| Origen-S: Scale system module to calculate fuel depletion, Actinide transmutation, fission product buildup and decay, and associated radiation source terms IC Gauld, OW Hermann, RM Westfall ORNL/TM-2005/39, Version 6, 2009 | 240 | 2009 |
| Isotopic depletion and decay methods and analysis capabilities in SCALE IC Gauld, G Radulescu, G Ilas, BD Murphy, ML Williams, D Wiarda Nuclear technology 174 (2), 169-195, 2011 | 237 | 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 |
| SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data F Michel-Sendis, I Gauld, JS Martinez, C Alejano, M Bossant, ... Annals of Nuclear Energy 110, 779-788, 2017 | 107 | 2017 |
| Study of Fukushima Daiichi nuclear power station unit 4 spent-fuel pool D Wang, IC Gauld, GL Yoder, LJ Ott, GF Flanagan, MW Francis, EL Popov, ... Nuclear technology 180 (2), 205-215, 2012 | 76 | 2012 |
| Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE G Ilas, IC Gauld, G Radulescu Annals of Nuclear Energy 46, 43-55, 2012 | 75 | 2012 |
| SCALE 5.1 predictions of PWR spent nuclear fuel isotopic compositions G Radulescu, IC Gauld, G Ilas Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2010 | 66 | 2010 |
| Strategies for application of isotopic uncertainties in burnup credit IC Gauld Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2002 | 57 | 2002 |
| ORIGEN-S: Depletion module to calculate neutron activation, actinide transmutation, fission product generation, and radiation source terms IC Gauld ORNL/TM-2005/39, Version 6, 2011 | 51 | 2011 |
| Isotopic analysis of high-burnup PWR spent fuel samples from the Takahama-3 reactor CE Sanders, IC Gauld Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear …, 2003 | 51 | 2003 |
| Nuclide importance to criticality safety, decay heating, and source terms related to transport and interim storage of high-burnup LWR fuel IC Gauld, JC Ryman Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2000 | 50 | 2000 |
| Validation of ORIGEN for LWR used fuel decay heat analysis with SCALE G Ilas, IC Gauld, H Liljenfeldt Nuclear Engineering and Design 273, 58-67, 2014 | 48 | 2014 |
| An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--isotopic Composition Predictions G Radulescu, IC Gauld, G Ilas, JC Wagner United States Nuclear Regulatory Commission, Office of Nuclear Regulatory …, 2012 | 48 | 2012 |
| Validation of SCALE 5 decay heat predictions for LWR Spent Nuclear Fuel IC Gauld, G Ilas, BD Murphy, CF Weber Nuclear Regulatory Commission report (ORNL/TM-2006/13), in preparation, 2010 | 48 | 2010 |
| Investigation of inconsistent ENDF/B-VII. 1 independent and cumulative fission product yields with proposed revisions MT Pigni, MW Francis, IC Gauld Nuclear Data Sheets 123, 231-236, 2015 | 47 | 2015 |
| 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 | 47 | 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 | 44 | 2015 |
| Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation—Calvert Cliffs, Takahama, and Three Mile Island Reactors G Ilas, IC Gauld, FC Difilippo, MB Emmett Office of Nuclear Regulatory Res, 2010 | 44 | 2010 |
| Validation of the ORIGEN-S code for predicting radionuclide inventories in used CANDU fuel JC Tait, I Gauld, AH Kerr Journal of nuclear materials 223 (2), 109-121, 1995 | 42 | 1995 |
| Derivation of initial radionuclide inventories for the safety assessment of the disposal of used CANDU fuel JC Tait, IC Gauld, GB Wilkin Atomic Energy of Canada Ltd., 1989 | 37 | 1989 |
