Heat Transfer Phenomena in Supercritical Water Nuclear Reactors | Zendy

Mark Anderson | Zendy; MichaelL. Corradini | Zendy; Riccardo Bonazza | Zendy; J. Licht | Zendy

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Heat Transfer Phenomena in Supercritical Water Nuclear Reactors

Author(s) -

Mark Anderson,

MichaelL. Corradini,

Riccardo Bonazza,

J. Licht

Publication year - 2007

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/918695

Subject(s) - supercritical fluid , heat transfer , materials science , critical heat flux , heat flux , mechanics , thermodynamics , flow (mathematics) , heat transfer coefficient , water flow , physics , engineering , geotechnical engineering

A supercritical water heat transfer facility has been built at the University of Wisconsin to study heat transfer in ancircular and square annular flow channel. A series of integral heat transfer measurements has been carried out over a wide range of heat flux, mas velocity and bulk water temperatures at a pressure of 25 MPa. The circular annular test section geometry is a 1.07 cm diameter heater rod within a 4.29 diameter flow channel

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