CTF, the Pennsylvania State University version of COBRA-TF, has been adopted as the subchannel thermal hydraulic (T/H) capability in the core simulator being developed by the Consortium for Advanced Simulation of Light Water Reactors (CASL). This has resulted in significant development efforts to expand the applicability of CTF to performing high-fidelity, full-core, multi-physics simulations. These efforts have focused on addressing CASL challenge problems for pressurized water reactors (PWRs), which include modeling of departure from nucleate boiling and CRUD induced power shift. Developments specific to full-core modeling capabilities include creation of a preprocessor utility for the user-friendly, rapid generation of pin-cell-resolved PWR models and implementation of a domain-decomposition parallelization of the code solution algorithm. In preparation for modeling CRUD growth phenomena, a coupling interface has been developed for CTF and the code has been incorporated into a multistate driver, which allows for modeling entire reactor operating cycles (i.e. years of operation). A simple CRUD modeling capability has been coupled to the code through this driver for capturing CRUD growth over these long operational periods. This paper presents an overview of these new features and shows results of a full-core, pin-cell resolved simulation of a Westinghouse 4-loop PWR core during a loss-of-flow transient as well as an initial coupled T/H-CRUD simulation of a 17× 17 assembly during a 15-month reactor operation cycle.
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