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Fully heterogeneous predictions of thermal neutron flux in a hypothetical metal-oxide-fueled PWR
SHARP neutronics Module Development
The SHARP neutronics module, PROTEUS, includes neutron and gamma transport solvers and cross-section processing tools as well as the capability for depletion and fuel cycle analysis. The existing high-fidelity solver package was extended to be independent of reactor technology and demonstrated with 2-D MOC and Sn method simulations of LWR core configurations. Efforts to support verification and validation of the DeCART code, used as one reference solution method by the SHARP code development team, continued as part of an I-NERI collaboration with the Korean Atomic Energy Research Institute.
The development of an intermediate fidelity 2D-1D capability using 2D fully heterogeneous MOC in the radial direction coupled to 3D coarse-mesh transport was initiated. This module, called PROTEUS-2D1D, will provide heterogeneous geometry power distributions and local reaction rates at reduced computational cost in comparison to the fully 3-D exact geometry methods. Initial development of the underlying toolsets needed to construct the 2D-1D model directly from 3D CAD or mesh descriptions derived from the SHARP framework module, MOAB, has been completed. An initial 2D MOC capability, derived from the high-fidelity MOC solver of PROTEUS, was also implemented as the basis for PROTEUS-2D1D.