Thermophysical properties of UF6-He mixtures relevant to circulating gas core reactor systems
Creators
- 1. University of Florida, College of Engineering, Department of Mechanical Engineering, Gainesville, Florida
Description
Thermodynamic and transport property predictions for UF6-He (gas mixtures) are presented covering the operating range of conceptual, circulating gas core nuclear systems. The gas mixtures of interest contain 10 to 20% helium by mass, which corresponds to helium mole fractions of 0.9 and higher. For UF6 partial pressure <10 atm and temperatures in the range of 500 to 2000 K, mixture density can be determined from the ideal gas equation of state with an uncertainty of < 10%. Compared to pure UF6, the thermal conductivity of the mixtures is an order of magnitude greater; specific heat is doubled while viscosity is changed very little. For identical systems, it is shown that heat transfer rates for UF6-He mixtures are five to six times greater than for pure UF6
Additional details
Publishing Information
- Journal Title
- Nucl. Technol.
- Journal Volume
- 69
- Journal Issue
- 2
- Series
- Nucl. Technol.
- Journal Page Range
- 161-169
- ISSN
- 0029-5450
- CODEN
- NUTYB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17028375
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BINARY MIXTURES; EQUATIONS OF STATE; FEASIBILITY STUDIES; GAS FUELED REACTORS; GAS FUELS; HEAT TRANSFER; HELIUM; PARTIAL PRESSURE; REACTOR CORES; SPECIFIC HEAT; THERMAL CONDUCTIVITY; URANIUM HEXAFLUORIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; DISPERSIONS; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; EQUATIONS; FLUID FUELED REACTORS; FLUORIDES; FLUORINE COMPOUNDS; FUELS; HALIDES; HALOGEN COMPOUNDS; HOMOGENEOUS REACTORS; MATERIALS; MIXTURES; NONMETALS; NUCLEAR FUELS; PHYSICAL PROPERTIES; RARE GASES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS; URANIUM FLUORIDES