A solid reactor core thermal model for nuclear thermal rockets. [He,Hz]
- Reactor Design and Analysis Group, Los Alamos National Laboratory, Los Alamos, New Mexico (USA)
A Helium/Hydrogen Cooled Reactor Analysis (HERA) computer code has been developed. HERA has the ability to model arbitrary geometries in three dimensions, which allows the user to easily analyze reactor cores constructed of prismatic graphite elements. The code accounts for heat generation in the fuel, control rods, and other structures; conduction and radiation across gaps; convection to the coolant; and a variety of boundary conditions. The numerical solution scheme has been optimized for vector computers, making long transient analyses economical. Time integration is either explicit or implicit, which allows the use of the model to accurately calculate both short- or long-term transients with an efficient use of computer time. Both the basic spatial and temporal integration schemes have been benchmarked against analytical solutions.
- OSTI ID:
- 5356312
- Report Number(s):
- CONF-910116-; CODEN: APCPC; TRN: 91-027512
- Journal Information:
- AIP Conference Proceedings (American Institute of Physics); (United States), Vol. 217:3; Conference: 8. symposium on space nuclear power systems, Albuquerque, NM (United States), 6-10 Jan 1991; ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
REACTOR CORES
COMPUTERIZED SIMULATION
SPACE PROPULSION REACTORS
COOLANTS
GAS COOLED REACTORS
HEAT TRANSFER
HELIUM
HYDROGEN
REACTOR CONTROL SYSTEMS
ROCKETS
TRANSIENTS
CONTROL SYSTEMS
ELEMENTS
ENERGY TRANSFER
FLUIDS
GASES
MOBILE REACTORS
NONMETALS
POWER REACTORS
PROPULSION REACTORS
RARE GASES
REACTOR COMPONENTS
REACTORS
SIMULATION
SPACE POWER REACTORS
NESDPS Office of Nuclear Energy Space and Defense Power Systems
220800* - Nuclear Reactor Technology- Propulsion Reactors