Abstract
The reproducibility of measurements performed with GR-100 (LiF:Mg,Ti) from the Solid Dosimetric Detector and Method Laboratory (DML) China, GR-107 (7LiF:Mg,Ti, DML), TLD-700H (7LiF:Mg,Cu,P, Harshaw) and Al2O3:Mg,Y (Hungary) in photon and mixed photon-neutron fields was investigated. Mixed-field irradiations were performed in a thermal neutron field generated at a nuclear reactor. GR-100 sensitivity decreased after mixed-field irradiations, while no significant change was found for the other materials. Using GR-100 for the dosimetry of mixed and high-intensity fields requires careful procedures.
Original language | English |
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Pages (from-to) | 481-484 |
Number of pages | 4 |
Journal | Radiation Protection Dosimetry |
Volume | 101 |
Issue number | 1-4 |
DOIs | |
State | Published - 1 Jan 2002 |
ASJC Scopus subject areas
- Radiation
- Radiological and Ultrasound Technology
- Radiology Nuclear Medicine and imaging
- Public Health, Environmental and Occupational Health