| Scale 6: Comprehensive nuclear safety analysis code system SM Bowman Nuclear Technology 174 (2), 126-148, 2011 | 265 | 2011 |
| ORIGEN-ARP: Automatic rapid processing for spent fuel depletion, decay, and source term analysis IC Gauld, SM Bowman, JE Horwedel, LC Leal ORNL/TM-2005/39, Version 6, 2006 | 178 | 2006 |
| Reactor physics methods and analysis capabilities in SCALE MD DeHart, SM Bowman Nuclear Technology 174 (2), 196-213, 2011 | 127 | 2011 |
| Scale cross-section libraries WC Jordan, SM Bowman, DF Hollenbach Vol. III, Section M4 of SCALE: A Modular Code System for Performing …, 1997 | 120 | 1997 |
| Validation of the SCALE system for PWR spent fuel isotopic composition analyses OW Hermann, SM Bowman, CV Parks, MC Brady Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 1995 | 110 | 1995 |
| Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages JJ Lichtenwalter, SM Bowman, MD DeHart, CM Hopper Nuclear Regulatory Commission, Washington, DC (United States). Office of …, 1997 | 90 | 1997 |
| ORIGEN-ARP: automatic rapid process for spent fuel depletion, decay, and source term analysis SM Bowman, LC Leal Vol. I, Sect. D1 of SCALE: A Modular Code System for Performing Standardized …, 2000 | 67 | 2000 |
| OrigenArp Primer: How to perform isotopic depletion and decay calculations with SCALE/ORIGEN SM Bowman, IC Gauld Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2010 | 48 | 2010 |
| 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 | 45 | 2015 |
| Validation of the SCALE Broad Structure 44-Group ENDF/BV Cross-Section Library for Use in Criticality Safety Analyses MD DeHart, SM Bowman US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div …, 1994 | 44 | 1994 |
| ORIGEN-ARP, a fast and easy-to-use source term generation tool SM Bowman, LC Leal, OW Hermann, CV Parks Journal of Nuclear Science and Technology 37 (sup1), 575-579, 2000 | 36 | 2000 |
| Tsunami primer: A primer for sensitivity/uncertainty calculations with scale BT Rearden, D Mueller, SM Bowman, RD Busch, S Emerson Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2009 | 35 | 2009 |
| Keno-vi Primer: A Primer for Criticality Calculations with SCALE/KENO-VI Using GEEWIZ SM Bowman ORNL/TM-2008/069, 2008 | 35 | 2008 |
| Computational Benchmark for Estimation of Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit DE Mueller, JM Scaglione, JC Wagner, SM Bowman United States Nuclear Regulatory Commission, Office of Nuclear Regulatory …, 2013 | 33 | 2013 |
| Overview of the SCALE code system SM Bowman TRANSACTIONS-AMERICAN NUCLEAR SOCIETY 97, 589, 2007 | 32 | 2007 |
| Monaco/MAVRIC: Computational Resources for Radiation Protection and Shielding in SCALE DE Peplow, SM Bowman, JE Horwedel, JC Wagner Transactions-American Nuclear Society 95, 669, 2006 | 30 | 2006 |
| Automatic rapid process for the generation of problem-dependent SAS2H/ORIGEN-S cross-section libraries LC Leal, OW Hermann, SM Bowman, CV Parks Nuclear technology 127 (1), 1-23, 1999 | 26 | 1999 |
| Validation of SCALE-4 for burnup credit applications SM Bowman, MD DeHart, CV Parks Nuclear technology 110 (1), 53-70, 1995 | 26 | 1995 |
| 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 | 25 | 2016 |
| Experience With the SCALE Criticality Safety Cross Section Libraries SM Bowman Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2000 | 24 | 2000 |
