LA MISOGINIA EN GRECIA MERCEDES MADRID PDF
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Directory of Open Access Journals Sweden. Neutron beams used in BNCT are mostly driven from reactors and therefore, not only have a neutron energy range which far exceeds the thermal region but also do have a great gamma component. Beam characterization and dosimetry are consequently one of the essential procedures to be overcome to properly apply this technique.
One of the methods currently used in mixed field field containing both neutron and gamma characterization, lies on the use of a pair of detectors with distinct responses to each beam component. But this technique needs to be better understood of how each thermoluminescent dosimeter TLD behaves in a mixed field or in a pure field.
This work presents the results of a set of simulations performed in order to analyze the response of three ordinary types of TLDs – TLDTLD and TLD – submitted to different irradiation fields from a Cobalt source and an Americium-Beryllium source inside a paraffin disk. And is also a possible method for performing the selection and calibration of theses TLDs.
Thermoluminescence dosimeters TLD as one type of dosimeter which are often used to substitute the film badge. Like a film badge, it is worn for a period of time and then must be processed to determine the dose received.
This study was to test the reproducibility of TLD using Radpro reader. Ten chips of TLD were irradiated using Eldorado machine with Co source at a distance of 5 meters from the source with 2 mSv dose exposure. These steps will be repeated for nine times to obtain reproducibility coefficient, r i.
The readings of dose obtained from experiment was almost equivalent to the actual dose.
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Results shows that the average value obtained for reproducibility coefficient, r i is 6. As conclusion, the dose obtained from experiment considered accurate because its value were almost equivalent to the actual dose and TLD Radpro was verified as a good reader to analyse the TLD.
Optimal misoignia of TLD chips. Large sets of TLD chips are often used to measure beam dose characteristics in madris. A sorting method is presented to allow optimal selection of chips from a chosen set.
This method considers the variation. Personal exposure control using TLD. The facilities involved are a fuel reprocessing plant, a PuO 2 -UO 2 mixed fuel production facility, and a centrifugal uranium enrichment development facility.
The situation of personal exposure control with TLD and the dose evaluation methods for respective radiations are explained. The number of personnel subject to exposure control, including transient people, is about – per three months. With casings made of ABS resin, the external dimensions are 76 mm x 46 mm.
Environmental effects on TLD Reference is made to a recent paper by Dhar et al Health Phys. Similar work is here reported on TLD at 0 C with half the crystals being heat treated in vacuum, madris and readout an then annealed in air, irradiated and readout while the other half of the crystals were air annealed and readout before vacuum annealing and readout.
In both cases no significant change was detected in contrast to the results of Dhar et al. When substantial differences exist in exposures recorded by TLD ‘s and DRD’s, it is often necessary to perform an exposure investigation to reconcile the difference. In working with several operating plants, the authors have observed a number of causes for these differences.
This paper outlines these observations and discusses procedures that can be used to minimize them.
A new TLD system for space research. A small, portable, vibration and shock resistant thermoluminescent dosemeter TLD system was developed to measure the cosmic radiation dose on board of a spacecraft.
The TLD reader can operate on a battery; its electrical power consumption is about 5 W, misoignia volume is about 1 dm 3 and its mass is about misogiinia kg. Details are given of the construction and technical parameters of the dosemeter and reader. Environmental monitoring with a portable TLD system.
Two types of TLD systems are used for environmental dose monitoring. Tm bulbs and a small, portable TLD reader built into a cross-country car and operated by means of the car battery. The laboratory TLD system has been used for many years for environmental monitoring and it has been tested and proved satisfactory at international intercomparisons for environmental dosemeters.
The new portable TLD system has the advantage of being able to establish the dose in a few minutes at the environmental station.
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The transport dose is omitted as the TLDs are evaluated at the field site. The evaluation of a bulb needs only a few minutes and the measured dose value can be reported back by radio – an important aspect during an emergency situation. An automated thermoluminescence dosimetry TLD system. Process automization, statistical computation, dose calculation as well as dose recording are carried out, using a microcomputer and floppy disk unit.
The main features of this TLD -system are its low costs, flexibility, easy to operate, and the feasibility for use in routine dosimetry as well as in complex TLD mmisoginia.
Because of its modular set-up several components of misoginis system are multifunctional in other operations. The system seems suited for medium sized Health Physics groups. It presents the radiation levels measured mardid the vicinity of NRC licensed facilities throughout the country for the third quarter of Automated TLD system for gamma radiation monitoring.
A gamma radiation monitoring system utilizing a maerid available TLD reader and unique microcomputer control has been built to assess the external radiation exposure to the resident population near a nuclear weapons testing facility. Maximum use of the microcomputer was made to increase the efficiency of data acquisition, transmission, and preparation, and to reduce grrcia costs.
The system was tested for conformance with an applicable national standard for TLD ‘s used in environmental measurements. Environmental monitoring system with TLD. It was studied the response of the environmental dosemeter DA in fields of photonic radiation of energies W60, Wl 10, W and Cs.
The irradiations were carried out following the recommendations of the standard ISO: It was analyzed the response in the DA of the detectors LiF: Mg, Ti and CaF 2: Dy for the different radiation qualities and the relative response at Cs of both. The methodology used in the evaluation of the dose includes: The dose is calculated applying the average pondered in uncertainty of the dose obtained for each type of detector. Its were analyzed and calculated the uncertainties that affect to the measurement following the recommendation of the Argentine standard IRAM The detection limit of the absorbed dose rate in free air of this system it is 3.
A new fully automated TLD badge reader. Of late the manual TLD badge readers are almost completely replaced by semiautomatic readers with a number of performance improvements like use of hot gas heating to reduce the readout time considerably. PC based design with storage of glow curve for every dosimeter, on-line dose computation and printout of dose reports, etc.
However the semiautomatic system suffers from the lack of a machine readable ID code on the badge and the physical design of the dosimeter card not readily compatible for automation. The new PC based reader has a built-in reader for reading the ID code, in the form of an array of holes, on the dosimeter card. The reader has a number of self-diagnostic features to ensure a high degree of reliability. Neutron area monitor with TLD pairs.
The response of a passive neutron area monitor with pairs of thermoluminescent dosimeters has been calculated using the Monte Carlo code MCNP5. The response was calculated for one TLD located at the center of a polyethylene cylinder, as moderator. When neutrons collide with the moderator lose their energy reaching the TLD with thermal energies where the ambient dose equivalent is calculated. The response was calculated for 47 monoenergetic neutron sources ranging from 1E -9 to 20 MeV.
Response was calculated using two irradiation geometries, one with an upper source and another with a lateral source. For both irradiation schemes the response was calculated with the TLDs in two positions, one parallel to the source and another perpendicular to the source. Misogihia advantage of this passive neutron monitor area is that can be used in locations with intense, pulsed and mixed radiation fields.
Through a large number of experiments some persuasive data are obtained, which show that an remarkable improvement has mercdes achieved, especially in its stability to the standard illuminates, data dispersivity, and effectiveness to glow curves analysis.
Working with the grecka developed data processing software, the comprehensive performance of the whole system will be enhanced greatly. Determination of the TLD physical parameters. This study was realized in the Physics service at the Radiotherapy Department of the National Institute of Neoplasic Diseases in Lima, Peru, it was determined the activation energy, the kinetic order and the frequency factor of the fifth peak of the TLD thermoluminescent spectra using different miwoginia.
This was carried out in parallel with the implementation and design of a software and an interface associated with the Tl lecturer which allows a semiautomatic control for a thermoluminescent lecturer process. Microcomputer control of automated TLD reader.
The interfacing electronics, the control algorithms and the developed programs of a microcomputer controlled automated TLD reader are described. The TL reading system is implemented with a photomultiplier tube and a charge-to-pulse converter.
The gain of the TL reading system is controlled through the use of a temperature compensated LED reference light source. Automatic compensation of PM tube dark current is optional. Ionizing radiation source detection by personal TLD.
The Laboratory for personal dosimetry has about workers under control. The most of them work in medicine.
Some institutions, as big health centers, have different ionizing radiation sources. It is usefull to analyze what has been the source of irradiation, special when appears a dosimeter with high dose. Personal dosimetry equipment is Harshaw TLD Misogginia Model and dosimeters consist of two chips LiF TLD assembled in bar-coded cards which are wearing in holders with one tissue-equivalent filter to determine H 10 and skin-equivalent the other to determine H 0.
The calibration dosimeters have been irradiated in holders by different sources: The dose ratio for two LiF cristals was calculated and represented with graphs. Also, there is the calibration for determination the time of irradiation, according to glow curve deconvolution. Greciw in the reader include a Windows NT TM -based vrecia system and a Pentium microprocessor for the host controller, a servo-controlled transport, a VGA display, mouse control, and modular assembly.
This high capacity reader will automatically read fourteen hundred TLD Cards in one loading. Up to misoginiz elements in a card can be heated without mechanical contact, using hot nitrogen gas. Improvements in performance include an increased throughput rate and more precise card positioning.