Presentation and comparison of experimental critical heat flux data at conditions prototypical of light water small modular reactors-Reference-Cited by-同舟云学术

Presentation and comparison of experimental critical heat flux data at conditions prototypical of light water small modular reactors

Published:2017-06 Issue: Volume:317 Page:220-231
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Greenwood M.S.,Duarte J.P.,Corradini M.

Funder

United States Department of Energy Office of Nuclear Energy’s Nuclear Energy University Programs

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

Reference19 articles.

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3. Fighetti, C.F., Reddy, D.G., 1983. Parametric Study of CHF Data, Volume 2: A Generalized Subchannel Correlation for PWR and BWR Fuel Assemblies, NP-2609 Volume 2.

4. : The Critical Heat Flux at Conditions Prototypical of Proposed Light Water Small Modular Reactors;Greenwood,2015

5. The 2006 CHF look-up table;Groeneveld;Nucl. Eng. Des.,2007

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