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Enhancing Nuclear Safety


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Design of a new IRSN thermal neutron fileds facility using Monte-carlo simulations


Congress title :NEUDOS 10 
Congress location :Uppsala
Congress date :12/06/2006
Journal title : Radiation Protection Dosimetry 126 issue 1-4 Pages 58-63

Document type > *Congrès/colloque

Keywords >

Research Unit > IRSN/DRPH/SDE/LMDN

Authors > LACOSTE Véronique

Publication Date > 01/08/2007

Summary

The Institute for Radiological Protection and Nuclear Safety owns a graphite-moderated AmBe neutron field facility, SIGMA, that has to be reconstructed. Monte-Carlo simulations were performed to study the design of a new thermal facility based on IRSN existing facilities. Studies related to an update version of SIGMA concerned the enhancement of the thermal neutrons contribution to the dose equivalent. Calculations were mainly performed for a 252Cf neutron source distribution located at the centre of a graphite moderator block. A quasi-pure thermal neutron field was obtained with a 2.4 x 2.4 x 2.4-m3 block of graphite. A second acceptable neutron field was obtained with 3.3-MeV mono-energetic neutrons created by a 400-kV accelerator coupled to a graphite assembly of 1.5 x 1.5 x 1.5 m3. The characteristics of the studied thermal fields with the requirement for a reference calibration field are compared, and the advantages and drawbacks of the different producing methods are discussed.

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