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Title: Mass optimization of a supercritical CO2 Brayton cycle with a direct cooled nuclear reactor for space surface power

Journal Article · · Applied Thermal Engineering
 [1];  [1]
  1. Univ. of Wisconsin, Madison, WI (United States)

A long life, reliable, and compact surface power system will be necessary to achieve future goals in space exploration. This application uniquely requires the system to be optimized with respect to mass because system mass directly drives the space launch cost associated with transporting the system to its desired location. In this study, a supercritical CO2 Brayton cycle coupled to a direct-cooled nuclear reactor was designed and optimized for mass. Robust models were developed for each Brayton cycle component in order to model the cycle performance. The three most massive components of this cycle are the radiator-based heat rejection system (subsequently referred to as the “radiator”), recuperator, and reactor. Mass correlations for the recuperator and radiator were established through interactions with component experts from industry and national labs. A reactor model was developed to predict the minimum mass reactor that satisfies neutronic and thermal limitations for given cycle conditions. The system optimization explores tradeoffs between the reactor, recuperator, and radiator sizes in order to identify the least massive system that will satisfy the power (40 kWe) and life (10 yr) requirements. To explore the effects of turbine inlet temperature on system mass, three types of microtube and shell recuperator technologies were considered: baseline stainless steel (which is consistent with the industry partner’s current designs), stainless steel with non-heritage tube sizes (which requires further development of manufacturing techniques), and Inconel (which is not a current/legacy design). Both stainless steel designs have a temperature limit of 823 K, which limits the turbine inlet temperature to 900 K. The baseline stainless steel design results in a combined mass of 738 kg. The stainless steel design allowing for non-heritage tube sizes reduces the combined mass to 674 kg (a 9% improvement). The Inconel design leads to an optimal turbine inlet temperature of 1120 K and reduces the combined mass to 391 kg (a 47% improvement). Furthermore, the interesting conclusion from this study include: (1) radiator mass dominates the total mass, and this drives the cycle to relatively high heat rejection temperatures resulting in a compressor inlet state point that is not close to the vapor dome; thus, the typical advantages of an sCO2 system are not realized, and a working fluid with a higher critical temperature may be more suitable, and (2) neutronic limitations cause the reactor size to be relatively unaffected by the power level.

Research Organization:
Univ. of Wisconsin, Madison, WI (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP); USDOE
Contributing Organization:
Creare, Sandia National Laboratory
Grant/Contract Number:
NE0008679
OSTI ID:
1646962
Alternate ID(s):
OSTI ID: 1780202
Journal Information:
Applied Thermal Engineering, Vol. 163; ISSN 1359-4311
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 23 works
Citation information provided by
Web of Science

References (10)

A Comparison of Fission Power System Options for Lunar and Mars Surface Applications conference January 2006
A comparison of Brayton and Stirling space nuclear power systems for power levels from 1 kilowatt to 10 megawatts conference January 2001
Analysis of thermal cycles and working fluids for power generation in space journal November 2007
Second law analysis of supercritical CO2 recompression Brayton cycle journal September 2009
Review of supercritical CO2 power cycle technology and current status of research and development journal October 2015
Performance analysis of heat pipe radiator unit for space nuclear power reactor journal May 2017
A Comparison of Coolant Options for Brayton Power Conversion Heat Rejection Systems conference January 2006
Design of radial turbomachinery for supercritical CO 2 systems using theoretical and numerical CFD methodologies journal September 2017
Preliminary studies of compact Brayton cycle performance for Small Modular High Temperature Gas-cooled Reactor system journal January 2015
Supercritical Carbon Dioxide turbomachinery design for water-cooled Small Modular Reactor application journal April 2014