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Moderator Considerations for Space Nuclear Power and Propulsion SystemsNuclear reactors have the potential to provide high energy density to enable sustainable surface power and advanced propulsion methods needed for human exploration activities at the moon and mars. Current mission planning is surveying different reactor types for space power and propulsion application. Of these reactor types, the use of a moderator within the reactor can enable reduced enrichment, reduce overall fuel loadings, and minimize the critical size of the reactor compared to unmoderated reference systems. This proceeding summarizes some moderator materials identified for space reactor applications: zirconium hydride, yttrium hydride, beryllium, and beryllium oxide, and the unique design considerations inherent to surface power and nuclear thermal propulsion reactor designs. It was found that there are four key considerations during the moderator selection and design process: nuclear properties, thermophysical & mechanical properties, manufacture & readiness, and environmental compatibility. Surface power reactors can benefit from moderators which minimize overall system mass and are capable of surviving high temperature irradiation environments for years with little degradation. Nuclear thermal propulsion reactors can benefit from moderators which are capable of retaining structural integrity under multiple burns while being exposed to a wide temperature range (40 < T < 500+ K). Moderator materials which exhibit good stability under irradiation and high temperature operation, minimize fuel pitch, and are high readiness are desirable for near term implementation.
Document ID
20210010285
Acquisition Source
Langley Research Center
Document Type
Conference Paper
Authors
Kelsa Benensky Palomares
(Analytical Mechanics Associates (United States) Hampton, Virginia, United States)
Date Acquired
February 18, 2021
Subject Category
Engineering (General)
Nuclear Physics
Meeting Information
Meeting: Nuclear and Emerging Technologies for Space 2021
Location: Knoxville, TN
Country: US
Start Date: April 26, 2021
End Date: April 30, 2021
Sponsors: Oak Ridge National Laboratory
Funding Number(s)
CONTRACT_GRANT: 80LARC17C0003
TASK: 10.020.000
Distribution Limits
Public
Copyright
Public Use Permitted.
Technical Review
Single Expert
Keywords
nuclear thermal propulsion
materials
moderator
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