In the case of an accident in a nuclear power plant with combined initiating events (loss of ultimate heat sink and station blackout), an additional heat removal system could transfer the decay heat from the core to an ultimate heat sink (UHS). One specific additional heat removal system, based upon a Brayton cycle with supercritical carbon dioxide (CO2) as working fluid, is currently investigated within the European Union-funded project “sCO2-HeRo” (supercritical carbon dioxide heat removal system). It serves as a self-launching, self-propelling, and self-sustaining decay heat removal system used in severe accident scenarios. Since this Brayton cycle produces more electric power than it consumes, the excess electric power can be used inside the power plant, e.g., for recharging batteries. A small-scale demonstrator is attached to the pressurized water reactor (PWR) glass model at Gesellschaft für Simulatorschulung (GfS), Essen, Germany. In order to design and build this small-scale model, cycle calculations are performed to determine the design parameters from which a layout can be derived.
Skip Nav Destination
Article navigation
January 2019
Research-Article
Cycle Calculations of a Small-Scale Heat Removal System With Supercritical CO2 as Working Fluid
Marcel Straetz,
Marcel Straetz
Institute of Nuclear Technology and Energy
Systems (IKE),
University of Stuttgart,
Pfaffenwaldring 31,
Stuttgart D-70569, Germany
e-mail: marcel.straetz@ike.uni-stuttgart.de
Systems (IKE),
University of Stuttgart,
Pfaffenwaldring 31,
Stuttgart D-70569, Germany
e-mail: marcel.straetz@ike.uni-stuttgart.de
Search for other works by this author on:
Joerg Starflinger,
Joerg Starflinger
Institute of Nuclear Technology and Energy
Systems (IKE),
University of Stuttgart,
Pfaffenwaldring 31,
Stuttgart D-70569, Germany
e-mail: joerg.starflinger@ike.uni-stuttgart.de
Systems (IKE),
University of Stuttgart,
Pfaffenwaldring 31,
Stuttgart D-70569, Germany
e-mail: joerg.starflinger@ike.uni-stuttgart.de
Search for other works by this author on:
Rainer Mertz,
Rainer Mertz
Institute of Nuclear Technology and Energy
Systems (IKE),
University of Stuttgart,
Pfaffenwaldring 31,
Stuttgart D-70569, Germany
e-mail: rainer.mertz@ike.uni-stuttgart.de
Systems (IKE),
University of Stuttgart,
Pfaffenwaldring 31,
Stuttgart D-70569, Germany
e-mail: rainer.mertz@ike.uni-stuttgart.de
Search for other works by this author on:
Dieter Brillert
Dieter Brillert
Chair of Turbomachinery,
University Duisburg-Essen,
Lotharstraße 1,
Duisburg D-47057, Germany
e-mail: dieter.brillert@uni-due.de
University Duisburg-Essen,
Lotharstraße 1,
Duisburg D-47057, Germany
e-mail: dieter.brillert@uni-due.de
Search for other works by this author on:
Marcel Straetz
Institute of Nuclear Technology and Energy
Systems (IKE),
University of Stuttgart,
Pfaffenwaldring 31,
Stuttgart D-70569, Germany
e-mail: marcel.straetz@ike.uni-stuttgart.de
Systems (IKE),
University of Stuttgart,
Pfaffenwaldring 31,
Stuttgart D-70569, Germany
e-mail: marcel.straetz@ike.uni-stuttgart.de
Joerg Starflinger
Institute of Nuclear Technology and Energy
Systems (IKE),
University of Stuttgart,
Pfaffenwaldring 31,
Stuttgart D-70569, Germany
e-mail: joerg.starflinger@ike.uni-stuttgart.de
Systems (IKE),
University of Stuttgart,
Pfaffenwaldring 31,
Stuttgart D-70569, Germany
e-mail: joerg.starflinger@ike.uni-stuttgart.de
Rainer Mertz
Institute of Nuclear Technology and Energy
Systems (IKE),
University of Stuttgart,
Pfaffenwaldring 31,
Stuttgart D-70569, Germany
e-mail: rainer.mertz@ike.uni-stuttgart.de
Systems (IKE),
University of Stuttgart,
Pfaffenwaldring 31,
Stuttgart D-70569, Germany
e-mail: rainer.mertz@ike.uni-stuttgart.de
Dieter Brillert
Chair of Turbomachinery,
University Duisburg-Essen,
Lotharstraße 1,
Duisburg D-47057, Germany
e-mail: dieter.brillert@uni-due.de
University Duisburg-Essen,
Lotharstraße 1,
Duisburg D-47057, Germany
e-mail: dieter.brillert@uni-due.de
1Corresponding author.
Manuscript received September 22, 2017; final manuscript received March 15, 2018; published online January 24, 2019. Assoc. Editor: Xiaojing Liu.
ASME J of Nuclear Rad Sci. Jan 2019, 5(1): 011011 (6 pages)
Published Online: January 24, 2019
Article history
Received:
September 22, 2017
Revised:
March 15, 2018
Citation
Straetz, M., Starflinger, J., Mertz, R., and Brillert, D. (January 24, 2019). "Cycle Calculations of a Small-Scale Heat Removal System With Supercritical CO2 as Working Fluid." ASME. ASME J of Nuclear Rad Sci. January 2019; 5(1): 011011. https://doi.org/10.1115/1.4039884
Download citation file:
Get Email Alerts
Cited By
Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates
ASME J of Nuclear Rad Sci (April 2025)
Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy
ASME J of Nuclear Rad Sci (April 2025)
Related Articles
Mass Optimization of a Supercritical CO 2 Brayton Cycle Power Conversion System for a Mars Surface Fission Power Reactor
ASME J of Nuclear Rad Sci (July,2017)
Performance Analysis and Optimization of Supercritical CO 2 Recompression Brayton Cycle Coupled With Organic Flash Cycle With a Two-Phase Expander
J. Thermal Sci. Eng. Appl (November,2024)
Dry-Cooled Supercritical CO 2 Power for Advanced Nuclear
Reactors
J. Eng. Gas Turbines Power (January,2015)
Optimization of Supercritical CO 2 Brayton Cycle for Simple Cycle Gas Turbines Exhaust Heat Recovery Using Genetic Algorithm
J. Energy Resour. Technol (July,2018)
Related Proceedings Papers
Related Chapters
Outlook
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Control and Operational Performance
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Performance Testing of Combined Cycle Power Plant
Handbook for Cogeneration and Combined Cycle Power Plants, Second Edition