skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Cooling molten salt reactors using “gas-lift”

Journal Article · · AIP Conference Proceedings
DOI:https://doi.org/10.1063/1.4892750· OSTI ID:22308419
; ;  [1]
  1. University of West Bohemia in Pilsen, Univerzitní 8, 306 14 Pilsen (Czech Republic)

This study briefly describes the selection of a type of two-phase flow, suitable for intensifying the natural flow of nuclear reactors with liquid fuel - cooling mixture molten salts and the description of a “Two-phase flow demonstrator” (TFD) used for experimental study of the “gas-lift” system and its influence on the support of natural convection. The measuring device and the application of the TDF device is described. The work serves as a model system for “gas-lift” (replacing the classic pump in the primary circuit) for high temperature MSR planned for hydrogen production. An experimental facility was proposed on the basis of which is currently being built an experimental loop containing the generator, separator bubbles and necessary accessories. This loop will model the removal of gaseous fission products and tritium. The cleaning of the fuel mixture of fluoride salts eliminates problems from Xenon poisoning in classical reactors.

OSTI ID:
22308419
Journal Information:
AIP Conference Proceedings, Vol. 1608, Issue 1; Conference: 19. international conference on the application of experimental and numerical methods in fluid mechanics and energetics 2014, Liptovsky Jan (Slovakia), 9-11 Apr 2014; Other Information: (c) 2014 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
Country of Publication:
United States
Language:
English