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Improvement of Nuclear Heating Evaluation inside the Core of the OSIRIS Material Testing Reactor

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Abstract

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 fuel elements axial distributions of 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.
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Dates and versions

cea-02928022 , version 1 (02-09-2020)

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  • HAL Id : cea-02928022 , version 1

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Arthur Peron, Fadhel Malouch, Cheikh M. Diop. Improvement of Nuclear Heating Evaluation inside the Core of the OSIRIS Material Testing Reactor. ISRD 2014 - 15th International Symposium on Reactor Dosimetry, May 2014, Aix en provence, France. ⟨cea-02928022⟩
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