A multi-sensor test-bench for determining the SAR (specific absorption rate) due to wireless devices emitting in equivalent human tissues is presented. Real-time SAR assessment is proposed considering a spatially distributed multiprobe test-bench. In comparison with a multi-axial robot SAR system, the proposed one does not require any displacement, thus reducing drastically acquisition time, once parallel data acquisition and interpolation techniques are employed for accelerating measurements. 相似文献
Thermoluminescence properties of lanthanum aluminum oxide (LaAlO3) crystals doped with optically active rare earth ions have been investigated for ultraviolet dosimetry purposes. Single crystals co-doped with 5.0 at.% of Ce3+ and 1.0 at.% of Dy3+ ions have two thermoluminescent (TL) peaks at 151 °C and 213 °C which can be sensitized after 1 h of UV exposure. The material shows very high TL output and linear response for UV spectral irradiance ranging from 0.04 to 1.20 mJ cm−2, that corresponds to 10 times the TL response of the Al2O3:C oxides. From 0.62 to 148.0 mJ cm−2 the dependence is linear with the logarithm of the spectral irradiance. The investigation demonstrates that LaAlO3:Ce,Dy crystals are very attractive to be investigated as UV dosimeters. 相似文献
It has been observed that a certain type of telephone chip-card can be used as radiation detectors for individuals exposed to external gamma doses. The radiation dose responses of more than 200 chip-cards, produced by various companies since 1990, were investigated using infrared stimulated luminescence (IRSL). The radiation dose responses of some of the chip-cards were found to be compatible with commonly used synthetic phosphors that are used for routine occupational dose monitoring. The IRSL signal is shown to be linear with a radiation dose from 250 mGy to 5 Gy and stable at ambient temperature, which allows the use of such chip-cards for reconstruction of doses for individuals. 相似文献
The ENEA fast neutron dosemeter is based on a planar poly allyl diglicol carbonate (PADC) placed in a polyethylene holder. The present paper reports the results of an experimental study of a CR-39® material with the addition of 0.1% of dioctylphthalate (DOP) produced by the Italian company Intercast Europe S.p.A.
The etching procedure is: pre-etching with 40% KOH water solution 6.25 N and 60% ethyl alcohol at 70°C followed by 12 h of etching in 6.25 N KOH water solution. For the energy dependence of response, dosemeters have been irradiated with neutron sources (241Am–Be, 252Cf, Pu–Li) and 14.9 MeV monoenergetic neutrons. The dosimetric performance of the material for fast neutrons is expressed in terms of sensitivity, background value, lowest detectable dose and energy dependence of response. Moreover, the results of a quality acceptance test of the material, performed on 11 sheets (980×980 mm2, 1.4 mm thick) of the same production batch, are given. Therefore, the homogeneity of the neutron sensitivity and of the background signal within a sheet and the whole batch is considered. The results are compared with the acceptance test outcome for a CR39 standard material batch. 相似文献
In the Laboratory of Nuclear Microanalysis, we have developed two techniques for neutron dosimetry; the first for low fluence, the second for high fluence. These two techniques use a Solid State Nuclear Track Detector (SSNTD): the CR-39. The low fluence technique is based on the measurement of etched tracks resulting from a neutron-proton conversion. A Monte Carlo code performs a simulation of the (n,p) collision in the detector, and a numerical computer code of latent track etching allows the evaluation of the etched track parameters. The object of this is to obtain characteristics of a neutron fluence from the measured etched track parameters. When there is a high fluence and high doses, CR-39 is unsuited for optical microscopy analysis. This is because of track overlapping which makes it impossible to carry out counting and exploitation. We have therefore developed a new method permitting the reading of samples based on the measurement of the angular distribution of coherent light (He---Ne laser) transmitted through the irradiated etched SSNTD. We present these two techniques and our initial results. 相似文献
A MOSFET-based low-energy neutron dosimeter has been fabricated using a 10B loaded gate electrode as (n,α) converter. The response to thermal neutrons has been studied. 相似文献
Subsequent to the proposal of a two-layer structured radiator for more efficient detection of high-energy neutrons with a plastic nuclear track detector (PNTD), its availability has been investigated both experimentally and theoretically. An inner deuterized hydrocarbon (CD2) layer adjacent to PNTD should play the role of both a radiator of deuterons recoiled there and a degrader for energetic protons recoiled in the outer layer of a CH2 material. It was found that the energy dependence of the efficiency was changed sensitively by the thickness of the CD2 layer. A best combination of CH2 and CD2 thickness was estimated under a condition of a constant total thickness. For example, the sensitivity could be flattened within 20% between about 5 and 70 MeV by using -CD2 and -CH2. 相似文献
A neutron personal dosemeter using CR-39 as a detector and hydrogenated materials as proton converters for fast neutron detection plus an air layer for thermal neutron detection is being developed in our laboratory. To increase the CR-39 response to thermal neutrons, the air converter was substituted with Nylon in some dosemeters. Several dosemeters with these two configurations were mounted on a water-filled phantom and exposed under different incidence angles (0, 30 and 60) to: (i) Three ISO neutron sources (241Am–Be, bare 252Cf and moderated 252Cf with Cd shielding), and (ii) two realistic neutron sources (SIGMA and moderated 252Cf) at the IRSN (Cadarache) facilities. The irradiated detectors were electrochemically etched and evaluated in order to determine their dose equivalent response in terms of Hp(10,α). The results obtained are compared to those obtained from Monte Carlo simulations using the MCNPX code. 相似文献