Skip Navigation


Radiation Protection Dosimetry Advance Access originally published online on November 10, 2004
Radiation Protection Dosimetry 2004 112(3):359-370; doi:10.1093/rpd/nch416
This Article
Right arrow Full Text
Right arrow Full Text (PDF)
Right arrow All Versions of this Article:
112/3/359    most recent
nch416v1
Right arrow Alert me when this article is cited
Right arrow Alert me if a correction is posted
Services
Right arrow Email this article to a friend
Right arrow Similar articles in this journal
Right arrow Similar articles in ISI Web of Science
Right arrow Similar articles in PubMed
Right arrow Alert me to new issues of the journal
Right arrow Add to My Personal Archive
Right arrow Download to citation manager
Right arrow Search for citing articles in:
ISI Web of Science (2)
Right arrowRequest Permissions
Google Scholar
Right arrow Articles by Girod, M.
Right arrow Articles by Postaük, J.
Right arrow Search for Related Content
PubMed
Right arrow PubMed Citation
Right arrow Articles by Girod, M.
Right arrow Articles by Postaük, J.
Social Bookmarking
Add to CiteULike   Add to Connotea   Add to Del.icio.us  
What's this?

Radiation Protection Dosimetry Vol. 112, No. 3 © Oxford University Press 2004; all rights reserved

Study and presentation of a fast neutron and photon dosemeter for area and criticality monitoring using radiophotoluminescent glass

M. Girod*, L. Bourgois, G. Cornillaux, S. Andre and J. Postaük

Service de Protection contre les Rayonnements, Commissariat à l'Energie Atomique de Saclay, Direction de l'Energie Nucléaire, DEN/SAC/DSP/SPR/SERD, CEA Saclay, 91191 Gif sur Yvette Cedex, France

* Corresponding author: girod{at}aquilon.cea.fr

This paper describes the results of a study performed on a mixed field neutron/gamma (n/{gamma}) area dosemeter incorporating radiophotoluminescent (RPL) glass detectors. RPL glass is known to be virtually insensitive to neutrons. The aim of the study was therefore to determine the neutron response of a dosemeter designed to combine n/{gamma} conversion with RPL detection capability. Monte Carlo calculations as well as measurements using monoenergetic beams and isotopic neutron sources showed this response to be constant, to within 30% in terms of H*(10), and independent of neutron energy from 250 keV to 10 MeV. For area monitoring, tests carried out in nuclear facilities (around PuO2 glove box and shipping casks containing PWR, MOX spent fuels or vitrified fission product) demonstrated that dosemeter response was accurate to within 15%, where the gamma component of the mixed n,{gamma} field remained below 1 MeV. When exposed in the Silene reactor simulating a criticality accident (1017 fissions—liquid 235U—e.g. 1 Gy neutron and 1 Gy photon), the dosemeter exhibited good correlation with reference values and other measurement technologies (again to within 30%), for both neutron and gamma absorbed dose.


Add to CiteULike CiteULike   Add to Connotea Connotea   Add to Del.icio.us Del.icio.us    What's this?




Disclaimer: Please note that abstracts for content published before 1996 were created through digital scanning and may therefore not exactly replicate the text of the original print issues. All efforts have been made to ensure accuracy, but the Publisher will not be held responsible for any remaining inaccuracies. If you require any further clarification, please contact our Customer Services Department.