1983 international intercomparison of nuclear accident dosimetry systems at Oak Ridge National Laboratory

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An international intercomparison of nuclear accident dosimetry systems was conducted during September 12-16, 1983, at Oak Ridge National Laboratory (ORNL) using the Health Physics Research Reactor operated in the pulse mode to simulate criticality accidents. This study marked the twentieth in a series of annual accident dosimetry intercomparisons conducted at ORNL. Participants from ten organizations attended this intercomparison and measured neutron and gamma doses at area monitoring stations and on phantoms for three different shield conditions. Results of this study indicate that foil activation techniques are the most popular and accurate method of determining accident-level neutron doses at area monitoring ... continued below

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Pages: 42

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Swaja, R.E.; Greene, R.T. & Sims, C.S. April 1, 1985.

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Description

An international intercomparison of nuclear accident dosimetry systems was conducted during September 12-16, 1983, at Oak Ridge National Laboratory (ORNL) using the Health Physics Research Reactor operated in the pulse mode to simulate criticality accidents. This study marked the twentieth in a series of annual accident dosimetry intercomparisons conducted at ORNL. Participants from ten organizations attended this intercomparison and measured neutron and gamma doses at area monitoring stations and on phantoms for three different shield conditions. Results of this study indicate that foil activation techniques are the most popular and accurate method of determining accident-level neutron doses at area monitoring stations. For personnel monitoring, foil activation, blood sodium activation, and thermoluminescent (TL) methods are all capable of providing accurate dose estimates in a variety of radiation fields. All participants in this study used TLD's to determine gamma doses with very good results on the average. Chemical dosemeters were also shown to be capable of yielding accurate estimates of total neutron plus gamma doses in a variety of radiation fields. While 83% of all neutron measurements satisfied regulatory standards relative to reference values, only 39% of all gamma results satisfied corresponding guidelines for gamma measurements. These results indicate that continued improvement in accident dosimetry evaluation and measurement techniques is needed.

Physical Description

Pages: 42

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NTIS, PC A03/MF A01.

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  • Other: DE85011303
  • Report No.: ORNL-6164
  • Grant Number: AC05-84OR21400
  • DOI: 10.2172/5776878 | External Link
  • Office of Scientific & Technical Information Report Number: 5776878
  • Archival Resource Key: ark:/67531/metadc1100678

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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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  • April 1, 1985

Added to The UNT Digital Library

  • Feb. 18, 2018, 3:59 p.m.

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  • May 11, 2018, 12:20 p.m.

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Swaja, R.E.; Greene, R.T. & Sims, C.S. 1983 international intercomparison of nuclear accident dosimetry systems at Oak Ridge National Laboratory, report, April 1, 1985; Tennessee. (digital.library.unt.edu/ark:/67531/metadc1100678/: accessed August 14, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.