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. PARCS: The Purdue Advanced Reactor Core Simulator (PARCS) is a computer code that solves the time-dependent two-group neutron diffusion equation in three-dimensional Cartesian geometry using nodal methods to obtain the transient neutron flux distribution.Reactor kinetics are used to obtain reactor transient neutron flux distributions: FRAPTRAN is a computer code used for transient and design basis accident analysis of the behavior of a single fuel rod under off-normal reactor operation conditions. ![]()
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