Radiation Protection Dosimetry Advance Access published online on May 14, 2007
Radiation Protection Dosimetry, doi:10.1093/rpd/ncm106
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FEASIBILITY STUDY OF EXTREMITY DOSEMETER BASED ON POLYALLYLDIGLYCOLCARBONATE (CR-39) FOR NEUTRON EXPOSURE
1 Institute for Radiological Protection and Nuclear Safety, BP 17, 92262 Fontenay-aux-Roses, France
2 Atomic Energy Commission at Cadarache, 13108 Saint Paul Lez Durance, France
* Corresponding author: quang.chau{at}irsn.fr
In nuclear facilities, some activities such as reprocessing, recycling and production of bare fuel rods expose the workers to mixed neutron–photon fields. For several workplaces, particularly in glove boxes, some workers expose their hands to mixed fields. The mastery of the photon extremity dosimetry is relatively good, whereas the neutron dosimetry still raises difficulties. In this context, the Institute for Radiological Protection and Nuclear Safety (IRSN) has proposed a study on a passive neutron extremity dosemeter based on chemically etched CR-39 (PADC: polyallyldiglycolcarbonate), named PN-3, already used in routine practice for whole body dosimetry. This dosemeter is a chip of plastic sensitive to recoil protons. The chemical etching process amplifies the size of the impact. The reading system for tracks counting is composed of a microscope, a video camera and an image analyser. This system is combined with the dose evaluation algorithm. The performance of the dosemeter PN-3 has been largely studied and proved by several laboratories in terms of passive individual neutron dosemeter which is used in routine production by different companies.
This study focuses on the sensitivity of the extremity dosemeter, as well as its performance in the function of the level of the neutron energy. The dosemeter was exposed to monoenergetic neutron fields in laboratory conditions and to mixed fields in glove boxes at workplaces.