Radiation Monitoring Instruments

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Link to IAEA Radiation Oncology Physics: A Handbook for Teachers and Students
Slides: Chapter 4. RADIATION MONITORING INSTRUMENTS
Text: Chapter 4. RADIATION MONITORING INSTRUMENTS

Contents

[edit] INTRODUCTION

[edit] OPERATIONAL QUANTITIES FOR RADIATION MONITORING

  1. Dosimetric quantities for radiation protection
  2. Appropriate quantities for radiation monitoring
  3. Appropriate quantities for area monitoring
  4. Ambient dose equivalent
  5. Directional dose equivalent
  6. Appropriate quantities for radiation monitoring
  7. Summary of operational quantities

[edit] AREA SURVEY METERS

  1. Ionisation chambers
  2. Proportional counters
  3. Neutron area survey meters
  4. GM counters
  5. Scintillator detectors
  6. Semiconductor detectors
  7. Commonly available features of area survey meters
  8. Calibration of survey meters
  9. Properties of survey meters

[edit] INDIVIDUAL MONITORING

  1. Film badge
  2. Thermoluminescent dosimetry (TLD) badge
  3. Radiophotoluminescent (RPL) glass dosimetry systems
  4. Optically stimulated luminescence (OSL) systems
  5. Direct reading personal monitors
  6. Calibration
  7. Properties of personal monitors

[edit] BIBLIOGRAPHY

  • ATTIX, F.H., “Introduction to radiological physics and radiation dosimetry”, Wiley, New York, New York, U.S.A. (1986).
  • INTERNATIONAL ATOMIC ENERGY AGENCY (IAEA), “Calibration of radiation protection monitoring instruments”, Safety Reports Series No 16, IAEA, Vienna, Austria (2000).
  • INTERNATIONAL ATOMIC ENERGY AGENCY (IAEA), “International basic safety standards for protection against ionizing radiation and for the safety of radiation sources”, Safety Standards Series. 115, IAEA, Vienna, Austria (1996).
  • INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION (ICRP), “Con-version coefficients for use in radiological protection against external radiation: Adopted by the ICRP and ICRU in September 1995”, ICRP Publication 78, ICRP, Oxford, United Kingdom (1997).
  • INTERNATIONAL COMMISSION ON RADIATION UNITS AND MEASUREMENTS, (ICRU), “Determination of dose equivalents resulting from external radiation sources”, ICRU Report 43, ICRU, Bethesda, Maryland, U.S.A. (1988).
  • INTERNATIONAL COMMISSION ON RADIATION UNITS AND MEASUREMENTS, (ICRU), “Measurement of dose equivalents from external photon and electron radiations”, ICRU Report 47, ICRU, Bethesda, Maryland, U.S.A. (1992).
  • INTERNATIONAL COMMISSION ON RADIATION UNITS AND MEASUREMENTS, (ICRU), “Quantities and units in radiation protection dosimetry”, ICRU Report 51, ICRU, Bethesda, Maryland, U.S.A. (1993).
  • INTERNATIONAL ORGANIZATION FOR STANDARDIZATION (ISO), “X and Gamma Reference Radiations for Calibrating Dosemeters and Dose Ratemeters and for Determining their Response as a Function of Energy”, International Standard ISO 4037. See also High Rate Series of Filtered X-Radiations, International Standard ISO 4037-1979/Addendum 1(1983); Low Rate Series of Filtered X-Radiations, International Standard ISO 4037-1979/Amendment 1-1983 (E), ISO, Geneva, Switzerland (1979).
  • INTERNATIONAL ORGANIZATION FOR STANDARDIZATION (ISO), “Reference beta radiations for calibrating dosimeters and dose rate meters and for determining their response as a function of beta radiation energy”, International Standard ISO 6980, ISO, Geneva, Switzerland (1984).
  • INTERNATIONAL ORGANIZATION FOR STANDARDIZATION (ISO), “Dosimetry of the reference radiation fields used for determining the response of protection level dosimeters and dose-rate meters at photon energies between 4 and 9 MeV”, Draft International Standard ISO/DP 9991, ISO, Geneva, Switzerland (1988).
  • INTERNATIONAL ORGANIZATION FOR STANDARDIZATION (ISO), “Dosimetry of X and Gamma Reference Radiations for Radiation Protection over the Energy Range from 9 keV to 1.3 MeV”, International Standard ISO/DIS 8963, ISO, Geneva, Switzerland (1988).
  • KNOLL, G. F., “Radiation detection and measurement”, Wiley, New York, New York, U.S.A. (1979).
  • NRPB-GS 5, “New radiation quantities recommended by ICRU for practical use in radiation protection: their implementation in the United Kingdom”, NRPB, Didcot, United Kingdom (1986).
  • NRPB document, “Dose quantities for protection against external radiations”, NRPB 4, No, 3, NRPB, Didcot, United Kingdom (1993).
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