{"title":"Gamma-Ray and Neutron Dosimetry Using Semiconductor Silicon Diodes","authors":"A. Eid, M. Gomaa","doi":"10.1080/10256018108544654","DOIUrl":null,"url":null,"abstract":"Radiation response to gamma-ray absorbed dose in the range of 10 to 750 kGy and neutron absorbed dose in the range of 10 mGy to 700 Gy were investigated using Swedish manufactured silicon diode, type 5422. The results indicated that its sensitivity to gamma-rays is 17.6 m V/kGY up to 60 kGy, and its sensitivity reduces to 10-17 mV/kGy from 70 kGy up to 700 kGy within an error of ±7%, while its response to fast fission neutrons is G7 mV/Gy. Factors affecting dosimeter reading such as dosimeter reading at high temperature, dosimeter annealing and reusability are also studied. The system teas used for gamma-ray and neutron dosimetry around high level gamma-ray source, reactor ducted concrete shield, and it is also examined for reactor core dosimetry.","PeriodicalId":230732,"journal":{"name":"November 1981","volume":"200 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"1981-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"2","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"November 1981","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1080/10256018108544654","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 2
Abstract
Radiation response to gamma-ray absorbed dose in the range of 10 to 750 kGy and neutron absorbed dose in the range of 10 mGy to 700 Gy were investigated using Swedish manufactured silicon diode, type 5422. The results indicated that its sensitivity to gamma-rays is 17.6 m V/kGY up to 60 kGy, and its sensitivity reduces to 10-17 mV/kGy from 70 kGy up to 700 kGy within an error of ±7%, while its response to fast fission neutrons is G7 mV/Gy. Factors affecting dosimeter reading such as dosimeter reading at high temperature, dosimeter annealing and reusability are also studied. The system teas used for gamma-ray and neutron dosimetry around high level gamma-ray source, reactor ducted concrete shield, and it is also examined for reactor core dosimetry.
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