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Enhancing Nuclear Safety


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Consideration of experimental data from an instrumented fuel element in the evaluation of the safety of IRIS experiments in the OSIRIS reactor

N. Fournier, L. Bertrand, J. Couturier,
10th International Topical Meeting on Research Reactor Fuel Management (RRFM), Sofia, Bulgaria, 30 April to 3 May 2006,
Rapport DSR 118

Summary

    Irradiation conditions on the experimental fuel plates in the IRIS facility in the OSIRIS reactor were examined by IRSN on behalf of the French Nuclear Safety Authority to qualify new types of fuel for the research reactors. Following a presentation of the IRIS facility, this paper addresses the measures and studies carried out by the OSIRIS reactor operator in response to the questions raised by IRSN and summarises the conclusions of this expert assessment. These questions cover in particular qualification of the computer codes used to check compliance of the safety thermal hydraulic criteria, the head losses in the facility, the axial distribution of the neutron flux and risks from the swelling of the experimental fuel plates.

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