Year: 2018
Type: report
Abstract: The PROTEUS-NODAL code is being developed as a three-dimensional (3D) neutron transport code based on homogenized geometry models of nuclear reactors. The code at present includes two solution options: diffusion theory and a nodal simplified P3 (SP3). The diffusion solution option is based upon the DIF3D-VARIANT PN transport methodology where the transport options have not been implemented due to the desire to create a SN based solution methodology. The diffusion solver works for Cartesian, hexagonal, and triangular-z geometries, while the SP3 solution option is currently available for hexagonal-z geometry only. Both diffusion and SP3 capabilities provide comparable solutions to DIF3D-VARIANT when using similar approximations. This document provides brief descriptions of inputs and outputs of the code.
DOI: 10.2172/1490693
Authors: Yeon Jung, USDOE Office of Nuclear Energy (NE), Changho Lee, Micheal Smith
Institution: Argonne National Laboratory
Language: English
Subfield: Nuclear Energy and Engineering
Field: Energy
Domain: Physical Sciences
Open Access status: green
OpenAlex ID: W2911201003