Quasi-Diffusion Method with 3-D Cross Sections for TREAT Core Analysis
NUCLEAR TECHNOLOGY, pp. 825-838, 2020.
Abstract:
The conventional two-step neutronics method used to perform full-core reactor neutronics simulation has been used successfully for light water reactor steady-state and transient analysis. The first step in the method is to generate assembly homogenized few-group cross sections from a lattice transport calculation at the anticipated range ...More
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