I. Gauld

发表

Study of Fukushima Daiichi Nuclear Power Station Unit 4 Spent-Fuel Pool

L. J. Ott, P. Jain, J. Gehin, 2012 .

Strategies for Application of Isotopic Uncertainties in Burnup Credit

I. C. Gauld, I. Gauld, 2002 .

Reactor Fuel Isotopics and Code Validation for Nuclear Applications

C. Weber, M. Pigni, I. Gauld, 2015 .

Validation of the ORIGEN-S code for predicting radionuclide inventories in used CANDU fuel

Ian C Gauld, J. C. Tait, I. Gauld, 1995 .

Overview of ORIGEN-ARP and its Applications to VVER RBMK

I. Gauld, G. Ilas, B. D. Murphy, 2007 .

Analysis of isotopic assay data from the MALIBU program

Ian C Gauld, Germina Ilas, I. Gauld, 2009 .

Evaluation of PWR Isotopic Composition Data

I. Gauld, G. Ilas, G. Radulescu, 2009 .

SCALE 6 ANALYSIS OF ISOTOPIC ASSAY BENCHMARKS FOR PWR SPENT FUEL

Ian C Gauld, Germina Ilas, I. Gauld, 2009 .

SCALE 5 Analysis of BWR Spent Nuclear Fuel Isotopic Compositions Safety Studies

I. Gauld, M. Francis, U. Mertyurek, 2011 .

Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE

Dorothea Wiarda, Ian C Gauld, Germina Ilas, 2011 .

Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE

Ian C Gauld, Germina Ilas, Georgeta Radulescu, 2012 .

SCALE Uncertainty Quantification Methodology for Criticality Safety Analysis of Used Nuclear Fuel

Dorothea Wiarda, Ian C Gauld, Frantisek Havluj, 2013 .

Automated Depletion Analysis of PBMR Fuel Using SCALE

I. Gauld, 2004 .

Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit

I. Gauld, U. Mertyurek, 2019, Nuclear Engineering and Design.

Advancing the Fork detector for quantitative spent nuclear fuel verification

S. Vaccaro, D. Wiarda, I. Gauld, 2018 .

Re-evaluation of Spent Nuclear Fuel Assay Data for the Three Mile Island Unit 1 Reactor and Application to Code Validation

T. J. Haverlock, I. Gauld, G. Ilas, 2016 .

Development of ORIGEN libraries for mixed oxide (MOX) fuel assembly designs

I. Gauld, U. Mertyurek, 2016 .

Developing Spent Fuel Assembly Standards for Advanced NDA Instrument Calibration – NGSI Spent Fuel Project

I. Gauld, Jianwei Hu, J. Banfield, 2014 .

Validation and Testing of ENDF/B-VII Decay Data

M. Pigni, I. Gauld, G. Ilas, 2014 .

Gamma Dose Rate Near a New 252Cf Brachytherapy Source

I. Gauld, C.K.C. Wang, E. Fortune, 2011 .

Yield Data for Nuclear Safeguards

R. Venkataraman, I. Gauld, A. Moore, 2019 .

Quantitative Assessment of Nuclear Data Uncertainties for National Security Applications

R. Venkatraman, D. McNabb, M. Pigni, 2015 .

Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - Vandellos II Reactor

Ian C Gauld, Germina Ilas, I. Gauld, 2011 .

SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions

Ian C Gauld, Germina Ilas, Georgeta Radulescu, 2010 .

(α,n) reactions in oxide compounds calculated from the R-matrix theory

M. Pigni, S. Croft, I. Gauld, 2020 .

Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses

Ian C Gauld, Germina Ilas, Georgeta Radulescu, 2014 .

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predictions

Ian C Gauld, John C. Wagner, Germina Ilas, 2011 .

Validation of ORIGEN-S Decay Heat Predictions for LOCA Analysis

Ian C Gauld, I. Gauld, 2006 .

Updates to the ORIGEN-S Data Libraries Using ENDF/B-VI, FENDL-2.0, and EAF-99 Data

I. C. Gauld, B. D. Murphy, I. Gauld, 2004 .

Technical Development on Burn-up Credit for Spent LWR Fuel

I. C. Gauld, I. Gauld, 2001 .

SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data

Ian C Gauld, Kenya Suyama, O. Cabellos, 2017 .

Integral nuclear data validation using experimental spent nuclear fuel compositions

Ian C Gauld, Franco Michel-Sendis, Mark L Williams, 2017 .

Scale 6.1 Enhancements for Nuclear Criticality Safety

Bradley T Rearden, Dorothea Wiarda, Ian C Gauld, 2011 .

MOX Cross-Section Libraries for ORIGEN-ARP

I. C. Gauld, I. Gauld, 2003 .

Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems

Ian C Gauld, Stephen M. Bowman, William Bj J Marshall, 2015 .

New Neutron Source Algorithms In the ORIGEN-S Code

I. C. Gauld, I. Gauld, 2002 .

Validation of ORIGEN for LWR used fuel decay heat analysis with SCALE

Ian C Gauld, Henrik Liljenfeldt, Germina Ilas, 2014 .

Development of an object-oriented ORIGEN for advanced nuclear fuel modeling applications

Ian C Gauld, Steven E. Skutnik, F. Havloej, 2013 .

MODULAR ORIGEN-S FOR MULTI-PHYSICS CODE SYSTEMS

Ian C Gauld, Kevin T. Clarno, Gokhan Yesilyurt, 2011 .

Impact of Nuclear Data Uncertainties on Calculated Spent Fuel Nuclide Inventories and Advanced NDA Instrument Response

Jianwei Hu, Ian C. Gauld, I. Gauld, 2014 .

Evaluation of Hanford B Reactor Experiments (PTA-069 and PTA-084) for Code and Data Benchmarking

Ian C Gauld, R. M. Westfall, Germina Ilas, 2014 .

Early applications of the R-matrix SAMMY code for charged-particle induced reactions and related covariances

Ian C Gauld, Stephen Croft, Marco T. Pigni, 2017 .

Investigation of Inconsistent ENDF/B-VII.1 Independent and Cumulative Fission Product Yields with Proposed Revisions

Ian C Gauld, Marco T. Pigni, Matthew W Francis, 2015 .

Uncertainty quantification in (α,n) neutron source calculations for an oxide matrix

Ian C Gauld, Stephen Croft, Marco T. Pigni, 2016 .

U.S. Commercial Spent Nuclear Fuel Assembly Characteristics - 1968-2013

S. Bowman, I. Gauld, J. Peterson, 2016 .

OrigenArp Primer: How to Perform Isotopic Depletion and Decay Calculations with SCALE/ORIGEN

Ian C Gauld, Stephen M. Bowman, S. Bowman, 2010 .

Analysis of new measurements of Calvert Cliffs spent fuel samples using SCALE 6.2

I. Gauld, G. Ilas, J. Giaquinto, 2017 .

Nuclide Importance to Criticality Safety, Decay Heating, and Source Terms Related to Transport and Interim Storage of High-Burnup LWR Fuel

I. C. Gauld, J. C. Ryman, I. Gauld, 2000 .

SFCOMPO DATABASE OF SPENT NUCLEAR FUEL ASSAY DATA – THE NEXT FRONTIER

I. Gauld, G. Ilas, P. Ortego, 2021, EPJ Web of Conferences.

GAMMA AND NEUTRON DOSE PROFILES NEAR A CF-252 BRACHYTHERAPY

S. Cho, I. Gauld, Chris Wang, 2010 .

SCALE 5 : Powerful New Criticality Safety Analysis Tools

D. F. Hollenbach, B. Rearden, S. Bowman, 2003 .

LWR Cross Section Libraries for ORIGEN-ARP in SCALE 5.1

I. Gauld, G. Ilas, V. Jodoin, 2006 .

OVERVIEW OF SCALE 6.2

B. Rearden, D. Wiarda, M. Dunn, 2013 .