Light emission in radiation detectors can increase due to nanoparticles presence. OSL detectors based on Brazilian natural CaF2 with silver nanoparticles (Nps-Ag/CaF2) were produced. It was observed an enhancement of OSL intensity from CaF2 detectors with Nps-Ag.
BNCT, optical fiber-based neutron detector, moderator-based neutron energy spectrometer
FNTDs (Fluorescence Nuclear Track Detector) exposed to fast neutrons were analyzed by acquiring a stack of images using a 2D-galvo FNTD reader. These stacks of images were processed to reconstruct the 3D recoil proton trajectories, providing ultimately an effective delta electron signal filtering and offering additional information on the exposure conditions.
We report plastic scintillators containing organic phosphors with aggregation-induced emission (AIE) properties. The optimum phosphor concentration was investigated upon changing the concentration of the phosphor. All of the as-prepared samples emitted scintillation light. Interestingly, the photoelectric peaks of the pulse height spectra were confirmed in the samples to which a large amount of phosphor were added.
The development of modern heavy-ion accelerators is associated with an increase in beam intensity. Accordingly, with high-intensity heavy-ion beams, the actual problem is beam diagnostics by non-destructive methods, because using of contact methods for beam diagnostics is impossible due to the high power of the beam.The beam diagnostics by non-destructive methods can be implemented on the basis of radiation detection resulting from the interaction of a heavy ion beam with accelerator construction materials.
Chips of CaSiO3 have been produced for ion accelerated detection.Irradiations with 290 MeV/n Carbon and 160 MeV proton.TL response, after irradiation, presented two prominent peaks at 120 °C and 270 °C.Doses from proton and carbon ions were compared with gamma doses from Cs(137) source.
A low cost multi-sample integrated thermo luminescence/optically stimulated luminescence (TL/OSL) reader (MS-ITOR) has been developed for various application. This reader system can handle 36 aliquots at a time. Apart from measuring the TL and OSL the reader has in-built irradiation and optical bleaching facilities.
Different concentrations of Eu doped LiMgAlF6 samples were synthesized by the spark plasma sintering method. Eu-doped LiMgAlF6 showed an intense thermally stimulated luminescence (TSL).
An instrument has been designed to image the recently identified Stokes-shifted IR-photoluminescence emission for routine measurements on large rock slices. Using samples of K-feldspar, appropriate routine measurement protocols were established and demonstrated.
Novel semiconductor devices for real-time sub-mm resolution dosimetry were developed.
This paper presents a new automatic algorithm for TL Glow Curve (GC) categorization. Possible irregular GCs can be automatically identified by this new procedure. The presented algorithm can be routinely used for quality control measures in individual monitoring services.
The precise energy measurement of an a particle using a silicon semiconductor detector (SSD) is very important to identify whether the a particle is emitted through the decay chain of superheavy elements (SHEs) with atomic numbers Z>103. The measurement of the total kinetic energy (TKE) of fission fragments generated through the decay of SHEs is also reliable because a high TKE indicates that fission occurred from a very heavy nucleus. It is necessary to evaluate the dead-layer thickness of the SSD to correct the measured energy to the initial energy of an a particle or the TKE of the fission fragment. To evaluate the dead-layer thicknesses of SSDs, energy spectra were first investigated using 241Am by irradiating a-rays at incident angles of 0, 25, and 45° for three types of SSD. The dead-layer thicknesses of the SSDs were deduced by comparing the peak shifts related to the incident angle of 0° with those obtained by a computer simulation using the particle and heavy ion transport code system (PHITS).
The effect of the body size on the detection efficiency of a newly developed thyroid monitor was estimated by Monte Carlo simulations using several voxel phantoms. The discrepancy from the efficiency in calibration was found to be 30 % at the maximum.
We studied a new effective energy measurement method using stacked thermoluminescence dosimeters (TLDs). We were able to obtain the decay curves through analyzing the relationship between the absorber depth and the absorbed dose, because the stacked small TLD plates have two functions as an absorber and a dosimeter. Given the importance of calculating the effective energies, the further study of this method would be of value to the field of radiation exposure dose management.
In this study, Tb3+- or Dy3+-doped CaO–Al2O3–B2O3 glasses were prepared with nB, 10B, and 11B, and thermoluminescence (TL) properties irradiated with X-ray, heavy particles, or neutron were investigated. X-ray- or heavy-particles-induced TL properties of 10B glass was similar to that of nB or 11B glass, but neutron-induced TL properties of 10B was not similar to that of 11B glass.
The DIAµDOS guard-ring microdosimeter prototypes have been fabricated at the Diamond Sensor Laboratory of the CEA in France. The characterization of the diamond detectors has been performed with the use of ion microbeam facilities at AIFIRA in France and ANSTO in Australia. The DIAµDOS detector has been evaluated by means of experimental measurements at CPO in France and experimental results supported by GEANT4 simulations.
The response to dose of commonly used solid state dosimeters show a strong energy dependence in the low energy range. Here we explore the alanine/EPR response to dose-to-water for a low filtered 40kV x-ray beam, and correct for the dose gradient within the 2.7mm thick dosimeter.
An inter-comparison of personal electronic dosimeters used by various nuclear facilities was performed. The overall results suggest that these active dosimeters have achieved the same dose responses as those passive dosimeters at each facility for legal dose records.
The transmission silicon strip detector is a dual purpose device capable of providing real time dosimetric data in addition to beam monitoring for rapid response in case of incident during treatment. The effect of a 375 µm thick transmission detector upon the depth dose response within solid water and a water tank was measured with a pinpoint ionisation chamber. The experimental results were found to be in agreement with Monte Carlo simulation results for three different beam filtration configurations corresponding to three different mean energies. The amount of perturbation (1-5%) of the beam due to the thick transmission detector directly corresponds to the mean energy and thus beam filtration used. Silicon based transmission detectors are deemed to be a suitable material of choice given accurate compensation of the known beam attenuation during the treatment planning.
The response of organic photodetectors for use in medical radiation therapy including, dose linearity, energy dependence and dose rate dependence, is characterised. Prior exposure to ionizing radiation (40kGy) increases device sensitivity.
A new RPL readout system has been developed to obtain dose in the range between 1 Gy and 1 MGy. The system combines the measurement of the emitted RPL light with a transmission measurement to cover the aforementioned dose range.
・Bismuth-doped plastic scintillators were successfully fabricated.・The maximum value of detection efficiency is 2.3%.・The time resolution hardly depends on the concentration of Bi, and has high values between ~0.2–0.3 ns.
Ce doped LaCl3/AECl2 (AE=Mg,Ca,Sr) system eutectics were explored. Ce:LaCl3/CaCl2 showed light output of 9,000 photon/MeV. Scintillation decay time of the Ce:LaCl3/CaCl2 was 26.8 ns (26%) 282 ns (74%).
This work studied the microdosimetric distributions and corresponding the relative biological effectiveness (RBE) of different ions, namely 12C, 14N and 16O, using a silicon-on-insulator (SOI) microdosimeter with well-defined 3D sensitive volumes (SV). We demonstrated the possibility of using SOI microdosimeter for Q ̅ and Hp(10) derivation in a radiation field mimicking Galactic Cosmic Rays outside and inside the International Space Station.
NOVAC 7 mobile IntraOperative Radiation Therapy (IORT) that involves the administration of a single dose of radiation to the tumor during surgery. To measure the relative dosimetry like Output Factors, PTW 60019 microDiamond detector exhibited the best performance.
A tailor made equipment was made for advance lyoluminescence (LL) measurements. The LL measurements were applied to recover information about absorbed dose in pure NaCl and halite crystals. Spectral properties of the emission were analyzed.
• The dosimeter can be cured by the photopolymerisation process in any shape • Fluorescence response of the dosimeter serves as a tool for measuring depth-dose distributions • Measured depth-dose profiles can be used as a dose verification in radiation processing of surfaces
Spectrum of X-rays around 20keV was estimated using high-performance Peltie type cloud chamber. Such low energy X-rays knock out photoelectrons that fly only several mm in air. Measurements of track length in cloud chamber give energy distribution of these photoelectrons. The track length was calibrated by characteristic X-rays from several metals excited by Sr-90 shielded beta-source.
The laser-accelerated protons from hydrogen clusters are measured by CR-39 track detectors. A step-wise energy moderator is installed in front of CR-39 to obtain the energy spectrum with the resolution of a few MeV. The designed detector unit revealed that the maximum energy and energy spectra depends on the size distributions of the hydrogen clusters.
Laser-based Thermoluminescent Dosimetry (TLD) can deliver very high heating rates. It is simple and can be used for measurements in remote locations. Noncontact close-loop temperature control makes more accurate results.
・Photoluminescence and scintillation properties of TlSr2Cl5 were studied.・TlSr2Cl5 crystals were prepared under vacuum using a self-seeding solidification method.・TlSr2Cl5 crystals showed broad emission bands peaking at 450 and 500 nm under X-ray excitation.・Light yield of TlSr2Cl5 crystals reached 16,000 photons/MeV under -ray irradiation.
The photoluminescence and scintillation properties of TlMg(Cl1–xBrx)3 were studied.・TlMg(Cl1–xBrx)3 crystals were prepared under vacuum using a self-seeding solidification method.・TlMg(Cl1–xBrx)3 crystals showed emission bands at 420 nm under X-ray excitation.・The light yields obtained for TlMg(Cl1–xBrx)3 crystals can reach 45,000 photons/MeV upon -ray excitation.
A new neutron radiography method was developed for fast neutron measurement, in which b-rays from irradiated threshold detectors such as 27Al(n,a)24Na and 24Mg(n,p)24Na are transferred and accumulated on X-ray imaging plate (IP).
Flexible OSL detectors with CaSO4:Dy were produced to be used for dose mapping. The matrix of the detector is based in high temperature silicone that allows thermal bleaching. OSL dosimetric properties demonstrate potential application in radiation measurements.
Fluorescent nuclear track detectors (FNTD) based on LiF crystals were successfully used for imaging tracks of various ionizing particles. This was achieved by exploiting photoluminescence of radiation induced F2 and F3+ color centers and a wide-field fluorescence microscope.
Dosimetrics GmbH München has developed a new detector element based on BeOSL technology. It can be used for extremity dosemeters without compromising the concept of automated bulk processing.
This study will firstly report the photo-physical and scintillation properties on different Pr concentrations in Lu2Si2O7 single crystals. Photoluminescence (PL) quantum yield (QY), scintillation light yield and other properties has been observed. Throughout the systematic studies on these properties, we found the optimum concentration for the Pr doped in Lu2Si2O7 for scintillator purpose.
This communication describes the different versions of a broad energy range, directional, neutron spectrometer consisting of several solid-state detectors within a single cylindrical moderator. Appropriate choice of detectors and dimensions made it suitable for a wide range of applications.
The CR-39 track detectors were used to measure neutrons emitted from DT neutron generator. The Monte Carlo simulations of experimental setup were performed. Activation method was used as a complementary diagnostics.
Thermal neutron fluxes of therapeutic intensities (> 1 × 109 cm-2 s-1) are required for basic researches of boron neutron capture therapy (BNCT). We developed polyethylene moderators obtaining the thermal neutron fluxes of 1.8 × 109 cm-2 s-1 in NIRS accelerator-based neutron source, named NASBEE facility. Additionally, dose contaminations of fast neutrons and gamma rays are estimated using CR-39 nuclear track detector and optically stimulated luminescence (OSL, Al2O3:C) dosimeters.
We developed new bulk-density controlled thermoluminescence dosimeters (TLDs) based on Al2O3 ceramics, aimed at developing an anthropomorphic dosimeter for photon radiation therapy. Their potential was evaluated by measurements of thermoluminescence (TL) properties and theoretical calculations.
Polyvinyl alcohol-iodide (PVA-I) radiochromic gel dosimeter utilizes the red-coloration due to PVA-iodide complex formed in the gel matrix by irradiation. The transparency is improved significantly by optimizing of the composition and the addition of sucrose without impairing the other desirable properties such as the high sensitivity and the dose-rate-independence. Furthermore, it is also found that the addition of sucrose results in the suppression of auto-oxidation of the gel dosimeter.
The portable thyroid dose monitoring system available in a situation of a severe nuclear accident is in development. In this presentation, the detailed design of the thyroid dose monitor and experimental results using prototype model will be described.
An in-situ, sub-surface environmental monitoring system is described based on radiophotoluminescence (RPL) from Ag-doped alkali-phosphate glass. The system uses a fiber-optic probe encased in a metal or plastic sheath. Once placed in the ground dose measurements can be made in-situ.
Designed calculations, simulation, and fabrication of a Nested Neutron Spectroscopy (NNS) have been carried out in this study based on MCNP6 and PHITS codes and a CAD software. With some benefits as light-weight and field portable, cylinders easily be positioned upright on a flat stand, quick configuration for measurements in demanding environments, and able to run in the current mode for high flux environments, the aims of this study is to fabricate the NNS system.
The RPL depth profiles of microscale patterns in Ag-activated glass and LiF crystal written using proton and carbon beams are compared and evaluated using multi- and single-photon microscopes.
A real-time fibre-optic-coupled dosimetry system using Ag-activated phosphate glass and LiF crystal based on the radiophotoluminescence phenomena are demonstrated.
Conceptual design of a passive TL/OSL dosemeter with ability of deconvolution of ambient photon energy composition. Application areas are emergency response (first respondents, military) and other applications where knowledge of incident photon spectrum is essential. The design is substantiated by Monte Carlo calculations and energy spectrum deconvolution algorithm.
Performance of a 2nd generation of Fluorescent Nuclear Track Detector (FNTD) reader prototype, utilizing laser line excitation and parallel multipixel fluorescence readout is described. The instrument demonstrated a 30-time increase in the readout speed, compared to the speed of the 1st generation commercial reader and improved image quality. The fluorescent imaging of 32 mm2 of FNTD area takes about 3 min and provides the sensitivity of 21 tracks/mm2/mSv for the Am-Be neutrons. Blind tests of the new reader prototype after irradiation with Am-Be neutrons in combination with M30 X-ray photons were performed and have demonstrated compliance with the ISO-14146 standard.
The responses of a diamond detector to gamma-rays, neutrons and alpha-particles were measured and simulated. We demonstrated that a diamond detector can be used for neutron dosimetry under extreme radiation environments with high-level gamma-ray contamination.
Real-time neutron personal dosimeters based on silicon sensor indicate smaller neutron energy response functions than the ICRP dose response curves at the neutron energy range between 10 keV and 1 MeV. Measurement values of these dosimeters are dependent on neutron fields having different energy spectra due to the disagreement between the energy response of dosimeters and the ICRP curves. We have simulated the neutron energy responses using PHITS3 code to improve the energy responses, by considering neutron angular responses in the response functions and reproducing a package of thermal neutron absorber.
A correction method for the background photons in high dose rate environment was developed to apply to the thyroid dose monitoring using the portable thyroid dose monitoring system developed at the Japan Atomic Energy Agency.
Stationary and portable equipment for OSL dosimetry based on BeO is presented, with an achievable coefficient of variation of 0.66 % for the OSL signal induced by the same dose with more than 100 repeats for a single MyOSLdosimeter.
Simulation of experimental chemical cross section induced by ions in a poly allyl diglycol carbonate (PADC – CR39) based on the radial dose deposited by secondary electrons removed by the incoming ion.
The proton-boron fusion reaction was investigated within the Plasma Focus facility. The distribution and energies of fast protons emitted during Plasma Focus discharges were determined. The CR-39 track detectors and silicon detector were used to measure emitted alpha particles.
Radon is a radioactive, carcinogen and naturally occurring gas present in indoor and outdoor environment. In the present paper, radon and thoron concentrations with their decay products has been measured by using passive measurement technique and compared with the recommended limits of WHO, ICRP and UNSCEAR.
The framework for testing the performance of neutron dosemeter has evolved. A first feedback on the new ISO 21909 standard will be presented based on experimental measurements obtained with our routine measurement process. An upgrade of our dose estimation algorithm using a Monte-Carlo method will also be discussed.
The VVR-S nuclear research reactor with thermal neutrons from Romania, used for radioisotopes production and physics research purposes was operated between 1957 and 1997 and finally shut down in 2002 in order to be decommissioned for safety reasons. The separator for fuel assemblies, was dismantled in 2014 using plasma torch technology. The process involved radiological risks for the workers due to the high levels of dose rate. The workers external exposure was monitored continuously and the internal exposure was assessed based on the activity concentration of the aerosols released during the cutting process.
The upper limits of the measurement uncertainty of passive personal and area dosimetry systems were estimated according to the IEC 62387 dosimetric performance requirements. The corresponding limits of the response of these dosemeters were calculated for 90 % and 95 % confidence probabilities and compared to the ISO 14146 ‘trumpet curve’ criteria for intercomparisons.
Gamma dose rates were measured using a portable NaI(Tl) dosimeter at two cities of Karnataka State in India. The dose rates in Mangalore and its surrounding were found to be within the normal level. Relative higher gamma dose rates were recorded within Mysore city due to the granite region.
The application of different Time-Temperature-Profiles and the influence of fading in the routines of the individual monitoring services were investigated at Seibersdorf Labor GmbH. Several Harshaw TLD-100 dosimeters have been irradiated and fully read out after different periods of storage. A following fade study with an optimization of the standard procedure was performed.
Determination of neutron exposures configurations encountered in well-logging activities.In-situ evaluation of neutron correction factors for each irradiation condition.Implementation of neutron personal dosimetry in Well-logging Oil industry.
DFT calculation was applied to know the substituent effect on the separation of Am(III) from Eu(III) by bis(trifluoromethylphenyl)dithiophosphinic acids. Optimized strictures revealed that Eu-S and Am-S distances are similar for all complexes, but m-,m-trifluoromethyl derivative has a relatively larger Am-S distance, while o-,o- and o-,m-trifluoromethyl derivatives have the relatively shorter Am-S distance.
Workplace field with high-energy neutron component usually available from May to December with a mean availability of 95 % at the Paul Scherrer Institute (PSI).
In this paper are presented the collective doses recorded during the period 1976 – 1995 for occupational exposed worker from nuclear research area, especially for Horia Hulubei, National Institute for R&D in Physics and Nuclear Engineering, IFIN-HH. The individual doses are also studied in this paper.
222Rn and 220Rn discrimination is investigated using a solid-state nuclear track detector (SSNTD) based passive detector named Radout used by Mi.am company. The analysis of track morphological parameters performed by Politrack allows to identify a critical parameter for the discrimination of the two radon isotopes: the recalculated reduced etch rate.
The Individual Monitoring Service (IMS) at the Helmholtz Zentrum München has developed a new ring dosemeter, a new eye lens dosimeter (ELD) for integration in radiation protection (RP) glasses and a new environmental dosemeter based on BeOSL technology.
The Individual Monitoring Service (IMS) at the Helmholtz Zentrum München has developed and characterized a new ring dosemeter for the measurement of Hp(0.07), based on BeOSL technology. The new detector element can be read out by means of standard BeOSL readers and fulfills IEC requirements.
Methods of imaging and detection for fast neutron using advanced nuclear emulsion technique with the automated scanning system were developed. Fast neutron pinhole imaging and collimated detection of fast neutrons were demonstrated.
Noble scintillation paper functionalized for detecting ß-particles was prepared. The paper had different structures to capture ß-particles from 90Y. Scintillation images were obtained and analyzed.
Possible application of a recently developed electronic personal dosimeter having a long-life battery for management of aviation doses of frequent flyers was investigated through the measurements onboard selected international flights.
CaF2 presented changes in the curve shape of OSL emission according to type and energy of radiation. Using parameters of curve deconvolution, the energy range can be estimated from OSL emission.
Existing shallow (skin) dose dosimeters, with modifications for the possibility to accurately measure personal dose equivalent Hp(3) for eye dosimetry, were tested on 5 different models. Most models performed suitably well to be considered as potential Hp(3) eye dosimeters.
Studying glasses for dosimetric applications offer lots of possibilities, as well as challenges. Different borate glasses were analyzed regarding some important characteristics that may be considered in dosimetric studies using the OSL technique.
To clarify the eye lens dosemeters positioning the shielding effect of full face mask respirators, photon irradiation experiments to various eye lens dosemeters attached on the head phantom was performed at the secondary photon calibration fields of Japan Atomic Energy Agency.
A new thyroid monitor using multiple Gd3(Al,Ga)5O12 (GAGG) detectors with each crystal size of one cubic centimeter has been developed. The GAGG detectors can be placed around the front surface of the human neck to increase the sensitivity for 131I in the thyroid, especially with the intension of measuring infants and small children. The arrangement of 8 GAGG detectors was tested using age-specific phantoms with thyroid shaped container filled with 131I solution, demonstrating that the minimum detectable activity (MDA) of the new monitor was lower than that of a conventional NaI(Tl) spectrometer (a crystal size of 2.54 cm in diameter x 2.54 cm in thickness).
The X-ray energy radiated from a Crookes tube is approximately 20 keV. It caused a distribution of Hp(0.07) dose enclosing the Crookes tube at 0.015 – 0.11 mSv in 1 hour. The dose concentrates in the central human body and relatively descend to expanded area.
Computational simulations were performed to investigate the availability of FASTSCAN, the whole-body counter widely used after the Fukushima nuclear disaster in 2011, for the population monitoring focusing on 131I accumulated in the human thyroid.
The plastic solid-state nuclear track detectors become more and more popular in the charged particles detection and environmental monitoring. In this paper, the characteristics of the CR-39 and cellulose acetate are compared , on the basis of the track-etching condition(6.5mol/L, 70℃, 8h) ,the CR-39 detector is calibrated with a calibration coefficient of 0.035 Tc/cm2/Bq﹒h/m3. Based on track-etching system, the Radon concentration of Anyang district and Chengdu city is measured. Some factors affecting the radon concentration are also discussed. The results indicate that radon concentrations in Anyang district are 13.0Bq/m3～54.2Bq/m3,while in Chengdu are 14.1Bq/m3～43.2 Bq/m3.
MgB4O7:Ce,Li detectors presented wide dose-response range required in clinical dosimetry and no significant energy dependence for irradiations with 6 and 10 MV.
Tb3+ doped LiMgBO3 was synthesized using sol gel method. Its structural characterizations were done using XRD, PL and SEM techniques. It has shown very good thermoluminescence (TL) response for thermal neutrons from graphite moderated 241Am-Be neutron source. The TL signal is stable with low fading rate.
Network of monitoring stations continuously measuring artificial gamma activity in surface water is being built in the Czech Republic. Functionality of the system is based on the failure resistant monitoring stations assembled to a network equipped with central data processing. Stations are automated, autonomous and of a simple construction, therefore failure protected, and their detection capabilities are enhanced by the Noise Adjustment Singular Value Decomposition (NASVD) method, which is used for data processing. This mathematical tool decreases the detection limits, what enables employment of the network not only for the purpose of emergency preparedness but also for normal monitoring with particularly more demanding requests due to detection limits.
Chiyoda Technol Corporation started eye lens dosimetry service using Hp(3) dosemeter DOSIRIS. Compatibility assessment for IEC 62387 of DOSIRIS was performed, and the characteristics of DOSIRIS met the requirements except for the angular dependence for 90Sr-90Y beta radiation. Angular dependence can be improved by optimization of filter.
Trees in the large area around the Fukushima Daiichi Nuclear Power Plant were contaminated by radioactive cesium owing to the accident in 2011, damaging mushroom industry using logs. To promote the industry again, no-contaminated safe trees should be selected. Herein, we developed a portable and sensitive radioactive detection system to select the trees before felling. By measuring in the field, we confirmed that the detector could operate in outdoor environments contaminated with low-level radiation, ~0.05 μSv/h.
Nowadays machine learning (ML) methods provides extremely important tools for intelligent environmental data analysis, processing and visualization. We describe application of ML to environmental sciences in the emphasis to radon exhalation rate.Nowadays machine learning (ML) methods provide extremely important tools for intelligent environmental data analysis, processing and visualization. We describe the application of ML to environmental sciences in relation to the radon exhalation rate.
The study investigates the effective subtraction of background components due to terrestrial radionuclides for environmental radiation monitoring using a scintillation spectrometer.
We present a measurement and an evaluation of high LET thermoluminescence glowcurve peaks and their advantage regarding new prospect in neutron dosimetry.
A new fluorite-based pellet has been produced with the objective of substituting the detector currently in use at the Laboratory of Dosimetry of the University of São Paulo.
We developed an omnidirectional scintillator-based Compton camera that visualizes low energy gamma rays radiated from radiopharmaceuticals with high sensitivity. We verified the performance of the detector by measuring the 99mTc and 111In in a nuclear medicine facility.
In order to improve angular dependence of small a radiophotoluminescence (RPL) glass dosemeter, DoseAce, the holder and filter were reviewed. It was confirmed by irradiation examination that the angular dependence of DoseAce with the new holder was improved.
The presence of gamma dose rate effects was investigated on the TL signal of 6 different dosimetric phosphors as well as the OSL signal of 3 of them.
To evaluate the relationship between the whole-body and eye lens dosimeters a field study using humanoid phantoms with different dosemeters attached were made at selected locations at the Fukushima Daiichi Nuclear Power Station.
A tentative uncertainty budget of track-etch detectors used in radon in thoron survey is presented. The consequences of uncertainty for decision making related to radon regulation are discussed.
To discuss how to monitor and manage the equivalent dose for the lens of the eye of radiation workers at nuclear facilities, the dose was measured at the head and the chest of the radiation workers around water storage tank areas (90Sr/90Y dominant area) and the nuclear reactor buildings (high dose gamma areas) of the Fukushima Daiichi Nuclear Power Station. The relationship between Hp(10) and Hp(3) for the workers in these areas and the doses measured at the head wearing a full-face mask and the chest were clarified.
Radioactive cesium inventory and air dose rate were measured in very sloped catchment. The radioactive cesium was distributed along the gradient elevation, however forest zone still maintained higher radioactive contamination.
A new BeOSL eye lens dosimeter (ELD) for integration in radiation protection (RP) glasses has been investigated in laboratory tests with an Alderson head phantom. The results show both the measurement capabilities of the dosemeters and the protective effect of the glasses. Results are supplemented by data from Monte Carlo Simulations and first clinical applications in radiology.
To propose a new methodology for prototyping and benchmarking based on the Dose Equivalent to the sensitive part of the eye lens; demonstrate the integration of CAD Software and Monte Carlo Simulation in Geant4 with mesh modeling simulation and 3d printing; demonstrate the use of strengths and drawbacks of 3D printing on the fast prototyping of new dosimeters.
The response of RPL (Radiophotoluminescence) glass ring dosemeter was improved by optimizing the dosemeter filter based on the Monte Carlo simulation. It was confirmed by irradiation experiments that the dosemeter fulfills the energy and angular criteria of IEC 62387:2012 standard1) in the energy range from 24 keV to 1,250 keV.
Mixed radiations were generated in high-energy radiation field. Equivalent dose of the environment during radiotherapy from neutrons and photons was measured to assess radiation risk of workers and patients using optically stimulated luminescence dosimeters (OSLDs).
In response to a change in legislation, lots of manufacturers started to offer the special type of personal dosemeters designed to measure dose equivalent at the depth of 3 mm (Hp(3)), which represents the operational quantity for the dose to the eye lens (Deye). Nevertheless, it has some properties that can limit its usability. What is more, introducing another dosemeter to the equipment of radiation workers may be difficult. These are the reasons why another ways of Deye monitoring are considered.
We have developed a non-doped LiF/CaF2 eutectic for thermoluminescence (TL) dosimetry. While the non-doped LiF/CaF2 eutectic and a CaF2 single crystal showed similar luminescence properties, the non-doped LiF/CaF2 eutectic can be obtained using a simple melt-solidification method with a lower melting temperature than that of CaF2. The TL intensity of the non-doped LiF/CaF2 eutectic was higher than that of the CaF2 single crystal, and the integrated TL intensity of the non-doped LiF/CaF2 eutectic monotonically increased as a function of X-ray dose from 10 to 1000 mGy.
Eu:BaAl2O4 single crystals were prepared by the floating zone method, and the ionizing-radiation-induced radioluminescence and storage luminescence properties were evaluated for dosimetry applications.
The thermoluminescence properties of Y3Al5O12 (YAG):Ce (Ce concentrations: 0.5, 0.8, and 2 mol%) were characterized after irradiation with heavy charged particles or gamma-rays. The effects of linear energy transfer (LET) were significant for YAG:0.5 mol% Ce. The LET dependence of the glow curve has a trend opposite to that of the gamma-ray dose dependence.
Functions describing PB broadening in water and EBT3 film sensitivity quenching were experimentally searched, for both protons and carbon ions. The results allow to perform suitable correction of the acquired dose images.
We have examined X-ray-induced luminescence of Sn-doped zinc borate (SZB) glasses prepared in Ar atmosphere. The scintillation intensity of SZB glasses increases with increasing tin concentration while the intensity of thermally stimulated luminescence (TSL) decreases. Clear inverse relationship between scintillation and TSL in SZB glasses is observed.