Thermal-Hydraulic modelling and analysis of VVER-1200 reactor core

Author:

El-Morshedy Salah El-Din,Awad Mostafa M.,Abo El-Fetouh Mohamed

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference25 articles.

1. A coupled neutronic/thermal–hydraulic module for the transient analysis of VVER-1000 reactor during reactivity insertion accidents;Ajami;Progress Nucl. Energy (121),2020

2. New generation first-of-the kind unit – VVER-1200 design features;Asmolov;Nucl. Energy and Technology,2017

3. The determination of forced-convection surface-boiling heat transfers, Transactions of the ASME 86 (Series C -;Bergles;Journal of Heat Transfer),1964

4. Critical heat flux phenomena at high pressure & low mass fluxes: NEUP final report part I: experiments;Corradini;Project No.,2014

5. Vapor Void Fractions for Forced Convection with Subcooled Boiling at Low Flow Rate;Dix,1971

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