CHF prediction in nuclear fuel elements by using round tube data-Reference-Cited by-同舟云学术

CHF prediction in nuclear fuel elements by using round tube data

Published:2002-11 Issue:17 Volume:29 Page:2071-2085
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Auxiliadora Fortini Maria,Veloso Marcelo A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference20 articles.

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2. Doroschuk, V.E., Levitan, L.L., Lantzman, F.P., 1975. Investigation into Burnout in Uniformly Heated Tubes. ASME Paper 75-WA/HT-22.

3. Tabular data for calculating burnout when boiling water in uniformly heat round tubes;Doroschuk;Thermal Engineering,1976

4. Figuetti, C.F., Reddy, D.G., 1982. Parametric study of CHF data. Technical Report EPRI-NP-2609, Electric Power Research Institute, Palo Alto, CA, vol. 3, parts 1 and 2.

5. 1986 AECL-UO critical heat flux lookup table;Groeneveld;Heat Thermal Engineering,1986

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