Entrainment and deposition studies in two-phase cross flow : comparison between air-water and steam-water in a square horizontal duct /

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Bibliographic Details
Main Author:	Berryman, R. J.
Corporate Authors:	U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, Atomic Energy Research Establishment (Harwell, England), United States. Government Printing Office, United States. National Technical Information Service
Other Authors:	Ralph, J. C., Wade, C. D.
Format:	Government Document Book
Language:	English
Published:	Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1981.
Subjects:	Two-phase flow. Nuclear fuel rods > Testing. Pressurized water reactors > Critical heat flux. Fluid dynamics Nuclear fuel rods > Testing Pressurized water reactors > Critical heat flux Two-phase flow Fluid mechanics. Two phase flow.

University of Minnesota

Holdings details from University of Minnesota
Call Number:	Y 3.N 88:25/1973