Ian C Gauld

Ian C Gauld

Distinguished R&D Staff

Bio

Ian is a Distinguished R&D Staff member in the Reactor Physics Group at Oak Ridge National Laboratory. He joined ORNL in 1999 and led development of the ORIGEN isotope generation and decay code and associated nuclear data libraries until 2014. He is actively engaged in international experimental programs to acquire data for code validation in the areas of decay heat using calorimeter measurements performed in Sweden and destructive radiochemical assay data from several domestic and international projects, and in applications of the code for reactor safety analysis under projects of the Nuclear Regulatory Commission (NRC) and the US Department of Energy (DOE). He has spearheaded safeguards projects to integrate ORIGEN for automated analysis of spent fuel Fork detector measurements in support of Euratom and IAEA nuclear inspections and for final verification measurements at repositories, has led projects on nuclear fuel isotopic analyses and nuclear data uncertainties for the US National Nuclear Security Administration (NNSA), and supported spent fuel analysis for the DOE Next-Generation Safeguards Initiative spent fuel project. Prior to joining ORNL, Ian worked 14 years with Atomic Energy of Canada Limited, where he led activities to develop and standardize computer codes and nuclear data for spent fuel analysis for the Canadian nuclear industry. Ian chairs the ANSI ANS-5.1 working group on Decay Heat Power for Light Water Reactors that prepared and issued the ANSI/ANS-5.1-2014 standard. He has chaired the OECD Nuclear Energy Agency Expert Group on Assay Data for Spent Nuclear Fuel since 2009 and is coordinating activities for the development and review of an expanded version of the Spent Fuel Composition Database (SFCOMPO) to be released in 2016. Ian has a Master’s degree in Physics from McMaster University in Hamilton Ontario, Canada.

Awards

2013: ORNL Significant Event Award for "Development of Technical Basis for NRC Regulatory Guidance to Enable Expanded Utilization of High-Capacity Spent Nuclear Fuel Storage and Transportation Systems," Team; J. Scaglione, G. Radulescu, I. Gauld, D. Mueller, G. Ilas, W. Marshall, J. Wagner.

2011: ORNL Significant Event Award for "Support to DOE in response to crisis at Fukushima Dai-ichi damaged reactors".

2011: ORNL Significant Event Award for "Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation," Team: I. Gauld, G. Ilas.

2002: Best Paper Award: I. C. Gauld, E. F. Shores, and R. T. Perry, "New Neutron Source Algorithms in the ORIGEN-S Code," in Proc. of American Nuclear Society 2002 Winter Meeting "Building the World Nuclear Community -- Strategies for the Deployment of New Nuclear Technologies," November 17-21, 2002, Washington, D.C.

Projects

OECD Nuclear Energy Agency: Coordinating the multinational compilation, review, and evaluation of measured spent fuel inventory data for a international spent fuel database used for nuclear safety, safeguards, and security applications.

DOE NNSA Office of International Nuclear Safeguards Engagement Program: DOE-Euratom project on cooperation on spent nuclear fuel verification; DOE-Euratom project on spent fuel measurements for respositories; DOE China project on spent fuel verification software.

DOE-NNSA Office of Nonproliferation and International Security, Next Generation Safeguards Initiative (NGSI) Spent Fuel Project.

DOE-NNSA Office of Defense Nuclear Nonproliferation R&D; Nuclear Data Needs Assessment.

SCALE Nuclear Safety Analysis and Design Code System - Oak Ridge National Laboratory; team lead for development of the ORIGEN isotope generation software and nuclear data development, testing, training, user support and validation (2001-2014).

US Nuclear Regulatory Commission; PWR Burnup Credit and technical basis studies; Validation studies for decay heat calculations supporting development of technical bases for extending Regulatory Guidance 3.54 for decay heat in an Independent Spent Fuel Storage Installation; BWR Burnup Credit.

CANDU Owners Group: Project for standardization of industry software and nuclear data in support of CANDU spent fuel composition and shielding analyses.

Publications

Journal Publications

M. T. Pigni, S. Croft and I. C. Gauld, “Uncertainty Quantification in (α,n) Neutron Source Calculations for an Oxide Matrix,” Progress in Nuclear Energy 91 (2016) pp147-152.

I. C. Gauld, J. M. Giaquinto, J. S. Delashmitt, J. Hu, G. Ilas, T. J. Keever, C. Romano, “Re-evaluation of Spent Nuclear Fuel Assay Data for the Three Mile Island Unit 1 Reactor and Application to Code Validation,” Annals of Nuclear Energy 87 (2016), pp. 267-281.

Ugur Mertyurek, Ian C. Gauld, “ORIGEN Libraries for MOX Fuel Assembly Designs,” Nuclear Engineering and Design 297 (2016) pp. 220–230.

M. Pigni, M. W. Francis, I. C. Gauld, “Investigation of Inconsistent ENDF/B-VII.1 Independent and Cumulative Fission Product Yields with Proposed Revisions,” Nuclear Data Sheets 1 (2015), p. 123.

I. C. Gauld, M. Pigni, G. Ilas, “Validation and Testing of ENDF/B-VII Decay Data,” Nuclear Data Sheets 120 (2014), pp. 33-36.

Germina Ilas, Ian C. Gauld, Henrik Liljenfeldt, Validation of ORIGEN for LWR used fuel decay heat analysis with SCALE, Nuclear Engineering and Design 273 (1), 58–67, July 2014.

S. Vaccaro, J. Hu, J. Svedkauskaite, A. Smejkal, P. Schwalbach, P. De Baere and I.C. Gauld, “A New Approach to Fork Measurements Data Analysis by RADAR-CRISP and ORIGEN Integration,” Trans. Nucl. Sci. (2014)

G. Radulescu, I. C. Gauld, G. llas, J. C. Wagner, “Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses,” Nucl. Tech. 188, 2 (2014) 154-157.

Germina Ilas, Ian C. Gauld, Georgeta Radulescu, “Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE,” Annals of Nuclear Energy 46 (2012) 43–55.

D. Wang, I. C. Gauld, G. L. Yoder, L. J. Ott, G. F. Flanagan, M. W. Francis, E. L. Popov, J. J. Carbajo, P. K. Jain, J. C. Wagner, J. C. Gehin, Study of Fukushima Dai-ichi Nuclear Power Station Unit 4 Spent Fuel Pool, submitted to Nucl. Tech. (2011).

Ian C. Gauld, Georgeta Radulescu, Germina Ilas, Brian D. Murphy, Mark L. Williams, Dorothea Wiarda, Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE, Nuclear Technology , 174, 2, 169 (2011).

Eugene C. Fortune IV, Ian C. Gauld, C-K Chris Wang, Gamma Dose Rate Near a New 252Cf Brachytherapy Source, Nuclear Technology, June 2010.

G. Ilas and I. C. Gauld, “SCALE Analysis of CLAB Decay Heat Measurements for PWR Spent Fuel Assemblies,” Annals of Nuclear Energy, Vol. 35, No. 1 (January 2008).

J.C. Tait, I.C. Gauld, and A.H. Kerr, “Validation Of The ORIGEN-S Code For Predicting Radionuclide Inventories In Used CANDU Fuel”, Journal of Nuclear Materials 223, 109–121 (1995).

I.C. Gauld, J.W. Harvey, T.J. Kennett, W.V. Prestwich, "Thermal neutron response of the Li2B4O7:Cu TL dosimeter," Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Volume 251, Issue 2, 15 October 1986, Pages 380-385

Conference papers and reports

Fast, I., Gauld, I., Michel-Sendis, F. And Caruso, S., ”Importance of Available Experimental and International Reference Inventory Data for the Estimation of Realistic SNF Inventory Bandwidths,” Spent Fuel Workshop 2016, Stockholm, 3-4 May 2016.

Francis, Matthew W; Weber, Charles F; Pigni, Marco T; Gauld, Ian C, Reactor Fuel Isotopics and Code Validation for Nuclear Applications, Oak Ridge National Laboratory report, ORNL/TM-2014/464, 2015.

J. Hu, I. Gauld, and A. Worrall, “Spent Fuel Modeling And Simulation Using ORIGAMI For Advanced NDA Instrument Performance Assessment,” ANS MC2015, Nashville.

B. J. Ade, W. J. Marshall, S. M. Bowman, I. C. Gauld, G. Ilas, J. S. Martinez, “Coolant Density and Control Blade History Effects in Extended BWR Burnup Credit, ICNC 2015, Charlotte, NC.

I. Gauld, J. Hu, P. DeBaere, S. Vaccaro, P. Schwalbach, H. Liljenfeldt, S. Tobin, “In-field Performance Testing of the Fork Detector for Quantitative Spent Fuel Verification,” In Proc. of ESARDA 2015.

Joshua Peterson, Ian Gauld, Steven Bowman, “Extended Burnup Summary of UO2 and MOX Fuel,” ANS 2015 International High-Level Radioactive Waste Management Conference, April 12-16, Charleston (2015).

Joseph M. Giaquinto, Jeffrey S. Delashmitt, Ian C. Gauld, David C. Glasgow, Tamara J. Keever, Benjamin D. Roach, Analytical Measurements and Protocols for the Qualification of NpO2 Targets For Irradiation In ORNL's High Flux Isotope Reactor, Radiobioassay and Radiochemical Measurements Conference (RRMC), Knoxville, TN (2014)

Roach, Benjamin D., Delashmitt, Jeffrey S., Gauld, Ian C., Giaquinto, Joseph M., Ilgner, Ralph H., Keever, Tamara Jo, Smith, Rob R., “High Accuracy Fission Product Measurements for the Qualification of NpO2 Targets for the Production of Plutonuim-238,” 8th International Conference on Isotopes and Expo (ANS), Chicago (2014).

G. Ilas, I. Gauld, R. M. Westfall, M. Pigni, “Evaluation of Hanford B Reactor Experiments (PTA-069 and PTA-084) for Code and Data Benchmarking,” Oak Ridge National Laboratory, ORNL/TM–2014/53 (2014).

B. J. Marshall, G. Radulescu, U. Mertyurek, B. J. Ade, I. C. Gauld, S. M. Bowman, “Peak Reactivity Burnup Credit for BWR Spent Fuel in Casks Using Standard Cold Core Geometry,” NUREG/CR report (in review) (2014).

J. Hu, I. C. Gauld, “Impact of Nuclear Data Uncertainties on Calculated Spent Fuel Nuclide Inventories and Advanced NDA Instrument Response,” ESARDA Bulletin (2014).

W.J. Marshall, S. Croft, I.C. Gauld, J. Hu, C. Romano, and A. Worrall, Special Nuclear Material Inventory Processes at US Domestic Nuclear Power Plants, proceeding of INMM 2014.

S. Vaccaro, I. C. Gauld, J. Hu, P. de Baere, P. Schwalbach, “Uncertainty Quantification of Fork Detector Measurements from Spent Fuel Loading Campaigns,” IAEA Safeguards Symposium 2014, Paper Number: IAEA-CN-220-179.

J. L. Peterson, I. C. Gauld, S. M. Bowman, “Extended Burnup Study of UO2 and MOX Fuel,” ANS 2015 International High-Level Radioactive Waste Management Conference, Charleston (2015).

Stefano Vaccaro, Ian C. Gauld, Jianwei Hu, Peter Schwalbach, Paul De Baere, Willi Koehne, “Enhanced Spent Fuel Verification by Analysis of Fork Measurements Data Based on Nuclear Modelling and Simulation,” INMM Information Analysis Technologies, Techniques and Methods for Safeguards, Nonproliferation and Arms Control Verification Conference, Portland, May 12-14, 2014.

S.J. Tobin, H. Liljenfeldt, H. Trellue, G. Baldwin, A. Belian, D. Blair, T. Burr, P. De-Baere, M. Fensin, A. Favalli, J. Galloway, I. Gauld, S. Grape, B. Grogan, Y. Ham, J. Hendricks, V. Henzel, J. Hu, K. Ianakiev, G. Ilas, P. Jansson, A. Kaplan, T. Martinik, H.O. Menlove, D. Meyers, V. Mozin, M. Newell, P. Polk, C. Rael, S. Pozzi, P. Santi, P. Schwalbach, A. Sjöland, S. Jacobsson Svärd, M.T. Swinhoe, T.J. Ulrich, S. Vaccaro, D. Vo, A. Worrall, Experimental and Analytical Plans for the Non-destructive Assay System of the Swedish Encapsulation and Repository Facilities, IAEA Safeguards Symposium 2014, Vienna, Austria (2014).

Ian Gauld, Nicholas Sly, Franco Michel-Sendis, OECD NEA Benchmark Database Of Spent Nuclear Fuel Isotopic Compositions For World Reactor Designs, PHYSOR 2014 – The Role of Reactor Physics Toward a Sustainable Future, Kyoto, Japan, September 28 – October 3 (2014).

F. Michel-Sendis, M. Bossant, N. Soppera, I. Gauld, A New OECD/NEA Database Of Nuclide Compositions Of Spent Nuclear Fuel, PHYSOR 2014 – The Role of Reactor Physics Toward a Sustainable Future, Kyoto, Japan, September 28 – October 3 (2014).

J. Hu, I.C. Gauld, J.E. Banfield, S.E. Skutnik, “Developing Spent Fuel Assembly Standards for Advanced NDA Instrument Calibration – NGSI Spent Fuel Project,” Oak Ridge National Laboratory, ORNL/TM-2013/576 (2014)

I. C. Gauld, G. Ilas, M. T. Pigni, D. Wiarda, “Integral Testing of the 239Np Capture Cross Section using Reactor Experiments,” Cross Section Evaluation Working Group Meeting (CSEWG), November (2013).

M.L. Williams, F. Havluj, D. Wiarda, M. T. Pigni, I. C. Gauld, SCALE Uncertainty Quantification Methodology for Criticality Safety Analysis of Used Nuclear Fuel, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar, Wilmington (2013).

W.A. Wieselquist, K.-S. Kim, G. Ilas, I. C. Gauld, “Comparison of Burnup Credit Uncertainty Quantification Methods,” NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar, Wilmington (2103).

M.T. Pigni and I. Gauld, “235U Fission Product Yield Covariance Data for the Thermal Neutron Range,” International Workshop on Nuclear Data Covariances, Santa Fe, NM (2014).

M.T. Pigni. I.C. Gauld, M.L. Williams, F. Havluj, D. Wiarda, G. Ilas, “Applications of Decay Data and Fission Product Yield Covariance Matrices in Uncertainty Quantification on Decay Heat,” OECD/NEA Working Party on International Nuclear Data Evaluation Co-operation, WPEC Subgroup 37 (Improved fission product yield evaluation methodologies), presented May 22, 2013. https://www.oecd-nea.org/science/wpec/sg37/Meetings/2013_May/32_Pigni_Co...

S. J. Tobin, H. O. Menlove, M. T. Swinhoe, H. Trellue, M. Humphrey, A. Belian, D. Bracken, B. Broadhead, T. Burr, L.W. Campbell, B. Castle, W. Charlton, J.M. Eigenbrodt, A. Favalli, C.R. Freeman, J. Galloway, I. Gauld, J. Gerhart, Y. Ham, J. Hendricks, V. Henzel, D. Henzlova, J. Hu, A. Hunt, A. Kaplan, J. Kulisek, D.W. Lee, N. Lundkivist, A. M. LaFleur, T. P. Lou, B.A. Ludewigt, V. Mozin, D. Rodriguez, C. Romano, S. Skutnik, and T. J. Ulrich, “Update on the Next Generation Safeguard Initiative Project to Determine Pu Mass in Spent Fuel Assemblies,” INMM 2012.

G. Radulescu, I. C. Gauld, G. llas, J. C. Wagner, An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses—Isotopic Composition Predictions, Nuclear Regulatory Commission report NUREG/CR-7108 (ORNL/TM-2011/509) April 2012.

Bryan Broadhead, Ian Gauld, Holly Trellue, Jack Galloway, and Tom Burr, Utilizing NGSI Spent Fuel Sensitivity Libraries to Estimate Model Uncertainties, Proceedings of the Institute for Nuclear Materials Management, INMM 2012.

S.E. Skutnik, I.C. Gauld, C. E. Romano, and H. R. Trellue, Creating NDA “working standards” through high-fidelity spent fuel modeling, Proceedings of the Institute for Nuclear Materials Management, INMM 2012.

A. Smejkal, K. Schoop, P. Schwalbach, D. Ancius, S. Vaccaro, M. Boella, I. Gauld, and D Wiarda, Improvements for spent fuel verification by safeguards inspectors, Proceedings of the Institute for Nuclear Materials Management, INMM 2012.

B. T. Rearden, L. M. Petrie, D. E. Peplow, M. A. Jessee, D. Wiarda, M. L. Williams, R. A. Lefebvre, J. P. Lefebvre, I. C. Gauld, and S. Goluoglu, Enhancement in SCALE 6.1, PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education, Knoxville, Tennessee, USA, April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2012)

R. N. Morris, C. A. Baldwin, J. M. Giaquinto, I. C. Gauld, Y. Yan, K. J. Leonard, H. F. Longmire, K. McCoy, J. M. Myers, and S. L. Voit, MOX PIE Fuel and Clad Examination Final Report, ORNL/LTR-2011/505, 2011.

B. J. Aide and I. C. Gauld, Decay Heat Calculations for PWR and BWR Assemblies Fueled with Uranium and Plutonium Mixed Oxide Fuel Using Scale, Oak Ridge National Laboratory, ORNL/TM-2011/290, September 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, ICNC 2011.

G. Radulescu, I. C. Gauld, And J. C. Wagner, Depletion Code Validation for Criticality Safety Analyses Employing Burnup Credit, International High-Level Radioactive Waste Management, April 10–14, 2011, Albuquerque, NM.

B. T. Rearden, L. M. Petrie, D. E. Peplow, M. A. Jessee, D. Wiarda, M. L. Williams, R. A. Lefebvre, J. P. Lefebvre, I. C. Gauld, And S. Goluoglu, Scale 6.1 Enhancements for Nuclear Criticality Safety, ICNC 2011, Edinburgh, Scotland, September, 2011.

G. Yesilyurt, K. T. Clarno, I. C. Gauld, Modular ORIGEN-S for Multi-Physics Code Systems, 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, G. Ilas, “SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions”, ORNL/TM-2010/44, March 2010.
U. Mertyurek, M. W. Francis, I. C. Gauld, “SCALE 5 Analysis of BWR Spent Nuclear Fuel Isotopic Compositions for Safety Studies,” Oak Ridge National Laboratory, ORNL/TM-2010/286 (2010).

S. M. Bowman and I. C. Gauld, OrigenArp Primer: How to Perform Isotopic Depletion and Decay Calculations with SCALE/ORIGEN, ORNL/TM-2010/43, April 2010.

C. V. Parks, J. C. Wagner, D. Mueller, and I. C. Gauld, “Development of Technical Basis for Burnup Credit Regulatory Guidance in the United States,” PATRAM 2010, London, UK, October 3-8, 2010.

Susan Hogle, G. Ivan Maldonado, Ian Gauld, Julie Ezold, “Calculating Transcurium Production Yields at the High Flux Isotope Reactor,” Trans. Am. Nucl. Soc., 2010 ANS Winter Meeting, November 7–11, 2010, Las Vegas.

Eugene C. Fortune IV, Ian C. Gauld, C-K Chris Wang, “Gamma Dose Near a New 252Cf Brachytherapy Source,” Trans. American Nuclear Society, 2010 ANS Topical Meeting, June 13–17, 2010, San Diego.

Ian Gauld and Matthew Francis, “INVESTIGATION OF PASSIVE GAMMA SPECTROSCOPY TO VERIFY SPENT NUCLEAR FUEL CONTENT,” INMM 51st Annual Meeting, Baltimore, July 11-15, 2010.

J. D. Galloway, G. I. Maldonado, I. Gauld, M. A. Jessee, and K. T. Clarno, “Generalized Isotopic Tracking Capabilities within the 3D BWR Nodal Simulator NESTLE,” Trans. Am. Nucl. Soc., 2010 ANS Winter Meeting, November 7–11, 2010, Las Vegas.

I. C. Gauld, S. M. Bowman, and J. E. Horwedel, ORIGEN-ARP: Automatic Rapid Processing For Spent Fuel Depletion, Decay, And Source Term Analysis, ORNL/TM-2005/39, Version 6, Vol. I, Sect. D1, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2009.

G. Radulescu, I. C. Gauld, STARBUCS: A SCALE ORNL/TM-2005/39, Version 6, Vol. I, Sect. C10, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2009.

I. C. Gauld and O. W. Hermann, COUPLE: SCALE System Module to Process Problem-Dependent Cross Sections and Neutron Spectral Data for ORIGEN-S Analyses, ORNL/TM-2005/39, Version 6, Vol. II, Sect. F6, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2009.

I. C. Gauld and O. W. Hermann and R. M. Westfall ORIGEN-S: SCALE System Module To Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup And Decay, And Associated Radiation Source Terms, ORNL/TM-2005/39, Version 6, Vol. II, Sect. F7, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2009.

I. C. Gauld and J. E. Horwedel, OPUS/PLOTOPUS: An ORIGEN-S Post-Processing Utility And Plotting Program For SCALE, ORNL/TM-2005/39, Version 6, Vol. II, Sect. F15, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2009.

I. C. Gauld, B. D. Murphy, M. L. Williams, ORIGEN-S Data Libraries, ORNL/TM-2005/39, Version 6, Vol. III, Sect. M6, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2009.

Ian Gauld and Y. Rugama, “Activities of the OECD/NEA Expert Group On Assay Data For Spent Nuclear Fuel,” IAEA International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Córdoba, Spain, 27-30 October, 2009.

Ian Gauld, Georgeta Radulescu and Germina Ilas, “SCALE Validation Experience Using An Expanded Isotopic Assay Database For Spent Nuclear Fuel,” IAEA International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Córdoba, Spain, 27-30 October, 2009

Georgeta Radulescu and Ian C. Gauld, “Enhancements To The Burnup Credit Criticality Safety Analysis Sequence In SCALE,” IAEA International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Córdoba, Spain, 27-30 October, 2009

Steven E. Skutnik and Ian C. Gauld, “OASIS: A Simplified User Interface for Advanced Fuel Cycle Analysis in SCALE,” submitted for publication in Trans. Amer. Nucl. Soc., 2009 ANS Winter Meeting, Washington, D.C., November 15–19, 2009.

Ian C Gauld, Michaele C. Brady Raap, William B. Wilson, and Frank Schmittroth, “Proposed Revision of the Decay Heat Standard ANSI/ANS-5.1-2005,” Trans. Am. Nuc. Soc., 2010 ANS Winter Meeting and Nuclear Technology Expo.

John C. Wagner, Cecil V. Parks, Don E. Mueller, and Ian Gauld, REVIEW OF TECHNICAL STUDIES IN THE UNITED STATES IN SUPPORT OF BURNUP CREDIT REGULATORY GUIDANCE, IAEA International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, October 27-30, 2009, Córdoba, Spain.

I. C. Gauld, S. M. Bowman, and J. E. Horwedel, ORIGEN-ARP: Automatic Rapid Processing For Spent Fuel Depletion, Decay, And Source Term Analysis, ORNL/TM-2005/39, Version 6, Vol. I, Sect. D1, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2009.

G. Radulescu and I. C. Gauld, STARBUCS: A Scale Control Module for Automated Criticality Safety Analyses Using Burnup Credit, ORNL/TM-2005/39, Version 6, Vol. I, Sect. C10, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2009.

I. C. Gauld and O. W. Hermann, COUPLE: SCALE System Module to Process Problem-Dependent Cross Sections and Neutron Spectral Data for ORIGEN-S Analyses, ORNL/TM-2005/39, Version 6, Vol. II, Sect. F6, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2009.

I. C. Gauld and O. W. Hermann and R. M. Westfall, ORIGEN-S: SCALE System Module To Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup And Decay, And Associated Radiation Source Terms, ORNL/TM-2005/39, Version 6, Vol. II, Sect. F7, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2009.

I. C. Gauld and J. E. Horwedel, OPUS/PLOTOPUS: An ORIGEN-S Post-Processing Utility and Plotting Program for SCALE, ORNL/TM-2005/39, Version 6, Vol. II, Sect. F15, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2009.

I. C. Gauld, B. D. Murphy, M. L. Williams, ORIGEN-S Data Libraries, ORNL/TM-2005/39, Version 6, Vol. III, Sect. M6, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2009.

Benjamin B. Cipiti, Valmor F. de Almeida, Ian C. Gauld, Joseph F. Birdwell, and David W. DePaoli, Coupling a Transient Solvent Extraction Module with the Separations and Safeguards Performance Model, SAND2009-6307 (ORNL/TM-2009/205), Sandia National Laboratory, October 2009.

Cecil V. Parks, John C. Wagner, Don E. Mueller, Ian Gauld, Development of Technical Basis For Burnup Credit Regulatory Guidance In The United States, PATRAM 2010.

G. Ilas, I. C. Gauld, and B. D. Murphy, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - ARIANE and REBUS International UOX Fuel Programs, NUREG/CR-6969 (ORNL/TM-2008/072) U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory.

G. Ilas, I. C. Gauld, F. C. Difilippo, and M. B. Emmett, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - Calvert Cliffs, Takahama, and Three Mile Island Reactors, NUREG/CR-6968 (ORNL/TM-2008/071) U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory.

B. D. Murphy and I. C. Gauld, Spent Fuel Decay Heat Measurements Performed at the Swedish Central Interim Storage Facility, NUREG/CR-6972 (ORNL/TM-2008/016) U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory.

I. C. Gauld, G. Ilas, B. D. Murphy, and C. F. Weber, Validation of SCALE 5 Decay Heat Predictions for LWR Spent Nuclear Fuel, NUREG/CR-6972 (ORNL/TM-2008/015) U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory.

G. Ilas and I. C. Gauld, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation—MALIBU Program (UO2 Fuel), NUREG/CR-6970 (ORNL/TM-2008/013) U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory.

I. C. Gauld and B. D. Murphy, Technical Basis for a Proposed Expansion of Regulatory Guide 3.54 – Decay Heat Generation in an Independent Spent Fuel Storage Installation, NUREG/CR- (ORNL/TM 2007/231) U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory.

I. C. Gauld and G. Ilas, Evaluation of Uncertainties in Predicted Isotopic Compositions for High Burnup PWR Spent Nuclear Fuel, NUREG/CR-7012 (ORNL/TM-2007/32) U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory.

H. J. Smith, I. C. Gauld, U. Mertyurek, “Analysis of Experimental Data for High Burnup BWR Spent Fuel Isotopic Validation— SVEA-96 and GE14 Assembly Designs,” NUREG/CR-7162, U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (2012).

G. Ilas and I. C. Gauld, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - Vandellós Reactor, NUREG/CR-7013 (ORNL/TM-2007/12) U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory.

I. Gauld and Y. Rugama, “Experimental Isotopic Data Compiled by the OECD/NEA Expert Group on Assay Data for Spent Nuclear Fuel,” submitted to American Nuclear Society, 2009 ANS Winter Meeting and Nuclear Technology Expo, November 15–19, 2009, Washington, D.C.

Georgeta Radulescu, Ian C. Gauld, and Germina Ilas, “Evaluation of PWR Isotopic Composition Data,” submitted to American Nuclear Society, 2009 ANS Winter Meeting and Nuclear Technology Expo, November 15–19, 2009, Washington, D.C.

Germina Ilas and Ian Gauld, “SCALE 6 Analysis of Isotopic Assay Benchmarks for PWR Spent Fuel,” submitted to American Nuclear Society, 2009 ANS Winter Meeting and Nuclear Technology Expo, November 15–19, 2009, Washington, D.C.

Georgeta Radulescu and Ian Gauld, “Enhancements to the Burnup Credit Criticality Safety Analysis Sequence in SCALE,” in Proc. of 2009 Nuclear Criticality Safety Division Topical Meeting on Realism, Robustness and the Nuclear Renaissance, September 13–17, 2009, Richland, Washington.

Valmor de Almeida, Joseph F. Birdwell Jr, David W. DePaoli, and Ian C. Gauld, Coupling a Transient Solvent Extraction Module with the Separations and Safeguards Performance Model, ORNL/TM-2009/205, UT-Battelle, LLC, Oak Ridge National Laboratory, September 2009

Y. Rugama, R Blomquist, M. Brady Raap, B. Briggs, V. Rouyer, Y. Miyoshi, I. Gauld, T. Ivanova, Fuel Cycle Associated Activities of the OECD/NEA/NSC Working Party on Nuclear Criticality Safety, GLOBAL 2009, "The Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives," September 6–11, 2009, Paris, France.

Germina Ilas, Ian C. Gauld, and Sang-Yoon Lee, Development of ORIGEN Libraries for HTR-10 Spent Fuel Safeguards Analyses - Interim Status Report, ORNL/TM-2009/164, UT-Battelle, LLC, Oak Ridge National Laboratory, July 2009.

Y. Rugama, I. Gauld and K. Suyama, “OECD/NEA Expert Group On Assay Data Of Spent Nuclear Fuel,” in Proceedings of ICAPP 2009, Paper 9057, May 11–14, 2009, Tokyo, Japan.

Mark D. DeHart, Ian C. Gauld, and Kenya Suyama,”Issues in Three-Dimensional Depletion Analysis of Measured Data Near the End of a Fuel Rod” 2008 ANS Winter Meeting and Nuclear Technology Expo, November 9–13, 2008, Reno Nevada. Trans. Amer. Nucl. Soc., 99, (2008).

Germina Ilas and Ian C. Gauld, “Analysis of isotopic assay data from the MALIBU program,” International Conference on Reactor Physics, Nuclear Power: A Sustainable Resource, September 14–19, 2008, Casino-Kursaal Conference Center, Interlaken, Switzerland.

Mark D DeHart, Ian C. Gauld, and Kenya Suyama, “Three-dimensional depletion analysis of the axial end of a Takahama fuel rod,” International Conference on Reactor Physics, Nuclear Power: A Sustainable Resource, September 14–19, 2008, Casino-Kursaal Conference Center, Interlaken, Switzerland.

I. C. Gauld, V&V of Spent Fuel Isotopic Compositions and Decay Heat: Review of Experimental Benchmark Data, Workshop on Verification and Validation Techniques, July 21, 2008, Idaho National Laboratory.

K. D. Kimball and I. C. Gauld, “Impact of NDA Uncertainties on NCS at the K-25 Site,” Trans. Amer. Nucl. Soc., 98, 214–215 (2008).
G. Ilas and I. C. Gauld, “SCALE Analysis of CLAB Decay Heat Measurements for PWR Spent Fuel Assemblies,” Annals of Nuclear Energy, Vol. 35, No. 1 (January 2008).

Germina Ilas, Brian D. Murphy, and Ian C. Gauld, “Overview of ORIGEN-ARP and its Applications to VVER RBMK,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc. 97, 601–603 (2007).

Germina Ilas, Brian D. Murphy, and Ian C. Gauld, “VVER and RBMK Cross Section Libraries for ORIGEN-ARP,” p. 413–417 in Proceedings of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), Vol. II, May 28–June 1, 2007, St. Petersburg, Russia.

M. D. DeHart, I. C. Gauld, and M. L. Williams, “High-Fidelity Lattice Physics Capabilities of the SCALE Code System Using TRITON,” mcsna05008full.1.pdf in Proc. of Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications (M&C + SNA2007), April 15–19, 2007, Monterey, California, American Nuclear Society, LaGrange Park, Illinois (2007).

C. V. Parks, J. C. Wagner, D. E. Mueller, and I. C. Gauld, “Full Burnup Credit in Transport and Storage Casks: Benefits and Implementation,” RadWaste Solutions, Vol. 14, No. 2, pp. 32–41, March/April 2007.

Ian Gauld, “Validation of ORIGEN-S Decay Heat Predictions for LOCA Analysis,” C183.pdf in Proc. of PHYSOR–2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, September 10–14, 2006, Vancouver, British Columbia, Canada.

Ian C. Gauld and John C. Wagner, “Status of Burnup Credit in the United States,” Workshop on the Need for Post Irradiation Experiments for Validate Fuel Depletion Calculation Methodologies, OECD Nuclear Energy Agency, WPNCS, Prague, Czech Republic, December 2006.

Ian C. Gauld, “Spent Fuel Isotopic Validation Activities in the United States: Status and Lessons Learned,” Workshop on the Need for Post Irradiation Experiments for Validate Fuel Depletion Calculation Methodologies, OECD Nuclear Energy Agency, WPNCS, Prague, Czech Republic, December 2006.

Bryan L. Broadhead and Ian C. Gauld, “Applicability of VVER-440 Isotopic Assay Measurements to Validate Codes for Western PWR Fuel Designs (and Vice Versa),” Workshop on the Need for Post Irradiation Experiments for Validate Fuel Depletion Calculation Methodologies, OECD Nuclear Energy Agency, WPNCS, Prague, Czech Republic, December 2006.

M. C. Brady Raap, I. C. Gauld, J. K. Dickens, and W. B. Wilson, “Revisions to the Decay Heat Standard: ANSI/ANS 5.1,” C125.pdf in Proc. of PHYSOR–2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, September 10–14, 2006, Vancouver, British Columbia, Canada.

Ian C. Gauld, Stephen M. Bowman, Brian D. Murphy, and P. Schwalbach, “Applications of ORIGEN to Spent Fuel Safeguards and Non-Proliferation,” 431_gauldian.pdf in Proc. of INMM 47th Annual Meeting, July 16–20, 2006, Nashville, Tennessee.

G. Ilas, I. C. Gauld, and V. J. Jodoin, “LWR Cross Section Libraries for ORIGEN-ARP in SCALE 5.1,” Trans Am. Nucl. Soc., 95, 706 (2006).

J. J. Klingensmith, Y. Y. Azmy, and I. C. Gauld, “Implementation and Verification of AMALGAMATE, an Interfacing Tool for TORTSQ and ORIGEN-S,” Trans. Am. Nucl. Soc., 95, 312–314 (2006).

Germina Ilas and Ian C. Gauld, “Analysis of Decay Heat Measurements for BWR Fuel Assemblies,” Trans. Am. Nucl. Soc., 94, 385–387 (2006).

F. C. Difilippo and I. C. Gauld, ORIGEN-ARP Cross-Section Libraries for Analysis of Spent Nuclear Fuel from South Korean Reactors, ORNL/TM-2005/95, UT-Battelle, LLC, Oak Ridge National Laboratory, August 2005.

I. C. Gauld and D. E. Mueller, Evaluation of Cross-Section Sensitivities in Computing Burnup Credit Fission Product Concentrations, ORNL/TM-2005/48, UT-Battelle, LLC, Oak Ridge National Laboratory, August 2005.

B. D. Murphy, P. DeBaere, and I. C. Gauld, “Monte Carlo Modeling of a Fork Detector System”, 27th ESARDA Annual Meeting, symposium on Nuclear Material Management, London, 10-12 May. 2005.

I. C. Gauld and D. E. Mueller, Status and Recommendations for Acquisition of Fission Product Radiochemical Assay Data, ORNL/TM-2005/47, UT-Battelle, LLC, Oak Ridge National Laboratory, June 2005.

J. J. Klingensmith and I. Gauld, “ORIGEN-S Gamma Decay Spectra Characterization and Benchmarking,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc., 92, 33-34 (June 2005).

I. C. Gauld, “Automated Depletion Analysis of PBMR Fuel Using SCALE,” Trans. Am. Nucl. Soc., 91, 673–674 (November 2004).
B. D. Murphy and I. C. Gauld, “Spent-Fuel Decay Heat Investigations for BWR Assemblies Using Both One- and Two-Dimensional Model Simulations,” Trans. Am. Nucl. Soc., 91, 670–672 (November 2004).

I. C. Gauld and B. D. Murphy, Updates to the ORIGEN-S Data Libraries Using ENDF/B-VI, FENDL-20, and EAF-99 Data, ORNL/TM-2003/118, UT-Battelle, LLC, Oak Ridge National Laboratory, May 2004.

S. M. Bowman, D. F. Hollenbach, M. D. DeHart, B. T. Rearden, I. C. Gauld, and S. Goluoglu, "SCALE 5: Powerful New Criticality Safety Analysis Tools," pp. 447-453 in Proc. of The 7th International Conference on Nuclear Criticality Safety (ICNC2003)," October 20–24, 2003, Tokai-mura, Japan.

I. C. Gauld, P. Chare, and R. C. Clark, "Development of ORIGEN-ARP Methods and Data for LEU and MOX Safeguards Applications," 0135.pdf in Proc of the 44th Annual Institute of Nuclear Materials Management (INMM) Annual Meeting, July 13–17, 2003, Phoenix, Arizona.

I. C. Gauld, MOX Cross-Section Libraries for ORIGEN-ARP, ORNL/TM-2003/2, UT-Battelle, LLC, Oak Ridge National Laboratory, July 2003.

I. C. Gauld, Strategies for Application of Isotopic Uncertainties in Burnup Credit, NUREG/CR-6811 (ORNL/TM-2001/257), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, June 2003.

C. E. Sanders and I. C. Gauld, Isotopic Analysis of High-Burnup PWR Spent Fuel Samples From the Takahama-3 Reactor, NUREG/CR-6798 (ORNL/TM-2001/259), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, January 2003.

Japan Atomic Energy Research Institute (JAERI), Technical Development on Burn-up Credit for Spent LWR Fuel, (Eds.) Y. Nakahara, K. Suyama, and T. Suzaki, JAERI-Tech 2000-071, Tokai-mura, Naka-gun, Ibaraki-ken, Japan, October 2000. [ORNL/TR-2001/01 English Translation, Oak Ridge National Laboratory, January 2002] – I. C. Gauld (ORNL) coordinated translation by JLS Language Corporation, Menlo Park, California 94025.

I. C. Gauld, E. F. Shores, and R. T. Perry, "New Neutron Source Algorithms in the ORIGEN-S Code," in Proc. of American Nuclear Society 2002 Winter Meeting "Building the World Nuclear Community -- Strategies for the Deployment of New Nuclear Technologies," November 17-21, 2002, Washington, D.C. Trans. Am. Nucl. Soc., 87, 406-407 (2002) --Highlights of RPSD 2002.

S. M. Bowman, D. F. Hollenbach, M. D. DeHart, B. T. Rearden, I. C. Gauld and S. Goluoglu, "An Overview of What's New in SCALE 5," in Proc. of American Nuclear Society 2002 Winter Meeting "Building the World Nuclear Community—Strategies for the Deployment of New Nuclear Technologies," November 17-21, 2002, Washington, D.C. Trans. Am. Nucl. Soc, 87, 265–268 (2002).

S. M. Bowman, J. E. Horwedel, I. C. Gauld, and D. L. Barnett, "ORIGEN-ARP: A New Windows PC Package for ORIGEN Users," bowman1m.pdf, Paper Log 6 in Proc. of American Nuclear Society 12th Biennial RPSD Topical Meeting, April 14-18, 2002, Santa Fe, New Mexico.

I. C. Gauld, E. F. Shores, and R. T. Perry, "New Neutron Source Algorithms in the ORIGEN-S Code," gauld1m.pdf, Paper Log 5 in Proc. of American Nuclear Society 12th Biennial RPSD Topical Meeting, April 14 18, 2002, Santa Fe, New Mexico.

C. V. Parks, B. L. Broadhead, M. D. DeHart, and I. C. Gauld, "Validation Issues for Depletion and Criticality Analysis in Burnup Credit," pp. 167–179 in Proc. of the Technical Committee Meeting on the Evaluation and Review of the Implementation of Burnup Credit in Spent Fuel Management Systems, July 10–14, 2000, Vienna, Austria (August 2001).

C. V. Parks, I. C. Gauld, J. C. Wagner, B. L. Broadhead, M. D. DeHart, and D. D. Ebert, "Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks," pp. 139 161, in Proceedings of the Twenty-Eighth Water Reactor Safety Information Meeting, October 23-25, 2000, Bethesda, Maryland, NUREG/CP-0172, May 2001.

I. C. Gauld, D. L. Barnett, O. W. Hermann, and S. M. Bowman, OPUS/PLOTOPUS: An ORIGEN-S Post-Processing Utility and Plotting Program for SCALE, NUREG/CR-6718 (ORNL/TM-2001/26), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, April 2001.

S. M. Bowman, I. C. Gauld, and J. C. Wagner, Recommendations on Standardized Technical Specifications for Spent Fuel Storage Casks, NUREG/CR-6716 (ORNL/TM-2000/385), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 2001.

I. C. Gauld and C. V. Parks, Review of Technical Issues Related to Predicting Isotopic Compositions and Source Terms for High-Burnup LWR Fuel, NUREG/CR-6701 (ORNL/TM-2000/277), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, January 2001.

I. C. Gauld and J. C. Ryman, Nuclide Importance to Criticality Safety, Decay Heating, and Source Terms Related to Transport and Interim Storage of High-Burnup LWR Fuel, NUREG/CR-6700 (ORNL/TM-2000/284), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, January 2001.

I. C. Gauld, Limited Burnup Credit in Criticality Safety Analysis: A Comparison of ISG-8 and Current International Practice, NUREG/CR-6702 (ORNL/TM-2000/72), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, January 2001.

B. L. Broadhead and I. C. Gauld, "Rankings of Nuclide Importance in Spent Fuel for Shielding Applications," pp. 702-709 in Proc. of Radiation Protection and Shielding Division Topical Conference, Radiation Protection for our National Priorities: Medicine, the Environment and the Legacy, September 17-20, 2000, Spokane, Washington.

I. C. Gauld, SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configurations, ORNL/TM 1999/247, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, March 2000.

I.C. Gauld and S.G. King, BETA-S: A Code to Calculate Multigroup Beta Spectra, AECL report RC-1564/COG 96-33-I, 1996.

I.C. Gauld, An ORIGEN-S Data Library for the Canadian Nuclear Fuels Waste Management Program, AECL report, RC-1632, 1996.

I.C. Gauld and K.A. Litwin, Verification and Validation of the ORIGEN-S Code and Nuclear Data Libraries, AECL report RC-1429/COG-95-150-I, 1995.

I.C. Gauld, P.A. Carlson, and K.A. Litwin, Production and Validation of ORIGEN-S Cross-Section Libraries for CANDU Reactor Fuel Studies, AECL report RC-1442/COG-95-200-I, 1995.

I.C. Gauld, H. McIlwain, and G.R. Penner, A 67-Group SN Transport Cross Section Library for CANDU Reactor Shielding Applications, AECL report RC-1259, 1994.

P.F.A. de Leege, J.M. Li, and I.C. Gauld, “Linking WIMS With The SCALE Depletion Sequence”, Joint International Conference on Mathematical Methods and Supercomputing in Nuclear Applications, Karlsruhe Proceedings Vol. 2, 577-589, 1993.

F. B. Walton and I. C. Gauld, Scoping Estimates for Ontario Hydro Power Reactor Process and Decommissioning Waste” Prediction and Characterization of 36Cl Waste Inventories, AECL COG-94-458 (CANDU Owners Group report), June 1995.

K. A. Litwin, I. C. Gauld, and G. R. Penner, Improvements to the Point Kernel Code QAD-CGGP: A Code Validation and Users Manual, AECL report RC-1214 (CANDU Owners Group COG-94-65), August 1994.