Subcooled Flow Boiling Critical Heat Flux (CHF) and Its Application to Fusion Energy Components. Part I. A Review of Fundamentals of CHF and Related Data Base
Author:
- 1 January 1985
- journal article
- review article
- Published by Taylor & Francis in Fusion Technology
- Vol. 7 (1) , 7-30
Abstract
The present understanding of critical heat flux (CHF) in subcooled flow boiling with water is reviewed and fusion reactor component high-heat flux (HHF) requirements are outlined. This survey (Parts I and II), which contains a representative coverage of the literature over the last 30 years, is concerned only with CHF in the subcooled flow boiling regime. Although not exhaustive, CHF data base parameter ranges are also given as an aid for fusion component designers in locating the appropriate data for an application. Because of the relatively HHF levels and long pulse durations in the next generation reactors, fusion components must be actively cooled. All fusion components are heated nonuniformly over their surface and their surface area ranges from 0.1 to 1000 m2. Although most components are subjected to fluxes from ∼0.005 kW/cm2 (first wall) to near 1 kW/cm2 (limiters and divertors), some components are subjected to fluxes from 2 kW/cm2 (first wall in compact reactors) to 8 kW/cm2 (beam dumps). Subcoo...Keywords
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