Development of a Higher Fidelity Thermal Hydraulic Subchannel Capability for Simulation of LWRs

The Consortium for Advanced Simulation of Light Water Reactors is developing a core simulator capability known as the Virtual Environment for Reactor Applications Core Simulator (VERA-CS) to improve understanding of nuclear industry challenge problems that include departure from nucleate boiling (DNB), crud-induced power shift, and reactivity insertion accident. CTF is the thermal-hydraulics subchannel code that provides pin- and subchannel-resolved solution data for other VERA-CS packages responsible for calculating neutronics and crud growth behavior. This seminar will discuss the CTF methodology as well as new developments and improvements, including computational fluid dynamics guided model improvement, that have been made to improve the solution fidelity for the intended applications.

Additional Information:

Dr. Robert Salko graduated from the Pennsylvania State University in 2006 with bachelor’s degrees in both mechanical and nuclear engineering, in 2009 with a master’s degree in nuclear engineering, and in 2012 with a PhD in nuclear engineering. In 2012, Robert joined Oak Ridge National Laboratory to support development of a high-fidelity core simulator capability. Robert is currently the lead developer for the subchannel thermal hydraulics code, CTF, and some of his significant contributions have included implementation of a comprehensive software quality assurance plan, performing substantial code performance improvements, supporting coupling activities, and development and implementation of improved modeling capabilities.

 

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