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

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.
Authors:
; ;  [1]
  1. University of West Bohemia in Pilsen, Univerzitní 8, 306 14 Pilsen (Czech Republic)
Publication Date:
OSTI Identifier:
22308419
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1608; Journal 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)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FISSION PRODUCTS; GAS LIFTS; LIQUID FUELS; MIXTURES; MOLTEN SALT REACTORS; NATURAL CONVECTION; TRITIUM; TWO-PHASE FLOW; XENON OSCILLATIONS