| Evaluation of thin plate hydrodynamic stability through a combined numerical modeling and experimental effort A Tentner, C Bojanowski, E Feldman, E Wilson, G Solbrekken, C Jesse, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2017 | 15 | 2017 |
| Final Report on the Generic Test Plate Assembly Flow Test Campaign CJ Jesse, WF Jones, AM Phillips INL/EXT-20-57793 Rev. 0, 2020 | 10 | 2020 |
| Reactor physics characterization of triply periodic minimal surface-based nuclear fuel lattices N Martin, S Seo, SB Prieto, C Jesse, N Woolstenhulme Progress in Nuclear Energy 165, 104895, 2023 | 8 | 2023 |
| Gas coolant channel optimization for transformational challenge reactor J Weinmeister, C Jesse, P Jain Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2020 | 7 | 2020 |
| Fluid-Structure Interaction (FSI) Modeling of Thin Plates CJ Jesse, JC Kennedy, GL Solbrekken 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2015 | 7 | 2015 |
| Analysis of the potential for flow-induced deflection of nuclear reactor fuel plates under high velocity flows CJ Jesse University of Missouri-Columbia, 2015 | 5 | 2015 |
| Fast neutron irradiation capability in existing thermal test reactors M Worrall, N Woolstenhulme, C Downey, C Jesse, C Murdock, M Tippet Annals of Nuclear Energy 207, 110731, 2024 | 4 | 2024 |
| Thermal hydraulic analysis of the AFIP-7 irradiation test in the Advanced test Reactor–Model correlation and performance evaluation C Xing, CJ Jesse, WF Jones, MP Johnson, AM Phillips, TD Marshall Nuclear Engineering and Design 395, 111857, 2022 | 4 | 2022 |
| Nuclear thermal propulsion scoping analysis of fuel plate core configurations GJ Youinou, CS Lin, A Abou-Jaoude, CJ Jesse Idaho National Lab.(INL), Idaho Falls, ID (United States), 2020 | 4 | 2020 |
| Channel Gap Measurements of Irradiated Plate Fuel and Comparison with Post-Irradiation Plate Thickness JA Smith, CJ Jesse, WA Hanson, CL Scott, DL Cottle Nuclear Engineering and Technology 55 (6), 2195-2205, 2023 | 3 | 2023 |
| Scoping study for fast flux testing in the advanced test reactor NE Woolstenhulme, JV Brookman, CJ Jesse, CM Downey, CJ Murdock Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2023 | 2 | 2023 |
| Coolant channel design for additively manufactured reactor cores J Weinmeister, CJ Jesse, P Jain, BJ Ade, D Schappel Nuclear Science and Engineering 196 (12), 1496-1516, 2022 | 2 | 2022 |
| Channel Gap Probe EMPIrE Report JA Smith, CJ Jesse, CL Scott, DL Cottle Idaho National Lab.(INL), Idaho Falls, ID (United States), 2018 | 2 | 2018 |
| Fluid structural interaction simulation of the MP-1 plate performance irradiated in the advanced test reactor C Xing, CJ Jesse, H Ozaltun, AM Phillips, TD Marshall Nuclear Engineering and Design 414, 112653, 2023 | 1 | 2023 |
| Thermal-Hydraulic Analysis of the AFIP-7 Irradiation Test in the Advanced Test Reactor—Oxide Growth Prediction and Correlation C Xing, CJ Jesse, WF Jones, MP Johnson, AM Phillips, TD Marshall Nuclear Science and Engineering 197 (7), 1467-1478, 2023 | 1 | 2023 |
| Numerical Study on Effect of Thermal Bowing ou Peak Cladding Temperature of MARVEL Microreactor SJ Yoon, CJ Jesse, C Parisi, Y Arafat Transactions of the American Nuclear Society 129, 1178-1181, 2023 | 1 | 2023 |
| Channel gap measurments in nuclear plate fuel J Smith, C Jesse, M Marshall, C Scott, D Cottle Review of Progress in Quantitative Nondestructive Evaluation, 2019 | 1 | 2019 |
| Mid-irradiation experiment examinations of monolithic U-10Mo fuel MP-1 irradiation tests at the advanced test reactor MA Marshall, J Smith, C Scott, D Cottle, C Jesse Transactions of the American Nuclear Society 121, 696-699, 2019 | 1 | 2019 |
| Thermal and hydraulic performance of volumetrically heated triply periodic minimal surface heaters B Prussack, I Jentz, TA Moreira, N Woolstenhulme, C Jesse, G Nellis, ... Applied Thermal Engineering 248, 123291, 2024 | | 2024 |
| Thermal-Hydraulics Characterization of Triply Periodic Minimal Surface-based Nuclear Fuel SS Shah, CJ Jesse, NE Woolstenhulme, P Sabharwall 2024 Pacific Basin Nuclear Conference, PBNC 2024, 528-533, 2024 | | 2024 |
