An overview of measurements, data compilations and prediction methods for the critical heat flux in water-cooled tubes-Reference-Cited by-同舟云学术

An overview of measurements, data compilations and prediction methods for the critical heat flux in water-cooled tubes

Published:2018-05 Issue: Volume:331 Page:211-221
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Groeneveld D.C.,Ireland A.,Kaizer J.,Vasic A.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference92 articles.

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2. An Independent assessment of Groeneveld et. al.'s 1995 CHF look-up table;Baek;Nucl. Eng. Des.,1997

3. Becker, K.M., Hernborg, O, Bode, M. Eriksson, O., 1965. Burnout Data for Flow of Boiling Water in Vertical Round Ducts, Annuli and Rod Clusters. Aktiebolaget Atomenergi, Stockholm, Sweden, Report AE-177.

4. Becker, K.M. 1965. An Analytical and Experimental Study of Burnout Conditions in Vertical Round Ducts. Aktiebolaget Atomenergi, Stockholm, Sweden, Report AE-178.

5. Bennett, A.W., Hewitt, G.F., Kearsey, H.A., Keeys, R.K.F., 1965. Measurements of Burnout Heat Flux in Uniformly Heated Round Tubes at 1000 psia. United Kingdom Atomic Energy Authority, Harwell, Berkshire, United Kingdom (UK), Report AERE-R 5055.

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