Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
4925858 | Nuclear Engineering and Design | 2016 | 12 Pages |
Abstract
This physical tool is described before presenting its comparison against SIMMER-III code results, including a space-and energy-dependent neutron transport kinetic model, on several test cases. Then some sensitivity studies on design parameters are presented providing preliminary information for this reactor fuel oxide core design.
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Authors
N. Marie, A. Bachrata, J.M. Seiler, F. Barjot, A. Marrel, S. Gossé, F. Bertrand,