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Enhancing Nuclear Safety


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Radiation tests of an operational dosemeter for neutrons complying with IEC 1323

International conference on occupational radiation protection: protecting workers against exposure to ionising radiation, Geneva, 26-30 August 2002. Q.Chau*, M. Ndontchueng-Moyo**, T.Lahaye*, S. Ménard*, T. Bolognese-Milsztajn* *Institute for radioprotection and nuclear safety (IRSN), DPHD/Dosimetry Department, B.P. 17, F-92262 Fontenay-aux-Roses cedex, France ** IAEA Grant-holder, DESS Radioprotection Trainee at IRSN

Summary

Personal neutron dosimetry represents one of current difficulties in the field of workers radiological protection. The development of a new neutron dosemeter generation was necessary to comply with the recommendations of ICRP Publication 60[1] and to implement the neutron active dosimetry. Since 1993, the Institute for Nuclear Safety Protection (IPSN) leads, in association with EDF, an R&D study of a personal electronic dosemeter for neutrons. The technology transfer towards the SAPHYMO Company was started in 1998. Initially identified under the project name “DIEDAC 2”[2], the dosemeter trademark will be "Saphydose-n". This compact designed dosemeter allows estimating the personal dose equivalent Hp (10, a) in mixed neutron-gamma radiation fields. It will be adapted for any nuclear facility without prior knowledge of the neutron spectrum nor of the neutron-gamma ratio. In July 2000, a prototype was tested successfully during the evacuation of an irradiated fuel cask at the EDF nuclear power plant in Dampierre-en-Burly. During 2001 a pre-commercial dosemeter was tested under radiation following the CEI 1323 standard[3]’s recommendations. We present here the results of these preliminary tests. In December 2001 the same pre-commercial dosemeter has been submitted to the CTHIR for homologation and marketing is waited before summer 2002.

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