| Experimental study of the free space optics communication system operating in the 8–12 µm spectral range M Garlinska, A Pregowska, I Gutowska, M Osial, J Szczepanski Electronics 10 (8), 875, 2021 | 28 | 2021 |
| OSU High Temperature Test Facility Design Technical Report I Gutowska, B Woods Oregon State University, Corvallis, May, 2019 | 13 | 2019 |
| Automation levels for nuclear reactor operations: A revised perspective AL Alberti, V Agarwal, I Gutowska, CJ Palmer, CRE de Oliveira Progress in Nuclear Energy 157, 104559, 2023 | 9 | 2023 |
| Overview of HTTF Modeling and Benchmark Efforts for Code Validation for Gas-Cooled Reactor Applications A Epiney, G Strydom, R Kile, MT Retamales, S Yoon, C Mueller, ... Proc. 4th Int. Conf. Generation IV Small Reactors (G4SR-4), 3-6, 2022 | 9 | 2022 |
| Instrumentation Plan for the OSU High Temperature Test Facility I Gutowska, B Woods OSU-HTTF-TECH-002-R4, 2019 | 8 | 2019 |
| Study on depressurized loss of coolant accident and its mitigation method framework at very high temperature gas cooled reactor I Gutowska | 8 | 2015 |
| CFD modeling of the OSU High Temperature Test Facility inlet plenum flow distribution during normal operation I Gutowska, BG Woods, SR Cadell Nuclear Engineering and Design 353, 110216, 2019 | 6 | 2019 |
| Digital twin framework for the resilient remote monitoring and operation of nuclear microreactors KR Stevens, JE Oncken, MJ Culler, TA Ulrich, R Boring, S Bukowski, ... AHFE International 117 (INL/CON-23-72922-Revision-1), 2023 | 5 | 2023 |
| Verification and validation of a lower plenum mixing test at the OSU High Temperature Test Facility J Halsted, I Gutowska Nuclear Engineering and Design 406, 112251, 2023 | 4 | 2023 |
| CFD simulations to characterize near wall heat transfer in high Prandtl number packed bed conditions CJ Dionne, I Gutowska, RB Jackson Nuclear Engineering and Design 396, 111868, 2022 | 3 | 2022 |
| Scaling Analysis for the Very High Temperature Reactor Test Facility at Oregon State University I Gutowska, B Woods OSU-HTTF-TECH-001-R1, Oregon State University, 2019 | 3 | 2019 |
| CFD Assessment of LOFA Intra Core Natural Circulation in the High Temperature Test Facility I Gutowska, B Woods 18th International Meeting on Nuclear Reactor Thermal Hydraulics, American …, 2019 | 3 | 2019 |
| Scaling Studies for Advanced High Temperature Reactor Concepts, Final Technical Report: October 2014—December 2017 B Woods, I Gutowska, H Chiger Oregon State Univ., Corvallis, OR (United States), 2018 | 3 | 2018 |
| Opportunities and challenges for remote microreactor operations KR Stevens, JE Oncken, HC Bryan, I Gutowska, TA Ulrich, RL Boring PhD, ... Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2023 | 2 | 2023 |
| Opportunities, Challenges, and Research Needs for Remote Microreactor Operations K Stevens, J Oncken, R Boring, T Ulrich, M Culler, H Bryan, J Browning, ... Nuclear Technology, 1-17, 2024 | 1 | 2024 |
| Epistemic Uncertainty Quantification of Deep Neural-Network Based Turbulence Closures C Grogan, S Dutta, M Tano, S Dhulipala, I Gutowska Bulletin of the American Physical Society, 2024 | | 2024 |
| Intracore Natural Circulation Study in the High Temperature Test Facility I Gutowska, R Kile, BG Woods, NR Brown Journal of Nuclear Engineering 5 (4), 500-517, 2024 | | 2024 |
| Status of the Light-Water, Small, Modular Reactors Research at Oregon State University I Gutowska, TK Howard, Q Wu, BG Woods International Conference on Nuclear Engineering 88247, V004T04A061, 2024 | | 2024 |
| Modeling for a Digital Twin-Based Remote Operation System Framework KR Stevens, JE Oncken, I Gutowska Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2024 | | 2024 |
| A THERMAL-HYDRAULIC ANALYSIS OF THE INL BOILING WATER REACTOR TEST FACILITY USING RELAP5-3D© A Prince, I Gutowska, W Marcum, N Oldham, J Barney, K Horman, ... ASTFE Digital Library, 2024 | | 2024 |
