| The SCALE Verified, Archived Library of Inputs and Data-VALID WBJ Marshall, BT Rearden Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2013 | 51 | 2013 |
| 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 | 43 | 2015 |
| Monte Carlo capabilities of the SCALE code system BT Rearden, LM Petrie, DE Peplow, KB Bekar, D Wiarda, C Celik, ... SNA+ MC 2013-Joint International Conference on Supercomputing in Nuclear …, 2014 | 33 | 2014 |
| Criticality safety validation of Scale 6.1 WJ Marshall, BT Rearden ORNL/TM-2011/450, 2011 | 33 | 2011 |
| Criticality safety validation of SCALE 6.2. 2 EM Saylor, WJ Marshall, JB Clarity, Z Clifton, BT Rearden Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 32 | 2018 |
| As-loaded criticality margin assessment of dual-purpose canisters using UNF-ST&DARDS JB Clarity, K Banerjee, HK Liljenfeldt, WJ Marshall Nuclear Technology 199 (3), 245-275, 2017 | 32 | 2017 |
| Development and testing of neutron cross section covariance data for SCALE 6.2 WBJ Marshall, ML Williams, D Wiarda, BT Rearden, ME Dunn, D Mueller, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2015 | 27 | 2015 |
| Axial moderator density distributions, control blade usage, and axial burnup distributions for extended bwr burnup credit W Marshall, BJ Ade, SM Bowman, JS Martinez-Gonzalez US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2016 | 24 | 2016 |
| Review and prioritization of technical issues related to burnup credit for bwr fuel DE Mueller, SM Bowman, WJ Marshall, JM Scaglione ORNL Report to the NRC, 6-9, 2013 | 19 | 2013 |
| Nuclear Data and Benchmarking Program: Nuclear Data Performance Assessment for Advanced Reactors F Bostelmann, AM Holcomb, JB Clarity, WBJ Marshall, V Sobes, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019 | 15 | 2019 |
| Shielding for a cyclotron used for medical isotope production in China R Pevey, LF Miller, BJ Marshall, LW Townsend, B Alvord Radiation protection dosimetry 115 (1-4), 415-419, 2005 | 14 | 2005 |
| Integral Experiment Request 554 CED-1 Summary Report MN Dupont, DE Ames, GA Harms, WBJ Marshall, MT Pigni Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2022 | 12 | 2022 |
| Validation of criticality safety calculations with SCALE 6.2 WBJ Marshall, D Wiarda, C Celik, BT Rearden Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2013 | 12 | 2013 |
| Consequences of fuel failure on criticality safety of used nuclear fuel WJ Marshall, JC Wagner ORNL/TM-2012/325, Oak Ridge National Laboratory, Oak Ridge, TN, 2012 | 11 | 2012 |
| Applications of nuclear data covariances to criticality safety and spent fuel characterization ML Williams, G Ilas, WJ Marshall, BT Rearden Nuclear Data Sheets 118, 341-345, 2014 | 10 | 2014 |
| A Case Study in the Application of TSUNAMI-3D-Part 1, Multigroup WJ Marshall, BT Rearden, ME Dunn, EL Jones Transactions of the American Nuclear Society 115, 2016 | 9 | 2016 |
| Proposal for benchmark phase IV role of integral experiment covariance data for criticality safety validation A Hoefer, T Ivanova, B Rearden, D Mennerdahl, O Buss Benchmark proposal, OECD-NEA, 2015 | 9 | 2015 |
| Assessment of Existing Transportation Packages for use with HALEU R Hall, WJ Marshall, WA Wieselquist Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020 | 8 | 2020 |
| A Quantitative Impact Assessment of Hypothetical Spent Fuel Reconfiguration in Spent Fuel Storage Casks and Transportation Packages JM Scaglione, G Radulescu, WJ Marshall, KR Robb United States Nuclear Regulatory Commission, Office of Nuclear Regulatory …, 2015 | 8 | 2015 |
| Validation of SCALE 6.2 Criticality Calculations Using KENO Va and KENO-VI WBJ Marshall, BT Rearden, EL Jones Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2015 | 8 | 2015 |
