The main object of interest was a typical fuel assembly, which constitutes a core of the nuclear reactor.
The aim of the paper is to describe the phenomena and calculate thermal-hydraulic characteristic parameters
in the fuel assembly for a European Pressurized Reactor (EPR). To perform thermal-hydraulic calculations, the
RELAP5 code was used. This code allows to simulate steady and transient states for reactor applications. It is
also an appropriate calculation tool in the event of a loss-of-coolant accident in light water reactors. The fuel
assembly model with nodalization in the RELAP5 (Reactor Excursion and Leak Analysis Program) code was
presented. The calculations of two steady states for the fuel assembly were performed: the nominal steady-state
conditions and the coolant flow rate decreased to 60% of the nominal EPR flow rate. The calculation for one
transient state for a linearly decreasing flow rate of coolant was simulated until a new level was stabilized and
SCRAM occurred. To check the correctness of the obtained results, the authors compared them against the reactor
technical documentation available in the bibliography. The obtained results concerning steady states nearly
match the design data. The hypothetical transient showed the importance of the need for correct cooling in the
reactor during occurrences exceeding normal operation. The performed analysis indicated consequences of
the coolant flow rate limitations during the reactor operation.
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