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Study and Realisation of a Microdosimetric Detector Intended to Radioprotection Measurement.


DE88750232

Publication Date 1986
Personal Author Tinelli, P.
Page Count 207
Abstract This work concerns the realisation of a tissue equivalent proportional counter. The detector, which is sensitive to neutron and gamma radiations, is intended to measure dose equivalent for radioprotection use. The microdosimetric analysis of the pulses allows us to calculate the absorbed dose and the quality factor; it is possible to discriminate the two kinds of particules. This work is a first step before making an electronic individual dosemeter. (ERA citation 13:004192)
Keywords
  • Microdosimetry
  • Proportional Counters
  • Tissue-Equivalent Detectors
  • Dose Equivalents
  • Dosemeters
  • Gamma Dosimetry
  • Kerma
  • LET
  • Neutron Dosimetry
  • Quality Factor
  • Radiation Protection
  • Specifications
  • Tissue-Equivalent Materials
  • Foreign technology
  • ERDA/440102
Source Agency
  • TIC Foreign Exchange Reports
NTIS Subject Category
  • 77E - Nuclear Instrumentation
  • 77F - Radiation Shielding, Protection, & Safety
Corporate Authors Toulouse-3 Univ. (France).
Supplemental Notes In French.
Document Type Technical Report
Title Note These (D. es Sci.),
NTIS Issue Number 198809
Study and Realisation of a Microdosimetric Detector Intended to Radioprotection Measurement.
Study and Realisation of a Microdosimetric Detector Intended to Radioprotection Measurement.
DE88750232

  • Microdosimetry
  • Proportional Counters
  • Tissue-Equivalent Detectors
  • Dose Equivalents
  • Dosemeters
  • Gamma Dosimetry
  • Kerma
  • LET
  • Neutron Dosimetry
  • Quality Factor
  • Radiation Protection
  • Specifications
  • Tissue-Equivalent Materials
  • Foreign technology
  • ERDA/440102
  • TIC Foreign Exchange Reports
  • 77E - Nuclear Instrumentation
  • 77F - Radiation Shielding, Protection, & Safety
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