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Darius Lisowski
Darius Lisowski
Nuclear Engineer, Argonne National Lab
Verified email at anl.gov
Title
Cited by
Cited by
Year
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
322014
Distributed temperature sensor testing in liquid sodium
C Gerardi, N Bremer, D Lisowski, S Lomperski
Nuclear Engineering and Design 312, 59-65, 2017
222017
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
182016
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
162013
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
142018
Experimental studies of NGNP reactor cavity cooling system with water
DD Lisowski, RM Scherrer, TC Haskin, MH Anderson, ML Corradini, ...
142011
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
132013
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
122015
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
112017
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
112016
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
92022
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
92017
Fiber optic distributed sensors for high-resolution temperature field mapping
S Lomperski, C Gerardi, D Lisowski
JoVE (Journal of Visualized Experiments), e54076, 2016
92016
Thermal hydraulic analysis of an experimental reactor cavity cooling system with water: Performance and stability
DD Lisowski
The University of Wisconsin-Madison, 2013
92013
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
82014
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
72019
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
72016
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
62020
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
62016
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
62013
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