Study and presentation of a fast neutron and photon dosemeter for area and criticality monitoring using radiophotoluminescent glass
This paper describes the results of a study performed on a mixed field neutron/gamma (n/γ) 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 d...
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Veröffentlicht in: | Radiation protection dosimetry 2004-01, Vol.112 (3), p.359-370 |
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description | This paper describes the results of a study performed on a mixed field neutron/gamma (n/γ) 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/γ 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,γ 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. |
doi_str_mv | 10.1093/rpd/nch416 |
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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/γ 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,γ 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.</description><subject>Fast Neutrons</subject><subject>Glass</subject><subject>Isotopes</subject><subject>Models, Theoretical</subject><subject>Monte Carlo Method</subject><subject>Neutrons</subject><subject>Particle Accelerators</subject><subject>Photons</subject><subject>Radiation Dosage</subject><subject>Radiation Monitoring - methods</subject><subject>Radiometry - instrumentation</subject><subject>Radiometry - methods</subject><subject>Radiotherapy, High-Energy - methods</subject><issn>0144-8420</issn><issn>1742-3406</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2004</creationdate><recordtype>article</recordtype><sourceid>EIF</sourceid><recordid>eNpFkE1v1DAQhi1ERZfSCz8A-cQBKa2_YjtHtAVaqVKRClLVi-U4k9aQ2IvtSOy5fxx3d0UvM6OZZ75ehN5TckZJx8_TZjgP7lFQ-QqtqBKs4YLI12hFqBCNFowco7c5_yKEqa4Vb9AxbVuupGQr9HRblmGLbRjwJkGGUGzxMeA4YotHmwsOsJRUMzvkMZYaDjHDDAUSHmPCNoHdVV3yxTs7-bLFcwy-xOTDA17ys0128HHXPy2zD5Bd3YUfJpvzO3Q02inD6cGfoJ9fv_xYXzbXN9-u1p-vG1dfKE3vWpCcESW4AwAtLdcUYORusEwzYkFI1o8CpB2kYpp2vHeqpV1ldc80P0Ef93M3Kf5ZIBcz-3rGNNkAccmGCsU6JmUFP-1Bl2LOCUazSX62aWsoMc-Smyq52Ute4Q-HqUs_w_CCHjSuQLMHfC7w93_dpt9GKq5ac3l3b-7W-ru-uLg1mv8DkACQpA</recordid><startdate>20040101</startdate><enddate>20040101</enddate><creator>Girod, M.</creator><creator>Bourgois, L.</creator><creator>Cornillaux, G.</creator><creator>Andre, S.</creator><creator>Postaük, J.</creator><general>Oxford University Press</general><scope>BSCLL</scope><scope>CGR</scope><scope>CUY</scope><scope>CVF</scope><scope>ECM</scope><scope>EIF</scope><scope>NPM</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7ST</scope><scope>C1K</scope><scope>SOI</scope></search><sort><creationdate>20040101</creationdate><title>Study and presentation of a fast neutron and photon dosemeter for area and criticality monitoring using radiophotoluminescent glass</title><author>Girod, M. ; Bourgois, L. ; Cornillaux, G. ; Andre, S. ; Postaük, J.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c420t-bc5e6320743ceee86a381eef3cda2820ae462bf4e6ad6728193bc7519ee88b283</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2004</creationdate><topic>Fast Neutrons</topic><topic>Glass</topic><topic>Isotopes</topic><topic>Models, Theoretical</topic><topic>Monte Carlo Method</topic><topic>Neutrons</topic><topic>Particle Accelerators</topic><topic>Photons</topic><topic>Radiation Dosage</topic><topic>Radiation Monitoring - methods</topic><topic>Radiometry - instrumentation</topic><topic>Radiometry - methods</topic><topic>Radiotherapy, High-Energy - methods</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Girod, M.</creatorcontrib><creatorcontrib>Bourgois, L.</creatorcontrib><creatorcontrib>Cornillaux, G.</creatorcontrib><creatorcontrib>Andre, S.</creatorcontrib><creatorcontrib>Postaük, J.</creatorcontrib><collection>Istex</collection><collection>Medline</collection><collection>MEDLINE</collection><collection>MEDLINE (Ovid)</collection><collection>MEDLINE</collection><collection>MEDLINE</collection><collection>PubMed</collection><collection>CrossRef</collection><collection>Environment Abstracts</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Environment Abstracts</collection><jtitle>Radiation protection dosimetry</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Girod, M.</au><au>Bourgois, L.</au><au>Cornillaux, G.</au><au>Andre, S.</au><au>Postaük, J.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Study and presentation of a fast neutron and photon dosemeter for area and criticality monitoring using radiophotoluminescent glass</atitle><jtitle>Radiation protection dosimetry</jtitle><addtitle>Radiat Prot Dosimetry</addtitle><date>2004-01-01</date><risdate>2004</risdate><volume>112</volume><issue>3</issue><spage>359</spage><epage>370</epage><pages>359-370</pages><issn>0144-8420</issn><eissn>1742-3406</eissn><abstract>This paper describes the results of a study performed on a mixed field neutron/gamma (n/γ) 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/γ 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,γ 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.</abstract><cop>England</cop><pub>Oxford University Press</pub><pmid>15537662</pmid><doi>10.1093/rpd/nch416</doi><tpages>12</tpages></addata></record> |
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source | MEDLINE; Oxford University Press Journals All Titles (1996-Current) |
subjects | Fast Neutrons Glass Isotopes Models, Theoretical Monte Carlo Method Neutrons Particle Accelerators Photons Radiation Dosage Radiation Monitoring - methods Radiometry - instrumentation Radiometry - methods Radiotherapy, High-Energy - methods |
title | Study and presentation of a fast neutron and photon dosemeter for area and criticality monitoring using radiophotoluminescent glass |
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