Twenty-first nuclear accident dosimetry intercomparison study, August 6-10, 1984

Technical Report · Wed May 01 00:00:00 EDT 1985

DOI:https://doi.org/10.2172/5642818· OSTI ID:5642818

Swaja, R E; Ragan, G E; Sims, C S

The twenty-first in a series of nuclear accident dosimetry (NAD) intercomparison (NAD) studies was conducted at the Oak Ridge National Laboratory's Dosimetry Applications Research Facility during August 6-10, 1984. The Health Physics Research Reactor operated in the pulse mode was used to simulate three criticality accidents with different radiation fields. Participants from five organizations measured neutron doses between 0.53 and 4.36 Gy and gamma doses between 0.19 and 1.01 Gy at area monitoring stations and on phantoms. About 75% of all neutron dose estimates based on foil activation, hair activation, simulated blood sodium activation, and thermoluminescent methods were within +-25% of reference values. Approximately 86% of all gamma results measured using thermoluminescent (TLD-700 or CaSO/sub 4/) systems were within +-20% of reference doses which represents a significant improvement over previous studies. Improvements observed in the ability of intercomparison participants to estimate neutron and gamma doses under criticality accident conditions can be partly attributed to experience in previous NAD studies which have provided practical tests of dosimetry systems, enabled participants to improve evaluation methods, and standardized dose reporting conventions. 16 refs., 15 tabs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5642818
• Report Number(s): ORNL-6173; ON: DE85012076
• Country of Publication: United States
• Language: English

Related Subjects

61 RADIATION PROTECTION AND DOSIMETRY
655003* -- Medical Physics-- Dosimetry
ACCIDENTS
ACCURACY
ACTIVATION DETECTORS
AIR COOLED REACTORS
BIOLOGICAL SHIELDING
COMPARATIVE EVALUATIONS
CRITICALITY
DATA
DOSEMETERS
DOSES
DOSIMETRY
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL DATA
FAST REACTORS
GAMMA DOSIMETRY
GAS COOLED REACTORS
HPRR REACTOR
INFORMATION
INTERLABORATORY COMPARISONS
LUMINESCENT DOSEMETERS
MEASURING INSTRUMENTS
MOCKUP
NEUTRON DETECTORS
NEUTRON DOSIMETRY
NUMERICAL DATA
Nuclear Criticality Safety Program (NCSP)
PHANTOMS
PULSED REACTORS
RADIATION ACCIDENTS
RADIATION DETECTORS
RADIATION DOSES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SHIELDING
STRUCTURAL MODELS
THERMOLUMINESCENT DOSEMETERS