Abstract
Many reactor safety simulation codes for nuclear power plants (NPPs) have been developed. However, it is very important to evaluate these codes by testing different accident scenarios in actual plant conditions. In reactor analysis, small break loss of coolant accident (SBLOCA) is an important safety issue. RELAP5-MV Visualized Modularization software is recognized as one of the best estimate transient simulation programs of light water reactors (LWR). RELAP5-MV has new options for improved modeling methods and interactive graphics display. Though the same models incorporated in RELAP5/MOD 4.0 are in RELAP5-MV, the significant difference of the latter is the interface for preparing the input deck. In this paper, RELAP5-MV is applied for the transient analysis of the primary system variation of thermal hydraulics parameters in primary loop under SBLOCA in AP1000 NPP. The upper limit of SBLOCA (10 inches) is simulated in the cold leg of the reactor and the calculations performed up to a transient time of 450,000.0 s. The results obtained from RELAP5-MV are in good agreement with those of NOTRUMP code obtained by Westinghouse when compared under the same conditions. It can be easily inferred that RELAP5-MV, in a similar manner to RELAP5/MOD4.0, is suitable for simulating a SBLOCA scenario.
Highlights
The passive safety injection system (PSIS) is employed to removal decay heat from the reactor core cooling system in cases of accident. It consists of two pressurized accumulators (ACCs) which provide a very high flow borated water in a short time after system pressure drops for a limited duration; two core makeup tanks (CMTs) which are involved in high pressure safety injection; in-containment refueling water storage tank (IRSWT) which provides a low pressure reactor coolant and lower flow but for a much longer time after pressure decreases to close the pressure of containment and provides an additional source of water for long-term core cooling [5, 9, 10]
The steady-state analysis of AP1000 reactor is performed in RELAP5-MV by using AP1000 model as described in previous section
small break loss of coolant accident (SBLOCA) Analysis and Comparison of Results Obtained from RELAP5-MV with NOTRUMP Code
Summary
The passive safety injection system (PSIS) is employed to removal decay heat from the reactor core cooling system in cases of accident It consists of two pressurized accumulators (ACCs) which provide a very high flow borated water in a short time after system pressure drops for a limited duration; two core makeup tanks (CMTs) which are involved in high pressure safety injection; in-containment refueling water storage tank (IRSWT) which provides a low pressure reactor coolant and lower flow but for a much longer time after pressure decreases to close the pressure of containment and provides an additional source of water for long-term core cooling [5, 9, 10]. It is characterized by a user friendly computer interface for building system models
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