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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Nuclear Thermal Propulsion (NTP) and Power A New Capability for Outer Planet Science and Exploration
No abstract available
Nuclear Thermal Propulsion Project - Cryogenic Fluid Management Studies for NTP
No abstract available
Design Options for a Versatile Nuclear Thermal Propulsion (NTP) Stage
No abstract available
Recent FY18/FY19 NTP Materials Development Activities at NASA Marshall
No abstract available
Nuclear Thermal Propulsion (NTP) In-Space Propulsion Demo Formulation
No abstract available
Space Technology Mission Directorate Game Changing Development Program - Nuclear Thermal Propulsion (NTP) FY19 Annual Review
No abstract available
RIDE ON: RapId Design Exploration Of NTP
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Cryogenic Fluid Management Technology Maturity Assessment: Liquid Hydrogen Systems for NTP Liquid Methane/Liquid Oxygen for In Space Chemical Propulsion Stage
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Modeling Validation and Its Design Relevance for NTP Fuel Elements
The development of Nuclear Thermal Propulsion engines depends heavily on modeling and simulation of a number of disciplines—neutronic / fluid / thermal / structural are only a start. Further, rockets involve extreme conditions, particularly high material temperatures in the nuclear fuel. This paper considers validation of the underling physical models and codes and how their accuracy influences several design challenges. Several issues are identified, where models, material data, could enable design solutions. In particular, thermal and CTE mismatch stresses are a concern, and stress predictions would benefit from improved mechanical property data at high temperatures. Nuclear inter-element heating causes propellant flow maldistribution and performance risks, but a simple model provides insights. High temperature chemical diffusion should be modeled to understand fuel element mass loss.
Modeling Validation and Its Design Relevance for NTP Fuel Elements
The development of Nuclear Thermal Propulsion engines depends heavily on modeling and simulation of a number of disciplines—neutronic / fluid / thermal / structural are only a start. Further, rockets involve extreme conditions, particularly high material temperatures in the nuclear fuel. This paper considers validation of the underling physical models and codes and how their accuracy influences several design challenges. Several issues are identified, where models, material data, could enable design solutions. In particular, thermal and CTE mismatch stresses are a concern, and stress predictions would benefit from improved mechanical property data at high temperatures. Nuclear inter-element heating causes propellant flow maldistribution and performance risks, but a simple model provides insights. High temperature chemical diffusion should be modeled to understand fuel element mass loss.
NTP Engine Systems Design
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Polymer Irradiation Testing for NTP Systems
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Comparison of Convective Heat Transfer Correlations and Their Application to NTP Reactors
This study analyzes various Nusselt number and friction factor correlations and applies them to a Small Nuclear Rocket Engine model with a Sinusoidal power distribution profile to understand their effects on the temperatures and pressures inside the reactor. A nodal thermal hydraulic solver was used to determine the fluid and channel surface temperatures while also incorporating variable fluid properties and channel roughness. The results showed that the considered friction factors could essentially be used interchangeably given that their difference affected the pressure by less than 1%. However, large variations in the tube surface temperature were obtained for the different Nusselt numbers while the fluid temperature distribution was forced to remain the same. Supersonic flow conditions presented by Maynard Taylor are investigated to serve as a baseline for how experimental errors can lead to uncertainties in the reported empirical correlations. Detailed experimental investigation is necessary to determine the Nusselt number correlation that will provide the best prediction of the thermal hydraulic performance inside the reactor fluid flow channels.
Mars Transportation Assessment Study: MTAS NTP Overview
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