Ian Gauld
Title
Cited by
Cited by
Year
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
1962009
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
1772011
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
1532006
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
612012
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
612012
Strategies for application of isotopic uncertainties in burnup credit
IC Gauld
ORNL/TM-2001/257, Oak Ridge National Laboratory, 2003
512003
OrigenArp Primer: How to perform isotopic depletion and decay calculations with SCALE/ORIGEN
SM Bowman, IC Gauld
Oak Ridge National Laboratory, Oak Ridge, USA, 2010
432010
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
422003
Scale 5.1 predictions of PWR spent nuclear fuel isotopic compositions
G Radulescu, IC Gauld, G Ilas
ORNL/TM-2010/44, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 2010
402010
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
372017
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
372012
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
371995
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
362011
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
352015
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
342010
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
331989
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
312014
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
302010
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
292015
High-fidelity lattice physics capabilities of the SCALE code system using TRITON
MD DeHart, IC Gauld, ML Williams
Joint international topical meeting on mathematics & computation and …, 2007
292007
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Articles 1–20