OpenMC data for simulating ARC reactor blanket

Published: 5 March 2020| Version 1 | DOI: 10.17632/2bncdpftxm.1
Contributor:
Stefano Segantin

Description

The following datasets are the main OpenMC output files converted from dataframe to xlsx files. They are divided in the enrichment folder, where each salt has been parametrized over Li-6 enrichment fraction, and the mesh folder, where mesh results have been used for coming up with the cumulative curves over distance from the neutron source. Each folder contains a Python input as example of the model used.

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Neutronics Modeling

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