Toward the Design of a Representative Heater for Boiling Flow Characterization under PWR’s Prototypical Thermalhydraulic Conditions
Author:
Affiliation:
1. Laboratory for Thermal Hydraulics in Core and Circuits, CEA Cadarache, 13108 Saint-Paul-lez-Durance, France
2. Laboratory of Geophysical Flow, Grenoble INP, 38000 Grenoble, France
3. Laboratory of Geophysical Flow, CNRS, 38000 Grenoble, France
Abstract
Publisher
MDPI AG
Subject
Fluid Flow and Transfer Processes,Computer Science Applications,Process Chemistry and Technology,General Engineering,Instrumentation,General Materials Science
Link
https://www.mdpi.com/2076-3417/13/3/1534/pdf
Reference11 articles.
1. Kurul, N., and Podowski, M. (1990, January 19–24). Multidimensional effects in forced convetion subcooled boiling. In Proceeding of the 9th International heat Transfer Conference, Jerusalem, Israel.
2. Bubble frequencies and departure volumes at Subatmospheric Pressures;Cole;AIChe J.,1966
3. Maximum bubble diameter, maximum bubble-growth time and bubble-growth rate during the subcooled nucleate flow boiling of water up to 17.7 mn/m2;Unal;Int. J. Heat Mass Tranfer,1976
4. March, P. (1999). Caractérisation et Modélisation de L’environnement thermohydraulique et Chimique des Gaines de Combustible des Réacteurs à eau sous Pression en Présence D’ébullition. [Ph.D. Thesis, Aix-Marseille University].
5. de Munk, P.J. (1973, January 9). Two-phase flow experiments in a 10 m long sodium heated steam generator test section. Proceedings of the International Meeting on Reactor Heat Transfer, Karlsruhe, Germany.
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