Thermal analyses of high-power advanced thermoacoustic radioisotope power system for future space exploration missions
- 1. Institute for Space and Nuclear Power Studies and Nuclear Engineering Department, The University of New Mexico, Albuquerque, NM (United States)
Description
Highlights: • 3-D thermal analyses of 440We advanced Radioisotope Power System (RPS). • System has 8 Step-2 General Purpose Heat Source (GPHS) modules and 4 TAPCs. • Calculated Iridium alloy cladding and FWPF aeroshells temperatures in GPHS modules. • Design modifications of heat source assembly meet GPHS temperature limits. • Final design decreases total mass of heat source assembly by 19.6 kg, ∼43% saving. This paper presents the results of 3-D thermal analyses of the heat source assembly of a 440 We advanced radioisotope power system (RPS) for future space exploration missions. This high thermal efficiency RPS employs a heat source assembly of eight Step 2 General Purpose Heat Source (GPHS) modules and four Thermoacoustic Power Converter (TAPC) units. Each unit is thermally coupled to two GPHS modules. The analyses investigated the temperatures of the Iridium (Ir) alloy cladding of the 238PuO2 fuel pellets and the surface of the Fine Weave Pierced Fabric (FWPF) aeroshell in the GPHS modules to ensure reliable operation and safety in case of an unlikely reentry. Conductive coupling of the GPHS modules to the heater heads of the TAPC units produces relatively uniform axial and azimuthal distributions of heat flux and temperature. However, for this case the temperature of the Ir alloy cladding is lower than the desired values of 1173 K to maintain sufficient ductility. Adding a 5 mm wide He filled gap and decreasing the thickness of the graphite sleeve to 10 mm increased Ir cladding temperature to 1197–1174 K, which are in the desired range. The maximum surface temperatures of the FWPF graphite aeroshell of 1022–1131 K is well below the NASA specified limit of 1373 K. In addition, the total mass of the heat source assembly decreased by 19.6 kg, ∼43% saving compared to original design.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2021.111504Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2021.111504;
- PII
- S0029549321004568;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 385
- Journal Page Range
- vp.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54014886
- Subject category
- S36: MATERIALS SCIENCE; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Descriptors DEI
- CLADDING; DESIGN; DUCTILITY; FUEL PELLETS; GRAPHITE; HEAT FLUX; SURFACES; THERMAL ANALYSIS
- Descriptors DEC
- CARBON; DEPOSITION; ELEMENTS; MECHANICAL PROPERTIES; MINERALS; NONMETALS; PELLETS; SURFACE COATING; TENSILE PROPERTIES
Optional Information
- Copyright
- Copyright (c) 2021 Elsevier B.V. All rights reserved.