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THERMAL-HYDRAULIC IN NUCLEAR REACTOR

I. Introduction An important aspect of nuclear reactor core analysis involves the determination of the optimal coolant flow distribution and pressure drop across the reactor core. On the one hand, higher coolant flow rates will lead to better heat transfer coefficients and higher Critical Heat Flux (CHF) limits. On the other hand, higher flows rates will also in large pressure drops across the reactor core, hence larger required pumping powers and larger dynamic loads on the core components. Thus, the role of the hydrodynamic and thermal-hydraulic analysis is to find proper operating conditions that assure both safe and economical operation of...

giotletinh_hd2009
20/04/2013

thermal hydraulic

nuclear reactor

energy from fission

fission yield

decay heat

coolant flow

heat transfer

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