Abstract
The VERA core physics benchmark progression problems proposed by Consortium for Advanced Simulation of LWRs (CASL) provide a method to demonstrate the computational capabilities for reactor physics methods and software. The benchmark is based on actual fuel from the initial core loading of Watts Bar Nuclear unit 1, and consists of 10 problems ranging from a simple 2D pin problem cell to the full cycle depletion and refueling of problem a 3D reactor core configuration. In this paper, the cosRMC code is applied to perform criticality calculation of the VERA benchmark problems and the eigenvalue, assembly power distribution, differential and integral control rod worth and reactivity coefficient are obtained. By comparing the cosRMC data with the referential KENO results, it is found that the two Monte Carlo codes agree with each other well. It indicates that the cosRMC code has the capability of 2D lattice and 3D core modeling with fairly good precision as KENO.
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