Analysis of the critical heat flux in round vertical tubes under low pressure and flow oscillation conditions. Applications of artificial neural network

Author:

Guanghui Su,Morita K,Fukuda K,Pidduck Mark,Dounan Jia,Miettinen Jaakko

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

Reference48 articles.

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2. Burnout in boiling heat transfer, Part II: subcooled and low-quality forced convection systems;Bergles;Nucl. Saf.,1977

3. Bobkov, V.P., Kirillov, P.L., Smogalev, I.P., Vinogradov, V.N., 1997. Look-up table developing methods for critical heat flux in rod bundles, Proceedings of the Eighth International topical meeting on nuclear reactor thermal-hydraulics (NURETH-8), September 30–October 4, Kyoto Japan, pp. 1581–1589.

4. Review of two-phase flow instability;Boure;Nucl. Eng. Des.,1973

5. Derivation of mechanistic critical heat flux model for water based on flow instability;Chang;Int. Comm. Heat Mass Transfer,1996

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