EPJ Web of Conferences
Volume 106, 2016ISRD 15 – International Symposium on Reactor Dosimetry
|Number of page(s)||9|
|Published online||03 February 2016|
Improvement of Nuclear Heating Evaluation Inside the Core of the OSIRIS Material Testing Reactor
Alternative Energies and Atomic Energy Commission (CEA), Saclay center, DEN/DANS/DM2S/SERMA, 91191 Gif-sur-Yvette Cedex, France
a Corresponding author: ARTHUR.PERON@cea.fr
Published online: 3 February 2016
In this paper we present a nuclear heating from neutron and photon rays calculation scheme mainly based on the Monte-Carlo neutral particle transport code TRIPOLI-4® which takes into account the axial distributions of fuel element compositions. This calculation scheme is applied to the OSIRIS reactor in order to evaluate the effect of using realistic axially heterogeneous compositions instead of uniform ones. After a description of nuclear heating evaluation, the calculation scheme is described. Numerical simulations and related results are detailed and analysed to determine the impact of axially heterogeneous compositions on fluxes, power and nuclear heating.
© Owned by the authors, published by EDP Sciences, 2016
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 2.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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