Influences of boil-off on the behavior of a two-phase natural circulation loop DD Lisowski, O Omotowa, MA Muci, A Tokuhiro, MH Anderson, ... International journal of multiphase flow 60, 135-148, 2014 | 32 | 2014 |
Distributed temperature sensor testing in liquid sodium C Gerardi, N Bremer, D Lisowski, S Lomperski Nuclear Engineering and Design 312, 59-65, 2017 | 22 | 2017 |
Final project report on rccs testing with air-based nstf DD Lisowski, CD Gerardi, DJ Kilsdonk, NC Bremer, SW Lomperski, R Hu, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2016 | 18 | 2016 |
Design Considerations for a Scaled Reactor Cavity Cooling System with Air for the VHTR DD Lisowski, MA Moses, MH Anderson, ML Corradini 15th International Topical Meeting on Nuclear Reactor Thermal-hydraulics …, 2013 | 16 | 2013 |
Preliminary Review Analysis of Distributed Sensors for Versatile Test Reactor (VTR) Environment A Heifetz, D Lisowski, M Weathered, Y Momozaki, HT Chien, S Bakhtiari Argonne National Lab.(ANL), Argonne, IL (United States), 2018 | 14 | 2018 |
Experimental studies of NGNP reactor cavity cooling system with water DD Lisowski, RM Scherrer, TC Haskin, MH Anderson, ML Corradini, ... | 14 | 2011 |
Study on the behavior of an asymmetrically heated reactor cavity cooling system with water in single phase DD Lisowski, TC Haskin, A Tokuhiro, MH Anderson, ML Corradini Nuclear Technology 183 (1), 75-87, 2013 | 13 | 2013 |
Thermal cycling testing of distributed fiber optic temperature sensors for high-temperature applications DD Lisowski, CD Gerardi, SW Lomperski Argonne National Lab.(ANL), Argonne, IL (United States), 2015 | 12 | 2015 |
Water NSTF Design, Instrumentation, and Test Planning DD Lisowski, CD Gerardi, R Hu, DJ Kilsdonk, NC Bremer, SW Lomperski, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2017 | 11 | 2017 |
Experimental observations of natural circulation flow in the NSTF DD Lisowski, AR Kraus, MD Bucknor, R Hu, MT Farmer Nuclear Engineering and Design 306, 124-132, 2016 | 11 | 2016 |
Development of a sodium fast reactor cartridge loop testing capability for the versatile test reactor MT Farmer, M Weathered, D Lisowski, N Bremer, D Kilsdonk, T Stack, ... Nuclear Science and Engineering 196 (sup1), 148-164, 2022 | 9 | 2022 |
Progress Report on Computational Analyses of Water-Based NSTF Q Lv, A Kraus, R Hu, M Bucknor, D Lisowski, D Nunez Argonne National Lab.(ANL), Argonne, IL (United States), 2017 | 9 | 2017 |
Fiber optic distributed sensors for high-resolution temperature field mapping S Lomperski, C Gerardi, D Lisowski JoVE (Journal of Visualized Experiments), e54076, 2016 | 9 | 2016 |
Thermal hydraulic analysis of an experimental reactor cavity cooling system with water: Performance and stability DD Lisowski The University of Wisconsin-Madison, 2013 | 9 | 2013 |
Design Report for the ½ Scale Air-Cooled RCCS Tests in the Natural convection Shutdown heat removal Test Facility (NSTF) DD Lisowski, MT Farmer, S Lomperski, DJ Kilsdonk, N Bremer, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2014 | 8 | 2014 |
RCCS Testing with the Water-based NSTF: Year-1 Single-Phase Results D Lisowski, Q Lv, R Hu, A Kraus, N Bremer, DJ Kilsdonk, M Farmer Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 7 | 2019 |
Mechanisms Engineering Test Loop-Phase 1 Status Report D Kultgen, C Grandy, M Hvasta, D Lisowski, W Toter, A Borowski Argonne National Lab.(ANL), Argonne, IL (United States), 2016 | 7 | 2016 |
Report on Year-2 of Water NSTF Matrix Testing: Two-Phase Baseline & Repeatability D Lisowski, Q Lv, N Bremer, R Hu, A Kraus, D Kilsdonk, S Lomperski, ... Argonne National Lab (ANL), Lemont, IL (United States), ANL-ART-206, 2020 | 6 | 2020 |
Comparisons of RELAP5-3D Analyses to Experimental Data from the Natural Convection Shutdown Heat Removal Test Facility M Bucknor, R Hu, D Lisowski, A Kraus Argonne National Lab.(ANL), Argonne, IL (United States), 2016 | 6 | 2016 |
Power Investigations on the Two-Phase Behavior and Instability in an Experimental Reactor Cavity Cooling System with Water D Lisowski, O Omotowa, A Tokuhiro, M Anderson, M Corradini The 15th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics …, 2013 | 6 | 2013 |