[en] From the application of the microdosimetric approach in dosimetry, the standard TEPC, i.e., Rossi-type detector, was found to be a well-suited device to measure 'first collision' neutron kerma and develop lineal energy spectra for incident neutrons. Subsequently, several attempts were carried out to assess the ambient dose equivalent for neutrons, with a mixed outcome, through the evaluation of the mean quality factor. The ICRU report 63, released in 2000, has officially recognized a good agreement between theoretical Kerma factor and value measured with standard TEPC5 for neutron energies ranging over 5-66 MeV. As a follow-up, benchmark with simulated results for Kerma calculation and lineal energy spectra concluded to a satisfactory agreement for Monte-Carlo transport codes such as FLUKA or GEANT4. Nevertheless, previous studies have highlighted major discrepancies with MCNP results for energy above the capture threshold, mainly stemming from the weakness of the alpha release. This paper emphasizes the improvement of the kerma factor calculation as well as the development of lineal energy spectra from a standard A150 plastic-wall TEPC with MCNP6.1. The shortcomings of the alpha release are overcome using INCL4/ABLA implementation instead of the default model for the Intra-nuclear cascade. This new approach lead to lineal energy spectra overlapping those from experiments. In addition, the neutron kerma is evaluated with a mean relative deviation not exceeding 5% of the ICRU standard values, for mono-energies from 100 keV to 19 MeV. This new approach is also relevant for usual neutron sources as AmBe and Cf-252 with a maximum deviation of roughly 6%. Nevertheless, major discrepancies remain for evaluation of the quality factor at the depth of 10 mm inside de ICRU sphere, with a mean relative deviation of 17%. However, this finding is consistent with discrepancies in literature. As regards the prospects, satisfactory results on lineal energy spectra and kerma evaluation henceforth offers the possibility to simulate microdosimetric spectra and determine neutron kerma for energies higher than a hundred keV up to twenty MeV. (authors)

[en] Recent studies in our laboratory have proved that electrochemical etching (ECE) of polycarbonate track detectors (PCTD) under 50 Hz – high voltage (HV) field conditions has potentials for time-integrated heavy charged particle detection and dosimetry applications. The rationale in the study is the ECE process of alpha particle tracks in 1 mm thick PCTDs by a 50 Hz – HV generator at optimized ECE conditions. Tracks of 3.2 MeV alpha particles from a collimated beam of an ²⁴¹Am source degraded in air and background tracks were registered. The effects of HV and ECE duration on alpha track registration efficiency and track diameters were studied for 3 sets of 50 Hz – 4, 5 and 6 kV field conditions in a PEW solution (potassium hydroxide, ethanol and water) at 26 °C. The optimized ECE conditions obtained at this stage of development for 1 mm thick PCTDs are 50 Hz – 4 kV in PEW solution at 26 °C for 10 h. Alpha track registration efficiency at 3.2 MeV is about 30% with 37 ± 6 μm mean track diameter. The mean background track density at the above stated optimized conditions is about 571 ± 16 tracks.cm⁻² with a mean diameter of 65 ± 5 μm. All tracks are observable by the unaided eyes. The mean background track diameter is near two times larger than that of alpha particle tracks at the optimum conditions applied; they are easily distinguished against each other. This high background track density while at this stage of development seems a drawback for low dose and low fluence particle applications, it has minimal effects on high fluence ion detection applications. The simple 50 Hz – HV generator used proved to be convenient for efficient alpha track amplifications. Studies are underway for improvement of the method in particular for reducing background track density. - Highlights: • Alpha particle tracks of 3.2 MeV were registered in 1 mm thick PC using 50 Hz – HV ECE mehtod. • Effects of HV and ECE duration on alpha and background track registration were studied. • ECE conditions were optimized with PEW etchant at 26 °C for 10 h at 50 Hz – 4 kV. • Efficiency of 30% for 3.2 MeV alphas with 37 ± 6 μm mean track diameter was obtained. • High background track density of 571 ± 16 tracks.cm⁻² is a drawback which is under improvement

[en] Seasonal (winter-summer) indoor and soil radon comparison is made in two villages in Najran region, south west of Saudi Arabia, using CR-39 Dosimeter. Summer indoor radon concentrations were measured in the villages of Fara Al-Jabal and Hadadah. The respective winter-summer average values of 42 ± 4 Bq m⁻³ and 74 ± 5 Bq m⁻³ are measured in Fara Al-Jable village and the average values of 47 ± 4 Bq m⁻³ and 76 ± 5 Bq m⁻³ are measured in Hadadah village. The respective winter-summer soil values are 1.40 ± 0.21 kBq m⁻³ and 0.99 ± 0.04 kBq m⁻³ in Fara Al-Jabal village while those measured in Hadadah village are 2.90 ± 0.17 kBq m⁻³ and 1.40 ± 0.66 kBq m⁻³. Indoor radon levels are found to be seasonal dependent while that of soil are found seasonal and location dependent. Meteorological and geological factors are expected to have caused the measured significant differences in radon levels in dwellings and soil in the two villages. - Highlights: • Indoor and Soil radon levels are measured in Najran region, Saudi Arabia. • Indoor radon levels are location independent but seasonal dependant. • Soil radon levels are seasonal and location dependent. • Meteorological and geological factors may have caused the differences

[en] Results of continuous spectral monitoring of indoor gamma background are reported for seismological application in one fault zone of the Western Caucasus. Background count rates were recorded every 5 min since 2004. Two detectors (a scintillation crystal CsI(Tl), 200 mm × 150 mm in a low background metal screen and a NaI(Tl) detector, 90 mm × 90 mm outside of the screen) were used. Various intervals of energy of gamma rays, for example, (2.50–3.40) MeV, (1.70–2.00) MeV, (1.35–1.55) MeV and others were analyzed. Averages for all measurements as well as seasonal and hourly changes of count rate of detectors were obtained. As an example, for the interval (1.70–2.00) MeV a minimal monthly count rate of detector CsI(Tl) was observed in June, and the maximal monthly count rate of detector NaI(Tl) was observed in July. Factors of correlation between different intervals of energy of gamma rays were also investigated. Strong changes of annual, monthly and daily factors were obtained. In each daily curve of all intervals of energy of gamma rays, the first Fourier harmonic was calculated. The deviations from 3σ (“splash”), which are upward or downward from the first harmonic, were compared with the seismological data. It was possible to correlate the low background dates of “splashes” with the dates of regional earthquakes through 9 ± 1 days. Change of ratio of count rate in different intervals of energy of gamma rays can be used to study processes of preparation of earthquakes. The factor of correlations between intervals (2.50–3.40) MeV and (1.70–2.00) MeV increased to almost 1.00 close to earthquakes. This effect was obtained in low background screen. Connection of the gamma data with the meteorological data was not obtained. - Highlights: • Count rate of different gamma spectrometers was investigated. • Annual, monthly and daily variations are obtained. • The gamma data can be used for the forecast of earthquakes

[en] New commercial dosimetry systems need careful characterization and can benefit from the comparison with similar, in-house developed solutions. A comparison between such two dosimetry systems, both based on fibre-coupled organic plastic scintillator detectors, is presented. One system is the Exradin W1, fully commercialized by Standard Imaging, while the other system is the non-commercial ME40 system, developed by DTU Nutech with the aim of fundamental dosimetric research. Both systems employ plastic scintillator detectors that can be considered similar in design, calibrated using the same method, but differing primarily in the signal detection hardware. The two systems were compared with respect to essential dosimetric properties, with the purpose of testing their performance under conditions less well discussed in the literature. A Farmer ionization chamber was used as the primary reference of the comparison. The study demonstrated that the Cerenkov light ratio calibration coefficient of both systems was not constant, but changed systematically with photon beam quality to a maximum difference of 1.1%. Calibration with respect to stem effect correction should therefore be performed for every investigated beam quality when using plastic scintillator detectors. Both systems were found to be dose rate independent, even for the highest instantaneous dose rate evaluated (1.5 mGy per pulse). Low-dose measurements revealed large uncertainties for both systems, although the ME40 system handled short beam deliveries under reference conditions with accuracy and precision within 0.4%. Changes in response due to field size dependence were investigated and found to be as large as 3.3% for the W1 and 5.4% for the ME40, biasing output factor measurements in large fields. Great caution is therefore advised if using either system for measurements in large fields or under circumstances where the fibre irradiation geometry is unfavourable. Measurements of reference dose to water yielded differences up to 1.5% when compared with the Farmer ionization chamber for all investigated beam qualities. - Highlights: • The Exradin W1 scintillator was compared with an in-house developed system. • The stem effect correction was found to be beam quality dependent. • Large uncertainties were seen for measurements in low-dose conditions. • Field size dependence was evident for large field measurements. • Reference dose measurements agreed within 1.5% with a Farmer ionization chamber

[en] The state-of-the-art in the use of thermoluminescence for the measurement of energy imparted by ionizing radiation is discussed. Emphasis is on the advantages obtainable by the use of computerized glow curve analysis in (i) quality control, (ii) low dose environmental dosimetry, (iii) medical applications (especially precision) and microdosimetric applications, and (iv) mixed field ionization-density–dosimetry. Possible frontiers of future research are highlighted: (i) vector representation in glow curve analysis, (ii) combined OSL/TL measurements, (iii) detection of sub-ionization electrons, (iv) requirements for new TL materials and (v) theoretical subjects involving kinetic modeling invoking localized/delocalized recombination applied to dose response and track structure theory including creation of defects. - Highlights:: • State of the art in thermoluminescence dosimetry. • Benefits of computerized glow curve deconvolution. • Frontiers of future research:new materials, mixed-field dosimetry. • Localized/delocalized kinetic theory:ionization density dependence. • Kinetic theory:creation of defects:track structure theory

[en] A new OSL phosphor CaSO₄:Eu was developed. The phosphor shows good OSL sensitivity which is about 55% of commercially available Al₂O₃:C. The phosphor also shows good TL sensitivity and the dosimetric peak, which appears around 186 °C, has sensitivity nearly 50% of Al₂O₃:C. After OSL readout of the irradiated sample, the TL peak around 250 °C depletes completely, with partial depletion of peak around 186 °C. Since the traps responsible for the high temperature peak are involved for the observed OSL, the sample shows low post-irradiation fading. The OSL decay is similar to Al₂O₃:C. Thus this phosphor due to its good OSL sensitivity, linear dose response, low fading and simple preparation technique could be useful for radiation dosimetry applications. - Highlights: • In this paper for the first time we report intense TL and OSL in CaSO4:Eu phosphor prepared by precipitation method. • The CaSO₄:Eu sample showed good OSL sensitivity which is about 55% of that of commercially available Al₂O₃:C. • The OSL decay is similar to Al₂O₃:C has linear dose response, negligible fading

[en] This work evaluates the dosimetric properties of crystals of CaSO₄ doped with unusual elements, such as europium (Eu) and silver (Ag), including their nanoparticle forms, after the incorporation of glass or Teflon and compares them with well-known thermoluminescent dosimeters (TLD). X-ray diffraction analyses showed that samples of doped CaSO₄ exhibit only a single phase corresponding to the crystal structure of anhydrite. Optical spectroscopy confirmed the presence of Eu³⁺ in the crystal matrix and a luminescent gain due the presence of silver nanoparticles. The composites showed thermoluminescent emission glow curves, with a single peak centered at approximately 200 °C for pellets with Teflon and at 230 °C for pellets with glass. The dosimeters based on calcium sulfate doped with europium and silver nanoparticles provided the most intense thermoluminescent (TL) emission of the composites studied. In comparison with commercial TLD, such as LiF:Mg,Ti and CaSO₄:Dy, the CaSO₄:Eu,Ag(NP)+glass produced in this work presented similar low detection limits and higher sensitivity. The new methods for the preparation of dosimeters and the incorporation of glass are shown to be viable because all of the samples presented a linear, reproducible and first order kinetic TL emission. - Highlights: • Thermoluminescent properties of CaSO₄ doped with Eu, Ag and Ag nanoparticles were evaluated. • Crystals were grown using a production route based in the Yamashita method. • Glass or Teflon was incorporate to the crystals in order to obtain composites. • The TL responses of the composites are proportional to the dose absorbed. • The CaSO₄:Eu,Ag(NP) + glass has potential to be used as a thermoluminescent dosimeter

[en] The paper describes the applicability of commercially available alanine detectors produced by Synergy Health for verification of the dose distribution calculated by the treatment planning system (TPS) used in proton eye radiotherapy – Eclipse Ocular Proton Planning (EOPP) program, version 8.9.06, Varian Medical Systems. The TPS-planned dose distribution at selected points in the eye phantom is compared to the dose registered by alanine detectors at these points during a simulated therapeutic irradiation at the proton eye radiotherapy facility in the Henryk Niewodniczanski Institute of Nuclear Physics (IFJ PAN), Krakow, Poland. The phantom was irradiated to obtain, a typical for choroidal melanoma, fraction dose of 15 CGE (13,64 Gy) at the tumor location. The dose registered with alanine pellets located inside the simulated tumor volume demonstrates a good agreement with the TPS-planned dose. The typical for proton radiotherapy, steep dose fall-off outside the treated area is registered by the alanine pellets however, it is difficult to assess it quantitatively, because the dose related EPR signal is registered from the entire pellet volume. - Highlights: • We confirmed the utility of alanine for in-phantom measurements in proton beams. • We compared TPS-planned and measured doses in proton eye radiotherapy simulation. • We discovered the limitation of alanine in registration the high dose gradients

[en] MOSFET detectors of 1 mVcGy⁻¹ sensitivity were tested for the accuracy of absorbed dose measurements in radiation therapy with the use of photon and electron beams. Before a detector was used in the study, several calibration coefficients were determined to allow for different factors affecting its operation. Then, the detector exposure response was compared with the dose calculated in the anthropomorphic phantom by the Monaco and MasterPlan treatment planning systems. MOSFET detectors were placed inside the phantom during the irradiation. Three different plans for thorax and pelvis areas were studied. The paper presents the differences between planned and MOSFET measured doses delivered to the selected target areas using conventional and IMRT techniques. - Highlights: • The response of MOSFET detectors to six different set-up factors affecting the measurements was investigated. • Detector readouts were compared with doses calculated by different treatment planning systems. • Doses were measured and calculated for the conventional and IMRT therapies using 6 and 15 MV beams. • The differences between planned and MOSFET measured doses delivered to the selected target areas are presented. • Three different plans for thorax and pelvis areas were studied