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Radiation Protection Dosimetry Advance Access published online on June 19, 2007
Radiation Protection Dosimetry, doi:10.1093/rpd/ncm013
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© The Author 2007. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

DESIGN OF A NEW IRSN THERMAL NEUTRON FIELD FACILITY USING MONTE-CARLO SIMULATIONS

V. Lacoste*

Institut de Radioprotection et de Sûreté Nucléaire, BP 3, 13115 Saint-Paul-lez-Durance, France

* Corresponding author: veronique.lacoste{at}irsn.fr

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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