Thermal-hydraulic modeling of porous bed reactors
Conference
·
OSTI ID:6260309
Optimum design of nuclear reactor core requires an iterative approach between the thermal-hydraulic, neutronic and operational analysis. This paper concentrates on the thermal-hydraulic behavior of a hydrogen cooled, small particle bed reactor (PBR). The PBR core, modeled here, consists of a hexagonal array of fuel elements embedded in a moderator matrix. The fuel elements are annular packed beds of fuel particles held between two porous cylindrical frits. These particles, 500 to 600 ..mu..m in diameter, have a uranium carbide core, which is coated by two layers of graphite and an outer coating of zirconium carbide. Coolant flow, radially inward, from the cold frit through the packed bed and hot frit and axially out the channel, formed by the hot frit, to a common plenum. 5 refs., 1 fig., 2 tabs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6260309
- Report Number(s):
- BNL-39916; CONF-871101-18; ON: DE87011297
- Country of Publication:
- United States
- Language:
- English
Similar Records
Thermal-hydraulic modeling of porous bed reactors
Steady-state thermal-hydraulic analysis of the pellet-bed reactor for nuclear thermal propulsion
High power density reactors based on direct cooled particle beds
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7100605
Steady-state thermal-hydraulic analysis of the pellet-bed reactor for nuclear thermal propulsion
Conference
·
Tue Dec 31 23:00:00 EST 1991
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:6683589
High power density reactors based on direct cooled particle beds
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5833879
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
ACTINIDE COMPOUNDS
ANNULAR FUEL ELEMENTS
CARBIDES
CARBON COMPOUNDS
DATA
DESIGN
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
GAS COOLED REACTORS
HEAT TRANSFER
HYDRAULICS
INFORMATION
MECHANICS
NUMERICAL DATA
REACTOR COMPONENTS
REACTORS
THEORETICAL DATA
URANIUM CARBIDES
URANIUM COMPOUNDS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
ACTINIDE COMPOUNDS
ANNULAR FUEL ELEMENTS
CARBIDES
CARBON COMPOUNDS
DATA
DESIGN
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
GAS COOLED REACTORS
HEAT TRANSFER
HYDRAULICS
INFORMATION
MECHANICS
NUMERICAL DATA
REACTOR COMPONENTS
REACTORS
THEORETICAL DATA
URANIUM CARBIDES
URANIUM COMPOUNDS