Thermal-hydraulic hot-spot analysis of IRT-5000 nuclear research reactor: Comparative safety evaluation

Author:

Taqi Al-Najjar,Ezzat Akram

Publisher

Centre for Evaluation in Education and Science (CEON/CEES)

Subject

Mechanical Engineering,Mechanics of Materials

Reference17 articles.

1. Khalil, M.Y., Abdelrazek, I.D., Nagy, M.E. and Shokr, A.M.: Hot channel factors evaluation for thermalhydraulic analysis of MTR reactors, Nukleonika, Vol. 49, No. 2, pp. 61-67, 2004.;

2. Chiang, K.Y.: Thermal Hydraulic Limits Analysis for the MIT Research Reactor Low Enrichment Uranium Core Conversion Using Statistical Propagation of Parametric Uncertainties, M.Sc. thesis, MIT, June 2012.;

3. Ardaneh, K. and Zaferanlouei, S.: An analytical solution for thermal-hydraulic analysis and safety margins in MTR-type research reactors cooled by natural convection, Annals of Nuclear Energy, Vol. 51, pp. 282-288, 2013.;

4. Farhadi, K.: Statistical calculation of hot channel factors, Journal of Nuclear and Radiation Physics, Vol. 3, No. 1, pp. 11-20, 2008.;

5. Al-Yahia, O.S. and Jo, D.: Onset of nucleate boiling for subcooled flow through a one-side heated narrow rectangular channel, Annals of Nuclear Energy, Vol. 109, pp. 30-40, 2017.;

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