Development and comparison of a TOPAZ-II system model with experimental data
- Univ. of New Mexico, Albuquerque, NM (United States). Inst. for Space Nuclear Power Studies
An integrated model of the TOPAZ-II space nuclear reactor system is developed and compared with measurements from the TOPAZ-II, V-71 unit tests. For a given reactor thermal power, the model calculates the coolant flow rate, temperature, and pressure throughout the system; load electric power; and overall system efficiency. Model predictions showed good agreement with the experimental data. The calculated coolant temperatures and pressure are within 15 K (< 2%) and 12% of the measurements, respectively. Analysis showed that at the nominal operating thermal power of the system (115 kW), and NaK coolant is highly subcooled. The largest subcooling of 365 K occurs at the exit of the electromagnetic pump, where coolant pressure is highest, and the lowest subcooling of 275 K occurs at the exit of the reactor core, where coolant temperature is highest.
- OSTI ID:
- 6834335
- Journal Information:
- Nuclear Technology; (United States), Vol. 108:2; ISSN 0029-5450
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
30 DIRECT ENERGY CONVERSION
TOPAZ REACTOR
REACTOR SIMULATORS
COMPARATIVE EVALUATIONS
HEAT TRANSFER
HYDRAULICS
POTASSIUM COMPOUNDS
SODIUM COMPOUNDS
SPACE POWER REACTORS
T CODES
THERMIONIC FUEL ELEMENTS
THERMIONIC REACTORS
ALKALI METAL COMPOUNDS
ANALOG SYSTEMS
COMPUTER CODES
ENERGY TRANSFER
EVALUATION
EXPERIMENTAL REACTORS
FLUID MECHANICS
FUEL ELEMENTS
FUNCTIONAL MODELS
HYDRIDE MODERATED REACTORS
MECHANICS
MOBILE REACTORS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SIMULATORS
NESDPS Office of Nuclear Energy Space and Defense Power Systems
210600* - Power Reactors
Auxiliary
Mobile Package
& Transportable
300400 - Thermionic Converters