Model Validation Using Computational Fluid Dynamics (CFD)-Grade Experimental Database for Next Generation Nuclear Plant (NGNP) Reactor Cavity Cooling Systems with Water and Air CX(s) Applied: B3.6 Date: 11/13/2013 Location(s): Michigan Offices(s): Ida...
Office of NEPA Policy and Compliance
November 13, 2013
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Model Validation Using Computational Fluid Dynamics (CFD)-Grade Experimental Database for Next Generation Nuclear Plant (NGNP) Reactor Cavity Cooling Systems with Water and Air
CX(s) Applied: B3.6
Date: 11/13/2013
Location(s): Michigan
Offices(s): Idaho Operations Office
The University of Michigan proposes to investigate specific thermal-hydraulic issues, which will ensure that the Reactor Cavity Cooling System (RCCS), a key safety system for the Next Generation Nuclear Plant, is able to successfully accomplish its safety functions under all conditions, and will result in improved computational methodologies for the prediction of the RCCS behavior.
CX(s) Applied: B3.6
Date: 11/13/2013
Location(s): Michigan
Offices(s): Idaho Operations Office
The University of Michigan proposes to investigate specific thermal-hydraulic issues, which will ensure that the Reactor Cavity Cooling System (RCCS), a key safety system for the Next Generation Nuclear Plant, is able to successfully accomplish its safety functions under all conditions, and will result in improved computational methodologies for the prediction of the RCCS behavior.