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Neutron field characterisation at mixed oxide fuel plant
C Passmore1, M Million, M Kirr
1Landauer, 2 Science Road, Glenwood, IL 60425-1586, USA. cpassmore@landauerinc.com
Radiation Protection Dosimetry
|October 27, 2011
Summary
Neutron dosimetry at the AREVA Melox Plant characterized neutron fields to improve worker dose accuracy. This study evaluated passive and active neutron dosemeters during mixed oxide fuel manufacturing.
Area of Science:
- Nuclear Engineering
- Radiation Protection
- Health Physics
Background:
- Neutron radiation fields are present during mixed oxide fuel manufacturing.
- Accurate dosimetry is crucial for worker safety and regulatory compliance.
- Landauer Europe provides radiation dosimetry services at the AREVA Melox site.
Purpose of the Study:
- Characterize neutron fields at various stages of fuel production.
- Assess the performance of passive and active neutron dosemeters.
- Determine the necessity of neutron correction factors for accurate dose reporting.
Main Methods:
- Field characterization using neutron detectors.
- Testing of passive and active neutron dosemeters.
- Analysis of dosimeter responses in mixed radiation fields.
Main Results:
- Established neutron field characteristics at different process stages.
- Quantified the response of selected neutron dosemeters.
- Provided data to support the evaluation of neutron correction factors.
Conclusions:
- Neutron field characterization is essential for accurate dosimetry.
- The study supports improved neutron dose assessment for workers.
- Findings contribute to enhanced radiation protection practices at the facility.
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