The modern nuclear reactor system operates at a level of sophistication whereby human reasoning and simple theoretical models are simply not capable of bringing to light full understanding of a system's response to some proposed perturbation, and yet, there is an inherent need to acquire such understanding. It may be run in the stand-alone mode or coupled to other NRC thermal-hydraulic codes such as RELAP5.Īdvanced computing plays a critical role in the design, licensing and operation of nuclear power plants. The code may be used in the analysis of reactivity-initiated accidents in light-water reactors where spatial effects may be important.
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