The 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 to 16, 1983, at Oak Ridge National Laboratory (ORNL) using the Health Physics Research Reactor operated in the pulse mode to simulate criticality accidents. Participants measured neutron and gamma doses at area monitoring stations and on phantoms for three different shield conditions. Results 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 used TLD's to determine gamma doses with very good results. Chemical dosimeters 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. Results indicate that continued improvement in accident dosimetry evaluation and measurement techniques is needed.
- Publication:
-
NASA STI/Recon Technical Report N
- Pub Date:
- April 1985
- Bibcode:
- 1985STIN...8534382S
- Keywords:
-
- Accidents;
- Dosage;
- Dosimeters;
- Gamma Ray Bursts;
- Neutron Irradiation;
- Radiation Damage;
- Radiation Injuries;
- Radiation Measurement;
- Simulation;
- Accident Prevention;
- Nuclear Research And Test Reactors;
- Pulsed Radiation;
- Radiation Effects;
- Instrumentation and Photography