Small-break loss of coolant accident analysis of a nuclear power plant

The postulated small-break loss-of-coolant accident (SBLOCA) occurs as a consequence of the rupture of the reactor primary flow path, and it poses a threat to the safety of nuclear power plants. Many methods have been developed over the years to study the system response under such a situation, and one of the methods is to perform the simulations on quantified system computer codes. The prior information obtained from such analyses becomes of paramount importance in designing, operating, and licensing a nuclear power system. The purpose of this study is to develop a RELAP5/MOD2 model for a nuclear power plant, achieve the steady state, and to conduct a small-break loss-of-coolant analysis