skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

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

Abstract

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 improvementmore » in accident dosimetry evaluation and measurement techniques is needed.« less

Authors:
; ;
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
OSTI Identifier:
5776878
Report Number(s):
ORNL-6164
ON: DE85011303
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
63 RADIATION, THERMAL, AND OTHER ENVIRON. POLLUTANT EFFECTS ON LIVING ORGS. AND BIOL. MAT.; 22 GENERAL STUDIES OF NUCLEAR REACTORS; 61 RADIATION PROTECTION AND DOSIMETRY; 29 ENERGY PLANNING, POLICY AND ECONOMY; DOSIMETRY; INTERLABORATORY COMPARISONS; RADIATION ACCIDENTS; GAMMA DOSIMETRY; NEUTRON DOSIMETRY; PERSONNEL; PHANTOMS; SIMULATION; ACCIDENTS; MOCKUP; STRUCTURAL MODELS; 560151* - Radiation Effects on Animals- Man; 220900 - Nuclear Reactor Technology- Reactor Safety; 655003 - Medical Physics- Dosimetry; 290300 - Energy Planning & Policy- Environment, Health, & Safety

Citation Formats

Swaja, R E, Greene, R T, and Sims, C S. 1983 international intercomparison of nuclear accident dosimetry systems at Oak Ridge National Laboratory. United States: N. p., 1985. Web. doi:10.2172/5776878.
Swaja, R E, Greene, R T, & Sims, C S. 1983 international intercomparison of nuclear accident dosimetry systems at Oak Ridge National Laboratory. United States. https://doi.org/10.2172/5776878
Swaja, R E, Greene, R T, and Sims, C S. 1985. "1983 international intercomparison of nuclear accident dosimetry systems at Oak Ridge National Laboratory". United States. https://doi.org/10.2172/5776878. https://www.osti.gov/servlets/purl/5776878.
@article{osti_5776878,
title = {1983 international intercomparison of nuclear accident dosimetry systems at Oak Ridge National Laboratory},
author = {Swaja, R E and Greene, R T and Sims, C S},
abstractNote = {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.},
doi = {10.2172/5776878},
url = {https://www.osti.gov/biblio/5776878}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Apr 01 00:00:00 EST 1985},
month = {Mon Apr 01 00:00:00 EST 1985}
}