Pellet bed reactor concept for nuclear electric propulsion

Conference · Fri Jan 15 00:00:00 EST 1993 · AIP Conference Proceedings (American Institute of Physics); (United States)

DOI:https://doi.org/10.1063/1.43209· OSTI ID:5535136

El-Genk, M S; Morley, N J ^[1]; Juhasz, A ^[2]

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1. Institute for Space Nuclear Power Studies, Dept. Chemical and Nuclear Engineering, The University of New Mexico, Albuquerque, New Mexico 87131 (United States)
2. NASA Lewis Research Center, MS: 301-3, Cleveland, Ohio 44135 (United States)

For Nuclear Electric Propulsion (NEP) applications, gas cooled nuclear reactors with dynamic energy conversion systems offer high specific power and low total mass. This paper describes the Pellet Bed Reactor (PeBR) concept for potential NEP missions to Mars. The helium cooled, 75--80 MW[sub t] PeBR, consists of a single annular fuel region filled with a randomly packed bed of spherical fuel pellets, is designed for multiple starts, and offers unique safety and operation features. Each fuel pellet, about 8--10 mm in diameter, is composed of hundreds of TRISO type fuel microspheres embedded in a graphite matrix for a full retention of fission products. To eliminate the likelihood of a single-point failure, the annular core of the PeBR is divided into three 120[degree] sectors. Each sector is self contained and separate and capable of operating and being cooled on its own and in cooperation with either one or two other sectors. Each sector is coupled to a separate, 5 MW[sub e] Closed Brayton Cycle (CBC) energy conversion unit and is subcritical for safe handling and launching. In the event of a failure of the cooling system of a core sector, the reactor power level may be reduced, allowing adjacent sectors to convect the heat away using their own cooling system, thus maintaining reactor operation. Also, due to the absence of an internal core structure in the PeBR core, fueling of the reactor can easily be performed either at the launch facility or in orbit, and refueling can be accomplished in orbit as needed to extend the power system lifetime

• OSTI ID: 5535136
• Report Number(s): CONF-930103-; CODEN: APCPCS
• Journal Information: AIP Conference Proceedings (American Institute of Physics); (United States), Vol. 271:2; Conference: 10. symposium on space nuclear power and propulsion, Albuquerque, NM (United States), 10-14 Jan 1993; ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
PEBBLE BED REACTORS
DESIGN
SPACE PROPULSION REACTORS
AFTER-HEAT REMOVAL
BRAYTON CYCLE
CLOSED-CYCLE SYSTEMS
COATED FUEL PARTICLES
FUEL SPHERES
GAS COOLED REACTORS
GRAPHITE
HELIUM
PYROLYTIC CARBON
REACTOR CONTROL SYSTEMS
REACTOR CORES
REACTOR FUELING
REACTOR SAFETY
URANIUM CARBIDES
ZIRCONIUM CARBIDES
ACTINIDE COMPOUNDS
CARBIDES
CARBON
CARBON COMPOUNDS
CONTROL SYSTEMS
ELEMENTAL MINERALS
ELEMENTS
FLUIDS
FUEL ELEMENTS
FUEL PARTICLES
GASES
HOMOGENEOUS REACTORS
MINERALS
MOBILE REACTORS
NONMETALS
POWER REACTORS
PROPULSION REACTORS
RARE GASES
REACTOR COMPONENTS
REACTORS
REMOVAL
SAFETY
SOLID HOMOGENEOUS REACTORS
SPACE POWER REACTORS
THERMODYNAMIC CYCLES
TRANSITION ELEMENT COMPOUNDS
URANIUM COMPOUNDS
ZIRCONIUM COMPOUNDS
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