Document Detail

Retrospective dosimetry: dose evaluation using unheated and heated quartz from a radioactive waste storage building.
MedLine Citation:
PMID:  12382805     Owner:  NLM     Status:  MEDLINE    
In the assessment of dose received from a nuclear accident, considerable attention has been paid to retrospective dosimetry using heated materials such as household ceramics and bricks. However, unheated materials such as mortar and concrete are more commonly found in industrial sites and particularly in nuclear installations. These materials contain natural dosemeters such as quartz, which usually is less sensitive than its heated counterpart. The potential of quartz extracted from mortar in a wall of a low-level radioactive-waste storage facility containing distributed sources of 60Co and 137Cs has been investigated. Dose-depth proliles based on small aliquots and single grains from the quartz extracted from the mortar samples are reported here. These are compared with results from heated quartz and polymineral fine grains extracted from an adjacent brick, and the integrated dose recorded by environmental TLDs.
M Jain; L Bøtter-Jensen; A S Murray; H Jungner
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Publication Detail:
Type:  Journal Article; Research Support, Non-U.S. Gov't    
Journal Detail:
Title:  Radiation protection dosimetry     Volume:  101     ISSN:  0144-8420     ISO Abbreviation:  Radiat Prot Dosimetry     Publication Date:  2002  
Date Detail:
Created Date:  2002-10-17     Completed Date:  2003-04-23     Revised Date:  2008-11-21    
Medline Journal Info:
Nlm Unique ID:  8109958     Medline TA:  Radiat Prot Dosimetry     Country:  England    
Other Details:
Languages:  eng     Pagination:  525-30     Citation Subset:  IM    
Risø National Laboratory, Roskilde, Denmark.
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MeSH Terms
Construction Materials / standards*
Hot Temperature
Minerals / analysis
Quartz* / analysis
Radioactive Waste*
Reproducibility of Results
Thermoluminescent Dosimetry / methods
Reg. No./Substance:
0/Minerals; 0/Radioactive Waste; 14808-60-7/Quartz

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