Two-dimensional thermal-hydraulics analyses of the Pellet Bed Reactor for Nuclear Thermal Propulsion

Conference · Tue Jun 01 04:00:00 EDT 1993

OSTI ID:5686769

Morley, N J; El-Genk, M S

Thermal-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. 20 refs.

• OSTI ID: 5686769
• Report Number(s): AIAA-Paper--93-2615; CONF-930633--
• Country of Publication: United States
• Language: English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210600* -- Power Reactors
Auxiliary
Mobile Package
& Transportable
COST ESTIMATION
DESIGN
ENERGY SOURCES
FLUIDS
FUEL ELEMENTS
FUELS
HYDRAULIC FLUIDS
ION PROPULSION
MATERIALS
NUCLEAR FUELS
PERFORMANCE
POROSITY
PROPULSION
PROPULSION REACTORS
PROPULSION SYSTEMS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTORS
RELIABILITY
TECHNOLOGY ASSESSMENT
WORKING FLUIDS