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Sample records for automated personal dosimetry

  1. Automated personal dosimetry monitoring system for NPP

    Energy Technology Data Exchange (ETDEWEB)

    Chanyshev, E.; Chechyotkin, N.; Kondratev, A.; Plyshevskaya, D. [Design Bureau ' Promengineering' , Moscow (Russian Federation)

    2006-07-01

    Full text: Radiation safety of personnel at nuclear power plants (NPP) is a priority aim. Degree of radiation exposure of personnel is defined by many factors: NPP design, operation of equipment, organizational management of radiation hazardous works and, certainly, safety culture of every employee. Automated Personal Dosimetry Monitoring System (A.P.D.M.S.) is applied at all nuclear power plants nowadays in Russia to eliminate the possibility of occupational radiation exposure beyond regulated level under different modes of NPP operation. A.P.D.M.S. provides individual radiation dose registration. In the paper the efforts of Design Bureau 'Promengineering' in construction of software and hardware complex of A.P.D.M.S. (S.H.W. A.P.D.M.S.) for NPP with PWR are presented. The developed complex is intended to automatize activities of radiation safety department when caring out individual dosimetry control. The complex covers all main processes concerning individual monitoring of external and internal radiation exposure as well as dose recording, management, and planning. S.H.W. A.P.D.M.S. is a multi-purpose system which software was designed on the modular approach. This approach presumes modification and extension of software using new components (modules) without changes in other components. Such structure makes the system flexible and allows modifying it in case of implementation a new radiation safety requirements and extending the scope of dosimetry monitoring. That gives the possibility to include with time new kinds of dosimetry control for Russian NPP in compliance with IAEA recommendations, for instance, control of the equivalent dose rate to the skin and the equivalent dose rate to the lens of the eye S.H.W. A.P.D.M.S. provides dosimetry control as follows: Current monitoring of external radiation exposure: - Gamma radiation dose measurement using radio-photoluminescent personal dosimeters. - Neutron radiation dose measurement using

  2. Automated personal dosimetry monitoring system for NPP

    International Nuclear Information System (INIS)

    Full text: Radiation safety of personnel at nuclear power plants (NPP) is a priority aim. Degree of radiation exposure of personnel is defined by many factors: NPP design, operation of equipment, organizational management of radiation hazardous works and, certainly, safety culture of every employee. Automated Personal Dosimetry Monitoring System (A.P.D.M.S.) is applied at all nuclear power plants nowadays in Russia to eliminate the possibility of occupational radiation exposure beyond regulated level under different modes of NPP operation. A.P.D.M.S. provides individual radiation dose registration. In the paper the efforts of Design Bureau 'Promengineering' in construction of software and hardware complex of A.P.D.M.S. (S.H.W. A.P.D.M.S.) for NPP with PWR are presented. The developed complex is intended to automatize activities of radiation safety department when caring out individual dosimetry control. The complex covers all main processes concerning individual monitoring of external and internal radiation exposure as well as dose recording, management, and planning. S.H.W. A.P.D.M.S. is a multi-purpose system which software was designed on the modular approach. This approach presumes modification and extension of software using new components (modules) without changes in other components. Such structure makes the system flexible and allows modifying it in case of implementation a new radiation safety requirements and extending the scope of dosimetry monitoring. That gives the possibility to include with time new kinds of dosimetry control for Russian NPP in compliance with IAEA recommendations, for instance, control of the equivalent dose rate to the skin and the equivalent dose rate to the lens of the eye S.H.W. A.P.D.M.S. provides dosimetry control as follows: Current monitoring of external radiation exposure: - Gamma radiation dose measurement using radio-photoluminescent personal dosimeters. - Neutron radiation dose measurement using thermoluminescent

  3. News on personal dosimetry

    International Nuclear Information System (INIS)

    What is going on in personal monitoring? The DIS-1 dosimeter (Rados/Mirion Technologies), on the market since 2000, is being introduced in the 4th dosimetry service in Switzerland. In Germany, dosimetry services are looking for alternatives to the film dosimeter. They have recently taken the decision for two technical solutions. IEC has published a standard which shall regulate technical requirements for dosimeters world-wide. (orig.)

  4. Personal radon daughter dosimetry

    International Nuclear Information System (INIS)

    The conventional means of radon daughter exposure estimatikn for uranium miners in Canada is by grab sampling and time weighting. Personal dosimetry is a possible alternative method with its own advantages and limitations. The author poses basic questions with regard to two methods of radon daughter detection, thermoluminescent chips and track-etch film. An historical review of previous and current research and development programs in Canada and in other countries is presented, as are brief results and conclusions of each dosimeter evaluation

  5. Automation at NRCN Dosimetry Laboratory

    International Nuclear Information System (INIS)

    Running a dosimetric service based on TLD technology such as at the Nuclear Research Centre Negev (NRCN) requires a large group of workers to carry out simple mechanical actions such as opening and closing TLD badges, placing and removal of TLD cards from the badges and operating the TLD reader. These actions can be automated to free human resources for other assignments and to improve the quality assurance. At NRCN a project was undertaken to design and build a robotic system based on a manipulator arm. The design was based on the experience achieved with an earlier prototype (1,2). The system stores the TLD badges in special designed boxes, which are transported and stored in computer defined bins. The robotic arm loads and unloads TLD cards to the badges, and loads/unloads the cards to a magazine for the TLD reader. At the Nuclear Research Center Negev (NRCN) each badge is assigned to a specific worker and bears a sticker containing the worker's personal details, also in a machine readable form (barcode). In order to establish a proper QA check, a barcode reader records the information on the badge and on the TLD card placed in this badge and checks their compatibility with the information contained in the main database. Besides the TLD cards loading/unloading station, there is a contamination check station, a cards cleaning station and a UV irradiation box used to reduce the history dependent residual dose. The system was installed at the NRCN dosimetry laboratory It was successfully tested for several hundreds of cycles and will become operational in the first quarter of 2014. As far as we know, there is no similar product available for automatic handling in a TLD laboratory

  6. The personal dosimetry in Mexico

    International Nuclear Information System (INIS)

    The Personal Dosimetry in Mexico, has an approximately 30 year-old history; and it had been and it is at the moment, one of the more important resources with which the personnel that works with ionizing radiation sources counts for its protection. The Personal Dosimetry begins with the film dosimetry, technique that even continues being used at the present time by some users, and the main reason of its use is for economic reasons. At the moment this technique, it has been surpassed, by the Thermoluminescent dosimetry, which has taken a lot of peak, mainly by the technological development with which it is counted at the present time; what has given as a result that this technique becomes tip technology; that supported in the characteristic of the used materials, as the handling and processing of the information associated with the new PC, digitizer cards, software etc, what has allowed increases it potential. In this work the current necessities of the market are presented as well as an analysis of the future real necessities in Mexico, at national level, the companies that provide this service and that they spread to satisfy this necessity of the market, including the different used technologies are also mentioned. The application ranges, at the same time, of the advantages and disadvantages of the different systems of Personal Dosimetry in the market. The companies that at the moment provide the service of Personal Dosimetry, its use materials and equipment in indistinct form, for the monitoring of gamma radiation, beta particles, different qualities of x-ray radiation, and sometimes neutrons. The monitoring of the exposed personnel at the diverse sources of ionizing radiation mentioned is carried out in many occasions without having with the materials (detectors), neither the appropriate infrastructure and therefore without the quality control that guarantees a correct evaluation of the dose equivalent, as a result of the exposure to the ionizing radiations; it

  7. Solid-State Personal Dosimetry

    Science.gov (United States)

    Wrbanek, John D.; Fralick, Gustave C.; Wrbanek, Susan Y.

    2005-01-01

    This document is a web site page, and a data sheet about Personal protection (i.e., space suits) presented to the Radiation and Micrometeoroid Mitigation Technology Focus Group meeting. The website describes the work of the PI to improve solid state personal radiation dosimetry. The data sheet presents work on the active personal radiation detection system that is to provide real-time local radiation exposure information during EVA. Should undue exposure occur, knowledge of the dynamic intensity conditions during the exposure will allow more precise diagnostic assessment of the potential health risk to the exposed individual.

  8. Personal dosimetry service in the Slovak Republic

    International Nuclear Information System (INIS)

    From first January 1996 in Slovak Republic (SR) was started a new independent national personal dosimetry service on external ionizing radiation provided by the Personal Dosimetry Laboratory in the Slovak Institute of Metrology in Bratislava. At first July 1998 was this laboratory delimited from Slovak Institute of Metrology to legal metrology services of SR. This dosimetry services is based fully on the Automated Thermoluminescent Dosimeter Card Reader System made in U.S.A. by Harshaw-Bicron NE, which was given to the Nuclear Regulatory Authority of SR and Slovak Institute of Metrology in Bratislava on an International Technical co-operation project piloted and financed by International Atomic Energy Agency. In this time we have complete TLD Readers Harshaw 6600 and we calibrate and evaluate TLDs of three different type of all body personal dosimeters: (1) beta-gamma TLDs type 0110 with 2 element TL chip type 100 (LiF:Mg,Ti 3.2 x 3.2 x 0.38 mm) fixed in two teflon windows in a aluminium card in a plastic holder with 1000 mg/cm2 Ptfe hemisphere thickens (o 10 mm) to measure the individual dose equivalent penetrating at a the depth 10 mm (Hp(10)) and individual dose equivalent superficial Hs(0.07) at recommended depth of 0.07 mm (type of this holder is 8814); (2) beta-gamma TLDs type 1111 in holders type 8805 with 4 elements of TL chips type 100 to measure both Hp(10) and Hs(0.07) plus lens of eye dose (Hle(3); (3) for measurement of doses in mixed neutron-beta-gamma fields we have more neutron beta gamma dosimeters type 7776 in holders type 8805 with 4 elements of TL chips: three TLD 700 and one TLD 600 LiF chip. The periods of the dosimeters evaluation are 3 months or 1 month for the basic (the all body) beta-gamma dosimeter with 2 element of TL-100 material and 1 month for all other type of dosimeters. Now we monitors about 6000 persons by all body TL dosimeters and about 720 persons by additive finger of wrist strap dosimeters. These are about 5000 measurements

  9. Personal dosimetry in NPP refuelling

    International Nuclear Information System (INIS)

    Doses received by people involved in the operation of Nuclear Power Plants may reach high values, sometimes near limits, particularly during the refuelling operation. With the new ICRP recommendations, the doses produced may exceed the limits that have been now established, hence the practice used must be revised and/or exposure times reduced. In this paper, personal dosimetry from the workers of a Service Company involved in the operation of several Nuclear Power Plants, has been analyzed in order to state the implications of the new ICRP recommendations. Doses higher than new limits will imply a revision of the refuelling policies, thus exposure time would be reduced, and perhaps more workers must be involved in the operation, at least in critical stages. Statistics over the collected data have been estimated and major remarks on possible changes in the practice have been summarized. (author)

  10. Dosimetry Termoluminiscent a new personal dosimetry concept in Nicaragua

    International Nuclear Information System (INIS)

    The present work is based on to study carried out along one year April 1996 until April 1997 at a hospital that located in Managua, here to control of personal dosimetric has been taken in 20 of people that work in the same one, this has been using jointly so much pocket dosemeters (ionization chambers) and thermoluminiscent dosemeters (TLD). To comparison was made among the two systems of personal dosimetry and the varying b was shown among the same ones, considering the fact that the pocket dosemeters to be able to carry out such to delicate company ace it is it the personal dosimetry inside the radiological protection

  11. Dose modulated computed tomography automated dosimetry

    International Nuclear Information System (INIS)

    the appropriate factors as they vary with position scanned through the patient. The ImPACT CT Patient Dosimetry Calculator program is called on a minimum number of times to reduce the time required to perform a dosimetry study. The results are presented in a similar format to the ImPACT CT Patient Dosimetry Calculator worksheet to enable comparisons and to assist use. This automated dose modulated CT dosimetry program has been successfully implemented to perform calculations which would otherwise be too onerous to attempt and has been used in the comparison of patient dose from CT studies submitted as part of a tender evaluation process. It is reliant on the use of the ImPACT CT Patient Dosimetry Calculator, which also utilises Excel. The program requires images to be within a single folder and in dicom format. This program has become an essential tool for performing CT dosimetry, required on scanners capable of dose modulation, in a time effective manner. Copyright (2004) Australasian College of Physical Scientists and Engineers in Medicine

  12. Non-conventional personal dosimetry techniques

    International Nuclear Information System (INIS)

    Established dosimetry has achieved a high standard in personnel monitoring. This applies particularly to photon dosimetry. Nevertheless, even in photon dosimetry, improvements and changes are being made. The reason may be technological progress, or the introduction of new tasks on the basis of the recommendations of international bodies (e.g. the new ICRU measurement unit) of national legislation. Since we are restricting ourselves here to technical trends the author would like to draw attention to various activities of current interest, e.g. the computation of receptor-related conversion coefficients from personal dose to organ or body doses, taking into account the conditions of exposure with respect to differential energy and angular distribution of the radiation field. Realistic data on exposure geometry are taken from work place analyses. Furthermore, the data banks of central personal dosimetry services are subject to statistical evaluation and radiation protection trend analysis. Technological progress and developments are considered from the point of view of personal dosimetry, partial body or extremity dosimetry and accidental dosimetry

  13. Performance testing of UK personal dosimetry laboratories

    CERN Document Server

    Marshall, T O

    1985-01-01

    The proposed Ionising Radiations Regulations will require all UK personal dosimetry laboratories that monitor classified personnel to be approved for personal dosimetry by the Health and Safety Executive. It is suggested that these approvals should be based on general and supplementary criteria published by the British Calibration Service (BCS) for laboratory approval for the provision of personal dosimetry services. These criteria specify certain qualitative requirements and also indicate the need for regular tests of performance to be carried out to ensure constancy of dosimetric standards. This report concerns the latter. The status of the BCS criteria is discussed and the need for additional documents to cover new techniques and some modifications to existing documents is indicated. A means is described by which the technical performance of laboratories, concerned with personal monitoring for external radiations, can be assessed, both initially and ongoing. The costs to establish the scheme and operate it...

  14. Performance testing of UK personal dosimetry laboratories

    International Nuclear Information System (INIS)

    The proposed Ionising Radiations Regulations will require all UK personal dosimetry laboratories that monitor classified personnel to be approved for personal dosimetry by the Health and Safety Executive. It is suggested that these approvals should be based on general and supplementary criteria published by the British Calibration Service (BCS) for laboratory approval for the provision of personal dosimetry services. These criteria specify certain qualitative requirements and also indicate the need for regular tests of performance to be carried out to ensure constancy of dosimetric standards. This report concerns the latter. The status of the BCS criteria is discussed and the need for additional documents to cover new techniques and some modifications to existing documents is indicated. A means is described by which the technical performance of laboratories, concerned with personal monitoring for external radiations, can be assessed, both initially and ongoing. The costs to establish the scheme and operate it are also estimated. (author)

  15. The NRPB PADC neutron personal dosimetry service

    International Nuclear Information System (INIS)

    The UK National Radiological Protection Board has been operating a successful contract neutron personal dosimetry service based on poly-allyl diglycol carbonate (PADC, also known by the trade name CR-39) since 1986, covering about 1500 workers and serving major nuclear sites in the UK and abroad. In that time approximately 100,000 dosemeters have been issued. Since the service was launched, a number of aspects have undergone evolution and it is therefore worthwhile to give an updated summary of how the service operates and performs today. The description covers the choice of plastic and of etching technique, the design of the dosemeter, the features of the automated image analysis, and the characteristics of the control software. Also described are the approaches to calibration and traceability and to compensation for energy and angle dependence, with particular mention of the ability of the service to estimate the quantity Hp(10) in accordance with the requirements of the European Council Directive 96/29/Euratom. (author)

  16. Developments in personal dosimetry for external radiations over the past twenty-one years

    International Nuclear Information System (INIS)

    Since 1963 when SRP was founded the basic philosophy and the techniques employed in personal dosimetry have continuously been developed. New measurement quantities have been recommended by ICRP and ICRU, primary radiation standards have been extended and reference radiations specified. Substantial effort has been spent on the development of new measuring techniques as well as the introduction of automation and computerised dose record keeping systems. This article highlights the major changes in personal dosimetry introduced during the past 21 years. (author)

  17. A low cost active personal dosimetry system

    International Nuclear Information System (INIS)

    A reliable, low cost and compact active personal dosimeter with an on-line alarm facility has been a long-felt need of the nuclear industry. A low cost active personal dosimetry system based on a commercially available p-n junction Si diode detector with a preset dose alarm feature is proposed. A prototype of the compact badge with the alarm facility has been developed and the design features are presented. (author)

  18. Argentine intercomparison programme for personal dosimetry

    International Nuclear Information System (INIS)

    Full text: In 1997 began in Argentine, sponsored by Nuclear Regulatory Authority (ARN) the intercomparison program for personal dosimetry laboratories, on a voluntary basis. Up to know 6 exercises have been done. The program began with a workshop to present the quantities, personal dose equivalent, Hp(10) and extremities dose equivalent, Hs(d). The first aim of this program was to know the true sate of personal dosimetry laboratories in the country, and then introduce the personal dose equivalent, Hp(10) into the dose measurements. The Regional Reference Center for Dosimetry (CCR), belonging to CNEA and the Physical Dosimetry Laboratory of ARN performed the irradiation. Those were done air free and on ICRU phantom, using x-ray, quality ISO: W60, W110 and W200; and 137Cs and 60Co gamma rays. The irradiation was made following ISO 4037 (2) recommendations. There are studied the dose, energy and angular response of the different measuring system. The range of the dose analyzed was from 0.2 mSv up to 80 mSv. The beam incidence was normal and also 20o and 60o. The dosimeters irradiation's were performed kerma in free in air and in phantom in order to study the availability of the service to evaluate the behavior as a function of kerma free in air or Hp(10). At the same time several items have been asked to each participant referring to the action range, the detectors characteristics, the laboratory procedures, the existence of an algorithm and its use for the dosimeter evaluation and the wish to participate in a quality assurance program. The program worked in writing a standard of personal dosimetry laboratories, that was published in 2001. In this work the results of each laboratory and its performance based on the ICRP-60 and ICRP-35 acceptance criteria are shown. Also the laboratory evolution and inquiry analyses have been included. (author)

  19. An updated computer software for personal dosimetry

    International Nuclear Information System (INIS)

    For use in personal dosimetry the ALNOR electronic pocket dosimetry system was installed in 1992. The standard error obtained routinely with this system was less than 10 % in the dose range of 5 μSv to 10 Sv. To keep the database up-to-date, a new software was developed with special emphasis on speed, minimum handling error, and ease-of-use. Except for archivation, this menu-controlled and user-friendly software fits well to different tasks of both datahandling and data-processing. (author)

  20. US accreditation programmes for personal radiation dosimetry

    International Nuclear Information System (INIS)

    In order to verify an acceptable level of safety in the workplace, it is necessary to measure the quantity of ionising radiation to which radiation workers could be, or actually are, exposed. At present, there are organisations capable of providing measurement results with good accuracy and precision. These organisations may provide personal dosimetry services to their own facilities, or to others on a contractual basis. They generally have high quality equipment and well trained personnel. However, in today's climate, it is important to demonstrate and document that these systems and services to others meet national standards of quality. In order to provide a higher level of confidence in the results generated by organisations that provide personal dosimetry services in the US, two accreditation programmes have been established. They are the Department of Energy Laboratory Accreditation Program (DOELAP) and the National Voluntary Laboratory Accreditation Program (NVLAP). These two programmes will be described and results will be given, along with plans for future development. (author)

  1. The ENEA neutron personal dosimetry service

    International Nuclear Information System (INIS)

    The ENEA Radiation Protection Inst. has been operating the only neutron personal dosimetry service in Italy since the 1970's. Since the 1980's the service has been based on PADC (poly-allyl-diglycol carbonate) for fast neutron dosimetry, while thermal neutron dosimetry has been performed using thermoluminescence (TL) dosemeters. Since the service was started, a number of aspects have undergone evolution. The latest and most important changes are as follows: in 1998 a new PADC material was introduced in routine, since 2001 TL thermal dosimetry has been based on LiF(Mg,Cu,P) [GR-200] and 7LiF(Mg,Cu,P) [GR-207] detectors and since 2003 a new image analysis reading system for the fast neutron dosemeters has been used. Herein an updated summary of how the service operates and performs today is presented. The approaches to calibration and traceability to estimate the quantity of Hp(10) are mentioned. Results obtained at the performance test of dosimetric services in the EU member states and Switzerland sponsored by the European Commission and organised by Eurados in 1999 are reported. Last but not least, quality assurance (QA) procedures introduced in the routine operation to track the whole process of dose evaluation (i.e. plastic QA, acceptance test, test etching bath reproducibility and 'dummy customer' (blind test) for each issuing monitoring period) are presented and discussed. (authors)

  2. Argentine republic intercomparation programme for personal dosimetry

    International Nuclear Information System (INIS)

    During the years 1997, 1998 and 1999 it was hold in Argentina, sponsored by Autoridad Regulatoria Nuclear (ARN) the first part of the intercomparison programme for personal dosimetry laboratories. The first aim of this programme was to know the true state of personal dosimetry laboratories in the country, and then to introduce the personal dose equivalent, Hp(10) into the dose measurements and to analyse the angular response of the different measuring systems. The personal dosimetry laboratories are 20, 12 of them belong to the government and the rest are private, they are distributed over all the country. The dosimetric detection systems are based, at a similar proportion, on TLD and films. The Physical Dosimetry Laboratory of ARN takes part in the programme as a verification laboratory. The dosimeters were irradiated in the Regional Reference Centre for Dosimetry of the Comision Nacional de Energia Atomica and in the ARN in radiation X beams, ISO WIDE SERIES W60, W110, W200 and Cs-137 and Co-60 sources. The dosimeters irradiations were performed kerma free in air and in phantom in order to study the availability of the service to evaluate the behaviour as a function of kerma free in air or the personal dose equivalent, Hp(10). The beam incidence was normal and also 20deg and 60deg. In order to know the operational conditions in each service for the dose assessment in normal and accidental situations high and low doses have been given to the dosimeters. At the same time several items have been asked to each participant referring to the action range, the detector characteristics, the availability of laboratory procedures, the existence of an algorithm and its use for the dosimeter evaluation and the wish to participate in a quality assurance programme. In this work the results of each laboratory and its performance based on the ICRP 60 and ICRP 35 acceptance criteria are shown. Also, the laboratory evolution and inquiry analyses have been included. At the same time

  3. Algorithm Verification for A TLD Personal Dosimetry System

    International Nuclear Information System (INIS)

    Dose algorithms are used in thermoluminescence personnel dosimetry for the interpretation of the dosimeter response in terms of equivalent dose. In the present study an Automated Harshaw 6600 reader was rigorously tested prior to use for dose calculation algorithm according to the standard established by the US Department of Energy Laboratory Accreditation Program (DOELAP). Also, manual Harshaw 4500 reader was used along with the ICRU slab phantom and the RANDO phantom in experimentally determining the photon personal doses in terms of deep dose, Hp(10), shallow dose, Hp(0.07), and eye lens dose, Hp(3),. Also, a Monte Carlo simulation program (VMC-dc) free code was used to simulate RANDO phantom irradiation process. The accuracy of the automated system lies well within DOELAP tolerance limits in all test categories

  4. The personal dosimetry in Mexico; La dosimetria personal en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Salazar, M.A. [Proxtronics/ Asesoria Integral en Dosimetria Termoluminiscente S.A. de C.V., Canal de Miramontes 2030-14, Col. Educacion, 04400 Mexico D.F. (Mexico)]. e-mail: aidtsa@avantel.net

    2006-07-01

    The Personal Dosimetry in Mexico, has an approximately 30 year-old history; and it had been and it is at the moment, one of the more important resources with which the personnel that works with ionizing radiation sources counts for its protection. The Personal Dosimetry begins with the film dosimetry, technique that even continues being used at the present time by some users, and the main reason of its use is for economic reasons. At the moment this technique, it has been surpassed, by the Thermoluminescent dosimetry, which has taken a lot of peak, mainly by the technological development with which it is counted at the present time; what has given as a result that this technique becomes tip technology; that supported in the characteristic of the used materials, as the handling and processing of the information associated with the new PC, digitizer cards, software etc, what has allowed increases it potential. In this work the current necessities of the market are presented as well as an analysis of the future real necessities in Mexico, at national level, the companies that provide this service and that they spread to satisfy this necessity of the market, including the different used technologies are also mentioned. The application ranges, at the same time, of the advantages and disadvantages of the different systems of Personal Dosimetry in the market. The companies that at the moment provide the service of Personal Dosimetry, its use materials and equipment in indistinct form, for the monitoring of gamma radiation, beta particles, different qualities of x-ray radiation, and sometimes neutrons. The monitoring of the exposed personnel at the diverse sources of ionizing radiation mentioned is carried out in many occasions without having with the materials (detectors), neither the appropriate infrastructure and therefore without the quality control that guarantees a correct evaluation of the dose equivalent, as a result of the exposure to the ionizing radiations; it

  5. Personal dosimetry service of VF, a.s. company

    International Nuclear Information System (INIS)

    The VF, a.s. Company will extend its services in the area of personal dosimetry at the end of 2008, which is fully in compliance with the requirements of the Atomic Act, section 9 paragraph (1) letter r) and Decree on Radiation Protection, section 59 paragraph (1) letter a). Optically stimulated luminescence was selected in VF .a.s. as the most advantageous and the most advanced technology for the integral personal dosimetry . Optically stimulated luminescence (OSL) has been using in dosimetry for more than ten years. Although it is relatively new technology , its indisputable advantages predetermine that technology has significantly benefited in personal dosimetry services within a short time all over the advanced world. The VF, a.s. personal dosimetry service is based on the licensed products of LANDAUER, the US company, which is the world leader in OSL dosimetry. Crystalline Al2O3:C was selected as the detection material. All equipment of personal dosimetry service is installed in the VF Centre of Technology in Cerna Hora. The personal dosimetry service is incorporated in the International LANDAUER Dosimetry Service Network, and in the European Union, it is directly linked to the LANDAUER European Headquarters with its office in Paris. As a part of the OSL technology licence, the VF personal dosimetry service was included in the inter-laboratory comparison programme of the LANDAUER syndicate. (author)

  6. Automation of radiation dosimetry using PTW dosemeter and LabVIEWTM

    International Nuclear Information System (INIS)

    Automation of UNIDOS 'Dosemeter' using personal computer (PC) is discussed in this paper. In order to save time and eliminate human operation errors during the radiation dosimetry, suitable software, using LabVIEWTM graphical programming language, was written to automate and facilitate the processes of measurements, analysis and data storage. The software calculates the calibration factor of the ionization chamber in terms of air kerma or absorbed dose to water according to IAEA dosimetry protocols. It also has the ability to print a calibration certificate. The obtained results using this software are found to be more reliable and flexible than those obtained by manual methods previously employed. Using LabVIEWTM as a development tool is extremely convenient to make things easier when software modifications and improvements are needed.

  7. Automation of radiation dosimetry using PTW dosemeter and LabVIEW™

    Science.gov (United States)

    Weiss, C.; Al-Frouh, K.; Anjak, O.

    2011-10-01

    Automation of UNIDOS "Dosemeter" using personal computer (PC) is discussed in this paper. In order to save time and eliminate human operation errors during the radiation dosimetry, suitable software, using LabVIEW™ graphical programming language, was written to automate and facilitate the processes of measurements, analysis and data storage. The software calculates the calibration factor of the ionization chamber in terms of air kerma or absorbed dose to water according to IAEA dosimetry protocols. It also has the ability to print a calibration certificate. The obtained results using this software are found to be more reliable and flexible than those obtained by manual methods previously employed. Using LabVIEW™ as a development tool is extremely convenient to make things easier when software modifications and improvements are needed.

  8. Personal dosimetry for external radiation exposure in Europe

    International Nuclear Information System (INIS)

    This article summarizes a report on harmonisation and dosimetric quality assurance in individual monitoring for external radiation, published by the European Radiation Dosimetry Group (EURADOS). The report comprises three parts: (1) procedures and regulations in countries of the European Union and Switzerland with respect to personal dosimetry; (2) a catalogue with descriptions of dosimetry systems in the fore-mentioned countries; and (3) performance testing of dosimetric services in EU Member States and Switzerland. 17 refs

  9. Personal Dosimetry Enhancement for Underground Workplaces

    Directory of Open Access Journals (Sweden)

    L. Thinová

    2005-01-01

    Full Text Available Personal dosimetry for underground workers mainly concerns measurement of the concentration of radon (and its daughters and the correct application of the data in dose calculation, using a biokinetic model for lung dosimetry. A conservative approach for estimating the potential dose in caves (or underground is based on solid state alpha track detector measurements. The obtained dataset is converted into an annual effective dose in agreement with the ICRP recommendations using the “cave factor”, the value of which depends on the spectrum of aerosol particles, or on the proportional representation of the unattached and the attached fraction and on the equilibrium factor. The main difference between apartments and caves is the absence of aerosol sources, high humidity, low ventilation rate and the uneven surface in caves. A more precisely determined dose value would have a significant impact on radon remedies or on restricting the time workers stay underground. In order to determine  how the effective dose is calculated, it is necessary to divide these areas into distinct categories by the following measuring procedures: continual radon measurement (to capture the differences in EERC between working hours and night-time, and also between daily and seasonal radon concentration variations; regular measurements of radon and its daughters to estimate the equilibrium factor and the presence of 218Po; regular indoor air flow measurements to study the location of the radon supply and its transfer among individual areas of the cave; natural radioactive element content evaluation in subsoils and in water inside/outside, a study of the radon sources in the cave; aerosol particle-size spectrum measurements to determine the free fraction; monitoring the behaviour of guides and workers to record the actual time spent in the cave, in relation to the continuously monitored levels of Rn concentration. 

  10. New TL detectors for personal neutron dosimetry

    International Nuclear Information System (INIS)

    One of the main objectives in the application of TL detectors to neutron dosimetry is to obtain a high ratio of neutron to gamma response for a better separation of the neutron component. In the case of 6LiF, one may reduce the effective thickness of the detector in order to exploit the difference between neutron and gamma absorption, either by making the sensitive layer of TL chip thinner or by reducing its transparency to TL light. Two new types of sintered 6LiF:Mg,Ti detectors have been developed: a sandwich detector with a non-thermoluminescent LiF base, and a detector in which the phosphor is mixed with graphite. Three thicknesses of the sensitive layer (45, 60, 80 mg.cm-2) and two carbon concentrations (1%, 4%) were tested. The detectors were irradiated by moderated neutrons from Pu-Be and 252Cf sources and by thermal neutrons from a nuclear research reactor. Results of measurements indicate that for the detector of thickness 45 mg.cm-2 the ratio of neutron to gamma response increases 2-4 times, compared with the Harshaw TLD-600 while the neutron sensitivity is maintained. Other dosimetric characteristics of the detector remain unchanged, making it possible to use standard annealing and readout procedures. The new detectors will be applied in a personal neutron albedo dosemeter with a detection limit better than 100 μSv in a gamma background of the range of several mSv. (author)

  11. Glass badge dosimetry system for large scale personal monitoring

    International Nuclear Information System (INIS)

    Glass Badge using silver activated phosphate glass dosemeter was specially developed for large scale personal monitoring. And dosimetry systems such as an automatic leader and a dose equipment calculation algorithm were developed at once to achieve reasonable personal monitoring. In large scale personal monitoring, both of precision for dosimetry and confidence for lot of personal data handling become very important. The silver activated phosphate glass dosemeter has basically excellent characteristics for dosimetry such as homogeneous and stable sensitivity, negligible fading and so on. Glass Badge was designed to measure 10 keV - 10 MeV range of photon. 300 keV - 3 MeV range of beta, and 0.025 eV - 15 MeV range of neutron by included SSNTD. And developed Glass Badge dosimetry system has not only these basic characteristics but also lot of features to keep good precision for dosimetry and data handling. In this presentation, features of Glass Badge dosimetry systems and examples for practical personal monitoring systems will be presented. (Author)

  12. Passive detectors for neutron personal dosimetry: State of the art

    International Nuclear Information System (INIS)

    Passive, solid-state detectors still dominate the field of neutron personal dosimetry, mainly thanks to their low cost, high reliability and elevated throughput. However, the recent appearance in the market of several electronic personal dosemeters for neutrons presents a challenge to the exclusive use of passive systems for primary or official dosimetry. This scenario drives research and development activities on passive dosemeters towards systems offering greater accuracy of response and lower detection limits. In addition, further applications and properties of the passive detectors, which are not met by the electronic devices, are also being explored. In particular, extensive investigations are in progress on the use of solid-state detectors for aviation and space dosimetry, where high-energy neutron fields are encountered. The present situation is also stimulating an acceleration in the development of international standards on performance and test requirements for passive dosimetry systems, which can expedite significantly the implementation of techniques in commercial personal dosimetry services. Upcoming standards will cover thermoluminescence albedo dosemeters, etched-track detectors, superheated emulsions and direct ion storage chambers, attesting to the level of maturity reached by these techniques. This work reviews the developments in the field of passive neutron dosimetry emerged since the previous Neutron Dosimetry Symposium, reporting on the current status of the subject and indicating the direction of ongoing research. (authors)

  13. Eurados trial performance test for neutron personal dosimetry

    DEFF Research Database (Denmark)

    Bordy, J.M.; Stadtmann, H.; Ambrosi, P.;

    2001-01-01

    measured, but particular problems were noted in the determination of intermediate energy fields and large incident angles, demonstrating the difficulties of neutron personal dosimetry. Of particular concern from a radiological protection point of view was the large number of results underestimating...... personal dose equivalent. A considerable over-response was noted in a few cases....

  14. System of data management in 'Dosis' personal dosimetry

    International Nuclear Information System (INIS)

    The storage and control of the data of a service of personal dosimetry is a task that requires specify care in data handling and manipulation. This activity becomes more annoying of making manually when the volume of users of the service is significant. The External Dosimetric Laboratory of the Center for Radiation Protection and Hygiene has developed a system of administration of data that allows the storage, control and analysis of the data generated by the Service of Personal Dosimetry in an efficient and reliable way. This paper describes the characteristics of the System for Administration of Data in Personal Dosimetry 'Dosis', as well as their design and programming. The importance of this System for the laboratory and the advantages of their application are described. The characteristics of the different modules are also described. (author)

  15. Nationwide quality assurance and control of Italian personal dosimetry services

    International Nuclear Information System (INIS)

    A working group (called ENEA-EDP, personal dosimetry experts) has been established in the framework of ENEA institutional tasks to assure the quality of Italian personal dosimetry services. The results are quite important as no official guidelines on the performance of personal dosimetry services have been established in Italy. The paper outlines the activity of the ENEA-EDP group and recalls the reliability evaluation criteria detailed in a different report. The paper also summarizes the procedures to be followed by the services, on a voluntary basis, in order to be listed among the 'officially' reliable ones. Results and comments of six test sessions for 51 services are also described. (author). 8 refs, 3 figs, 3 tabs

  16. Eurados trial performance test for neutron personal dosimetry

    DEFF Research Database (Denmark)

    Bordy, J.M.; Stadtmann, H.; Ambrosi, P.; Bartlett, D.T.; Christensen, P.; Colgan, T.; Hyvonen, H.

    This paper reports on the results of a neutron trial performance test sponsored by the European Commission and organised by EURADOS. As anticipated, neutron dosimetry results were very dependent on the dosemeter type and the dose calculation algorithm. Fast neutron fields were generally well...... measured, but particular problems were noted in the determination of intermediate energy fields and large incident angles, demonstrating the difficulties of neutron personal dosimetry. Of particular concern from a radiological protection point of view was the large number of results underestimating...... personal dose equivalent. A considerable over-response was noted in a few cases....

  17. EURADOS trial performance test for neutron personal dosimetry

    International Nuclear Information System (INIS)

    This paper reports on the results of a neutron trial performance test sponsored by the European Commission and organised by EURADOS. As anticipated, neutron dosimetry results were very dependent on the dosemeter type and the dose calculation algorithm. Fast neutron fields were generally well measured, but particular problems were noted in the determination of intermediate energy fields and large incident angles, demonstrating the difficulties of neutron personal dosimetry. Of particular concern from a radiological protection point of view was the large number of results underestimating personal dose equivalent. A considerable over-response was noted in a few cases. (author)

  18. Argentine intercomparison programme for personal dosimetry

    International Nuclear Information System (INIS)

    An Intercomparison Programme is being carried out in Argentina for individual monitoring services. The programme was designed to test, on a voluntary basis, the performance of the laboratories that provide individual monitoring services for X and gamma radiation fields in the range from low-level dose up to 100 mSv. Irradiations were performed in full accordance with ISO 4037-3 recommendations by the Regional Reference Centre for Dosimetry (CRRD), belonging to Atomic Energy Commission (CNEA) and the Physical Dosimetry Laboratory of the Nuclear Regulatory Authority (ARN). At the same time, several items have been asked to each participant pertaining to the action range, the detectors' characteristics, the laboratory procedures, the existence of an algorithm and its use for the dosemeter evaluation. In this study the evolution of the laboratories' performance throughout the programme, based on ISO 14146 acceptance criteria, is shown. (authors)

  19. New web interface for Personal dosimetry VF, a.s

    International Nuclear Information System (INIS)

    The lecture will introduce new functions and graphic design WebSOD - web interface Personal dosimetry Service VF. a.s. which will be updated in November 2014. The new interface will have a new graphic design, intuitive control system and will be providing a range of new functions: - Personal doses - display of personal doses from personal, extremity and neutron dosimeters including graphs, annual and electronic listings of doses; - Collective doses - display of group doses for selected periods of time; Reference levels - setting and display of three reference levels; - Evidence - enables administration of monitored individuals - beginning, ending of monitoring, or editing the data of monitored persons and centers. (author)

  20. Personal Dosimetry in UHC Sestre Milosrdnice: 10-Years Review

    International Nuclear Information System (INIS)

    Personal dose monitoring in UHC 'Sestre milosrdnice' is regulary performed for about 300 exposed workers involved in a variety of tasks with different sources of ionizing radiation. Exposed workers are required to wear personal dosimeters which are read on monthly basis and dose records are kept in the hospital. In this paper an overview of personal dosimetry data from year 2003 till 2013 is presented. Film dosimeters were used for personal dosimetry untill 2010 when the thermoluminescent (TL) dosimetry was introduced. Dosimeters are calibrated to measure personal dose equivalent Hp(10). Received doses are analyzed for workers in the field of nuclear medicine, radiotherapy (external beam and brachytherapy), general diagnostic radiology and interventional radiology. Analysis of received doses in the whole period resulted with an average individual dose in nuclear medicine of 0.6 mSv/y, which decreased to 0.21 mSv/y in the last three years, caused by more precise dosimetric methods with TL dosimetry and improved conditions of radiation protection. In the same three-year period, in interventional radiology doses were 0.32 mSv/y, compared to 0.29 mSv/y obtained for a previous seven years. This was expected due to the escalation in a number of interventions and new installed equipment. There was no such difference in diagnostic radiology doses, showing that film dosimetry is suitable for x ray energies. Analysis of all the readings showed a significant influence of measurement procedures on personal dosimeter dose and also the importance of continuous monitoring of the dose records in order to improve the conditions of radiation protection and achieving the ALARA goal.(author)

  1. Trends of personal dosimetry at atomic power plants

    International Nuclear Information System (INIS)

    The individual dosimetry at the atomic power station is sorted for monthly dosimetry, daily dosimetry and special job dosimetry in high dose circumstance. Film badge (passive dosimeter) can measure gamma dose, beta dose and neutron dose respectively lower than about 0.1 mSv. While workers are in the radiation controlled area, they have to wear the dosimeters and the individual dose is accumulated for every one month. Recently the Silicon semiconductors detecting beta ray and neutron have been developed. With microcircuit technology and these new sensors, new multiple function dosimeter of the card size had been put to practical use. The result of dose measurement obtained by the electronic dosimeter is consistent well with the measurement of usual film badge and new dosimeter can determine the dose as low as 0.01 mSv. The result is stored in the non-volatile memory in the electronic personal dosimeter and held for more than one year without the power supply. The function to read data directly from the memory improves the reliability of the data protection. The realization of the unified radiation control system that uses the electronic personal dosimeter for monthly dosimetry is expected. (J.P.N.)

  2. Thermoluminescent dosimetry and assessment of personal dose

    International Nuclear Information System (INIS)

    Thermoluminescence is discussed in terms of the energy band structure of a crystalline solid and the trapping of charge carriers by point defects. Some general properties of thermoluminescent materials used for dosimetry are outlined, with thermoluminescence of CaSO4:Dy being described in detail. The energy response function and the modification of the energy response of a dosimeter by shielding are discussed. The final section covers the connection between exposure, as recorded by a TLD badge, and the absorbed dose to various organs from gamma radiation in a uranium mine; the conversion from absorbed dose to dose equivalent; and uncertainties in assessment of dose equivalent

  3. Technical features of the personal internal dosimetry service of Tecnatom

    International Nuclear Information System (INIS)

    Since the beginning of the operation of nuclear energy in Spain, all the nuclear power plants have established dosimetry services with all the means necessary to measure and determine doses, both internal as external. In that way, the Personal Internal Dosimetry Service of Tecnatom was authorised by the Spanish Nuclear Safety Council (CSN) in October 1988. Actually, the capabilities of the Service are the following: - Direct dosimetry (in-vivo measurements): assistance to the existing services in the plants and installations of the nuclear-fuel cycle, in order to carry out routine and incident bioassay analysis, and also in situations where there is a great movement of personnel such as outages and shutdowns. - Indirect dosimetry (in-vitro measurements): complete process, radiochemistry analysis and internal dose assessments of radionuclide intakes. - Participation in special situations like real emergencies, drill exercises and exceptional tests. - Calibration and verification of fast and bed internal dosimetry counters for the Dosimetry Services in NPP. For this purpose, the Dosimetry Service has two Mobiles Units, each one containing a body counter from Helgeson Scientific Company. Mobile Unit I is provided with a counter with four INa (Tl) detectors, as well as twenty proportional detectors to assess and evaluate also external surface contamination. This equipment is intended to be used for the fast determination of the presence or not of radionuclides inside the body. In one or two minutes this equipment is able of confirming whether or not radioactive materials are present inside, as well as outside the body. Mobile Unit II is provided with a 'Whole Body Counter' (WBC), with four INa (Tl) detectors. The detector system provides also a variable collimator to allow accurate measurements of some specific organs. This unit is specially designed to perform routine and non-routine measurements of nuclear, radioactive, medical and industrial facilities as well as

  4. Study of a personal passive multielement dosimeter for neutron dosimetry

    International Nuclear Information System (INIS)

    Personal neutron dosimetry is presently carried out with unsatisfying methods, viz. the use of nuclear emulsions ''blind'' for energy below 1.5 MeV, or the operation of albedo detectors that must be calibrated at the various working places since their responses vary largely as a function of neutron energies. A progress report is presented on the DINEM project studies. The DINEM (personal multielement neutron dosimeter) is made of an albedo dosimeter ''PGP-DIN'' detecting neutrons with energies below 7 keV and a solid track detector detecting energies above 100 keV. The latest improvements on the use of CN 85 as a solid track detector announce that the difficult problem of personal dosimetry should be solved soon

  5. Current problems and expected improvements in personal neutron dosimetry

    International Nuclear Information System (INIS)

    Many technological activities involve the potential for worker exposure to neutrons. The determination of neutron personal dose equivalent is difficult due to a number of factors including the materials and methods used to evaluate the response of personal dosemeters and the quantities for expressing dose equivalent. Nevertheless, recent progress has been made in the development of devices and techniques for the measurement and calibration of neutron personal dosemeters. The quantities and units used to express neutron dose equivalent are being improved and clarified. Therefore, it is expected that a number of remaining difficulties with neutron dosimetry will be mitigated. (authors)

  6. A personal dosimetry intercomparison study in Asian and Pacific region

    International Nuclear Information System (INIS)

    Two personal dosimeter intercomparisons were conducted under International Atomic Energy Agency's RCA (Regional Cooperative Agreement) radiation protection project for Asian and Pacific region during 1990 - 1997. The first intercomparison program was carried out from 1990 to 1992. The main objective of that program was to obtain information on the technical status of basic radiation protection measurements in each participating member country and their ability to conduct monitoring for occupational protection. The dosimeters were irradiated free-in-air and the doses were expressed as exposure in R. The program was successfully completed and the results have been published. The second personal dosimeter intercomparison program was conducted from 1995 to 1997. A major objective of the second program was assess the ability of RCA member state personal dosimetry services to make measurements in terms of the operational quantity, personal dose equivalent, Hp(d), including suitable use of the associated calibration procedures. More than thirty dosimetry services from 16 RCA member countries participated in this program. The intercomparison was performed in two irradiation phases. Four calibration laboratories from three member countries provided X-ray and gamma ray irradiations for over a thousand dosimeters. The irradiations were conducted in 12 categories, defined by their photon energies and angles of incidence, using ISO water filled back-scatter phantom. All the results were expressed as the ratio of the dose value evaluated by each participant to the delivered dose. The deviations of these values from unity were used for analyzing the results. The performance of each dosimetry system was evaluated against draft recommendations of the International Atomic Energy Agency for personal dosimetry system accuracy. The results showed that the quality of individual monitoring in most of the RCA member countries was at an acceptable level with a few exceptions. They also

  7. Qualification of personal dosimetry services in Italy: procedures and results

    International Nuclear Information System (INIS)

    About 80 services, processing over 2,000,000 dosemeters yearly, operate in Italy today. As no official guidelines on the performance of personal dosimetry services have been established in Italy, a Working Group (called ENEA-EDP, Personal Dosimetry Experts) has been established within the framework of the ENEA institutional task, to test, on a voluntary basis, the reliability of the services. The Group published a paper on the test programme: it deals with services' methods, facilities, instruments, staff, organisation and also with the irradiation test in the 0.1-50 mGy air-kerma range at different X and gamma ray energies. The test programme follows the international standards, with due attention to European Community recommendations. At year's end 1992, 52 services, gathering 56 different types of dosemeters, have been tested in nine sessions. The results of the tests and the evaluation methods of the services tested are discussed. (author)

  8. Status and technology of personal dosimetry in Latvia

    International Nuclear Information System (INIS)

    Measurement and control of the doses absorbed under ionising radiation diminish the risk of professional diseases, for which purpose the personal dosimetry should be applied. Dose measuring and register keeping is performed at the Thermoluminescent Dosimetry (LTD) Laboratory of the P.Stradin Clinical University Hospital. As an alternative method for individual dose estimation, the Electron Paramagnetic Resonance (EPR) spectroscopy is applied . The LTD method based on lithium fluoride (FiF) material is used for monitoring the occupationally exposed workers and it can serve more than one thousand persons. The EPR technique has been applied for dose measurements of Chernobyl clean-up workers. The paper reports on the problem at dose estimation by TLD and EPR methods and quality control by TLD method and describes them based on the analysis od the doses received by personnel. (author)

  9. The status of personal dosimetry in the United Kingdom

    International Nuclear Information System (INIS)

    At present personnel monitoring is carried out in the UK in accordance with Regulations and Codes of Practice. In the near future these will be replaced by new Regulations. About 120,000 persons wear personal dosemeters issued by some 47 laboratories. The main requirement is for body monitoring for X-, beta- and gamma-radiations performed by photographic film and thermoluminescent dosemeters. In addition, small percentages of the total monitored receive extremity or neutron dosemeters. Substantial effort is being applied to research in personnel dosimetry in new materials, dosemeters and dosimetry systems. No intercomparison exercises have been carried out in the UK since 1971 but the larger laboratories have taken part in the CEC Intercomparison programme from which useful information has emerged. (author)

  10. Intercomparison of personal dosimetry for service providers in Pakistan.

    Science.gov (United States)

    Jabeen, Akhter; Salman, Syed Ahmad

    2009-02-01

    An intercomparison exercise for personal dosimetry service providers within Pakistan was conducted by the Health Physics Division of the Pakistan Institute of Nuclear Science and Technology. Participation in the exercise was on voluntary basis. The exercise was carried out to harmonize individual dose monitoring techniques for high energy photons in terms of a new operational quantity, namely personal dose equivalent Hp(10), for personal dosimetry in accordance with the recommendations of the International Commission on Radiation Units and Measurements. Each laboratory submitted 25 dosimeters for participation in the intercomparison exercise. Protection level Co and Cs sources were used for irradiation of dosimeters on a water phantom according to International Atomic Energy Agency protocol at the Secondary Standard Dosimetry Laboratory. Hp(10) doses for five different dose levels were measured by the participating laboratories. The ratios of measured dose/true dose (Hm/Ht) remained in the range of 0.66 to 1.11 for the Co source and 0.84 to 1.17 for the Cs source. Performance of service providers' laboratories to measure Hp(10) doses was analyzed and evaluated in terms of trumpet curves plotted for photons at a 95% confidence level. PMID:19125056

  11. Personal dosimetry performance testing in the United States

    International Nuclear Information System (INIS)

    The basis for personal dosimetry performance testing in the United States is ANSI/HPS N13.11. Now in it's fourth edition, this standard has been in place since 1983. Testing under this standard is administered by the National Voluntary Laboratory Accreditation Program (NVLAP), and accreditation of dosimetry processors under this program is required by U.S. Nuclear Regulatory Commission (NRC) regulations. The U.S. Department of Energy (DOE) also maintains a testing program for its laboratories and contractors, administered by the Department of Energy Laboratory Accreditation Program (DOELAP). One of the goals of this current revision was the modification of ANSI/HPS N13.11 to allow acceptance by both testing programs in order to bring harmonization to U.S. personal dosemeter performance testing. The testing philosophy of ANSI/HPS N13.11 has always combined elements of type testing and routine performance testing and is thus different from the testing philosophy used in the rest of the world. In this paper, the history of performance testing in the U.S. is briefly reviewed. Also described is the revision that produced the fourth edition of this standard, which has taken place over the last three years (2005-2008) by a working group representing national standards laboratories, government laboratories, the military, dosimetry vendors, universities and the nuclear power industry. (author)

  12. Personal dosimetry in the PET Centre Prague

    International Nuclear Information System (INIS)

    This work is focused on radiation protection in the PET Centre Prague. The personal year dose equivalents of physicians, technologists and labtechnologists in the period 1997-2000 are presented. Dose equivalents are listed for each group as collective, mean and maximum dose equivalents and number of people in the evaluated group. There is an increase in the dose equivalents in 1999 when the PET scanner was installed. Later on, when personnel was trained and better local shielding was used, the increase is not much higher even though the number of patients investigated per day doubled. The radiation field measurements showed that the radiation dose equivalent rate outside the controlled area is on the background level of about 0.17-0.18 mSv/hour. (author)

  13. System for personal dosimetry in interventional radiology

    International Nuclear Information System (INIS)

    The progress made in radiological image processing and transmission is being widely applied in new branches of medicine. The increasing use of interventional radiology in research and clinical practice means that new groups of workers are being exposed to radiation and need to be covered by a system of radiation protection. Interventional radiology requires the operator and assisting personnel to remain close to the patient; typically these procedures require placement of the hands within the radiation field. A system of hand dose monitoring was introduced in Poland in 2000. This system uses ring badges with TL dosemeters. The measurements conducted so far characteristically show an asymmetric right-sided distribution of monthly doses. As expected, operators and their assistants are the most exposed groups of medical personnel. Average hand doses may be very dependent on the type of procedure, personal skills and quality of equipment. The hand doses of these personnel are significant from a radiological protection point of view. (author)

  14. Education and training activities on personal dosimetry service in Turkey

    International Nuclear Information System (INIS)

    A personal dosimetry service that evaluates the occupational doses for external and internal radiation of the radiation workers is one of the main components of radiation protection programme. The education and training (E and T) activities in this field are basic aspects of the optimisation of all exposures to radiation. The E and T activities in the field of occupational radiation protection at the national and international level are of main interest and implemented by the Ankara Nuclear Research and Training Center. This study describes the Turkish experience in E and T of the staff of dosimetry services, postgraduate students and medical physics experts. In Turkey, the first individual monitoring training course was conducted in 2012. The aim of this study is to provide a structured description of postgraduate courses that are addressed to qualified experts and medical physics experts, and the modules are mainly dedicated to individual monitoring. (authors)

  15. Testing and evaluating personal dosimetry services in 1976

    International Nuclear Information System (INIS)

    The National Sanitation Foundation (NSF) of Ann Arbor, Michigan, conducts an annual testing program for personal dosimetry services. In 1976, five processors participated in the testing program in order to be certified by NSF. Four other processors participated on a non-certification basis. Six of the participants are large commercial processors, and three are non-commercial, in-house processors. Some dosimetry services submitted film badges, some submitted thermoluminescent dosimeters, and some submitted both. This paper shows the results of all processors in each of nine radiation categories. The average performance of all the processors tested is good. The average reported quantity of radiation among the 927 dosimeters tested is within about 25% of the actual delivered quantity. However, the individual performance of some processors varies greatly from the average performance of all the processors. (author)

  16. Personal Doses Recorded by Service of Personal Dosimetry

    International Nuclear Information System (INIS)

    In this work we present occupational exposure statistics on: number of workers on different dose ranges; average of the mean annual doses (MAD) over the period 2000 - 2007 on all monitored workers as well as on those who have been received doses over the minimum detection limit (MDL). The statistic is made on different types of nuclear laboratories. The data are obtained on almost 1000 workers occupational exposure to different sources of radiations (gamma and X-ray) and monitored by Photo dosimetry Survey Unit, IFIN - HH. These results point out the evolution of the individual doses received during eight years and can be used to analyse the need of radiation protection in different nuclear facilities from Romania

  17. Personal radon dosimetry from eyeglass lenses

    International Nuclear Information System (INIS)

    Eyeglass lenses are commonly composed of allyl-diglycol carbonate (CR-39), an alpha-particle detecting plastic, thus making such lenses personal radon dosemeters. Samples of such lenses have been obtained, etched to reveal that radon and radon progeny alpha tracks can be seen in abundance, and sensitivities have been calibrated in radon chambers as a primary calibration, and with a uranium-based source of alpha particles as a convenient secondary standard. With one exception natural, environmental (fossil) track densities ranged from less than 3,000 to nearly 70,000 per cm2 for eyeglasses that had been worn for various times from one to nearly five years. Average radon concentrations to which those wearers were exposed are inferred to be in the range 14 to 130 Bq.m-3 (0.4 to 3.5 pCi.l-1). A protocol for consistent, meaningful readout is derived and used. In the exceptional case the fossil track density was 1,780,000 cm-2, and the inferred (24 h) average radon concentration was 6500 Bq.m-3 (175 pCi.l-1) for a worker at an inactive uranium mine that is used for therapy. (author)

  18. Automation of the particle dosimetry and the dose application for radiobiological experiments at a vertical proton beam

    CERN Document Server

    Moertel, H; Eyrich, W; Fritsch, M; Distel, L

    2002-01-01

    A facility with a vertical beam for radiobiological experiments with low-energy protons has been setup at the Tandem accelerator at Erlangen. This energy region is optimal to investigate the biological effects of the linear energy transfer in the Bragg region under physiological conditions. A new automated data acquisition system for dosimetry and monitoring based on a personal computer was developed and optimized for this setup. A specially designed sample holder offers possibilities of cooling or changing of atmosphere during irradiation. First irradiations of biological samples have shown the functionality of the setup.

  19. Automation of the particle dosimetry and the dose application for radiobiological experiments at a vertical proton beam

    Science.gov (United States)

    Mörtel, H.; Georgi, J.; Eyrich, W.; Fritsch, M.; Distel, L.

    2002-08-01

    A facility with a vertical beam for radiobiological experiments with low-energy protons has been setup at the Tandem accelerator at Erlangen. This energy region is optimal to investigate the biological effects of the linear energy transfer in the Bragg region under physiological conditions. A new automated data acquisition system for dosimetry and monitoring based on a personal computer was developed and optimized for this setup. A specially designed sample holder offers possibilities of cooling or changing of atmosphere during irradiation. First irradiations of biological samples have shown the functionality of the setup.

  20. BeOSL system for personal dosimetry : dosimetric characteristics and practical application

    International Nuclear Information System (INIS)

    Full text: BeOSL system of Dosimetric s is very easy to use, assimilate and maintain. Our dosimeter defines a milestone in the supervision of personal equivalent dose of Hp (10) and Hp (0.07) it covers the range of total energy of 16 KeV to 10 MeV. For this energy range is exceptional in its energy dependence for official personal dosimetry. The BeOSL system consists of two modules, one of them is the BeOSL reader that measures the radiation exposure using the latest technology, optically stimulated luminescence (OSL). The reading is extremely fast; it does not require consumables such as nitrogen or other. The detector material is beryllium oxide (Be O); this is an OSL material tissue equivalent and therefore is ideal for personal dosimetry. The BeOSL technology allows multiple readings of the dosimeter (re-read) to verify the dose or archive the dosimeter. One of the biggest advantages of BeOSL system is its modular concept allows the system to run as a manual solution or as a complete automated robotic system, which can be filled with up to 5,000 dosimeters as bulk cargo. (Author)

  1. Official dosimetry with personal electronic dosemeters - The framework in Germany

    International Nuclear Information System (INIS)

    In Germany, personal electronic dosemeters (AEPDs) are presently applied mainly for operational radiation protection monitoring particularly in nuclear power engineering companies, large hospitals and research centres. This is done in addition to the official dosimetry of record. Therefore, frequently, double monitoring occurs - officially and operationally. A crucial advantage of AEPDs compared with passive dosemeters is the ability to adapt the monitoring period to the working time in controlled areas and to allow an immediate readout of the dose after leaving the controlled area, e.g. a job-related monitoring is possible by correlating the readout dose with the job performed. Germany started a general research project, consisting of two parts, for an optimised implementation of personal electronic dosemeters into official dosimetry. The use of AEPDs as official dosemeters depends on an approval by Federal and Federal State ('Laender') authorities as an official dosimetry system, which has to comply with special requirements ensuring that the legal requirements are fulfilled. The formulation of these special requirements is in the focus of part one of the research project, supervised by the Federal Office for Radiation Protection (BfS) and performed by the Gesellschaft fuer Anlagen-und Reaktorsicherheit (GRS) mbH. As a result of part one, a framework was developed which is the basis for a future technical implementation project. Part one is described in the paper, while part two is still to be initiated and will deal with the implementation and testing phase of the introduction of personal electronic dosemeters as official dosemeters. (authors)

  2. History of personal dosimetry performance testing in the United States

    International Nuclear Information System (INIS)

    The basis for personal dosimetry performance testing in the United States is ANSI/HPS N13.11 (2001). Now in its third edition, this standard has been in place since 1983. Testing under this standard is administered by the National Voluntary Accreditation Program (NVLAP), and accreditation of dosimetry processors under this program is required by US Nuclear Regulatory Commission (NRC) regulations. The US Dept. of Energy (DOE) also maintains a testing program for its laboratories and contractors, administered by the Dept. of Energy Laboratory Accreditation Program (DOELAP). A focus in recent years has been the modification of ANSI/HPS N13.11 to allow acceptance by both testing programs in order to bring harmonisation to US personal dosemeter processing testing. Since there is no type testing program in the US for personal dosemeters, the testing philosophy of ANSI N13.11 has always combined elements of type testing and routine performance testing. This philosophy is explored in detail in this presentation, along with trends in the development of the document to its present state. In addition, a look will be taken at what the future holds for the next revision of the document, scheduled to begin in 2005. (authors)

  3. First national intercomparison of personal dosimetry for dosimetry service providers in paec

    International Nuclear Information System (INIS)

    Health Physics Division, PINSTECH, has conducted an intercomparison exercise for PAEC organizations which are responsible for providing personal dosimetry services for the assessment of occupational doses of radiation workers. The exercise was on voluntary basis and it was designed to harmonize the procedure of individual dose monitoring techniques in terms of new ICRP operational quantities of personal dose equivalent Hp (10) for photons. Cobalt-60 and Cesium-137 protection level sources were used for irradiation. The dosimeters were exposed to radiation in the range of 0.46 to 24.20 mSv. Irradiations were performed in Secondary Standard Dosimetry Laboratory (SSDL) at HPD, PINSTECH according to IAEA/WHO standards. The performance of the participating laboratories was judged by trumpet curve that provides the acceptable limits on overall accuracy for occupational dose monitoring at 95% confidence level according to international standards. The response of measured dose/standard true dose (Hm/Ht lies in the range of 0.66 to 1.11 for 60CO and 0.84 to 1.17 for 137CS. This report describes the procedure and results of the intercomparison exercise. (author)

  4. Introduction of a new dosimetry system based on optically stimulated luminescence (OSL) in our personal monitoring service

    Energy Technology Data Exchange (ETDEWEB)

    Hubner, S., E-mail: stephan.huebner@helmholtz-muenchen.de [Helmholtz Zentrum Munchen, German Research Center for Environmental Health, D-80219, Munich (Georgia)

    2014-08-15

    The personal monitoring service named Auswertungsstelle is part of the Helmholtz Zentrum Munchen, a non-profit-making research center in Germany. As one of the four monitoring services in Germany, we have been a reliable partner in radiation protection for more than 60 years. With about 1.9 million dose assessments per year, we are the largest monitoring service in Europe. For dozens of years, our main dosimeter used in whole-body dosimetry has been a film dosimeter. Although its dosimetric properties are still up to date, film dosimetry won.t be a sustainable technique for the use in monitoring services. Therefore, a project with the objective of investigating alternative dosimetric materials and methods was launched in the late 1990 at the Helmholtz Zentrum Munchen. Based on this research work, the use of Be O as an OSL dosimeter was studied by the radiation physics group of the Tu Dresden, by order and on account of the Auswertungsstelle at the Helmholtz Zentrum Munchen. It was shown, that ceramic Be O features promising dosimetric properties, making Be O detectors particularly suitable for being used in all applications in whole-body dosimetry measuring photons. Ceramic Be O material has an excellent resistance to environmental influences. The Be O chips are almost tissue equivalent. Therefore, these detectors show low photon energy dependence. A new personal dosimetry system based on the OSL dosimetry of Be O was developed. Applying this system, the Auswertungsstelle offers OSL-dosimeters for official monitoring of the Personal Dose Equivalent Hp(10) since 2011. This OSL-System is accredited according to DIN IEC 62387 and we obtained the corresponding type approval by the Ptb, the national metrology institute in Germany. Sophisticated logistics was developed and installed. High degree of automation was achieved by robots for dosimeter assembly and machines for packing, labelling and unpacking of the dosimeters. To become a sustainable dosimetry system not only

  5. Introduction of a new dosimetry system based on optically stimulated luminescence (OSL) in our personal monitoring service

    International Nuclear Information System (INIS)

    The personal monitoring service named Auswertungsstelle is part of the Helmholtz Zentrum Munchen, a non-profit-making research center in Germany. As one of the four monitoring services in Germany, we have been a reliable partner in radiation protection for more than 60 years. With about 1.9 million dose assessments per year, we are the largest monitoring service in Europe. For dozens of years, our main dosimeter used in whole-body dosimetry has been a film dosimeter. Although its dosimetric properties are still up to date, film dosimetry won.t be a sustainable technique for the use in monitoring services. Therefore, a project with the objective of investigating alternative dosimetric materials and methods was launched in the late 1990 at the Helmholtz Zentrum Munchen. Based on this research work, the use of Be O as an OSL dosimeter was studied by the radiation physics group of the Tu Dresden, by order and on account of the Auswertungsstelle at the Helmholtz Zentrum Munchen. It was shown, that ceramic Be O features promising dosimetric properties, making Be O detectors particularly suitable for being used in all applications in whole-body dosimetry measuring photons. Ceramic Be O material has an excellent resistance to environmental influences. The Be O chips are almost tissue equivalent. Therefore, these detectors show low photon energy dependence. A new personal dosimetry system based on the OSL dosimetry of Be O was developed. Applying this system, the Auswertungsstelle offers OSL-dosimeters for official monitoring of the Personal Dose Equivalent Hp(10) since 2011. This OSL-System is accredited according to DIN IEC 62387 and we obtained the corresponding type approval by the Ptb, the national metrology institute in Germany. Sophisticated logistics was developed and installed. High degree of automation was achieved by robots for dosimeter assembly and machines for packing, labelling and unpacking of the dosimeters. To become a sustainable dosimetry system not only

  6. An approved personal dosimetry service based on an electronic dosimeter

    International Nuclear Information System (INIS)

    At the Second Conference on Radiation Protection and Dosimetry a paper was presented which, in part, announced the development of an electronic dosimeter to be undertaken in the UK by the National Radiological Protection Board (NRPB) and Siemens Plessey Controls Ltd. This dosimeter was to be of a standard suitable for use as the basis of an approved personal dosimetry service for photon and beta radiations. The project has progressed extremely well and dosimeters and readers are about to become commercially available. The system and the specification of the dosimeter are presented. The NRPB is in the process of applying for approval by the Health and Safety Executive (HSE) to operate as personal monitoring service based on this dosimeter. As part of the approval procedure the dosimeter is being type tested and is also undergoing an HSE performance test and wearer trials. The tests and the wearer trials are described and a summary of the results to date presented. The way in which the service will be organized and operated is described and a comparison is made between the running of the service and others based on passive dosimeters at NRPB

  7. Luminescence dosimetry using building materials and personal objects

    International Nuclear Information System (INIS)

    There is a growing public awareness of the risk of accidental radiation exposure due to ageing nuclear power installations, illegal dumping of nuclear waste and terrorist activities, and of the consequential health risks to populations in addition to social and economic disturbance extending beyond national boundaries. In the event of catastrophic incidents where no direct radiation monitoring data are available, the application of retrospective dosimetry techniques such as luminescence may be employed with materials from the immediate environment to confirm values of cumulative gamma dose to compare with or augment computational modeling calculations. Application of the method to post-Chernobyl studies has resulted in the development of new procedures using fired building materials with the capability to measure cumulative doses owing to artificial sources of gamma radiation as low as 20 mGy. Combined with Monte Carlo simulations of photon transport, values of cumulative dose in brick can be presented in a form suitable for use in dose-reconstruction efforts. Recent investigations have also shown that certain types of cementitious building material, including concrete, mortar and plaster, and personal objects in the form of telephone cards containing microchips and dental ceramics have the potential to be used for retrospective dosimetry. Examples of the most recent research concerning new materials and examples of application to sites in the Former Soviet Union are discussed. (authors)

  8. An automated dosimetry system for testing whole-body ultraviolet phototherapy cabinets

    International Nuclear Information System (INIS)

    A new technique is described for automated ultraviolet dosimetry within whole-body phototherapy cabinets. A dual-head detector system has been designed, permitting simultaneous assessment of irradiance levels and radiant intensities from individual lamps. One detector is used in combination with a diffuser/filter system for the measurement of irradiance and the other is mounted at the end of a slit collimator to provide a measurement which can be related to the radiant intensities of the individual lamps. These quantities are derived from 800 separate measurements made during rotation of the detector head around a 360 deg. circle at a fixed height and position within the cabinet under remote computer software control. The device has advantages compared with standard techniques, enabling measurements to be made without the need for a person to be present in the cabinet. A full set of measurements is made with minimal switching of the power supply to the lamps. This simplifies the assessment and reduces the uncertainty from variation in output after the lamps are switched on. Variations in irradiance with orientation for the smaller phototherapy cabinets are clearly demonstrated. Plots of data from the collimated detector show peaks corresponding to the lamps and the surrounding reflectors. The plots enable failed lamps to be detected and peak values can be related to radiant intensities of individual lamps. (author)

  9. Comparative behaviour of different personal neutron dosimetry systems

    International Nuclear Information System (INIS)

    The results of measurements with different personal neutron dosimetry systems are presented. This study is part of a broad programme of neutron and gamma dose measurements carried out at four Swiss nuclear power plants. The measurements were made simultaneously with various active and passive systems. The results reported are those obtained by poly-allyl-diglycol-carbonate (PADC/CR-39), fission-track and bubble detectors. The irradiation positions covered a variety of neutron spectra, neutron-to-photon ratios, and dose equivalent rates. All the measurements were made with a water phantom. Different types/thicknesses of track detector materials were used. The agreement between the results of the dose equivalent rates obtained by the fission-track, bubble and CR-39 detectors was found to be within a statistical uncertainty of ∼ ± 30%. (author)

  10. Automated Spectral Manipulation and Data Analysis for EPR Dosimetry of Teeth

    International Nuclear Information System (INIS)

    A method for automating the spectral manipulation and data analysis procedures for EPR dosimetry of teeth is presented. The method is shown to correlate with conventional spectral peak-to-peak values to within 10 mGy for the reconstructed doses. Paired difference t-test data show that definitive systematic differences exist but that these effects on the reconstructed dose accuracy and precision are negligible for typical applications in tooth enamel EPR dosimetry. The algorithm is written in Hypercard script for Macintosh computers but could be implemented on other platforms (author)

  11. A new TLD for personal dosimetry in n-γ mixed field

    International Nuclear Information System (INIS)

    The new thermoluminescence dosimeter ZGHJ 2000 with seven regions is described. It is firm and durable and is suitable for personal dosimetry in n-γ mixed field, for simultaneous measurement of γ ray dose, thermal neutron dose and fast neutron dose. It's dosimetry character coincides with the requirements of technological standard

  12. Optimization of radiation protection in nuclear medicine: from reference dosimetry to personalized dosimetry

    International Nuclear Information System (INIS)

    In nuclear medicine, radiopharmaceuticals are distributed in the body through biokinetic processes. Thus, each organ can become a source of radiation delivering a fraction of emitted energy in tissues. Therefore, dose calculations must be assessed accurately and realistically to ensure the patient radiation protection. Absorbed doses were until now based on mathematical standard models and electron transport approximations. The International Commission on Radiological Protection (ICRP) has recently adopted voxel phantoms as a more realistic representation of the reference adult. The main goal of this thesis was to study the influence of the use of the new reference models and Monte Carlo methods on the major dosimetric quantities. In addition, the contribution of patients? specific geometry to the absorbed dose was compared to a standard geometry, enabling the evaluation of uncertainties arising from the reference values. Particular attention was paid to the bone marrow which is characterized by a high radiosensitivity and a complex microscopic structure. An accurate alpha dosimetry was assessed for bone marrow using microscopic images of several trabecular bone sites. The results showed variations in the absorbed fractions as a function of the particles? energy, the skeletal site and the amount of fat within marrow cavities, three parameters which are not taken into account in the values published by the ICRP. Finally, the heterogeneous activity distribution of the radiopharmaceuticals was considered within the framework of the treatment of a hepato-cellular carcinoma with selective internal radiotherapy using Yttrium-90 through the analysis of dose-volume histograms. The developments made in this thesis show the importance and the feasibility of performing a personalized dosimetry for nuclear medicine patients. (author)

  13. Dosimetry

    International Nuclear Information System (INIS)

    Eight articles treat the dosimetry. Two articles evaluate the radiation doses in specific cases, dosimetry of patients in radiodiagnosis, three articles are devoted to detectors (neutrons and x and gamma radiations) and a computer code to build up the dosimetry of an accident due to an external exposure. (N.C.)

  14. Thermoluminescence dosimetry of electronic components from personal objects

    International Nuclear Information System (INIS)

    Owing to the existence of ceramic materials inside common personal objects such as cellular phones and USB flash drives, these objects may be very useful in emergency (accident) dosimetry. Here we will present initial results regarding the dosimetric properties as determined by thermoluminescence (TL) from two alumina-rich electronic components from a USB flash drive. The TL method was applied in order to investigate the potential of conventional TL equipment for such purposes. For comparison, the optically stimulated luminescence (OSL) of the components was investigated as well. The studied components are ceramic resonators and alumina-based substrates from electrical resistors. The results show that various TL-related properties such as fading, optical stability and zero-dose response are different for the two investigated components. On the basis of these properties, the ceramic resonator was selected for dose recovery tests using TL and OSL. The given dose could reliably be determined using both methods, assuming that prompt measurement and/or fading correction is possible.

  15. Thermoluminescence dosimetry of electronic components from personal objects

    Energy Technology Data Exchange (ETDEWEB)

    Beerten, Koen [Radiation Protection Dosimetry and Calibration, Belgian Nuclear Research Centre, Boeretang 200, 2400 Mol (Belgium)], E-mail: kbeerten@sckcen.be; Woda, Clemens [Helmholtz Zentrum Muenchen - German Research Centre for Environmental Health, Institute of Radiation Protection, Ingolstaedter Landstrasse 1, D-85764 Neuherberg (Germany); Vanhavere, Filip [Radiation Protection Dosimetry and Calibration, Belgian Nuclear Research Centre, Boeretang 200, 2400 Mol (Belgium)

    2009-05-15

    Owing to the existence of ceramic materials inside common personal objects such as cellular phones and USB flash drives, these objects may be very useful in emergency (accident) dosimetry. Here we will present initial results regarding the dosimetric properties as determined by thermoluminescence (TL) from two alumina-rich electronic components from a USB flash drive. The TL method was applied in order to investigate the potential of conventional TL equipment for such purposes. For comparison, the optically stimulated luminescence (OSL) of the components was investigated as well. The studied components are ceramic resonators and alumina-based substrates from electrical resistors. The results show that various TL-related properties such as fading, optical stability and zero-dose response are different for the two investigated components. On the basis of these properties, the ceramic resonator was selected for dose recovery tests using TL and OSL. The given dose could reliably be determined using both methods, assuming that prompt measurement and/or fading correction is possible.

  16. State of the art in thermoluminescent dosimetry using dosemeters with automated read-out

    International Nuclear Information System (INIS)

    In the beginning, the results obtained with automated read-out TLD have been quite disappointing, both for manufacturers and users. In response to this, industry then seeked advice and assistance from those experienced in the practical use of dosemeters, and the development of the second generation of automated TLD has been a common task of manufacturers and purchosers. As a preliminary achievement of development work along this line, a dosemeter has been presented by a Japanese manufacturer, meeting the requirements in quite a satisfactory way. The device is characterized by a frequency of disturbance of -5, a microprocessor for controlling the measuring and control functions, possibility of active input of device parameters and boundary conditions, extensive self-control of operating functions, complete data protection, and thin-film detector technique. Pursuing this line of development, and taking into account future recommentations, automated thermoluminescent dosimetry does seem to be a promising alternative to current measuring techniques in personnel monitoring. (orig./RW)

  17. A new card holder for personal X and gamma dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Rossi, Francesco [S.O.D. Fisica Sanitaria, Azienda Ospedaliero - Universitaria Careggi, Firenze (Italy)], E-mail: rossif@aou-careggi.toscana.it; Arilli, Chiara [Dipartimento di Fisica, Universita degli Studi di Firenze, Firenze (Italy); Falivene, Annamaria; Gori, Cesare [S.O.D. Fisica Sanitaria, Azienda Ospedaliero - Universitaria Careggi, Firenze (Italy)

    2008-02-15

    The aim of this work is the description of the new card holder developed at the Dosimetry Service of the University Hospital in Firenze, specifically designed for medical occupational exposure measurements. The basic dosimeter (card), already in use at the Dosimetry Service, contains two LiF100 detectors, the second one being filtered to get energy response correction. The rationale for a new holder was both the agreement to the statements of the Italian law promoted after to the BSS Directive [Council Directive 96/29/EURATOM of 13 May 1996 laying down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionizing radiation.] and the practical need of dosimeter which is easy to handle. Therefore, robustness, ease of sliding in and pulling out the card, feasibility of applying a personal identification label, etc. were goals to achieve, as well as increasing the efficiency of the service. The work describes the response of the whole dosimeter (card and holder) to the incident radiation. The Italian National law, derived from BSS European Directive [Council Directive 96/29/EURATOM of 13 May 1996 laying down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionizing radiation.], states that individual dosimeters must measure H{sub p}(10) for the monitoring of occupationally exposed workers, so the main goal of our work was to reach optimum response in terms of H{sub p}(10). However, the dosimeter was also designed to allow the measurement of H{sub p}(3), for monitoring eye lens doses, and of H{sub p}(0.07), to measure weakly penetrating radiation fields. The test procedure was performed according to international ISO standard [ISO 4037-1, ISO 4037-2, ISO 4037-3, 1996. - X and gamma reference radiation for calibrating dosimeters and dose-rate meters and for determining their response as a function of photon energy.]. We also

  18. A new card holder for personal X and gamma dosimetry

    International Nuclear Information System (INIS)

    The aim of this work is the description of the new card holder developed at the Dosimetry Service of the University Hospital in Firenze, specifically designed for medical occupational exposure measurements. The basic dosimeter (card), already in use at the Dosimetry Service, contains two LiF100 detectors, the second one being filtered to get energy response correction. The rationale for a new holder was both the agreement to the statements of the Italian law promoted after to the BSS Directive [Council Directive 96/29/EURATOM of 13 May 1996 laying down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionizing radiation.] and the practical need of dosimeter which is easy to handle. Therefore, robustness, ease of sliding in and pulling out the card, feasibility of applying a personal identification label, etc. were goals to achieve, as well as increasing the efficiency of the service. The work describes the response of the whole dosimeter (card and holder) to the incident radiation. The Italian National law, derived from BSS European Directive [Council Directive 96/29/EURATOM of 13 May 1996 laying down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionizing radiation.], states that individual dosimeters must measure Hp(10) for the monitoring of occupationally exposed workers, so the main goal of our work was to reach optimum response in terms of Hp(10). However, the dosimeter was also designed to allow the measurement of Hp(3), for monitoring eye lens doses, and of Hp(0.07), to measure weakly penetrating radiation fields. The test procedure was performed according to international ISO standard [ISO 4037-1, ISO 4037-2, ISO 4037-3, 1996. - X and gamma reference radiation for calibrating dosimeters and dose-rate meters and for determining their response as a function of photon energy.]. We also tested the response in terms

  19. Personal dosimetry statistics and specifics of low dose evaluation

    International Nuclear Information System (INIS)

    The dose statistics of a personal dosimetry service, considering 35,000+ readings, display a sharp peak at low dose (below 0.5 mSv) with skewness to higher values. A measure of the dispersion is that approximately 65% of the doses fall below the average plus 2 standard deviations, an observation which may prove helpful to radiation protection agencies. Categorizing the doses by the concomitant use of a finger ring dosimeter, that skewness is larger in the whole body, and ring dosimeters. The use of Harshaw 5500 readers at high gain leads to frequent values of the glow curve that are judged to be spurious, i.e. values not belonging to the roughly normal noise over the curve. A statistical criterion is shown for identifying those anomalous values, and replacing them with the local behavior, as fit by a cubic polynomial. As a result, the doses above 0.05 mSv which are affected by more than 2% comprise over 10% of the data base. The low dose peak of the statistics, above, has focused our attention on the evaluation of LiF(Mg,Ti) dosimeters exposed at low dose, and read with Harshaw 5500 readers. The standard linear procedure, via an overall reader calibration factor, is observed to fail at low dose, in detailed calibrations from 0.02 mSv to 1 Sv. A significant improvement is achieved by a piecewise polynomials calibration curve. A cubic, at low dose is matched, at ∼10 mSv, in value and first derivative, to a linear dependence at higher doses. This improvement is particularly noticeable below 2 mSv, where over 60% of the evaluated dosimeters are found. (author)

  20. A thermoluminescence dosimetry system for personal monitoring in Ireland

    International Nuclear Information System (INIS)

    In 1993 the decision was taken to replace film badges with thermoluminescence dosemeters (TLDs) as the main form of dosemeter for both whole-body and extremity monitoring at the Dosimetry Service of the Radiological Protection Institute of Ireland (RPII) in Dublin. A review of commercially available TLD systems was carried out to identify the system which best met the RPII's requirements. This paper describes the dosimetry system used, and, in addition, discusses the problems encountered and how these were addressed. (author)

  1. Statistical analysis of personal dosimetry of exposed workers

    International Nuclear Information System (INIS)

    The dosimetry centers accredited by the Nuclear Safety Council (CSN) normally report overcoming legal limits, or some fraction thereof, but do not provide comparative dosimetric criteria indicating if assigned to a given dose is large TPE or small relative to that of their peers. In order to help to resolve the difficulties mentioned ds, it has developed an application that statistically processes the dosimetric data provided by the National Dosimetry Center. (Author)

  2. General guidance for laboratories providing personal dosimetry services

    International Nuclear Information System (INIS)

    This guidance is recommended to all dosimetry services in the interests of good radiation protection practice. For dosimetry services who seek approval under the Ionising Radiation Regulations 1985, the Health and Safety Executive (HSE) would invoke compliance with this guidance, in broad terms, as well as other published guidance. The recommendations include sections concerning laboratory organizations and staff, documentation of procedures, laboratory accommodation and services, equipment, calibration and traceability, housekeeping, dosimetric capability, laboratory records. (Author)

  3. Management of an automated dosimetry and dose record keeping service

    International Nuclear Information System (INIS)

    The National Radiological Protection Board has recently introduced a comprehensive service for monitoring the exposure of individuals to external radiation. It is based on a new type of thermoluminescent dose meter processed in an automated laboratory and linked to a dose record keeping system operated in a central computer. Workers are identified by their National Insurance Number and provision is made in the records for storing, if necessary, information on internally received doses. Identification by National Insurance Number enables the continuity of individual dose histories to be maintained automatically during changes of employment; this is an important feature that has demonstrated a major advantage of a centralized system of this kind. The new service is now expanding after a period of trial operation and the main attraction to employers is the relief afforded from dose record keeping and the decrease in the amount of manual transcriptions required. This paper gives an outline description of the constituent parts of the new service, followed by a description of the organization and management of it and some of the experience gained so far. (author)

  4. Implementation of an electronic personal dosimetry system (EPD) at Oldbury-on-Severn power station

    International Nuclear Information System (INIS)

    This article presents the implementation of an electronic personal dosemeter (EPD) as a film badge replacement at Oldbury-on-Severn power station, which is the first major site to use an approval issued by the UK Health and Safety Executive (HSE) for dose measurement by an EPD. The practicalities and history behind the introduction of an EPD for personal dosimetry are described. (author)

  5. BeOSL system for personal dosimetry : dosimetric characteristics and practical application; Sistema BeOSL para dosimetria personal : caracteristicas dosimetricas y la aplicacion practica

    Energy Technology Data Exchange (ETDEWEB)

    Mende, E. [Helmholtz Zentrum Munchen, German Research Center for Environmental Health, Working Group Engineering, D-85764 Neuherberg (Germany)

    2015-10-15

    Full text: BeOSL system of Dosimetric s is very easy to use, assimilate and maintain. Our dosimeter defines a milestone in the supervision of personal equivalent dose of Hp (10) and Hp (0.07) it covers the range of total energy of 16 KeV to 10 MeV. For this energy range is exceptional in its energy dependence for official personal dosimetry. The BeOSL system consists of two modules, one of them is the BeOSL reader that measures the radiation exposure using the latest technology, optically stimulated luminescence (OSL). The reading is extremely fast; it does not require consumables such as nitrogen or other. The detector material is beryllium oxide (Be O); this is an OSL material tissue equivalent and therefore is ideal for personal dosimetry. The BeOSL technology allows multiple readings of the dosimeter (re-read) to verify the dose or archive the dosimeter. One of the biggest advantages of BeOSL system is its modular concept allows the system to run as a manual solution or as a complete automated robotic system, which can be filled with up to 5,000 dosimeters as bulk cargo. (Author)

  6. Dosimetry

    International Nuclear Information System (INIS)

    The fundamental units of dosimetry are defined, such as exposure rate, absorbed dose and equivalent dose. A table is given of relative biological effectiveness values for the different types of radiation. The relation between the roentgen and rad units is calculated and the concepts of physical half-life, biological half-life and effective half-life are discussed. Referring to internal dosimetry, a mathematical treatment is given to β particle-and γ radiation dosimetry. The absorbed dose is calculated and a practical example is given of the calculation of the exposure and of the dose rate for a gama source

  7. The reliability of the systems of personal dosimetry

    International Nuclear Information System (INIS)

    The dosimeters of companies and institutions have been irradiated at various energy and dose equivalent levels. Systematic and coincident errors in measurement are presented. The results show that relatively large systematic errors can be made by both the thermoluminescent and film systems. Various techniques to judging the quality of the dosimetry are discussed. (G.B.)

  8. A microcomputer controlled thermoluminescence dosimetry system

    International Nuclear Information System (INIS)

    Using a microcomputer, an automatic thermoluminescence dosimetry system for personal dosimetry and thermoluminescence detector (TLD) research was developed. Process automation, statistical computation and dose calculation are provided by this microcomputer. Recording of measurement data, as well as dose record keeping for radiological workers is carried out with floppy disk. The microcomputer also provides a human/system interface by means of a video display and a printer. The main features of this dosimetry system are its low cost, high degree of flexibility, high degree of automation and the feasibility for use in routine dosimetry as well as in TLD research. The system is in use for personal dosimetry, environmental dosimetry and for TL-research work. Because of its modular set-up several components of the system are in use for other applications, too. The system seems suited for medium sized health physics groups. (author)

  9. Proposal of a Brazilian accreditation program for personal dosimetry using OSL

    International Nuclear Information System (INIS)

    After the development of the highly sensitive material Al2O3:C, personal dosimetry using optically stimulated luminescence (OSL) has been continuously adopted in place of thermoluminescence dosimeters (TLD) by different countries (e.g. USA and Japan). In order to use a dosimetric system in Brazil it is necessary to develop a protocol and to fulfill performance and type tests in accordance with the accreditation program approved by the responsible governmental committee. This paper presents a proposal for an accreditation program for OSL personal dosimetry using a commercial dosimetric system, including tests that follow the same rules as applied to TLD and film dosimetry. The experimental results are within the reliability interval and in accordance to the expected behavior. A new test concerning re-analysis of exposed badges is also proposed.

  10. Personal dosimetry TLD 100 in orthopedic surgeons exposed to ionizing radiation in Bogota - Colombia

    International Nuclear Information System (INIS)

    Orthopedic surgeons should be considered as professionals occupationally exposed to ionizing radiation, for using C arc (fluoroscope) an equipment of X type radiation emission, during surgical procedures for imaging generation. Some health institutes, use of C arc under uncontrolled circumstances, such a lack of dosimetry control, incomplete or absence of personnel protective elements and protective measures, which in turn, lead to a high exposition to the personnel. Materials and methods. Study of double match cohort by age and gender, was conducted, in four health institutions of second and third level of attention in Bogota city. Personal dosimetry measurements with TLD-100 dosimetry crystals in both cohorts and environmental dosimetry in each of operation rooms used for orthopedic procedures, were carry out during six months of follow up. Dosimetry crystals were read in a Harshaw 4500 - Bicron equipment, in the Medical Physics Laboratory of National University of Colombia. Results. Dosimetry measurements are compatibles with those of occupationally exposed personnel 3.44 mSv/6 m CI 95% (1.66-3.99), even does not overpass ICRP recommendations, are higher as were expect at the beginning of the study. The median of effective accumulative dose in thorax is 3,4 mSv CI 95% (1,66-3,99), higher in comparison with neck value 2,7 mSv CI 95% (1,73-3,80) and hand dosimetry 1,42 mSv CI 95% (0,96-2,34). Conclusions: Orthopedic surgeons should be considered occupational exposed to ionizing radiation, who has to accomplish to the radiological protection measures, dosimetric follow up and maintenance of the used X ray equipment. It was confirm throughout this study that dosimetry shows higher levels as expected at the beginning of the study, compatible with occupationally exposed personnel. (Author)

  11. An automated voxelized dosimetry tool for radionuclide therapy based on serial quantitative SPECT/CT imaging

    Energy Technology Data Exchange (ETDEWEB)

    Jackson, Price A.; Kron, Tomas [Department of Physical Sciences, Peter MacCallum Cancer Centre, East Melbourne 3002 (Australia); Beauregard, Jean-Mathieu [Department of Radiology, Université Laval, Quebec City G1V 0A6 (Canada); Hofman, Michael S.; Hogg, Annette; Hicks, Rodney J. [Department of Molecular Imaging, Peter MacCallum Cancer Centre, East Melbourne 3002 (Australia)

    2013-11-15

    Purpose: To create an accurate map of the distribution of radiation dose deposition in healthy and target tissues during radionuclide therapy.Methods: Serial quantitative SPECT/CT images were acquired at 4, 24, and 72 h for 28 {sup 177}Lu-octreotate peptide receptor radionuclide therapy (PRRT) administrations in 17 patients with advanced neuroendocrine tumors. Deformable image registration was combined with an in-house programming algorithm to interpolate pharmacokinetic uptake and clearance at a voxel level. The resultant cumulated activity image series are comprised of values representing the total number of decays within each voxel's volume. For PRRT, cumulated activity was translated to absorbed dose based on Monte Carlo-determined voxel S-values at a combination of long and short ranges. These dosimetric image sets were compared for mean radiation absorbed dose to at-risk organs using a conventional MIRD protocol (OLINDA 1.1).Results: Absorbed dose values to solid organs (liver, kidneys, and spleen) were within 10% using both techniques. Dose estimates to marrow were greater using the voxelized protocol, attributed to the software incorporating crossfire effect from nearby tumor volumes.Conclusions: The technique presented offers an efficient, automated tool for PRRT dosimetry based on serial post-therapy imaging. Following retrospective analysis, this method of high-resolution dosimetry may allow physicians to prescribe activity based on required dose to tumor volume or radiation limits to healthy tissue in individual patients.

  12. A method for automating calibration and records management for instrumentation and dosimetry

    International Nuclear Information System (INIS)

    Current industry requirements are becoming more stringent on quality assurance records and documentation for calibration of instruments and dosimetry. A novel method is presented here that will allow a progressive automation scheme to be used in pursuit of that goal. This concept is based on computer-controlled irradiators that can act as stand-alone devices or be interfaced to other components via a computer local area network. In this way, complete systems can be built with modules to create a records management system to meet the needs of small laboratories or large multi-building calibration groups. Different database engines or formats can be used simply by replacing a module. Modules for temperature and pressure monitoring or shipping and receiving can be added, as well as equipment modules for direct IEEE-488 interface to electrometers and other instrumentation

  13. Automated image analyzer for batch processing of CR-39 foils for fast neutron dosimetry

    International Nuclear Information System (INIS)

    An automated image analysis system has been developed for counting of tracks generated in CR-39 detectors after processing by Electro-chemical etching (ECE). The tracks are caused by exposure to fast neutron, and is used for measuring the neutron dose received by the radiation workers. The system is capable of batch processing a group of 20 foils in a single cycle, rendering the measurement process elegant and efficient. Thus, the system provides a marked improvement over the earlier one, which has provision of handling one foil at a time. The image analysis software of this system is empowered with the capability to resolve the overlapping tracks, which are commonly found in foils exposed to higher levels of neutron dose. The algorithm employed to resolve the tracks is an enhancement over that utilized in the earlier system. This results in improved accuracy of dosimetry. (author)

  14. A method for automating calibration and records management for instrumentation and dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    O`Brien, J.M. Jr.; Rushton, R.O.; Burns, R.E. Jr. [Atlan-Tech, Inc., Roswell, GA (United States)

    1993-12-31

    Current industry requirements are becoming more stringent on quality assurance records and documentation for calibration of instruments and dosimetry. A novel method is presented here that will allow a progressive automation scheme to be used in pursuit of that goal. This concept is based on computer-controlled irradiators that can act as stand-alone devices or be interfaced to other components via a computer local area network. In this way, complete systems can be built with modules to create a records management system to meet the needs of small laboratories or large multi-building calibration groups. Different database engines or formats can be used simply by replacing a module. Modules for temperature and pressure monitoring or shipping and receiving can be added, as well as equipment modules for direct IEEE-488 interface to electrometers and other instrumentation.

  15. Solid-state radiation detectors for active personal dosimetry and radiations source tracking

    International Nuclear Information System (INIS)

    We report on the design of the readout electronics using PIN diode radiation detector of 5 mm thickness for nuclear safety and active personal dosimetry. Our effort consisted in designing and fabricating the electronics to reflect the needs of gamma radiations dosimetry and hybrids PIN diode arrays for charged particle detectors. We report results obtained during testing and characterizing the new devices in gamma fields, operating at room temperature. There were determined the energy spectrum resolution, radiation hardness and readout rate. Also, data recording methods and parallel acquisition problems from a transducer matrix are presented. (authors)

  16. Recent trends in radioprotection dosimetry: Promising solutions for personal neutron dosimetry

    Science.gov (United States)

    Tommasino, L.

    1987-03-01

    Conventional detectors used in radiation protection dosimetry (for a given amount of energy deposited in their macroscopic volumes) are more sensitive to sparse radiations (electrons, X or gamma) than to fast neutrons or high-LET particles, i.e. those particles characterized by high biological effectiveness. By contrast, detectors needed in radiation protection monitoring should have a registration sensitivity which follows the opposite trend. With conventional detectors, in order to register the high-LET component in mixed fields, it is necessary to count individual energy-depositing tracks thus requiring elaborate electronics or complex automatic systems. In this paper new detecting methods will be described, which are very sensitive to fast neutrons and are completely insensitive to gamma radiations. These new detectors are based on the same properties of highly ionizing particles which determine their high biological effectiveness, namely the high deposition of energy at microscopic and submicroscopic distances from the particle trajectory in solid materials. Another important characteristic, common to these new detecting methods, is the exploitation of the high-energy deposition in the vicinity of the track to initiate avalanche-type of processes, which can be easily detected. These new registration techniques are respectively the electrochemically etched damage track detectors and the bubble damage polymer detectors. The simplicity, low cost and small size of these new detecting systems, together with their high sensitivity and their ability to discriminate against large fluxes of sparsely ionizing radiations make it possible to tackle some of the most difficult problems yet to be solved in radioprotection monitoring, such as personnel neutron dosimetry.

  17. Quality assurance in personal dosimetry of external radiation: present situation and future needs

    International Nuclear Information System (INIS)

    Whole body personal dosimetry is well established for the individual monitoring of radiation workers. High quality radiation dosimetry is essential for workers who rely upon personal dosemeters to record the amount of radiation to which they are exposed. The mandate has been given to the Personal Dosimetry, (secondary standard dosimetry laboratories) S.S.D.L., (Malaysian institute for nuclear energy research) M.I.N.T. to assure the individual monitoring for radiation workers in Malaysia. In 2005, the S.S.D.L;-M.I.N.T. supply, process and read out of personal dosemeters of nearly 13,000 dosimeters monthly, whereby. 12,000 are films and 1,000 are T.L.D.s. The objective of individual monitoring is not limited to the measurement of doses delivered to individuals, but it should demonstrate that limits of exposure have not been exceeded and that working conditions have not unexpectedly deteriorated. Dosimetry measurements are an important component of radiation protection programs and must be of high quality. The exposure of workers to radiation must be controlled and monitored in order to comply with regulatory requirements. S.S.D.L.-M.I.N.T; demonstrates that its performance is at an acceptable level by implementing overall system performance, as evidenced by the ISO 9001 certification of the Personal Dosimetry Service in 2002 and ISO/I.E.C. 17025 accreditation to the calibration laboratory in 2004. The certification and accreditation processes achieved the goal by formalizing the recognition of satisfactory performance, and providing evidence of this performance. Overall performances are assessed, personnel operating the system will be trained and are well qualified and all actions will be documented. The paper describes the overview of the Q.M.S. carried out at the S.S. D.L.-M.I.N.T.. During the implementation of Q.M.S. a few areas has been identified for future consideration. These include performance specification and type testing of dosemeters, which provide a

  18. Evaluation of effective dose equivalent for personal dosimetry

    International Nuclear Information System (INIS)

    The concept of effective dose equivalent was recommended as a primary limit in the ICRP publication 26. And dose equivalent index and ALI were introduced as the secondary limits for external and internal dose limitation system respectively. The evaluation method of effective dose equivalent and its application to a routinal dosimetry were studied as the followings, 1). For the external dose evaluation, the measuring method of 1 cm deep dose equivalent by a TL-dosemeter using Li2B4O7(Cu) element is shown. Also the relationship between 1 cm deep dose equivalent and effective dose equivalent is disscused. 2). For the internal dose evaluation, the monitering methods and the dose evaluation method are shown for the case of 239Pu or 137Cs intake. (author)

  19. The task of official personal monitoring in Germany using electronic dosimetry systems

    International Nuclear Information System (INIS)

    Full text: Since the establishment of the first German personal monitoring services as competent measuring bodies in the year 1952, official personal dosimetry is carried out using passive dosimeters such as film batches, RPL- and TL-dosimeters solely. On the other hand, electronic dosimeters are in use in some big institutions like Nuclear Power Plants, hospitals or industrial units for operational purposes. In most cases, these dosimeters are regulated by competent authorities. For more than 20 years electronic dosimeters proved their worth of being appropriate personal dosimeters. Since 2001 concepts to implement electronic personal dosimeters into the official individual monitoring of occupational exposed workers were developed in different research projects. The EU market of personal dosimetry changes to an open and competitive one, the number of outside workers, especially during the outages of Nuclear Power Plants increases, the landscape of customers is getting more and more heterogeneous. Being able to face these tasks of a sustainable personal monitoring requires the introduction of modern electronic dosimeters into to the official monitoring. Doing so, the needed prompt exchange of dose-data between different monitoring services as well as between the customers and the related monitoring service can be warranted. In cooperation with the industry, competent authorities and a research centre a method for official dosimetry using electronic dosimetry systems was developed, realised and tested successfully by the three big monitoring services of Germany. These investigations are supported by the German Federal Ministry for the Environment, Nature Conservation and Nuclear Safety. For this purpose a network between customers and monitoring services was built up in order to monitor people, who work in different places related to different measuring bodies in only one period of surveillance. (author)

  20. Gaining competitive advantage in personal dosimetry services through ISO 9001 certification

    International Nuclear Information System (INIS)

    Full text: In Malaysia, the harmonization of dose monitoring for almost 12,000 radiation workers is assigned to the Secondary Standard Dosimetry Laboratory of Malaysian Institute for Nuclear Technology Research, SSDL-MINT. Established in 1980, SSDL-MINT is responsible for improving personal and workplace safety by providing high quality personal dosimetry services. It is important to demonstrate that the performance of personal dosimetry meets recognized standards, to ensure radiation doses to individual workers are within the safe limits and to verify compliance with dose limits. Concern on the quality of personal dosimetry service began to be expressed in 2000. The concern led to the ISO certification, which brought an unprecedented effort characterized by high degree coordination, proper documentation and well trained of personal dosimetry operators. These huge efforts resulted with certification ISO 9002:1994 by the SIRIM International QAS Sdn. Bhd. in January 2002. The adoption of these requirements for the ISO 9002 standard makes routine handling of the process easier, and increases the reliability and effectiveness of the services. This helps to increase the quality and uniformity of personal dosimetry. The revision of the ISO 9002:1994 to ISO 9001:2000 necessitated SSDL-MINT revising its quality management system. The work began in middle 2002, and by May 2003, SSDL-MINT has been upgraded to ISO 9001:2000. Certification to the ISO 9001:2000 demonstrates our ability to consistency provide service that meets the requirements of the customer and the regulatory authority. These includes: improved consistency of service / product performance and therefore higher customer satisfaction levels; uniformity in work processes across organizations; simplified and more uniform structure for quality documents; improved customer perception of the organizations image, culture and performance; reduced number of product and process non-conformances; greater employee

  1. Present status of the PSI CR-39 neutron personal dosimetry system

    International Nuclear Information System (INIS)

    Full text: At the Paul Scherrer Institute a personal neutron dosimetry system based on chemically etched CR-39 detectors and automatic track counting is in routine use since the beginning of 1998. The quality of the CR-39 detectors has always been a crucial aspect to maintain a trustable personal neutron dosimetry system. This paper summarizes the 5-year experience regarding the background track density and its deviation and the effect of material defects which could lead to false positive neutron doses. The potentiality of improving the background statistics by extending the pre-etch time is investigated and involves as a drawback a quite lower sensitivity to thermal neutrons. Furthermore the impact of small changes in the production process of the detectors on the sensitivity to fast and thermal neutrons is shown. In 2004 a new dosimetry concept was launched by combining a CR-39 neutron dosemeter with a Direct-Ion Storage (DIS) dosemeter for photon and beta radiation. The exposition period of the CR-39 dosemeters is prolonged from now 3 months up to 12 months. In this context the dosimetry concept and the long-term behavior over one year of the background track density and the sensitivity of the CR-39 dosemeter is described. (author)

  2. Recent trends in radioprotection dosimetry: Promising solutions for personal neutron dosimetry

    International Nuclear Information System (INIS)

    In this paper new detecting methods will be described, which are very sensitive to fast neutrons and are completely insensitive to gamma radiations. These new detectors are based on the same properties of highly ionizing particles which determine their high biological effectiveness, namely the high deposition of energy at microscopic and submicroscopic distances from the particle trajectory in solid materials. Another important characteristic, common to these new detecting methods, is the exploitation of the high-energy deposition in the vicinity of the track to initiate avalanche-type of processes, which can be easily detected. These new registration techniques are respectively the electrochemically etched damage track detectors and the bubble damage polymer detectors. The simplicity, low cost and small size of these new detecting systems, together with their high sensitivity and their ability to discriminate against large fluxes of sparsely ionizing radiations make it possible to tackle some of the most difficult problems yet to be solved in radioprotection monitoring, such as personnel neutron dosimetry. (orig./HSI)

  3. Calibration of a tertiary standard in N-ISO qualities for radioprotection and personal dosimetry

    International Nuclear Information System (INIS)

    Dosimetric calibration of radiation monitors and personal dosimeters in different radiological quantities are performed in order to obtain accurate measurements, for this reason the SSDL calculates the dosimetry calibration factor and its associated uncertainty, for each range of use. The calibration factor is performed using the known radiation field method and its uncertainty is calculated according to the ISO recommendations. The SSDL calculates the expanded uncertainty (Uc) with a coverage factor that provides a level of not less than 95 % of confidence. (authors).

  4. Personal dosimetry and area monitoring for neutrons and radon in workplaces

    International Nuclear Information System (INIS)

    The first successful applications of damage track detectors in radiation protection have been made in the early 1970s in personal dosimetry of neutrons, radon and its progenies. Most of the scientists actively engaged in the solution of the complex problem of personal neutron dosimetry by damage track detectors-SSNTD, have attempted to develop individual radon monitoring for exposure in mines by using the same SSNTDs. In late 1970s and the early 1980s, new radon monitoring devices based on SSNTDs have been developed to measure radon in soil, mainly for applications in uranium prospecting or more generally in earth sciences. Most of the radon monitors, developed since then for completely different applications in mind, have been used later for large scale survey of indoor radon. With the current implementation within Europe of the European Union Directive 96/29, applications of damage track detectors will increase drastically, specially for the assessment of the exposure of the workers to natural sources of radiation. In this case, the early work on personal neutron/radon dosimetry, is highly valuable to tackle these new problems of individual monitoring

  5. Retrospective ESR dosimetry for persons chronically exposed to ionizing radiation

    International Nuclear Information System (INIS)

    Objective: To establish an electron spin resonance (ESR) method to estimate the dose of persons chronically exposed to ionizing radiation. Methods: ESR method was used to detect the ESR signal intensities of tooth enamel samples from two persons chronically exposed to ionizing radiation. The external calibration curve method and the additive dose method were used to reconstruct the irradiation doses of those teeth in order to find whether it is feasible to estimate the chronic dose by enamel ESR. And the effects of radiation energy on the ESR signal intensities were also observed. Results: The estimated doses of two teeth from each person were similar using two methods. Compared 1.25 MeV with 6 MeV X rays, the regression coefficients of the calibration curve were similar, and the doses estimated after combined irradiation were the same as the actually exposed doses. Conclusion: Reconstruction of dose for persons chronically exposed to radiation can be achieved using tooth enamel ESR measurement. The radiation energy, between 1.25 MeV and 6 MeV has little effect on tooth enamel ESR measurement

  6. Type tests to the automatic thermoluminescent dosimetry system acquired by the CPHR for personal dosimetry

    International Nuclear Information System (INIS)

    The CPHR individual monitoring service acquired an automatic RADOS TLD system to improve its capacities to satisfy the increasing needs of their national customers. The TLD system consists of: two automatic TLD reader, model DOSACUS, a TLD irradiator and personal dosimeters card including slide and holders. The dosimeters were composed by this personal dosimeters card and LiF:Mg,Cu,P (model GR-200) detectors. These readers provide to detectors a constant temperature readout cycle using hot nitrogen gas. In order to evaluate the performance characteristics of the system, different performance tests recommended by the IEC 1066 standard were carried out. Important dosimetric characteristics evaluated were batch homogeneity, reproducibility, detection threshold, energy dependence, residual signal and fading. The results of the tests showed good performance characteristics of the system. (Author)

  7. Evolution and current status of personal dosimetry in the Slovak NPPS

    International Nuclear Information System (INIS)

    In the archives of the Public Health Office, there are a lot of documents which demonstrate that since the beginning of design of the fir=st NPP in Slovakia, there has been considerable attention dedicated to personal dosimetry. But only few facts will be mentioned here. The external exposure was monitored by national (Czechoslovak) dosimetry service in Prague until 1977. NPPs have had their own services since then. Film detectors have been used for legal purposes since the beginning. The structure of the film detector allows measurements of beta and gamma radiation, assessment of main direction and energy of radiation, identification of surface contamination. Exposed films are kept in the archive. The operational dosimetry has been developed significantly, from simple pen detectors with ionisation chamber to electronic dosimeters. The internal contamination has been monitored by medical service (under Health Ministry) which was established in NPP Bohunice until 19,7. Since then the internal dosimetry services have been operated by the NPPs. The whole body counters and laboratories for analysis of biological samples have been available on both nuclear sites of Slovakia. The measurement system, the rules and the methodology were regularly improved. Quick body monitors and monitors for thyroid monitoring are available also on both sites at present. (authors)

  8. Personal dosimetry of staff involved with I-131 therapeutic procedures

    International Nuclear Information System (INIS)

    Full text: Introduction: Therapeutic doses of liquid 131l (370 MBq) and 131l MIBG (3700 MBq) are frequently used in the treatment of patients with hyperthyroidism and neuroblastoma respectively. 131l is volatile and can be inhaled and accumulate in the thyroid of personnel responsible for the dispensing and administration of doses. The aim of this study was to report and assess the radiation doses to personnel involved with liquid 131l therapeutic procedures. Materials and methods: 131l liquid dispensing and administration: The uptake of 131l in the thyroid of the physicists responsible for dispensing, and medical doctors for administration of therapeutic doses was determined with a whole body counter. 131l MIBG dispensing and administration: The radiation doses received by the subjects have been monitored using calibrated lithium fluoride thermo luminescent dosimetry (TLD) discs and a direct reading pocket dosimeter. The TLD discs have been issued and worn by the physicists and the dedicated nurses doing duty at the patient. The dedicated nurses and voluntarily comforters of the patients were also issued with pocket dosimeters to measure the whole body dose received. Results: 131l liquid dispensing and administration: The activities in the thyroid of the personnel handling the therapeutic doses of liquid 131l varied from 49Bq -1466Bq. The activity that was handled varied from 370 - 3182 MBq / week. The limit set by the ICRP for 131l uptake in the thyroid is 2 MBq. 131l MIBG dispensing and administration: The whole body radiation doses received by the caregivers of 131l MIBG therapy patients varied from 0,13-.12 mSv. The ICRP whole body limit to the public is 1 mSv per year. The physicists' whole body radiation doses varied from 0.20 - 1.18 mSv per treatment. Their hand doses varied from 0.67 - 8.85 mSv. The ICRP whole body limit for radiation workers is 20 mSv per year (- 0.4 mSv per week) while the dose to the skin (hands) should not exceed 5O0mSv per year (10m

  9. Statistical results of the personal dosimetry service at the GSF

    International Nuclear Information System (INIS)

    The first aim of the project is to indicate the trends in personal and collective doses on the available database and to correlate it to the state structure of the Federal Republic of Germany and professional groups. The second aim is to assess individual life time doses in view of the already implemented limits for the effective life time dose in the FRG. (R.P.) 2 figs

  10. Ambient dose measurement and personal dosimetry in nuclear medicine

    International Nuclear Information System (INIS)

    The dose measurements reported were performed with TLD dosemeters consisting of two glass tubes filled with CaSO4:TM powder. The measurements were done around a positron emission tomograph, in a nuclear medicine outpatient department, and in a hospital (therapy with unsealed radioactive substances). The personal doses measured during the campaign reported did not exceed the range of radiation doses and its fluctuations due to natural radiation exposure of the population. (DG)

  11. TLD characterization and its roles in the personal dosimetry service

    International Nuclear Information System (INIS)

    Precision of personal dose analysis using TLD card depends on the TLD characterization that needs to be carried out before the card is supplied to the users. Characterization includes determination of ECC (Element Correction Coefficient), RCF (Reader Calibration Factor), Reproducibility and Linearity test against exposure. All tests are carried out using 137 Cs sources at Bunker 2, SSDL. TLD cards which have performance within ±10% of delivered exposure (i.e. 100 mR) are then supplied to the users. (Author)

  12. Electronic neutron personal dosimetry with superheated drop detectors

    International Nuclear Information System (INIS)

    The prototype of an electronic personal neutron dosemeter based on superheated drop detectors is presented. This battery operated device comprises a neutron sensor, bubble-counting electronics and a temperature controller ensuring an optimal dose equivalent response. The neutron sensor is a 12 ml detector vial containing an emulsion of about 50,000 halocarbon-12 droplets of 100 μm diameter. The temperature controller is a low-power, solid-state device stabilising the emulsion at 31.5 deg. C by means of an etched foil heater. The microprocessor-controlled counting electronics relies on a double piezo-electric transducer configuration to record bubble formation acoustically via a comparative pulse-shape analysis of ambient noise and detector signals. The performance of the dosemeter was analysed in terms of the requirements presently developed for neutron personal dosemeters. The detection threshold is about 1 μSv, while the personal dose equivalent response to neutrons in the thermal to 62 MeV range falls within a factor 1.6 of 13 bubbles per μSv. (author)

  13. PeDaB - the personal dosimetry database at the research centre Juelich

    International Nuclear Information System (INIS)

    In May, 1997 the mainframe based registration, processing and archiving of personal monitoring data at the research centre Juelich (FZJ) was transferred to a client server system. A complex database application was developed. The client user interface is a Windows based Microsoft ACCESS application which is connected to an ORACLE database via ODBC and TCP/IP. The conversion covered all areas of personal dosimetry including internal and external exposition as well as administrative areas. A higher degree of flexibility, data security and integrity was achieved. (orig.)

  14. Evolution and current status of personal dosimetry in the Slovak NPPs

    International Nuclear Information System (INIS)

    In archive of the Public Health Office, there is a lot of documents which demonstrate that since the beginning of design of the first NPP in Slovakia, there has been considerable attention dedicated to personal dosimetry. But only few facts will be mentioned here. The external exposure was monitored by national (Czechoslovak) dosimetry service in Prague until 1977. NPPs have had their own services since then. Film detectors have been used for legal purposes since the beginning. The structure of the film detector allows measurements of beta and gamma radiation, assessment of main direction and energy of radiation, identification of surface contamination. Exposed films are kept in the archive. The operational dosimetry has been developed significantly, from simple pen detectors with ionization chamber to electronic dosimeters. The internal contamination has been monitored by medical service (under Health Ministry) which was established in NPP Bohunice until 1987. Since then the internal dosimetry services have been operated by the NPPs. The whole body counters and laboratories for analysis of biological samples have been available on both nuclear sites of Slovakia. The measurement system, the rules and the methodology were regularly improved. Quick body monitors and monitors for thyroid monitoring are available also on both sites at present. In conclusion a good system of personal monitoring is the basic condition for appropriate radiation protection of occupationally exposed workers. Current system of individual personal monitoring of occupationally exposed workers in Slovak NPPs seems to be adequate and compatible with good practice. The main weakness of the system seems to be the missing system of the radiation passports. But we can expect that this problem will be solved till the end of this year. (authors)

  15. First intercomparison exercise in the frame of the coordinated investigation program of the IAEA on regional intercomparison of personal dosimetry

    International Nuclear Information System (INIS)

    During the days 7 and 11 of October of 1996 took place in Buenos Aires, Argentina, the first Meeting of the Coordinated Investigation program of the IAEA on Regional Intercomparison of Personal Dosimetry for Latin American. In this meeting participated nine representatives of reference laboratories and of personal dosimetry of the region. Fundamental aspect of personal dosimetry relates with the quantity personal dose equivalent Hp application and the implementation of intercomparison exercise in order to improve the quality of the dose estimation have been discussed. Also lectures carried out by the specialist on Hp and practical aspects of it implementation; answer and calibration according to the ISO 4037; intercomparison methods: procedures and organizations. It was carried out the first intercomparison exercise where the participants collaborated in the preparations and irradiations of personal dosemeters they have brought. (author)

  16. Statistics of official personal dosimetry and monitoring activities of the period 1994-1995

    International Nuclear Information System (INIS)

    The measuring laboratory of the GSF in Neuherberg is the largest of the six official supervisory laboratories in Germany. It distributes the officially approved personal dosemeters and is responsible for personal dosimetry monitoring of about 140,000 persons in the German federal states of Bavaria, Hesse, Schleswig-Holstein, and, since 1989, Baden-Wuerttmeberg. Dosemeter readouts are recorded here in a database together with personal data and data describing activities, so that the information collected can be used as a source of reference for establishing general surveys of occupational exposure to external irradiation with ionizing radiation. The report first describes the dosemeter designs and the methods applied by the GSF lab for quality assurance, then explains results of the statistical evaluation of the recent data from 1994-1995, and concludes with explaining tendencies shown by long-term curves of the collective and average annual doses recorded in the years from 1986 until 1995. (orig./CB)

  17. Requirements for personal dosimetry in new Slovak legislation

    International Nuclear Information System (INIS)

    New Slovak legislation in an area of radiation protection is covering basics for surveillance and an evaluation of occupational doses, a general guidance for a workplace monitoring - law No. 355/2007 Coll., governmental decree No. 345/2006 Coll. adapting directive 96/29/EURATOM and ordinance No. 545/2007 Coll. For users is necessary more detailed regulation and guidance with objective to ensure unified procedures for monitoring and evaluation of measured occupational doses. The draft of reference levels for occupational monitoring will be presented as useful example for most of workplaces with sources of ionizing radiation. The new ordinance No. 545/2007 Coll. is adopting new requirements for using of two personal dosimeters mainly in interventional radiology and for using extremity dosimeters. (author)

  18. Current status of personal dosimetry in industry, research and medicine in Lithuania

    Energy Technology Data Exchange (ETDEWEB)

    Morkunas, G.; Griciene, B.; Jankauskiene, D

    2001-07-01

    The personal dosimetry service of the Radiation Protection Centre performs individual monitoring for all the industrial, medical and research radiation workers. The Rados and DTU TLD systems are used for monitoring of doses. The DTU TLD system is used for measurements of doses to extremities and for measurements of public external exposure. Finger ring TLDs are used in therapy which uses radiopharmaceuticals. The Rados system is also used for evaluation of patients' doses in selected hospitals. The dosimetry service recently provided individual monitoring of approximately 3000 workers. The average occupational dose was about 1.06 mSv for medical workers and 3.2 mSv for industrial radiography workers in 1999. Detailed analysis of doses received by different categories of workers is performed. A system for urgent review of work conditions in the case of increased dose has been set up. (author)

  19. Current status of personal dosimetry in industry, research and medicine in Lithuania

    International Nuclear Information System (INIS)

    The personal dosimetry service of the Radiation Protection Centre performs individual monitoring for all the industrial, medical and research radiation workers. The Rados and DTU TLD systems are used for monitoring of doses. The DTU TLD system is used for measurements of doses to extremities and for measurements of public external exposure. Finger ring TLDs are used in therapy which uses radiopharmaceuticals. The Rados system is also used for evaluation of patients' doses in selected hospitals. The dosimetry service recently provided individual monitoring of approximately 3000 workers. The average occupational dose was about 1.06 mSv for medical workers and 3.2 mSv for industrial radiography workers in 1999. Detailed analysis of doses received by different categories of workers is performed. A system for urgent review of work conditions in the case of increased dose has been set up. (author)

  20. PorTL - a compact, portable TLD reader for environmental and personal dosimetry

    International Nuclear Information System (INIS)

    Thermoluminescent dosimeters (TLDs) are commonly used for environmental monitoring, for personal and medical dosimetry, for dosimetry in nuclear facilities, etc. Major advantages are their independence of the power supply, small dimension, sensitivity, good stability, wide measuring range, resistance to environmental changes and relatively low cost. The disadvantage is that the detector must be transported for evaluation to a laboratory equipped with a large, heavy and expensive TLD Reader operated by qualified personnel, which considerably increases the costs and delays results. To overcome this disadvantage, the KFKI Atomic Energy Research Institute (KFKI AEKI), in co-operation with BL Electronics (Hungary), has developed a new and unique TLD system containing a small, portable, battery powered and moderate-price reader for commercial use. This paper gives a detailed description and parameters of this system.(author)

  1. Topics under debate - The use of computerised glow curve analysis will optimise personal thermoluminescence dosimetry measurements

    International Nuclear Information System (INIS)

    Personal dosimetry is normally a regulated activity whose results must comply with established accuracy requirements. Although these requirements may not be extremely stringent, it is important to note that there are many factors influencing accuracy and therefore influencing results. These include the energy and angular dependence of dose equivalent response, signal reproducibility, stability and fading, along with other influence factors that tend to complicate the correct measurement of the low doses usually encountered in the monitoring of radiation workers. The statistical uncertainty associated with the measurement of dose equivalent in the workplace is dependent upon the reproducibility of the many conditions, and in the case of the readings produced by thermoluminescence (TL) dosemeters the analysis of the rather complex TL signals can be a source of uncertainty. Glow curve analysis may offer a method for reducing uncertainties, but it must be considered whether such an analysis can be accomplished in the context of a large scale worker dosimetry programme. (author)

  2. Radon exposure at workplaces. A comparative analysis of local and personal dosimetry

    International Nuclear Information System (INIS)

    The monitored radiation workers (n = 24) at 19 working places are exposed partially to significant increased concentrations of radon gas as well as radon decay products. According part 3 chapter 2 StrlSchV the required procedure of assessment of the radon exposure in self-responsibility of the responsible persons was verified. The results show differences between the estimated values on the one hand on the basis of personnel dosemeters and on the other hand on the basis of short-term measurements. In four of nine cases the values estimated with short-term measuring devices were lower as compared with long-term personnel dosimetry. In three additional companies can be observed overestimations as well as underestimations, if personnel and short-term dosimetry are compared. In the verified water plants the radon exposures are significantly below the action level. (orig.)

  3. An automated neutron dosimetry system based on the chemical etch of CR-39

    International Nuclear Information System (INIS)

    The dosimetric characteristics of two types of personal neutron dosemeter have recently been extensively assessed. The effects of exposure to various extreme environments have also been studied. Both types of dosemeter utilise chemically etched elements which are read in an automated reader, the Autoscan 60, which uses an edge illumination system to increase the pit image size. One type of dosemeter contains three elements in a pyramid structure. The other uses one or two elements in a planar structure. The results indicate that both types of dosemeter can be used to assess accurately the personal dose from neutrons in a range of harsh environments. Formal approval for the operational use of the system has been received. (author)

  4. Emergency dosimetry using ceramic components in personal electronic devices

    International Nuclear Information System (INIS)

    The rapid assessment of radiation dose to members of the public exposed to significant levels of ionizing radiation during a radiological incident presents a significant difficulty in the absence of planned radiation monitoring. However, within most personal electronic devices components such as resistors with alumina substrates can be found that have potentially suitable properties as solid state dosimeters using luminescence measurement techniques. The suitability of several types of ceramic-based components (e.g., resonators, inductors and resistors) has been previously examined using optically stimulated luminescence (OSL) and thermoluminescence (TL) techniques to establish their basic characteristics for the retrospective determination of absorbed dose. In this paper, we present results obtained with aluminum oxide surface mount resistors extracted from mobile phones that further extend this work. Very encouraging results have been obtained related to the measurement of luminescence sensitivity, dose response, reusability, limit of detection, signal reproducibility and known-dose recovery. However, the alumina exhibits a rapid loss of the latent luminescence signal with time following irradiation attributed to athermal (or anomalous) fading. The issues related to obtaining a reliable correction protocol for this loss and the detailed examinations required of the fading behavior are discussed. (author)

  5. Emergency Dosimetry Using Ceramic Components in Personal Electronic Devices

    Science.gov (United States)

    Kouroukla, E. C.; Bailiff, I. K.; Terry, I.

    2014-02-01

    The rapid assessment of radiation dose to members of the public exposed to significant levels of ionizing radiation during a radiological incident presents a significant difficulty in the absence of planned radiation monitoring. However, within most personal electronic devices components such as resistors with alumina substrates can be found that have potentially suitable properties as solid state dosimeters using luminescence measurement techniques. The suitability of several types of ceramic-based components (e.g., resonators, inductors and resistors) has been previously examined using optically stimulated luminescence (OSL) and thermoluminescence (TL) techniques to establish their basic characteristics for the retrospective determination of absorbed dose. In this paper, we present results obtained with aluminum oxide surface mount resistors extracted from mobile phones that further extend this work. Very encouraging results have been obtained related to the measurement of luminescence sensitivity, dose response, reusability, limit of detection, signal reproducibility and known-dose recovery. However, the alumina exhibits a rapid loss of the latent luminescence signal with time following irradiation attributed to athermal (or anomalous) fading. The issues related to obtaining a reliable correction protocol for this loss and the detailed examinations required of the fading behavior are discussed.

  6. Cosmic radiation protection dosimetry using an electronic personal dosemeter (Siemens EPD) on selected international flights

    International Nuclear Information System (INIS)

    The effectiveness of an Electronic Personal Dosemeter (Siemens EPD) for cosmic-radiation dosimetry at aviation altitudes was examined on eight international flights between March and September, 1998. The EPD values (Hepd) of the dose equivalent from penetrating radiation, Hp(10), were assumed to be almost the same as the electron absorbed doses during those flights. Based on the compositions of cosmic radiation in the atmosphere and the 1977 ICRP recommendation, an empirical equation to conservatively estimate the personal dose equivalent (Hp77) at a depth of 5 cm was derived as Hp77=3.1 x Hepd. The personal dose equivalent (Hp90) based on the 1990 ICRP recommendation was given by Hp90=4.6 x Hepd; the conservative feature of Hp90 was confirmed in a comparison with the calculated effective doses by means of the CARI-6 code. It is thus expected that the EPD will be effectively used for radiation protection dosimetry on selected international flights. (author)

  7. Yttrium-90 hepatic radioembolization: clinical review and current techniques in interventional radiology and personalized dosimetry.

    Science.gov (United States)

    Tong, Aaron K T; Kao, Yung Hsiang; Too, Chow Wei; Chin, Kenneth F W; Ng, David C E; Chow, Pierce K H

    2016-06-01

    In recent years, yttrium-90 ((90)Y) microsphere radioembolization has been establishing itself as a safe and efficacious treatment for both primary and metastatic liver cancers. This extends to both first-line therapies as well as in the salvage setting. In addition, radioembolization appears efficacious for patients with portal vein thrombosis, which is currently a contraindication for surgery, transplantation and transarterial chemoembolization. This article reviews the efficacy and expanding use of (90)Y microsphere radioembolization with an added emphasis on recent advances in personalized dosimetry and interventional radiology techniques. Directions for future research into combination therapies with radioembolization and expansion into sites other than the liver are also explored. PMID:26943239

  8. Pilot study on the application of computerised glow curve analysis in TL based personal dosimetry services

    International Nuclear Information System (INIS)

    Preliminary results of an inter-laboratory collaborative work on the application of computerised glow curve analysis to TL personal dosimetry are presented. Very simple analysis methods have proved to be useful for the evaluation of glow curves similar to those encountered in the dosimetric control of radiation workers. A first result obtained in the study has been the possibility of simplifying the TL working procedures by eliminating pre-annealing or pre-heating steps employed in conventional systems to avoid low temperature peaks. The presence of these unwanted peaks can be detected by the computerised evaluation methods, discriminating their contribution to the dosimetric TL data. (author)

  9. Accreditation of the Personal Dosimetry internal Service Tecnatom by the National Entity (ENAC)

    International Nuclear Information System (INIS)

    The service of personal Dosimetry internal Tecnatom has made the process of adapting its methodology and quality assurance, requirements technical and management will be required to obtain accreditation from the National Accreditation Entity according to ISO / IEC 170251 standard General Requirements competence of testing and calibration laboratories. To carry out this process, the laboratory has defined quality criteria set out in their test procedures, based on ISO Standards 27048: 2011; ISO 20553: 2005 and ISO 28218: 2010. This paper describes what has been the methodology used to implement the requirements of different ISO test methods of SDPI Tecnatom. (Author)

  10. Teledosimetry: Personal and Area Dosimetry Control in order to evaluate the risk in real time

    Energy Technology Data Exchange (ETDEWEB)

    Galan Montenegro, P.; Macias Jaen, J.; Bodineau Gil, C.; Sanchez Hidalgo, M.

    2004-07-01

    Telemedicine is now an essential part of Health care and so, in addition to the scientific programme in the Carlos Haya Hospital in Malaga, Physics Department is involved into a process of change about the vision as a new Health Centre of XXI Century: Knowledge Hospital, by digital architecture and digitally integrated in its world. The Integrating the Health care Enterprise is the model used in order to get a big grade of relationship between medical images and information system. This change must be done in colaboration between some Departments of our centre, because it is a multidisciplinary task. It is understood that Teledosimetry can be considered as an important part of Telemedicine in the Radiological Protection field for workers and general public. In order to get this objective, the first step since 2000 it has been to prepare the internal hospital network with personal dosimetry information. From here workers in our hospital can obtain their dosimetry information data in more than 300 computers and since 2003, from home too. For access, each one of all have got an user identification and a password and so it can be guaranteed the privacy. We transform dose data reported by CND (Dosimetry National Center) in a big and visible database in PHP4 and Javascript format. This process is marked of problems about all due to the big manipulated information. Our intention is to make a better and friendly control, customisable and in real-time of the information dosimetry by a modular monitoring system of electronic dosimeters by the web. These radiation detectors would be located in representatives places. (Author)

  11. Teledosimetry: Personal and Area Dosimetry Control in order to evaluate the risk in real time

    International Nuclear Information System (INIS)

    Telemedicine is now an essential part of Health care and so, in addition to the scientific programme in the Carlos Haya Hospital in Malaga, Physics Department is involved into a process of change about the vision as a new Health Centre of XXI Century: Knowledge Hospital, by digital architecture and digitally integrated in its world. The Integrating the Health care Enterprise is the model used in order to get a big grade of relationship between medical images and information system. This change must be done in colaboration between some Departments of our centre, because it is a multidisciplinary task. It is understood that Teledosimetry can be considered as an important part of Telemedicine in the Radiological Protection field for workers and general public. In order to get this objective, the first step since 2000 it has been to prepare the internal hospital network with personal dosimetry information. From here workers in our hospital can obtain their dosimetry information data in more than 300 computers and since 2003, from home too. For access, each one of all have got an user identification and a password and so it can be guaranteed the privacy. We transform dose data reported by CND (Dosimetry National Center) in a big and visible database in PHP4 and Javascript format. This process is marked of problems about all due to the big manipulated information. Our intention is to make a better and friendly control, customisable and in real-time of the information dosimetry by a modular monitoring system of electronic dosimeters by the web. These radiation detectors would be located in representatives places. (Author)

  12. Uncertainties in personal dosimetry for external radiation: A Monte Carlo approach

    International Nuclear Information System (INIS)

    This paper explores the possibilities of numerical methods for uncertainty analysis of personal dosimetry systems. Using a numerical method based on Monte Carlo sampling the probability density function (PDF) of the dose measured using a personal dosemeter can be calculated using type-test measurements. From this PDF the combined standard uncertainty in the measurements with the dosemeter and the confidence interval can be calculated. The method calculates the output PDF directly from the PDFs of the inputs of the system such as the spectral distribution of the radiation and distributions of detector parameters like sensitivity and zero signal. The method can be used not only in its own right but also for validating other methods because it is not limited by restrictions that apply to using the Law of Propagation of Uncertainty and the Central Limit Theorem. The use of the method is demonstrated using the type-test data of the NRG-TLD. (authors)

  13. Results of the ninth exercise of intercomparison in services of personal dosimetry in Argentina Republic in the year of 2011

    International Nuclear Information System (INIS)

    In this paper we present the results of the ninth intercomparison exercise personal dosimetry services, conducted by the Nuclear Regulatory Authority in 2011. The exercise was designed to evaluate the performance of laboratories providing personal dosimetry services in Argentina , for X-rays and gamma radiation fields . This exercise was organized by the Nuclear Regulatory Authority with the Ministry of Health of the Nation and the Regional Reference Laboratory Centre for Dosimetry of the National Atomic Energy Commission . The irradiations were carried out in full accordance with ISO 4037-3 . Participates all private companies in Argentina serving all personal dosimetry laboratories and agencies, provincial and national. Furthermore, the Laboratories from Cuba, Brazil and Uruguay also participate. The performance of a laboratory is considered acceptable if it meets the criteria established in the IRAM- ISO 14146 , which states: 'It is recognized that at most, one-tenth of dosimeters irradiated to exceed the limits'. Of all of the laboratories that participated , 68% reported their results within the acceptance criteria above. The primary objective of this intercomparison exercise is to provide an objective tool to evaluate the ability of personnel dosimetry services. (author)

  14. Study of the improvement of TLD cards for personal neutron dosimetry

    Science.gov (United States)

    Rabie, N.; Hassan, G. M.; El-Sersy, A. R.; Ezzat, M.

    In this work, personal thermoluminescence dosimeter (TLD) cards type of GN-6770 (holder type 8806) from Harshaw were used for personal neutron dosimetry. The response of the dosimeters has been determined in terms of the personal absorbed dose and personal dose equivalent for different neutron energy components, based on the recommendations of ICRP-60 and ICRU-49. Neutron irradiation was performed using a 5 mCi Am-Be neutron source. The TLD reader, type Harshaw 6600, was installed and calibrated for accurate neutron doses equivalent to gamma-ray doses. It was found that fast neutron doses measured by TLD (badges or cards) are in agreement with those measured by neutron TE (tissue equivalent gas) ionization chambers and neutron monitors. Thermal neutron doses measured by TLD cards were overestimated when compared with those measured by neutron monitors. Additional Cd was used to reduce thermal neutron doses to be in agreement with actual thermal doses. Other configurations for TLD crystals are also suggested for accurate thermal neutron dose measurements.

  15. Pediatric personalized CT-dosimetry Monte Carlo simulations, using computational phantoms

    Science.gov (United States)

    Papadimitroulas, P.; Kagadis, G. C.; Ploussi, A.; Kordolaimi, S.; Papamichail, D.; Karavasilis, E.; Syrgiamiotis, V.; Loudos, G.

    2015-09-01

    The last 40 years Monte Carlo (MC) simulations serve as a “gold standard” tool for a wide range of applications in the field of medical physics and tend to be essential in daily clinical practice. Regarding diagnostic imaging applications, such as computed tomography (CT), the assessment of deposited energy is of high interest, so as to better analyze the risks and the benefits of the procedure. The last few years a big effort is done towards personalized dosimetry, especially in pediatric applications. In the present study the GATE toolkit was used and computational pediatric phantoms have been modeled for the assessment of CT examinations dosimetry. The pediatric models used come from the XCAT and IT'IS series. The X-ray spectrum of a Brightspeed CT scanner was simulated and validated with experimental data. Specifically, a DCT-10 ionization chamber was irradiated twice using 120 kVp with 100 mAs and 200 mAs, for 1 sec in 1 central axial slice (thickness = 10mm). The absorbed dose was measured in air resulting in differences lower than 4% between the experimental and simulated data. The simulations were acquired using ∼1010 number of primaries in order to achieve low statistical uncertainties. Dose maps were also saved for quantification of the absorbed dose in several children critical organs during CT acquisition.

  16. Environmental dosimetry with the BeOSL personal dosimeter – State of the Art

    International Nuclear Information System (INIS)

    In the course of this work, the possibility of the measurement of ambient dose equivalent H*(10) with the BeOSL dosimetry system was evaluated. Calculations for the energy response of the 2-element BeOSL dosimeter for irradiation with H*(10) were performed. The response doesn't fulfil the requirements of IEC 62387-1. Especially the response for photon energies of 60–100 keV is to low. It is possible to correct this under response using a modified BeOSL 2-element dosimeter and a linear algorithm. So the national requirements for a H*(10) dosimeter in Germany can be fulfilled. An incidence angle independent measurement is not possible because for several angles of incidences (>60°) the filters of the 2-element dosimeter doesn't shield the correct element. Another material which is more suitable for the H*(10) measurement was tested. So the doping of BeO with Lanthanum leads to an enhanced energy response for measurement of H*(10). Furthermore a higher OSL sensitivity was found for this material. Further tests on the influence of Lanthanum concentration on the dosimetric properties are necessary. - Highlights: • Dosimetry using OSL of BeO. • Environmental dosimeter with modified personal dosimeter and linear algorithm. • Use of doped BeO chips for better energy response

  17. Personal dosimetry TLD 100 in orthopedic surgeons exposed to ionizing radiation in Bogota - Colombia; Dosimetria personal TLD 110 en medicos ortopedistas expuestos a radiacion ionizante en Bogota - Colombia

    Energy Technology Data Exchange (ETDEWEB)

    Sierra C, B. Y.; Jimenez, Y. [Universidad Nacional de Colombia, Departamento de Fisica, Grupo de Fisica Medica, Carrera 45 No. 26-85, Bogota (Colombia); Plazas, M. C. [Hospital Universitario Fundacion Santa Fe de Bogota, Instituto de Oncologia Carlos Ardila Lulle, Calle 119, No. 7-90, 220246 Bogota (Colombia); Eslava S, J. [Universidad Nacional de Colombia, Instituto de Investigaciones Clinicas, Grupo Equidad en Salud, Carrera 45 No. 26-85, Bogota (Colombia); Groot R, H., E-mail: brigith.sierra@gmail.com [Universidad de los Andes, Laboratorio de Genetica Humana, Carrera 1 No. 18A -12, Bogota (Colombia)

    2014-08-15

    Orthopedic surgeons should be considered as professionals occupationally exposed to ionizing radiation, for using C arc (fluoroscope) an equipment of X type radiation emission, during surgical procedures for imaging generation. Some health institutes, use of C arc under uncontrolled circumstances, such a lack of dosimetry control, incomplete or absence of personnel protective elements and protective measures, which in turn, lead to a high exposition to the personnel. Materials and methods. Study of double match cohort by age and gender, was conducted, in four health institutions of second and third level of attention in Bogota city. Personal dosimetry measurements with TLD-100 dosimetry crystals in both cohorts and environmental dosimetry in each of operation rooms used for orthopedic procedures, were carry out during six months of follow up. Dosimetry crystals were read in a Harshaw 4500 - Bicron equipment, in the Medical Physics Laboratory of National University of Colombia. Results. Dosimetry measurements are compatibles with those of occupationally exposed personnel 3.44 mSv/6 m CI 95% (1.66-3.99), even does not overpass ICRP recommendations, are higher as were expect at the beginning of the study. The median of effective accumulative dose in thorax is 3,4 mSv CI 95% (1,66-3,99), higher in comparison with neck value 2,7 mSv CI 95% (1,73-3,80) and hand dosimetry 1,42 mSv CI 95% (0,96-2,34). Conclusions: Orthopedic surgeons should be considered occupational exposed to ionizing radiation, who has to accomplish to the radiological protection measures, dosimetric follow up and maintenance of the used X ray equipment. It was confirm throughout this study that dosimetry shows higher levels as expected at the beginning of the study, compatible with occupationally exposed personnel. (Author)

  18. Cosmic-radiation dosimetry using electronic personal dosemeter (EPD) at commercial aircraft altitude

    International Nuclear Information System (INIS)

    Electronic Personal Dosemeter (EPD) was examined for effectiveness in cosmic radiation dosimetry at aircraft altitude through the measurements in a Japan-US round trip. The EPD value (Hepd) of individual dose equivalent, penetrating, Hp(10), was considered to be almost equal the deep absorbed dose attributed to electrons at the aircraft altitude. By assuming the fractions and the effective quality factors for other components (muons, protons, and neutrons) based on model-calculation data, an empirical equation to estimate a conservative deep dose-equivalent at 5 cm-tissue depth, H(50), was given as H(50)=3.1 x Hepd. Estimated H(50) values in the international flights were 4.9 μSv h-1 from Tokyo to New York and 3.6 μSv h-1 from Los Angeles to Tokyo. These values agreed well with the predicted values presented by NCRP. (author)

  19. Dosimetry Service

    CERN Multimedia

    2005-01-01

    Please remember to read your dosimeter at least once a month. Regular read-outs are vital to ensure that your personal dose is periodically monitored. Dosimeters should be read even if you have not visited the controlled areas. Dosimetry Service - Tel. 72155 http://cern.ch/rp-dosimetry

  20. Dosimetry Service

    CERN Multimedia

    Dosimetry Service

    2005-01-01

    Please remember to read your dosimeter at least once a month. Regular read-outs are vital to ensure that your personal dose is periodically monitored. Dosimeters should be read even if you have not visited the controlled areas. Dosimetry Service Tel. 7 2155 http://cern.ch/rp-dosimetry

  1. Dosimetry Service

    CERN Multimedia

    2005-01-01

    Please remember to read your dosimeter at least once a month. Regular read-outs are vital to ensure that your personal dose is periodically monitored. Dosimeters should be read even if you have not visited the controlled areas. Dosimetry Service - Tel. 7 2155 http://cern.ch/rp-dosimetry

  2. Present and future aspects of harmonization in official and operational personal dosimetry

    International Nuclear Information System (INIS)

    New international standards in the field of personal dosimetry were set up in the recent years. Resulting requirements appointed in the national Radiation Protection Ordinance actuated the discussion about necessary developments and the future structure of the radiation protection surveillance. The latest evolution of Electronic Personal Dosimeters (EPD) reaches a raised technical level fulfilling the new EC recommendations and the requirements for practical radiation protection in case of external exposure to ionising radiation. The Physikalisch-Technische Bundesanstalt (PTB) in Braunschweig, Germany assigned the first type-approvals according to the new requirements for modern EPDs. In some European countries EPDs can already be. applied as official dosimeter under certain conditions. After characterising the present structure of radiation protection surveillance in Germany, proposals for the future developments in official Personal Dose Monitoring System will be discussed in this paper., taking into account the different demands, interests and aims of all the different parties hereto, namely the operators of the installations with their workers kept under surveillance, the government and competent authorities, the manufacturers of modern dosimetric systems and last but not least the official monitoring centres. (authors)

  3. Optimization of radiation protection in nuclear medicine: from reference dosimetry to personalized dosimetry; Optimisation de la radioprotection en medecine nucleaire: de la dosimetrie de reference a la dosimetrie personnalisee

    Energy Technology Data Exchange (ETDEWEB)

    Hadid, Lama

    2011-09-09

    In nuclear medicine, radiopharmaceuticals are distributed in the body through biokinetic processes. Thus, each organ can become a source of radiation delivering a fraction of emitted energy in tissues. Therefore, dose calculations must be assessed accurately and realistically to ensure the patient radiation protection. Absorbed doses were until now based on mathematical standard models and electron transport approximations. The International Commission on Radiological Protection (ICRP) has recently adopted voxel phantoms as a more realistic representation of the reference adult. The main goal of this thesis was to study the influence of the use of the new reference models and Monte Carlo methods on the major dosimetric quantities. In addition, the contribution of patients? specific geometry to the absorbed dose was compared to a standard geometry, enabling the evaluation of uncertainties arising from the reference values. Particular attention was paid to the bone marrow which is characterized by a high radiosensitivity and a complex microscopic structure. An accurate alpha dosimetry was assessed for bone marrow using microscopic images of several trabecular bone sites. The results showed variations in the absorbed fractions as a function of the particles? energy, the skeletal site and the amount of fat within marrow cavities, three parameters which are not taken into account in the values published by the ICRP. Finally, the heterogeneous activity distribution of the radiopharmaceuticals was considered within the framework of the treatment of a hepato-cellular carcinoma with selective internal radiotherapy using Yttrium-90 through the analysis of dose-volume histograms. The developments made in this thesis show the importance and the feasibility of performing a personalized dosimetry for nuclear medicine patients. (author)

  4. A study on the development of personal radiation dosimetry system based on the pulsed optically stimulated luminescence of α-Al2O3:C

    International Nuclear Information System (INIS)

    High quality radiation dosimetry is for workers who rely upon personal dosimeters to record the amount of radiation to which they are exposed. Radiation physicists have been exploring thermoluminescence dosimeter (TLD) for personal monitoring since the mid 1960s, although, widespread use has only occurred in the last 20 years as automated analytical systems and high quality TLD crystals became commercially available. nowadays, multiple TLD (thermoluminescence dosimeter) chips with appropriate physical filters are generally used for measurements of the personal dose equivalent quantities, Hp(d). Though the TLD offers several advantages not possessed by radiological film, it does not offer the some type of advantages as films: re-analysis of an exposure situation is prohibited because the analysis process clears all of the useful dosimetric traps and a record of the luminescence intensity in the form of a glow curve is all that is available after analysis. In addition, the high heating temperatures restrict packaging methods and prevent competitively priced thin films of TLD crystal powders. Optically stimulated luminescence (OSL) technology avoids many engineering limitations imposed by the high heating temperatures used for TLD technology. OSL crystalline powders can be dispersed in various plastics unable to withstand the TLD heating regimen. With uniform dispersion in the plastic, mass-manufacturing techniques can produce large quantities of identically performing detectors. The first proposal conducted by Markey et al. for applications and potentials of α-AI2O3:C for OSL dosimetry opened a new era for this phosphor. Pulsed and continuous wave OSL studies carried out on α-AI2O3:C have shown that the material seems to be the most promising for routine application of OSL for dosimetric purposes. The main objective of this study is to develop a multi-area personal OSL dosimetry system using α-AI2O3:C by taking advantage of its optical properties and energy

  5. Current challenges in personal dosimetry at the US DOE Hanford site

    International Nuclear Information System (INIS)

    An overview is presented of the dosimetry system, dose equivalent calculation methodology, and QA/QC practices used at the US Department of Energy Hanford site. It describes some of the problems encountered in accurately measuring dose equivalent quantities under a broad range of field conditions that do not necessarily correlate with laboratory calibration conditions and the approach taken to solve these problems. Personnel at Hanford are monitored with a combination of Harshaw model 8825 and 8816 thermoluminescent dosemeters and CR-39 track etch dosemeters. Extremities are monitored using the ICN MeasuRing loaded with a Harshaw XD740 chipstrate TLD. All dosemeters employ LiF:Mg,Ti elements that are read on-site with Harshaw model 8800 and 6600 TLD readers. CR-39 dosemeters are electrochemically etched in non-commercial etch chambers and counted with an automated track counting system developed by Pacific Northwest National Laboratory. Problems with over-response of the 8825 with respect to Hp(0.07), under-response of the 8825 with respect to Hp(3), and over response of the 8825 with respect to Hp(10) in Hanford's 90Sr/90Y beta radiation fields are discussed. Approaches to measurement of the operational quantities for field conditions and algorithm solutions to the above problems are described. Methods used to calibrate the ring dosemeter for Hanford field conditions together with limitations of the ring dosemeter in measuring Hp(0.07) for extremities, particularly when covered with protective clothing, are also discussed. (author)

  6. Individual Differences in Response to Automation: The Five Factor Model of Personality

    Science.gov (United States)

    Szalma, James L.; Taylor, Grant S.

    2011-01-01

    This study examined the relationship of operator personality (Five Factor Model) and characteristics of the task and of adaptive automation (reliability and adaptiveness--whether the automation was well-matched to changes in task demand) to operator performance, workload, stress, and coping. This represents the first investigation of how the Five…

  7. Design and characteristic studies on new personal Radon dosimetry bu using polycarbonate detectors

    International Nuclear Information System (INIS)

    Passive radon dosimeters, based on alpha particle etched track detectors, are widely used for the assessment of radon exposure. These methods, are often applied in environmental monitoring for a long period of time. At this research, we have developed a new method for personal radon dosimetry, with high efficiency that is based upon detection of alpha particles from 218Po and 214Po collected on the fiber glass filter, which affect the polycarbonate detector surface. The radon daughter were collected on the filter surface by passing a fixed air flow through and the polycarbonate detector is exposed by their alpha particles simultaneously. After exposure, the latent tracks on the detector will be appeared by means of electrochemical etching process which is proportional to radon dose. The air flow rate and distance between the detector and the filter are the major factors that can effect the performance of the dosimeter. The relevant experimental investigations have shown that 4cm distance between the detector and the filter and 4 lit/min air flow rate through the filter are the best conditions for design of high efficient personal radon dosimeter. The most important advantages of this method are exact, fast and convenient in application and individual dose assessment. In this paper, the optimized parameters of design are presented and discussed

  8. Accreditation of a personal dosimetry service in Switzerland: Practical experience and transition from EN 45004 to ISO 17025

    International Nuclear Information System (INIS)

    In compliance with the Swiss legislation on radiological protection, the Paul Scherrer Institute (PSI) operates a dosimetry service that is approved by the Swiss Federal Nuclear Safety Inspectorate. In 1997, the dosimetry service was also accredited by the Swiss Federal Office of Metrology and Accreditation as an inspection body for legal personal and environmental dosimetry, according to EN 45004. The accreditation covers determination of personal dose equivalent for photon, neutron and beta radiation, and ambient dose equivalent for photon and neutron radiation, by means of thermoluminescence and solid state track detection techniques. Within this formal accreditation it was confirmed that the relevant requirements of ISO 9002 are also fulfilled. The first re-accreditation will take place in 2001 and work is going on to achieve the transition from EN 45004 to ISO 17025. Accreditation is a feasible, practicable and acceptable way to achieve harmonisation in the field of dosimetry. However, before starting on the path to formal accreditation, a careful analysis should be made, taking into consideration not only cost-benefit aspects but also national legal requirements. (author)

  9. SU-E-T-497: Semi-Automated in Vivo Radiochromic Film Dosimetry Using a Novel Image Processing Algorithm

    International Nuclear Information System (INIS)

    Purpose: To validate an automated image processing algorithm designed to detect the center of radiochromic film used for in vivo film dosimetry against the current gold standard of manual selection. Methods: An image processing algorithm was developed to automatically select the region of interest (ROI) in *.tiff images that contain multiple pieces of radiochromic film (0.5x1.3cm2). After a user has linked a calibration file to the processing algorithm and selected a *.tiff file for processing, an ROI is automatically detected for all films by a combination of thresholding and erosion, which removes edges and any additional markings for orientation. Calibration is applied to the mean pixel values from the ROIs and a *.tiff image is output displaying the original image with an overlay of the ROIs and the measured doses. Validation of the algorithm was determined by comparing in vivo dose determined using the current gold standard (manually drawn ROIs) versus automated ROIs for n=420 scanned films. Bland-Altman analysis, paired t-test, and linear regression were performed to demonstrate agreement between the processes. Results: The measured doses ranged from 0.2-886.6cGy. Bland-Altman analysis of the two techniques (automatic minus manual) revealed a bias of -0.28cGy and a 95% confidence interval of (5.5cGy,-6.1cGy). These values demonstrate excellent agreement between the two techniques. Paired t-test results showed no statistical differences between the two techniques, p=0.98. Linear regression with a forced zero intercept demonstrated that Automatic=0.997*Manual, with a Pearson correlation coefficient of 0.999. The minimal differences between the two techniques may be explained by the fact that the hand drawn ROIs were not identical to the automatically selected ones. The average processing time was 6.7seconds in Matlab on an IntelCore2Duo processor. Conclusion: An automated image processing algorithm has been developed and validated, which will help minimize user

  10. Will the future of knowledge work automation transform personalized medicine?

    OpenAIRE

    Gauri Naik; Sanika S. Bhide

    2014-01-01

    Today, we live in a world of ‘information overload’ which demands high level of knowledge-based work. However, advances in computer hardware and software have opened possibilities to automate ‘routine cognitive tasks’ for knowledge processing. Engineering intelligent software systems that can process large data sets using unstructured commands and subtle judgments and have the ability to learn ‘on the fly’ are a significant step towards automation of knowledge work. The applications of this t...

  11. Cosmic-radiation dosimetry using electronic personal dosemeter (EPD) at commercial aircraft altitude

    Energy Technology Data Exchange (ETDEWEB)

    Yasuda, Hiroshi; Fujitaka, Kazunobu [National Inst. of Radiological Sciences, Chiba (Japan). International Space Radiation Lab.

    2000-02-01

    Electronic Personal Dosemeter (EPD) was examined for effectiveness in cosmic radiation dosimetry at aircraft altitude through the measurements in a Japan-US round trip. The EPD value (H{sub epd}) of individual dose equivalent, penetrating, H{sub p}(10), was considered to be almost equal the deep absorbed dose attributed to electrons at the aircraft altitude. By assuming the fractions and the effective quality factors for other components (muons, protons, and neutrons) based on model-calculation data, an empirical equation to estimate a conservative deep dose-equivalent at 5 cm-tissue depth, H(50), was given as H(50)=3.1 x H{sub epd}. Estimated H(50) values in the international flights were 4.9 {mu}Sv h{sup -1} from Tokyo to New York and 3.6 {mu}Sv h{sup -1} from Los Angeles to Tokyo. These values agreed well with the predicted values presented by NCRP. (author)

  12. Light induced fading associated with the application of OSL to personal dosimetry

    International Nuclear Information System (INIS)

    Al2O3:C is the best material example that presents OSL response and adequate dosimetric behaviour for OSL dosimetry. It was the first commercial material manufactured for use in personal monitoring based on an OSL reader system from Landauer. The purpose of this paper was to report the results of optical fading experiments for the nanoDot commercial OSL detectors (Al2O3:C), provided by Landauer Inc. Five groups of different experimental conditions were formed with all detectors, exposing them to fluorescent and semiconductor light sources and to sun light. The loss of OSL signal when the detectors are kept open, was verified, which was already expected, but a loss in the OSL signal even when the detectors are exposed to light and covered with the manufacturer plastic protection are also revealed. The results show also that the use of Mylar filters can delay the OSL fading of the detectors. - Highlights: • The light fading is one of the most important dosimetric characteristics of Al2O3:C. • Optical decay of the OSL signal was studied when exposed to light in different ways. • A loss in the OSL signal was found in all tested ways

  13. Performance testing of personal dosemeters from eleven dosimetry services in Sweden

    International Nuclear Information System (INIS)

    The Swedish regulation, SSI FS 98:5, requires that radiological workers of category A use dosemeters from an approved personal dosimetry service. The 11 services operating in Sweden at the moment use five different types of dosemeter. All have been tested for their ability to determine Hp(10) and some of them to determine Hp(0.07) according to the European Commission report Radiation Protection 73, EUR 14852, of 1994. The five unique systems have been tested regarding the angular and energy dependence of the response of the dosemeters. The test points for the determination of Hp(10) are all, except one, within the trumpet curve and for the unique systems it is shown that the uncertainty related to angular response at three different energies is within the required ±40% except for the lowest X ray quality 40 kV. The energy dependence dominates over the directional dependence and the choice of radiation quality for calibration is of great importance for the system performance. (author)

  14. The magnetostrictive laser diode magnetometer for personal magnetic field dosimetry (abstract)

    Science.gov (United States)

    Chung, R.; Weber, R.; Jiles, D. C.

    1993-05-01

    This paper reports on the completion of a new type of magnetometer for personal magnetic field dosimetry.1,2 The instrument is a small 15 cm×10 cm×2.5 cm device which can be worn by the user. It utilizes the magnetostrictive response of a Tb-Dy-Fe sensor to measure the prevailing ac magnetic field amplitude. The results are stored using an on-board microprocessor which then integrates the field values to determine the total exposure ∫ Hmax(ω) dt over a given time period. The performance of this new device is reported for a range of ac field frequencies from 10 Hz to 30 kHz. It has been found that the sensitivity of the device is greatly enhanced by using a localized 16 kA/m dc bias field to operate the sensor at the condition of highest dλ/dH. The device can detect fields down the 5 μ T range, and by suitable signal processing, has been designed to give an output signal in both field amplitude and frequency. The device contains a rugged laser diode interferometer of the type used in compact disk audio systems, an AlNiCo permanent magnet to provide the bias field and a Tb0.3Dy0.7Fe1.9 magnetostrictive alloy sensors with strain amplitudes up to 1000 ppm.

  15. Automated DICOM metadata and volumetric anatomical information extraction for radiation dosimetry

    Science.gov (United States)

    Papamichail, D.; Ploussi, A.; Kordolaimi, S.; Karavasilis, E.; Papadimitroulas, P.; Syrgiamiotis, V.; Efstathopoulos, E.

    2015-09-01

    Patient-specific dosimetry calculations based on simulation techniques have as a prerequisite the modeling of the modality system and the creation of voxelized phantoms. This procedure requires the knowledge of scanning parameters and patients’ information included in a DICOM file as well as image segmentation. However, the extraction of this information is complicated and time-consuming. The objective of this study was to develop a simple graphical user interface (GUI) to (i) automatically extract metadata from every slice image of a DICOM file in a single query and (ii) interactively specify the regions of interest (ROI) without explicit access to the radiology information system. The user-friendly application developed in Matlab environment. The user can select a series of DICOM files and manage their text and graphical data. The metadata are automatically formatted and presented to the user as a Microsoft Excel file. The volumetric maps are formed by interactively specifying the ROIs and by assigning a specific value in every ROI. The result is stored in DICOM format, for data and trend analysis. The developed GUI is easy, fast and and constitutes a very useful tool for individualized dosimetry. One of the future goals is to incorporate a remote access to a PACS server functionality.

  16. New tool for biological dosimetry: Reevaluation and automation of the gold standard method following telomere and centromere staining

    International Nuclear Information System (INIS)

    Graphical abstract: - Highlights: • We have applied telomere and centromere (TC) staining to the scoring of dicentrics. • TC staining renders the scoring of dicentrics more rapid and robust. • TC staining allows the scoring of not only dicentrics but all chromosomal anomalies. • TC staining has led to a reevaluation of the radiation dose–response curve. • TC staining allows automation of the scoring of chromosomal aberations. • Automated scoring of dicentrics after TC staining was as efficient as manual scoring. - Abstract: Purpose: The dicentric chromosome (dicentric) assay is the international gold-standard method for biological dosimetry and classification of genotoxic agents. The introduction of telomere and centromere (TC) staining offers the potential to render dicentric scoring more efficient and robust. In this study, we improved the detection of dicentrics and all unstable chromosomal aberrations (CA) leading to a significant reevaluation of the dose–effect curve and developed an automated approach following TC staining. Material and methods: Blood samples from 16 healthy donors were exposed to 137Cs at 8 doses from 0.1 to 6 Gy. CA were manually and automatically scored following uniform (Giemsa) or TC staining. The detection of centromeric regions and telomeric sequences using PNA probes allowed the detection of all unstable CA: dicentrics, centric and acentric rings, and all acentric fragments (with 2, 4 or no telomeres) leading to the precise quantification of estimated double strand breaks (DSB). Results: Manual scoring following TC staining revealed a significantly higher frequency of dicentrics (p < 10−3) (up to 30%) and estimated DSB (p < 10−4) compared to uniform staining due to improved detection of dicentrics with centromeres juxtaposed with other centromeres or telomeres. This improvement permitted the development of the software, TCScore, that detected 95% of manually scored dicentrics compared to 50% for the best currently

  17. An application of artificial neural intelligence for personal dose assessment using a multi-area OSL dosimetry system

    International Nuclear Information System (INIS)

    Significant advances have been made in recent years to improve measurement technology and performance of phosphor materials in the fields of optically stimulated luminescence (OSL) dosimetry. Pulsed and continuous wave OSL studies recently carried out on α-Al2O3 : C have shown that the material seems to be the most promising for routine application of OSL for dosimetric purposes. The main objective of the study is to propose a new personal dosimetry system using α-Al2O3 : C by taking advantage of its optical properties and energy dependencies. In the process of the study, a new dose assessment algorithm was developed using artificial neural networks in hopes of achieving a higher degree of accuracy and precision in personal OSL dosimetry system. The original hypothesis of this work is that the spectral information of an X- and γ-ray fields may be obtained by the analysis of the response of a multi-element system. In this study, a feedforward neural network using the error back-propagation method with Bayesian optimization was applied for the response unfolding procedure. The validation of the proposed algorithm was investigated by unfolding the 10 measured responses of α-Al2O3 : C for arbitrarily mixed photon fields which range from 20 to 662 keV

  18. Dosimetry Service

    CERN Multimedia

    Dosimetry Service

    2005-01-01

    Please remember to read your dosimeter at least once every month. A regular read-out is indispensable to ensure periodic monitoring of your personal dose. You must read your dosimeter even if you have not visited the controlled areas. Film badges are no longer valid at CERN and holders of film badges are no longer allowed to enter the controlled radiation areas or work with a source. Dosimetry Service Tel. 72155 http://cern.ch/rp-dosimetry

  19. A new TL finger ring dosimetry system with automated ring identification

    International Nuclear Information System (INIS)

    TL finger ring dosemeters, particularly if used during surgery, etc., have to be small, convenient to wear and suitable for cold sterilisation. This makes automated ring identification difficult to achieve. A new approach is described, based on a circular TLD chip mounted with Kapton foil on a small aluminium disc containing a miniaturised circular bar code (radial 6 digit ITF) and a six digit number. The ring is inserted into a disposable plastic finger ring and protected by a circular cover plate. This ring design is convenient to wear, fits all finger sizes and can be cold sterilised for multiple use in surgery. For readout the ring is opened by a semi-automated device and up to four bar coded discs inserted into a modified standard TLD card for automatic processing by Harshaw readers models 6600 or 8800. The reader contains a video bar code identification system based on a minaturised CCD camera and image processing by special PC software. The circular bar codes are mathematically linearised and decoded directly from the enhanced grey scale picture obtained with optimised illumination by power LEDs. The system described (Patent No. A 398005/1994) is a fast and economic solution for fully (or semi-) automated evaluation of TLD finger rings in larger personnel monitoring services. (author)

  20. A new personal dosimetry system for HP(10) and HP(0.07) photon dose based on OSL-dosimetry of beryllium oxide

    International Nuclear Information System (INIS)

    In recent years the personal dosimetric system “iBeOx” using optically stimulated luminescence of beryllium oxide (BeO) has been developed by the TU Dresden radiation physics group in cooperation with the Helmholtz Zentrum Muenchen and IBA Dosimetry GmbH Schwarzenbruck. Continuous wave stimulation with a blue LED and measurement of the luminescence light with an enclosed photo sensor module are performed from opposite detector sides. A microcontroller controls the complete measurement cycle, processes the digitized signals, performs extensive checks of the system states and communicates via USB with the external PC software. The resulting OSL signal can be used for dose evaluation. Two types of personal dosimeters are available, both conform to the standard. The dose response is linear from the lowest detection limit of 50 μSv–10 Sv. Long-term fading of the signal is negligible. Due to the near tissue equivalence and the resulting low photon energy dependence of BeO the personal dose can be evaluated from 12 keV up to 7 MeV by one dosimetric element without any corrections. In an automatized environment the system is able to process several hundred dosimeters per hour.

  1. Automation of film densitometry for application in personal monitoring

    International Nuclear Information System (INIS)

    In this research work, a semi-automatic densitometry system has been developed for large-scale monitoring services by use of film badge dosemeters. The system consists of a charge-coupled device (CCD)-based scanner that can scan optical densities (ODs) up to 4.2, a computer vision algorithm to improve the quality of digitised films and an analyser program to calculate the necessary information, e.g. the mean OD of region of interest and radiation doses. For calibration of the system, two reference films were used. The Microtek scanner International Color Consortium (ICC) profiler is applied for determining the colour attributes of the scanner accurately and a reference of the density step tablet, Bundesanstalt fuer Materialforschung und-pruefung (BAM) is used for calibrating the automatic conversion of gray-level values to OD values in the range of 0.2-4.0 OD. The system contributes to achieve more objectives and reliable results. So by applying this system, we can digitise a set of 20 films at once and calculate their relative doses less than about 4 min, and meanwhile it causes to avoid disadvantages of manual process and to enhance the accuracy of dosimetry. (authors)

  2. An automated dosimetry system for CT scanners using silicon P-i-n diodes

    International Nuclear Information System (INIS)

    A revolution in diagnostic radiology was started in 1967 when Hounsfield developed a new x-ray transmission system - the computed axial tomography scanner (CT scanner). This device uses an x-ray source that scans (axially) through a section of the patient's body. Transmitted photons proportional to the density of the material they must traverse are detected and computer reconstructed to produce an image of the tomographic plane of the patient (slice). Only limited dosimetric studies have been performed on CT scanners. Many factors may influence the dose given to patients during a diagnostic study including the scan width, the scan time, the number of slices taken, and the voltage and current settings of the x-ray tube on a particular unit. Adequate health care planning and delivery requires that detailed dosimetric studies be conducted on CT scanners during their infancy. If this can be done, possible questions and criticisms as to the usefulness of this type of diagnostic procedure can be largely eliminated. The study proposed involves the design and construction of a portable radiation dosimetry phantom for CT scanner operations. At the present, there is no efficient method of obtaining accurate X-Y as well as Z-axis dose information from a scanner. Silicon P-i-n diodes, used as the radiation sensors, are arranged inside a phantom to provide reproducible positional and directional dosimetric measurements. Data acquisition circuitry is used to convert the unprocessed signals into a form that is microcomputer compatible. Data storage operations, the application of correction factors, and other manipulations are provided by the microcomputer before transfer to an output display device. The final form of the data consists of absorbed dose values corresponding to the radiation received by the semiconductor detectors. (author)

  3. Are HPS N13.11-2001 test conditions and performance criteria appropriate for evaluating personal dosimetry systems?

    International Nuclear Information System (INIS)

    This very interesting debate points out the fact that there is no such thing as a perfect test. The N13.11-2001 standard has been improved with respect to its previous version. It now incorporates many ISO beam qualities, and this helps to make the tests more consistent with international recommendations. The additional beams make the proficiency tests more difficult, and that may lead the way to additional improvements in personal dosimetry. The content of the standard now paves the way for its use by both the DOELAP and NVLAP programs, and this is a significant achievement. However, it should be kept in mind that proficiency tests are conducted in the laboratory, and it is still difficult to judge whether those tests result in significant improvements in the workplace. Studies of dosemeter performance in the workplace have been conducted in the US and Europe, and additional studies should be encouraged to provide information as to how personal dosemeters are performing in actual workplace conditions. Note: The views expressed in these debates are the personal opinions of the debaters and do not necessarily represent the views of their respective institutions, or of the journal Radiation Protection Dosimetry and its editorial board. (authors)

  4. Dosimetry Service

    CERN Multimedia

    Dosimetry Service

    2004-01-01

    We wish to remind the people who are invited to the dosimetry service to exchange the new CERN dosimeter that the hours are from Monday to Friday 8:30 to 11:00 and 14:00 to 16:00. For all other services we are at your disposition from 8:30 to 12:00 and 14:00 to 17:00. Do not forget to read your dosimeter. A regular read-out is indispensable in order to ensure a periodic monitoring of personal dose. This read-out should be done during the first week of every month. Thank you for your cooperation. The personnel of the Dosimetry Service wish you a Merry Christmas and a Happy New Year. Dosimetry Service Tel. 767 21 55 http://cern.ch/rp-dosimetry

  5. Application of numerical analysis in personal dosimetry by thermoluminescent; Aplicacion de metodos de analisis numerico en un sistema de dosimetria personal por termoluminiscencia

    Energy Technology Data Exchange (ETDEWEB)

    Gomez Ros, J. M.; Delgado, A.; Fantuzzi, E.

    2003-07-01

    The main features of the methods for computerised glow curve analysis are presented in this communication together with a description of their advantages for TLD in replacement of standard procedures. A protocol for the employment of different kinds of computerised methods for personal dosimetry is proposed. The new results now presented demonstrate the possibility, using a very simple computerised analysis, of working with LiF GR-200 without any pre-heat or annealing simplifying the working procedures, now reduced to the simplest possible: a single step readout up to 240 degree celsius. (Author) 7 refs.

  6. Implementation of a new personal dosimetry service by the French Army

    International Nuclear Information System (INIS)

    This paper will describe the motivation of the Service de Protection Radiologique des Armees (S.P.R.A.) for replacing their existing dosimetry service based on photographic films with one centralized at Clamart, near Paris, and adopting dosemeters based on Optically Stimulated Luminescence (O.S.L.). The advantages of centralization and of the new technology adopted will be discussed. (authors)

  7. Comparison groups on bills: Automated, personalized energy information

    Energy Technology Data Exchange (ETDEWEB)

    Iyer, Maithili; Kempton, Willett; Payne, Christopher

    2006-07-01

    A program called ``Innovative Billing?? has been developed to provide individualized energy information for a mass audience?the entireresidential customer base of an electric or gas utility. Customers receive a graph on the bill that compares that customer?s consumption with othersimilar customers for the same month. The program aims to stimulate customers to make ef?ciency improvements. To group as many as severalmillion customers into small ``comparison groups??, an automated method must be developed drawing solely from the data available to the utility.This paper develops and applies methods to compare the quality of resulting comparison groups.A data base of 114,000 customers from a utility billing system was used to evaluate Innovative Billing comparison groups, comparing fouralternative criteria: house characteristics (?oor area, housing type, and heating fuel); street; meter read route; billing cycle. Also, customers wereinterviewed to see what forms of comparison graphs made most sense and led to fewest errors of interpretation. We ?nd that good qualitycomparison groups result from using street name, meter book, or multiple house characteristics. Other criteria we tested, such as entire cycle, entiremeter book, or single house characteristics such as ?oor area, resulted in poor quality comparison groups. This analysis provides a basis forchoosing comparison groups based on extensive user testing and statistical analysis. The result is a practical set of guidelines that can be used toimplement realistic, inexpensive innovative billing for the entire customer base of an electric or gas utility.

  8. Dosimetry Service

    CERN Multimedia

    2005-01-01

    The Dosimetry Service will be closed every afternoon the week of 21st to 25th February 2005. The opening hours will be from 8.30 am to 12.00 midday. Don't forget to read your dosimeter, as regular read-outs are indispensable to ensure periodic monitoring of personal doses. Thank you for you cooperation.

  9. Micro-Fabricated Solid-State Radiation Detectors for Active Personal Dosimetry

    Science.gov (United States)

    Wrbanek, John D.; Wrbanek, Susan Y.; Fralick, Gustave C.; Chen, Liang-Yu

    2007-01-01

    Active radiation dosimetry is important to human health and equipment functionality for space applications outside the protective environment of a space station or vehicle. This is especially true for long duration missions to the moon, where the lack of a magnetic field offers no protection from space radiation to those on extravehicular activities. In order to improve functionality, durability and reliability of radiation dosimeters for future NASA lunar missions, single crystal silicon carbide devices and scintillating fiber detectors are currently being investigated for applications in advanced extravehicular systems. For many years, NASA Glenn Research Center has led significant efforts in silicon carbide semiconductor technology research and instrumentation research for sensor applications under extreme conditions. This report summarizes the technical progress and accomplishments toward characterization of radiation-sensing components for the recommendation of their fitness for advanced dosimetry development.

  10. A new paradigm in personal dosimetry using LiF:Mg,Cu,P

    International Nuclear Information System (INIS)

    The United States Navy has been monitoring personnel for occupational exposure to ionising radiation since 1947. Film was exclusively used until 1973 when thermoluminescence dosemeters were introduced and used to the present time. In 1994, a joint research project between the Naval Dosimetry Center, Georgetown University, and Saint Gobain Crystals and Detectors (formerly Bicron RMP formerly Harshaw TLD) began to develop a state-of-the-art thermoluminescent dosimetry system. The study was conducted from a large-scale dosimetry processor point of view with emphasis on a systems approach. Significant improvements were achieved by replacing the LiF:Mg,Ti with LiF:Mg,Cu,P TL elements due to the significant sensitivity increase, linearity, and negligible fading. Dosemeter filters were optimised for gamma and X ray energy discrimination using Monte Carlo modelling resulting in significant improvement in accuracy and precision. Further improvements were achieved through the use of neural-network based dose calculation algorithms. Both back propagation and functional link methods were implemented and the data compared with essentially the same results. Several operational aspects of the system are discussed, including (1) background subtraction using control dosemeters, (2) selection criteria for control dosemeters, (3) optimisation of the TLD readers, (4) calibration methodology, and (5) the optimisation of the heating profile. (author)

  11. In-situ fluorescence hybridization applied to biological dosimetry: contribution of automation to the counting of radio-induced chromosome aberrations

    International Nuclear Information System (INIS)

    The frequency of chromosome aberrations on peripheral blood lymphocytes is a dose indicator in the case of ionizing radiations over-exposure. Stable chromosome aberrations (translocations, insertions) are visualized after labelling of some chromosomes using the fluorescence in-situ hybridization (FISH). The study of the use of the FISH technique in biological dosimetry is done with dose-effect curves. It seems that a bias is introduced during the observation of chromosome aberrations involving only 3 pairs of chromosomes. In order to avoid this bias, it would be useful to test the feasibility of using the multi-FISH technique in biological dosimetry. Moreover, this type of chromosome aberration changes with the type of irradiation. It is thus important to define the aberrations to be considered when the FISH technique is used. In order to reduce the time of image analysis, the CYTOGEN system, developed by IMSTAR company (Paris, France) has been adapted to the needs of biological dosimetry. This system allows to localize automatically the metaphases on the slide, which reduces the observation time by 2 or 4. An automatic detection protocol for chromosome aberrations has been implemented. It comprises the image capture, the contours detection and the classification of some chromosome aberrations. The different steps of this protocol have been tested in order to check that no bias is introduced by the automation. However, because radio-induced aberrations are rare events, it seems that a totally automatic system is not foreseeable. A semi-automatic analysis is more suitable. The use of the Slit-Scan technology (Laboratory of applied physics, Heidelberg, Germany) in biological dosimetry has been studied too. This technique allows to analyze rapidly a huge number of chromosomes. A good correlation has been observed between the dicentric frequency measured automatically and by manual counting. The system is under development and should be adapted to the detection of

  12. A Cooperative Personal Automated Transport System - A CityMobil Demonstration in Rocquencourt

    OpenAIRE

    Resende, Paulo; Nashashibi, Fawzi; Charlot, François; Holguin, Carlos; Bouraoui, Laurent; Parent, Michel

    2012-01-01

    International audience This article tackles the problem of the autonomous navigation and coordination of multiple driverless vehicles for the transport of persons or goods in outdoor environments. The system composed of fully automated road vehicles, capable of providing an effective transportation service, was recently tested at the city of La Rochelle. This same system was further improved, and a new demonstration was performed at Inria Rocquencourt, in order to demonstrate the validity ...

  13. Some practical and theoretical considerations of personal alpha-particle dosimetry. Joint panel on occupational and environmental research for uranium production in Canada (JP-2)

    International Nuclear Information System (INIS)

    The status of personal α-particle dosimetry in the uranium industry is presented. A brief description of personal dosimeters and prototypes is followed by some theoretical considerations regarding their practical use under steady-state and time-dependent field conditions. It is suggested that, at present, more effort should be placed on the evaluation of dosimeters than in the development of new ones. Also, more information should be gathered from countries which use personal α-particle dosimeters routinely. Furthermore, emphasis is recommended on comparison of personal dosimetry data with experimental data by area monitoring, using continuous monitoring systems, as well as with data by grab-sampling techniques. (author). 44 refs., 1 tab

  14. Establishment of ANSI N13.11 X-ray radiation fields for personal dosimetry performance test by computation and experiment.

    OpenAIRE

    Kim, J L; Kim, B. H.(Seoul National University, 151-742, Seoul, South Korea); Chang, S Y; J. K. Lee

    1997-01-01

    This paper describes establishment by computational and experimental methods of the American National Standard Institute (ANSI) N13.11 X-ray radiation fields by the Korea Atomic Energy Research Institute (KAERI). These fields were used in the standard irradiations of various personal dosimeters for the personal dosimetry performance test program performed by the Ministry of Science and Technology of Korea in the autumn of 1995. Theoretical X-ray spectra produced from two KAERI X-ray generator...

  15. Report of results of the tests of evaluation of the operation of service of personal dosimetry of the CNLV

    International Nuclear Information System (INIS)

    The ININ realized the evaluation of the service of personal dosimetry in the CNLV, in the categories: IV.- (Photons of high energy of 137Cs) and the VA.- (Particles beta of 90Sr/90Y); in the category IV the test was satisfactory, however in the chart 1 has an underestimation a the American Standard HP over the value true conventional of a 9%; for this irregularity it is recommended to revise the procedures of evaluation of the process and the determination of the chart 1 of the HP. In the category VA, the test is also satisfactory, however the results contrasted with the chart 2 and the HP, the values were overestimated in 29% of the true conventional value, and for that problem is recommended to revise the evaluation procedures in contrast with the values determined by the standard HP. (Author)

  16. The application of computerised analysis of glow curves to personal dosimetry in LiF:Mg,Cu,P

    International Nuclear Information System (INIS)

    In personnel monitoring services, it is important to omit the high-temperature annealing process so that large numbers of TL detectors can be produced economically. There are two efficient ways of reducing the residual signal of LiF:Mg,Cu,P. One is by increasing the maximum readout temperature and the other is by improving the preparation procedure (increasing the Cu concentration and the sintering temperature) but both reduce the TL sensitivity. In personal dosimetry the real dosimetric signals are separated from the residual signals by computerised analysis of glow curves. The adverse influence of the high residual signals of LiF:Mg,Cu,P TL material has been effectively eliminated and the sensitivity remains stable. A good dosimetric result using only reader measurement without pre-irradiation oven annealing is attained in a dose range of 50-80,000 μGy. (author)

  17. Results of the ninth exercise of intercomparison in services of personal dosimetry in Argentina Republic in the year of 2011; Resultados del noveno ejercicio de intercomparacion de servicios de dosimetria personal realizado en la Republica Argentina en el ano 2011

    Energy Technology Data Exchange (ETDEWEB)

    Ferrufino, G.A.; Discacciatti, P.A.; Lopez, F.O., E-mail: gferrufino@am.gob.ar [Autoridad Regulatoria Nuclear (ARN), Buenos Aies (Argentina)

    2013-10-01

    In this paper we present the results of the ninth intercomparison exercise personal dosimetry services, conducted by the Nuclear Regulatory Authority in 2011. The exercise was designed to evaluate the performance of laboratories providing personal dosimetry services in Argentina , for X-rays and gamma radiation fields . This exercise was organized by the Nuclear Regulatory Authority with the Ministry of Health of the Nation and the Regional Reference Laboratory Centre for Dosimetry of the National Atomic Energy Commission . The irradiations were carried out in full accordance with ISO 4037-3 . Participates all private companies in Argentina serving all personal dosimetry laboratories and agencies, provincial and national. Furthermore, the Laboratories from Cuba, Brazil and Uruguay also participate. The performance of a laboratory is considered acceptable if it meets the criteria established in the IRAM- ISO 14146 , which states: 'It is recognized that at most, one-tenth of dosimeters irradiated to exceed the limits'. Of all of the laboratories that participated , 68% reported their results within the acceptance criteria above. The primary objective of this intercomparison exercise is to provide an objective tool to evaluate the ability of personnel dosimetry services. (author)

  18. Long term stability studies of the Harshaw Tld 6600 system used for personal dosimetry monitoring in Ghana

    International Nuclear Information System (INIS)

    A dosimetry system made up of the Harshaw TLD 6600 has been used in the monitoring of occupationally exposed workers and for research purposes in Ghana since 1998. Continuous use, calibration and maintenance have been done periodically on the equipment at the Personal Monitoring Service (PMS) laboratory since its installation at the PMS laboratory of the Radiation Protection Institute in Ghana. The Daily Electronics Quality Control (DEQC) test carried out to ensure that the Harshaw 6600 TLD Reader was in good working condition prior to the reading of TLD cards. The present work was done to assess the long term stability of the system with respect to the DEQC parameter in order to ensure quality control and accurate measurements for personal dosimetry in Ghana. The parameters under investigation included the high voltage, temperature, reference light, plus and minus 15 volts, ground, digital to analog conversion and the photomultiplier tube noise. WINREMS software is incorporated into a computer to monitor these parameters in order to verify whether they conform to performance standards. The annual mean reference light values in nano coulomb for chip (ii) were 471.0±49.5, 77.0±109.2, 18.5±7.9, 31.0±81.1 and 18.7±3.2; for chip (iii) were 475.1±45.7, 102.4±132.8, 74.3±107.4, 83.7±125.3 and 8.6±3.1 respectively. These values are outside the reference ranges indicating instability for the period of five (5) years (2008 to 2012). Measurement of exposed TLDs to known doses at the SSDL confirmed the PMT gain stability of system. The instability in the reference light readings was due to ageing and yellowing of the optical portion of the reference light. The high voltage and the reference light were unstable. The temperature, plus and minus 15 volts, ground and digital to analog conversion and PMT noise were all stable. The study indicates the PMS therefore provides a reliable and accurate dosimetry in the long term. (au)

  19. [Long-term follow-up cytogenetic survey and biological dosimetry in persons evacuated from 30-km Chernobyl NPP zone].

    Science.gov (United States)

    Maznik, N A

    2004-01-01

    The paper presents the results of the follow-up cytogenetic survey and biological dosimetry carried out in inhabitants of Pripiat' town and nearby villages, who were departured from the Chernobyl NPP 30-km exclusive zone during first days after the Chernobyl catastrophe. The unstable chromosome aberration level in inhabitants were significantly increased above control in terms up to 1 year after evacuation and declined gardually during next 14 years. In early period the cytogenetic damage frequency in evacuees showed no dependence on gender. The chromosome type aberration level appeared to be lower in young persons comparing with adults. The dicentrics plus centric rings yield had a positive correlation with duration of staying at Chernobyl zone. The average doses of protracted exposure were calculated from the dicentrics and centric rings yields; the dose estimations appeared to be 1.4 times higher in persons evacuated 3-11 days after the accident than that of in persons with shorter departure time. Uing the Bayesian analysis the probabilistic distribution of biological doses was constructed for the studied evacuees group. This distribution was characterized by a mean dose of 360 mGy, the modal doses of 200-450 mGy and 80% of probability density within the dose range 0-1000 mGy, that seems to be sufficient for considering the increased risk of late somatic radiation effects for this cohort. PMID:15571047

  20. Fiber remote and real time optoelectronic dosimetry based on the optically stimulated luminescence phenomenon: Development of sensors based on aluminium oxide doped with carbon for applications in personal dosimetry

    International Nuclear Information System (INIS)

    An optical fiber sensor based on the use of classical technologies (optoelectronic, laser, optical fibers,...) can be connected to the Optically Stimulated Luminescence properties (or OSL) of the aluminium oxide doped with carbon in order to provide several new capabilities compared to usual dosimeters: remote dose measurements, quasi 'real time' dose measurements, applied to personal dosimetry thanks to a low fading level at room temperature. This thesis work shows the studies about: 1)the state of the art about dosimetry based on the aluminium oxide doped with carbon and its OSL properties (emission and stimulation spectra, glow curves, trap and recombination energy levels,...), 2)the state of the art about international standardization, not only, with regard to personal dosimetry (IEC 61066 Standard) but also to the description of operational quantities called personal dose equivalent Hp(10) and Hp(0,07), 3)the experimental development of a new sensor device based on aluminium oxide crystals (design, realization, tests,...), 4)the application of statistical Monte Carlo calculation methods (code MCNP4B) to the simulation of the sensor head in accordance with the IEC Standard 61066 with regard to the energy and angular response Hp(10). (author)

  1. Studying dosimetric parameters of thermoluminescent dosemeter of CaSO4:Dy powder made in the Nuclear Research Institute for personal radiation dosimetry

    International Nuclear Information System (INIS)

    The research group of the Nuclear Research Institute (NRI) itself studied and successfully made thermoluminescent dosemeters (TLDs) using powder material of CaSO4:Dy in 2014. For external personal dosimetry, dosimetric parameters of the TLDs were surveyed by radiating with various gamma doses of 137Cs source and measured by Rexon-320 Reader such as glow curve with temperature, calibration factor (or response value), homogeneity of the batch, reproducibility of measurement, linearity of dose response, limit of detection, fading, light sensitivity, dose-rate dependence, and energy dependence of the response, etc. The studied results were shown that the dosemeters were ensured for personal dosimetry according to the standards of IEC-61066:2006. Besides, the TLDs were also radiated with standard doses of gamma (137Cs) and X-rays at the Secondary Standards Dosimetry Laboratory (SSDL) of the Institute for Nuclear Science and Technology in Hanoi. Comparison results on dose were shown that the TLDs have been confident. Therefore, they have been used for routinely external personal dosimetry for radiation workers in the NRI and other radiation installations from the beginning of 2015. (author)

  2. A new algorithm for identifying abnormal glow curves in thermoluminescence personal dosimetry

    International Nuclear Information System (INIS)

    In this paper an algorithm for the investigation of routine curves in thermoluminescence personnel dosimetry is presented. In rare cases, the luminescence glow curves do not exhibit the expected form. They have an abnormal shape as a result of, for example, external contamination, hardware problems, and poor heat transfer. So, glow curves from a monthly exposure period are compared with regular glow curves. Each curve is divided into four regions of interest (ROIs) and the relationship between the different ROIs are analysed. There are few criteria combining all four ROIs, which are necessary to distinguish between normal and abnormal glow curves. For that, the numerical value and the channel of the curves maximum also need to be considered. In most cases an additional set of criteria permits the identification of the ROI in which the irregularity occurs. (author)

  3. Personal dosimetry in terms of HP(3):Monte Carlo and experimental studies

    International Nuclear Information System (INIS)

    Hp(3) has been defined as the operational quantity for eye lens dosimetry. Hp(3)/ka conversion coefficients were evaluated at the GSF (Germany) in a 30 x 30 x 15 x cm3 4-elements ICRU slab phantom for various energies and incident angles through Monte Carlo. The ISO report 12,794 suggests to employ a PMMA water filled phantom, of the same dimensions, for dosemeter calibration in terms of Hp(3). The present paper briefly summarises the main aspects of a study carried out at ENEA-Radiation Protection Inst. (Bologna (Italy)) to provide practical procedures for the calibration of dosemeters in terms of Hp(3). Tabulations of a new set conversion coefficients and air kerma backscatter factors are provided as a function of energy and incident angle. The paper demonstrates that a more accurate approach to the dosimetric assessment in terms of Hp(3) could be rather simply introduced employing a reduced phantom. (authors)

  4. Occupational dosimetry commissioning of a PET-CT: learning curve and staff participation; Dosimetria ocupacional en la puesta en funcionamiento de un PET-TC curva de aprendizaje y participacion del personal

    Energy Technology Data Exchange (ETDEWEB)

    Sierra Diaz, F.; Hurtado Sanchez, A.; Gomez Cortes, M. S.; Gonzalez Ruiz, C.; Gago Gomez, P.; Ruiz Galan, G.; Lopez Bote, M. A.

    2011-07-01

    The Nuclear Medicine Department, Hospital General Universitario Gregorio Maranon has been in clinical use PET-CT equipment at the end of 2009. The Dosimetry and Radiation Protection Service has been conducting surveillance at the facility and individual environmental dosimetry. Following the obligations contained in the performance specifications of the authorization granted by the Nuclear Safety Council (CSN), during the first year of the PET-CT has been tracking personal dosimetry of the professionals involved. As a novelty, had to take the ring dosimetry to control the dose equivalent in the hands instead of the normal wrist.

  5. Personal and environmental dosimetry of neutrons in a storage facility and humidity probes soil density; Dosimetria personal y ambiental de neutrones en una instalacion de almacenamiento de sondas de densidad y humedad de suelos

    Energy Technology Data Exchange (ETDEWEB)

    Garcia-Fuste, M. J.; Amgarou, K.; Dan Pedro, M. de; Garcia-Orellana, J.; Domingo, C.

    2011-07-01

    The equipment operators are professionally exposed to radiation and the premises where stored are considered controlled areas. Although control of the personal doses of gamma radiation received by the operators during the operation, maintenance and storage of the probes is required and is performed by dosimetry services officially approved, the control of personal and environmental doses due to neutrons generally omitted, since they are small in comparison to the gamma dose.

  6. Dosimetry service removal

    CERN Multimedia

    Safety Commission

    2010-01-01

    Dear personal dosimeter user, Please note that the Dosimetry service has moved in building 55, the service is now located in the main floor: 55-R-004. Main floor instead of second floor. On your right hand when accessing in the building. Thank you Dosimetry Service

  7. Personal neutron dosimetry in nuclear power plants using etched track and albedo thermoluminescence dosemeters

    International Nuclear Information System (INIS)

    Measurement of the personal dose equivalent rates for neutrons is a difficult task because available dosemeters do not provide the required energy response and sensitivity. Furthermore, the available wide calibration spectra recommended by the International Standard Organisation does not reproduce adequately the spectra encountered in practical situations of the nuclear industry. There is a real necessity to characterise the radiation field, in which workers can be exposed, and to calibrate personal dosemeters in order to determine the dose equivalent in these installations. For this reason, we measure the neutron spectrum with our Bonner sphere system and we fold this spectrum with energy-dependent fluence-to-dose conversion coefficients to obtain the reference dose equivalent rate. This reference value is then compared with the personal dosemeter reading to determine a field-specific correction factor. In this paper, we present the values of this field-specific correction factor for etched track and albedo thermoluminescence dosemeters at three measurement locations inside the containment building of the Vandellos II nuclear power plant. We have found that assigning to each personal dosemeter the mean value of the field-specific correction factors of the three measurement locations, allows the evaluation of neutron personal dose equivalent rate with a relative uncertainty of∼25 and 15% for the PADC and albedo dosemeters, respectively. (authors)

  8. Conversion coefficients from air kerma to personal dose equivalent Hp(3) fir eye-lens dosimetry

    International Nuclear Information System (INIS)

    This work has been performed within the frame of the European Union ORAMED project (Optimization of Radiation protection for Medical staff). The main goal of the project is to improve standards of protection for medical staff for procedure resulting in potentially high exposures and to develop methodologies for better assessing and for reducing exposures to medical staff. The Work Package WP2 is involved in the development of practical eye lens dosimetry in interventional radiology. This study is complementary of the part of the ENEA report concerning the calculations with the MCNP code of the conversion factors related to the operational quantity Hp(3). A set of energy and angular dependent conversion coefficients Hp(3)/Kair in the new proposed square cylindrical phantom of ICRU tissue, have been calculated with the Monte-Carlo code PENELOPE. The Hp(3) values have been determined in terms of absorbed dose, according to the definition of this quantity, and also with the kerma approximation as formerly reported in ICRU reports. At low photon energy, up to 1 MeV, the two sets of conversion coefficients are consistent. Nevertheless, the differences increase at higher energy. This is mainly due to the lack of electronic equilibrium, especially for small angle incidences. The values of the conversion coefficients obtained with the code MCNP published by ENEA, agree with the kerma approximation calculations with PENELOPE. They are coherent with previous calculations in phantoms different in shape. But above 1 MeV, differences between conversion coefficient values calculated with the absorbed dose and with kerma approximation are significantly increasing, especially at low incidence angles. At those energies the electron transport has to be simulated. (author)

  9. A proposal for fast neutron personal real time dosimetry in mixed n, γ fields

    International Nuclear Information System (INIS)

    A method for fast neutron monitoring has been studied, resulting from computer simulation analysis of fast neutron and gamma interaction responses in silicon counters. A real time personal dosemeter with a response accuracy better than 30% in a mixed n, γ field for neutron energies between 0.75 and 15 MeV is proposed. (author)

  10. Track method for personal dosimetry for a nuclear-powered fleet

    International Nuclear Information System (INIS)

    This work presents the development results of a high-sensitivity personal neutron track dosimeter for nuclear-powered ice-breakers. The dosimeter consists of a uranium-235 target and PET track detector in cadmium filters. Dose per track value of the dosimeter is 0.012 mrem fission-1 with scattering of 15%, affording a minimum measurable dose of 0.1 mrem. The main characteristics of this dosimeter are compared with the TLD-albedo ALNOR dosimeter. (author)

  11. Correlation Between Clinical Dosimetry and Physical Controls Based on Personal Sampling

    International Nuclear Information System (INIS)

    During a period of eighteen months, various persons exposed to atmospheric contamination in a radioisotope production plant were monitored by two different methods: one was based on personal samples taken over a limited period and used to establish the exposures undergone, qualitatively and quantitatively, from filter examination; the other method involved systematic examination using whole- body spectrometry. Iodine-131 is the radioisotope to which the persons in question were most frequently exposed. Taking account of the effective decay arising between the moment of inhalation and the moment of making the spectrometric measurements, the authors established a ratio K between the inhaled activity, estimated from samples and corrected for decay, and the activity measured directly on the individual. For 34 results obtained on six different individuals, who performed the same tasks in rotation, it seems that these K ratios have a log-normal distribution characterized by a geometric mean Kg = 1.3 and a standard geometric deviation og = 2.2. If the activity retained by the body is 75% of the inhaled activity, it seems likely that the results of the two control methods are, on average, identical. Results have also been obtained with other radioisotopes, especially caesium-137. It is shown how the two methods can be used simultaneously to resolve practical difficulties. (author)

  12. 12''th International Conference on Solid State Dosimetry Casa del Cordon. Conference Center (Caja de Burgos), July 5''th-10''th, 1998, Burgos Spain: Programme and Abstracts

    International Nuclear Information System (INIS)

    The 12 International Conference on Solid State Dosimetry celebrate in Burgos (Spain) during July on 1998. 1.- Basic Physical Processes 2.- Materials characteristics 3.- Instrumentation 4.- Personal Dosimetry 5.- Clinical Dosimetry 6.- Environmental Dosimetry 7.- Dating retrospective dosimetry 8.- Miscellaneous

  13. Dosimetry Service

    CERN Multimedia

    Dosimetry Service

    2005-01-01

    Please remember to read your dosimeter every month at least once and preferably during the first week. A regular read-out is indispensable in order to ensure a periodic monitoring of the personal dose. You should read your dosimeter even if you have not visited the controlled areas. If you still have the old dosimeter (film badge), please send it immediately for evaluation to us (Bdg 24 E-011). After January 2005 there will be no developing process for the old film system. Information for Contractors: Please remember also to bring the form ‘Confirm Reception of a CERN Dosimeter' signed with ‘Feuille d'enregistrement du CERN'. Without these forms the dosimeter cannot be assigned. Thank you for your cooperation. Dosimetry Service Tel 767 2155 http://cern.ch/rp-dosimetry

  14. Multiple-Purpose Personal Dosimeter Suitable for Dosimetry of High Accidental Exposures

    International Nuclear Information System (INIS)

    The paper describes the personal dosimeter designed by the Commissariat à l'énergie atomique to permit evaluation of the doses received by workers liable to high accidental exposures. It consists of a film dosimeter plus a glass, threshold and activation detector pack. The film dosimeter consists of a case fitted with screens demarcating seven different areas of the film. The latter, which provides density measurements by reflection, consists of three emulsions of different sensitivities on a common base, so that a single development covers the dose range between 20 mr and 800 r. An NTA nuclear-emulsion, fast-neution dosimeter can be added. Two glass dosimeters of different characteristics are included to permit separate evaluation of gamma and thermal neutron radiation. The unit also possesses conventional threshold and activation detectors. (author)

  15. Personal characteristics and environmental factors influencing lung dosimetry of inhaled radon decay products

    International Nuclear Information System (INIS)

    The attempt to interpret lung cancer incidence caused by inhaled radon decay products in items of radiation dose raises the question of the relevant dose. The various dosimetric approaches published by now are characterized by an increasing complexity in the structure of the models used. Due to uncertainties of physical and biological parameters involved and the application of different anatomical and physiological models the calculated doses are varying up to one order of magnitude. Independent of the choice of these dosimetric models applied to the calculation of lung doses, deposition, clearance and resulting dose are affected essentially by the properties of the inhaled aerosol as well as by personal characteristics. Both the properties of the exposed individual as well as of the inhaled environmental atmosphere have to be considered in radiation protection. It is the main objective of this paper to illustrate the influence of both parameter sets on basal cell doses by varying the above parameters

  16. Calibration of individual dosemeters by using external beams of photon radiation. A nationwide survey among Personal Dosimetry Services, authorized by CSN

    International Nuclear Information System (INIS)

    A nationwide survey in 1995 among Personal Dosimetry Services, authorized by the Spanish Nuclear Safety Council (CSN), has led the Spanish Dosimetry Laboratories to review and update the dosimetric conversion coefficients and correction factors in use in Spain since 1987. The recommendations of the ICRU Report 47(1992) are discussed and adopted. In addition differences in back-scattering form IRCU tissue and PMMA phantoms are analysed. Analytical functions used to calculate conversion coefficients and back-scattering correction factors due to the use of different phantom materials are presented, together with the adopted final values. Firstly, the above mentioned parameters are applied to ISO narrow spectra series, which are discribed in this report. Secondly, differences between 1995 and 1987 values are also shown. (Author)

  17. Development of a dosimetry system for personal monitoring in mixed beta and gamma field

    International Nuclear Information System (INIS)

    A dosimetric thermoluminescent system for the determination of strongly and weakly penetrating radiation dose Hp(10) and Hp(0,07), respectively, was developed. The system consists of CaSO4:Dy as T L active material, a polyethylene badge and different metallic filters used for radiation attenuation. For the system development and design parameter calculation different computer codes were used. After the definition of the dosemeter an experimental validation of the whole system was performed. The research was directed towards the optimization of the design parameters. The determination of the energy deposited by beta and gamma radiations in the dosimetric material as a function of chemical composition and densities was calculated using computer codes that simulate those process. The dosemeter calibration was performed in standard fields. The angular dependency of T L response and its behavior in a mixed field was studied. The validation of the dosimetric system was performed for beta nad gamma radiations doses between 0,1 mSv and 200 MSv. Ana analysis of associated uncertainties shows that the developed dosemeters are in accordance with the ICRP-35 requirements of energetic and angular dependence for personal dosemeters. (author)

  18. Improving the Success Rate of Delivering Annual Occupational Dosimetry Reports to Persons Issued Temporary External Dosimeters

    Energy Technology Data Exchange (ETDEWEB)

    Mallett, Michael Wesley [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-09-09

    Workers who are not routinely monitored for occupational radiation exposure at LANL may be issued temporary dosimeters in the field. Per 10CFR835 and DOE O 231.1A, the Laboratory's radiation protection program is responsible for reporting these results to the worker at the end of the year. To do so, the identity of the worker and their mailing address must be recorded by the delegated person at the time the dosimeter is issued. Historically, this data has not been consistently captured. A new online application was developed to record the issue of temporary dosimeters. The process flow of the application was structured such that: 1) the worker must be uniquely identified in the Lab's HR database, and 2) the mailing address of record is verified live time via a commercial web service, for the transaction to be completed. A COPQ savings (Type B1) of $96K/year is demonstrated for the new application.

  19. Suitability of CR-39 dosimeters for personal dosimetry around CANDU reactors

    International Nuclear Information System (INIS)

    The capabilities and limitations of CR-39 damage track detectors have been evaluated for their use as personal neutron dosimeters around CANDU reactors. Since the energy response is a critical characteristic, the neutron energy spectra expected within CANDU containments were studied. In the boiler rooms, around the moderator cooling systems, and in most of the fueling machine vaults, the spectra vary considerably, but the majority of the dose is expected to be delivered by neutrons above 80 keV, the approximate threshold for electrochemically-etched CR-39 detectors. In the Pickering A fueling machine vault, and in areas in other stations to which neutrons from reactors have been multiply scattered, lower energy neutrons may be important. In nearly all areas where people work, it appears that working times will be limited by gamma rays rather than by neutrons. The characteristics of other neutron dosimeters - bubble and superheated drop detectors, albedo detectors, and Si real-time detectors - were also reviewed. For workers who typically receive neutron doses that are small compared with regulatory limits, CR-39 is the most suitable available dosimeter for demonstrating compliance. All single dosimeters have poor angular response over the range 0 to 180 degrees because of the shielding of the body. Albedo and Si detectors have particularly poor energy responses over the energy range of importance. Bubble and superheated drop detectors have the advantages of immediate readout and high sensitivity, but the disadvantages of inability to integrate doses over a long period, temperature dependence, very limited range and higher cost. (Author) (110 refs., 45 figs.)

  20. Guidance on the use of protective lead aprons in medical radiology protection efficiency and correction factors for personal dosimetry

    International Nuclear Information System (INIS)

    Workers in clinical radiology wear lead aprons when standing in the vicinity of a patient being exposed to x-rays. A lead apron protects the person's trunk against radiation scattered rom the patient. Our research is focused on two main issues: 1. How much protection does a lead apron provide, and what are the main factors that determine the protection efficiency 2. How can measured badge dose be translated into a realistic estimate of the effective dose, and how does this depend on dosemeter placement Using a model for x-ray shielding and dosimetry we calculated equivalent organ doses and personal depth dose HP(10) for various exposure conditions, x-ray energies and types of aprons that occur in clinical practice. We concluded that apron model and fit are often more important than lead thickness. In others, increasing lead thickness of a badly chosen apron will not provide better protection. For many fluoroscopy applications an apron of good model and fit need not be thicker than 0.5 mm of lead (equivalent). In case of intensive and frequent interventional work lead we advise higher lead thickness (0.35 mm), and preferably additional neck shielding for protection of the oesophagus and thyroid. A well chosen lead apron reduces effective dose by 75%up to 90%. We also concluded that the dosemeter badge should always be worn outside the apron, at mid front of collar or chest. In our view this dosemeter position enables reliable evaluation of effective dose from badge readings. As a standard practice we recommend translating measured badge dose to effective dose by dividing by a factor of five, provide that the worker wears a suitable lead apron. Finally, some research was done on the subject of the protective effect of lead aprons for the uterus, and the relation of uterus dose and badge dose. Use of a lead apron is found to reduce uterus dose by a factor of 5 to 10. Our study shows that in case of worker pregnancy, exposure of the unborn child may de adequately

  1. Use of epr-dosimetry of dental enamel for persons exposed to radiation due to the Chernobyl accident

    International Nuclear Information System (INIS)

    Technique of epr-dosimetry of dental enamel enabling to measure the accumulated dose equivalents of the external irradiation with the accuracy equal to several sGr limits is studied. The PC code enabling to standardize the spectra processing is elaborated. The code is rather reliable and may be used when elaborating the methodical provision of the activity of the dosimetric services directed to determine the accumulated dose equivalents of the external irradiation using the dental enamel epr-dosimetry technique, in particular, in cases of people affected by the Chernobyl accident

  2. Development of an automated speech recognition interface for personal emergency response systems

    Directory of Open Access Journals (Sweden)

    Mihailidis Alex

    2009-07-01

    Full Text Available Abstract Background Demands on long-term-care facilities are predicted to increase at an unprecedented rate as the baby boomer generation reaches retirement age. Aging-in-place (i.e. aging at home is the desire of most seniors and is also a good option to reduce the burden on an over-stretched long-term-care system. Personal Emergency Response Systems (PERSs help enable older adults to age-in-place by providing them with immediate access to emergency assistance. Traditionally they operate with push-button activators that connect the occupant via speaker-phone to a live emergency call-centre operator. If occupants do not wear the push button or cannot access the button, then the system is useless in the event of a fall or emergency. Additionally, a false alarm or failure to check-in at a regular interval will trigger a connection to a live operator, which can be unwanted and intrusive to the occupant. This paper describes the development and testing of an automated, hands-free, dialogue-based PERS prototype. Methods The prototype system was built using a ceiling mounted microphone array, an open-source automatic speech recognition engine, and a 'yes' and 'no' response dialog modelled after an existing call-centre protocol. Testing compared a single microphone versus a microphone array with nine adults in both noisy and quiet conditions. Dialogue testing was completed with four adults. Results and discussion The microphone array demonstrated improvement over the single microphone. In all cases, dialog testing resulted in the system reaching the correct decision about the kind of assistance the user was requesting. Further testing is required with elderly voices and under different noise conditions to ensure the appropriateness of the technology. Future developments include integration of the system with an emergency detection method as well as communication enhancement using features such as barge-in capability. Conclusion The use of an automated

  3. 3D-personalized Monte Carlo dosimetry in 90Y-microspheres therapies of primary and secondary hepatic cancers: absorbed dose and biological effective dose considerations

    International Nuclear Information System (INIS)

    Full text of publication follows. Purpose: a 3D-Personalized Monte Carlo Dosimetry (PMCD) was developed for treatment planning in nuclear medicine. The method was applied to Selective Internal Radiation Therapy (SIRT) using 90Y-microspheres for unresectable hepatic cancers. Methods: The PMCD method was evaluated for 20 patients treated for hepatic metastases or hepatocellular carcinoma at the European Hospital Georges Pompidou (Paris). First, regions of interest were outlined on the patient CT images. Using the OEDIPE software, patient-specific voxel phantoms were created. 99mTc-MAA SPECT data were then used to generate 3D-matrices of cumulated activity. Absorbed doses and Biologically Effective Dose (BED) were calculated at the voxel scale using the MCNPX Monte Carlo transport code. Finally, OEDIPE was used to determine the maximum injectable activity (MIA) for tolerance criteria on organs at risk (OARs), i.e. the lungs and non tumoral liver (NTL). Tolerance criteria based on mean absorbed doses, mean BED, Dose-Volume Histograms (DVHs) or BED-Volume Histograms (BVHs) were considered. Those MIAs were compared to the Partition Model with tolerance criteria on mean absorbed doses, which is a conventional method applied in clinical practice. Results: compared to Partition Model recommendations, performing dosimetry using the PMCD method enables to increase the activity prescription while ensuring OARs' radiation protection. Moreover, tolerance criteria based on DVHs allow us to enhance treatment planning efficiency by taking advantage of the parallel characteristic of the liver and the lungs, whose functions are not impaired if the level of irradiation to a fraction of the organ is kept sufficiently low. Finally, multi-cycle treatments based on tolerance criteria on mean BED and BVHs, were considered to go further in the dose optimization, taking into account biological considerations such as cell repair or radiosensitivity. Conclusion: besides its feasibility

  4. Accreditation of the Personal Dosimetry internal Service Tecnatom by the National Entity (ENAC); Acreditacion del Servicio de Dosimetria Personal Interna de Tecnatom por la Entidad Nacional de Acreditacion (ENAC)

    Energy Technology Data Exchange (ETDEWEB)

    Bravo, B.; Marchena, P.

    2014-07-01

    The service of personal Dosimetry internal Tecnatom has made the process of adapting its methodology and quality assurance, requirements technical and management will be required to obtain accreditation from the National Accreditation Entity according to ISO / IEC 170251 standard {sup G}eneral Requirements competence of testing and calibration laboratories. To carry out this process, the laboratory has defined quality criteria set out in their test procedures, based on ISO Standards 27048: 2011; ISO 20553: 2005 and ISO 28218: 2010. This paper describes what has been the methodology used to implement the requirements of different ISO test methods of SDPI Tecnatom. (Author)

  5. Exposure to mobile telecommunication networks assessed using personal dosimetry and well-being in children and adolescents: the German MobilEe-study

    Directory of Open Access Journals (Sweden)

    von Kries Rüdiger

    2008-11-01

    Full Text Available Abstract Background Despite the increase of mobile phone use in the last decade and the growing concern whether mobile telecommunication networks adversely affect health and well-being, only few studies have been published that focussed on children and adolescents. Especially children and adolescents are important in the discussion of adverse health effects because of their possibly higher vulnerability to radio frequency electromagnetic fields. Methods We investigated a possible association between exposure to mobile telecommunication networks and well-being in children and adolescents using personal dosimetry. A population-based sample of 1.498 children and 1.524 adolescents was assembled for the study (response 52%. Participants were randomly selected from the population registries of four Bavarian (South of Germany cities and towns with different population sizes. During a Computer Assisted Personal Interview data on participants' well-being, socio-demographic characteristics and potential confounder were collected. Acute symptoms were assessed three times during the study day (morning, noon, evening. Using a dosimeter (ESM-140 Maschek Electronics, we obtained an exposure profile over 24 hours for three mobile phone frequency ranges (measurement interval 1 second, limit of determination 0.05 V/m for each of the participants. Exposure levels over waking hours were summed up and expressed as mean percentage of the ICNIRP (International Commission on Non-Ionizing Radiation Protection reference level. Results In comparison to non-participants, parents and adolescents with a higher level of education who possessed a mobile phone and were interested in the topic of possible adverse health effects caused by mobile telecommunication network frequencies were more willing to participate in the study. The median exposure to radio frequency electromagnetic fields of children and adolescents was 0.18% and 0.19% of the ICNIRP reference level respectively

  6. Personalized Monte Carlo dosimetry for the planning and evaluation of internal radiotherapy treatments: development and application to selective internal radiotherapy (SIRT)

    International Nuclear Information System (INIS)

    Medical techniques in full expansion arousing high therapeutic expectations, targeted radionuclide therapies (TRT) consist of administering a radiopharmaceutical to selectively treat tumors. Nowadays, the activity injected to the patient is generally standardized. However, in order to establish robust dose-effect relationships and to optimize treatments while sparing healthy tissues at best, a personalized dosimetry must be performed, just like actual clinical practice in external beam radiotherapy. In that context, this PhD main objective was to develop, using the OEDIPE software, a methodology for personalized dosimetry based on direct Monte Carlo calculations. The developed method enables to calculate the tridimensional distribution of absorbed doses depending on the patient anatomy, defined from CT or MRI data, and on the patient-specific activity biodistribution, defined from SPECT or PET data. Radiobiological aspects, such as differences in radiosensitivities and repair time constants between tumoral and healthy tissues, have also been integrated through the linear-quadratic model. This methodology has been applied to the selective internal radiation therapy (SIRT) which consists in the injection of 90Y-microspheres to selectively treat unresectable hepatic cancers. Distributions of absorbed doses and biologically effective doses (BED) along with the equivalent uniform biologically effective doses (EUD) to hepatic lesions have been calculated from 99mTc-MAA activity distributions obtained during the evaluation step for 18 patients treated at Hopital Europeen Georges Pompidou. Those results have been compared to classical methods used in clinics and the interest of accurate and personalized dosimetry for treatment planning has been investigated. On the one hand, the possibility to increase the activity in a personalized way has been highlighted with the calculation of the maximal activity that could be injected to the patient while meeting tolerance criteria

  7. Miniature semiconductor detectors for in vivo dosimetry

    International Nuclear Information System (INIS)

    Silicon mini-semiconductor detectors are found in wide applications for in vivo personal dosimetry and dosimetry and Micro-dosimetry of different radiation oncology modalities. These applications are based on integral and spectroscopy modes of metal oxide semiconductor field effect transistor and silicon p-n junction detectors. The advantages and limitations of each are discussed. (authors)

  8. Dosimetry and Calibration Section

    International Nuclear Information System (INIS)

    The Dosimetry and Calibration Section fulfils two tasks within CERN's Radiation Protection Group: the Individual Dosimetry Service monitors more than 5000 persons potentially exposed to ionizing radiation on the CERN sites, and the Calibration Laboratory verifies throughout the year, at regular intervals, over 1000 instruments, monitors, and electronic dosimeters used by RP Group. The establishment of a Quality Assurance System for the Individual Dosimetry Service, a requirement of the new Swiss Ordinance for personal dosimetry, put a considerable workload on the section. Together with an external consultant it was decided to identify and then describe the different 'processes' of the routine work performed in the dosimetry service. The resulting Quality Manual was submitted to the Federal Office for Public Health in Bern in autumn. The CERN Individual Dosimetry Service will eventually be officially endorsed after a successful technical test in March 1999. On the technical side, the introduction of an automatic development machine for gamma films was very successful. It processes the dosimetric films without an operator being present, and its built-in regeneration mechanism keeps the concentration of the processing chemicals at a constant level

  9. 'Au.Raex': An Automated, Long Lasting Exposimeter for Monitoring Persons with Increased Radon-Exposure

    International Nuclear Information System (INIS)

    Within this framework, the automated radon exposimeter 'au.raex' improves the long-established method of radon exposure measurements using nuclear track detectors in a decisive method. Unlike conventional nuclear track exposimeters this radon measurement is switchable. By movement recognition the exposition is constrained automatically to the period in which it is actually worn, the exposition time is captured automatically. Despite these advantages, it is comfortable to wear au.raex. It has roughly the dimensions of a cigarette box. Used as a time-controlled ambient exposimeter it captures only the radon expositions during relevant and defined periods. The timing control has been implemented in form of a complete calendar. Thus, the on-and off separately for each weekday, as well as public holidays and holiday periods are defined, in which the detector, against the rule, remains completely closed. Data evaluation and programming are performed using the USB port and software on a computer. The switchability of the measurement is achieved by a movable slide at a small distance above the detector film. Both movement- and time-depended control of the closure are optimized for low electronic energy consumption. The 'au.raex' is applicable for measuring campaigns lasting about several years, without the need to charge the device or further maintenance. Calibration as well as the practical testing of 'au.raex' were made by the Radon Laboratory of Karlsruhe Institute of Technology KIT using their own nuclear track films and evaluation process. To validate the operation of the instrument, measurements are to be performed on persons with known increased radon exposure.(author)

  10. Progress towards the development of a personal neutron dosimetry system based on the chemical etch of CR39

    International Nuclear Information System (INIS)

    A brief historical review of systems used for monitoring individual neutron dose underlines the significance of the discovery that the plastic CR39 can be used to detect protons, and hence form the basis of a great improvement in neutron dosimetry. Proton tracks are revealed by etching the CR39 plastic in a hot concentrated caustic solution. First studies at BNL into the fundamental etch characteristics of commercially available CR39 showed that ''dosimetry grade'' material would be required with a low density of spurious etch pits and reproducible etch characteristics. This is now commercially available. There was also a requirement for a simple system which would give a rapid estimate of the number of etch pits with diameters less than 6 μm over areas of order one square centimetre. Many possible systems were studied. The one shown to be most effective is based on side illumination of the CR39 sample which is then viewed by a videcon tube through a low-power microscope. The etch pit images which are effectively magnified by the videcon tube are counted by an inexpensive automatic image analysis system in less than one second. The thermal neutron sensitive CR39 is ideal for use as the detecting element in an albedo dosimetry system. This implies that a single dosemeter, of size comparable with the present film badge can be used to detect thermal, intermediate and fast neutrons: the measurement of which currently requires two separate dosemeters. (author)

  11. Radiation dosimetry

    CERN Document Server

    Hine, Gerald J; Hine, Gerald J

    1956-01-01

    Radiation Dosimetry focuses on the advancements, processes, technologies, techniques, and principles involved in radiation dosimetry, including counters and calibration and standardization techniques. The selection first offers information on radiation units and the theory of ionization dosimetry and interaction of radiation with matter. Topics include quantities derivable from roentgens, determination of dose in roentgens, ionization dosimetry of high-energy photons and corpuscular radiations, and heavy charged particles. The text then examines the biological and medical effects of radiation,

  12. Development of a personal dosimetry system based on optically stimulated luminescence of α-Al2O3 : C for mixed radiation fields

    International Nuclear Information System (INIS)

    To develop a personal (OSL) optically stimulated luminescence dosimetry system for mixed radiation fields using α-Al2O3 : C, a discriminating badge filter system was designed by taking advantage of its optically stimulable properties and energy dependencies. This was done by designing a multi-element badge system for powder layered α-Al2O3 : C material and an optical reader system based on high-intensity blue light-emitting diode (LED). The design of the multi-element OSL dosimeter badge system developed allows the measurement of a personal dose equivalent value Hp(d) in mixed radiation fields of β and γ. Dosimetric properties of the personal OSL dosimeter badge system investigated here were the dose response, energy response and multi-readability. Based on the computational simulations and experiments of the proposed dosimeter design, it was demonstrated that a multi-element dosimeter system with an OSL technology based on α-Al2O3 : C is suitable to obtain personal dose equivalent information in mixed radiation fields

  13. Dosimetry Service

    CERN Multimedia

    2004-01-01

    We wish to remind the people who are invited to the dosimetry service to exchange the new CERN dosimeter that the hours are from Monday to Friday 8.30 to 11.00 and 14.00 to 16.00. http://service-rp-dosimetry.web.cern.ch/service-rp-dosimetry/

  14. Dosimetry Service

    CERN Multimedia

    2006-01-01

    Cern Staff and Users can now consult their dose records for an individual or an organizational unit with HRT. Please see more information on our web page: http://cern.ch/rp-dosimetry Dosimetry Service is open every morning from 8.30 - 12.00. Closed in the afternoons. We would like to remind you that dosimeters cannot be sent to customers by internal mail. Short-term dosimeters (VCT's) must always be returned to the Service after the use and must not be left on the racks in the experimental areas or in the secretariats. Dosimetry Service Tel. 7 2155 Dosimetry.service@cern.ch http://cern.ch/rp-dosimetry

  15. Dosimetry of extremities in health personnel of interventionist radiology and nuclear medicine; Dosimetria de extremidades en personal sanitario de radiologia intervencionista y medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ginjaume, M.; Perez, S.; Carnicer, A.; Ortega, X.; Tormo, M.L.; Amor, I.; Rodriguez, M.

    2011-07-01

    Monitoring of workers constitutes an important part of any radiological protection program. In some medical applications of radiation, such as nuclear medicine and interventional radiology, there is a high risk of receiving locally high exposures in the hands. This paper presents the main results of a measurement campaign of extremely dosimetry. The results confirm the need to introduce routine extremely monitoring. In addition it is shown that on general basis, the ring dosemeter is preferred to the wrist dosemeter, in particular for nuclear medicine. In the field of interventional radiology, the surgeon located at distances closer to the beam is the person who receives higher doses. Biliary drainage is the type of intervention for which higher values were recorded. Among the analyzed nuclear medicine procedures, the preparation of PET radiopharmaceuticals was found to be one which entailed higher skin equivalent dose per unit of handled activity. (Author). 9 refs.

  16. Establishment of ANSI N13.11 X-ray radiation fields for personal dosimetry performance test by computation and experiment.

    Science.gov (United States)

    Kim, J L; Kim, B H; Chang, S Y; Lee, J K

    1997-12-01

    This paper describes establishment by computational and experimental methods of the American National Standard Institute (ANSI) N13.11 X-ray radiation fields by the Korea Atomic Energy Research Institute (KAERI). These fields were used in the standard irradiations of various personal dosimeters for the personal dosimetry performance test program performed by the Ministry of Science and Technology of Korea in the autumn of 1995. Theoretical X-ray spectra produced from two KAERI X-ray generators were estimated using a modified Kramers' theory with target attenuation and backscatter correction and their spectral distributions experimentally measured by a high-purity germanium semiconductor detector through proper corrections for measured pulse height distributions with photopeak efficiency, Compton fraction, and K-escape fraction. The average energies and conversion coefficients obtained from the computation and experimental methods, when compared with ANSI N13.11 and the recently published National Institute of Standards and Technology X-ray beams, appeared to be in good agreement--(+/-)3% between corresponding values--and thus, could be satisfactorily applied in the performance test of personal dosimeters. PMID:9467054

  17. Establishing a minimum reporting level (gamma) for the personal dosimetry device worn at the Idaho National Engineering Laboratory (INEL)

    International Nuclear Information System (INIS)

    The report evaluated various approaches to defining a minimum reporting level (MRL) for personnel thermoluminescent dosimetry (TLS) systems. The evaluations include the traditional statically-based approaches, using lower limit of detection and critical level as well as several unique approaches developed as part of the study. The advantages and disadvantages of each technique are discussed with the conclusion that none of the statistically based methods satisfy the need to provide accurate low-level data without being overwhelmed with apparent false positive values. A unique approach is presented on the premise of optimizing the accuracy of the total monitored dose. This approach requires the analysis of the distribution of TLD results around zero and provides some insight into the performance of TLD systems at very low dose values

  18. Radio-analysis. Applications: biological dosimetry

    International Nuclear Information System (INIS)

    Radioisotopes have revolutionized the medical biology. Radio-immunology remains the reference measurement of the infinitely small in biology. Constant efforts have been performed to improve the simpleness, detectability and fastness of the method thanks to an increasing automation. This paper presents: 1 - the advantages of compounds labelling and the isotopic dilution; 2 - the antigen-antibody system: properties, determination of the affinity constant using the Scatchard method; 3 - radio-immunologic dosimetry: competitive dosimetry (radioimmunoassay), calibration curve and mathematical data processing, application to the free thyroxine dosimetry, immunoradiometric dosimetry (immunoradiometric assay), evaluation of the analytical efficiency of a radioimmunoassay; 4 - detection of the radioactive signal (solid and liquid scintillation). (J.S.)

  19. Report of results of the tests of evaluation of the operation of service of personal dosimetry of the CNLV; Informe de resultados de las pruebas de evaluacion del funcionamiento de servicio de dosimetria personal de la CNLV

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez R, J.T.; Tovar M, V.M. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2005-11-15

    The ININ realized the evaluation of the service of personal dosimetry in the CNLV, in the categories: IV.- (Photons of high energy of {sup 137}Cs) and the VA.- (Particles beta of {sup 90}Sr/{sup 90}Y); in the category IV the test was satisfactory, however in the chart 1 has an underestimation a the American Standard HP over the value true conventional of a 9%; for this irregularity it is recommended to revise the procedures of evaluation of the process and the determination of the chart 1 of the HP. In the category VA, the test is also satisfactory, however the results contrasted with the chart 2 and the HP, the values were overestimated in 29% of the true conventional value, and for that problem is recommended to revise the evaluation procedures in contrast with the values determined by the standard HP. (Author)

  20. ESR Dosimetry

    International Nuclear Information System (INIS)

    ESR dosimetry is widely used for several applications such as dose assessment in accidents, medical applications and sterilization of food and other materials. In this work the dosimetric properties of natural and synthetic Hydroxyapatite, Alanine, and 2-Methylalanine are presented. Recent results on the use of a K-Band (24 GHz) ESR spectrometer in dosimetry are also presented

  1. Neutron dosimetry

    International Nuclear Information System (INIS)

    A neutron irradiation facility was designed and built in order to establish a procedure for calibrating neutron monitors and dosemeters. A 185 GBq 241 Am Be source of known is used as a reference source. The irradiation facility using this source in the air provides neutron dose rates between 9 nSv s-1 and 0,5 μSv s-1. A calibrated 50 nSv s-1 thermal neutron field is obtained by using a specially designed paraffin block in conjunction with the 241 Am Be source. A Bonner multisphere spectrometer was calibrated, using a procedure based on three methods proposed by international standards. The unfold 241 Am Be neutron spectrum was determined from the Bonner spheres data and resulted in a good agreement with expected values for fluence rate, dose rate and mean energy. A dosimetric system based on the electrochemical etching of CR-39 was developed for personal dosimetry. The dosemeter badge using a (n,α) converter, the etching chamber and high frequency power supply were designed and built specially for this project. The electrochemical etching (ECE) parameters used were: a 6N KOH solution, 59 deg C, 20 kVpp cm-1, 2,0 kHz, 3 hours of ECE for thermal and intermediate neutrons and 6 hours for fast neutrons. The calibration factors for thermal, intermediate and fast neutrons were determined for this personal dosemeter. The sensitivities determined for the developed dosimetric system were (1,46± 0,09) 104 tracks cm-2 mSv-1 for thermal neutrons, (9±3) 102 tracks cm-2 mSV-1 for intermediate neutrons and (26±4) tracks cm-2 mSv-1 for fast neutrons. The lower and upper limits of detection were respectively 0,002 mSv and 0,6 mSv for thermal neutrons, 0,04 mSv and 8 mSv for intermediate neutrons and 1 mSv and 12 mSv for fast neutrons. In view of the 1990's ICRP recommendations, it is possible to conclude that the personal dosemeter described in this work is sufficiently sensitive to thermal and intermediate neutrons but fast neutron monitoring ar radiological protection level

  2. Internal dosimetry technical basis manual

    International Nuclear Information System (INIS)

    The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs

  3. Results of the dosimetry intercomparison

    International Nuclear Information System (INIS)

    The appropriate way to verify the accuracy of the results of dose reported by the laboratories that offer lend personal dosimetry service is in the periodic participation of round of intercomparison dosimetry, undertaken by laboratories whose standards are trace (Secondary Laboratory). The Laboratory of External Personal Dosimetry of the CNEA-PY has participated in three rounds of intercomparison. The first two were organized in the framework of the Model Project RLA/9/030 RADIOLOGICAL WASTE SECURITY, and the irradiations were carried out in the Laboratory of Regional Calibration of the Center of Nuclear Technology Development, Belo Horizonte-Brazil (1998) and in the National Laboratory of Metrology of the ionizing radiations of the Institute of Radioprotection and Dosimetry, Rio de Janeiro-Brazil (1999). The third was organized by the IAEA and the irradiations were made in the Physikalisch-Technische Bundesanstalt PTB, Braunschweig - Federal Republic of Germany (1999-2000)

  4. Internal dosimetry technical basis manual

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-20

    The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs.

  5. A new laser thermoluminescence dosimetry system for the determination of the personal dose equivalent Hp(10) and the irradiation condition

    International Nuclear Information System (INIS)

    For the purpose of radiation protection additional information about the irradiation conditions may be important if a personal dose above a specified threshold is detected. The objective of the development of a new personal dosemeter therefore is to determine the personal dose equivalent with the necessary accuracy and, also, to provide information about the irradiation conditions. To fulfill these requirements, a new laser-heated TL dosemeter (TLD) system, commercially available and produced by International Sensor Technology Inc. has been modified. A new algorithm based on linear programming is applied to improve the dose determination. A TL-sheet is inserted into the dosemeter badge to allow information to be obtained about the irradiation conditions. (author)

  6. Comparison of radiation doses obtained for radiation monitoring of controlled areas with radiation doses obtained for personnel dosimetry in radiodiagnosis centers; Comparacion de dosis obtenidas por monitoreo en areas controladas con las obtenidas por dosimetria personal en centros de radiodiagnostico

    Energy Technology Data Exchange (ETDEWEB)

    Lescano, Roberto; Caspani, Carlos [Ministerio de Salud y Medio Ambiente, Santa Fe (Argentina). Direccion General de Auditoria Medica. Radiofisica Sanitaria]|[Universidad Nacional del Litoral, Santa Fe (Argentina). Faculdad de Bioquimica y Ciencias Biologicas. Escuela Superior de Sanidad

    2001-07-01

    In this paper we propose to search an indicator that shows, at an objective way, the quality of the radioprotection actions. The method is about to determine doses, measured in the work area, connecting them with the workload, and finally get the dose for the center. Them we make a comparison with the personal film dosimetry data. We discuss the final results, evaluating the radioprotection conditions in daily work. (author)

  7. Type tests to the automatic thermoluminescent dosimetry system acquired by the CPHR for personal dosimetry; Pruebas tipo al sistema de dosimetria termoluminiscente automatico adquirido por el CPHR para dosimetria personal

    Energy Technology Data Exchange (ETDEWEB)

    Molina P, D.; Pernas S, R.; Martinez G, A. [Centro de Proteccion e Higiene de las Radiaciones (CPHR), Calle 20 No. 4113 e/41 y 47. Playa, C.P. 11300, A.P. 6195, C.P. 10600 La Habana (Cuba)

    2006-07-01

    The CPHR individual monitoring service acquired an automatic RADOS TLD system to improve its capacities to satisfy the increasing needs of their national customers. The TLD system consists of: two automatic TLD reader, model DOSACUS, a TLD irradiator and personal dosimeters card including slide and holders. The dosimeters were composed by this personal dosimeters card and LiF:Mg,Cu,P (model GR-200) detectors. These readers provide to detectors a constant temperature readout cycle using hot nitrogen gas. In order to evaluate the performance characteristics of the system, different performance tests recommended by the IEC 1066 standard were carried out. Important dosimetric characteristics evaluated were batch homogeneity, reproducibility, detection threshold, energy dependence, residual signal and fading. The results of the tests showed good performance characteristics of the system. (Author)

  8. Dosimetry and Calibration Section

    International Nuclear Information System (INIS)

    The two tasks of the Dosimetry and Calibration Section at CERN are the Individual Dosimetry Service which assures the personal monitoring of about 5000 persons potentially exposed to ionizing radiation at CERN, and the Calibration Laboratory which verifies all the instruments and monitors. This equipment is used by the sections of the RP Group for assuring radiation protection around CERN's accelerators, and by the Environmental Section of TISTE. In addition, nearly 250 electronic and 300 quartz fibre dosimeters, employed in operational dosimetry, are calibrated at least once a year. The Individual Dosimetry Service uses an extended database (INDOS) which contains information about all the individual doses ever received at CERN. For most of 1997 it was operated without the support of a database administrator as the technician who had assured this work retired. The Software Support Section of TIS-TE took over the technical responsibility of the database, but in view of the many other tasks of this Section and the lack of personnel, only a few interventions for solving immediate problems were possible

  9. A whole-body dosimetry system for personal monitoring based on hot-pressed thin layer TLD.

    Science.gov (United States)

    Busch, F; Engelhardt, J; Martini, E; Lesz, J

    2011-03-01

    We are introducing a new high-capacity thermoluminescent dosemeter (TLD) system to measure the whole body values of H(p)(10) and H(p)(0.07) from photons for use in individual monitoring services. Small and light-weight badges allow a convenient application in a wide variety of workplaces with photon radiation from 20 keV to at least 7 MeV. The main advantage of this system will be the large capacity of ∼ 100,000 dosemeters per month at costs equivalent to the current film monitoring. The hot-pressed thin-layer TL detector (LiF:Mg,Ti) is welded onto an aluminium substrate and provided with a data matrix code for automatic processing. The detector holder has been optimised, that no additional filter is necessary. The new designed TLD reader with readout times <10 s will allow a large throughput and a considerable degree of automation. PMID:21227958

  10. A whole-body dosimetry system for personal monitoring based on hot-pressed thin layer TLD

    International Nuclear Information System (INIS)

    We are introducing a new high-capacity thermoluminescent dosemeter (TLD) system to measure the whole body values of Hp(10) and Hp(0.07) from photons for use in individual monitoring services. Small and light-weight badges allow a convenient application in a wide variety of workplaces with photon radiation from 20 keV to at least 7 MeV. The main advantage of this system will be the large capacity of ∼100 000 dosemeters per month at costs equivalent to the current film monitoring. The hot-pressed thin-layer TL detector (LiF:Mg,Ti) is welded onto an aluminium substrate and provided with a data matrix code for automatic processing. The detector holder has been optimised, that no additional filter is necessary. The new designed TLD reader with readout times <10 s will allow a large throughput and a considerable degree of automation. (authors)

  11. Person-like intelligent systems architectures for robotic shared control and automated operations

    Science.gov (United States)

    Erickson, Jon D.; Aucoin, Paschal J., Jr.; Ossorio, Peter G.

    1992-01-01

    An approach to rendering robotic systems as 'personlike' as possible to achieve needed capabilities is outlined. Human characteristics such as knowledge, motivation, know-how, performance, achievement and individual differences corresponding to propensities and abilities can be supplied, within limits, with computing software and hardware to robotic systems provided with sufficiently rich sensory configurations. Pushing these limits is the developmental path for more and more personlike robotic systems. The portions of the Person Concept that appear to be most directly relevant to this effort are described in the following topics: reality concepts (the state-of-affairs system and descriptive formats, behavior as intentional action, individual persons (person characteristics), social patterns of behavior (social practices), and boundary conditions (status maxims). Personlike robotic themes and considerations for a technical development plan are also discussed.

  12. Characterization of an automatic TLD system based on LiF:Mg, Cu, P (GR-200) detectors for personal dosimetry

    International Nuclear Information System (INIS)

    Full text: The CPHR individual monitoring service acquired an automatic RADOS TLD system to improve its capacities to satisfy the increase of their national customers. The TLD system consists of two automatic TLD reader, model DOSACUS, a TLD irradiator and personal dosimeters card including slide and holders. The dosimeters were composed by this personal dosimeters card and LiF:Mg, Cu, P (model GR-200) detectors. These readers provide to detectors a constant temperature readout cycle using hot nitrogen gas. In order to evaluate the performance characteristics of the system, different performance tests recommended by the IEC 1066 standard were carried out. Important dosimetric characteristics evaluated were batch homogeneity, reproducibility, detection threshold, energy dependence, residual signal and fading. The results of the tests showed good performance characteristics of the system. (author)

  13. Using Personal Health Records for Automated Clinical Trials Recruitment: the ePaIRing Model

    OpenAIRE

    Wilcox, Adam; Natarajan, Karthik; Weng, Chunhua

    2009-01-01

    We describe the development of a model describing the use of patient information to improve patient recruitment in clinical trials. This model, named ePaIRing (electronic Participant Identification and Recruitment Model) describes variations in how information flows between stakeholders, and how personal health records can specifically facilitate patient recruitment.

  14. Dosimetry methods

    DEFF Research Database (Denmark)

    McLaughlin, W.L.; Miller, A.; Kovacs, A.; Mehta, K. K.

    Chemical and physical radiation dosimetry methods, used for the measurement of absorbed dose mainly during the practical use of ionizing radiation, are discussed with respect to their characteristics and fields of application.......Chemical and physical radiation dosimetry methods, used for the measurement of absorbed dose mainly during the practical use of ionizing radiation, are discussed with respect to their characteristics and fields of application....

  15. Quality assurance and quality control programme in the personal dosimetry department of the Greek Atomic Energy Commission

    International Nuclear Information System (INIS)

    A quality assurance (QA) and quality control (QC) programme was applied to the personal monitoring department (TLD based) of the Greek Atomic Energy Commission. This programme was designed according to the recommendations of international bodies such as the International Organization for Standardization, the International Electrotechnical Commission, the International Atomic Energy Agency and the European Commission. This paper deals with the presentation of the QA/QC programme which includes administrative data and information, technical checking of the equipment, acceptance tests of new equipment and dosemeters, issuing and processing of the dosemeters, dose evaluation, record keeping and reporting, traceability and reproducibility, handling of complaints, internal reviews and external audits. (author)

  16. For information: Individual dosimetry service

    CERN Multimedia

    2004-01-01

    The service has noticed that there are dosimeter holders who have changed their activities and thus have no longer need of dosimeter as a permanent basis in their work (persons who go rarely to the controlled areas). The reduction of persons in the regular distribution list of dosimeters will lighten the work of the service (distribution, evaluation and consolidation of doses) as well as the work of the distributors, needless to say the economical input this would have for CERN. For the persons who only need a dosimeter temporarily we would like to remind that there is a quick and simple procedure to have one immediately from the Individual Dosimetry Service. Please contact the service (dosimetry.service@cern.ch) if you do not need a dosimeter regularly. Thank you for your cooperation. http://cern.ch/rp-dosimetry

  17. European Crew Personal Active Dosimeter (EuCPAD), a novel dosimetry system utilizing operational and scientific synergies for the benefit of humans in space

    Science.gov (United States)

    Straube, Ulrich; Berger, Thomas

    A significant expansion of Human presence in space can be recognized over the last decade. Not only the frequency of human space mission did rise, but also time in space, mission duration with extended flights lasting half a year or more are becoming "standard". Despite the challenges to human health and well-being are still significant, or may even increase with mission length and work density. Also radiation exposure in space remains one of the inevitable and dominating factors relevant to crew- health, -safety and therefore mission success. The radiation environment that the space crews are exposed to differs significantly as compared to earth. Exposure in flight exceed doses that are usually received by terrestrial radiation workers on ground. Expanding "medical" demands are not a solely characteristics of current and current and upcoming mission scenarios. Likewise the margins for what is understood as "efficient utilization" for the fully operational science platform ISS, are immense. Understanding, accepting and approaching these challenges ESA-HSO did choose a particular pass of implementation for one of their current developments. Exploiting synergies of research, science and medical operational aspects, the "European Crew Personal Active Dosimeter for Astronauts (EuCPAD)" development exactly addresses these circumstances. It becomes novel part of ESA Radiation Protection Initiative for astronauts. The EuCPAD project aims at the development and manufacturing of an active (powered) dosimeter system to measure astronaut's exposures, support risk assessment dose management by providing a differentiated data set. Final goal is the verification of the system capabilities for medical monitoring at highest standards. The EuCPAD consists of several small portable Personal Active Dosimeters (MU = Mobile Unitas) and a rack mounted docking station “Personal Storage Device (PSD)” for MU storage, data read out and telemetry. The PSD furthermore contains a Tissue

  18. Quality assurance and quality control programme in the Personal Dosimetry Department of the Greek Atomic Energy Commission.

    Science.gov (United States)

    Kamenopoulou, V; Drikos, G; Carinou, E; Papadomarkaki, E; Askounis, P; Kyrgiakou, H; Kefalonitis, N

    2002-01-01

    A quality assurance (QA) and quality control (QC) programme was applied to the personal monitoring department (TLD based) of the Greek Atomic Energy Commission (GAEC). This programme was designed according to the recommendations of international bodies such as the International Organization for Standardization (ISO), the International Electrotechnical Commission (IEC), the International Atomic Energy Agency (IAEA) and the European Commission (CEC). This paper deals with the presentation of the QA/QC programme which includes administrative data and information, technical checking of the equipment, acceptance tests of new equipment and dosemeters, issuing and processing of the dosemeters, dose evaluation, record keeping and reporting, traceability and reproducibility, handling of complaints, internal reviews and external audits. PMID:12382742

  19. Thermoluminescent dosimetry in veterinary diagnostic radiology

    International Nuclear Information System (INIS)

    This paper presents the results of Environmental and Personnel Dosimetry made in a radiology area of a veterinary hospital. Dosimetry was realized using thermoluminescent (TL) materials. Environmental Dosimetry results show that areas closer to the X-ray equipment are safe. Personnel Dosimetry shows important measurements of daily workday in some persons near to the limit established by ICRP. TL results of radiation measurement suggest TLDs are good candidates as a dosimeter to radiation dosimetry in veterinary radiology. - Highlights: ► Personnel dosimetry in laboratory veterinary diagnostic was determined. ► Student workplaces are safe against radiation. ► Efficiency value of apron lead was determined. ► X-ray beams distribution into veterinarian laboratory was measured.

  20. Dosimetry standards

    International Nuclear Information System (INIS)

    The following leaflets are contained in this folder concerning the National Physical Laboratory's measurement services available in relation to dosimetry standards: Primary standards of X-ray exposure and X-ray irradiation facilities, X-ray dosimetry at therapy levels, Protection-level X-ray calibrations, Therapy-level gamma-ray facility, Fricke dosemeter reference service, Low-dose-rate gamma-ray facility, Penetrameter and kV meter calibration, Measurement services for radiation processing, Dichromate dosemeter reference service, Electron linear accelerator. (U.K.)

  1. Highlights and pitfalls of 20 years of application of computerised glow curve analysis to thermoluminescence research and dosimetry.

    Science.gov (United States)

    Horowitz, Y S; Moscovitch, M

    2013-01-01

    The technical and dosimetric aspects of computerised glow curve analysis are described in detail including a review of the current 'state-of-the-achieved' in applications to environmental and personal dosimetry, clinical dosimetry, quality control, characterisation of new materials, continuing characterisation of 'old' materials, heavy charged particle dosimetry, mixed field n-gamma dosimetry, X-ray dosimetry and other aspects of thermoluminescence dosimetry. Fearless emphasis is placed on 'pitfalls' as well as successes. PMID:22987121

  2. Comparison of results of the manual and automated scoring of micronucleus frequencies in 60Co-irradiated peripheral blood lymphocytes for triage dosimetry

    International Nuclear Information System (INIS)

    Scoring micronuclei in the peripheral blood lymphocytes of individuals exposed to ionizing radiation is a rapid biodosimetry assay. Peripheral blood lymphocytes from five individuals were exposed in vitro to 0–5 Gy of 60Co γ-radiation at a dose rate of 0.76 Gy/min. The blood cultures were initiated with RPMI-1640 (80%) supplemented with FBS (20%), stimulated with mitogen and incubated at 37 °C for 44 h. At the 44th hour, cytochalasin-B (6 µg/mL) was added, and the cultures were incubated for 28 h more. The cells were harvested with a pre-chilled hypotonic solution (0.075 M) and fixed with a Carnoy's solution (methanol/acetic acid 5:1). Giemsa- and propidium-iodide-stained cells affixed to slides for microscopy were scored manually and automatically with the micronucleus scoring software from MetaSystems. The micronucleus frequencies determined in the Giemsa-stained cells by manual and automated scoring were 23.6% different (P<0.0001) with an efficiency of 24.9%. Slides stained with propidium iodide are a better choice for automated scoring than Giemsa-stained ones. - Highlights: • Stains (Giemsa and PI) used did not influence the MN dose response. • No significant variation in the MN yield at lower doses between scoring methods. • Automated scoring of MN in PI stained cells would be the choice for triage

  3. NOTE FROM THE DOSIMETRY SERVICE

    CERN Document Server

    2002-01-01

    During March, the Dosimetry Service will be opened from 8h30 to 12h in the morning and closed every afternoon.   We have established that many people, who are provided regularly with a personal dosimeter (film badge), have changed their activity and do not need it anymore, because they do not, or only exceptionally, enter controlled areas. If you are one of these persons, please contact the Personal Dosimeter Service (tel: 72155). There is a simplified procedure for obtaining a dosimeter if you have an immediate need for short-term visits in controlled areas. A reduction of the number of persons on the regular distribution list of dosimeters would decrease our and the distributors workload. It would also contribute to significant savings in the dosimetry, and thus CERN, budget. We thank you in advance for your understanding and for your collaboration.

  4. Present Status and Prospects for Biological Dosimetry using Chromosome Aberration Analysis (invited paper)

    Energy Technology Data Exchange (ETDEWEB)

    Jin, C.Z.; Liu, X.L.; Zhang, Z.Y.; Luo, Y.S

    1998-07-01

    Biological dosimetry of radiation exposures was performed in 21 persons who received an overexposure to radiation in several radiation accidents during 1980-1996 in China. Based on the frequencies of dicentrics and rings the individual dose was estimated. Long-term follow-up studies have been carried out on five of the moderate and high dose exposed victims. The automated karyotype analysis system and the FISH technique have been established. The application of FISH for a dose-response relationship for translocations after irradiation with {sup 60}Co {gamma} rays has been performed. (author)

  5. Neutron personnel dosimetry

    International Nuclear Information System (INIS)

    The current state-of-the-art in neutron personnel dosimetry is reviewed. Topics covered include dosimetry needs and alternatives, current dosimetry approaches, personnel monitoring devices, calibration strategies, and future developments

  6. Cell detection in phase-contrast images used for alpha-particle track-etch dosimetry: a semi-automated approach

    Science.gov (United States)

    Altman, Michael B.; Wang, Steven J.; Whitlock, Jenny L.; Roeske, John C.

    2005-01-01

    A novel alpha-particle irradiator has recently been developed that provides the ability to characterize cell response. The irradiator is comprised of a collimated, planar alpha-particle source which, from below, irradiates cells cultured on a track-etch material. Cells are imaged using phase-contrast microscopy before and following irradiation to obtain geometric information and survival rates; these can be used with data from alpha-particle track images to assess cell response. A key step in this process is determining cell location within the pre-irradiation images. Although this can be done completely by a human observer, the number of images requiring analysis makes the process time-consuming and tedious. To reduce the potential human error and decrease user interaction time, a semi-automated, computer-aided method of cell detection has been developed. The method employs a two-level adaptive thresholding technique to obtain size and position information about potential cell cytoplasms and nuclei. Proximity and geometry-based thresholds are then used to mark structures as cells. False-positive detections from the automated algorithm are due mostly to imperfections in the track-etch background, camera effects and cellular residue. To correct for these, a human observer reviews all detected structures, discarding false positives. When analysing two randomly selected cell dish image databases, the semi-automated method detected 92-94% of all cells and 94-97% of cells with a well-defined cytoplasm and nucleus while reducing human workload by 32-83%.

  7. Dosimetry of persons in Switzerland occupationally exposed to radiation. 20. report of the Federal Commission on Radiation Protection for the year 1995

    International Nuclear Information System (INIS)

    The report is a summary of the data that was registered in Switzerland from 10 dosimetry stations for people. Given are whole and part body doses, doses as a result of incorporation as well as the accumulated total doses. 11 figs., 7 tabs

  8. State of art: Optically stimulated luminescence dosimetry – Frontiers of future research

    International Nuclear Information System (INIS)

    Since the commercial adoption of the optically stimulated luminescence (OSL) technique in dosimetry, almost 20 years ago, we have seen major advances in the deployment of OSL dosimeters in different areas, including personal, medical, and space dosimetry. The objective of this paper is to provide a critical overlook at the OSL technique from three different points of view: strengths, challenges and opportunities. We discuss factors that made the OSL technique successful: its simplicity, accuracy, wide dynamic range of measured dose, ease for automation, re-read capability, ability to perform imaging, and the availability of diverse instruments and materials. We look into problems that were overcome and others that remain in several areas of new applications into which OSL has expanded in the past 10 years, such as medical, space, neutron and accident dosimetry. Finally, we discuss unexplored possibilities, new driving forces, and open questions. We hope the broad overview presented here will encourage more discussion and stimulate the research that will advance our fundamental understanding of the OSL process. - Highlights: • Critical overlook of the OSL technique is presented. • Factors that made the OSL technique successful are discussed. • New applications in medical, space and accident dosimetry are discussed. • Unexplored possibilities, new driving forces, and open questions are presented

  9. Hematological dosimetry

    International Nuclear Information System (INIS)

    The principles of hematological dosimetry after acute or protracted whole-body irradiation are reviewed. In both cases, over-exposure is never homogeneous and the clinical consequences, viz medullary aplasia, are directly associated with the mean absorbed dose and the seriousness and location of the overexposure. The main hematological data required to assess the seriousness of exposure are the following: repeated blood analysis, blood precursor cultures, as indicators of whole-body exposure; bone marrow puncture, medullary precursor cultures and medullary scintigraphy as indicators of the importance of a local over-exposure and capacity for spontaneous repair. These paraclinical investigations, which are essential for diagnosis and dosimetry, are also used for surveillance and for the main therapeutic issues

  10. Radiation dosimetry.

    OpenAIRE

    Cameron, J.

    1991-01-01

    This article summarizes the basic facts about the measurement of ionizing radiation, usually referred to as radiation dosimetry. The article defines the common radiation quantities and units; gives typical levels of natural radiation and medical exposures; and describes the most important biological effects of radiation and the methods used to measure radiation. Finally, a proposal is made for a new radiation risk unit to make radiation risks more understandable to nonspecialists.

  11. Dosimetry Service

    CERN Multimedia

    2004-01-01

    We wish to remind the people who are invited to the Dosimetry Service to exchange the new CERN dosimeter that the hours are from Monday to Friday 8.30 to 11.00 and 14.00 to 16.00. Do not forget to read your dosimeter. The reading should be done during the first week of every month. Thank you for your cooperation.

  12. Radio-analysis. Applications: biological dosimetry; Radioanalyse. Applications: dosage biologique

    Energy Technology Data Exchange (ETDEWEB)

    Bourrel, F. [CEA Saclay, INSTN, Institut National des Sciences et Techniques Nucleaires, 91 - Gif-sur-Yvette (France); Courriere, Ph. [UFR de Pharmacie, 31 - Toulouse (France)

    2003-06-01

    Radioisotopes have revolutionized the medical biology. Radio-immunology remains the reference measurement of the infinitely small in biology. Constant efforts have been performed to improve the simpleness, detectability and fastness of the method thanks to an increasing automation. This paper presents: 1 - the advantages of compounds labelling and the isotopic dilution; 2 - the antigen-antibody system: properties, determination of the affinity constant using the Scatchard method; 3 - radio-immunologic dosimetry: competitive dosimetry (radioimmunoassay), calibration curve and mathematical data processing, application to the free thyroxine dosimetry, immunoradiometric dosimetry (immunoradiometric assay), evaluation of the analytical efficiency of a radioimmunoassay; 4 - detection of the radioactive signal (solid and liquid scintillation). (J.S.)

  13. Dosimetry optimization at COGEMA-La Hague

    International Nuclear Information System (INIS)

    At the present time, the la Hague site strives to apply international recommendations together with national regulations concerning radiation protection, and especially the respect of limitation and optimization principles. The application of these principles is based on the implementation of a passive dosimetry and an active dosimetry. The monthly passive dosimetry is monitored by means of a photographic dosimetry film, completed with lithium fluorine thermoluminescent film badges. This personal dosimetry common to X, β, γ and neutron radiations is carried out in close relationship between the Radiation Protection Department, the Occupational Medical Department and the staff running the Plant. The application or ALARA's principle as well as that of radiation protection optimization implies to implement a complementary active dosimetry enabling to gain in real time, the personal dosimetry of each intervening person, either they be COGEMA's workers or external companies'. This active dosimetry provides with following information: This preventive dosimetry is based on the knowledge of doses integration in real time and is fitted with alarm thresholds according to the total amount of doses and dose rates. Thresholds on the dose rate are also set relatively to the radiological environment. This knowledge of doses and dose rates allows a stricter management of the works, while analyzing them according to the nature of the work, to the location and to the skills of the intervening people. This dosimetry allows to analyze and optimize doses integration according to the works nature for the whole intervening staff. The la Hague Site has developed an active personal dosimetry system, common to every intervening person, COGEMA or external companies. The DOSICARD was thus elaborated, shaped as an electronic dosimeter fitted with an alarm and a smart card. The access to controlled areas is conditioned to information given by the DOSICARD concerning medical aptitudes and

  14. The BNFL legal electronic dosimetry service

    International Nuclear Information System (INIS)

    BNFL Magnox Generation started a three year scheme in April 1996 to introduce Siemens Electronic Personal Dosimetry (EPD) systems into its reactor sites as part of an initiative to improve the control of doses and the accuracy of dose statistics and to record personal legal dose. Concurrent with the installation of the EPD systems a successful application was made to the United Kingdom Health and Safety Executive (HSE) for approval of the BNFL dosimetry service to use the Siemens EPD Mk 1.2 for recording legal doses. This paper discusses the experiences of the BNFL dosimetry service in operating the approved dosimetry service since it's approval by the HSE in January 2000. (authors)

  15. Personalization.

    Science.gov (United States)

    Shore, Rebecca Martin

    1996-01-01

    Describes how a typical high school in Huntington Beach, California, curbed disruptive student behavior by personalizing the school experience for "problem" students. Through mostly volunteer efforts, an adopt-a-kid program was initiated that matched kids' learning styles to adults' personality styles and resulted in fewer suspensions and numerous…

  16. Topics in radiation dosimetry radiation dosimetry

    CERN Document Server

    1972-01-01

    Radiation Dosimetry, Supplement 1: Topics in Radiation Dosimetry covers instruments and techniques in dealing with special dosimetry problems. The book discusses thermoluminescence dosimetry in archeological dating; dosimetric applications of track etching; vacuum chambers of radiation measurement. The text also describes wall-less detectors in microdosimetry; dosimetry of low-energy X-rays; and the theory and general applicability of the gamma-ray theory of track effects to various systems. Dose equivalent determinations in neutron fields by means of moderator techniques; as well as developm

  17. Aplicación para la configuración automática del certificado digital en un ordenador personal

    OpenAIRE

    Khubchandani Khubchandani, Ravi Raj

    2014-01-01

    [ES] Programa de escritorio compatible con sistemas operativos Windows 7 y Windows 8.1. El programa configura el ordenador personal del usuario de modo que la firma electrónica de la Universidad de Las Palmas de Gran Canaria funcione correctamente en los navegadores web elegidos por el usuario. Al iniciarse la aplicación, el usuario elige dichos navegadores. El programa incorpora dos modos de instalación. La primera forma es la instalación automática, todos los componentes requeridos, que no ...

  18. Individual dosimetry of workers and patients: implementation and perspectives

    International Nuclear Information System (INIS)

    These days organised by the section of the technical protection of the S.F.R.P. review the different techniques of dosimetry used in France and Europe, and present the future orientations.The different interventions are as follow: Individual exposures of the workers: historic assessment and perspectives; medical exposure: where are the doses; legal obligations in individual dosimetry: which are the objective and the need on the subject; the dosimetry follow-up of workers by the S.I.S.E.R.I. system: assessment and perspectives; impact of the norm ISO 20553 on the follow-up of internal exposure; the implementation of the patient dose measurement in Belgium; techniques of passive dosimetry used in Europe; Supervision radiation protection at EDF: long term and short term approach; Comparison active and passive dosimetry at Melox; methodology for the choice of new neutron dosemeters; the working group M.E.D.O.R.: guide of internal dosimetry for the use of practitioners; O.E.D.I.P.E.: tool of modeling for the personalized internal dosimetry; the use of the Monte-Carlo method for the planning of the cancer treatment by radiotherapy becomes a reality; the works of the committee 2 of the ICRP; passive dosimetry versus operational dosimetry: situation in Europe; Implementation of the in vivo dosimetry in a radiotherapy department: experience of the Gustave Roussy institute; experience feedback on the in vivo measures in radiotherapy, based on the use of O.S.L. pellets; multi points O.S.L. instrumentation for the radiation dose monitoring in radiotherapy; dosimetry for extremities for medical applications: principle results of the European contract C.O.N.R.A.D.; references and perspectives in dosimetry; what perspectives for numerical dosimetry, an example: Sievert; system of dose management: how to answer to needs; the last technical evolutions in terms of electronic dosimetry in nuclear power plant; the fourth generation type reactors: what dosimetry. (N.C.)

  19. TLD personnel dosimetry and its relationship with the radiodiagnostic training; Dosimetria personal TLD y su relacion con la capacitacion en radiodiagnostico

    Energy Technology Data Exchange (ETDEWEB)

    Gaona, E.; Franco E, J.G. [DEHA, Universidad Autonoma Metropolitana-Xochimilco, Mexico D.F. (Mexico); Gaona C, E. [Universidad Tecnologica de Mexico, Mexico D.F. (Mexico)

    2002-07-01

    The personnel dosimetry and the training in radiological protection in radiodiagnostic in Mexico before 1997 were almost nonexistent except few services of public and private radiology, we can to say that the personnel dosimetry and the obligatory training was born in the year 1997, together with the present Mexican Official Standards in radiology. This study has the purpose to make an evaluation of the personnel dosimetry of 110 radiology services distributed in the Mexican Republic for the year 2001 and to estimate the annual and bimonthly mean doses, as well as its trust intervals and its relationships with the personnel training in radiological protection by means of a sampling that was realized in two stages (1997 and 2000) in the metropolitan area of Mexico City. The results show that the received doses by the medical and technical personnel in the participating radiology services are in the 0.03 mSv and 0.94 mSv interval and the mean is 0.25 mSv. The estimated annual personnel dose would be in the 0.18 mSv to 5.64 mSv interval, which are values very lower to the annual dose limit that is 50 mSv and its magnitude is similar to the effective annual dose by natural background radiation. In the first stage in training was found that there is not a significant difference in the response frequencies among the medical and technical personnel with a p < 0.05. The 52% of the occupational exposure personnel of radiology uses dosemeter, but only 17% of them know the dose reports. the 15.8% of personnel considers that dosemeter protects against radiation and only 16.5% knows the annual maximum permissible dose for stochastic effects. The second stage, the results shown that there is a significant difference in the response of frequencies among medical and technical personnel, the same results which are obtained for members and non members of a professional association with a p < 0.05. The 38% has personnel dosimetry, the 19% knows the principles of radiological

  20. Type tests to the automatic system of thermoluminescent dosimetry acquired by the CPHR for personnel dosimetry; Pruebas tipo al sistema de dosimetria termoluminiscente automatico adquirido por el CPHR para dosimetria personal

    Energy Technology Data Exchange (ETDEWEB)

    Molina P, D.; Pernas S, R. [Centro de Proteccion e Higiene de las Radiaciones (CPHR), Calle 20, No. 4113 e/ 41 y 47, Miramar, Ciudad de la Habana (Cuba)]. e-mail: daniel@cphr.edu.cu

    2005-07-01

    The CPHR individual monitoring service acquired an automatic RADOS TLD system to improve its capacities to satisfy the increasing needs of their national customers. The TLD system consists of: two automatic TLD reader, model DOSACUS, a TLD irradiator and personal dosimeters card including slide and holders. The dosimeters were composed by this personal dosimeters card and LiF: Mg,Cu,P (model GR-200) detectors. These readers provide to detectors a constant temperature readout cycle using hot nitrogen gas. In order to evaluate the performance characteristics of the system, different performance tests recommended by the IEC 1066 standard were carried out. Important dosimetric characteristics evaluated were batch homogeneity, reproducibility, detection threshold, energy dependence, residual signal and fading. The results of the tests showed good performance characteristics of the system. (Author)

  1. Medical dosimetry in Hungary

    Science.gov (United States)

    Turák, O.; Osvay, M.; Ballay, L.

    2012-09-01

    Radiation exposure of medical staff during cardiological and radiological procedures was investigated. The exposure of medical staff is directly connected to patient exposure. The aim of this study was to determine the distribution of doses on uncovered part of body of medical staff using LiF thermoluminescent (TL) dosimeters in seven locations. Individual Kodak film dosimeters (as authorized dosimetry system) were used for the assessment of medical staff's effective dose. Results achieved on dose distribution measurements confirm that wearing only one film badge under the lead apron does not provide enough information on the personal dose. The value of estimated annual doses on eye lens and extremities (fingers) were in good correlation with international publications.

  2. Automated Personalized Feedback for Physical Activity and Dietary Behavior Change With Mobile Phones: A Randomized Controlled Trial on Adults

    OpenAIRE

    Rabbi, Mashfiqui; Pfammatter, Angela; Zhang, Mi; Spring, Bonnie; Choudhury, Tanzeem

    2015-01-01

    Background A dramatic rise in health-tracking apps for mobile phones has occurred recently. Rich user interfaces make manual logging of users’ behaviors easier and more pleasant, and sensors make tracking effortless. To date, however, feedback technologies have been limited to providing overall statistics, attractive visualization of tracked data, or simple tailoring based on age, gender, and overall calorie or activity information. There are a lack of systems that can perform automated trans...

  3. The Vinca dosimetry experiment

    International Nuclear Information System (INIS)

    On 15 October 1958 there occurred a very brief uncontrolled run of the zero-power reactor at the Boris Kidric Institute of Nuclear Science, Vinca, near Belgrade, Yugoslavia. During this run six persons received various doses of radiation. They were subsequently given medical treatment of a novel kind at the Curie Hospital, Paris. In atomic energy operations to date, very few accidents involving excessive radiation exposure to human beings have occurred. In fact, the cases of acute radiation injury are limited to about 30 known high exposures, few of which were in the lethal or near-lethal range. Since direct experiment to determine the effects of ionizing radiation on man is unacceptable, information on these effects has to be based on a consideration of data relating to accidental exposures, viewed in the light of the much more extensive data obtained from experiments on animals. Therefore, any direct information on the effects of radiation on humans is very valuable. The international dosimetry project described in this report was carried out at Vinca, Yugoslavia, under the auspices of the International Atomic Energy Agency to determine the precise amount of radiation to which the persons had been exposed during the accident. These dosimetry data, together with the record of the carefully observed clinical effects, are of importance both for the scientific study of radiation effects on man and for the development of methods of therapy. The experiment and measurements were carried out at the end of April 1960. The project formed part of the Agency's research programme in the field of health and safety. The results of the experiment are made available through this report to all Member States

  4. Breast dosimetry

    International Nuclear Information System (INIS)

    The estimation of the absorbed dose to the breast is an important part of the quality control of the mammographic examination. Knowledge of breast dose is essential for the design and performance assessment of mammographic imaging systems. This review gives a historical introduction to the measurement of breast dose. The mean glandular dose (MGD) is introduced as an appropriate measure of breast dose. MGD can be estimated from measurements of the incident air kerma at the surface of the breast and the application of an appropriate conversion factor. Methods of calculating and measuring this conversion factor are described and the results discussed. The incident air kerma itself may be measured for patients or for a test phantom simulating the breast. In each case the dose may be determined using TLD measurements, or known exposure parameters and measurements of tube output. The methodology appropriate to each case is considered and the results from sample surveys of breast dose are presented. Finally the various national protocols for breast dosimetry are compared

  5. Neutron dosimetry - A review

    International Nuclear Information System (INIS)

    This review summarizes information on the following subjects: (1) physical processes of importance in neutron dosimetry; (2) biological effects of neutrons; (3) neutron sources; and (4) instruments and methods used in neutron dosimetry. Also, possible improvements in dosimetry instrumentation are outlined and discussed. (author)

  6. Implementation of a dosimetry service for the occupationally exposed personnel of the ESFM-IPN; Implementacion de un servicio de dosimetria para el personal ocupacionalmente expuesto de la ESFM-IPN

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez A, Y. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico); Sanchez R, A. A. [IPN, Escuela Superior de Fisica y Matematicas, U. P. Adolfo Lopez Mateos, Edif. 9, 07738 Mexico D. F. (Mexico); Ceron R, P. V.; Rivera M, T. [IPN, Centro de Investigacion en Ciencia y Tecnologia Avanzada, Unidad Legaria, Av. Legaria No. 694, 11500 Mexico D. F. (Mexico); Vega C, H. R., E-mail: yamani.hernandez@cnsns.gob.mx [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas (Mexico)

    2014-10-15

    Because the ionizing radiations handling implies a risk for the health, is necessary to take a control of the radiation quantity that the occupationally exposed personnel receives during their daily work with ionizing radiations. For this purpose there are several types of dosimetry and companies that provide the service, but taking advantage that the Escuela Superior de Fisica y Matematicas del Instituto Politecnico Nacional (ESFM-IPN) possesses a thermoluminescence equipment (Tl) was decided to develop a personnel dosimetry service for gammas, with thermoluminescent glasses of type TLD-100. First one carries out a glasses characterization, for which the glasses were washed with a methyl alcohol solution, without rubbing them for not damaging them; after the drying, they were subjected to a temperature of 400 C during one hour and later on 100 grades C for two hours in order to erasing them the bottom information that they could have. 200 glasses were exposed to gamma radiation coming from a Cobalt 60 source property of ESFM-IPN in order to selecting the glasses that had a response whose precision was inside a standard deviation. Of this characterization 80 dosimeters were selected that had better response according to the obtained readings as well as of their shine curves. These selected TLD-100 glasses were irradiated to different dose of gamma radiation and with those readings it was built a dose response curve in m R against readings of electric load in pick Coulombs (pCou). The response curve was a direct line or calibration curve. As final exercise some glasses of this selected lot were subjected to irradiation dose not known by the person that carried out the readings and this way was proven that the results were appropriate with the calibration curve. Finally these dosimeters were placed in port-dosimeters and erased guides of dosimeters, of equipment use and dosimeters lecture were also elaborated. (Author)

  7. Thermoluminescence in medical dosimetry; Termoluminiscencia en dosimetria medica

    Energy Technology Data Exchange (ETDEWEB)

    Rivera, T., E-mail: trivera@ipn.mx [IPN, Centro de Investigacion en Ciencia Aplicada y Tecnologia Avanzada, Av. Legaria 694, Col. Irrigacion, 11500 Mexico D. F. (Mexico)

    2011-10-15

    The dosimetry by thermoluminescence (Tl) is applied in the entire world for the dosimetry of ionizing radiations specially to personal and medical dosimetry. This dosimetry method has been very interesting for measures in vivo because the Tl dosimeters have the advantage of being very sensitive in a very small volume and they are also equivalent to tissue and they do not need additional accessories (for example, cable, electrometer, etc.) The main characteristics of the diverse Tl materials to be used in the radiation measures and practical applications are: the Tl curve, the share homogeneity, the signal stability after the irradiation, precision and exactitude, the response in function with the dose and the energy influence. In this work a brief summary of the advances of the radiations dosimetry is presented by means of the thermally stimulated luminescence and its application to the dosimetry in radiotherapy. (Author)

  8. Neutron dosimetry characteristics of PADC manufactured by Instrument Plastics Ltd

    International Nuclear Information System (INIS)

    PADC from a UK manufacturer with no history of producing dosimetry grade material has been obtained with a view to assessing the potential for this new material being used in the HPA neutron personal dosimetry service. The HPA is always looking for alternative suppliers, both to seek out better dosimetry grade PADC, but also to secure long-term supplies for the dosimetry service. This new material has been tested in terms of its mean background, background variability and response to ascertain its dosimetric potential. The stopping of high-energy α-particles has also been studied in a stack of dosemeters to compare the LET threshold of the new material with that currently used in the personal neutron dosimetry service.

  9. Application of a personal computer for analysis and data reduction of TLD-300 glow curves for dosimetry in mixed neutron and photons fields

    International Nuclear Information System (INIS)

    TLD-300 material can be used to measure simultaneously neutron and photon absorbed dose with one small detector. It is applied for clinical dosimetry for d(14)+Be neutrons to measure whole dose distributions of complex treatment technique. In this application many glow curves are measured and should be stored for documentation. Therefore it is desirable to reduce the number of data which must be stored for one glow curve. The TLD-300 glow curves can be approximated by a sum of 8 Gauss functions, so that the whole glow curve can be reconstructed from 24 numerical values. Moreover by a appropriate fitting procedure it is found that the positions and widths of the Gauss functions needed are almost the same for all detectors. They seem to be independent of dose and beam quality. Only the parameters of the two Gauss functions at the lowest heating temperature, amplitude and even position and width, depend on time elapsed between irradiation and read-out of the detector

  10. Czech results at criticality dosimetry intercomparison 2002

    Czech Academy of Sciences Publication Activity Database

    Spurný, František; Trousil, J.

    2004-01-01

    Roč. 110, 1-4 (2004), s. 455-458. ISSN 0144-8420 R&D Projects: GA AV ČR KSK4055109 Institutional research plan: CEZ:AV0Z1048901 Keywords : personal dosimetry * thermoluminescent detectors * individual dosimeters Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.617, year: 2003

  11. Solid-state dosimetry applications: thermoluminescence dating, thermocurrent dosimetry

    International Nuclear Information System (INIS)

    In the new TL method for the testing of authenticity of archaeological findings the fraction between 100-250 μm from the whole substance of the pottery is used. The mass of the sample being about 0.1 g the method entails a negligible destruction of the object. For the determination of absolute age the TL of quartz grains separated from the ceramic object is used. A TLD method for the measurement of internal dose rate was developed an supplemented with elemental analysis to raise accuracy (at present about 20%). The temporary change in the conductivity of the insulating materials under ionizing radiation and heating - the so-called thermocurrent (TC) effect - offer new possibilities for the dosimetry of ionizing radiations. From the practical point of view the TC dosimetry distinguishes itself by the simplicity of read-out and, consequently, by excellent reproducibility. The dose measurable by sapphire crystals ranges from 100 μGy to 10 Gy, so the method is hopeful in personal dosimetry, too. The only drawback is the high scattering of parameters of the samples measured. (author)

  12. Silicon diode dosimetry

    International Nuclear Information System (INIS)

    The theory of silicon dosimetry is briefly reviewed with respect to operation of these diodes without reverse bias in the short-circuit current mode. The problems of temperature dependence, radiation damage, and the dependence on photon energy are discussed. Various applications of the diodes to practical radiation dosimetry are then described with a view toward pointing out the pitfalls as well as the advantages of using these diodes for dosimetry. (author)

  13. Silicon diode dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Dixon, R.L.; Ekstrand, K.E. (Wake Forest Univ., Winston-Salem, NC (USA). Bowman Gray School of Medicine)

    1982-11-01

    The theory of silicon dosimetry is briefly reviewed with respect to operation of these diodes without reverse bias in the short-circuit current mode. The problems of temperature dependence, radiation damage, and the dependence on photon energy are discussed. Various applications of the diodes to practical radiation dosimetry are then described with a view toward pointing out the pitfalls as well as the advantages of using these diodes for dosimetry.

  14. Aptitudes of external irradiation measures devices destined to working zones survey or personal dosimetry to measure new operational quantities. Case of photons

    International Nuclear Information System (INIS)

    Recommendations of ICRP advocating evaluation of efficient dose equivalent to estimate radiological risks, led ICRU to develop, to measure external irradiation, new operational quantities for practical use in radiation protection. After calling to mind of these quantities with their consequences on calibration of radiation protection measure equipment, is examined the aptitude to measure the new quantities of some radiation protection apparatus, particularly for working areas and for personal dosemeters destined to photons measures. 18 refs. 19 figs

  15. Advances in biomedical dosimetry

    International Nuclear Information System (INIS)

    The symposium was organized in order to focus on the problems, developments and areas of further research in the life sciences. Forty-nine papers were presented dealing with instrumentation, techniques, experimental and theoretical studies. They included neutron sources and mixed-field dosimetry; developments (e.g. thermocurrent dosimetry) in dosimetry; physical aspects of radiation therapy, and treatment planning; international, national and regional radiation metrology programmes; diagnostic medical x-ray sources, imaging systems and patient doses; high-energy electron and γ-ray dosimetry; and doses determination for ingested or administered radionuclides

  16. Measurement assurance in dosimetry

    International Nuclear Information System (INIS)

    The uses of radiation in medicine and industry are today wide in scope and diversity and there is a need for reliable dosimetry in most applications. In particular, high accuracy in dosimetry is required in the therapeutic use of radiation. Consequently, calibration procedures for radiotherapy generally meet also the accuracy requirements for applications in other fields, such as diagnostic radiology, radiation protection and industrial radiation processing. The emphasis at this symposium was therefore mainly or radiotherapy dosimetry, but the meeting also included one session devoted to dosimetry in diagnostic radiology. Refs, fig and tabs

  17. Internal sources dosimetry

    International Nuclear Information System (INIS)

    The absorbed dose, need of estimation in risk evaluation in the application of radiopharmaceuticals in Nuclear Medicine practice,internal dosimetry,internal and external sources. Calculation methodology,Marinelli model,MIRD system for absorbed dose calculation based on biological parameters of radiopharmaceutical in human body or individual,energy of emitted radiations by administered radionuclide, fraction of emitted energy that is absorbed by target body.Limitation of the MIRD calculation model. A explanation of Marinelli method of dosimetry calculation,β dosimetry. Y dosimetry, effective dose, calculation in organs and tissues, examples. Bibliography .

  18. Dosimetry of ionizing radiation

    International Nuclear Information System (INIS)

    The publication deals with a major field of ionizing radiation dosimetry, viz., integrating dosimetric methods, which are the basic means of operative dose determination. It is divided into the following sections: physical and chemical effects of ionizing radiation; integrating dosimetric methods for low radiation doses (film dosimetry, nuclear emulsions, thermoluminescence, radiophotoluminescence, solid-state track detectors, integrating ionization dosemeters); dosimetry of high ionizing radiation doses (chemical dosimetric methods, dosemeters based on the coloring effect, activation detectors); additional methods applicable to integrating dosimetry (exoelectron emission, electron spin resonance, lyoluminescence, etc.); and calibration techniques for dosimetric instrumentation. (Z.S.). 422 refs

  19. Dosimetry in Interventional Radiology - Effective Dose Estimation

    International Nuclear Information System (INIS)

    Interventional radiological procedures can lead to significant radiation doses to patients and to staff members. In order to evaluate the personal doses with respect to the regulatory dose limits, doses measured by dosimeters have to be converted to effective doses (E). Measurement of personal dose equivalent Hp(10) using a single unshielded dosimeter above the lead apron can lead to significant overestimation of the effective dose, while the measurement with dosimeter under the apron can lead to underestimation. To improve the accuracy, measurements with two dosimeters, one above and the other under the apron have been suggested (double dosimetry). The ICRP has recommended that interventional radiology departments develop a policy that staff should wear two dosimeters. The aim of this study was to review the double dosimetry algorithms for the calculation of effective dose in high dose interventional radiology procedures. The results will be used to develop general guidelines for personal dosimetry in interventional radiology procedures. This work has been carried out by Working Group 9 (Radiation protection dosimetry of medical staff) of the CONRAD project, which is a Coordination Action supported by the European Commission within its 6th Framework Program.(author)

  20. Individual dosimetry of workers and patients: implementation and perspectives; La dosimetrie individuelle des travailleurs et de patients: mise en oeuvre et perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Rannou, A.; Aubert, B.; Lahaye, Th.; Scaff, P.; Casanova, Ph.; Van Bladel, L.; Queinnec, F.; Valendru, N.; Jehanno, J.; Grude, E.; Berard, Ph.; Desbree, A.; Kafrouni, H.; Paquet, F.; Vanhavere, F.; Bridier, A.; Ginestet, Ch.; Magne, S.; Donadille, L.; Bordy, J.M.; Bottollier-Depois, J.F.; Barrere, J.L.; Ferragut, A.; Metivier, H.; Gaillard-Lecanu, E

    2008-07-01

    These days organised by the section of the technical protection of the S.F.R.P. review the different techniques of dosimetry used in France and Europe, and present the future orientations.The different interventions are as follow: Individual exposures of the workers: historic assessment and perspectives; medical exposure: where are the doses; legal obligations in individual dosimetry: which are the objective and the need on the subject; the dosimetry follow-up of workers by the S.I.S.E.R.I. system: assessment and perspectives; impact of the norm ISO 20553 on the follow-up of internal exposure; the implementation of the patient dose measurement in Belgium; techniques of passive dosimetry used in Europe; Supervision radiation protection at EDF: long term and short term approach; Comparison active and passive dosimetry at Melox; methodology for the choice of new neutron dosemeters; the working group M.E.D.O.R.: guide of internal dosimetry for the use of practitioners; O.E.D.I.P.E.: tool of modeling for the personalized internal dosimetry; the use of the Monte-Carlo method for the planning of the cancer treatment by radiotherapy becomes a reality; the works of the committee 2 of the ICRP; passive dosimetry versus operational dosimetry: situation in Europe; Implementation of the in vivo dosimetry in a radiotherapy department: experience of the Gustave Roussy institute; experience feedback on the in vivo measures in radiotherapy, based on the use of O.S.L. pellets; multi points O.S.L. instrumentation for the radiation dose monitoring in radiotherapy; dosimetry for extremities for medical applications: principle results of the European contract C.O.N.R.A.D.; references and perspectives in dosimetry; what perspectives for numerical dosimetry, an example: Sievert; system of dose management: how to answer to needs; the last technical evolutions in terms of electronic dosimetry in nuclear power plant; the fourth generation type reactors: what dosimetry. (N.C.)

  1. Radiation therapy dosimetry system

    International Nuclear Information System (INIS)

    New therapeutic treatments generally aim to increase therapeutic efficacy while minimizing toxicity. Many aspects of radiation dosimetry have been studied and developed particularly in the field of external radiation. The success of radiotherapy relies on monitoring the dose of radiation to which the tumor and the adjacent tissues are exposed. Radiotherapy techniques have evolved through a rapid transition from conventional three-dimensional (3D) conformal radiation therapy to intensity-modulated radiation therapy (IMRT) treatments or radiosurgery and robotic radiation therapy. These advances push the frontiers in our effort to provide better patient care by improving the precision of the absorbed dose delivered. This paper presents state-of-the art radiation therapy dosimetry techniques as well as the value of integral dosimetry (INDOS), which shows promise in the fulfillment of radiation therapy dosimetry requirements. - highlights: • Pre-treatment delivery and phantom dosimetry in brachytherapy treatments were analyzed. • Dose distribution in the head and neck was estimated by physical and mathematical dosimetry. • Electron beam flattening was acquired by means of mathematical, physical and “in vivo” dosimetry. • Integral dosimetry (INDOS) has been suggested as a routine dosimetric method in all radiation therapy treatments

  2. Dosimetry in process control

    International Nuclear Information System (INIS)

    Measurement of absorbed dose and dose distribution in irradiated medical products relies on the use of quality dosimetry systems, trained personnel and a thorough understanding of the energy deposition process. The interrelationship of these factors will be discussed with emphasis on the current and future practices of process control dosimetry. (author)

  3. Usage of JENDL dosimetry file for material dosimetry in JOYO

    International Nuclear Information System (INIS)

    A cross section set with covariance error matrix for neutron spectrum unfolding has been newly prepared from JENDL-3 dosimetry file and was applied to the dosimetry test in the MK-II core (the irradiation core) of Experimental Fast Reactor 'JOYO'. The dosimetry results by the new cross section set were compared with the previous ones by ENDF/B-V dosimetry file to evaluate the applicability and accuracy for the fast reactor dosimetry. In this work, it has been concluded that more improvement can be expected for the JOYO dosimetry test by employing JENDL-3 dosimetry file. (author)

  4. Retrospective dosimetry by chromosomal analysis

    International Nuclear Information System (INIS)

    The joint EU/CIS project ECP-6, was set up to examine whether cytogenetic dosimetry is possible for persons irradiated years previously at Chernobyl. The paper describes the possibility of achieving this by the examination of blood lymphocytes for unstable and stable chromosome aberrations; dicentrics and translocations. Emphasis was placed on the relatively new fluorescence in situ hybridization (FISH) method for rapid screening for stable translocations. In a collaborative experiment in vitro dose response calibration curves for dicentrics and FISH were produced with gamma radiation over the range 0-1.0 Gy. A pilot study of about 60 liquidators with registered doses ranging from 0-300 mSv was undertaken to determine whether the chromosomal methods may verify the recorded doses. It was concluded that the dicentric is no longer valid as a measured endpoint. Translocations may be used to verify early dosimetry carried out on highly irradiated persons. For the vast majority of lesser exposed subjects FISH is impractical as an individual dosimeter; it may have some value for comparing groups of subjects

  5. On-Board TL Dosimetry: Possibilities and Limitations

    International Nuclear Information System (INIS)

    Full text: The paper shortly deals with application of TLDs for dosimetry of ISS, e.g. personal dosimetry, phantom measurements, mapping, monitoring and neutron dosimetry. The main characteristics of the on-board and ground evaluation are compared. The main advantages and disadvantages of the on-board evaluation are summarised. Finally the planned future improvements of the Pille system are discussed like development of an RS485 interface for alternative data transfer, introduction of smaller dosimeters (capsules), use of a more use-friendly display (80 characters), application of internal memory instead of memory card and improvement of the dosimeter evaluation (glow curve fit, background subtraction). (author)

  6. Automated counting and analysis of etched tracks in CR-39 plastic

    International Nuclear Information System (INIS)

    An image analysis system has been set up which is capable of automated counting and analysis of etched nuclear particle tracks in plastic. The system is composed of an optical microscope, CCD camera, frame grabber, personal computer, monitor, and printer. The frame grabber acquires and displays images at video rate. It has a spatial resolution of 512 x 512 pixels with 8 bits of digitisation corresponding to 256 grey levels. The software has been developed for general image processing and adapted for the present purpose. Comparisons of automated and visual microscope counting of tracks in chemically etched CR-39 detectors are presented with emphasis on results of interest for practical radon measurements or neutron dosimetry, e.g. calibration factors, background track densities and variations in background. (author)

  7. INFORMATION: INDIVIDUAL DOSIMETRY SERVICE

    CERN Multimedia

    2004-01-01

    We inform you that the Individual Dosimetry Service will be exceptionally closed on April 13 and 14 (Tuesday and Wednesday). Only the very urgent cases will be handled during the days mentioned above.

  8. Dosimetry for radiation processing

    DEFF Research Database (Denmark)

    Miller, Arne

    1986-01-01

    During the past few years significant advances have taken place in the different areas of dosimetry for radiation processing, mainly stimulated by the increased interest in radiation for food preservation, plastic processing and sterilization of medical products. Reference services both by...... and sterilization dosimetry, optichromic dosimeters in the shape of small tubes for food processing, and ESR spectroscopy of alanine for reference dosimetry. In this paper the special features of radiation processing dosimetry are discussed, several commonly used dosimeters are reviewed, and factors...... international organizations (IAEA) and national laboratories have helped to improve the reliability of dose measurements. Several dosimeter systems like calorimetry, perspex, and radiochromic dye films are being improved and new systems have emerged, e.g. spectrophotometry of dichromate solution for reference...

  9. EPR TOOTH DOSIMETRY OF SNTS AREA INHABITANTS

    OpenAIRE

    Sholom, Sergey; Desrosiers, Marc; Bouville, André; Luckyanov, Nicholas; Chumak, Vadim; Simon, Steven L.

    2007-01-01

    The determination of external dose to teeth of inhabitants of settlements near the Semipalatinsk Nuclear Test Site (SNTS) was conducted using the EPR dosimetry technique to assess radiation doses associated with exposure to radioactive fallout from the test site. In this study, tooth doses have been reconstructed for 103 persons with all studied teeth having been formed before the first nuclear test in 1949. Doses above those received from natural background radiation, termed “accident doses”...

  10. Individual Dosimetry Service

    CERN Multimedia

    2004-01-01

    Individual Dosimetry Service will be closed on Thursday 9 September (Jeûne genevois) and on Friday 10 September. We inform all staffs and users under regular dosimetry control that the dosimeters for the monitoring period SEPTEMBER-OCTOBER 2004 are available from their usual dispatchers. Please have your films changed before the 13 SEPTEMBER 2004. The color of the dosimeter valid in SEPTEMBER-OCTOBER 2004 is RED.

  11. ESR dosimetry for atomic bomb survivors and radiologic technologists

    Science.gov (United States)

    Tatsumi-Miyajima, Junko

    1987-06-01

    An individual absorbed dose for atomic bomb (A-bomb) survivors and radiologic technologists has been estimated using a new personal dosimetry. This dosimetry is based on the electron spin resonance (ESR) spectroscopy of the CO 33- radicals, which are produced in their teeth by radiation. Measurements were carried out to study the characteristics of the dosimetry; the ESR signals of the CO 33- radicals were stable and increased linearly with the radiation dose. In the evaluation of the absorbed dose, the ESR signals were considered to be a function of photon energy. The absorbed doses in ten cases of A-bomb victims and eight cases of radiologic technologists were determined. For A-bomb survivors, the adsorbed doses, which were estimated using the ESR dosimetry, were consistent with the ones obtained using the calculations of the tissue dose in air of A-bomb, and also with the ones obtained using the chromosome measurements. For radiologic technologists, the absorbed doses, which were estimated using the ESR dosimetry, agreed with the ones calculated using the information on the occupational history and conditions. The advantages of this method are that the absorbed dose can be directly estimated by measuring the ESR signals obtained from the teeth of persons, who are exposed to radiation. Therefore, the ESR dosimetry is useful to estimate the accidental exposure and the long term cumulative dose.

  12. Individual Monitoring and TL Dosimetry in Hungary

    International Nuclear Information System (INIS)

    The widespread development and application of X-ray and nuclear energy resulted in the problem of ionizing radiation dosimetry also in Hungary. The individual monitoring started in 1955 using film badge and various ''pen type'' ionization chambers with different measuring ranges to determine the external photon radiation doses. Since 1966 the film badge has been accepted as the official personal dosimeter system in Hungary. The film monitors are presently processed bimonthly. The personal monitoring for about 16 000 occupationally exposed ''A category'' workers is conducted by the National Research Institute of Radiobiology and Radiohygiene, with Kodak film badge. The calibration of dosimeters is performed in the primary standard laboratory of the National Standardization Laboratory (OMH) according to ISO17025 standard. The thermoluminescent (TL) method for personal dosimetry purposes was introduced in Hungary in the early 1970's. Central Research Insitute of Physics and Insitute of Isotopes developed together a solid state dosimetry system using first 2 pieces of LiF (TLD-100) TL dosimeters in the same badge together with the film. Later, the Harshaw LiF dosimeters were changed to the Polish LiF (MTS-N) ones, having higher sensitivity to gamma and to mixed neutron-gamma field dosimetry purposes. At present, besides the national film dosimetry service, there are three TL dosimetry services as well (Atomic Energy Research Institute, Institute of Isotopes, Nuclear Power Plant). The thermoluminescent (TL) whole body dosimeters are used for individual monitoring parallel with the film and the evaluation of the various types of LiF (TLD-100, Polish MTS-N etc.) is performed at ''home'' dosimetry services using different manual and automatic TL readers (Harshaw 4000, Harshaw 3500, Alnor TLD reader). Personal dosimetry data measured by film and TL method are regularly compared. In addition to the successful applications of various TL dosimeters for work place monitoiring

  13. Occupational dosimetry commissioning of a PET-CT: learning curve and staff participation

    International Nuclear Information System (INIS)

    The Nuclear Medicine Department, Hospital General Universitario Gregorio Maranon has been in clinical use PET-CT equipment at the end of 2009. The Dosimetry and Radiation Protection Service has been conducting surveillance at the facility and individual environmental dosimetry. Following the obligations contained in the performance specifications of the authorization granted by the Nuclear Safety Council (CSN), during the first year of the PET-CT has been tracking personal dosimetry of the professionals involved. As a novelty, had to take the ring dosimetry to control the dose equivalent in the hands instead of the normal wrist.

  14. Speculation on improving personal dosimetry in mammography

    International Nuclear Information System (INIS)

    The increasing importance of radiation protection of the patient in diagnostic radiology has created an interest in the dose individuals receive from X-ray mammography, although this is an area where the most important aspect of protection is based on the inter comparison of machines using phantoms and standard conditions. In 1987 the ICRP established the critical quantity as being the average absorbed dose to the glandular tissue of the breast, and identified a composition of 50% adipose; 50% glandular tissue as a reference. Several authors have published experimental and monte carlo simulation resuluts to enable the determination of this quantity from output, beam quality and compressed breast thickness. Many centres, including ourselves, have studied the distribution of radiation dose on this basis. The result is however dependant on the assumption made about tissue composition. It is apparently common knowledge among pathologists and frequently mentioned in general anatomy texts, that the amount of glandular tissue is independent of breast size; that is larger breasts will have a higher adipose:glandular tissue ratio. Such a systematic variation would lead to an overestimate of the dose being received by women with larger breasts. I will review the availabe pathology and demonstrate the effect of applying the assumed breast composition on our own data. (author)

  15. Improvement of personal dosimetry - Digital pocket dosemeter

    International Nuclear Information System (INIS)

    Physical dosimetric surveillance of professional groups working with various radiation sources is a regular procedure in Croatia, established almost 40 years ago. Data available point out that the majority of professionals under surveillance are those employed in medical facilities, most of them working with X-ray sources. Depending on the nature of professional activities, personnel occupationally exposed to radiation sources are obliged to wear either film badge, TLD or film+TLD badge. Unfortunately, due to the line of data processing, all standard dosemeters have the same disadvantage i.e. up to 40 days delay in dose reporting, regarding the time of actual exposure. The significance of such a delay raises in cases when radiation dose was received within the short time or when technical failure on the operating unit(s) is suspected. Bearing this in mind, the additional dosimetric monitoring becomes an imperative. Therefore, we decided to introduce a palette of digital pocket dosemeters, meant to be used in different workplaces in the radiation zone, each of them being adjusted to the specificities of a particular workplace

  16. Secondary standard dosimetry laboratory (SSDL)

    International Nuclear Information System (INIS)

    A secondary Standard Dosimetry Laboratory has been established in the Tun Ismail Research Centre, Malaysia as a national laboratory for reference and standardization purposes in the field of radiation dosimetry. This article gives brief accounts on the general information, development of the facility, programmes to be carried out as well as other information on the relevant aspects of the secondary standard dosimetry laboratory. (author)

  17. Topics in radiation dosimetry radiation dosimetry, v.1

    CERN Document Server

    Attix, Frank H

    2013-01-01

    Radiation Dosimetry, Supplement 1: Topics in Radiation Dosimetry covers instruments and techniques in dealing with special dosimetry problems. The book discusses thermoluminescence dosimetry in archeological dating; dosimetric applications of track etching; vacuum chambers of radiation measurement. The text also describes wall-less detectors in microdosimetry; dosimetry of low-energy X-rays; and the theory and general applicability of the gamma-ray theory of track effects to various systems. Dose equivalent determinations in neutron fields by means of moderator techniques; as well as developm

  18. Reconstructive dosimetry for cutaneous radiation syndrome

    Energy Technology Data Exchange (ETDEWEB)

    Lima, C.M.A.; Lima, A.R.; Degenhardt, Ä.L.; Da Silva, F.C.A., E-mail: dasilva@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Valverde, N.J. [Fundacao Eletronuclear de Assistencia Medica, Rio de Janeiro, RJ (Brazil)

    2015-10-15

    According to the International Atomic Energy Agency (IAEA), a relatively significant number of radiological accidents have occurred in recent years mainly because of the practices referred to as potentially high-risk activities, such as radiotherapy, large irradiators and industrial radiography, especially in gammagraphy assays. In some instances, severe injuries have occurred in exposed persons due to high radiation doses. In industrial radiography, 80 cases involving a total of 120 radiation workers, 110 members of the public including 12 deaths have been recorded up to 2014. Radiological accidents in industrial practices in Brazil have mainly resulted in development of cutaneous radiation syndrome (CRS) in hands and fingers. Brazilian data include 5 serious cases related to industrial gammagraphy, affecting 7 radiation workers and 19 members of the public; however, none of them were fatal. Some methods of reconstructive dosimetry have been used to estimate the radiation dose to assist in prescribing medical treatment. The type and development of cutaneous manifestations in the exposed areas of a person is the first achievable gross dose estimation. This review article presents the state-of-the-art reconstructive dosimetry methods enabling estimation of local radiation doses and provides guidelines for medical handling of the exposed individuals. The review also presents the Chilean and Brazilian radiological accident cases to highlight the importance of reconstructive dosimetry. (author)

  19. Dosimetry of neutron irradiations

    International Nuclear Information System (INIS)

    Biological dosimetry of neutron irradiation appears to be of great difficulty due to the multiparametric aspect of the relative biological effectiveness and the heterogeneity of the neutron dose distribution. Dosimetry by sodium 24 activation which can be performed by means of portable radiameters appears to be very useful for early triage within the 3 h following neutron irradiation, whereas hematological dosimetry by slope and level analysis of the lymphocyte drop cannot be used in this case. Chromosomic aberration analysis allows to evaluate the neutron dose heterogeneity by the frequency measurement of acentric fragments not originating from the formation of dicentrics or rings. Finally, recent experimental data on large primate models (baboons) have shown that some plasma hemostasia factors appear to be reliable biological indicators and noticeable markers of the prognosis of neutron irradiation

  20. Interstitial brachytherapy dosimetry update

    International Nuclear Information System (INIS)

    In March 2004, the American Association of Physicists in Medicine (AAPM) published an update to the AAPM Task Group No. 43 Report (TG-43) which was initially published in 1995. This update was pursued primarily due to the marked increase in permanent implantation of low-energy photon-emitting brachytherapy sources in the United States over the past decade, and clinical rationale for the need of accurate dosimetry in the implementation of interstitial brachytherapy. Additionally, there were substantial improvements in the brachytherapy dosimetry formalism, accuracy of related parameters and methods for determining these parameters. With salient background, these improvements are discussed in the context of radiation dosimetry. As an example, the impact of this update on the administered dose is assessed for the model 200 103Pd brachytherapy source. (authors)

  1. Secondary standards dosimetry laboratories

    International Nuclear Information System (INIS)

    The Secondary Standards Dosimetry Laboratory (SSDL) is part of an international network of dosimetry laboratories established by the IAEA and WHO. The network services maintain the consistency and accuracy of the therapeutic dose by exercising a national and international intercomparison program as well as providing calibration services to the end users, mainly radiotherapy departments in hospitals. The SSDL's are designated by national laboratories (such as Primary Standards Dosimetry Laboratories, PSDL's) to provide national and international absorbed dose traceability for users in that country. The advantage of the SSDL is that the absorbed dose measurements are consistent among the stakeholder countries.The Physics and Safety divisions have recently re-established an SSDL at ANSTO. The SSDL utilises a collimated cobalt-60 source of activity 170 TBq and dose rate of SmGy/sec at 1 metre (within ±2%), and provides a service to calibrate therapy level thimble ionisation chambers and electrometers

  2. Nuclear medicine radiation dosimetry

    CERN Document Server

    McParland, Brian J

    2010-01-01

    Complexities of the requirements for accurate radiation dosimetry evaluation in both diagnostic and therapeutic nuclear medicine (including PET) have grown over the past decade. This is due primarily to four factors: growing consideration of accurate patient-specific treatment planning for radionuclide therapy as a means of improving the therapeutic benefit, development of more realistic anthropomorphic phantoms and their use in estimating radiation transport and dosimetry in patients, design and use of advanced Monte Carlo algorithms in calculating the above-mentioned radiation transport and

  3. EURADOS trial performance test for photon dosimetry

    International Nuclear Information System (INIS)

    Within the framework of the EURADOS Action entitled Harmonisation and Dosimetric Quality Assurance in Individual Monitoring for External Radiation, trial performance tests for whole-body and extremity personal dosemeters were carried out. Photon, beta and neutron dosemeters were considered. This paper summarises the results of the whole-body photon dosemeter test. Twenty-six dosimetry services from all EU Member States and Switzerland participated. Twelve different radiation fields were used to simulate various workplace irradiation fields. Dose values from 0.4 mSv to 80 mSv were chosen. From 312 single results, 26 fell outside the limits of the trumpet curve and 32 were outside the range 1/1.5. Most outliers resulted from high energy R-F irradiations without electronic equilibrium. These fields are not routinely encountered by many of the participating dosimetry services. If the results for this field are excluded, most participating services satisfied the evaluation criteria. (author)

  4. Status of radiation processing dosimetry

    DEFF Research Database (Denmark)

    Miller, A.

    Several milestones have marked the field of radiation processing dosimetry since IMRP 7. Among them are the IAEA symposium on High Dose Dosimetry for Radiation Processing and the international Workshops on Dosimetry for Radiation Processing organized by the ASTM. Several standards have been or are...... being published by the ASTM in this field, both on dosimetry procedures and on the proper use of specific dosimeter systems. Several individuals are involved in this international cooperation which contribute significantly to the broader understanding of the role of dosimetry in radiation processing....... The importance of dosimetry is emphasized in the standards on radiation sterilization which are currently drafted by the European standards organization CEN and by the international standards organization ISO. In both standards, dosimetry plays key roles in characterization of the facility, in...

  5. Quality control and quality assurance philosophy introduced in national personnel dosimetry service

    International Nuclear Information System (INIS)

    There in National Personnel Dosimetry Service (NPDS) the implementation of the control system to guarantee the credibility of the measured personal dose equivalents results was given on the basis of the international recommendations published by the European Commission and the IAEA and in particular of the decree of the SUJB No. 132/2008 Coll. The quality control and the quality assurance are carried out in all three personal dosimetry services introduced in NPDS: in the film badge, thermoluminescent (TL) and neutron dosimetry. (authors)

  6. Home Automation

    OpenAIRE

    Ahmed, Zeeshan

    2010-01-01

    In this paper I briefly discuss the importance of home automation system. Going in to the details I briefly present a real time designed and implemented software and hardware oriented house automation research project, capable of automating house's electricity and providing a security system to detect the presence of unexpected behavior.

  7. Ion storage dosimetry

    Science.gov (United States)

    Mathur, V. K.

    2001-09-01

    The availability of a reliable, accurate and cost-effective real-time personnel dosimetry system is fascinating to radiation workers. Electronic dosimeters are contemplated to meet this demand of active dosimetry. The development of direct ion storage (DIS) dosimeters, a member of the electronic dosimeter family, for personnel dosimetry is also an attempt in this direction. DIS dosimeter is a hybrid of the well-established technology of ion chambers and the latest advances in data storage using metal oxide semiconductor field effect transistor (MOSFET) analog memory device. This dosimeter is capable of monitoring legal occupational radiation doses of gamma, X-rays, beta and neutron radiation. Similar to an ion chamber, the performance of the dosimeter for a particular application can be optimized through the selection of appropriate wall materials. The use of the floating gate of a MOSFET as one of the electrodes of the ion chamber allows the miniaturization of the device to the size of a dosimetry badge and avoids the use of power supplies during dose accumulation. The concept of the device, underlying physics and the design of the DIS dosimeter are discussed. The results of preliminary testing of the device are also provided.

  8. Individual Dosimetry Service

    CERN Multimedia

    2004-01-01

    We inform all staffs and users under regular dosimetry control that the dosimeters for the monitoring period MAY-JUNE 2004 are available from their usual dispatchers. Please have your films changed before the 11th MAY 2004. The color of the dosimeter valid in MAY-JUNE 2004 is YELLOW.

  9. Individual dosimetry service

    CERN Multimedia

    2004-01-01

    We inform all staffs and users under regular dosimetry control that the dosimeters for the monitoring period MARCH/APRIL 2004 are available from their usual dispatchers. Please have your films changed before the 11th MARCH 2004. The color of the dosimeter valid in MARCH/APRIL 2004 is BLUE.

  10. Individual dosimetry service

    CERN Multimedia

    2004-01-01

    We inform all staff and users under regular dosimetry control that the dosimeters for the monitoring period JULY-AUGUST 2004 are available from their usual dispatchers. Please have your films changed before the 15 JULY 2004. The color of the dosimeter valid in July-August 2004 is PINK.

  11. Dosimetry in diagnostic radiology

    International Nuclear Information System (INIS)

    Dosimetry is an area of increasing importance in diagnostic radiology. There is a realisation amongst health professionals that the radiation dose received by patients from modern X-ray examinations and procedures can be at a level of significance for the induction of cancer across a population, and in some unfortunate instances, in the acute damage to particular body organs such as skin and eyes. The formulation and measurement procedures for diagnostic radiology dosimetry have recently been standardised through an international code of practice which describes the methodologies necessary to address the diverging imaging modalities used in diagnostic radiology. Common to all dosimetry methodologies is the measurement of the air kerma from the X-ray device under defined conditions. To ensure the accuracy of the dosimetric determination, such measurements need to be made with appropriate instrumentation that has a calibration that is traceable to a standards laboratory. Dosimetric methods are used in radiology departments for a variety of purposes including the determination of patient dose levels to allow examinations to be optimized and to assist in decisions on the justification of examination choices. Patient dosimetry is important for special cases such as for X-ray examinations of children and pregnant patients. It is also a key component of the quality control of X-ray equipment and procedures.

  12. Ion-kill dosimetry

    Science.gov (United States)

    Katz, R.; Cucinotta, F. A.; Fromm, M.; Chambaudet, A.

    2001-01-01

    Unanticipated late effects in neutron and heavy ion therapy, not attributable to overdose, imply a qualitative difference between low and high LET therapy. We identify that difference as 'ion kill', associated with the spectrum of z/beta in the radiation field, whose measurement we label 'ion-kill dosimetry'.

  13. High frequency electromagnetic dosimetry

    CERN Document Server

    Sánchez-Hernández, David A

    2009-01-01

    Along with the growth of RF and microwave technology applications, there is a mounting concern about the possible adverse effects over human health from electromagnetic radiation. Addressing this issue and putting it into perspective, this groundbreaking resource provides critical details on the latest advances in high frequency electromagnetic dosimetry.

  14. Dosimetry of pion beams

    International Nuclear Information System (INIS)

    Negative pion beams are probably the most esoteric and most complicated type of radiation which has been suggested for use in clinical radiotherapy. Because of the limited availability of pion beams in the past, even to nuclear physicists, there exist relatively fewer basic data for this modality. Pion dosimetry is discussed

  15. The ARN critical dosimetry system

    International Nuclear Information System (INIS)

    The ARN critical dosimetry system is shown in this work. It includes personal and area dosemeters, and the information of typical spectra. The spectra of the critical facilities in our country are characterised by measurements with our Bonner Sphere System (BSS) or by computational methods in order to evaluate the dose in each case with the actual spectrum. The personal and area dosemeters are able to evaluate the gamma and neutron contributions. The detectors used are thermoluminescents, (TLD) 7Li:Mg,Ti for gamma and threshold detectors (Indium and sulphur pellets) and activation detectors Au (bare and Cd cover) for neutron. The Gamma-ray spectrometry is made with GeHp and MCA (Canberra) calibrated with 133Ba and 137Cs sources. The Beta-ray counting is made with a Geiger Muller (LND)(8%) with an electronic counter prototype developed in Argentina. The system is calibrated with the tioacetamida-technique carried out in our chemistry laboratory. The TLD are calibrated in Argentine SSDL with 60Co source, free in air. The calibration curve has been extended up to 10Gy. The neutron fluence distribution is obtained considering the thermal region as a Maxwellian distribution with a modal energy of 0.0253 eV and the intermediate region with a 1/E spectrum from 0.5 eV to E=200 keV. The basic data are the measured activities in the gold foils. The fast neutron fluence is calculated considering the mean cross section for the selected spectrum over the energy range. The basic data are the measured activities in indium foil and sulphur pellets with threshold energy of 1.7MeV and 2.5MeV respectively. The neutron kerma dose, the recoil charged particle dose and the contribution of the 1H(n, γ) 2H dose component, are calculated applying the dose conversion factors published in TRS211. The area dosemeter gives the gamma incident radiation kerma, and the personal dosemeter, the gamma total dose. This system has participated at the International Intercomparison of Criticality

  16. Critical Reflections on Neutron Dosimetry

    International Nuclear Information System (INIS)

    Neutron dosimetry is unsatisfactory at present because the true meaning of the experimental data is not clear. Flux measurements cannot be used to determine the absorbed doses without simultaneous measurement of the spectral distribution of the neutrons, whose QF varies considerably according to the energy. Even with a unit of absorbed dose such as the rad (whose definition is based on physical measuring systems), there is still the problem of how to measure the absorbed energy. Essentially, an instrument for measuring absorbed doses should satisfy at least the following conditions: (1) It should produce no change in the primary flux incident on the subject or should modify it in the same proportions as the subject. (2) It should indicate the absorbed energy accurately. Calorimetric measurements come to mind, but they are insufficiently sensitive (100 rads/min in a substance of unit specific heat produces a temperature rise of 2.5 x 10-4 degC/min). (3) The absorbed energy per unit mass of the dosimeter should be equal or proportional to that absorbed per unit mass of human tissue. Personal dosimetry by means of film badges is inaccurate and insufficiently sensitive. At present, the most reliable dose measurements are those made with tissue-equivalent ionization chambers, but these, too, are unsatisfactory, at least for neutrons of energy between 0.025 eV and 20 keV and above 30 MeV. The authors propose a method for measuring high-energy neutron doses capable of causing nuclear disintegrations in the body. (author)

  17. A new method of fast neutron dosimetry using nuclear emulsions

    International Nuclear Information System (INIS)

    A new high sensitivity neutron dosimetry method in mixed fluxes applicable to an extensive automatic radiological personal monitoring of workers professionally exposed to radiation is performed through the neutron activation of residual silver grains constituting tracks due to proton recoil from elastic reaction (n, p) in nuclear photographic emulsion

  18. Computational methods in several fields of radiation dosimetry

    International Nuclear Information System (INIS)

    Full text: Radiation dosimetry has to cope with a wide spectrum of applications and requirements in time and size. The ubiquitous presence of various radiation fields or radionuclides in the human home, working, urban or agricultural environment can lead to various dosimetric tasks starting from radioecology, retrospective and predictive dosimetry, personal dosimetry, up to measurements of radionuclide concentrations in environmental and food product and, finally in persons and their excreta. In all these fields measurements and computational models for the interpretation or understanding of observations are employed explicitly or implicitly. In this lecture some examples of own computational models will be given from the various dosimetric fields, including a) Radioecology (e.g. with the code systems based on ECOSYS, which was developed far before the Chernobyl reactor accident, and tested thoroughly afterwards), b) Internal dosimetry (improved metabolism models based on our own data), c) External dosimetry (with the new ICRU-ICRP-Voxelphantom developed by our lab), d) Radiation therapy (with GEANT IV as applied to mixed reactor radiation incident on individualized voxel phantoms), e) Some aspects of nanodosimetric track structure computations (not dealt with in the other presentation of this author). Finally, some general remarks will be made on the high explicit or implicit importance of computational models in radiation protection and other research field dealing with large systems, as well as on good scientific practices which should generally be followed when developing and applying such computational models

  19. New modalities (setting, fractionation) of radioimmunotherapy by 90Y-ibritumomab tiuxetan (90Y zevalin) in first line treatment of follicular type non Hodgkin malignant lymphomas: efficiency, toxicity and personalized dosimetry approach

    International Nuclear Information System (INIS)

    Rationale: radioimmunotherapy (R.I.T.) with 90Y-ibritumomab tiuxetan ([90Y] Zevalin ) is a new treatment option for patients with relapsed/refractory non Hodgkin follicular lymphoma (F.L.). Efficacy increases when Zevalin is used earlier in the disease course. Currently, Zevalin dosage is based on weight and not dosimetry. This most likely results in a wide range of absorbed dose to critical organs and tumor, which in turn translates in unpredictable efficacy and toxicity. Optimizing R.I.T. with [90Y] Zevalin will require its use as part of first-line therapy and implementation of patient-specific dosimetry methods in clinical trials. Objectives and methods: we have consecutively studied 2 new modalities of using Zevalin in first line therapy of F.L.. First, we conducted an international, randomized, phase 3 trial to evaluate the efficacy and safety of consolidation with Zevalin(15 MBq/Kg) in patients with advanced-stage F.L. achieving at least a partial response after induction immuno chemotherapy. A second approach consisted of evaluating a fractionated schedule with 2 doses of Zevalin (11.1 MBq/kg each), 9 to 13 weeks apart, as front line therapy in F.L. patients with high tumor burden. As part of this second approach, we designed a refined imaging-based (planar and 3-dimensional) dosimetry protocol to improve prediction of dose efficacy and toxicity after each dose of zevalin. Data acquisition was performed in 3 centers (Lille, Nantes and Manchester) while data treatment and specific dose calculations for major organ, tumor masses and bone marrow were centralized. Conclusion: Consolidation of first remission with 90Y-ibritumomab tiuxetan in advanced-stage follicular lymphoma is highly effective with no unexpected toxicities, prolonging P.F.S. by 2 years and resulting in high P.R.-to-C.R. conversion rates regardless of type of first-line induction treatment. Preliminary data show the feasibility of front line fractionated R.I.T. with Zevalin in patient with high

  20. Radiation protection dosimetry in medicine - Report of the working group n.9 of the European radiation dosimetry group (EURADOS) - coordinated network for radiation dosimetry (CONRAD - contract EC N) fp6-12684; Dosimetrie pour la radioprotection en milieu medical - rapport du groupe de travail n. 9 du European radiation dosimetry group (EURADOS) - coordinated netword for radiation dosimetry (CONRAD - contrat CE fp6-12684)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    This report present the results achieved within the frame of the work the WP 7 (Radiation Protection Dosimetry of Medical Staff) of the coordination action CONRAD (Coordinated Network for Radiation Dosimetry) funded through the 6. EU Framework Program. This action was coordinated by EURADOS (European Radiation Dosimetry Group). EURADOS is an organization founded in 1981 to advance the scientific understanding and the technical development of the dosimetry of ionising radiation in the fields of radiation protection, radiobiology, radiation therapy and medical diagnosis by promoting collaboration between European laboratories. WP7 coordinates and promotes European research for the assessment of occupational exposures to staff in therapeutic and diagnostic radiology workplaces. Research is coordinated through sub-groups covering three specific areas: 1. Extremity dosimetry in nuclear medicine and interventional radiology: this sub-group coordinates investigations in the specific fields of the hospitals and studies of doses to different parts of the hands, arms, legs and feet; 2. Practice of double dosimetry: this sub-group reviews and evaluates the different methods and algorithms for the use of dosemeters placed above and below lead aprons in large exposure during interventional radiology procedures, especially to determine effective doses to cardiologists during cardiac catheterization; and 3. Use of electronic personal dosemeters in interventional radiology: this sub-group coordinates investigations in laboratories and hospitals, and intercomparisons with passive dosemeters with the aim to enable the formulation of standards. (authors)

  1. Dosimetry for food irradiation

    International Nuclear Information System (INIS)

    A Manual of Food Irradiation Dosimetry was published in 1977 under the auspices of the IAEA as Technical Reports Series No. 178. It was the first monograph of its kind and served as a reference in the field of radiation processing and in the development of standards. While the essential information about radiation dosimetry in this publication has not become obsolete, other publications on radiation dosimetry have become available which have provided useful information for incorporation in this updated version. There is already a Codex General Standard for Irradiated Foods and an associated Code of Practice for Operation of Irradiation Facilities used for Treatment of Food, issued in 1984 by the Codex Alimentarius Commission of the FAO/WHO Food Standard Programme. The Codex Standard contains provisions on irradiation facilities and process control which include, among other requirements, that control of the processes within facilities shall include the keeping of adequate records including quantitative dosimetry. Appendix A of the Standard provides an explanation of process control and dosimetric requirements in compliance with the Codex Standard. By 1999, over 40 countries had implemented national regulations or issued specific approval for certain irradiated food items/classes of food based on the principles of the Codex Standard and its Code of Practice. Food irradiation is thus expanding, as over 30 countries are now actually applying this process for the treatment of one or more food products for commercial purposes. Irradiated foods are being marketed at retail level in several countries. With the increasing recognition and application of irradiation as a sanitary and phytosanitary treatment of food based on the provisions of the Agreement on the Application of Sanitary and Phytosanitary Measures of the World Trade Organization, international trade in irradiated food is expected to expand during the next decade. It is therefore essential that proper dosimetry

  2. Factors influencing EPR dosimetry in fingernails

    International Nuclear Information System (INIS)

    The technique based on the detection of ionizing radiation induced radicals by EPR in tooth enamel is an established method for the dosimetry of exposed persons in radiological emergencies. Dosimetry based on EPR spectral analysis of fingernail clippings, currently under development, has the practical advantage of the easier sample collection. A limiting factor is that overlapping the radiation induced signal (RIS), fingernails have shown the presence of two mechanically induced signals, called MIS1 and MIS2, due to elastic and plastic deformation respectively, at the time of fingernails cutting. With a water treatment, MIS1 is eliminated while MIS2 is considerably reduced. The calibration curves needed for radiation accident dosimetry should have 'universal' characteristics, ie. Represent the variability that can be found in different individuals. Early studies were directed to the analysis of factors affecting the development of such universal calibration curves. The peak to peak amplitude of the signal before and after the water treatment as well as the effect of size and number of clippings were studied. Furthermore, the interpersonal and intrapersonal variability were analyzed. Taking into account these previous studies, the optimal conditions for measurement were determined and EPR spectra of samples irradiated at different doses were used for the developing of dose-response curves. This paper presents the analysis of the results.(authors)

  3. Modern methods of personnel dosimetry

    International Nuclear Information System (INIS)

    The physical properties of radiation detectors for personnel dosimetry are described and compared. The suitability of different types of dosimeters for operational and central monitoring of normal occupational exposure, for accident and catastrophe dosimetry and for background and space-flight dosimetry is discussed. The difficulties in interpreting the dosimeter reading with respect to the dose in individual body organs are discussed briefly. 430 literature citations (up to Spring 1966) are given

  4. The dosimetry of ionizing radiation

    CERN Document Server

    1990-01-01

    A continuation of the treatise The Dosimetry of Ionizing Radiation, Volume III builds upon the foundations of Volumes I and II and the tradition of the preceeding treatise Radiation Dosimetry. Volume III contains three comprehensive chapters on the applications of radiation dosimetry in particular research and medical settings, a chapter on unique and useful detectors, and two chapters on Monte Carlo techniques and their applications.

  5. Eurados trial performance test for photon dosimetry

    DEFF Research Database (Denmark)

    Stadtmann, H.; Bordy, J.M.; Ambrosi, P.;

    2001-01-01

    Within the framework of the EURADOS Action entitled Harmonisation and Dosimetric Quality Assurance in Individual Monitoring for External Radiation, trial performance tests for whole-body and extremity personal dosemeters were carried out. Photon, beta and neutron dosemeters were considered. This...... paper summarises the results of the whole-body photon dosemeter test. Twenty-six dosimetry services from all EU Member States and Switzerland participated. Twelve different radiation fields were used to simulate various workplace irradiation fields. Dose values from 0.4 mSv to 80 mSv were chosen. From...

  6. Neutron spectrometry and dosimetry with ANNs

    International Nuclear Information System (INIS)

    Artificial neural networks technology has been applied to unfold the neutron spectra and to calculate the effective dose, the ambient equivalent dose, and the personal dose equivalent for 252Cf and 241AmBe neutron sources. A Bonner sphere spectrometry with a 6LiI(Eu) scintillator was utilized to measure the count rates of the spheres that were utilized as input in two artificial neural networks, one for spectrometry and another for dosimetry. Spectra and the ambient dose equivalent were also obtained with BUNKIUT code and the UTA4 response matrix. With both procedures spectra and ambient dose equivalent agrees in less than 10%. (author)

  7. Neutron beam measurement dosimetry

    International Nuclear Information System (INIS)

    This report describes animal dosimetry studies and phantom measurements. During 1994, 12 dogs were irradiated at BMRR as part of a 4 fraction dose tolerance study. The animals were first infused with BSH and irradiated daily for 4 consecutive days. BNL irradiated 2 beagles as part of their dose tolerance study using BPA fructose. In addition, a dog at WSU was irradiated at BMRR after an infusion of BPA fructose. During 1994, the INEL BNCT dosimetry team measured neutron flux and gamma dose profiles in two phantoms exposed to the epithermal neutron beam at the BMRR. These measurements were performed as a preparatory step to the commencement of human clinical trials in progress at the BMRR

  8. Ambiguities in thermoluminescence dosimetry

    International Nuclear Information System (INIS)

    On one hand, thermoluminescence dosimetry is one of most reliable, rugged and economical system of passive dosimetry but on the other hand there are several ambiguities, which need attention. The PTTL is a complex phenomenon and it is difficult to identify the source for the transfer of the charge carrier to repopulate the traps related to the glow peaks. For the photon energy dependence it is difficult to explain the change in the response for 662 keV gamma rays of 137Cs as compared to the response for 1.25 MeV gamma rays of 60Co. The increase in the response of a TLD with increasing heating rate poses another ambiguity and so is the case with the observations of the supra linearity of different glow peaks. To over come the ambiguities, efforts have to continue to enhance the understanding and to harmonize the protocol for reliable experimental data

  9. Neutron beam measurement dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Amaro, C.R. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

    1995-11-01

    This report describes animal dosimetry studies and phantom measurements. During 1994, 12 dogs were irradiated at BMRR as part of a 4 fraction dose tolerance study. The animals were first infused with BSH and irradiated daily for 4 consecutive days. BNL irradiated 2 beagles as part of their dose tolerance study using BPA fructose. In addition, a dog at WSU was irradiated at BMRR after an infusion of BPA fructose. During 1994, the INEL BNCT dosimetry team measured neutron flux and gamma dose profiles in two phantoms exposed to the epithermal neutron beam at the BMRR. These measurements were performed as a preparatory step to the commencement of human clinical trials in progress at the BMRR.

  10. Sixth symposium on neutron dosimetry

    International Nuclear Information System (INIS)

    This booklet contains all abstracts of papers presented in 13 sessions. Main topics: Cross sections and Kerma factors; analytical radiobiology; detectors for personnel monitoring; secondary charged particles and microdosimetric basis of q-value for neutrons; personnel dosimetry; concepts for radiation protection; ambient monitoring; TEPC and ion chambers in radiation protection; beam dosimetry; track detectors (CR-39); dosimetry at biomedical irradiation facilities; health physics at therapy facilities; calibration for radiation protection; devices for beam dosimetry (TLD and miscellaneous); therapy and biomedical irradiation facilities; treatment planning. (HP)

  11. Personnel radiation dosimetry

    International Nuclear Information System (INIS)

    The book contains the 21 technical papers presented at the Technical Committee Meeting to Elaborate Procedures and Data for the Intercomparison of Personnel Dosimeters organizaed by the IAEA on 22-26 April 1985. A separate abstract was prepared for each of these papers. A list of areas in which additional research and development work is needed and recommendations for an IAEA-sponsored intercomparison program on personnel dosimetry is also included

  12. Dosimetry: an ARDENT topic

    CERN Multimedia

    CERN Bulletin

    2012-01-01

    The first annual ARDENT workshop took place in Vienna from 20 to 23 November. The workshop gathered together the Early-Stage Researchers (ESR) and their supervisors, plus other people involved from all the participating institutions.   “The meeting, which was organised with the local support of the Austrian Institute of Technology, was a nice opportunity for the ESRs to get together, meet each other, and present their research plans and some preliminary results of their work,” says Marco Silari, a member of CERN Radiation Protection Group and the scientist in charge of the programme. Two full days were devoted to a training course on radiation dosimetry, delivered by renowned experts. The workshop closed with a half-day visit to the MedAustron facility in Wiener Neustadt. ARDENT (Advanced Radiation Dosimetry European Network Training) is a Marie Curie ITN project funded under EU FP7 with €4 million. The project focuses on radiation dosimetry exploiting se...

  13. Dosimetry of the patient and occupational in interventional procedures

    International Nuclear Information System (INIS)

    The big necessity to estimate the entrance doses in skin that the patients receive when are exposed to interventional procedures and the personal dosimetry of the professionals that work in these procedures in operating room, has taken to the analysis of different possibilities that allow to carry out these estimates. The objective of this work was to analyze the possibility of using Optically Stimulated Luminescence dosimeters; comparing the results with ionizing cameras and electronic personal dosimeters. To carry out these estimates, we work with a X-ray equipment Phillips Allure, acrylic phantoms, a dosimetry system formed by ionization camera and dosimeter UNIDOS E, OSL (Nano dots) dosimeters and electronic lavalieres Aloka brand, PDM 117 models. To estimate the doses that the patients receive, entrance dose was measured in skin and in personal dosimetry inside places where the medical professionals are habitually located in different situations among 5 and 60 irradiation min. In the case of direct radiation, the OSL (Nano dots) present reliable readings and only were dispersed values for the measurements of secondary radiation. The measured values and the linking among them were also analyzed. The OSL (Nano dot) dosimetry behaves reliable way when is located in the ranges of more dose to 0,1 mGy, according to the maker indications and fundamentally for direct beams of the hemodynamics equipment being ideal for the measurement of entrance dose in skin. For the Nano dots use in personal dosimetry the results should be read carefully for values major to 0,1 mGy and being completely inappropriate for minor values. (Author)

  14. IAEA/WHO TLD postal dose audit service and high precision measurements for radiotherapy level dosimetry

    International Nuclear Information System (INIS)

    Since 1969 the International Atomic Energy Agency, together with the World Health Organization, has performed postal TLD audits to verify calibration of radiotherapy beams in developing countries. The TLD programme also monitors activities of Secondary Standard Dosimetry Laboratories (SSDLs). The programme has checked approximately 4000 clinical beams in over 1100 hospitals, and in many instances significant errors have been detected in the beam calibration. Subsequent follow-up actions help to resolve the discrepancies, thus preventing further mistreatment of patients. The audits for SSDLs check the implementation of the dosimetry protocol in order to assure proper dissemination of dosimetry standards to the end-users. The TLD audit results for SSDLs show good consistency in the basic dosimetry worldwide. New TLD procedures and equipment have recently been introduced by the IAEA that include a modified TLD calibration methodology and computerised tools for automation of dose calculation from TLD readings. (author)

  15. Advances in biomedical dosimetry

    International Nuclear Information System (INIS)

    Full text: Radiation dosimetry, the accurate determination of the absorbed dose within an irradiated body or a piece of material, is a prerequisite for all applications of ionizing radiation. This has been known since the very first radiation applications in medicine and biology, and increasing efforts are being made by radiation researchers to develop more reliable, effective and safe instruments, and to further improve dosimetric accuracy for all types of radiation used. Development of new techniques and instrumentation was particularly fast in the field of both medical diagnostic and therapeutic radiology. Thus, in Paris in October the IAEA held the latest symposium in its continuing series on dosimetry in medicine and biology. The last one was held in Vienna in 1975. High-quality dosimetry is obviously of great importance for human health, whether the objectives lie in the prevention and control of risks associated with the nuclear industry, in medical uses of radioactive substances or X-ray beams for diagnostic purposes, or in the application of photon, electron or neutron beams in radiotherapy. The symposium dealt with the following subjects: General aspects of dosimetry; Special physical and biomedical aspects; Determination of absorbed dose; Standardization and calibration of dosimetric systems; and Development of dosimetric systems. The forty or so papers presented and the discussions that followed them brought out a certain number of dominant themes, among which three deserve particular mention. - The recent generalization of the International System of Units having prompted a fundamental reassessment of the dosimetric quantities to be considered in calibrating measuring instruments, various proposals were advanced by the representatives of national metrology laboratories to replace the quantity 'exposure' (SI unit = coulomb/kg) by 'Kerma' or 'absorbed dose' (unit joule/kg, the special name of which is 'gray'), this latter being closer to the practical

  16. The micronucleus test in biological dosimetry

    International Nuclear Information System (INIS)

    The determination of micronuclei in lymphocytes on the basis of the Cytochalasine B method may already be regarded as a most useful tool following short-term wholebody exposure to doses in the range between approx. 0.3 and 7 Gy and thus offers a genuine alternative to the conventional analysis of chromosomes. Further efforts in the research on micronuclei as a biological system of dosimetry should primarily be made in the field of radiosensitive subpopulations and, additionally, the field of automated evaluation procedures. It is to be expected that this will permit the limit of detection to be lowered to doses of even less than approx. 0.2 - 0.3 Gy. (orig.)

  17. Dose computation algorithms for individual thermoluminescence dosimetry

    International Nuclear Information System (INIS)

    Dose computation algorithms have been developed for interpretation of the TL readings obtained from three CaSO4:Dy-Teflon dosemeters positioned in the presently used TLD badge, in terms of equivalent dose. Algorithms are based on parametrization of the response to the various pure and mixed fields. It identifies the radiation field type, position of the badge during use i.e. above or below the lead apron and provide the equivalent dose making use of the appropriate correction factors. These algorithms have been successfully tested for routine personnel dosimetry and will be of great advantage with the TL reading system being coupled with PC for envisaged automation in large scale personnel monitoring programme. (author). 4 refs

  18. Time reduction and automation of routine planning activities through the use of macros

    International Nuclear Information System (INIS)

    The use of macros in scheduler automates Adac Pinnacle3 much of the routine activities in the planning process, from the display options and placement of beams, to, among other possibilities, systematic naming them and export of the physical and clinical dosimetry. This automation allows reduction of the times associated with the planning process and an error reduction.

  19. Library Automation

    OpenAIRE

    Dhakne, B. N.; Giri, V. V; Waghmode, S. S.

    2010-01-01

    New technologies library provides several new materials, media and mode of storing and communicating the information. Library Automation reduces the drudgery of repeated manual efforts in library routine. By use of library automation collection, Storage, Administration, Processing, Preservation and communication etc.

  20. Research needs related to internal dosimetry. Joint panel on occupational and environmental research for uranium production in Canada (JP-1)

    International Nuclear Information System (INIS)

    There are several important techniques of internal dosimetry for use with uranium mine and mill workers: personal radon daughter dosimetry, uranium content of urine, whole body counter to evaluate the uranium in lung burden, and assay of uranium in biopsy or autopsy tissue samples. There are problems with each of these techniques and further research is required in internal dosimetry (as well as the alternative of monitoring exposure levels). This research should be aimed at improved or supplementary dosimetry techniques, enhanced theoretical interpretation of dosimetry results and fundamental research not directly related to the techniques mentioned above. Proposals for research as presented by the working group in this report should be considered by funding organizations concerned with internal dosimetry as it relates to the uranium mining industry, and, since this report was first presented. AECB has proceeded with related projects. (author)

  1. Neutron dosimetry; Dosimetria de neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Fratin, Luciano

    1993-12-31

    A neutron irradiation facility was designed and built in order to establish a procedure for calibrating neutron monitors and dosemeters. A 185 GBq {sup 241} Am Be source of known is used as a reference source. The irradiation facility using this source in the air provides neutron dose rates between 9 nSv s{sup -1} and 0,5 {sup {mu}}Sv s{sup -1}. A calibrated 50 nSv s{sup -1} thermal neutron field is obtained by using a specially designed paraffin block in conjunction with the {sup 241} Am Be source. A Bonner multisphere spectrometer was calibrated, using a procedure based on three methods proposed by international standards. The unfold {sup 241} Am Be neutron spectrum was determined from the Bonner spheres data and resulted in a good agreement with expected values for fluence rate, dose rate and mean energy. A dosimetric system based on the electrochemical etching of CR-39 was developed for personal dosimetry. The dosemeter badge using a (n,{alpha}) converter, the etching chamber and high frequency power supply were designed and built specially for this project. The electrochemical etching (ECE) parameters used were: a 6N KOH solution, 59 deg C, 20 kV{sub pp} cm{sup -1}, 2,0 kHz, 3 hours of ECE for thermal and intermediate neutrons and 6 hours for fast neutrons. The calibration factors for thermal, intermediate and fast neutrons were determined for this personal dosemeter. The sensitivities determined for the developed dosimetric system were (1,46{+-} 0,09) 10{sup 4} tracks cm{sup -2} mSv{sup -1} for thermal neutrons, (9{+-}3) 10{sup 2} tracks cm{sup -2} mSV{sup -1} for intermediate neutrons and (26{+-}4) tracks cm{sup -2} mSv{sup -1} for fast neutrons. The lower and upper limits of detection were respectively 0,002 mSv and 0,6 mSv for thermal neutrons, 0,04 mSv and 8 mSv for intermediate neutrons and 1 mSv and 12 mSv for fast neutrons. In view of the 1990`s ICRP recommendations, it is possible to conclude that the personal dosemeter described in this work is

  2. Radiation-induced signals analysed by EPR spectrometry applied to fortuitous dosimetry

    International Nuclear Information System (INIS)

    Dosimetry based on the detection by electron paramagnetic resonance (EPR) spectroscopy of ionizing radiation-induced radicals is an established method for the retrospective dosimetry of past exposures and the dosimetry of potentially exposed persons in radiological emergencies. The dose is estimated by measuring the physical damage induced in materials contained in objects placed on or next to the potentially exposed person. The aim of this paper is to survey the current literature about methodologies and materials that have been proposed for EPR dosimetry, in order to identify those that could be suitable for population triage according to criteria such as ubiquity, non invasiveness and easy sample collection, presence of a post-irradiation EPR signal, negligible background signal, linearity of dose-response relationship, minimum detection limit and post-irradiation signal stability. The paper will survey the features of sugar, plastics, glass, clothing tissues, and solid biological tissues (nails, hair and calcified tissues).

  3. Implementation of a quality system based on ISO 9001 requirement in Malaysia national dosimetry services for monitoring external exposure

    International Nuclear Information System (INIS)

    Long term radiation protection activities in Malaysia has resulted in great efforts to improve mechanisms for controlling and monitoring of external radiation exposure. The requirements for the personal monitoring of Category A workers and of the area known as Personal Dosimetry Services is managed by the Secondary Standard Dosimetry Laboratory of Malaysian Institute for Nuclear Technology Research, SSDLMINT. SSDL-MINT is expanding into a new frontier in ensuring good quality personal dosimetry services for about 11,000 radiation workers from 1500 different workplaces throughout the country. Recent emphasis on the ISO requirements presents a new challenge to the existing system and offers global measurement harmonization for the radiation protection community. The essential elements of the certification for the SSDL-MINT Personal Dosimetry System are described. This paper provides an insight on the efforts of SSDL-MINT to provide a model national laboratory with emphasis on quality as the valuable and regular features of the activities. (author)

  4. The Hanford Emergency Dosimetry System

    International Nuclear Information System (INIS)

    The Hanford project is a major atomic industrial complex, including nuclear reactors, fuel fabrication plants, chemical separation facilities and research laboratories. In addition to a surveillance and control programme for personnel radiation exposures, an emergency dosimetry system has been developed to provide rapid assessment of high dose rates, identification and control of employees, staff notifications and formation of staff emergency control centres, assessment of external exposure doses, evaluation of body burdens of radioactive materials, detection and control of radioactive environmental contamination and rapid exposure estimates for guidance of rescue and medical personnel. Primary reliance is placed upon the Hanford Film Badge Dosimeter, worn by all persons within controlled areas. The badge provides positive identification of the wearer and the film can be evaluated within 90 min. Separately, yet simultaneously, the remaining components of the badge can be processed for determinations of the neutron spectrum and dose in five energy groups, as well as provide an early estimate of the single collision neutron dose from a few to several thousand rads. Gamma-ray detection ranges from 20 mr to 1500 r from the film components to 10 to 10 000 r from tantalum shielded fluorods. The emergency system includes programmes that ensure employee understanding, monitor training and management co-operation for fast identification, control and segregation of affected employees. Monitoring personnel, using portable instrumentation, obtain on-site in vivo measurements of Na24 or measurements of activated indium foil in the film-badge dosimeter for preliminary dose estimates. The staff notification and operation of emergency control centres provide technical guidance and mobile supportive equipment including a mobile whole-body counter. Back-up laboratory facilities give supportive dosimetry through the analysis of blood for Na24 activation, P32 hair content

  5. Spanish National Dosimetry Bank

    International Nuclear Information System (INIS)

    The National Dosimetry Bank (BDN) was designed to be a useful instrument for the protection of exposed workers. On the basis of individual doses, in conjunction with the type of facility where they were received and the type of work involved, it is possible to monitor and control the individual conditions of an exposed worker. In addition to this primary objective, the BDN's structure and utilities are such that it can be used for applications such as determining the suitability of the working conditions in various areas of ionizing radiation applications, evaluating exposure trends and the most affected areas, and supplying statistical data that can be used for legal studies

  6. Relocation of Dosimetry Service

    CERN Multimedia

    2007-01-01

    The Dosimetry Service is moving from Building 24 to Building 55 and will therefore be closed on Friday, March 30. From Monday, April 2 onwards you will find us in building 55/1-001. Please note that during that day we might still have some problems with the internet connections and cannot fully guarantee normal service procedures. The service's opening hours and telephone number will not change as a result of the move 8.30 - 12.00, afternoons closed Tel. 72155

  7. Individual dosimetry and calibration

    International Nuclear Information System (INIS)

    In 1995 both the Individual Dosimetry and Calibration Sections worked under the condition of a status quo and concentrated fully on the routine part of their work. Nevertheless, the machine for printing the bar code which will be glued onto the film holder and hence identify the people when entering into high radiation areas was put into operation and most of the holders were equipped with the new identification. As far as the Calibration Section is concerned the project of the new source control system that is realized by the Technical Support Section was somewhat accelerated

  8. Dosimetry in Radiology

    International Nuclear Information System (INIS)

    The steady growth in the use of ionizing radiation in diagnostic imaging requires to maintain a proper management of patient’s dose. Dosimetry in Radiology is a difficult topic to address, but vital for proper estimation of the dose the patient is receiving. The awareness that every day is perceived in our country on these issues is the appropriate response to this problem. This article describes the main dosimetric units used and easily exemplifies doses in radiology through internationally known reference values. (authors)

  9. Fast neutron dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    DeLuca, P.M. Jr.; Pearson, D.W.

    1992-01-01

    This progress report concentrates on two major areas of dosimetry research: measurement of fast neutron kerma factors for several elements for monochromatic and white spectrum neutron fields and determination of the response of thermoluminescent phosphors to various ultra-soft X-ray energies and beta-rays. Dr. Zhixin Zhou from the Shanghai Institute of Radiation Medicine, People's Republic of China brought with him special expertise in the fabrication and use of ultra-thin TLD materials. Such materials are not available in the USA. The rather unique properties of these materials were investigated during this grant period.

  10. Process automation

    International Nuclear Information System (INIS)

    Process automation technology has been pursued in the chemical processing industries and to a very limited extent in nuclear fuel reprocessing. Its effective use has been restricted in the past by the lack of diverse and reliable process instrumentation and the unavailability of sophisticated software designed for process control. The Integrated Equipment Test (IET) facility was developed by the Consolidated Fuel Reprocessing Program (CFRP) in part to demonstrate new concepts for control of advanced nuclear fuel reprocessing plants. A demonstration of fuel reprocessing equipment automation using advanced instrumentation and a modern, microprocessor-based control system is nearing completion in the facility. This facility provides for the synergistic testing of all chemical process features of a prototypical fuel reprocessing plant that can be attained with unirradiated uranium-bearing feed materials. The unique equipment and mission of the IET facility make it an ideal test bed for automation studies. This effort will provide for the demonstration of the plant automation concept and for the development of techniques for similar applications in a full-scale plant. A set of preliminary recommendations for implementing process automation has been compiled. Some of these concepts are not generally recognized or accepted. The automation work now under way in the IET facility should be useful to others in helping avoid costly mistakes because of the underutilization or misapplication of process automation. 6 figs

  11. Development of operation individual dosimetry programs in a developing country

    International Nuclear Information System (INIS)

    Development of Operational Individual Dosimetry (OID) Programs is the principle rationale for any national radiation protection regulatory program in both developed and developing countries. Individual dosimetry for external radiation means making exposure measurements by equipment carried out on the persons or workers. An operational individual dosimetry (OID) program is defined as development of a program in an operational state to provide national or institutional dosimetry services; i.e. to cover routine, operational and special monitoring as defined by ICRP 35. The development of an OID program depends on many legal, administrative, psychological and technical factors such as number of institutions and radiation workers or persons to be monitored, radiation types and conditions of the workplaces, the state of related sciences and technologies, radiation protection infrastructure as regard to laws and regulations, the existence of qualified leader and manpower, desire to develop such a program, degree of self-dependency required, etc. Although development of such a program is fairly easy with a proper arrangement, some problems still exist in particular in a developing country. In this paper, the stated points and recommendations for development of OID programs in developing countries based on the experiences of the Islamic Republic of Iran and some other countries are presented and discussed. (author). 32 refs

  12. 112: Rapid areal dosimetry using a computer based plastic scintillator-video camera system

    International Nuclear Information System (INIS)

    A novel water-tank dosimetry system is described based on capturing the scintillation emitted from an irradiated sheet of plastic scintillator immersed in water with a digital camera interfaced to an IBM PC/XT personal computer. Rapid areal dosimetry data are measured in seconds. Adequate data for the entire beam is obtained within one minute. Preliminary studies are promising, showing qualitatively good agreement with conventional methods. 3 refs.; 3 figs

  13. Dosimetry of industrial sources

    International Nuclear Information System (INIS)

    The gamma rays are produced during the disintegration of the atomic nuclei, its high energy allows them to cross thick materials. The capacity to attenuate a photons beam allows to determine the density, in line, of industrial interest materials as the mining. By means of two active dosemeters and a TLDs group (passive dosimetry) the dose rates of two sources of Cs-137 used for determining in line the density of mining materials were determined. With the dosemeters the dose levels in diverse points inside the grave that it harbors the sources and by means of calculations the isodoses curves were determined. In the phase of calculations was supposed that both sources were punctual and the isodose curves were calculated for two situations: naked sources and in their Pb packings. The dosimetry was carried out around two sources of 137Cs. The measured values allowed to develop a calculation procedure to obtain the isodoses curves in the grave where the sources are installed. (Author)

  14. Internal Dosimetry. Chapter 18

    International Nuclear Information System (INIS)

    The Committee on Medical Internal Radiation Dose (MIRD) is a committee within the Society of Nuclear Medicine. The MIRD Committee was formed in 1965 with the mission to standardize internal dosimetry calculations, improve the published emission data for radionuclides and enhance the data on pharmacokinetics for radiopharmaceuticals [18.1]. A unified approach to internal dosimetry was published by the MIRD Committee in 1968, MIRD Pamphlet No. 1 [18.2], which was updated several times thereafter. Currently, the most well known version is the MIRD Primer from 1991 [18.3]. The latest publication on the formalism was published in 2009 in MIRD Pamphlet No. 21 [18.4], which provides a notation meant to bridge the differences in the formalism used by the MIRD Committee and the International Commission on Radiological Protection (ICRP) [18.5]. The formalism presented in MIRD Pamphlet No. 21 [18.4] will be used here, although some references to the quantities and parameters used in the MIRD primer [18.3] will be made. All symbols, quantities and units are presented

  15. Thermo-luminescent dosimetry

    International Nuclear Information System (INIS)

    The development of paediatric radiology which began in the late 195O's has been characterised by the need to limit the dose of ionising radiation to which the child is subjected. The aim has been to keep radiation exposure as low as possible by the introduction of suitable techniques and by the development of new methods. It is therefore surprising that studies in dosimetry in the paediaytric age range have only been carried out in recent years. One reason for this may have been the fact that a suitable technique of measurement was not available at the time. The introduction of solid state dosimetry based on thermo-luminescence, first into radiotherapy (1968) and subsequently into radiodiagnosis, has made it possible to abandon the previously widely used ionisation chamber (1, 2, 3, 4, 6, 7, 10, 11, 12, 14, and 14). The purpose of the present paper is to indicate the suitability of this form of dose measurement for paediatric radiological purposes and to stimulate its application in this field. (orig.)

  16. Clinical dosimetry using mosfets

    International Nuclear Information System (INIS)

    Purpose: The use of metal oxide-silicon field effect transistors (MOSFETs) as clinical dosimeters is demonstrated for a number of patients with targets at different clinical sites. Methods and Materials: Commercially available MOSFETs were characterized for energy response, angular dependency of response, and effect of accumulated dose on sensitivity and some inherent properties of MOSFETs. The doses determined both by thermoluminescence dosimetry (TLD) and MOSFETs in clinical situation were evaluated and compared to expected doses determined by calculation. Results: It was observed that a standard calibration of 0.01 Gy/mV gave MOSFET determined doses which agreed with expected doses to within 5% at the 95% confidence limit for photon beams from 6 to 25 MV and electron beams from 5 to 14 MeV. An energy-dependent variation in response of up to 28% was observed between two orientations of a MOSFET. The MOSFET doses compared very well with the doses estimated by TLDs, and the patients tolerated MOSFETs very well. A standard deviation of 3.9% between expected dose and MOSFET determined dose was observed, while for TLDs the standard deviation was 5.1%. The advantages and disadvantages of using MOSFETs for clinical dosimetry are discussed in detail. Conclusion: It was concluded that MOSFETs can be used as clinical dosimeters and can be a good alternative to TLDs. However, they have limitations under certain clinical situations

  17. Radiation dosimetry in Cyprus

    International Nuclear Information System (INIS)

    Cyprus is a small island in the eastern part of the mediterranean sea with a population of 700,000. A small Physics Department in the Nicosia General Hospital is responsible for all matters related to ionising radiation. The main applications of ionising radiation are in medicine, some applications of radioisotopes in agriculture and hydrology research and very few applications in industry with sealed radiation sources. The same problems in radiation dosimetry are encountered as in any other countries but on a smaller scale. These have to be solved locally, because of the island's geographic isolation. All the infrastructure including Secondary Standard Dosemeters, field instruments and calibration sources is needed in order to achieve this, but the financial resources available are very limited. For this reason improvisation is often necessary. The Co-60 and other X-ray units intended for radiotherapy or other clinical use, are used as radiation sources for dosimetry and calibration of the instruments. Simple, locally made phantoms are designed in order to decrease costs whenever possible. (author). 7 refs, 1 fig

  18. Design and development of an automated, portable and handheld tablet personal computer-based data acquisition system for monitoring electromyography signals during rehabilitation.

    Science.gov (United States)

    Ahamed, Nizam U; Sundaraj, Kenneth; Poo, Tarn S

    2013-03-01

    This article describes the design of a robust, inexpensive, easy-to-use, small, and portable online electromyography acquisition system for monitoring electromyography signals during rehabilitation. This single-channel (one-muscle) system was connected via the universal serial bus port to a programmable Windows operating system handheld tablet personal computer for storage and analysis of the data by the end user. The raw electromyography signals were amplified in order to convert them to an observable scale. The inherent noise of 50 Hz (Malaysia) from power lines electromagnetic interference was then eliminated using a single-hybrid IC notch filter. These signals were sampled by a signal processing module and converted into 24-bit digital data. An algorithm was developed and programmed to transmit the digital data to the computer, where it was reassembled and displayed in the computer using software. Finally, the following device was furnished with the graphical user interface to display the online muscle strength streaming signal in a handheld tablet personal computer. This battery-operated system was tested on the biceps brachii muscles of 20 healthy subjects, and the results were compared to those obtained with a commercial single-channel (one-muscle) electromyography acquisition system. The results obtained using the developed device when compared to those obtained from a commercially available physiological signal monitoring system for activities involving muscle contractions were found to be comparable (the comparison of various statistical parameters) between male and female subjects. In addition, the key advantage of this developed system over the conventional desktop personal computer-based acquisition systems is its portability due to the use of a tablet personal computer in which the results are accessible graphically as well as stored in text (comma-separated value) form. PMID:23662342

  19. Radiation dosimetry instrumentation and methods

    CERN Document Server

    Shani, Gad

    2000-01-01

    Radiation dosimetry has made great progress in the last decade, mainly because radiation therapy is much more widely used. Since the first edition, many new developments have been made in the basic methods for dosimetry, i.e. ionization chambers, TLD, chemical dosimeters, and photographic films. Radiation Dosimetry: Instrumentation and Methods, Second Edition brings to the reader these latest developments. Written at a high level for medical physicists, engineers, and advanced dosimetrists, it concentrates only on evolvement during the last decade, relying on the first edition to provide the basics.

  20. Information from the Dosimetry Service

    CERN Multimedia

    2006-01-01

    Please note the following opening hours of the Service: From 31st July onwards: Every morning from 8:30 to 12:00 The Service is closed in the afternoons. We should like to remind you that dosimeters cannot be sent to customers by internal mail. Short-term dosimeters (VCTs) must always be returned to the Service after use and must not be left on the racks in the experimental areas or in the secretariats. Dosimetry Service Tel 72155 Bldg. 24 E 011 Dosimetry.service@cern.ch http://cern.ch/rp-dosimetry

  1. IAEA/RCA external dosimetry intercomparison (1995-97)

    International Nuclear Information System (INIS)

    IAEA/RCA personal dosimeters intercomparison of external radiation was conducted by JAERI during the year 1995-1997. 17 countries using 38 types of personnel dosimeters participated in this intercomparison. Out of 38 dosimetry systems 26 used TLD, 10 film badge and 2 RPL dosimeters. Our laboratory participated with BARC personal dosimeter badge using TLD (CaSO4:Dy). Reference calibration source check of the participating laboratories was done using RPL glass dosimetry by JAERI. The dosimeters of the participants were exposed to ISO x-ray beams and γ sources to low and moderate doses during phase 1 and to mixed x-ray beams, mixed x-γ radiation, non-perpendicular radiation and x and γ radiation separately in phase 2. The participant laboratories estimated the values of the exposures given in terms of operational quantities. The results of BARC/TLD badge are presented and compared with respect to other laboratories. (author)

  2. Dosimetry of hands and human factor

    International Nuclear Information System (INIS)

    The human factor in facilities where open radioactive sources are managed it can be controlled through the use of the ring dosimetry, however, that these devices only provide qualitative information that is not extrapolated to legislative limits. lt is present the case analysis of hands dosimetry of female person with responsibility for professional standards and a very high profile with ratings that allow her to have a high level of knowledge of the basic standards, and because with an attitude and a culture rooted of radiation protection, among other qualities. Their records reveal a trend in which monthly doses are below the 7 mSv, and only occasionally are between 7 and 12 mSv per month and hand. The other case correspond to a technician, trained in radiological techniques, also with a high profile, with two courses for occupationally exposed personnel more than 10 annual retraining, and work experience of over 10 years as occupationally exposed personnel, in which knowledge of standards and because of the entrenched culture of radiation protection and their interest degree in the care of their exposure is still in a phase half, in this case also shows a trend in the monthly dose where found registers between 7 and 11 mSv per month and hand. The third case is of a second technician with less experience and most basic knowledge, his dose register not show a real trend, sometimes be found reads of irregular values as if the dosimeter is not used and some other times as if misused by exposing to purpose (was observed at least one reading above the monthly 30 mSv). By way of conclusion, it is noted that the hands dosimetry is a useful tool to monitor transactions through the data compilation susceptible to analysis with variations which can be placed in the context of the human factor. (Author)

  3. Radioembolization Dosimetry: The Road Ahead

    Energy Technology Data Exchange (ETDEWEB)

    Smits, Maarten L. J., E-mail: m.l.j.smits-3@umcutrecht.nl; Elschot, Mattijs [University Medical Center Utrecht, Department of Radiology and Nuclear Medicine (Netherlands); Sze, Daniel Y. [Stanford University School of Medicine, Division of Interventional Radiology (United States); Kao, Yung H. [Austin Hospital, Department of Nuclear Medicine (Australia); Nijsen, Johannes F. W. [University Medical Center Utrecht, Department of Radiology and Nuclear Medicine (Netherlands); Iagaru, Andre H. [Stanford University School of Medicine, Division of Nuclear Medicine and Molecular Imaging (United States); Jong, Hugo W. A. M. de; Bosch, Maurice A. A. J. van den; Lam, Marnix G. E. H. [University Medical Center Utrecht, Department of Radiology and Nuclear Medicine (Netherlands)

    2015-04-15

    Methods for calculating the activity to be administered during yttrium-90 radioembolization (RE) are largely based on empirical toxicity and efficacy analyses, rather than dosimetry. At the same time, it is recognized that treatment planning based on proper dosimetry is of vital importance for the optimization of the results of RE. The heterogeneous and often clustered intrahepatic biodistribution of millions of point-source radioactive particles poses a challenge for dosimetry. Several studies found a relationship between absorbed doses and treatment outcome, with regard to both toxicity and efficacy. This should ultimately lead to improved patient selection and individualized treatment planning. New calculation methods and imaging techniques and a new generation of microspheres for image-guided RE will all contribute to these improvements. The aim of this review is to give insight into the latest and most important developments in RE dosimetry and to suggest future directions on patient selection, individualized treatment planning, and study designs.

  4. Carbon nanotube dosimetry: from workplace exposure assessment to inhalation toxicology

    OpenAIRE

    Erdely, Aaron; Dahm, Matthew; Chen, Bean T.; Zeidler-Erdely, Patti C.; Fernback, Joseph E.; Birch, M. Eileen; Evans, Douglas E.; Kashon, Michael L; Deddens, James A.; Hulderman, Tracy; Bilgesu, Suzan A; Battelli, Lori; Schwegler-Berry, Diane; Leonard, Howard D.; McKinney, Walter

    2013-01-01

    Background Dosimetry for toxicology studies involving carbon nanotubes (CNT) is challenging because of a lack of detailed occupational exposure assessments. Therefore, exposure assessment findings, measuring the mass concentration of elemental carbon from personal breathing zone (PBZ) samples, from 8 U.S.-based multi-walled CNT (MWCNT) manufacturers and users were extrapolated to results of an inhalation study in mice. Results Upon analysis, an inhalable elemental carbon mass concentration ar...

  5. Dosimetry of breast cancer

    International Nuclear Information System (INIS)

    The systemic therapy of breast cancer has also changed profoundly during the last 60 years, and in this time the integration of treatment modalities involve a major area of investigation. The dosimetry of breast cancer presents different complications which can range from the Physician's handling of the neoplasia up to the simple aspects of physical simulation, contour design, radiation fields, irregular surfaces and computer programs containing mathematical equations which differ little or largely with the reality of the radiation distribution into the volume to be irradiated. We have studied the problem using two types of measurements to determine how the radiation distribution is in irregular surfaces, and designing an easier skill to be used with each patient, in order to optimize the treatment with respect to the simulation and verification process. (author). 7 refs

  6. Dosimetry of iodoantipyrine

    International Nuclear Information System (INIS)

    Dosimetry of iodoantipyrine labeled with radioactive iodine was determined by measuring the biodistribution of 131I-iodoantipyrine in 41 female rabbits. Following administration of the radiopharmaceutical, subjects were killed at 0.5, 6, 12, 17, 24, 36, and 48 h. Organs and samples of tissues and body fluids were assayed. Results were corrected for physical decay. Exponential functions were employed to describe the time-concentration curves; representative value would be the biological half life of 9.96±0.55 h for blood. Cumulated activity estimates for 123I, 125I and 131I were then computed. Extrapolation to absorbed dose in humans followed the formulation of the Medical International Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine. The whole body absorbed doses are 0.7 μGray, 0.5 μGray and 2.9 μGray per MBq of 123I, 123I, and 131I administered respectively. (orig.)

  7. Strahlungsmessung und Dosimetrie

    CERN Document Server

    Krieger, Hanno

    2013-01-01

    „Strahlungsquellen und Dosimetrie“ ist Teil einer Lehrbuchreihe zur Strahlungsphysik und zum Strahlenschutz. Der erste Teil befasst sich mit den physikalischen Grundlagen der Strahlungsdetektoren und der Strahlungsmessung. Im zweiten Teil werden die Konzepte und Verfahren der klinischen Dosimetrie dargestellt. Der dritte Abschnitt erläutert ausführlich die Dosisverteilungen der klinisch angewendeten Strahlungsarten. Im vierten Teil werden weitere Messaufgaben der Strahlungsphysik einschließlich der Messsysteme für die Bildgebung mit Röntgenstrahlung dargestellt. Neben den grundlegenden Ausführungen enthält dieser Band im laufenden Text zahlreiche Tabellen und Grafiken zur technischen und medizinischen Radiologie, die bei der praktischen Arbeit sehr hilfreich sein können und 199 Übungsaufgaben mit Lösungen zur Vertiefung der Inhalte. Für die zweite Auflage wurden die Darstellungen der Elektronen- und der Protonendosimetrie sowie der bildgebenden Verfahren mit Computertomografen deutlich erweit...

  8. Radioiodotherapy: dosimetry planning

    International Nuclear Information System (INIS)

    The results of treatment of 142 case histories of 125 patients who had been treated with radioactive iodine at the Medical Radiological Research Center of Russian Academy of Medicine Sciences from 1983 to 1999 are given in the presentation. Among the patients, 35 cases of diffuse toxic goiter with signs of thyrotoxicosis of a mild degree, 25 cases of Diffuse toxic goiter with severe thyrotoxicosis, 6 cases of differentiated thyroid cancer with metastases to lymph-nodes of the neck, 30 cases of thyroid cancer with metastases to lymph-nodes of the neck and lung and 1 case of thyroid cancer with metastases to bones were diagnosed. This paper gives recommendations for individual dosimetry planning for radioiodine-therapy. (authors)

  9. A Test of Reliability of the Personnel Dosimetry Services Authorized by CSN using Photon Beams; Control de los servicios de dosimetria personal autorizados por el CSN, usando haces de fotones

    Energy Technology Data Exchange (ETDEWEB)

    Brosed, A.; Delgado, A.; Granados, C. E.; Lopez Ortiz, G.

    1987-07-01

    In 1987 the Consejo de Seguridad Nuclear (CSN) had eight Personnel Dosimetry Services (PDS) authorized to asses the equivalent doses to the spanish occupationally exposed workers, by means of the readings from the dosemeters wear by them. An audit was carried on the PDS on behalf of CSN under the control of CIEMAT. Batches of dosemeters from each one of the PDS were irradiated to dose equivalent values which were well established by CIEMAT but kept hidden from the PDS. By comparing the true values with those obtained by the PDS, it was possible to evaluate the Services according to the analysis of the quantity Q= I B I -I- S where B is the average of the individual deviations between the dosemeters belonging to the same group and the true value as established by CIEMAT, whereas S is the standard deviation of the values inside of this same group. The results of the evaluation, which was made using the new ICRU quantities for personnel monitoring, are presented. (Author) 8 refs.

  10. Dosimetry in radionuclide therapy

    International Nuclear Information System (INIS)

    While it is known that therapeutic effects of radionuclides are due to absorbed radiation dose and to radiosensitivity, individual dosimetry in 'Gy' is practiced rarely in clinical Nuclear Medicine but 'doses' are described in 'mCi' or 'MBq', which is only indirectly related to 'Gy' in the target. To estimate 'Gy', the volume of the target, maximum concentration of the radiopharmaceutical in it and residence time should be assessed individually. These parameters can be obtained usually only with difficulty, involving possibly also quantitative SPET or PET, modern imaging techniques (sonography, CT, MRT), substitution of y- or positron emitting radiotracers for β-emitting radiopharmaceuticals as well as whole-body distribution studies. Residence time can be estimated by obtaining data on biological half-life of a comparable tracer and transfer of these data in the physical characteristics of the therapeutic agent. With all these possibilities for gross dosimetry the establishment of a dose-response-relation should be possible. As distribution of the radiopharmaceutical in lesions is frequently inhomogenous and microdosimetric conditions are difficult to assess in vivo as yet, it could be observed since decades that empirically set, sometimes 'fixed' doses (mCi or MBq) can also be successful in many diseases. Detailed dosimetric studies, however, are work- and cost-intensive. Nevertheless, one should be aware at a time when more sophisticated therapeutic possibilities in Nuclear Medicine arise, that we should try to estimate radiation dose (Gy) in our new methods even as differences in individual radiosensitivity cannot be assessed yet and studies to define individual radiosensitivity in lesions should be encouraged. (author)

  11. Dosimetry in intravascular brachytherapy

    International Nuclear Information System (INIS)

    Among the cardiovascular diseases responsible for deaths in the adult population in almost all countries of the world, the most common is acute myocardial infarction, which generally occurs because of the occlusion of one or more coronary arteries. Several diagnostic techniques and therapies are being tested for the treatment of coronary artery disease. Balloon angioplasty has been a popular treatment which is less invasive than traditional surgeries involving revascularization of the myocardium, thus promising a better quality of life for patients. Unfortunately, the rate of restenosis (re-closing of the vessel) after balloon angioplasty is high (approximately 30-50% within the first year after treatment).Recently, the idea of delivering high radiation doses to coronary arteries to avoid or delay restenosis has been suggested. Known as intravascular brachytherapy, the technique has been used with several radiation sources, and researchers have obtained success in decreasing the rate of restenosis in some patient populations. In order to study the radiation dosimetry in the patient and radiological protection for the attending staff for this therapy, radiation dose distributions for monoenergetic electrons and photons (at nine discrete energies) were calculated for blood vessels of diameter 0.15, o,30 and 0.45 cm with balloon and wire sources using the radiation transport code MCNP4B. Specific calculations were carried out for several candidate radionuclides as well. Two s tent sources (metallic prosthesis that put inside of patient's artery through angioplasty) employing 32 P are also simulated. Advantages and disadvantages of the various radionuclides and source geometries are discussed. The dosimetry developed here will aid in the realization of the benefits obtained in patients for this promising new technology. (author)

  12. Hanford internal dosimetry program manual

    Energy Technology Data Exchange (ETDEWEB)

    Carbaugh, E.H.; Sula, M.J.; Bihl, D.E.; Aldridge, T.L.

    1989-10-01

    This document describes the Hanford Internal Dosimetry program. Program Services include administrating the bioassay monitoring program, evaluating and documenting assessments of internal exposure and dose, ensuring that analytical laboratories conform to requirements, selecting and applying appropriate models and procedures for evaluating internal radionuclide deposition and the resulting dose, and technically guiding and supporting Hanford contractors in matters regarding internal dosimetry. 13 refs., 16 figs., 42 tabs.

  13. Hanford internal dosimetry program manual

    International Nuclear Information System (INIS)

    This document describes the Hanford Internal Dosimetry program. Program Services include administrating the bioassay monitoring program, evaluating and documenting assessments of internal exposure and dose, ensuring that analytical laboratories conform to requirements, selecting and applying appropriate models and procedures for evaluating internal radionuclide deposition and the resulting dose, and technically guiding and supporting Hanford contractors in matters regarding internal dosimetry. 13 refs., 16 figs., 42 tabs

  14. Fifth international radiopharmaceutical dosimetry symposium

    International Nuclear Information System (INIS)

    This meeting was held to exchange information on how to get better estimates of the radiation absorbed dose. There seems to be a high interest of late in patient dosimetry; discussions were held in the light of revised risk estimates for radiation. Topics included: Strategies of Dose Assessment; Dose Estimation for Radioimmunotherapy; Dose Calculation Techniques and Models; Dose Estimation for Positron Emission Tomography (PET); Kinetics for Dose Estimation; and Small Scale Dosimetry and Microdosimetry. (VC)

  15. Dosimetry, instrumentation and exposure chambers for dc magnetic field studies

    Energy Technology Data Exchange (ETDEWEB)

    Tenforde, T.S.

    1979-03-01

    The principal objective of this report is to describe in detail an exposure chamber that was developed at the Lawrence Berkeley Laboratory for automated, noninvasive studies of rodent physiology during exposure to high DC magnetic fields. A second objective is to discuss some of the unique instrumentation problems that must be overcome in order to record bioelectric signals from laboratory animals in the presence of a magnetic field. Finally, a description will be given of the various dosimetry techniques that can be employed for quantitation of magnetic field strength.

  16. Dosimetry, instrumentation and exposure chambers for dc magnetic field studies

    International Nuclear Information System (INIS)

    The principal objective of this report is to describe in detail an exposure chamber that was developed at the Lawrence Berkeley Laboratory for automated, noninvasive studies of rodent physiology during exposure to high DC magnetic fields. A second objective is to discuss some of the unique instrumentation problems that must be overcome in order to record bioelectric signals from laboratory animals in the presence of a magnetic field. Finally, a description will be given of the various dosimetry techniques that can be employed for quantitation of magnetic field strength

  17. Internal dosimetry, past and future

    International Nuclear Information System (INIS)

    This paper is a review of the progress in the dosimetry of internally deposited radionuclides (internal dosimetry) since World War II. Previous to that, only naturally occurring radionuclides were available and only a limited number of studies of biokinetics and dosimetry were done. The main radionuclides studied were 226Ra, 228Ra, and 224Ra but natural uranium was also studied mainly because of its toxic effect as a heavy metal, and not because it was radioactive. The effects of 226Ra in bone, mainly from the radium dial painters, also formed the only bases for the radiotoxicity of radionuclides in bone for many years, and it is still, along with 224Ra, the main source of information on the effects of alpha emitters in bone. The publications of the International Commission on Radiological Protection that have an impact on internal dosimetry are used as mileposts for this review. These series of publications, more than any other, represent a broad consensus of opinion within the radiation protection community at the time of their publication, and have formed the bases for radiation protection practice throughout the world. This review is not meant to be exhaustive; it is meant to be a personnel view of the evolution of internal dosimetry, and to present the author's opinion of what the future directions in internal dosimetry will be. 39 refs., 2 tabs

  18. DRDC Ottawa working standard for biological dosimetry

    International Nuclear Information System (INIS)

    This Standard provides quality assurance, quality control, and evaluation of the performance criteria for the purpose of accreditation of the Radiation Biology laboratory at Defence Research and Development Canada - Ottawa (DRDC Ottawa) using biological dosimetry to predict radiation exposure doses. The International Standard (ISO 19238) and the International Atomic Energy Association (IAEA) Technical Report Series No. 405 are used as guiding documents in preparation of this working document specific to the DRDC Ottawa Radiation Biology Laboratory. This Standard addresses: 1. The confidentiality of personal information, for the customer and the service laboratory; 2. The laboratory safety requirements; 3. The calibration sources and calibration dose ranges useful for establishing the reference dose-effect curves allowing the dose estimation from chromosome aberration frequency, and the minimum detection levels; 4. Transportation criteria for shipping of test samples to the laboratory; 5. Preparation of samples for analysis; 6. The scoring procedure for unstable chromosome aberrations used for biological dosimetry; 7. The criteria for converting a measured aberration frequency into an estimate of absorbed dose; 8. The reporting of results; 9. The quality assurance and quality control plan for the laboratory; and 10. Informative annexes containing examples of a questionnaire, instructions for customers, a data sheet for recording aberrations, a sample report and other supportive documents. (author)

  19. DRDC Ottawa working standard for biological dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Segura, T.M.; Prud' homme-Lalonde, L. [Defence Research and Development Canada, Ottawa, Ontario (Canada); Thorleifson, E. [Health Canada, Gatineau, Quebec (Canada); Lachapelle, S.; Mullins, D. [JERA Consulting (Canada); Qutob, S. [Health Canada, Gatineau, Quebec (Canada); Wilkinson, D.

    2005-07-15

    This Standard provides quality assurance, quality control, and evaluation of the performance criteria for the purpose of accreditation of the Radiation Biology laboratory at Defence Research and Development Canada - Ottawa (DRDC Ottawa) using biological dosimetry to predict radiation exposure doses. The International Standard (ISO 19238) and the International Atomic Energy Association (IAEA) Technical Report Series No. 405 are used as guiding documents in preparation of this working document specific to the DRDC Ottawa Radiation Biology Laboratory. This Standard addresses: 1. The confidentiality of personal information, for the customer and the service laboratory; 2. The laboratory safety requirements; 3. The calibration sources and calibration dose ranges useful for establishing the reference dose-effect curves allowing the dose estimation from chromosome aberration frequency, and the minimum detection levels; 4. Transportation criteria for shipping of test samples to the laboratory; 5. Preparation of samples for analysis; 6. The scoring procedure for unstable chromosome aberrations used for biological dosimetry; 7. The criteria for converting a measured aberration frequency into an estimate of absorbed dose; 8. The reporting of results; 9. The quality assurance and quality control plan for the laboratory; and 10. Informative annexes containing examples of a questionnaire, instructions for customers, a data sheet for recording aberrations, a sample report and other supportive documents. (author)

  20. Radiation protection dosimetry in medicine - Report of the working group n.9 of the European radiation dosimetry group (EURADOS) - coordinated network for radiation dosimetry (CONRAD - contract EC N) fp6-12684

    International Nuclear Information System (INIS)

    This report present the results achieved within the frame of the work the WP 7 (Radiation Protection Dosimetry of Medical Staff) of the coordination action CONRAD (Coordinated Network for Radiation Dosimetry) funded through the 6. EU Framework Program. This action was coordinated by EURADOS (European Radiation Dosimetry Group). EURADOS is an organization founded in 1981 to advance the scientific understanding and the technical development of the dosimetry of ionising radiation in the fields of radiation protection, radiobiology, radiation therapy and medical diagnosis by promoting collaboration between European laboratories. WP7 coordinates and promotes European research for the assessment of occupational exposures to staff in therapeutic and diagnostic radiology workplaces. Research is coordinated through sub-groups covering three specific areas: 1. Extremity dosimetry in nuclear medicine and interventional radiology: this sub-group coordinates investigations in the specific fields of the hospitals and studies of doses to different parts of the hands, arms, legs and feet; 2. Practice of double dosimetry: this sub-group reviews and evaluates the different methods and algorithms for the use of dosemeters placed above and below lead aprons in large exposure during interventional radiology procedures, especially to determine effective doses to cardiologists during cardiac catheterization; and 3. Use of electronic personal dosemeters in interventional radiology: this sub-group coordinates investigations in laboratories and hospitals, and intercomparisons with passive dosemeters with the aim to enable the formulation of standards. (authors)

  1. Conversion coefficients from air kerma to personal dose equivalent H{sub p}(3) fir eye-lens dosimetry; Coeficients de conversion du kerma dans l'air a l'equivalent de dose individuel H{sub p}(3) pour la dosimetrie du cristalin

    Energy Technology Data Exchange (ETDEWEB)

    Daures, J.; Gouriou, J.; Bordy, J.M

    2009-07-01

    This work has been performed within the frame of the European Union ORAMED project (Optimization of Radiation protection for Medical staff). The main goal of the project is to improve standards of protection for medical staff for procedure resulting in potentially high exposures and to develop methodologies for better assessing and for reducing exposures to medical staff. The Work Package WP2 is involved in the development of practical eye lens dosimetry in interventional radiology. This study is complementary of the part of the ENEA report concerning the calculations with the MCNP code of the conversion factors related to the operational quantity H{sub p}(3). A set of energy and angular dependent conversion coefficients H{sub p}(3)/K{sub air} in the new proposed square cylindrical phantom of ICRU tissue, have been calculated with the Monte-Carlo code PENELOPE. The H{sub p}(3) values have been determined in terms of absorbed dose, according to the definition of this quantity, and also with the kerma approximation as formerly reported in ICRU reports. At low photon energy, up to 1 MeV, the two sets of conversion coefficients are consistent. Nevertheless, the differences increase at higher energy. This is mainly due to the lack of electronic equilibrium, especially for small angle incidences. The values of the conversion coefficients obtained with the code MCNP published by ENEA, agree with the kerma approximation calculations with PENELOPE. They are coherent with previous calculations in phantoms different in shape. But above 1 MeV, differences between conversion coefficient values calculated with the absorbed dose and with kerma approximation are significantly increasing, especially at low incidence angles. At those energies the electron transport has to be simulated. (author)

  2. Automation of the method gamma of comparison dosimetry images

    International Nuclear Information System (INIS)

    The objective of this work was the development of JJGAMMA application analysis software, which enables this task systematically, minimizing intervention specialist and therefore the variability due to the observer. Both benefits, allow comparison of images is done in practice with the required frequency and objectivity. (Author)

  3. Automating dicentric chromosome detection from cytogenetic bio-dosimetry data

    International Nuclear Information System (INIS)

    We present a prototype software system with sufficient capacity and speed to estimate radiation exposures in a mass casualty event by counting dicentric chromosomes (DCs) in metaphase cells from many individuals. Top-ranked metaphase cell images are segmented by classifying and defining chromosomes with an active contour gradient vector field (GVF) and by determining centromere locations along the centreline. The centreline is extracted by discrete curve evolution (DCE) skeleton branch pruning and curve interpolation. Centromere detection minimises the global width and DAPI-staining intensity profiles along the centreline. A second centromere is identified by reapplying this procedure after masking the first. Dicentrics can be identified from features that capture width and intensity profile characteristics as well as local shape features of the object contour at candidate pixel locations. The correct location of the centromere is also refined in chromosomes with sister chromatid separation. The overall algorithm has both high sensitivity (85 %) and specificity (94 %). Results are independent of the shape and structure of chromosomes in different cells, or the laboratory preparation protocol followed. The prototype software was re-coded in C++/OpenCV; image processing was accelerated by data and task parallelization with Message Passaging Interface and Intel Threading Building Blocks and an asynchronous non-blocking I/O strategy. Relative to a serial process, metaphase ranking, GVF and DCE are, respectively, 100 and 300-fold faster on an 8-core desktop and 64-core cluster computers. The software was then ported to a 1024-core supercomputer, which processed 200 metaphase images each from 1025 specimens in 1.4 h. (authors)

  4. Integration of external and internal dosimetry in Switzerland

    International Nuclear Information System (INIS)

    Individual monitoring regulations in Switzerland are based on the ICRP60 recommendations. The annual limit of 20 mSv for the effective dose applies to the sum of external and internal radiation. External radiation is monitored monthly or quarterly with TLD, DIS or CR-39 dosemeters by 10 approved external dosimetry services and reported as Hp(10) and Hp(0.07). Internal monitoring is done in two steps. At the workplace, simple screening measurements are done frequently in order to recognise a possible incorporation. If a nuclide dependent activity threshold is exceeded then one of the seven approved dosimetry services for internal radiation does an incorporation measurement to assess the committed effective dose E50. The dosimetry services report all the measured or assessed dose values to the employer and to the National Dose Registry. The employer records the annually accumulated dose values into the individual dose certificate of the occupationally exposed person, both the external dose Hp(10) and the internal dose E50 as well as the total effective dose E = Hp(10) + E50. Based on the national dose registry an annual report on the dosimetry in Switzerland is published which contains the statistics for the total effective dose, as well as separate statistics for external and internal exposure. (authors)

  5. State of the art of solid state dosimetry

    International Nuclear Information System (INIS)

    Passive solid-state detectors still dominate the personal dosimetry field. This article provides state of the art in this field and summarizes the most recent works presented on TL, OSL and RPL during the 17th International Conference on Solid State Dosimetry held in Recife in September 2013. The Article contains in particular the techniques Thermoluminescence (TL), Optically Stimulated Luminescence (OSL), radio photoluminescence (RPL). Thermoluminescence has the biggest advantage of the wide availability of commercial materials for dosimetry, and the nature tissue-equivalent of several of these materials. The limitation of the TL dosimetry presents fading luminance signal and the need for high temperatures to obtain the signal. The Optically Stimulated Luminescence has the advantages of high sensitivity, the possibility of multiple reading, while its limit is the need to use response compensating filters in addition to the high cost of equipment and dosimeters still restricted very few options trading . The radio photoluminescence has a reading that is completely non-destructive, but their dosimeters present lack of tissue-equivalent and a high cost. Presents the details of the techniques and the advantages and limitations of each of these will be discussed

  6. Radiotherapy gel dosimetry

    International Nuclear Information System (INIS)

    shapes and sizes while sparing normal tissue. The situation is further complicated if the normal tissues are critical organs or are particularly sensitive to radiation. Radiotherapy techniques employed to obtain a closer conformation of the dose distribution to the tumour volume are referred to as conformal radiotherapy techniques. The clinical implementation of conformal therapy has been delayed by limitations in the verification of conformal dose distributions calculated by treatment planning systems prior to the irradiation of the patient and the verification of complex treatments during its delivery to the patient. There are several aspects of conformal therapy that complicate dose verification. To achieve the dose distributions conforming to complex 3D volumes, high dose gradients arise in the treatment volume. Further, overdose or underdose regions can exist when separate radiation fields are used to deliver additional radiation. These aspects require that practical dose measurement (dosimetry) techniques be able to integrate dose over time and easily measure dose distributions in 3D with high spatial resolution. Traditional dosimeters, such as ion chambers, thermoluminescent dosimeters and radiographic film do not fulfil these requirements. Novel gel dosimetry techniques are being developed in which dose distributions can potentially be determined in vitro in 3D using anthropomorphic phantoms to simulate a clinically irradiated situation. As long ago as the 1950's, radiation-induced colour change in dyes was used to investigate radiation doses in gels. It was subsequently shown that radiation induced changes in nuclear magnetic resonance (NMR) relaxation properties of gels infused with conventional Fricke dosimetry solutions could be measured using magnetic resonance imaging (MRI). In Fricke gels, Fe2+ ions in ferrous sulphate solutions are usually dispersed throughout a gelatin, agarose or PVA matrix. Radiation-induced changes in the dosimeters are considered to

  7. Applied internal dosimetry staff exposed to Uranium

    International Nuclear Information System (INIS)

    Dosimetric calculations are performed in order to estimate the quantity of a radionuclide that is incorporated by a worker. Urine determinations of activity and mass of uranium are made in the laboratory of Personal and Area Dosimetry. The paper presents reference values concerning the activity excreted in urine due to the incorporation of uranium compounds. The compounds analyzed are natural uranium and uranium enriched to 20 %, both soluble and insoluble. According to the limits allowed for the incorporation of uranium compounds of Type F and M, we verify that the times of monitoring and the detection limits of the equipment used to determine the activity are appropriate. On the other hand, the S-type compounds determination in urine is useful in cases of accidental incorporations (above the ALI) as a first and quick estimate; MDA (0.017 Bq / L) does not allow detection in routine monitoring; measurement in lungs, and faeces should be included. (author)

  8. Internal Dosimetry for Nuclear Power Program

    International Nuclear Information System (INIS)

    Internal dosimetry which refers to dosage estimation from internal part of an individual body is an important and compulsory component in order to ensure the safety of the personnel involved in operational of a Nuclear Power Program. Radionuclides particle may deposit in the human being through several pathways and release wave and/or particle radiation to irradiate that person and give dose to body until it been excreted or completely decayed from the body. Type of radionuclides of concerning, monitoring program, equipment's and technique used to measure the concentration level of such radionuclides and dose calculation will be discussed in this article along with the role and capability of Malaysian Nuclear Agency. (author)

  9. Skin dosimetry with new MOSFET detectors

    Energy Technology Data Exchange (ETDEWEB)

    Kwan, I.S.; Rosenfeld, A.B. [Centre for Medical Radiation Physics, University of Wollongong, Northfields Ave., Wollongong (Australia); Qi, Z.Y. [Centre for Medical Radiation Physics, University of Wollongong, Northfields Ave., Wollongong (Australia); Radiation Oncology Department, Cancer Center, Sun Yat-Sen University, Guangzhou (China); Wilkinson, D.; Lerch, M.L.F. [Centre for Medical Radiation Physics, University of Wollongong, Northfields Ave., Wollongong (Australia); Cutajar, D.L. [Centre for Medical Radiation Physics, University of Wollongong, Northfields Ave., Wollongong (Australia)], E-mail: deanc@uow.edu.au; Safavi-Naeni, M. [Centre for Medical Radiation Physics, University of Wollongong, Northfields Ave., Wollongong (Australia); Butson, M. [Illawarra Cancer Care Centre, Wollongong Hospital, Crown Street, Wollongong (Australia); Bucci, J.A.; Chin, Y. [St. George Cancer Care Centre, St. George Hospital, Kogarah (Australia); Perevertaylo, V.L. [SPA BIT (Ukraine)

    2008-02-15

    The MOSkin, a new MOSFET-based detector designed by the Centre for Radiation Physics, was engineered to provide accurate measurements of skin doses in radiotherapy and personal monitoring. The International Commission on Radiological Protection (ICRP) estimates the radiosensitive basal layer to be at an average depth of 0.070 mm. Current commercially available MOSFETs utilize an epoxy bubble encapsulation, making measurements at equivalent depths of 0.070 mm difficult. The MOSkin utilizes a novel packaging design that allows the measurement of doses at this equivalent depth. The MOSkin has shown excellent agreement with the Attix chamber for surface measurements in a 6 MV photon beam of various field sizes and has minimal angular dependence due to the encapsulation. The new design will diversify the use of MOSFETs for dosimetry in radiotherapy and radiation protection.

  10. Management system of personnel dosimetry based on ISO 9001:2008 for medical diagnostic

    International Nuclear Information System (INIS)

    MDose is a computer management system of personal dosimetry in diagnostic radiology services physician based on ISO 9001:9008 management system. According to Brazilian law all service radiology should implement a control of personal dosimetry in addition to radiation doses greater than 1.5 mSv/year service should do research of high dose, which is to identify the causes the resulting dose increase professional. This work is based on the use of the PDCA cycle in a JAVA software developed as a management method in the analysis of high doses in order to promote systematic and continuous improvement within the organization of radiological protection of workers

  11. Thermoluminescence Dosimetry Applied to Radiation Protection

    DEFF Research Database (Denmark)

    Christensen, Poul; Bøtter-Jensen, Lars; Majborn, Benny

    1982-01-01

    This is a general review of the present state of the development and application of thermoluminescence dosimetry (TLD) for radiation protection purposes. A description is given of commonly used thermoluminescent dosimeters and their main dosimetric properties, e.g. energy response, dose range......, fading, and LET dependence. The applications of thermoluminescence dosimetry in routine personnel monitoring, accident dosimetry, u.v. radiation dosimetry, and environmental monitoring are discussed with particular emphasis on current problems in routine personnel monitoring. Finally, the present state...

  12. Upgrading the dosimetry at Ontario Hydro

    International Nuclear Information System (INIS)

    Ontario Hydro has embarked upon a major programme to replace and upgrade its external dosimetry systems. In two year's time, the utility expects to have two state-of-the-art dosimetry systems in place: a new TLD dosimetry of legal record that was designed nearly 30 years ago; and an electronic dosimetry system which could eventually replace the TLD as the primary system. (Author)

  13. Biological dosimetry; Dosimetria biologica

    Energy Technology Data Exchange (ETDEWEB)

    Guerrero C, C.; Arceo M, C., E-mail: citlali.guerrero@inin.gob.m [ININ, Departamento de Biologia, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-07-01

    In the Instituto Nacional de Investigaciones Nucleares (ININ) the works to establish a laboratory of biological dosimetry were initiated in 1998, with the purpose that could assist any situation with respect to the exposition to radiation, so much of the occupational exposed personnel as of individuals not related with the handling of radio-active material. The first activity that was realized was to develop the corresponding curves in vitro of dose response for different qualities and radiation types. In the year 2000 the curve corresponding to the gamma radiation of {sup 60}Co was published and up to 2002 the curve corresponding to the X rays of 58 KeV, 120 and 250 kVp. In all the cases, the curves contain the requirements to be used in the determination of the exposition dose. At the present time the curves dose-response are developing for neutrons take place in the reactor Triga Mark III of ININ. Additionally to these activities, cases of suspicion of accidental exposition to radiation have been assisted, using in a beginning the curves published by the IAEA and, from the year 2000, the curves developed in the ININ. (Author)

  14. Fast neutron dosimetry

    International Nuclear Information System (INIS)

    During 1988--1990 the magnetic resonance dosimetry project was completed, as were the 250 MeV proton shielding measurements. The first cellular experiment using human cells in vitro at the 1 GeV electron storage ring was also accomplished. More detail may be found in DOE Report number-sign DOE/EV/60417-002 and the open literature cited in the individual progress subsections. We report Kinetic Energy Released in Matter (KERMA), factor measurements in several elements of critical importance to neutron radiation therapy and radiation protection for space habitation and exploration for neutron energies below 30 MeV. The results of this effort provide the only direct measurements of the oxygen and magnesium kerma factors above 20 MeV neutron energy, and the only measurements of the iron kerma factor above 15 MeV. They provide data of immediate relevance to neutron radiotherapy and impose strict criteria for normalizing and testing nuclear models used to calculate kerma factors at higher neutron energies

  15. Dosimetry of iodoantipyrine

    Energy Technology Data Exchange (ETDEWEB)

    Chu, R.Y.L.; Ekeh, S. (Oklahoma Univ., Oklahoma City, OK (USA). Dept. of Radiological Sciences; Veterans Administration Medical Center, Oklahoma City, OK (USA)); Basmadjian, G. (Oklahoma Univ., Oklahoma City, OK (USA). Dept. of Pharmaceutical Sciences)

    1989-12-01

    Dosimetry of iodoantipyrine labeled with radioactive iodine was determined by measuring the biodistribution of {sup 131}I-iodoantipyrine in 41 female rabbits. Following administration of the radiopharmaceutical, subjects were killed at 0.5, 6, 12, 17, 24, 36, and 48 h. Organs and samples of tissues and body fluids were assayed. Results were corrected for physical decay. Exponential functions were employed to describe the time-concentration curves; representative value would be the biological half life of 9.96+-0.55 h for blood. Cumulated activity estimates for {sup 123}I, {sup 125}I and {sup 131}I were then computed. Extrapolation to absorbed dose in humans followed the formulation of the Medical International Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine. The whole body absorbed doses are 0.7 {mu}Gray, 0.5 {mu}Gray and 2.9 {mu}Gray per MBq of {sup 123}I, {sup 123}I, and {sup 131}I administered respectively. (orig.).

  16. Dosimetry of ionizing radiation

    International Nuclear Information System (INIS)

    The book informs of the whole range of the physical foundations of dosimetry. In the chapter dealing with the interaction of ionizing radiation with matter the processes are described of the interaction between the individual types of ionizing radiation and matter and the effects of ionizing radiation on matter. The chapter dealing with dosimetric quantities and units gives a survey and definitions of quantities and their inter-relations. The chapters relating to the determination of basic dosimetric quantities and to integral dosimetric methods give a detailed description of the individual methods. The chapter relating to radionuclides in the environment concerns the occurrence of natural radionuclides in the environment and in the human organism, cosmic radiation and artificial sources of radioactivity connected with the development of civilisation and technology. The chapter related to radiation protection gives guidelines for the calculation of shielding for individual types of radiation. The supplement contains a list of the properties of certain radionuclides widespread in the environment, their basic physico-chemical and biological characteristics, parameters of metabolism and values of maximum permissible concentrations. (M.D.)

  17. Nuclear accident dosimetry intercomparison studies.

    Science.gov (United States)

    Sims, C S

    1989-09-01

    Twenty-two nuclear accident dosimetry intercomparison studies utilizing the fast-pulse Health Physics Research Reactor at the Oak Ridge National Laboratory have been conducted since 1965. These studies have provided a total of 62 different organizations a forum for discussion of criticality accident dosimetry, an opportunity to test their neutron and gamma-ray dosimetry systems under a variety of simulated criticality accident conditions, and the experience of comparing results with reference dose values as well as with the measured results obtained by others making measurements under identical conditions. Sixty-nine nuclear accidents (27 with unmoderated neutron energy spectra and 42 with eight different shielded spectra) have been simulated in the studies. Neutron doses were in the 0.2-8.5 Gy range and gamma doses in the 0.1-2.0 Gy range. A total of 2,289 dose measurements (1,311 neutron, 978 gamma) were made during the intercomparisons. The primary methods of neutron dosimetry were activation foils, thermoluminescent dosimeters, and blood sodium activation. The main methods of gamma dose measurement were thermoluminescent dosimeters, radiophotoluminescent glass, and film. About 68% of the neutron measurements met the accuracy guidelines (+/- 25%) and about 52% of the gamma measurements met the accuracy criterion (+/- 20%) for accident dosimetry. PMID:2777549

  18. Standardization of dosimetry in diagnostic radiology

    International Nuclear Information System (INIS)

    Three objectives of dosimetry in diagnostic radiology can be identified: (1) Measurement of patient doses for comparison with diagnostic reference levels; (2) Assessment of equipment performance; (3) Patient dose measurements for risk assessment. In this paper author deals with problems of standardization of dosimetry in diagnostic radiology. Recommended application specific quantities for dosimetry in diagnostic radiology are presented

  19. 4.2 Methods for Internal Dosimetry

    Science.gov (United States)

    Noßke, D.; Mattsson, S.; Johansson, L.

    This document is part of Subvolume A 'Fundamentals and Data in Radiobiology, Radiation Biophysics, Dosimetry and Medical Radiological Protection' of Volume 7 'Medical Radiological Physics' of Landolt-Börnstein - Group VIII 'Advanced Materials and Technologies'. It contains the Section '4.2 Methods for Internal Dosimetry' of the Chapter '4 Dosimetry in Nuclear Medicine Diagnosis and Therapy' with the contents:

  20. Initial radiation dosimetry at Hiroshima and Nagasaki

    International Nuclear Information System (INIS)

    The dosimetry of A-bomb survivors at Hiroshima and Nagasaki is discussed in light of the new dosimetry developed in 1980 by the author. The important changes resulting from the new dosimetry are the ratios of neutron to gamma doses, particularly at Hiroshima. The implications of these changes in terms of epidemiology and radiation protection standards are discussed

  1. Dosimetry through the Secondary Laboratory of Dosimetric Calibration of Mexico

    International Nuclear Information System (INIS)

    In the beginnings of the sixty years an urgent necessity is presented mainly in the developing countries, of improving in important form the accuracy in the dosimetry of external faces in therapy of radiations (radiotherapy centers), mainly in the calibration of clinical dosemeters. In 1976 the International Atomic Energy Agency, (IAEA), and the World Health Organization, (WHO), they carried out a mutual agreement with regard to the establishment and operation of a net of Secondary Patron Laboratories of Dosimetry, (LSCD). The necessity to establish measure patterns in the field of the dosimetry of the ionizing radiations, is necessary, to have an accuracy but high in the dosimetry of the radiation beams in therapy which is highly dependent of the dose given to the tumor of those patient with cancer. Similar levels of accuracy are required in protection measures to the radiation with an acceptable smaller accuracy, however, when the personal dosemeters are used to determine the doses received by the individuals under work conditions, such mensurations in therapy of radiations and radiological protection will have traceability through a chain of comparisons to primary or national patterns. The traceability is necessary to assure the accuracy and acceptability of the dosimetric measures, as well as, the legal and economic implications. The traceability is also necessary in the dosimetry of high dose like in the sterilization of different products. The main function of the LSCD is to provide a service in metrology of ionizing radiations, maintaining the secondary or national patterns, which have a traceability to the International System of measures, which is based for if same in the comparison of patterns in the Primary Laboratories of Dosimetry (LPD) under the auspice of the International Office of Weights and Measure (BIPM). The secondary and national patterns in the LSCD constitute in Mexico, the national patterns of the magnitudes in the dosimetry of the ionizing

  2. Integration of external and internal dosimetry in Switzerland

    International Nuclear Information System (INIS)

    Full text: Individual monitoring regulations in Switzerland are based on the ICRP60 recommendations from 1990. The annual limit of 20 mSv for the effective dose applies to the sum of external and internal radiation. External radiation is monitored monthly or quarterly with TLD, DIS or CR-39 dosemeters by 10 approved dosimetry services and reported as Hp(10) and Hp(0.07). Internal monitoring is done in two steps. At the workplace simple screening measurements are done frequently in order to recognize a possible incorporation. If a nuclide dependent activity threshold is exceeded one of the 5 approved dosimetry services for internal radiation performs an incorporation measurement to assess the committed effective dose E50. In practice, the screening measurements are sometimes not done separately but combined with regular incorporation measurements, e.g. LSC measurements of urine. The dosimetry services report all the measured dose values to the employer and to the national dose registry. The employer records the annually accumulated dose values into the individual dose certificate of the occupationally exposed person, both the external dose Hp(10) and the internal dose E50 as well as the total effective dose E = Hp(10) + E50. The Swiss National Dose Registry contains all the dose records from external radiation exposure in Switzerland since 1989. Since the internal dosimetry services have been approved in 2001 the registry includes also the results from incorporation measurements. Based on the national dose registry an annual report on dosimetry in Switzerland is published which contains the statistics for the total effective dose as well as separate statistics for external and internal exposure. (author)

  3. Information from the Dosimetry Service

    CERN Multimedia

    2006-01-01

    Please note the following opening hours of the Service: In June: Every morning from 8:30 to 12:00 In July: Mondays, Wednesdays and Fridays from 8:30 to 11:30 Closed all day on Tuesdays and Thursdays From 31st July onwards: Every morning from 8:30 to 12:00 The Service is closed in the afternoons. We should like to remind you that dosimeters cannot be sent to customers by internal mail. Short-term dosimeters (VCTs) must always be returned to the Service after use and must not be left on the racks in the experimental areas or in the secretariats. Dosimetry Service Tel 72155 Bldg. 24 E 011 Dosimetry.service@cern.ch http://cern.ch/rp-dosimetry

  4. External audit in radiotherapy dosimetry

    International Nuclear Information System (INIS)

    Quality audit forms an essential part of any comprehensive quality assurance programme. This is true in radiotherapy generally and in specific areas such as radiotherapy dosimetry. Quality audit can independently test the effectiveness of the quality system and in so doing can identify problem areas and minimize their possible consequences. Some general points concerning quality audit applied to radiotherapy are followed by specific discussion of its practical role in radiotherapy dosimetry, following its evolution from dosimetric intercomparison exercises to routine measurement-based on-going audit in the various developing audit networks both in the UK and internationally. Specific examples of methods and results are given from some of these, including the Scottish+ audit group. Quality audit in radiotherapy dosimetry is now well proven and participation by individual centres is strongly recommended. Similar audit approaches are to be encouraged in other areas of the radiotherapy process. (author)

  5. Dosimetry standards for radiation processing

    International Nuclear Information System (INIS)

    For irradiation treatments to be reproducible in the laboratory and then in the commercial environment, and for products to have certified absorbed doses, standardized dosimetry techniques are needed. This need is being satisfied by standards being developed by experts from around the world under the auspices of Subcommittee E10.01 of the American Society for Testing and Materials (ASTM). In the time period since it was formed in 1984, the subcommittee has grown to 150 members from 43 countries, representing a broad cross-section of industry, government and university interests. With cooperation from other international organizations, it has taken the combined part-time effort of all these people more than 13 years to complete 24 dosimetry standards. Four are specifically for food irradiation or agricultural applications, but the majority apply to all forms of gamma, x-ray, Bremsstrahlung and electron beam radiation processing, including dosimetry for sterilization of health care products and the radiation processing of fruits, vegetables, meats, spices, processed foods, plastics, inks, medical wastes and paper. An additional 6 standards are under development. Most of the standards provide exact procedures for using individual dosimetry systems or for characterizing various types of irradiation facilities, but one covers the selection and calibration of dosimetry systems, and another covers the treatment of uncertainties. Together, this set of standards covers essentially all aspects of dosimetry for radiation processing. The first 20 of these standards have been adopted in their present form by the International Organization of Standardization (ISO), and will be published by ISO in 1999. (author)

  6. Automation Security

    OpenAIRE

    Mirzoev, Dr. Timur

    2014-01-01

    Web-based Automated Process Control systems are a new type of applications that use the Internet to control industrial processes with the access to the real-time data. Supervisory control and data acquisition (SCADA) networks contain computers and applications that perform key functions in providing essential services and commodities (e.g., electricity, natural gas, gasoline, water, waste treatment, transportation) to all Americans. As such, they are part of the nation s critical infrastructu...

  7. Calorimetric dosimetry of reactor radiation

    International Nuclear Information System (INIS)

    Calorimetric dosimetry of reactor radiation is relatively new reactor dosimetry method and the number of relevant papers is rather small. Some difficulties in applying standard methods (chemical dosemeters, ionization chambers) exist because of the complexity of radiation. In general application of calorimetric dosemeters for measuring absorbed doses is most precise. In addition to adequate choice of calorimetric bodies there is a possibility of determining the yields of each component of the radiation mixture in the total absorbed dose. This paper contains a short review of the basic calorimetry methods and some results of measurements at the RA reactor in Vinca performed by isothermal calorimeter

  8. Radiation dosimetry and radiation biophysics

    International Nuclear Information System (INIS)

    Radiation dosimetry and radiation biophysics are two closely integrated programs whose joint purpose is to explore the connections between the primary physical events produced by radiation and their biological consequences in cellular systems. The radiation dosimetry program includes the theoretical description of primary events and their connection with the observable biological effects. This program also is concerned with the design and measurement of physical parameters used in theory or to support biological experiments. The radiation biophysics program tests and uses the theoretical developments for experimental design, and provides information for further theoretical development through experiments on cellular systems

  9. Radiation dosimetry and radiation biophysics

    International Nuclear Information System (INIS)

    Radiation dosimetry and radiation biophysics are two closely integrated programs whose joint purpose is to explore the connections between the primary physical events produced by radiation and their biological consequences in cellular systems. The radiation dosimetry program includes the theoretical description of primary events and their connection with the observable biological effects. This program also is concerned with design and measurement of those physical parameters used in the theory or to support biological experiments. The radiation biophysics program tests and makes use of the theoretical developments for experimental design. Also, this program provides information for further theoretical development through experiments on cellular systems

  10. Information from the Dosimetry Service

    CERN Multimedia

    2006-01-01

    CERN Staff and Users can now consult their dose records for an individual or an organizational unit with HRT. Please see more information on our web page: http://cern.ch/rp-dosimetry. The Dosimetry Service is open every morning from 8.30 to 12.00 and is closed in the afternoons. We would like to remind you that dosimeters cannot be sent to customers by internal mail. Short-term dosimeters (VCT's) must always be returned to the Service after use and must not be left on the racks in the experimental areas or in the secretariats.

  11. Information from the Dosimetry Service

    CERN Multimedia

    2006-01-01

    CERN Staff and Users can now consult their dose records for an individual or an organizational unit with HRT. Please see more information on our web page http://cern.ch/rp-dosimetry. The Dosimetry Service is open every morning from 8.30 - 12.00, and closed in the afternoons. We would like to remind you that dosimeters cannot be sent to customers by internal mail. Short-term dosimeters (VCT's) must always be returned to the Service after use and must not be left on the racks in the experimental areas or in the secretariats.

  12. Ideal dosimetry system: dosimetry systems in current use

    International Nuclear Information System (INIS)

    In radiation processing - validation and process control (sterilization, food irradiation, etc.) depend on the measurement of absorbed dose. Measurements of absorbed dose shall be performed using a dosimetric system or systems having a known level of accuracy and precision (European standard EN552:1994). Lecture describes application of different dosimetry systems in the radiation processing of different materials

  13. An upgraded personnel dosimetry system for TMI-2 [Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Following the Three Mile Island Unit 2 (TMI-2) accident, it was identified that due to the unusual radiological conditions created, an improved thermoluminescent dosimetry (TLD) system was needed to support the cleanup and recovery. The deficiencies of the existing system were identified as an unsuitable dosimeter design and limited system automation available to support the ∼6000 dosimeters being processed monthly for record dose. As a result, a Panasonic-based TLD personnel dosimetry system was developed and installed by GPU Nuclear at the TMI facility. The components of this dosimetry system include a dosimeter design and associated interpretation algorithm, an extensive quality assurance program, and a computer-based dosimeter processing system. This dosimeter/algorithm design provides for the use of a changing beta correction factor (BCF), which is derived from beta spectral data collected by the dosimeter. The system computer-based processing equipment is driven using software developed to be user friendly, totally menu driven, and geared toward the implementation of an extensive quality assurance program for a production dosimetry system. In total, this software consists of over 95 programs that specifically support written dosimetry procedures

  14. Cytogenetic Dosimetry: Applications in Preparedness for and Response to Radiation Emergencies

    International Nuclear Information System (INIS)

    Cytogenetic dosimetry is recognized as a valuable dose assessment method which fills a gap in dosimetric technology, particularly when there are difficulties in interpreting the data, in cases where there is reason to believe that persons not wearing dosimeters have been exposed to radiation, in cases of claims for compensation for radiation injuries that are not supported by unequivocal dosimetric evidence, or in cases of exposure over an individual's working lifetime. The IAEA has maintained a long standing involvement in biological dosimetry commencing in 1978. This association has been through a sequence of coordinated research programmes (CRPs), the running of regional and national training courses, the sponsorship of individual training fellowships, and the provision of equipment to laboratories in Member States, establishing capabilities in biological dosimetry. From this has arisen the provision to Member States of advice regarding the best focus for research and suggestions for the most suitable techniques for future practice in biological dosimetry. One CRP resulted in the publication in 1986 of a manual, entitled Biological Dosimetry: Chromosomal Aberration Analysis for Dose Assessment (Technical Reports Series No. 260). This was superseded in 2001 by a revised second edition, Technical Reports Series No. 405. This present publication constitutes a third edition, with extensive updating to reflect the considerable advances that have been made in cytogenetic biological dosimetry during the past decade.

  15. Cytogenetic Dosimetry: Applications in Preparedness for and Response to Radiation Emergencies (Arabic Edition)

    International Nuclear Information System (INIS)

    Cytogenetic dosimetry is recognized as a valuable dose assessment method which fills a gap in dosimetric technology, particularly when there are difficulties in interpreting the data, in cases where there is reason to believe that persons not wearing dosimeters have been exposed to radiation, in cases of claims for compensation for radiation injuries that are not supported by unequivocal dosimetric evidence, or in cases of exposure over an individual's working lifetime. The IAEA has maintained a long standing involvement in biological dosimetry commencing in 1978. This association has been through a sequence of coordinated research programmes (CRPs), the running of regional and national training courses, the sponsorship of individual training fellowships, and the provision of equipment to laboratories in Member States, establishing capabilities in biological dosimetry. From this has arisen the provision to Member States of advice regarding the best focus for research and suggestions for the most suitable techniques for future practice in biological dosimetry. One CRP resulted in the publication in 1986 of a manual, entitled Biological Dosimetry: Chromosomal Aberration Analysis for Dose Assessment (Technical Reports Series No. 260). This was superseded in 2001 by a revised second edition, Technical Reports Series No. 405. This present publication constitutes a third edition, with extensive updating to reflect the considerable advances that have been made in cytogenetic biological dosimetry during the past decade

  16. The FISH chromosome painting technique in Biological Dosimetry : Evolution and applicability

    International Nuclear Information System (INIS)

    The capacity of ionising radiation to induce chromosomal aberrations has been used during decades to assess doses in persons accidentally exposed, giving rise to the discipline Biological Dosimetry. the Biological Dosimetry is a complement to the physical methods of dosimetry and in the situations where those are not available represent the only way to asses the doses received. During decades biological dosimetry has used the dicentric score to determine doses, since a good correlation between in vitro and in vivo irradiation results exists and the background yields are low. However, dicentrics yields decrease with time after irradiation. The translocations and insertions represent stable aberrations what means that they do not decrease in further cell divisions. The development at the end of the 80s of the FISH technique (Fluorescence In Situ Hybridization), represented a great step for the applicability of translocations score for biological dosimetry. In this paper, a review of the FISH chromosome painting technique is presented, addressing the facts that have needed to be solve before its routine use in retrospective dosimetry, as well as the aspects that will need further research in the near future. (Author) 54 refs

  17. Cytogenetic Dosimetry: Applications in Preparedness for and Response to Radiation Emergencies (French Edition)

    International Nuclear Information System (INIS)

    Cytogenetic dosimetry is recognized as a valuable dose assessment method which fills a gap in dosimetric technology, particularly when there are difficulties in interpreting the data, in cases where there is reason to believe that persons not wearing dosimeters have been exposed to radiation, in cases of claims for compensation for radiation injuries that are not supported by unequivocal dosimetric evidence, or in cases of exposure over an individual's working lifetime. The IAEA has maintained a long standing involvement in biological dosimetry commencing in 1978. This association has been through a sequence of coordinated research programmes (CRPs), the running of regional and national training courses, the sponsorship of individual training fellowships, and the provision of equipment to laboratories in Member States, establishing capabilities in biological dosimetry. From this has arisen the provision to Member States of advice regarding the best focus for research and suggestions for the most suitable techniques for future practice in biological dosimetry. One CRP resulted in the publication in 1986 of a manual, entitled Biological Dosimetry: Chromosomal Aberration Analysis for Dose Assessment (Technical Reports Series No. 260). This was superseded in 2001 by a revised second edition, Technical Reports Series No. 405. This present publication constitutes a third edition, with extensive updating to reflect the considerable advances that have been made in cytogenetic biological dosimetry during the past decade

  18. The application of thermoluminescence dosimetry in X-ray energy discrimination.

    Science.gov (United States)

    Nelson, V K; Holloway, L; McLean, I D

    2015-12-01

    Clinical dosimetry requires an understanding of radiation energy to accurately determine the delivered dose. For many situations this is known, however there are also many situations where the radiation energy is not well known, thus limiting dosimetric accuracy. This is the case in personnel dosimetry where thermo luminescent (TL) dosimetry is the method of choice. Traditionally beam energy characteristics in personnel dosimetry are determined through discrimination with the use of various filters fitted within a radiation monitor. The presence of scattered and characteristic radiation produced by these metallic filters, however, can compromise the results. In this study the TL response of five materials TLD100, TLD100H, TLD200, TLD400 and TLD500, was measured at various X-ray energies. The TL sensitivity ratio for various combinations of materials as a function of X-ray energy was calculated. The results indicate that in personal dosimetry a combination of three or more TL detector system has a better accuracy of estimation of effective radiation energy of an X-ray beam than some of the current method of employed for energy estimation and has the potential to improve the accuracy in dose determination in a variety of practical situations. The development of this method also has application in other fields including quality assurance of the orthovoltage therapy machines, dosimetry intercomparisons of kilovoltage X-ray beams, and measurement of the dose to critical organs outside a treatment field of a megavoltage therapy beam. PMID:26330215

  19. Cytogenetic Dosimetry: Applications in Preparedness for and Response to Radiation Emergencies (Russian Edition)

    International Nuclear Information System (INIS)

    Cytogenetic dosimetry is recognized as a valuable dose assessment method which fills a gap in dosimetric technology, particularly when there are difficulties in interpreting the data, in cases where there is reason to believe that persons not wearing dosimeters have been exposed to radiation, in cases of claims for compensation for radiation injuries that are not supported by unequivocal dosimetric evidence, or in cases of exposure over an individual's working lifetime. The IAEA has maintained a long standing involvement in biological dosimetry commencing in 1978. This association has been through a sequence of coordinated research programmes (CRPs), the running of regional and national training courses, the sponsorship of individual training fellowships, and the provision of equipment to laboratories in Member States, establishing capabilities in biological dosimetry. From this has arisen the provision to Member States of advice regarding the best focus for research and suggestions for the most suitable techniques for future practice in biological dosimetry. One CRP resulted in the publication in 1986 of a manual, entitled Biological Dosimetry: Chromosomal Aberration Analysis for Dose Assessment (Technical Reports Series No. 260). This was superseded in 2001 by a revised second edition, Technical Reports Series No. 405. This present publication constitutes a third edition, with extensive updating to reflect the considerable advances that have been made in cytogenetic biological dosimetry during the past decade

  20. Cytogenetic Dosimetry: Applications in Preparedness for and Response to Radiation Emergencies (Spanish Edition)

    International Nuclear Information System (INIS)

    Cytogenetic dosimetry is recognized as a valuable dose assessment method which fills a gap in dosimetric technology, particularly when there are difficulties in interpreting the data, in cases where there is reason to believe that persons not wearing dosimeters have been exposed to radiation, in cases of claims for compensation for radiation injuries that are not supported by unequivocal dosimetric evidence, or in cases of exposure over an individual’s working lifetime. The IAEA has maintained a long standing involvement in biological dosimetry commencing in 1978. This association has been through a sequence of coordinated research programmes (CRPs), the running of regional and national training courses, the sponsorship of individual training fellowships, and the provision of equipment to laboratories in Member States, establishing capabilities in biological dosimetry. From this has arisen the provision to Member States of advice regarding the best focus for research and suggestions for the most suitable techniques for future practice in biological dosimetry. One CRP resulted in the publication in 1986 of a manual, entitled Biological Dosimetry: Chromosomal Aberration Analysis for Dose Assessment (Technical Reports Series No. 260). This was superseded in 2001 by a revised second edition, Technical Reports Series No. 405. This present publication constitutes a third edition, with extensive updating to reflect the considerable advances that have been made in cytogenetic biological dosimetry during the past decade

  1. Intercomparison of dispersed radiation readings among film dosimetry, electronic and OSL with X-rays for low dose

    International Nuclear Information System (INIS)

    One of the personal dosimetry methods more used for several decades is the dosimetry type film, characterized to possess readings with certain margin of trust. Today other methods exist that many times are presupposed more reliable due to the nature of the detection like the electronic dosimeters or the OSL (Optically Stimulated Luminescence) dosimetry. With the purpose of comparing different methods and to can determining the existent differences among each method has been carried out an intercomparison assay. The different dosimeters have been exposed to dispersed radiation generated by a Hemodynamics equipment of the type -arch in C- and a dispersing system of the primary beam. Film dosimeters have been used; OSL (In Light), OSL (Nano Dots) and Electronic with the purpose of knowing and to valorize the existent differences among its readings. Always, the intercomparison exercises have demonstrated to be an useful tool when establishing the measurement capacity and the quality of the results emitted by the laboratories of personal dosimetry services. Also, this type of assays allows obtaining quality indicators of the laboratory performance and they are habitual part of the procedures for accreditation of the same ones. The Optically Stimulated Luminescence is a technology that has grown in Argentina so much in the area of personal dosimetry as in dosimetry in vivo (radiotherapy area). In this intercomparison study, the answers corresponding to each technology were looked for oneself irradiation of the disperse type, that is to say, of very low energy. (Author)

  2. In aqua vivo EPID dosimetry

    NARCIS (Netherlands)

    Wendling, M.; McDermott, L.N.; Mans, A.; Olaciregui-Ruiz, I.; Pecharroman-Gallego, R.; Sonke, J.J.; Stroom, J.; Herk, M. van; Mijnheer, B.J.

    2012-01-01

    PURPOSE: At the Netherlands Cancer Institute--Antoni van Leeuwenhoek Hospital in vivo dosimetry using an electronic portal imaging device (EPID) has been implemented for almost all high-energy photon treatments of cancer with curative intent. Lung cancer treatments were initially excluded, because t

  3. Manual of food irradiation dosimetry

    International Nuclear Information System (INIS)

    Following items are discussed: Fundamentals of dosimetry; description of irradiators; dose distribution in the product and commissioning the process; plant operation and process control; detailed instructions on using various dose-meter systems; references; glossary of some basic terms and concepts

  4. In vivo dosimetry in brachytherapy

    DEFF Research Database (Denmark)

    Tanderup, Kari; Beddar, Sam; Andersen, Claus Erik; Kertzscher Schwencke, Gustavo Adolfo Vladimir; Cygler, Joanna E.

    2013-01-01

    In vivo dosimetry (IVD) has been used in brachytherapy (BT) for decades with a number of different detectors and measurement technologies. However, IVD in BT has been subject to certain difficulties and complexities, in particular due to challenges of the high-gradient BT dose distribution and the...

  5. Thermoluminescence dosimetry environmental monitoring system

    International Nuclear Information System (INIS)

    In this report, characteristics and performances of an environmental monitoring system with thermoluminescence dosimetry are presented. Most of the work deals with the main physical parameters necessary for measurements of ambiental dose. At the end of this report some of level doses in the environment around the site of the ENEA Center of Energy Research Salluggia (Italy) are illustrated

  6. Dosimetry for Electron Beam Applications

    DEFF Research Database (Denmark)

    Miller, Arne

    1983-01-01

    This report describes two aspects of electron bean dosimetry, on one hand developaent of thin fil« dosimeters and measurements of their properties, and on the other hand developaent of calorimeters for calibration of routine dosimeters, e.g. thin films. Two types of radiochromic thin film dosimet...

  7. Video equipment of tele dosimetry and audio

    International Nuclear Information System (INIS)

    To develop a work in an area with high radiation, it requires of a detailed knowledge of the surroundings work, a communication and effective vision, a near dosimetric control. In a work where the spaces variables and reduced accesses exist, noise that hinders the communication, defendant operative condition, radiation field and taking of decision, it is necessary to have tools that allow a total control of the environment to make opportune and effective decisions, there where the task is developed. Under this elementary concept, it was developed in the Laguna Verde Central a project that it allowed a mechanism, interactive of control in spaces complex; to see, to hear, to speak, to measure. This concept takes to the creation of an equipped system with closed circuit of television, wireless communication systems, tele dosimetry wireless systems, VHS and DVD recording equipment, uninterrupted energy units. The system requires of an electric power socket, and the installation of two cables by CCTV camera. The system is mobilized by a person. He puts on in operation in 5 minutes using a verification list. The concept was developed in the project denominated VETA-1, (Video Equipment of Tele dosimetry and Audio). It is objective of this work to present before the society the development of the VETA-1 tool that conclude in their first prototype in May of the present year. The VETA-1 project arises by a necessity of optimizing dose, it is an ALARA tool, with a countless applications, like it was proven in the 12 recharge stop of the Unit 1. The VETA-1 project integrate a recording system, with the primary end of analyzing in the place where the task is developed the details for an effective and opportune decision, but the resulting information is of utility for the personnel's training and the planning of future works. The VETA-1 system is an ALARA tool of quick response control. (Author)

  8. Dosimetry of the Embalse nuclear power plant neutron/gamma mixed fields

    International Nuclear Information System (INIS)

    The aim of this work is to describe the method used at the Embalse nuclear power plant for carrying out personal dosimetry of the agents affected to the tasks on the Embalse nuclear power plant neutron-gamma mixed fields. (Author)

  9. Dosimetry in diagnostic and interventional radiology: international commission on radiation units and measurements and IAEA activities

    International Nuclear Information System (INIS)

    Dosimetric quantities are used in diagnostic and interventional radiology for the establishment of guidance or diagnostic reference levels and for the assessment of comparative risk; only a limited number of measurements serve for the assessment of potential risk. An additional objective of dosimetry in medical imaging is the assessment of equipment performance. The present situation in dosimetry for medical X ray imaging clearly indicates the need for international recommendations on appropriate radiation quantities and units. In addition, guidance on the calibration of instruments and measurements in hospitals is also needed.This has been recognized by the International Commission on Radiation Units and Measurements (ICRU) and resulted in the establishment of an ICRU report committee on patient dosimetry in medical imaging. The ICRU proposes a harmonized system of quantities and units for patient dosimetry in medical X ray imaging. New symbols are proposed for various quantities. General information is provided on measurement methods, the calibration of dosimeters and methods of determining organ and tissue doses. The IAEA is developing an international code of practice for dosimetry in X ray diagnostic radiology.The main objective is to help to achieve and maintain a high level of quality in dosimetry, to improve the implementation of traceable standards at the national level and to ensure the control of dose in X ray medical imaging worldwide. Compared with the ICRU, the IAEA puts more emphasis on the practical aspects of establishing proper calibration facilities, for example at the secondary standards dosimetry laboratories, and provides more detailed recommendations for clinical dosimetry. Coordination between ICRU and IAEA activities is considered important by both organizations. This has been taken into account in part by having a person who is a member of both committees.The intention is to have a restricted overlap between both documents and to harmonize

  10. ESR dosimetry: achievements and challenges

    Energy Technology Data Exchange (ETDEWEB)

    Baffa, O., E-mail: baffa@usp.br [Universidade de Sao Paulo, Departamento de Fisica, Av. Bandeirantes 3900, 14040-901 Ribeirao Preto, Sao Paulo (Brazil)

    2015-10-15

    Full text: Electron Spin Resonance (ESR), also known as Electron Paramagnetic Resonance (EPR) and more recently as Electron Magnetic Resonance (Emr), is a spectroscopy technique able to detect unpaired electrons such as those created by the interaction ionizing radiation with matter. When the unpaired electrons created by ionizing radiation are stable over some reasonable time, ESR can be used to measure the radiation dose deposited in the material under study. In principle, any insulating material that satisfies this requisite can be used as a dosimeter. ESR has been used in retrospective dosimetry in case of radiological accidents using natural constituents of human body such as teeth, bones and nails as well as fortuitous materials as sugar, sweeteners and plastics. When using teeth the typical detected dose is 0.5 Gy for, for X-Band spectrometers (9 GHz) and even lower doses if higher frequency spectrometers are used. Clinical dosimetry is another area of potential use of this dosimetric modality. In this application the amino acid alanine has been proposed and being used. Alanine dosimeters are very easy to prepare and require no complicated treatments for use. Alanine/ESR dosimetry satisfies many of the required properties for clinical applications such as water equivalent composition, independence of response for the energy range used in therapy and high precision. Other organic materials such as ammonium tartrate are being investigated to increase the sensitivity of ESR for clinical applications. Finally, industrial applications can also benefit from this dosimetry. The challenges to expand applications, the number of users and research groups of ESR dosimetry will be discussed. (Author)

  11. ESR dosimetry: achievements and challenges

    International Nuclear Information System (INIS)

    Full text: Electron Spin Resonance (ESR), also known as Electron Paramagnetic Resonance (EPR) and more recently as Electron Magnetic Resonance (Emr), is a spectroscopy technique able to detect unpaired electrons such as those created by the interaction ionizing radiation with matter. When the unpaired electrons created by ionizing radiation are stable over some reasonable time, ESR can be used to measure the radiation dose deposited in the material under study. In principle, any insulating material that satisfies this requisite can be used as a dosimeter. ESR has been used in retrospective dosimetry in case of radiological accidents using natural constituents of human body such as teeth, bones and nails as well as fortuitous materials as sugar, sweeteners and plastics. When using teeth the typical detected dose is 0.5 Gy for, for X-Band spectrometers (9 GHz) and even lower doses if higher frequency spectrometers are used. Clinical dosimetry is another area of potential use of this dosimetric modality. In this application the amino acid alanine has been proposed and being used. Alanine dosimeters are very easy to prepare and require no complicated treatments for use. Alanine/ESR dosimetry satisfies many of the required properties for clinical applications such as water equivalent composition, independence of response for the energy range used in therapy and high precision. Other organic materials such as ammonium tartrate are being investigated to increase the sensitivity of ESR for clinical applications. Finally, industrial applications can also benefit from this dosimetry. The challenges to expand applications, the number of users and research groups of ESR dosimetry will be discussed. (Author)

  12. Dosimetry for radiopharmaceuticals (invited paper)

    International Nuclear Information System (INIS)

    Developments in internal dosimetry for radiopharmaceuticals are summarised, with special reference to work carried out within the International Commission on Radiological Protection (ICRP). Differences and similarities with internal dosimetry for occupationally exposed workers and for members of the public are identified. What is unique for radiopharmaceuticals is their special biokinetics. The products are designed to get high uptake in certain organs and tissues. When a new compound is introduced there are few long-term retention data for humans available. Therefore efforts have continuously to be made to investigate the biokinetics and dosimetry of new products as well as older products, for which the dosimetry is uncertain, e.g. pure β-emitters. Serial, quantitative gamma camera images of patients will continue to be the base for biokinetic information together with analysis of urine samples. The observed time-activity curves are described using exponential functions with specified fractional activities and half-times. The physical calculations are based on the MIRD formalism. For more detailed dosimetry, CT, MR and ultrasound can be used to localise organs and to determine their volumes. Such measurements are also needed for the construction of realistic phantoms (mathematically describable phantoms, 'voxel' phantoms and anthropomorphic phantoms) which are the geometrical base for dose calculations. Variations in anatomy and biokinetics between individuals due to age, gender and disease have to be given greater consideration in the future. Information on the distribution of a radionuclide within organs and tissues is of importance for its therapeutic use as is the intracellular localisation of low energy electron emitters both in therapy and diagnosis. (author)

  13. The EURADOS/CONRAD activities on radiation protection dosimetry in medicine

    International Nuclear Information System (INIS)

    Full text: This presentation gives an overview on the research activities that EURADOS coordinates in the field of radiation protection dosimetry in medicine. EURADOS is an organization founded in 1981 to advance the scientific understanding and the technical development of the dosimetry of ionising radiation in the fields of radiation protection, radiobiology, radiation therapy and medical diagnosis by promoting collaboration between European laboratories. EURADOS operates by setting up Working Groups dealing with particular topics. Currently funded through the CONRAD project of the 6th EU Framework Programme, EURADOS has working groups on Computational Dosimetry, Internal Dosimetry, Complex mixed radiation fields at workplaces, and Radiation protection dosimetry of medical staff. The latter working group coordinates and promotes European research for the assessment of occupational exposures to staff in therapeutic and diagnostic radiology workplaces. Research is coordinated by sub-groups covering three specific areas: 1: Extremity dosimetry in nuclear medicine and interventional radiology: this sub-group coordinates investigations in the specific fields of the hospitals and studies of doses to different parts of the hands, arms, legs and feet; 2: Practice of double dosimetry: this sub-group reviews and evaluates the different methods and algorithms for the use of dosemeters placed above and below lead aprons, especially to determine personal doses to cardiologists during cardiac catheterisation, but also in CT-fluoroscopy and some nuclear medicine developments (e.g. use of Re-188); and 3: Use of electronic personal dosemeters in interventional radiology: this sub-group coordinates investigations in laboratories and hospitals, and intercomparisons with passive dosemeters with the aim to enable the formulation of standards. (author)

  14. Person, personality, responsibility

    OpenAIRE

    GHEORGHE MIHAI; EMILIA MIHAI

    2005-01-01

    Modern times consider as a person the individual man being endowed with reason and conscience; this man cannot be but person because he shows so many persons. According to the positive law the human individual is considered a person: natural person in civil relations; criminal in criminal relations; public officer in administrative relations, etc. “Natural person”, “criminal”, “public officer” are terms from legal terminology of different branches of law that define the individual in the law,...

  15. Automated Calibration of Dosimeters for Diagnostic Radiology

    International Nuclear Information System (INIS)

    Calibration of dosimeters for diagnostic radiology includes current and charge measurements, which are often repetitive. However, these measurements are usually done using modern electrometers, which are equipped with an RS-232 interface that enables instrument control from a computer. This paper presents an automated system aimed to the measurements for the calibration of dosimeters used in diagnostic radiology. A software application was developed, in order to achieve the acquisition of the electric charge readings, measured values of the monitor chamber, calculation of the calibration coefficient and issue of a calibration certificate. A primary data record file is filled and stored in the computer hard disk. The calibration method used was calibration by substitution. With this system, a better control over the calibration process is achieved and the need for human intervention is reduced. the automated system will be used in the calibration of dosimeters for diagnostic radiology at the Cuban Secondary Standard Dosimetry Laboratory of the Center for Radiation Protection and Hygiene. (Author)

  16. Metabolic dosimetry: how to reduce arbitrary?; Dosimetrie metabolique: comment reduire l'arbitraire

    Energy Technology Data Exchange (ETDEWEB)

    Bardies, M. [Centre National de la Recherche Scientifique, 44 - Nantes (France). Unite INSERM 463

    1999-10-01

    The dosimetry in the case of diagnosis is in the field of radiation protection, it is a question of making sure of being under the acceptable limits for the patients. In the case of therapy, it is necessary to know the radiation dose susceptible to be delivered to the patient. this dose must predict the potential efficiency of the treatment. three methods are used actually. By order of increasing precision, we have the calculations with anthropomorphic phantoms, the techniques of convolutions of kernel-points and the methods of direct calculation by Monte-Carlo simulation. The first one is faster than the others ones but it is not personalized as the second ones are. Different techniques of images processing, SPECT, PET are reviewed to see their advantages and disadvantages. Others techniques such counting of eliminated activity by urines and or faeces allow to raise the activity present in the body by simple substraction. (N.C.)

  17. AUTOMATION OF INVENTORY PROCESS OF PERSONAL COMPUTERS

    Directory of Open Access Journals (Sweden)

    A. I. Zaharenko

    2013-01-01

    Full Text Available The modern information infrastructure of a large or medium-sized enterprise is inconceivable without an effective system of the computer equipment and fictitious assets inventory. An example of creation of such system which is simple for implementation and has low cost of possession is considered in this article.

  18. Improvement and calibration of a SSNT personal dosemeter and study of importance of albedo factor for dose calculation

    International Nuclear Information System (INIS)

    The Neutriran albedo neutron dosemeter has been improved and calibrated for neutron personal dosimetry. The Monte Carlo code MCNP4b was used to calculate the thermal neutrons backscattered from the body (albedo factor). Backscattering from the wall, ceiling and floor in calibration room was considered also via simulation by MCNP4C. A semi automated counting system applying a high-resolution scanner was used for counting of tracks. An 241Am source was used to produce similar alpha particles from 10B (n,α) 7Li reaction for the optimisation of scanner parameters to distinguish and separate the tracks in SSNTD, which lead to a better distinction between etched alpha tracks and, consequently, a higher linear region of dose characteristic. (authors)

  19. Proceedings of the 5. symposium on neutron dosimetry. Beam dosimetry

    International Nuclear Information System (INIS)

    Proceedings of the fifth symposium on neutron dosimetry, organized at Neuherberg, 17-21 September 1984, by the Commission of the European Communities and the GSF Neuherberg, with the co-sponsorship of the US Department of Energy, Office of Health and Environmental Research. The proceedings deal with research on concepts, instruments and methods in radiological protection for neutrons and mixed neutron-gamma fields, including the generation, collection and evaluation of new dosimetric data, the derivation of relevant radiation protection quantitites, and the harmonization of experimental methods and instrumentation by intercomparison programmes. Besides radiation protection monitoring, the proceedings also report on the improvement of neutron beam dosimetry in the fields of radiobiology and radiation therapy

  20. System of automated map design

    International Nuclear Information System (INIS)

    Preprint 'System of automated map design' contains information about the program shell for construction of territory map, performing level line drawing of arbitrary two-dimension field (in particular, the radionuclide concentration field). The work schedule and data structures are supplied, as well as data on system performance. The preprint can become useful for experts in radioecology and for all persons involved in territory pollution mapping or multi-purpose geochemical mapping. (author)

  1. Development of new methodology for dose calculation in photographic dosimetry

    International Nuclear Information System (INIS)

    The personal dosemeter system of IPEN is based on film dosimetry. Personal doses at IPEN are mainly due to X or gamma radiation. The use of personal photographic dosemeters involves two steps: firstly, data acquisition including their evaluation with respect to the calibration quantity and secondly, the interpretation of the data in terms of effective dose. The effective dose was calculated using artificial intelligence techniques by means of neural network. The learning of the neural network was performed by taking the readings of optical density as a function of incident energy and exposure from the calibration curve. The obtained output in the daily grind is the mean effective energy and the effective dose. (author)

  2. Dosimetry Control: Technic and methods. Proceedings of the international workshop 'Actual problems of dosimetry'

    International Nuclear Information System (INIS)

    There is a number of unsolved problems of both dosimetric and radiometric control, questions of the biological dosimetry, reconstruction of dozes of irradiation of the population at radiation incidents, which require coordination of efforts of scientists in various areas of a science. The submitted materials are grouped on five units: dosimetry engineering, biological dosimetry and markers of radiation impact, dosimetry of a medical irradiation, normative and measurement assurance of the dosimetric control, monitoring and reconstruction of dozes at radiation incidents

  3. Automated Budget System

    Data.gov (United States)

    Department of Transportation — The Automated Budget System (ABS) automates management and planning of the Mike Monroney Aeronautical Center (MMAC) budget by providing enhanced capability to plan,...

  4. Worldwide quality assurance networks for radiotherapy dosimetry

    International Nuclear Information System (INIS)

    Several national and international organizations have developed various types and levels of external audit systems for radiotherapy dosimetry, either based on on-site review visits or using mailed dosimetry systems.Three major TLD (thermoluminescence dosimetry) networks make available postal dose audits to a large number of radiotherapy centres on a regular basis. These are the IAEA/WHO (World Health Organization) TLD postal dose audit service, which operates worldwide; the European Society for Therapeutic Radiology and Oncology (ESTRO) network, known as EQUAL, which operates in the European Union; and the Radiological Physics Center (RPC) network in North America. Other external audit programmes are either associated with national and international clinical trial groups or perform national dosimetry comparisons that check radiotherapy dosimetry at various levels. The paper discusses the present status of the worldwide quality assurance networks in radiotherapy dosimetry and reviews the activities of the three main TLD networks: the IAEA/WHO, EQUAL and RPC networks. (author)

  5. Dosimetry by ESR spectroscopy of alanine

    International Nuclear Information System (INIS)

    Dosimetry based on electron spin resonance analysis of radiation-induced free radicals in amino acids (e.g. L-alanine) is relevant to biological dosimetry applications. Typical features are a wide dose range covering more than 5 decades (1-105Gy), energy independent response for photons above 100 keV, long-term stability of the ESR signal, and fast straightforward readout technique. Typical dosimeter samples, consisting of small pellets of microcrystalline amino acids in paraffin, are rugged, non-toxic, and insensitive to surface contaminations. Moreover, they are prepared homogeneously and inexpensively in large batches and can be evaluated repeatedly and supply archival dosimetry data. They have proven to be highly useful in various applications of radiation processing and sterilization dosimetry, food irradiation, quality control, radiation dosimetry, radiation therapy measurements, and as a reference system for dosimetry mailing intercomparisons. (author)

  6. Energy response improvement for photon dosimetry using pulse analysis

    Science.gov (United States)

    Zaki, Dizaji H.

    2016-02-01

    During the last few years, active personal dosimeters have been developed and have replaced passive personal dosimeters in some external monitoring systems, frequently using silicon diode detectors. Incident photons interact with the constituents of the diode detector and produce electrons. These photon-induced electrons deposit energy in the detector's sensitive region and contribute to the response of diode detectors. To achieve an appropriate photon dosimetry response, the detectors are usually covered by a metallic layer with an optimum thickness. The metallic cover acts as an energy compensating shield. In this paper, a software process is performed for energy compensation. Selective data sampling based on pulse height is used to determine the photon dose equivalent. This method is applied to improve the energy response in photon dosimetry. The detector design is optimized for the response function and determination of the photon dose equivalent. Photon personal dose equivalent is determined in the energy range of 0.3-6 MeV. The error values of the calculated data for this wide energy range and measured data for 133Ba, 137Cs, 60Co and 241Am-Be sources respectively are up to 20% and 15%. Fairly good agreement is seen between simulation and dose values obtained from our process and specifications from several photon sources.

  7. Results from 2010 Caliban Criticality Dosimetry Intercomparison

    International Nuclear Information System (INIS)

    The external dosimetry program participated in a criticality dosimetry intercomparison conducted at the Caliban facility in Valduc, France in 2010. Representatives from the dosimetry and instrumentation groups were present during testing which included irradiations of whole-body beta/gamma (HBGT) and neutron thermoluminescent dosimeters (TLDs), a fixed nuclear accident dosimeter (FNAD), electronic alarming dosimeters, and a humanoid phantom filled with reference man concentrations of sodium. This report reviews the testing procedures, preparations, irradiations, and presents results of the tests.

  8. Report on the Personnel Dosimetry at AB Atomenergi during 1962

    International Nuclear Information System (INIS)

    This report presents the results of the personnel dosimetry at AB Atomenergi during 1962. No doses exceeding the recommendations of ICRP have been reported. The sum of the reported external total body doses (≥ 100 mrem/quarter) is for the whole of AB Atomenergi during this year 74. 2 manrem corresponding to about 50 mrem/year and person or 1 % of the maximum permissible dose. 32500 gamma films and 6200 neutron films have been evaluated. The total number of urine analyses is 2700 and of whole body measurements 10

  9. Report on the Personnel Dosimetry at AB Atomenergi during 1962

    International Nuclear Information System (INIS)

    This report presents the results of the personnel dosimetry at AB Atomenergi during 1963. No doses exceeding the recommendations of ICRP have been reported. The sum of the reported external total body doses during the year is for AB Atomenergi 64.2 manrem which, distributed over the whole company personnel, corresponds to about 40 mrem per year and person or about 1 % of the maximum permissible dose. 37800 gamma films and 6700 neutron films have been evaluated. The total number of urine analyses is 3603 and of whole body measurements 211

  10. An overview of retrospective occupational dosimetry at BNFL

    International Nuclear Information System (INIS)

    Reconstruction of occupational radiation doses in BNFL has been shown to be feasible but has required a significant level of technical resources to cater for the complexity and range of the plants involved and is generally limited in scale of use because of the key requirement for detailed work history information in the dose reconstruction process. The main dose reconstruction work required in BNFL has involved neutron doses for litigation and Compensation Scheme purposes, reflecting the historical difficulties associated with personal neutron dosimetry. Early indications are that the level of reconstructed neutron dose is, in general, small compared to the recorded photon dose. (author)

  11. Personnel radiation monitoring by thermoluminescence dosimetry (1995-96)

    International Nuclear Information System (INIS)

    Personnel radiation monitoring which is the dose assessment of individual doses from external radiation received by radiation workers has been carried out by Thermoluminescence Dosimetry system consisting of a Vinten Toledo TLD reader, LiF dosimeters and associated equipment. The exposed TLD dosimeters were measured by TLD reader and the dose evaluation and dose registration were done on personal computer. Due to the records of 1995-96, most of the radiation workers complied with the permissible dose recommended by IAEA and ICRP 60. (author)

  12. Gel dosimetry for conformal radiotherapy

    International Nuclear Information System (INIS)

    With the continuum development of conformal radio therapies, aimed at delivering high dose to tumor tissue and low dose to the healthy tissue around, the necessities has appeared of suitable improvement of dosimetry techniques giving the possibility of obtaining dose images to be compared with diagnostic images. Also if wide software has been developed for calculating dose distributions in the fields of various radiotherapy units, experimental verifications are necessary, in particular in the case of complex geometries in conformal radiotherapy. Gel dosimetry is a promising method for imaging the absorbed dose in tissue-equivalent phantoms, with the possibility of 3D reconstruction of the spatial dose distribution, with milli metric resolution. Optical imaging of gel dosimeters, based on visible light absorbance analysis, has shown to be a reliable technique for achieving dose distributions. (Author)

  13. Dosimetry in radiotherapy. V.1

    International Nuclear Information System (INIS)

    A series of symposia on dosimetry in medicine and biology have been held by the IAEA in co-operation with WHO. The present symposium was the first one focusing on ''Dosimetry in Radiotherapy''. The papers presented reflected the different steps in the calibration chain such as the calibration standards established by the National Standards Laboratories and the conversion of the reading of calibrated instruments to the desired quantity, i.e. absorbed dose to water at a reference point in the user's beam at the radiotherapy clinic. The programme further examined the procedures necessary for optimization of the treatment of the patient, such as treatment planning methods, dose distribution studies, new techniques of dose measurement, improvements in the physical dose distributions/conformation therapy and special problems involved in total body treatments. Results of quality assurance in radiotherapy were presented from local hospitals as well as from national and international studies. Refs, figs and tabs

  14. Radiation protection dosimetry and calibrations

    International Nuclear Information System (INIS)

    At the SCK-CEN different specialised services are delivered for a whole range of external and internal customers in the radiation protection area. For the expertise group of radiation protection dosimetry and calibrations, these services are organized in four different laboratories: dosimetry, anthropogammametry, nuclear calibrations and non-nuclear calibrations. The services are given by a dedicated technical staff who has experience in the handling of routine and specialised cases. The scientific research that is performed by the expertise group makes sure that state-of-the-art techniques are being used, and that constant improvements and developments are implemented. Quality Assurance is an important aspect for the different services, and accreditation according national and international standards is achieved for all laboratories

  15. Relative dosimetry by Ebt-3

    International Nuclear Information System (INIS)

    In the present work relative dosimetry in two linear accelerator for radiation therapy was studied. Both Varian Oncology systems named Varian Clinac 2100-Cd and MLC Varian Clinac i X were used. Gaf Chromic Ebt-3 film was used. Measurements have been performed in a water equivalent phantom, using 6 MV and 18 MV photon beams on both Linacs. Both calibration and Electron irradiations were carried out with the ionization chamber placed at the isocenter, below a stack of solid water slabs, at the depth of dose maximum (D max), with a Source-to-Surface Distance (SSD) of 100 cm and a field size of 10 cm x 10 cm. Calibration and dosimetric measurements photons were carried out under IAEA-TRS 398 protocol. Results of relative dosimetry in the present work are discussed. (Author)

  16. Some aspects on neutron dosimetry

    International Nuclear Information System (INIS)

    The American National Council on Radiation Protection and measurements (1) has recently issued a statement regarding dose limitation system for neutrons. The changes proposed in that statement presented substantial problems regarding the personnel exposure to neutrons and had pointed out the need to reassess an adequate current neutron dosimetry practice. Generally, the same types of dosimeters i.e. Nuclear Track (NTA films) and TLD-Albedo, have been used at major nuclear facilities over the past 15 years. here recently, other dosimetry methods such as track etch with polycarbonates such as CR-39 have been developed. However these should be recognized as local systems aiming to the development of better and more applicable dosimeters. 4 tab

  17. Dosimetry in radiotherapy. V.2

    International Nuclear Information System (INIS)

    A series of symposia on dosimetry in medicine and biology have been held by the IAEA in co-operation with WHO. The present symposium was the first one focusing on ''Dosimetry in Radiotherapy''. The papers presented reflected the different steps in the calibration chain such as the calibration standards established by the National Standards Laboratories and the conversion of the reading of calibrated instruments to the desired quantity, i.e. absorbed dose to water at a reference point in the user's beam at the radiotherapy clinic. The programme further examined the procedures necessary for optimization of the treatment of the patient, such as treatment planning methods, dose distribution studies, new techniques of dose measurement, improvements in the physical dose distributions/conformation therapy and special problems involved in total body treatments. Results of quality assurance in radiotherapy were presented from local hospitals as well as from national and international studies. Refs, figs and tabs

  18. Dose Estimation from Daily and Weekly Dosimetry Data

    Energy Technology Data Exchange (ETDEWEB)

    Ostrouchov, G.

    2001-11-16

    amount of bias also varies greatly between person-years. Second, the addition of pocket-meter information reduces uncertainty for some person-years, while increasing it for others. Together, these results suggest that detailed pocket-meter and film dosimetry information is required to obtain unbiased and reliable dosimetry data for use in epidemiologic studies of workers at ORNL.

  19. Dose Estimation from Daily and Weekly Dosimetry Data

    International Nuclear Information System (INIS)

    greatly between person-years. Second, the addition of pocket-meter information reduces uncertainty for some person-years, while increasing it for others. Together, these results suggest that detailed pocket-meter and film dosimetry information is required to obtain unbiased and reliable dosimetry data for use in epidemiologic studies of workers at ORNL

  20. MISTI Shielding and Dosimetry Experiment Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Reliable on-orbit dosimetry is necessary for understanding effects of space radiation environments on spacecraft microelectronics performance and comparison of...

  1. Dosimetry for electron beam sterilization

    International Nuclear Information System (INIS)

    According to ISO 11137-1 (sect 4.3.4) dosimetry used in the development, validation and routine control of the sterilization process shall have measurement traceability to national or international standards and shall have a known level of uncertainty. It can only be obtained through calibration of the dosimeters. In presented lecture different types of dosimeter systems for electron beams (calorimeters, radiochromic film dosimeters, alanine / EPR) and their calibration are described

  2. Dosimetry of β extensive sources

    International Nuclear Information System (INIS)

    In this work, we have been studied, making use of the Penelope Monte Carlo simulation code, the dosimetry of β extensive sources in situations of spherical geometry including interfaces. These configurations are of interest in the treatment of the called cranealfaringyomes of some synovia leisure of knee and other problems of interest in medical physics. Therefore, its application can be extended toward problems of another areas with similar geometric situation and beta sources. (Author)

  3. Dosimetry of total body irradiation

    International Nuclear Information System (INIS)

    In the treatment of disseminated malignancies an improvement in the curability and reduction of complication rates require high precision total body irradiation (TBI) and correct reporting of relevant treatment parameters. Optimal TBI dosimetry is the basis. Radiooncological and radiobiological requirements as well as the special physical situation have to be considered. To review the efforts of medical physicists, highlights from TBI workshops and publications are summarized. Additionally, dosimetric data from 34 European radiooncological centres contributing to the recent ESTRO inquiry on TBI are analysed. The topics are: absorbed dose and dose monitor calibration, determination of absolute and relative doses, dose ratios, attenuation data and heterogeneity corrections; TBI dose calculation methods regarding patient position, beam incidence, body shape and thickness, lung size and density; methods of TBI treatment planning including calculated dose modification and of TBI quality assurance. In conclusion, the following recommendations can be given: TBI dosimetry shall be performed under TBI conditions, close to the real treatment situation. The absorbed dose to water must be determined. The dose monitor should be calibrated against dose measurements at the centre of a water equivalent phantom of TBI equivalent size and typical thickness. Photon fluence profiles have to be measured with small phantoms. Influences on the local dose must be investigated systematically. A reproducible AP/PA TBI technique should be used. The TBI dose shall be specified to mid-abdomen and reported in units of gray. The single and total dose and the dose rate to the lungs, the number of fractions and the treatment time schedule must be stated. In vivo dosimetry is required if non-reliable TBI techniques are used. An international TBI dosimetry intercomparison could assist these efforts to improve the treatment of acute leukaemia. (author). 89 refs, 3 figs, 13 tabs

  4. Topical Review: Polymer gel dosimetry

    OpenAIRE

    Baldock, C; De Deene, Y; Doran, S.; Ibbott, G; Jirasek, A.; Lepage, M.; McAuley, K B; Oldham, M; Schreiner, L J

    2010-01-01

    Polymer gel dosimeters are fabricated from radiation sensitive chemicals which, upon irradiation, polymerize as a function of the absorbed radiation dose. These gel dosimeters, with the capacity to uniquely record the radiation dose distribution in three-dimensions (3D), have specific advantages when compared to one-dimensional dosimeters, such as ion chambers, and two-dimensional dosimeters, such as film. These advantages are particularly significant in dosimetry situations where steep dose ...

  5. Radiation protection, dosimetry and archaeometry

    International Nuclear Information System (INIS)

    The activities performed by the radiation protection, dosimetry and archeometry group of the Atomic Institute of the Austrian Universities during 1999-2001 are briefly described, they include: internal radiation protection (a pilot project based on select x-ray diagnostics investigations where the surface dose was measured and compared against the EU standards), dose rates for patients and personnel during radiological check up, environmental monitoring. In the field of dosimetry, a new dosimeter material (CaF2:Tm was investigated), an active and a passive Bonner-Kugel-spectrometer to measure the neutron spectrum and their dose at high altitudes was built. In the project phantom during 600 days the energy distribution and equivalent dose in a human phantom was measured. Dosimetry and spectrometry (neutrons) on high mountains and airplanes were performed. Earlier cells apoptosis after irradiation with 60Co gamma radiation and neutrons was investigated and age estimation was performed on samples from middle Neolithic period, Bronze age an Roman empire. (nevyjel)

  6. EPR Dosimetry - Present and Future

    International Nuclear Information System (INIS)

    In the past, IAEA has played a central role in stipulating research and development in EPR high-dose standardisation as well as in coordinating and organising international dose intercomparison programs, within the Member States of the United Nations from the mid-seventies till today. The future tasks of EPR dosimetry seem to tend towards different subjects such as bio markers, biological radiation effects, post-accident dose reconstruction in the environment, and retrospective human dosimetry. The latter may be considered a promising tool for epidemiology on the way to re-define radiation risk of man for chronicle radiation exposures, based on e.g. South Ural civil population and radiation workers. There are on-going international activities in the field of standardising high-level dosimetry by the American Standards on Testing and Materials (Astm), and by the International Organisation of Standards (ISO). The International Commission on Radiation Units and Measurements (ICRU) is considering the establishment of relevant recommendations concerning industrial radiation processing, but also human dose reconstruction. (Author)

  7. EPR Dosimetry - Present and Future

    Energy Technology Data Exchange (ETDEWEB)

    Regulla, D.F. [GSF - National Research Centre for Environment and Health, Institute of Radiation Protection, 85764 Neuherberg (Germany)

    1999-07-01

    In the past, IAEA has played a central role in stipulating research and development in EPR high-dose standardisation as well as in coordinating and organising international dose intercomparison programs, within the Member States of the United Nations from the mid-seventies till today. The future tasks of EPR dosimetry seem to tend towards different subjects such as bio markers, biological radiation effects, post-accident dose reconstruction in the environment, and retrospective human dosimetry. The latter may be considered a promising tool for epidemiology on the way to re-define radiation risk of man for chronicle radiation exposures, based on e.g. South Ural civil population and radiation workers. There are on-going international activities in the field of standardising high-level dosimetry by the American Standards on Testing and Materials (Astm), and by the International Organisation of Standards (ISO). The International Commission on Radiation Units and Measurements (ICRU) is considering the establishment of relevant recommendations concerning industrial radiation processing, but also human dose reconstruction. (Author)

  8. Dosimetry studies in Zaborie village

    Energy Technology Data Exchange (ETDEWEB)

    Takada, J. E-mail: jtakada@ipc.hiroshima-u.ac.jp; Hoshi, M.; Endo, S.; Stepanenko, V.F.; Kondrashov, A.E.; Petin, D.; Skvortsov, V.; Ivannikov, A.; Tikounov, D.; Gavrilin, Y.; Snykov, V.P

    2000-05-15

    Dosimetry studies in Zaborie, a territory in Russia highly contaminated by the Chernobyl accident, were carried out in July, 1997. Studies on dosimetry for people are important not only for epidemiology but also for recovery of local social activity. The local contamination of the soil was measured to be 1.5-6.3 MBq/m{sup 2} of Cs-137 with 0.7-4 {mu}Sv/h of dose rate. A case study for a villager presently 40 years old indicates estimations of 72 and 269 mSv as the expected internal and external doses during 50 years starting in 1997 based on data of a whole-body measurement of Cs-137 and environmental dose rates. Mean values of accumulated external and internal doses for the period from the year 1986 till 1996 are also estimated to be 130 mSv and 16 mSv for Zaborie. The estimation of the 1986-1996 accumulated dose on the basis of large scale ESR teeth enamel dosimetry provides for this village, the value of 180 mSv. For a short term visitor from Japan to this area, external and internal dose are estimated to be 0.13 mSv/9d (during visit in 1997) and 0.024 mSv/50y (during 50 years starting from 1997), respectively.

  9. EPR dosimetry - present and future

    International Nuclear Information System (INIS)

    In the past, IAEA has played a central role in stipulating research and development in EPR high-dose standardisation as well as co-ordinating and organising international dose intercomparison programs, within the Member States of the United Nations from the mid-seventies till today. The future tasks of EPR dosimetry seem to tend towards different subjects such as biomarkers, biological radiation effects, post-accident dose reconstruction in the environment, and retrospective human dosimetry. The latter may be considered a promising tool for epidemiology on the way to re-define radiation risk of man for chronicle radiation exposures, based on e.g. South Ural civil population and radiation workers. There are on-going international activities in the field of standardising high-level dosimetry by the American Standards on Testing and Materials (ASTM), and the International Organisation of Standards (ISO) as well as those of the International Commission on Radiation Units and Measurements (ICRU) considering the establishment of relevant recommendations concerning industrial radiation processing, but also human dose reconstruction. (author)

  10. Fourth international radiopharmaceutical dosimetry symposium

    International Nuclear Information System (INIS)

    The focus of the Fourth International Radiopharmaceutical Dosimetry Symposium was to explore the impact of current developments in nuclear medicine on absorbed dose calculations. This book contains the proceedings of the meeting including the edited discussion that followed the presentations. Topics that were addressed included the dosimetry associated with radiolabeled monoclonal antibodies and blood elements, ultrashort-lived radionuclides, and positron emitters. Some specific areas of discussion were variations in absorbed dose as a result of alterations in the kinetics, the influence of radioactive contaminants on dose, dose in children and in the fetus, available instrumentation and techniques for collecting the kinetic data needed for dose calculation, dosimetry requirements for the review and approval of new radiopharmaceuticals, and a comparison of the effect on the thyroid of internal versus external irradiation. New models for the urinary blader, skeleton including the active marrow, and the blood were presented. Several papers dealt with the validity of traditional ''average-organ'' dose estimates to express the dose from particulate radiation that has a short range in tissue. These problems are particularly important in the use of monoclonal antibodies and agents used to measure intracellular functions. These proceedings have been published to provide a resource volume for anyone interested in the calculation of absorbed radiation dose

  11. Recall of Personal Dosimeters Not Presently in Use

    CERN Multimedia

    SC Unit

    2008-01-01

    The Dosimetry Service requests all persons who do not require access to radiation areas in the foreseeable future to return their personal dosimeter to the Dosimetry Service. This concerns, for example, experimental physicists whose beam time is over until 2009, or persons whose work profile has changed and therefore no longer need regular access to radiation areas. When regular access to radiation areas is needed again at a later date, a new dosimeter can be attributed if the prerequisites (medical fitness certificate, RP course) are met. This recall will allow personal dosimeters to be attributed to personnel who will soon be working in newly created radiation areas at the LHC. Thank you for your understanding and collaboration. Thomas Otto on behalf of the Dosimetry Service Radiation Protection Group

  12. Study on personal dosimetric method using OSL dosimeter

    International Nuclear Information System (INIS)

    Ionization radiation measurement using Optically Stimulated Luminescence (OSL) technology has been researched and developed for more than 50 years in several advanced countries in the world as USA, Japan, etc. OSL has many advantages as high sensitivity, faster readout process, convenient and simple procedure,etc. This technology is widely used in many applications. Recently, for the purpose of applying more various approaches on personal dosimetry, Radiation Dosimetry Laboratory belong to Center for Radiation Protection/ INST has researched OSL technology for personal dosimetry purpose, in this study we present OSL principle and experiments to determine characteristics of OSL personal dosimeters using Al2O3:C material and procedure to evaluate personal dose using OSL InLight dosimeters and Microstar system for photon radiation. (author)

  13. Personal monitoring for external radiations: associated work of EURADOS

    International Nuclear Information System (INIS)

    This paper was presented at the Society for Radiological Protection Meeting on Practical Radiation Protection held in London, 31 March - 1 April 1987. The paper covers a number of topical issues on personal dosimetry concerning technical and financial aspects as well as new initiatives and developments within the field. The paper concludes with a summary of the related work of EURADOS, (European Radiation Dosimetry Group). (author)

  14. Modern phosphate glass dosimeters - the alternative in personal monitoring

    International Nuclear Information System (INIS)

    After a pattern approval by the PTB a new automatic photoluminescence dosimetry (PLD) system has been recently introduced as an official dosimeter into routine monitoring. As an example this dosimeter characterizes the recent developments in personal dosimetry. The paper describes the dosimetric properties of the flat glass dosimeter using the readout system Toshiba FGD-10 and aspects of application in comparison to other dosimeter types. The flat glass dosimeter is today an attractive alternative to the still used film and thermoluminescence dosimeters. (orig.)

  15. Personal radiation monitoring with thermoluminescent dosemeters

    International Nuclear Information System (INIS)

    The technique of personal dosimetry used by SAPRA (Servico de Assessoria e Protecao Radiologica S/C Ltda., Brazil) is presented. Thermoluminescent monitors and CaSO4: Dy are used in pastilles united by teflon. Characteristics of the dosemeters are briefly reported. The system of thermoluminescent measurement, designed and constructed by SAPRA, and the system of personal monitoring are described. (M.A.C.)

  16. Biological dosimetry-knowing what happened

    International Nuclear Information System (INIS)

    Effective medical management of a suspected radiation overexposure incident necessitates recording dynamic medical data and measuring appropriate radiation bioassays in order to provide diagnostic information to the treating physician and dose assessment for the personnel radiation protection records. Biological Assessment Tool (BAT), a radiation casualty management software application available at the AFRRI's website (www.afrri.usuhs.mil), was developed to facilitate medical recording and to assist in bioassay dose predictions. Prodromal signs and symptoms as well as the body location and degree of transitory radiation-induced erythema should be recorded. Goans and colleagues have recently published dose prediction models for the prodromal symptom, time until onset of vomiting, following photon and criticality accident exposures. A complete blood cell count (CBC) with white cell differential should be obtained immediately after exposure, three times a day for the next 2-3 days, and then twice a day for the following 3- 6 days. Lymphocyte cell counts and lymphocyte depletion kinetics provide a dose assessment prediction between 1 and 10 Gy photon equivalent dose range. A blood sample should also be taken for dose assessment, following coordination with a qualified radiation cytogenetic biodosimetry laboratory, typically 24 hours after exposure using the 'gold standard' lymphocyte-dicentric radiation bioassay. Several of these cytogenetic biodosimetry laboratories use the premature chromosome condensation (PCC) bioassay, which permits dose assessment at higher doses (>5 Gy photon equivalent and acute high-dose rate exposures). Other opportunistic dosimetry approaches should be considered if available. Automated instrumentation to accomplish sample preparation and analysis for the conventional cytogenetic-based bioassays need to be integrated and beta tested in reference cytogenetic biodosimetry laboratories. Complimentary novel interphase-based cytological

  17. Manufacturing and automation

    OpenAIRE

    Ernesto Córdoba Nieto

    2010-01-01

    The article presents concepts and definitions from different sources concerning automation. The work approaches automation by virtue of the author’s experience in manufacturing production; why and how automation prolects are embarked upon is considered. Technological reflection regarding the progressive advances or stages of automation in the production area is stressed. Coriat and Freyssenet’s thoughts about and approaches to the problem of automation and its current state are taken and e...

  18. Irregular glow curves in TL dosimetry

    International Nuclear Information System (INIS)

    The Personal Dosimetry Service Seibersdorf analyses monthly a large number of thermo luminescent dosemeters. In rare cases the luminescent glow curves of the routine analyse do not have the expected form. The typical spurious effects in glow curves are well known and it is possible to find many examples in the related literature. A curve can have an abnormal shape due to UV radiation, electric discharge, external contaminants on or absorbed in the crystal, the light sensitivity of the PTFE components, etc. In this work many of these effects were verified and another (like the effect of mechanic shock, static electricity, humidity,..) were examined. Particularly the influence on the shape of the glow curves was studied. It is necessary to know, if these experimental effects could also take place during the routine evaluation. An algorithm, which permits to identify irregular glow curves through comparison with a standard curve, was developed and applied in routine evaluations. This investigation has shown that in rare cases, in which the dosimeter was not used correctly (opened package, stored with high temperatures, washing machine, etc.), irregular glow curves can appear and a correct dose evaluation is not possible. Current analyse of the glow curves is therefore necessary in order to find such effects and to enforce the necessary corrections. (orig.)

  19. Artificial neural networks in neutron dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Vega C, H.R.; Hernandez D, V.M.; Manzanares A, E.; Mercado, G.A.; Perales M, W.A.; Robles R, J.A. [Unidades Academicas de Estudios Nucleares, UAZ, A.P. 336, 98000 Zacatecas (Mexico); Gallego, E.; Lorente, A. [Depto. de Ingenieria Nuclear, Universidad Politecnica de Madrid, (Spain)

    2005-07-01

    An artificial neural network has been designed to obtain the neutron doses using only the Bonner spheres spectrometer's count rates. Ambient, personal and effective neutron doses were included. 187 neutron spectra were utilized to calculate the Bonner count rates and the neutron doses. The spectra were transformed from lethargy to energy distribution and were re-binned to 31 energy groups using the MCNP 4C code. Re-binned spectra, UTA4 response matrix and fluence-to-dose coefficients were used to calculate the count rates in Bonner spheres spectrometer and the doses. Count rates were used as input and the respective doses were used as output during neural network training. Training and testing was carried out in Mat lab environment. The artificial neural network performance was evaluated using the {chi}{sup 2}- test, where the original and calculated doses were compared. The use of Artificial Neural Networks in neutron dosimetry is an alternative procedure that overcomes the drawbacks associated in this ill-conditioned problem. (Author)

  20. Characterization of a thermoluminiscence personnel dosimetry system

    International Nuclear Information System (INIS)

    Various tests carried out to characterize a Thermoluminiscence Personnel Dosimetry Automatic System, based on the optical heating of a multielement dosemeter are presented. The dosemeter consists of Lithium Borate (Copper) and Calcium Sulphate (Thallium) phosphors. The Dosimetric System shows some outstanding features, such as its simplicity (no aditional annealing procedures are required), its short reading cycle (160 TLD per hour and its data handling capabilities (RS-232C and Parallel Printer digital ports and four analigic outputs for Glow Curve Adquisition). The tests performed have been designed to conform with the different existing international Standards and Recommendations (ANSI: N13.11-1983; IEC:Draft 45B-1987, ISO:DP 8034-1984) The new radiological quantities (I.C.R.U.-19855) have been used for calibration. The results obtained (linearity, repeatibility, detection threshold, residue, stability of stored information, etc) show the optimum performance of this dosimetric system in its aplication to routine personnel dose monitoring. Based on the dosemeter energy discriminating response, an algorithm for dose assesment has been developed. The method allows personal dose calculations within 10% and gives valuable information on the quality and energy of incident radiation, for photons from 30 to 2000 keV and for Beta penetrating radiation (Sr/Y, U). (Author)

  1. Artificial neural networks in neutron dosimetry

    International Nuclear Information System (INIS)

    An artificial neural network (ANN) has been designed to obtain neutron doses using only the count rates of a Bonner spheres spectrometer (BSS). Ambient, personal and effective neutron doses were included. One hundred and eighty-one neutron spectra were utilised to calculate the Bonner count rates and the neutron doses. The spectra were transformed from lethargy to energy distribution and were re-binned to 31 energy groups using the MCNP 4C code. Re-binned spectra, UTA4 response matrix and fluence-to-dose coefficients were used to calculate the count rates in the BSS and the doses. Count rates were used as input and the respective doses were used as output during neural network training. Training and testing were carried out in the MATLABR environment. The impact of uncertainties in BSS count rates upon the dose quantities calculated with the ANN was investigated by modifying by ±5% the BSS count rates used in the training set. The use of ANNs in neutron dosimetry is an alternative procedure that overcomes the drawbacks associated with this ill-conditioned problem. (authors)

  2. Artificial neural networks in neutron dosimetry

    International Nuclear Information System (INIS)

    An artificial neural network has been designed to obtain the neutron doses using only the Bonner spheres spectrometer's count rates. Ambient, personal and effective neutron doses were included. 187 neutron spectra were utilized to calculate the Bonner count rates and the neutron doses. The spectra were transformed from lethargy to energy distribution and were re-binned to 31 energy groups using the MCNP 4C code. Re-binned spectra, UTA4 response matrix and fluence-to-dose coefficients were used to calculate the count rates in Bonner spheres spectrometer and the doses. Count rates were used as input and the respective doses were used as output during neural network training. Training and testing was carried out in Mat lab environment. The artificial neural network performance was evaluated using the χ2- test, where the original and calculated doses were compared. The use of Artificial Neural Networks in neutron dosimetry is an alternative procedure that overcomes the drawbacks associated in this ill-conditioned problem. (Author)

  3. Personal neutron dosemeter of the Czech Republic: Review of basic properties, results of recent tests

    Czech Academy of Sciences Publication Activity Database

    Trousil, J.; Spurný, František; Plichta, J.

    2006-01-01

    Roč. 14, 7/8 (2006), s. 246-253. ISSN 1210-7085 Institutional research plan: CEZ:AV0Z10480505 Keywords : detectors * dosemeters * personal dosimetry Subject RIV: DN - Health Impact of the Environment Quality

  4. Radiation dosimetry with optically stimulated luminescent detectors at the SCK.CEN

    International Nuclear Information System (INIS)

    The Belgian Nuclear Research Centre, SCK.CEN, developed technologies for external dosimetry for more than fifty years. The thermoluminescence dosemeter (TLD) is now in routine application with more than 6000 read-outs every month. In 2002, the Centre also begun R and D investigations in the field of optically stimulated luminescence (OSL) dosimetry for personal, retrospective and space dosimetry. One of the purposes of this research is to extend the capabilities of the laboratory by taking profit of the different advantages of the OSLD's: wider dynamic range, sensitivity and reusability, low fading and ease of use. The Al2O3:C crystal is chosen as first material to study the OSL techniques. Recently developed modular devices for TL and OSL are described with their applications. After a short historical review of the dosimetry service and of the laboratory for external dosimetry, the OSL technique as used at the SCK.CEN will be described in the context of services and the research. (author)

  5. Fundamentals of materials, techniques and instrumentation for OSL and FNTD dosimetry

    Science.gov (United States)

    Akselrod, M. S.

    2013-02-01

    The optically stimulated luminescence (OSL) technique has already become a successful commercial tool in personal radiation dosimetry, medical dosimetry, diagnostic imaging, geological and archeological dating. This review briefly describes the history and fundamental principles of OSL materials, methods and instrumentation. The advantages of OSL technology and instrumentation in comparison with thermoluminescent technique are analyzed. Progress in material and detector engineering has allowed new and promising developments regarding OSL applications in the medical field. Special attention is dedicated to Al2O3:C as a material of choice for many dosimetric applications including fiberoptic OSL/RL sensors with diameters as small as 300 μm. A new RL/OSL fiberoptic system has a high potential for in vivo and in vitro dosimetry in both radiation therapy and diagnostic mammography. Different aspects of instrumentation, data processing algorithms, post-irradiation and real-time measurements are described. The next technological breakthrough was done with Fluorescent Nuclear Track detectors (FNTD) that has some important advantages in measuring fast neutron and high energy heavy charge particles that became the latest tool in radiation therapy. New Mg-doped aluminum oxide crystals and novel type of imaging instrumentation for FNTD technology were engineered and successfully demonstrated for occupational and accident dosimetry, for medical dosimetry and radiobiological research.

  6. Automation of a fixed-bed continuous–flow reactor

    OpenAIRE

    Alcántara, R.; Canoira, L.; R. Conde; Fernández-Sánchez, J. M.; Navarro, A.

    1994-01-01

    This paper describes the design and operation of a laboratory plant with a fixed-bed continuous-flow reactor, fully automated and controlled from a personal computer. The automated variables include two gas flows, one liquid flow, six temperatures, two pressures, one circulation of a cooling liquid, and 10 electrovalves. An adaptive-predictive control system was used. The chemical process chosen to run the automated reactor was the conversion of methanol to gasoline over a ZSM-5 catalyst. Thi...

  7. Dosimetry in Nuclear Medicine Diagnosis and Therapy

    Science.gov (United States)

    Noßke, D.; Mattsson, S.; Johansson, L.

    This document is part of Subvolume A 'Fundamentals and Data in Radiobiology, Radiation Biophysics, Dosimetry and Medical Radiological Protection' of Volume 7 'Medical Radiological Physics' of Landolt-Börnstein - Group VIII 'Advanced Materials and Technologies'. It contains the Section '4.7 Necessity of Patient-Specific Dose Planning in Radionuclide Therapy' of the Chapter '4 Dosimetry in Nuclear Medicine Diagnosis and Therapy'.

  8. Dosimetry of Low-Energy Beta Radiation

    DEFF Research Database (Denmark)

    Borg, Jette

    Useful techniques and procedures for derermination of absorbed doses from exposure in a low-energy beta radiation were studied and evaluated. The four techniques included were beta spectrometry, extrapolation chamber dosimetry, Monte Carlo (MC) calculations, and exoelectron dosimetry. As a typical...

  9. Patient dosimetry and protection in diagnostic radiology

    International Nuclear Information System (INIS)

    The paper discussed the following subjects: x-ray in medicine as they represent by far the largest man-made sources of population exposure to ionizing radiation, methods of patient dosimetry, entrance surface dose per radiograph, dose-area product per examination, dosimetry for assessing risk, potential of dose reduction

  10. Good Practice of Clinical Dosimetry Reporting

    International Nuclear Information System (INIS)

    The intention of the guidance of this paper, Good Practice of Clinical Dosimetry Reporting, by the Dosimetry Committee of the European Association for Nuclear Medicine, is to guide the reader through a series of suggestions for reporting dosimetric approaches in nuclear medicine. (author)

  11. High dose dosimetry for radiation processing

    International Nuclear Information System (INIS)

    Radiation processing today offers various advantages in the field of sterilization of medical and pharmaceutical products, food preservation, treatment of chemical materials and a variety of other products widely used in modern society, all of which are of direct relevance to health and welfare. The safety and economic importance of radiation processing is clearly recognized. It is understood that reliable dosimetry is a key parameter for quality assurance of radiation processing and irradiated products. Furthermore, the standardization of dosimetry can provide a justification for the regulatory approval of irradiated products and form the basis of international clearance for free trade. After the initiation of the Agency's high dose standardization programme (1977), the first IAEA Symposium on High Dose Dosimetry was organized in 1984. As a result, concern as to the necessity of reliable dosimetry has greatly escalated not only in the scientific community but also in the radiation processing industry. The second International Symposium on High Dose Dosimetry for Radiation Processing was held in Vienna from 5 to 9 November, 1990, with a view to providing an international forum for the exchange of technical information on up to date developments in this particular field. The scientific programme held promises for an authoritative account of the status of high dose dosimetry throughout the world in 1990. Forty-one papers presented at the meeting discussed the development of new techniques, the improvement of reference and routine dosimetry systems, and the quality control and assurance of dosimetry. Refs, figs and tabs

  12. Basics of the ionizing radiation dosimetry

    International Nuclear Information System (INIS)

    The dosimetry basic physics issues, ionizing irradiation interaction with the substance and the radiation parameter regulation principles were considered. The special attention was paid to the methods of the ionizing radiation measurement. The edition is the manual on the dosimetry principles and is intended, first of all, for the university students of the technical and engineering specialties

  13. Recent developments in personal monitoring

    International Nuclear Information System (INIS)

    Introduction: Throughout the years there have been new developments in the field of personal radiation dose monitoring, from film dosimetry, to Thermoluminescence and Optically Stimulated Luminescence, Electronic Personal Dosimeters, and Radiophotoluminescent Dosimeters, to the present day Direct Ion Storage. This paper will discuss the progression of personal dosimetry from the film age up to the digital age with the new Instadose Direct Ion Storage personal dosimeter. Dosimeter Theory: A comparison of the different dosimeter theories including methods for analyzing and reporting doses. Test Data Review: A comparison of the various dosimeter types will be discussed including recent data from film, TLD, and DIS as well as published data from OSL and RPL. Tests include: Energy response tests; Angularity response tests; Response at various temperatures; Drop Tests; Computer USB Power tests (DIS only); Low Dose Tests; Pulsed radiation tests; Dose Rate Tests; Dose Linearity. This paper will discuss the results of each of these tests. Operational Experiences with the new DIS Instadose dosimeter: Since InstadoseTM utilizes a unique form for receiving personal radiation exposure by having the individual wearer perform the reading, there have been some operational experiences that were learned over the last couple years of implementation. Some of these include: How to ensure wearers read their dosimeter; PC related issues (i.e. firewalls, proxy servers, USB ports), Temperature effects on the InstadoseTM dosimeter Details of each will be highlighted and discussed.

  14. Report on external occupational dosimetry in Canada

    International Nuclear Information System (INIS)

    In light of the new recommendations of the ICRP in Report 60 on dose quantities and dose limits, this working group was set up to examine the implications for external dosimetry in Canada. The operational quantities proposed by the ICRU are discussed in detail with regard to their applicability in Canada. The current occupational dosimetry services available in Canada are described as well as the several performance intercomparisons that have been carried out within the country as well as internationally. Recommendations are given with respect to standards for dosimetry, including accuracy and precision. More practical advice is given on the choice of dosimeter to use for external dosimetry, frequency of monitoring, and who should be monitored. Specific advice is given on the monitoring of pregnant workers and problem of non-uniform irradiation. Accident and emergency dosimetry are dealt with briefly. Suggestions are given regarding record keeping both for employers and for the national dose registry. 48 refs., 6 tabs., 1 fig

  15. The principles of radioiodine dosimetry following a nuclear accident

    International Nuclear Information System (INIS)

    Based upon the experience of radioiodine dosimetry after the Chernobyl accident main principals of radioiodine measurements and dosimetry in thyroid glands of population in case of a radiation accident are discussed in the report. For the correct dose estimation following the radioiodine measurement in the thyroid one should know the ''history'' of radionuclide intake into the body of a contaminated person. So a measurement of radioiodine thyroid content should be accompanied by asking questions of investigated persons about, their life style and feeding after a nuclear incident. These data coincidently with data of radionuclides dynamic in the air and food (especially in milk products) are used for the development of radioiodine intake model and then for thyroid dose estimation. The influence of stable iodine prophylaxis and other countermeasures on values are discussed in dependence on the time of its using. Some methods of thyroid dose reconstruction used after the Chernobyl accident in Russia for a situation of thyroid radioiodine measurements lacking in a contaminated settlement are presented in the report. (author). 16 refs, 5 figs, 3 tabs

  16. Proceedings of the international workshop 'Actual problems of dosimetry'

    International Nuclear Information System (INIS)

    Materials grouped to six main issues: dosimetry and radiometry equipment, dosimetry of the medical irradiation, standard and metrology support of dosimetric and radiometric control, biological dosimetry and markers of radiation effects, monitoring and reconstruction of radiation doses at radiation accidents and dosimetry of unionizing radiations

  17. ESR dosimetry using eggshells and tooth enamel for accidental dosimetry

    International Nuclear Information System (INIS)

    The CO2- signal of eggshells showed a good dose linearity and was appropriate in the wide dose range from 1 to 10 kGy, while ESR signal of CO2- in sea and fresh water shells were saturated at a dose od below 10 kGy. The minimum detectable dose and G-value of CO2- in eggshells were estimated 0.3 Gy and 0.28, respectively. The lifetime of CO2- in eggshells could not be determined exactly because of overlapping organic signals, however it is still sufficiently long for practical use as ESR dosimeter materials. Various bird's or reptile's eggshells would be available as natural retrospective ESR dosimeter materials after nuclear accidents. Eggshells will be useful for the food irradiation dosimetry in the dose range of about a few kGy. Tooth enamel is one of the most useful dosimeter materials in public at a accident because of its high sensitivity. ESR dosimetry will replace TLD in near future if the cost of an ESR reader is further reduced . (author)

  18. Radiation dosimetry and standards at the austrian dosimetry laboratory

    International Nuclear Information System (INIS)

    The Austrian Dosimetry Laboratory, established and operated in cooperation between the Austrian Research Center Seibersdorf and the Federal Office of Metrology and Surveying (Bundesamt and Eich- und Vermessungswesen) maintains the national primary standards for radiation dosimetry. Furthermore its tasks include routine calibration of dosemeters and dosimetric research. The irradiation facilities of the laboratory comprise three X-ray machines covering the voltage range from 5 kV to 420 kV constant potential, a 60Co teletherapy unit, a circular exposure system for routine batch calibration of personnel dosemeters with four gamma ray sources (60Co and 137Cs) and a reference source system with six gamma ray sources (60Co and 137Cs). In addition a set of calibrated beta ray sources are provided (147Pm, 204Tl and 90Sr). The dosimetric equipment consists of three free-air parallelplate ionization chambers serving as primary standards of exposure for the X-ray energy region, graphite cavity chambers with measured volume as primary standards for the gamma radiation of 137Cs and 60Co as well as different secondary standard ionization chambers covering the dose rate range from the natural background level up to the level of modern therapy accelerators. In addition for high energy photon and electron radiation a graphite calorimeter is provided as primary standard of absorbed dose. The principle experimental set-ups for the practical use of the standards are presented and the procedures for the calibration of the different types of dosemeters are described. (Author)

  19. Gamma dosimetry of high doses

    International Nuclear Information System (INIS)

    The gamma dosimetry of high doses is problematic in almost all the classic dosemeters either based on the thermoluminescence, electric, chemical properties, etc., because they are saturated to very high dose and they are no longer useful. This work carries out an investigation in the interval of high doses. The solid system of heptahydrate ferrous sulfate, can be used as solid dosemeter of routine for high doses of radiation. The proposed method is simple, cheap and it doesn't require sophisticated spectrophotometers or spectrometers but expensive and not common in some laboratories

  20. Air Force neutron dosimetry program

    International Nuclear Information System (INIS)

    Approximately 1000 Air Force personnel are monitored for neutron radiation resulting from various sources at more than thirty worldwide locations. Neutron radiation spanning several orders of magnitude in energy is encountered. The Air Force currently uses albedo thermoluminescent neutron dosimeters for personnel monitoring. The energy dependence of the albedo neutron dosimeter is a current problem and the development of site specific correction factors is ongoing. A summary of data on the energy dependence is presented as well as efforts to develop algorithms for the dosimeter. An overview of current Air Force neutron dosimetry users and needs is also presented