Related Experiment Videos
Czech results at criticality dosimetry intercomparison 2002
Spurný Frantisek1, Trousil Jaroslav
1Nuclear Physics Institute, Department of Radiation Dosimetry, Czech Academy of Sciences, Na Truhlárce 39/64, 18086 Praha 8, Czech Republic. spurny@ujf.cas.cz
Radiation Protection Dosimetry
|September 9, 2004
Summary
Czech participants evaluated two criticality dosimetry systems for accident exposure. Thermoluminescent detectors (TLDs) and Si-diodes provided reliable neutron dose estimations, while routine systems showed limitations for high neutron doses.
Area of Science:
- Nuclear physics and dosimetry
- Radiation protection and safety
Background:
- Criticality accidents pose significant radiation exposure risks.
- Accurate dosimetry is crucial for assessing accidental doses and ensuring worker safety.
- Existing personal dosimetry services need evaluation for criticality accident scenarios.
Purpose of the Study:
- To assess the reliability of two distinct criticality dosimetry systems.
- To evaluate the performance of routine Czech personal dosimetry equipment in criticality accidents.
- To identify limitations in current dosimetry methods for high-level neutron exposure.
Main Methods:
- Testing of thermoluminescent detectors (TLDs) (Al-P glasses) and Si-diodes as passive neutron dosemeters.
- Evaluation of routine individual dosemeters used in the Czech personal dosimetry service.
- Analysis of etched track detectors with 232Th or 235U-Al alloy for neutron dosimetry.
Main Results:
- The TLD and Si-diode system provided reliable estimations of accidental neutron doses.
- Routine photon dosimetry systems (TLDs, film badges) performed adequately.
- Etched track detectors exhibited track density saturation, limiting accurate neutron dose measurement above approximately 1 Gy for neutrons >1 MeV.
Conclusions:
- The tested passive neutron dosimetry system is suitable for reliable accidental dose assessment.
- Routine photon dosimetry is generally reliable for criticality events.
- Limitations exist for neutron dosimetry at high doses (>1 Gy) with etched track detectors using spark counting.