Local Heat Transfer and CHF for Subcooled Flow Boiling - Annual Report 1997 | Zendy

Ronald D. Boyd | Zendy

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Local Heat Transfer and CHF for Subcooled Flow Boiling - Annual Report 1997

Author(s) -

Ronald D. Boyd

Publication year - 2000

Publication title -

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

Language(s) - English

Resource type - Reports

DOI - 10.2172/769390

Subject(s) - subcooling , thermal hydraulics , nuclear engineering , heat transfer , critical heat flux , reliability (semiconductor) , boiling , flow (mathematics) , heat flux , thermal , environmental science , thermodynamics , mechanical engineering , mechanics , materials science , engineering , physics , power (physics)

The Thermal Science Research Center (TSRC) at Prairie View A&M University is involved in an international fusion reactor technology development program aimed at demonstrating the technical feasibility of magnetic fusion energy. This report highlights: (1) Recent accomplishments and pinpoints thermal hydraulic problem areas of immediate concern to the development of plasma-facing components, and (2) Next generation thermal hydraulic problems which must be addressed to insure safety and reliability in component operation. More specifically, the near-term thermal hydraulic problem entails: (1) generating an appropriate data base to insure the development of single-side heat flux correlations, and (2) evaluating previously developed single-side/uniform heated transformations and correlations to determine which can be used to relate the vast two-phase heat transfer and critical heat flux (CHF) technical literature for uniformly heated flow channels to single-side heated channels

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