Study of Critical Heat Flux in Natural Convection–Cooled TRIGA Reactors with Single Annulus and Rod Bundle Geometries

Jun Yang,Michael Scott Greenwood,Matthew De Angelis,Michael Avery,Mark Anderson,Michael L. Corradini,James Matos,Floyd E. Dunn,E. E. Feldman

Study of Critical Heat Flux in Natural Convection–Cooled TRIGA Reactors with Single Annulus and Rod Bundle Geometries

2015

Jun Yang
Michael Scott Greenwood
Matthew De Angelis
Michael Avery
Mark Anderson
Michael L. Corradini
James Matos
Floyd E. Dunn
E. E. Feldman

A critical heat flux (CHF) experimental study at low pressure and natural convection condition has been conducted. The test apparatus is a natural circulation loop with an upward flow channel, simu...

Keywords:

Bundle
Nuclear physics
Annulus (oil well)
Natural convection
TRIGA
Critical heat flux
Physics
Nuclear engineering

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