Development and comparison of a TOPAZ-II system model with experimental data
Creators
- 1. Univ. of New Mexico, Albuquerque, NM (United States). Inst. for Space Nuclear Power Studies
Description
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
Additional details
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 108
- Journal Issue
- 2
- Journal Page Range
- p. 157-170.
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26026221
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S30: DIRECT ENERGY CONVERSION;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; HEAT TRANSFER; HYDRAULICS; POTASSIUM COMPOUNDS; REACTOR SIMULATORS; SODIUM COMPOUNDS; SPACE POWER REACTORS; T CODES; THERMIONIC FUEL ELEMENTS; THERMIONIC REACTORS; TOPAZ REACTOR
- Descriptors DEC
- ALKALI METAL COMPOUNDS; ANALOG SYSTEMS; COMPUTER CODES; ENERGY TRANSFER; EVALUATION; EXPERIMENTAL REACTORS; FUEL ELEMENTS; FUNCTIONAL MODELS; HYDRIDE MODERATED REACTORS; MOBILE REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATORS