Scale 6.2 lattice physics code accuracy assessment for light water reactor fuel U Mertyurek, BR Betzler, MA Jessee, SM Bowman | 7 | 2018 |
| Hybrid reduced order modeling for assembly calculations Y Bang, HS Abdel-Khalik, MA Jessee, U Mertyurek Nuclear Engineering and Design 295, 661-666, 2015 | 7 | 2015 |
| Crane: A new scale super-sequence for neutron transport calculations C Wang, HS Abdel-Khalik, U Mertyurek Mathematics and Computations, Supercomputing in Nuclear Applications and …, 2015 | 7 | 2015 |
| Assessment of Core Physics Characteristics of Extended Enrichment and Higher Burnup LWR Fuels Using the Polaris/PARCS Two-Step Approach. Vol. I: PWR Fuel J Hu, U Mertyurek, WA Wieselquist Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2022 | 6 | 2022 |
| Criticality safety enhancements for scale 6.2 and beyond BT Rearden, KB Bekar, C Celik, KT Clarno, ME Dunn, SW Hart, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2015 | 6 | 2015 |
| Verification of the sensitivity and uncertainty-based criticality safety validation techniques: ORNL’s SCALE case study D Huang, U Mertyurek, H Abdel-Khalik Nuclear Engineering and Design 361, 110571, 2020 | 5 | 2020 |
