![]() Ian GauldDistinguished R&D StaffReactor Physics Reactor and Nuclear Systems Division Nuclear Science and Engineering Directorate Oak Ridge National Laboratory P.O. Box 2008, Bldg. 5700 Oak Ridge, TN 37831-6170 Phone: 865.576.5257 gauldi@ornl.gov Curriculum Vitae Research Interests
Education
Publications2012 G. Ilas and I. C. Gauld, Analysis of Uncertainty in Spent Nuclear Fuel Source Terms Due to Nuclear Data Uncertainties, ORNL/LTR-2012/34, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2012. 2011 I. C. Gauld, Task 2: Uncertainty Methods for Isotopic Depletion and Source Term Analysis, ORNL/LTR-2011/436, Oak Ridge National Laboratory, Oak Ridge, Tenn. (2011) T. E. Valentine, B. W. Patton, and I. C. Gauld, Evaluation of High Energy Delayed Gamma Spectroscopy Measurements of Spent Nuclear Fuel at the ORNL Irradiated Fuels Examination Laboratory, ORNL/LTR-2011/519, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2011. B. J. Ade and I. C. Gauld, Decay Heat Calculations for PWR and BWR Assemblies Fueled with Uranium and Plutonium Mixed Oxide Fuel using SCALE, ORNL/TM-2011/290, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2011. 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," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011. G. Radulescu, I. C. Gauld, and J. C. Wagner, "An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses - Isotopic Composition Predictions," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011. E. C. Fortune, I. C. Gauld, and C. Wang, "Gamma Dose Rate Near a New (252)Cf Brachytherapy Source," Nuclear Technology 175 (1), 73-76 (July 2011). I. C. Gauld et al., "Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE," Nucl. Technol. 174(2), 169-195, May 2011. I. C. Gauld and D. Wiarda, ORIGEN-S Data Libraries, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2011. I. C. Gauld, ORIGEN-S: Depletion Module to Calculate Neutron Activation, Actinide Transmutation, Fission Product Generation and Radiation Source Terms, Sect. F7 of ORNL/TM-2005/39, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2011. I. C. Gauld, COUPLE: A Nuclear Decay and Cross-Section Data Processing Code for Creating ORIGEN-S Libraries, Sect. F6 of ORNL/TM-2005/39, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2011. G. Yesilyurt, K. T. Clarno, I. C. Gauld, and J. Galloway, "Modular ORIGEN-S for Multi-Physics Code Systems," Proc. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, Brazil, May 8-12, 2011. G. Radulescu, I. C. Gauld, and G. Ilas, "Burnup Credit Isotopic Validation," presented at the U. S. Nuclear Regulatory Commission, May 6, 2011, Rockville, Md. C. V. Parks, J. C. Wagner, D. Mueller, and I. C. Gauld, "Development of Technical Basis for a Burnup Credit Regulatory Guidance in the United States," Proc. PATRAM 2010, London, U.K., October 3-8, 2010 (April 2011). U. Mertyurek, M. W. Francis, and I. C. Gauld, SCALE 5 Analysis of BWR Spent Nuclear Fuel Isotopic Compositions Safety Studies, ORNL/TM-2010/286, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2011. I. C. Gauld, G. Ilas, and G. Radulescu, Uncertainties in Predicted Isotopic Compositions for High Burnup PWR Spent Nuclear Fuel, ORNL/TM-2010/41 (NUREG/CR-7012), prepared for the Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2011. G. Ilas and I. C. Gauld, Source Term for High Burnup HTGR Fuel – Pebble Bed Design, ORNL/LTR-2011/20, prepared for the U. S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2011. G. Ilas and I. C. Gauld, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation – Vandelios II Reactor, ORNL/TM-2009/321, prepared for the Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2011. |


