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A WIMS-NESTLE reactor physics model for an RBMK reactor
Author(s) -
R.T. Perry,
George H. Meriwether
Publication year - 1996
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/266875
Subject(s) - rbmk , nuclear engineering , thermal hydraulics , physics , nuclear physics , work (physics) , nuclear reactor , engineering , mechanics , thermodynamics , heat transfer
This work describes the static neutronic calculations made for a three-dimensional model of an RBMK (Russian) reactor. Future work will involve the use of this neutronic model and a thermal-hydraulic model in coupled calculations. The lattice code, WIMS-D, was used to obtain the cross sections for the static neutronic calculations. The static reactor neutronic calculations were made with NESTLE, a three-dimensional nodal diffusion code. The methods used to establish an RBMK reactor model for use in these codes are discussed, and the cross sections calculated are given

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