Third Personnel Dosimetry Intercomparison Study

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The third Personnel Dosimetery Intercomparison Study was held at the Oak Ridge National Laboratory Dosimetry Applications Research Facility during March 15--16, 1977. The Health Physics Research Reactor (HPRR), used unshielded, with a 12-cm-thick Lucite shield or a 13-cm-thick steel shield, provided three neutron and gamma-ray spectra. The characteristics of these fields such as neutron energy spectra, intensity, and uniformity had been measured previously during nuclear accident dosimetry studies. Exposures were made to simulate total exposures likely to be encountered in personnel dosimetry. Neutron dose equivalents of the order of 500 millirem were produced by controlling the reactor power level and ... continued below

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Pages: 20

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Gilley, L. W. & Dickson, H. W. January 1, 1979.

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Description

The third Personnel Dosimetery Intercomparison Study was held at the Oak Ridge National Laboratory Dosimetry Applications Research Facility during March 15--16, 1977. The Health Physics Research Reactor (HPRR), used unshielded, with a 12-cm-thick Lucite shield or a 13-cm-thick steel shield, provided three neutron and gamma-ray spectra. The characteristics of these fields such as neutron energy spectra, intensity, and uniformity had been measured previously during nuclear accident dosimetry studies. Exposures were made to simulate total exposures likely to be encountered in personnel dosimetry. Neutron dose equivalents of the order of 500 millirem were produced by controlling the reactor power level and exposure time. Dosimeters were mounted on the trunk section of water-filled phantoms, the front edges of which were located 3 m from the reactor center. When shields were used they were placed at 2 m from the core. Sulfur pellets exposed at a standard location on the reactor during the intercomparison were used to calculate values of tissue kerma for neutrons at the 3-m position based on previous measurements. Using the fission yield and the calculated leakage of the HPRR, the neutron fluence was calculated for each reactor run. Then the dose was calculated based on the HPRR neutron spectra and the dose conversion factors, which had been calculated previously for the three spectra. The results of these personnel dosimetry intercomparison studies reveal that estimates of dose equivalent vary over a wide range. The standard deviation of the mean of participants data was in the range of 25 to 50%.

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Pages: 20

Notes

Dep. NTIS, PC A02/MF A01.

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  • Report No.: ORNL/TM-6114
  • Grant Number: W-7405-ENG-26
  • DOI: 10.2172/6472903 | External Link
  • Office of Scientific & Technical Information Report Number: 6472903
  • Archival Resource Key: ark:/67531/metadc1206957

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • January 1, 1979

Added to The UNT Digital Library

  • July 5, 2018, 11:11 p.m.

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  • Aug. 30, 2018, 5:47 p.m.

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Gilley, L. W. & Dickson, H. W. Third Personnel Dosimetry Intercomparison Study, report, January 1, 1979; United States. (digital.library.unt.edu/ark:/67531/metadc1206957/: accessed January 15, 2019), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.