TL detectors for gamma ray dose measurements in criticality accidents

Determination of gamma-ray dose in mixed neutron + gamma-ray fields is still a demanding task. Dosemeters used for gamma-ray dosimetry are usually in some extent sensitive to neutrons and their response variations depend on neutron energy i.e. on neutron spectra. Besides, it is necessary to take into account the energy dependence of dosemeter responses to gamma-rays. In this work, several types of thermoluminescent detectors (TLD) placed in different holders used for gamma-ray dose determination in the mixed fields were examined. Dosemeters were from three different institutions: Ruđer Bošković Institute (RBI), Croatia, Jožef Stefan Institute (JSI), Slovenia and Autoridad Regulatoria Nuclear (ARN), Argentina. All dosemeters were irradiated during the International Intercomparison of Criticality Accident Dosimetry Systems at the SILENE Reactor, Valduc, June 2002. Three accidental scenarios were reproduced and in each irradiation dosemeters were exposed placed on the front of phantom and "free-in-air". Following types of TLDs were used: 7LiF (TLD-700), CaF2:Mn and Al2O3:Mg, Y - all from RBI ; CaF2:Mn from JSI and 7LiF (TLD-700) from ARN. Reported doses were compared with the reference values as well as with the mean participants' values. The results show satisfactory agreement with other dosimetry systems used in the Intercomparison. The influence of different types of holders and applied corrections of dosemeters' readings are discussed