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Two-dimensional thermal-hydraulics analyses of the Pellet Bed Reactor for Nuclear Thermal PropulsionThermal-hydraulics design and analyses of the Pellet Bed Reactor for nuclear thermal propulsion are performed using the nuclear propulsion thermal-hydraulic analysis model to determine the 2D steady-state temperature, pressure, and flow fields in the core and optimize the orificing in the hot-frit to avoid hot spots in the core at full power operation. Results show that by properly adjusting the axial porosity profile in the hot frit, hot spots in the core can be essentially eliminated during full power operation. This important accomplishment is achieved at the expense of slightly larger pressure losses in the core because of flow restriction at the hot frit. However, the overall pressure losses is only about 11 percent of the propellant inlet pressure.
Document ID
19930066324
Acquisition Source
Legacy CDMS
Document Type
Conference Paper
Authors
Morley, Nicholas J.
(NASA Headquarters Washington, DC United States)
El-Genk, Mohamed S.
(New Mexico Univ. Albuquerque, United States)
Date Acquired
August 16, 2013
Publication Date
June 1, 1993
Subject Category
Spacecraft Propulsion And Power
Report/Patent Number
AIAA PAPER 93-2615
Meeting Information
Meeting: AIAA, SAE, ASME, and ASEE, Joint Propulsion Conference and Exhibit
Location: Monterey, CA
Country: United States
Start Date: June 28, 1993
End Date: June 30, 1993
Sponsors: ASME, ASEE, SAE, AIAA
Accession Number
93A50321
Distribution Limits
Public
Copyright
Other

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