关注
Ian Greenquist
Ian Greenquist
Nuclear Fuels Analyst, Oak Ridge National Laboratory
在 ornl.gov 的电子邮件经过验证
标题
引用次数
引用次数
年份
Development of a microstructural grand potential-based sintering model
I Greenquist, MR Tonks, LK Aagesen, Y Zhang
Computational Materials Science 172, 109288, 2020
492020
Grand potential sintering simulations of doped UO2 accident-tolerant fuel concepts
I Greenquist, M Tonks, M Cooper, D Andersson, Y Zhang
Journal of Nuclear Materials 532, 152052, 2020
272020
Review of sintering and densification in nuclear fuels: Physical mechanisms, experimental results, and computational models
I Greenquist, MR Tonks, Y Zhang
Journal of Nuclear Materials 507, 381-395, 2018
272018
Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 1: Overview and code coupling strategies
I Greenquist, A Wysocki, J Hirschhorn, N Capps
Annals of Nuclear Energy 191, 109913, 2023
102023
Metallic fuel performance benchmarks for versatile test reactor applications
JA Hirschhorn, JJ Powers, I Greenquist, RT Sweet, J Hu, DL Porter, ...
Nuclear Science and Engineering 196 (sup1), 123-147, 2022
82022
Research Needs for Uranium-Zirconium-Based Metallic Fuels
A Aitkaliyeva, M Tonks, J Hirschhorn, J Powers, I Greenquist, B Beeler
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2020
82020
Development of a U-19Pu-10Zr fuel performance benchmark case based on the IFR-1 experiment
I Greenquist, KM Cunningham, J Hu, JJ Powers, DC Crawford
Journal of Nuclear Materials 553, 152997, 2021
72021
A Metallic Fuel Performance Benchmark Problem Based on the IFR-1 Experiment
I Greenquist, KM Cunningham, J Hu, JJ Powers
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020
72020
Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 3: Thermal hydraulic evaluation of large break LOCA under high-burnup conditions
A Wysocki, J Hirschhorn, I Greenquist, N Capps
Annals of Nuclear Energy 192, 109951, 2023
62023
25-Pin metallic fuel performance benchmark case based on the EBR-II X430 experiments series
I Greenquist, JJ Powers
Journal of Nuclear Materials 556, 153211, 2021
62021
Assessment of the Effect of Prototypic High-Burnup Operating Conditions of Fuel Fragmentation, Relocation, and Dispersal Susceptibility
N Capps, J Hirschhorn, A Wysocki, I Greenquist
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2022
52022
Metallic Fuel Benchmark Simulations Based on the X430 Experiments
IT Greenquist, JJ Powers
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020
52020
Multiphysics analysis of fuel Fragmentation, Relocation, and dispersal Susceptibility–Part 2: High-Burnup Steady-State operating and fuel performance conditions
J Hirschhorn, I Greenquist, A Wysocki, N Capps
Annals of Nuclear Energy 192, 109952, 2023
42023
Sensitivity and uncertainty of the IFR-1 BISON benchmark
I Greenquist, JJ Powers
Progress in Nuclear Energy 152, 104361, 2022
42022
Analysis of the impact of fuel microstructure on irradiation-enhanced densification using grand potential simulations
I Greenquist, M Tonks, Y Zhang
Annals of Nuclear Energy 151, 107858, 2021
42021
Development of Microreactor Automated Control System (MACS): Surrogate Plant-level Modeling and Control Algorithms Integration
W Williams, P Ramuhalli, I Greenquist
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2023
22023
Coupled Neutronics, Thermal Hydraulics, and Fuel Performance Simulations of a Natural Circulation Based SMR
R Sweet, I Greenquist, A Graham, R Trotta, C Lietwiler, F Odeh
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2023
22023
Multiphysics Analysis of Fuel Fragmentation, Relocation, and Dispersal Susceptibility–Part 2: High-Burnup Steady-State Operating and Fuel Performance Conditions
N Capps, J Hirschhorn, I Greenquist, A Wysocki
Relocation, and Dispersal Susceptibility–Part 2, 2023
22023
Effects of transient fission gas release on rod balloon burst behavior during a loss-of-coolant accident
I Greenquist, N Capps
Annals of Nuclear Energy 196, 110213, 2024
12024
Accelerated fission rate irradiation design, pre-irradiation characterization, and adaptation of conventional PIE methods for U-10Mo and U-17Mo
P Doyle, C Massey, D Richardson, I Greenquist, R Seibert, G Helmreich, ...
Frontiers in Nuclear Engineering 1, 1054288, 2023
12023
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