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CNTR: Explanation of Propellant Flow and Description of Initial ExperimentsThe Centrifugal Nuclear Thermal Rocket (CNTR) is one of few designs that could enable extremely rapid missions to Mars using currently available technologies. McCarthy conducted the first conceptual study of high performance nuclear thermal propulsion (NTP) and published his findings in 1954. High performance NTP was further investigated by Princeton researchers in the early 1960s and continued by other researchers throughout the 60s, 70s, and 80s. An interagency panel conducted in 1991 demonstrated the potential of liquid core nuclear rockets, such as the Liquid Annular Reactor System (LARS), to reach temperatures up to 5000 K and specific impulses (Isp) up to 2000 s. A more recent study of versatile NTP asserts that a similar propulsion system, the Centrifugal Gas Core Reactor (CGCR), can reach an estimated Isp of 1800 s[4]. An Isp of that magnitude significantly reduces travel times and consequently health risks to flight crews. The CNTR seeks to build on the work of previous liquid core NTP systems and aims to reach an Isp in the range of 1500 s to 1800 s while using hydrogen as the propellant. However, the CNTR is not limited to hydrogen and can instead utilize other volatiles such as ammonia, methane, or water at about half the Isp of hydrogen. This flexibility expands the CNTR’s mission range considerably by providing propellant storability and the potential for directly using volatiles available in-situ.
Document ID
20205006599
Acquisition Source
Marshall Space Flight Center
Document Type
Conference Paper
Authors
Ethan Fisher
(Summer Intern Program Starkville, Mississippi, United States)
C. Miller McSwain
(Mississippi State University Starkville, Mississippi, United States)
Thomas J. Godfroy
(Godfroy Consulting)
Michael G. Houts
(Marshall Space Flight Center Redstone Arsenal, Alabama, United States)
Florent Heidet
(Argonne National Laboratory Lemont, Illinois, United States)
Rittu S. Raju
(University of Michigan–Ann Arbor Ann Arbor, Michigan, United States)
Darrin Leer
(University of North Carolina at Charlotte Charlotte, North Carolina, United States)
Jonathan T. Gates
(Argonne National Laboratory Lemont, Illinois, United States)
Date Acquired
August 20, 2020
Subject Category
Spacecraft Propulsion And Power
Meeting Information
Meeting: American Nuclear Society Winter Meeting
Location: Online
Country: US
Start Date: November 16, 2020
End Date: November 19, 2020
Sponsors: American Nuclear Society
Funding Number(s)
WBS: 039889.01.01.62
Distribution Limits
Public
Copyright
Public Use Permitted.
Technical Review
Single Expert
Keywords
Nuclear Thermal Propulsion Human Mars
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