Neutron personnel dosimetry considerations for fusion reactors

International Nuclear Information System (INIS)

Barton, T.P.; Easterly, C.E.

1979-07-01

The increasing development of fusion reactor technology warrants an evaluation of personnel neutron dosimetry systems to aid in the concurrent development of a radiation protection program. For this reason, current state of knowledge neutron dosimeters have been reviewed with emphasis placed on practical utilization and the problems inherent in each type of dosimetry system. Evaluations of salient parameters such as energy response, latent image instability, and minimum detectable dose equivalent are presented for nuclear emulsion films, track etch techniques, albedo and other thermoluminescent dosimetry techniques, electrical conductivity damage effects, lyoluminescence, thermocurrent, and thermally stimulated exoelectron emission. Brief summaries of dosimetry regulatory requirements and intercomparison study results help to establish compliance and recent trends, respectively. Spectrum modeling data generated by the Neutron Physics Division of Oak Ridge National Laboratory for the Princeton Tokamak Fusion Test Reactor (TFTR) Facility have been analyzed by both International Commission on Radiological Protection fluence to dose conversion factors and an adjoint technique of radiation dosimetry, in an attempt to determine the applicability of current neutron dosimetry systems to deuterium and tritium fusion reactor leakage spectra. Based on the modeling data, a wide range of neutron energies will probably be present in the leakage spectra of the TFTR facility, and no appreciable risk of somatic injury to occupationally exposed workers is expected. The relative dose contributions due to high energy and thermal neutrons indicate that neutron dosimetry will probably not be a serious limitation in the development of fusion power

US Department of Energy Laboratory Accreditation Program for personnel dosimetry systems (DOELAP)

International Nuclear Information System (INIS)

Carlson, R.D.; Gesell, T.F.; Kalbeitzer, F.L.; Roberson, P.L.; Jones, K.L.; MacDonald, J.C.; Vallario, E.J.; Pacific Northwest Lab., Richland, WA; USDOE Assistant Secretary for Nuclear Energy, Washington, DC

1988-01-01

The US Department of Energy (DOE) Office of Nuclear Safety has developed and initiated the DOE Laboratory Accreditation Program (DOELAP) for personnel dosimetry systems to assure and improve the quality of personnel dosimetry at DOE and DOE contractor facilities. It consists of a performance evaluation program that measures current performance and an applied research program that evaluates and recommends additional or improved test and performance criteria. It also provides guidance to DOE, identifying areas where technological improvements are needed. The two performance evaluation elements in the accreditation process are performance testing and onsite assessment by technical experts. Performance testing evaluates the participant's ability to accurately and reproducibly measure dose equivalent. Tests are conducted in accident level categories for low- and high-energy photons as well as protection level categories for low- and high-energy photons, beta particles, neutrons and mixtures of these

Quality assurance manual for the Department of Energy laboratory accreditation program for personnel dosimetry systems

International Nuclear Information System (INIS)

1987-02-01

The overall purpose of this document is to establish a uniform approach to quality assurance. This will ensure that uniform, high-quality personnel dosimetry practices are followed by the participating testing laboratories. The document presents guidelines for calibrating and maintaining measurement and test equipment (M and TE), calibrating radiation fields, and subsequently irradiating and handling personnel dosimeters in laboratories involved in the DOE dosimetry systems testing program. Radiation energies for which the test procedures apply are photons with approximately 15 keV to 2 MeV, beta particles above 0.3 MeV, neutrons with approximately 1 keV to 2 MeV. 12 refs., 4 tabs

Personnel neutron dosimetry using electrochemically etched CR-39 foils

International Nuclear Information System (INIS)

Hankins, D.E.; Homann, S.; Westermark, J.

1986-01-01

A personnel neutron dosimetry system has been developed based on the electrochemical etching of CR-39 plastic at elevated temperatures. The doses obtained using this dosimeter system are more accurate than those obtained using other dosimetry systems, especially when varied neutron spectra are encountered. This Cr-39 dosimetry system does not have the severe energy dependence that exists with albedo neutron dosimeters or the fading and reading problems encountered with NTA film. The dosimetry system employs an electrochemical etch procedure that be used to process large numbers of Cr-39 dosimeters. The etch procedure is suitable for operations where the number of personnel requires that many CR-39 dosimeters be processed. Experience shows that one full-time technician can etch and evaluate 2000 foils per month. The energy response to neutrons is fairly flat from about 80 keV to 3.5 MeV, but drops by about a factor of three in the 13 to 16 MeV range. The sensitivity of the dosimetry system is about 7 tracks/cm 2 /mrem, with a background equivalent to about 8 mrem for new CR-39 foils. The limit of sensitivity is approximately 10 mrem. The dosimeter has a significant variation in directional dependence, dropping to about 20% at 90 0 . This dosimeter has been used for personnel neutron dosimetry at the Lawrence Livermore National Laboratory for more tha 18 months. 6 refs., 23 figs., 2 tabs

The Seibersdorf TL Personnel Dosimetry Service

Energy Technology Data Exchange (ETDEWEB)

Duftschmid, K E [Oesterreichisches Forschungszentrum Seibersdorf GmbH (Austria)

1994-11-01

Since 1976 the Department for Radiation Protection of the Austrian Research Centre Seibersdorf has been operating a TLD Personnel Monitoring Service, which presently covers about 18,000 radiation workers in Austria, with monthly monitoring periods. We have been the first accredited monitoring service in Europe, which fully converted from film dosimetry to TLD. From the beginning up to 1991 the service was based on three automated TLD systems Model 2271 from HARSHAW, USA. After extensive testing and comparisons, since almost four years now, the monitoring service has been operating on two HARSHAW 8800 systems, which are described in more detail below. (author).

The Seibersdorf TL Personnel Dosimetry Service

International Nuclear Information System (INIS)

Duftschmid, K.E.

1994-11-01

Since 1976 the Department for Radiation Protection of the Austrian Research Centre Seibersdorf has been operating a TLD Personnel Monitoring Service, which presently covers about 18,000 radiation workers in Austria, with monthly monitoring periods. We have been the first accredited monitoring service in Europe, which fully converted from film dosimetry to TLD. From the beginning up to 1991 the service was based on three automated TLD systems Model 2271 from HARSHAW, USA. After extensive testing and comparisons, since almost four years now, the monitoring service has been operating on two HARSHAW 8800 systems, which are described in more detail below. (author)

TLD personnel dosimetry and its relationship with the radiodiagnostic training

International Nuclear Information System (INIS)

Gaona, E.; Franco E, J.G.; Gaona C, E.

2002-01-01

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

The Martin Marietta Energy Systems personnel neutron dosimetry program

International Nuclear Information System (INIS)

McMahan, K.L.

1991-01-01

Martin Marietta Energy Systems, Inc. (Energy Systems), manages five sites for the US Department of Energy. Personnel dosimetry for four of the five sites is coordinated through a Centralized External Dosimetry System (CEDS). These four sites are the Oak Ridge National Laboratory (ORNL), the Oak Ridge Y-12 Plant (Y-12), the Oak Ridge K-25 Site (K-25), and the Paducah Gaseous Diffusion Plant (PGDP). The fifth Energy Systems site, Portsmouth Gaseous Diffusion Plant, has an independent personnel dosimetry program. The current CEDS personnel neutron dosimeter was first issued in January 1989, after an evaluation and characterization of the dosimeters' response in the workplaces was performed. For the workplace characterization, Energy Systems contracted with Pacific Northwest Laboratory (PNL) to perform neutron measurements at selected locations at ORNL and Y-12. K-25 and PGDP were not included because their neutron radiation fields were similar to others already planned for characterization at ORNL and Y-12. Since the initial characterization, PNL has returned to Oak Ridge twice to perform follow up measurements, and another visit is planned in the near future

Review of the current deficiencies in personnel beta dosimetry, with recommendations

International Nuclear Information System (INIS)

Sherbini, S.; Porter, S.W.

1983-06-01

The report describes the design and use of personnel dosimeters used by the nuclear power industry to monitor occupational radiation exposure. It then shows why the monitoring method is inaccurate when personnel are exposed to beta particles. Then the report describes alternatives that would lead to improved measurements. The report also critiques the dosimetry processor testing criteria developed by the Health Physics Society Standards Committee. Survey instruments are shown often to be inaccurate when used to measure beta dose rates

Personnel Dosimetry for Radiation Accidents. Proceedings of a Symposium on Personnel Dosimetry for Accidental High-Level Exposure to External and Internal Radiation

International Nuclear Information System (INIS)

1965-01-01

Accidents involving the exposure of persons to high levels of radiation have been few in number and meticulous precautions are taken in an effort to maintain this good record. When, however, such an accident does occur, a timely estimate of the dose received can be of considerable help to the physician in deciding whether a particular person requires medical treatment, and in selecting the most appropriate treatment. Individual dosimetry provides the physical basis for relating the observed effects to those in other accident cases, to other human data, and to data from animal experiments, thus providing an important aid to rational treatment and to the accumulation of a meaningful body of knowledge on the subject. It is most important therefore that, where there is a possibility of receiving high-level exposure, methods of personnel dosimetry should be available that would provide the dosimetric information most useful to the physician. Provision of good personnel dosimetry for accidental high-level exposure is in many cases an essential part of emergency planning because the information provided may influence emergency and rescue operations, and can lead to improved accident preparedness. Accordingly, the International Atomic Energy Agency and the World Health Organization jointly organized the Symposium on Personnel Dosimetry for Accidental High-Level Exposure to External and Internal Radiation for the discussion of such methods and for a critical review of the procedures adopted in some of the radiation accidents that have already occurred. The meeting was attended by 179 participants from 34 countries and from five other international organizations. The papers presented and the ensuing discussions are published in these Proceedings. It is hoped that the Proceedings will be of help to those concerned with the organization and development of wide-range personnel monitoring systems, and with the interpretation of the results provided

Personnel radiation dosimetry symposium: program and abstracts

Energy Technology Data Exchange (ETDEWEB)

1984-10-01

The purpose was to provide applied and research dosimetrists with sufficient information to evaluate the status and direction of their programs relative to the latest guidelines and techniques. A technical program was presented concerning experience, requirements, and advances in gamma, beta, and neutron personnel dosimetry.

Personnel radiation dosimetry symposium: program and abstracts

International Nuclear Information System (INIS)

1984-10-01

The purpose was to provide applied and research dosimetrists with sufficient information to evaluate the status and direction of their programs relative to the latest guidelines and techniques. A technical program was presented concerning experience, requirements, and advances in gamma, beta, and neutron personnel dosimetry

Internal dosimetry for occupationally exposed personnel in nuclear medicine

International Nuclear Information System (INIS)

Garcia, M.T.; Alfaro, L.M.M.; Angeles, C.A.

2013-01-01

Internal dosimetry plays an important role in nuclear medicine dosimetry control of personnel occupationally exposed, and that in recent years there has been a large increase in the use of radionuclides both in medical diagnosis as radiotherapy. But currently, in Mexico and in many parts of the world, this internal dosimetry control is not performed. The Instituto Nacional de lnvestigaciones Nucleares de Mexico (ININ) together with the Centro Oncologico de Toluca (ISEMMYM) have developed a simple and feasible methodology for monitoring of personnel working in these facilities. It was aimed to carry out the dosimetry of the personnel, due to the incorporation of I-131, using the spectrometric devices that the hospital has, a gamma camera. The first step in this methodology was to make a thyroid phantom to meet the specifications of the ninth ANSI. This phantom is compared under controlled conditions with RMC- II phantom used for system calibration of the ININ internal dosimetry (ACCUSCAN - Ll), and with another phantom developed in Brazil with ANSI specifications, in order to determine the variations in measurements due to the density of the material of each of the phantoms and adjust to the system ACCUSCAN, already certificate. Furthermore, necessary counts were performed with the gamma camera of the phantom developed at ININ, with a standard source of 133 Ba which simulates the energy of 131 I. With these data, were determined the counting efficiencies for a distance of 15 to 20 cm between the surface of the phantom and the the plate of the detectors. Another important aspect was to determine the lower limit of detection (LLD). In this paper we present the results obtained from the detectors calibration of the gamma camera of the hospital.

Multisphere system neutron spectrometry applied to dosimetry for the personnel

International Nuclear Information System (INIS)

Allinei, P.G.

1992-01-01

Neutron dosimetry is a necessity that must be dealt with in order to ensure efficient monitoring of all personnel regarding radiology safety. Dosimetric variables are difficult to measure for they are dependent on complex functions evolving with the energy of neutrons, which forces us to determine their energetic distribution. We have chosen to use the multisphere system associated to an unfolding code in order to perform neutron spectrometry, our purpose being to determine these dosimetric variables. The initial stage consists in modifying a research code, the code SOHO, in order to adapt it to our needs. The resulting new version was subsequently tested and proven successful by means of computerized simulations. Afterwards, we used reference dosimetric and spectral beams to confirm the position results previously obtained. At the time of this test, the code SOHO yielded results coherent with the theoretical values, and even allowed the quantity of radiation diffused by the laboratory structures to be estimated. The final part of this study consists in applying the previously perfected technique to authentic situations. The results thus obtained are compared to those obtained by conventional methods in order to reveal the interest of neutron spectrometry used for dosimetry of the personnel

The US Department of Energy Personnel Dosimetry Evaluation and Upgrade Program

International Nuclear Information System (INIS)

Faust, L.G.; Stroud, C.M.; Swinth, K.L.; Vallario, E.J.

1987-11-01

The US Department of Energy (DOE) Personnel Dosimetry Evaluation and Upgrade Program is designed to identify and evaluate dosimetry deficiencies and to conduct innovative research and development programs that will improve overall capabilities, thus ensuring that DOE can comply with applicable standards and regulations for dose measurement. To achieve these goals, two programs were initiated to evaluate and upgrade beta measurement and neutron dosimetry. 3 refs

The U.S. Department of Energy Laboratory Accreditation Program for testing the performance of extremity dosimetry systems: a summary of the program status

International Nuclear Information System (INIS)

Cummings, F.M.; Carlson, R.D.; Gesell, T.F.; Loesch, R.M.

1992-01-01

In 1986, The U.S. Department of Energy (DOE) implemented a program to test the performance of its personnel whole-body dosimetry systems. This program was the DOE Laboratory Accreditation Program (DOELAP). The program parallels the performance testing program specified in the American National Standard for Dosimetry - Personnel Dosimetry Performance -Criteria for Testing (ANSI N13.11-1983), but also addresses the additional dosimetry needs of DOE facilities. As an extension of the whole-body performance testing program, the DOE is now developing a program to test the performance of personnel extremity dosimetry systems. The draft DOE standard for testing extremity dosimetry systems is much less complex than the whole-body dosimetry standard and reflects the limitations imposed on extremity dosimetry by dosimeter design and irradiation geometry. A pilot performance test session has been conducted to evaluate the proposed performance-testing standard. (author)

Background dose subtraction in personnel dosimetry

International Nuclear Information System (INIS)

Picazo, T.; Llorca, N.; Alabau, J.

1997-01-01

In this paper it is proposed to consider the mode of the frequency distribution of the low dose dosemeters from each clinic that uses X rays as the background environmental dose that should be subtracted from the personnel dosimetry to evaluate the doses due to practice. The problems and advantages of this indirect method to estimate the environmental background dose are discussed. The results for 60 towns are presented. (author)

Personnel dosimetry methods introduced in the Czechoslovak national laboratories

International Nuclear Information System (INIS)

Trousil, J.; Singer, J.; Kokta, L.; Prouza, Z.

1979-01-01

Personnel dosimetry methods are described that were developed in the Institute for Research, Production and Application of Radioisotopes and that have been or will be introduced in the national personnel dosimetry service. In Czechoslovakia, workers exposed to a radiation risk are divided into two groups, according to the level of the risk. The criterion is the possibility of exceeding one tenth of the MPD. For the higher risk group, a complex dose meter is usually used for dosimetry of photon and beta radiation; it contains a film dose meter and a radiothermoluminescent (RTL) glass dose meter. The RTL glass dose meter also serves as an accident dose meter. For neutron dosimetry, a dose meter comprising a solid-state track detector in combination with fissionable foils has been introduced. For accident dosimetry, a silicon diode of Czechoslovak production is used. For the lower risk group, only the introduction of an RTL dose meter is foreseen. There will be a three month control period; for neutron dosimetry, the track detector in combination with fissionable foils is retained. For measurements of hand doses, a themoluminescent ring dose meter has been introduced. The dose meters are described, giving information on the types of detectors employed, measurement techniques and descriptions of the basic characteristics of the instruments, their basic dosimetric parameters and the dose and energy ranges which can be measured. The results of international comparisons are presented; these have served to confirm the measurement precision. In conclusion, some questions of dose-meter calibration are summarized, and the problems of dose measurement in mixed fields of neutrons and gamma rays are discussed. (author)

The personnel dosimetry record keeping system at AEE Winfrith

International Nuclear Information System (INIS)

Gill, D.W.

1979-09-01

Since May 1978 the exposure of personnel to external radiation has been assessed by Thermoluminescent Dosimetry, (TLD). The dosemeter consists of a TLD card similar to that used by the National Radiological Protection Board, held in a plastic badge designed at AEE Winfrith, and used in conjunction with a D A Pitman Ltd Type 605 Automatic Reader. The report describes the dosemeter, the operation of the dosimetry service and the system for maintaining a computerised record keeping system. (author)

Characterization of a thermoluminiscence personnel dosimetry system

International Nuclear Information System (INIS)

Vazquez Lopez, C.; Saez, J.C.; Labarta, T.

1989-01-01

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)

Performance comparisons of selected personnel-dosimetry systems in use at Department of Energy facilities

International Nuclear Information System (INIS)

Roberson, P.L; Holbrook, K.L.; Yoder, R.C.; Fox, R.A.; Hadley, R.T.; Hogan, B.T.; Hooker, C.D.

1983-10-01

Dosimeter performance data were collected to help develop a uniform approach to the calibration and use of personnel dosimetry systems for Department of Energy (DOE) laboratories. Eleven DOE laboratories participated in six months of testing using the American National Draft Standard, Criteria for Testing Personnel Dosimetry Performance, ANSI N13.11, and additional testing categories. The tests described in ANSI N13.11 used a pass/fail system to determine compliance with the draft standard. Recalculation to PNL irradiations showed that the 137 Cs, 90 Sr/ 90 Y, and 252 Cf categories can be recalibrated to have acceptable performance for nearly all participant systems. Deficient dosimeter design or handling techniques caused poor performance in the x-ray category for nearly half of the participants. Too little filtration for the deep-dose element caused poor performance in the beta/photon mixture category for one participant. Two participants had excessively high standard deviations in the neutron category due to dosimeter design or handling deficiencies. The participating dosimetry systems were separated into three categories on their dose evaluation procedure for low-energy photons. These were film dosimeters, fixed-calibration thermoluminescent (TL) dosimeters, and variable-calibration TL dosimeters. The performance of the variable-calibration design was best while the film dosimeters performed considerably worse than either TL dosimeter design. Beta energy dependence studies confirmed a strong correlation between sensitive element thickness, shallow element filtration and low-energy beta response. Studies of neutron calibration conditions for each participant suggested a relationship between response and calibration facility design

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

International Nuclear Information System (INIS)

Trousil, J.; Zelenka, Z.; Kvasnicka, O.

2008-01-01

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)

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...

Interim status report of the TMI personnel-dosimetry project

International Nuclear Information System (INIS)

Rich, B.L.; Alvarez, J.L.; Adams, S.R.

1981-06-01

The current 2-chip TLD personnel dosimeter in use at Three Mile Island (TMI) has been shown inadequate for the anticipated high beta/gamma fields during TMI recovery operations in some areas. This project surveyed the available dosimeter systems, set up an Idaho National Engineering Laboratory (INEL) prototype system, and compared this system with those commercial systems that could be made immediately available for comparison. Of the systems tested, the new INEL personnel dosimeter was found to produce the most accurate results for use in recovery operations at TMI-2. The other multiple-chip or multiple-filter systems were found less desirable at present. The most prominent deficiencies in the INEL dosimeter stem from the fact that it lacks a completely automated reader and its x-ray and thermal neutron responses require additional development. A automated prototype reader system may be in operation by the end of CY-1981. Three alternatives for operational dosimetry are discussed. A combination of a modified version of the presently used Harshaw 2-chip dosimeter and the INEL dosimeter is recommended

Eleventh DOE workshop on personnel neutron dosimetry

International Nuclear Information System (INIS)

1991-01-01

Since its formation, the Office of Health (EH-40) has stressed the importance of the exchange of information related to and improvements in neutron dosimetry. This Workshop was the eleventh in the series sponsored by the Department of Energy (DOE). It provided a forum for operational personnel at DOE facilities to discuss current issues related to neutron dosimetry and for leading investigators in the field to discuss promising approaches for future research. A total of 26 papers were presented including the keynote address by Dr. Warren K. Sinclair, who spoke on, ''The 1990 Recommendations of the ICRP and their Biological Background.'' The first several papers discussed difficulties in measuring neutrons of different energies and ways of compensating or deriving correction factors at individual facilities. Presentations were also given by the US Navy and Air Force. Current research in neutron dosimeter development was the subject of the largest number of papers. These included a number on the development of neutron spectrometers

Implications of ISO 9000 for personnel dosimetry

International Nuclear Information System (INIS)

Yoder, R.C.

1995-01-01

Landauer, Inc. has gained approval to provide personnel dosimetry services in several countries. Each experiene reflects the different concerns adopted by national approval agencies. None have adopted ISO 9000 registration as evidence of a suitable quality system of management. Instead, each organization has prepared its own set of requirements with no provisions for recognizing the results of performance tests or audits conducted by other approval organizations. As ISO 9000 has become a communication symbol for commercial organizations dealing with each other, it has not been similarly viewed by radiation regulation bodies. A key reason arises from a tradition to regulate bodies. A key reason arises from a tradition to regulate, not promote, international trade, not encourage innovation, nor foster economic competition. A second reason is the inability to separate the technical requirements from quality assurance. ISO 9000 may become useful once the national technical organizations learn to trust those of other countries

Retrospective assessment of personnel neutron dosimetry for workers at the Hanford Site

International Nuclear Information System (INIS)

Fix, J.J.; Wilson, R.H.; Baumgartner, W.B.

1996-09-01

This report was prepared to examine the specific issue of the potential for unrecorded neutron dose for Hanford workers, particularly in comparison with the recorded whole body (neutron plus photon) dose. During the past several years, historical personnel dosimetry practices at Hanford have been documented in several technical reports. This documentation provides a detailed history of the technology, radiation fields, and administrative practices used to measure and record dose for Hanford workers. Importantly, documentation has been prepared by personnel whose collective experience spans nearly the entire history of Hanford operations beginning in the mid-1940s. Evaluations of selected Hanford radiation dose records have been conducted along with statistical profiles of the recorded dose data. The history of Hanford personnel dosimetry is complex, spanning substantial evolution in radiation protection technology, concepts, and standards. Epidemiologic assessments of Hanford worker mortality and radiation dose data were initiated in the early 1960s. In recent years, Hanford data have been included in combined analyses of worker cohorts from several Department of Energy (DOE) sites and from several countries through the International Agency for Research on Cancer (IARC). Hanford data have also been included in the DOE Comprehensive Epidemiologic Data Resource (CEDR). In the analysis of Hanford, and other site data, the question of comparability of recorded dose through time and across the respective sites has arisen. DOE formed a dosimetry working group composed of dosimetrists and epidemiologists to evaluate data and documentation requirements of CEDR. This working group included in its recommendations the high priority for documentation of site-specific radiation dosimetry practices used to measure and record worker dose by the respective DOE sites

Neutron personnel dosimetry

International Nuclear Information System (INIS)

Griffith, R.V.

1982-01-01

The measurement of neutron exposures to personnel is an issue that has received increased attention in the last few years. It is important to consider key aspects of the whole dosimetry system when developing dose estimates. This begins with selection of proper dosimeters and survey instruments, and extends through the calibration methods. One must match the spectral response and sensitivity of the dosimeter to the spectral characteristics of the neutron fields. Threshold detectors that are insensitive to large fractions of neutrons in the lower energy portion of reactor spectra should be avoided. Use of two or more detectors with responses that complement each other will improve measurement quality. It is important to understand the spectral response of survey instruments, so that spectra which result in significant overresponse do not lead to overestimation of dose. Calibration sources that do not match operational field spectra can contribute to highly erroneous results. In those situations, in-field calibration techniques should be employed. Although some detection developments have been made in recent years, a lot can be done with existing technology until fully satisfactory, long term solutions are obtained

Personnel-dosimetry intercomparison studies at the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Swaja, R.E.; Sims, C.S.

1982-01-01

Since 1974, seven annual personnel dosimetry intercomparison studies have been conducted at the Oak Ridge National Laboratory using the Health Physics Reactor. These studies have produced more than 2000 measurements by 72 participating organizations of neutron and gamma dose equivalents between 0.1 to 15.0 mSv in six mixed radiation fields. The relative performance of three basic types of personnel neutron dosimeters (nuclear emulsion film, thermoluminescent, and track-etch) and two basic types of gamma dosimeters (film and thermoluminescent) was assessed based on experimental results obtained during the seven intercomparisons

Report on the Personnel Dosimetry at AB Atomenergi during 1962

Energy Technology Data Exchange (ETDEWEB)

Edvardsson, K A; Hagsgaard, S

1964-07-15

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.

Performance testing of UK personal dosimetry laboratories

International Nuclear Information System (INIS)

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 are also estimated. (author)

Pilot test of ANSI draft standard N13.29 environmental dosimetry -- Performance criteria for testing

International Nuclear Information System (INIS)

Klemic, G.; Shebell, P.; Monetti, M.; Raccah, F.; Sengupta, S.

1998-09-01

American National Standards Institute Draft N13.29 describes performance tests for environmental radiation dosimetry providers. If approved it would be the first step toward applying the types of performance testing now required in personnel dosimetry to environmental radiation monitoring. The objective of this study was to pilot test the draft standard, before it undergoes final balloting, on a small group of dosimetry providers that were selected to provide a mix of facility types, thermoluminescent dosimeter designs and monitoring program applications. The first phase of the pilot test involved exposing dosimeters to laboratory photon, beta, and x-ray sources at routine and accident dose levels. In the second phase, dosimeters were subjected to ninety days of simulated environmental conditions in an environmental chamber that cycled through extremes of temperature and humidity. Two out of seven participants passed all categories of the laboratory testing phase, and all seven passed the environmental test phase. While some relatively minor deficiencies were uncovered in the course of the pilot test, the results show that draft N13.29 describes useful tests that could be appropriate for environmental dosimetry providers. An appendix to this report contains recommendations that should be addressed by the N13.29 working group before draft N13.29 is submitted for balloting

Personnel radiation monitoring by thermoluminescence dosimetry (1995-96)

International Nuclear Information System (INIS)

Daw Mi Cho Cho; Daw Yi Yi Khin; Daw San San; U Maung Maung Tin; Daw Hla Hla Win

2001-01-01

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)

Report on the Personnel Dosimetry at AB Atomenergi during 1965

Energy Technology Data Exchange (ETDEWEB)

Edvardsson, K A

1966-10-15

This report presents the results of the personnel dosimetry at AB Atomenergi during 1965. No doses exceeding the recommendations of ICRP were reported. For AB Atomenergi the average external total body dose during the year was 60 mrem which corresponds to 89.4 manrem. 31200 gamma films and 5850 neutron films were evaluated. 2067 urine analyses and 692 measurements of body activity were made.

Report on the Personnel Dosimetry at AB Atomenergi during 1965

International Nuclear Information System (INIS)

Edvardsson, K.A.

1966-10-01

This report presents the results of the personnel dosimetry at AB Atomenergi during 1965. No doses exceeding the recommendations of ICRP were reported. For AB Atomenergi the average external total body dose during the year was 60 mrem which corresponds to 89.4 manrem. 31200 gamma films and 5850 neutron films were evaluated. 2067 urine analyses and 692 measurements of body activity were made

A Test of Reliability of the Personnel Dosimetry Services Authorized by CSN using Photon Beams

International Nuclear Information System (INIS)

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

1987-01-01

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

Report on the Personnel Dosimetry at AB Atomenergi during 1964

International Nuclear Information System (INIS)

Edvardsson, K.A.; Hagsgaard, S.

1966-01-01

This report presents the results of the personnel dosimetry at AB Atomenergi during 1964. No doses exceeding the recommendations of ICRP were reported. The sum of the reported external total body doses during the year was for AB Atomenergi 51.5 manrem which, distributed over the whole company personnel, corresponds to an average dose of about 35 mrem per year and person or less than 1 % of the maximum permissible dose. 31,400 gamma films and 5,800 neutron films were evaluated. The films were changed every month. Urine analyses numbered 2,731 and whole body measurements 485. A comparison is made between dose distributions at AB Atomenergi and at institutions in other countries. The fraction of all personnel carrying dosimeters and exposed to more than a nominal dose seems generally to have been less than 10-20 %

Report on the Personnel Dosimetry at AB Atomenergi during 1964

Energy Technology Data Exchange (ETDEWEB)

Edvardsson, K A; Hagsgaard, S

1966-01-15

This report presents the results of the personnel dosimetry at AB Atomenergi during 1964. No doses exceeding the recommendations of ICRP were reported. The sum of the reported external total body doses during the year was for AB Atomenergi 51.5 manrem which, distributed over the whole company personnel, corresponds to an average dose of about 35 mrem per year and person or less than 1 % of the maximum permissible dose. 31,400 gamma films and 5,800 neutron films were evaluated. The films were changed every month. Urine analyses numbered 2,731 and whole body measurements 485. A comparison is made between dose distributions at AB Atomenergi and at institutions in other countries. The fraction of all personnel carrying dosimeters and exposed to more than a nominal dose seems generally to have been less than 10-20 %.

Report on the Personnel Dosimetry at AB Atomenergi during 1968

Energy Technology Data Exchange (ETDEWEB)

Carlsson, J; Wahlberg, T

1969-08-15

This report presents the results of personnel dosimetry at AB Atomenergi during 1968. 25600 gamma films and 3900 neutron films were evaluated. 1737 urine analyses and 1066 measurements of body activity were made. The external total body gamma dose for all employees (quarterly doses {<=} 100 mrem are not reported) corresponds to 136 manrem. The highest external total body gamma dose during 1968 to one person was 4,500 mrem.

Report on the Personnel Dosimetry at AB Atomenergi during 1967

International Nuclear Information System (INIS)

Carlsson, J.; Wahlberg, T.

1968-12-01

This report presents the results of personnel dosimetry at AB Atomenergi during 1967. The external total body gamma dose for all employees (quarterly doses ≤ 100 mrem are not reported) corresponds to 140 manrem. The highest external total body gamma dose during 1967 to one person was 5700 mrem. 24700 gamma films and 3900 neutron films were evaluated. 1988 urine analyses and 989 measurements of body activity were made

Report on the Personnel Dosimetry at AB Atomenergi during 1967

Energy Technology Data Exchange (ETDEWEB)

Carlsson, J; Wahlberg, T

1968-12-15

This report presents the results of personnel dosimetry at AB Atomenergi during 1967. The external total body gamma dose for all employees (quarterly doses {<=} 100 mrem are not reported) corresponds to 140 manrem. The highest external total body gamma dose during 1967 to one person was 5700 mrem. 24700 gamma films and 3900 neutron films were evaluated. 1988 urine analyses and 989 measurements of body activity were made.

Intercomparison of personnel dosimetry for thermal neutron dose equivalent in neutron and gamma-ray mixed fields

International Nuclear Information System (INIS)

Ogawa, Yoshihiro

1985-01-01

In order to consider the problems concerned with personnel dosimetry using film badges and TLDs, an intercomparison of personnel dosimetry, especially dose equivalent responses of personnel dosimeters to thermal neutron, was carried out in five different neutron and gamma-ray mixed fields at KUR and UTR-KINKI from the practical point of view. For the estimation of thermal neutron dose equivalent, it may be concluded that each personnel dosimeter has good performances in the precision, that is, the standard deviations in the measured values by individual dosimeter were within 24 %, and the dose equivalent responses to thermal neutron were almost independent on cadmium ratio and gamma-ray contamination. However, the relative thermal neutron dose equivalent of individual dosimeter normalized to the ICRP recommended value varied considerably and a difference of about 4 times was observed among the dosimeters. From the results obtained, it is suggested that the standardization of calibration factors and procedures is required from the practical point of radiation protection and safety. (author)

Report on the Personnel Dosimetry at AB Atomenergi during 1969

Energy Technology Data Exchange (ETDEWEB)

Carlsson, J; Wahlberg, T

1971-05-15

This report presents the results of personnel dosimetry at AB Atomenergi during 1969. 24,200 gamma films and 3,300 neutron films were evaluated. 770 urine analyses and 1,150 measurements of body activity were made. The external total body gamma dose for all employees (quarterly doses < 100 mrem are not reported) corresponds to 136 manrem. The highest external total body gamma dose during 1969 to one person was 4,800 mrem

Hanford External Dosimetry Program

International Nuclear Information System (INIS)

Fix, J.J.

1990-10-01

This document describes the Hanford External Dosimetry Program as it is administered by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy (DOE) and its Hanford contractors. Program services include administrating the Hanford personnel dosimeter processing program and ensuring that the related dosimeter data accurately reflect occupational dose received by Hanford personnel or visitors. Specific chapters of this report deal with the following subjects: personnel dosimetry organizations at Hanford and the associated DOE and contractor exposure guidelines; types, characteristics, and procurement of personnel dosimeters used at Hanford; personnel dosimeter identification, acceptance testing, accountability, and exchange; dosimeter processing and data recording practices; standard sources, calibration factors, and calibration processes (including algorithms) used for calibrating Hanford personnel dosimeters; system operating parameters required for assurance of dosimeter processing quality control; special dose evaluation methods applied for individuals under abnormal circumstances (i.e., lost results, etc.); and methods for evaluating personnel doses from nuclear accidents. 1 ref., 14 figs., 5 tabs

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

Choice of measuring site in external personnel routine dosimetry

International Nuclear Information System (INIS)

Rothe, W.

1975-01-01

In personnel routine dosimetry the choice of a suitable measuring site is of great importance because there may be great differences between the measured doses and the equivalent doses of the whole body and of single organs, respectively. In the literature there are different points of view with regard to the measuring site particularly if diagnostic X-radiation is used and the body is partly covered with protective clothing. Likewise in most cases the conclusions regarding the most suitable measuring site drawn from measurements of dose distributions on the body surface are not in agreement. (author)

Performance of neutron and gamma personnel dosimetry in mixed radiation fields

International Nuclear Information System (INIS)

Swaja, R.E.; Sims, C.S.

1981-01-01

From 1974 to 1980, six personnel dosimetry intercomparison studies (PDIS) were conducted at the Oak Ridge National Laboratory (ORNL) to evaluate the performance of personnel dosimeters in a variety of neutron and gamma fields produced by operating the Health Physics Research Reactor (HPRR) in the steady state mode with and without spectral modifying shields. A total of 58 different organizations participated in these studies which produced approximately 2000 measurements of neutron and gamma dose equivalents on anthropomorphic phantoms for five different reactor spectra. Based on these data, the relative performance of three basic types of neutron dosimeters [nuclear emulsion film, thermoluminescent (TLD), and track-etch] and two basic types of gamma dosimeters (film and TLD) in mixed radiation fields was assessed

Report on the Personnel Dosimetry at AB Atomenergi during 1962

International Nuclear Information System (INIS)

Edvardsson, K.A.; Hagsgaard, S.

1963-12-01

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

Report on the Personnel Dosimetry at AB Atomenergi during 1962

Energy Technology Data Exchange (ETDEWEB)

Edvardsson, K A; Hagsgaard, S

1963-12-15

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.

Type tests performed on a personnel dosimetry system according to IEC 61066

International Nuclear Information System (INIS)

Castillo, Romel; Huamanlazo, Paula; Rojas, Enrique

2015-01-01

In this study, the verification of the Harshaw 6600 Plus TLD personal dosimetry system was made using the method of the IEC-61066 type tests and the recommendations of the ISO 4037 standards. For this purpose, five dosimeters were irradiated over a water phantom using an irradiator with a 137 Cs source; five dosimeters as control were also used. The evaluated parameters were homogeneity, detection limit, residual reading, linearity, reproducibility, droppings and temperature and humidity variations. The obtained results show that the Harshaw 6600 TLD dosimetric system fulfills the IEC 61066 criteria. (author)

Participation of the regional reference center for dosimetry of Argentina in the personnel dosimetry intercomparison for Latin America

International Nuclear Information System (INIS)

Alvarez, P.; Lindner, C.; Montano, R.G.; Saravi, M.

1998-01-01

Full text: A Regional Personnel Dosimetry Intercomparison was organized in the Regional Reference Center for Dosimetry (CRRD), in agreement with the International Atomic Energy Agency (IAEA) and the Nuclear Regulatory Authority (ARN), with the participation of 9 countries of Latin America. For dosimeter irradiations, X-ray, 60 Co γ-ray and 137 Cs γ-ray beams were used during the intercomparison. The air kerma rate was measured with the Secondary Standard NE 2560 and NE 2561 ionisation chamber. In compliance with ISO 4037 guideline, the wide spectrum series W60, W110 and W200 for the X-ray irradiations were chosen, determining their quality by the HVL method. Prior to the intercomparison, these beams were checked by the Physikalish Technische Bundesanstalt (PTB) using thermoluminescence dosimeters 'pill box', which were irradiated in air and in ICRU phantom. As result of this check, only one 'X ray beam got a deviation of 7%, while the rest of them were less than 3%. Periodic checks of the beams by a Primary Standard Dosimetry Laboratory such as PTB give reliability to the irradiations performed by this CRRD. (author) [es

Current status of personnel monitoring for beta particles

International Nuclear Information System (INIS)

Plato, P.; Miklos, J.

1983-01-01

From 1975 to 1982, a concerted effort was made to develop a uniform procedure to test the performance of personnel dosimetry processors throughout the United States. The heart of this effort is a standard developed by the Health Physics Society Standards Committee (HPSSC) and adopted by the American National Standards Institute (ANSI) as ANSI N13.11-1982. The US Nuclear Regulatory Commission (NRC) sponsored a five year pilot study of this Standard which included three trial tests in which approximately 80 dosimetry processors participated. The Standard has made several contributions to the art and science of personnel monitoring for beta particles. First, the Standard defines test categories for beta particles and mixtures of beta particles plus gamma rays in addition to test categories for other types of radiation. Second, it defines a reference beta-particle source for test purposes. Third, it provides test criteria which are used to determine acceptable performance by a processor. The pilot study provided information on the state of the art of personnel monitoring within the bounds of the Standard. In addition, since the pilot study was advertised as the forerunner of a future mandatory certification program for dosimetry processors throughout the United States, considerable attention was given to personnel monitoring in general, and beta particles in particular. This paper discusses specific contibutions of the HPSSC/ANSI Standard and the pilot study to beta-particle dosimetry. The results of the three tests of the pilot study are summarized. The paper also amplifies on the needs to define the monitoring particle sources clearly

Tenth ORNL Personnel Dosimetry Intercomparison Study

International Nuclear Information System (INIS)

Swaja, R.E.; Chou, T.L.; Sims, C.S.; Greene, R.T.

1985-03-01

The Tenth Personnel Dosimetry Intercomparison Study was conducted at the Oak Ridge National Laboratory during April 9-11, 1984. Dosemeter badges from 31 participating organizations were mounted on 40cm Lucite phantoms and exposed to a range of dose equivalents which could be encountered during routine personnel monitoring in mixed radiation fields. The Health Physics Research Reactor served as the only source of radiation for eight of the ten irradiations which included a low (approx. 0.50 mSv) and high (approx. 10.00 mSv) neutron dose equivalent run for each of four shield conditions. Two irradiations were also conducted for which concrete- and Lucite-shield reactor irradiations were gamma-enhanced using a 137 Cs source. Results indicated that some participants had difficulty obtaining measurable indication of neutron and gamma exposures at dose equivalents less than about 0.50 mSv and 0.20 mSv, respectively. Albedo dosemeters provided the best overall accuracy and precision for the neutron measurements. Direct interaction TLD systems showed significant variation in accuracy with incident spectrum, and threshold neutron dosemeters (film and recoil track) underestimated reference values by more than 50%. Gamma dose equivalents estimated in the mixed fields were higher than reference values with TL gamma dosemeters generally yielding more accurate results than film. Under the conditions of this study in which participants had information concerning exposure conditions and radiation field characteristics prior to dosemeter evaluation, only slightly more than half of all reported results met regulatory standards for neutron and gamma accuracy. 19 refs., 2 figs., 29 tabs

RCT: Module 2.04, Dosimetry, Course 8769

Energy Technology Data Exchange (ETDEWEB)

Hillmer, Kurt T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-08-11

This course will introduce the types of instruments used to measure external and internal radiation to people. Dosimetry is the quantitative assessment of radiation received by the human body. Several types of dosimeters are used worldwide. This information is valuable to all radiological control personnel because dosimeters are the only direct method to measure and document personnel radiation exposure and ensure regulatory compliance with applicable limits. This course will cover dosimetry terms, Department of Energy (DOE) limits, Los Alamos National Laboratory (LANL) administrative guidelines, thermoluminescent dosimeters (TLDs), LANL dosimetry, and bioassay assessment methods. This course will prepare the student with the skills necessary for radiological control technician (RCT) qualification by passing quizzes, tests, and the RCT Comprehensive Phase 1, Unit 2 Examination (TEST 27566) and providing in-thefield skills.

The calibration procedures in the Studsvik standardized personnel dosimetry system

International Nuclear Information System (INIS)

Widell, C.O.

1978-01-01

Every large nuclear installation in Sweden reads its own personnel TLDs. In order to supervise this decentralized reading of dose meters, the TLD readers are connected by telephone lines to a central computer for dose registration. This computer is used both for registering the personnel doses and for checking the TLD readers. This checking is performed by the use of pre-irradiated calibration dose meters which are always used when a batch of personnel dose meters are read. The pre-irradiated dose meters are either irradiated using 137 Cs to various doses up to 100mSv(10000mrem) or using a 90 Sr source in a reference dose irradiator to a dose equal to 3mSv(300mrem) from a 137 Cs source. The results from the reading of the pre-irradiated dose meters are processed by the computer and a calibration factor is calculated. The calibration factor is automatically used to calculate the doses to the personnel TLD's. However, if the calibration factor deviates by more than 10% from the previously used factor, this fact is shown to the operator - who then has to decide what calibration factor is going to be used. This calibration and supervisory procedure together with the safety interlocks in the TLD readers has resulted in a very reliable and accurate dosimetry system. (author)

Thermoluminescent dosimetry in veterinary diagnostic radiology

International Nuclear Information System (INIS)

Hernández-Ruiz, L.; Jimenez-Flores, Y.; Rivera-Montalvo, T.; Arias-Cisneros, L.; Méndez-Aguilar, R.E.; Uribe-Izquierdo, P.

2012-01-01

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.

French nuclear tests: the medical follow up of Cea participating personnel

International Nuclear Information System (INIS)

2004-01-01

For the personnel exposed to the risk of ionizing radiations, two types of examinations, in the aim of detecting any track of internal contamination were practiced at regular interval, at the arrival and at the departure from the site. A gamma spectrometry, and radio toxicological examination of feces and urines were practiced. furthermore, the exposed personnel received a specific film devoted to measure their external dosimetry. The same examinations were made for the local personnel and for the personnel of intervening societies. (N.C.)

Annual course of retraining for the occupational exposure personnel of the laboratory of internal dosimetry

International Nuclear Information System (INIS)

Alfaro L, M.M.

2002-09-01

The general objective of this report is to instruct the personnel in the basic concepts of radiological protection and in the Manual of Procedures of Radiological Safety of the Laboratory of Internal Dosimetry. Also, to exchange experiences during the activities that are carried out in the laboratory and in the knowledge of abnormal situations. The referred Manual consists of 14 procedures and 5 instructions which are listed in annex of this document. The content of this course consists of three topics: 1. Basic principles of radiological protection to reduce the received dose equivalent. 2. Use of radiation measurer equipment. 3. Emergency procedures of the laboratory of internal dosimetry. (Author)

Machine vision applications for physical security, quality assurance and personnel dosimetry

International Nuclear Information System (INIS)

Kar, S.; Shrikhande, S.V.; Suresh Babu, R.M.

2016-01-01

Machine vision is the technology used to provide imaging-based solutions to variety of applications, relevant to nuclear facilities and other industries. It uses computerized image analysis for automatic inspection, process control, object sorting, parts assembly, human identity authentication, and so on. In this article we discuss the in-house developed machine vision systems at EISD, BARC for three specific areas: Biometric recognition for physical security, visual inspection for QA of fuel pellets, and fast neutron personnel dosimetry. The advantages in using these systems include objective decision making, reduced man-rem, operational consistency, and capability of statistical quantitative analysis. (author)

Sixth symposium on neutron dosimetry

International Nuclear Information System (INIS)

1987-01-01

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)

The introduction of the personnel dosimetry information system in Greece designed as a relational database and the improvements achieved

International Nuclear Information System (INIS)

Drikos, G.; Psaromiligos, J.; Geotgiou, G.; Kamenopoulou, V.K.

1997-01-01

Dose record keeping is the making and keeping of personnel dose records for radiation workers. It is an essential part of the process of monitoring the exposure of individuals to radiation and shares in the same objectives. The dose record keeping is becoming more and more critical because of the importance of statistical analysis and epidemiological studies in radiation protection, and of the increasing cooperation and exchange of personnel between countries.The GAEC's personnel dosimetry laboratory assures the personnel dosimetry all over the country and keeps the official central dose record.The personnel dosimetry information system had been established in an electronic form on 1989 in Cobol language. Since then appeared various arguments that imposed the change of the data base used. Some of them are: 1. There was no distinction between establishments and their laboratories. 2. The workers did not have a unique code number. consequently, the total dose of a person working in more than one place could not't be estimated. The workers were directly related to their workplace, so if somebody changed his working place he was treated as a new entry, resulting an overestimation of the number of monitored workers introducing an source of errors in the collective and average dose calculations. 3. With the increasing applications of the ionising radiations many types of dosemeters became indispensable e.g. for beta and gamma, for neutrons and for the extremities. Also, the new category of outside workers appeared requesting a special treatment. All these distinctions were not achievable with the previous system. 4. Last years appeared an increasing, interesting in statistical analysis of the personal doses. A program written in Cobol does not't offer many possibilities and has no flexibility for such analysis. The new information system has been rebuilt under the design of a relational database with more possibilities and more flexibility. (authors)

Nevada test site neutron dosimetry-problems/solutions

International Nuclear Information System (INIS)

Sygitowicz, L.S.; Bastian, C.T.; Wells, I.J.; Koch, P.N.

1991-01-01

Historically, neutron dosimetry at the NTS was done using NTA film and albedo LiF TLD's. In 1987 the dosimeter type was changed from the albedo TLD based system to a CR-39 track etch based system modeled after the program developed by D. Hankins at LLNL. Routine issue and return is performed quarterly for selected personnel using bar-code readers at permanent locations. The capability exists for work site issue as-needed. Issue data are transmitted by telephone to a central computer where it is stored until the dosimeter is returned, processed and read, and the dose calculation is performed. Dose equivalent calculations are performed using LOTUS 123 and the results are printed as a hard copy record. The issue and dose information are hand-entered into the Dosimetry database. An application is currently being developed to automate this sequence

Textbook of dosimetry. 4. ed.

International Nuclear Information System (INIS)

Ivanov, V.I.

1999-01-01

This textbook of dosimetry is devoted to the students in physics and technical physics of high education institutions, confronted with different application of atomic energy as well as with protection of population and environment against ionizing radiations. Atomic energy is highly beneficial for man but unfortunately incorporates potential dangers which manifest in accidents, the source of which is either insufficient training of the personnel, a criminal negligence or insufficient reliability of the nuclear facilities. The majority of the incident and accident events have had as origin the personnel errors. This was the case with both the 'Three Miles Island' (1979) and Chernobyl (1986) NPP accidents. The dosimetry science acquires a vital significance in accident situations since the data obtained by its procedures are essential in choosing the correct immediate actions, behaviour tactics, orientation of liquidation of accident consequences as well as in ensuring the health of population. An important accent is placed in this manual on clarification of the nature of physical processes taken place in dosimetric detectors, in establishing the relation between radiation field characteristics and the detector response as well as in defining different dosimetric quantities. The terminology and the units of physical quantities is based on the international system of units. The book contains the following 15 chapters: 1. Ionizing radiation field; 2. Radiation doses; 3. Physical bases of gamma radiation dosimetry; 4. Ionization dosimetric detectors; 5. Semiconductor dosimetric detectors; 6. Scintillation detection in the gamma radiation dosimetry; 7. Luminescent methods in dosimetry; 8. The photographic and chemical methods of gamma radiation dosimetry; 9. Neutron dosimetry; 10. Dosimetry of high intensity radiation; 11. Dosimetry of high energy Bremsstrahlung; 12. Measurement of the linear energy transfer; 13. Microdosimetry; 14. Dosimetry of incorporated

Current status of personnel monitoring for β particles

International Nuclear Information System (INIS)

Plato, P.; Miklos, J.

1984-01-01

From 1975 to 1982, a concerted effort was made to develop a uniform procedure to test the performance of personnel dosimetry processors throughout the United States. The heart of this effort is a standard developed by the Health Physics Society Standards Committee (HPSSC) and adopted by the American National Standards Institute (ANSI) as ANSI N13.11-1982. The US Nuclear Regulatory Commission (NRC) sponsored a five year pilot study of this Standard which included three trial tests in which approximately 80 dosimetry processors participated. This paper addresses two major questions. First, what have the HPSSC/ANSI Standard and the NRC-sponsored pilot study contributed toward improvements in personnel monitoring for β particles. Second, what additional improvements are necessary. The Standard defines test categories for β particles and mixtures of β particles plus γ rays in addition to test categories for other types of radiation. It also defines a reference β-particle source for test purposes. Third, it provides test criteria which are used to determine acceptable performance by a processor. The pilot study provided information on the state of the art of personnel monitoring within the bounds of the Standard. In addition, since the pilot study was advertised as the forerunner of a future mandatory certification program for dosimetry processors throughout the United States, considerable attention was given to personnel monitoring in general, and β particles in particular, that otherwise would have been given to other squeaky wheels. The results of the three tests of the pilot study are summarized. The paper also amplifies on the needs to define the monitoring problems of the work place and to define appropriate β-particle sources clearly

Personnel dose assignment practices

International Nuclear Information System (INIS)

Fix, J.J.

1993-04-01

Implementation of DOE N 5480.6 Radiological Control Manual Article 511(3) requirements, to minimize the assignment of personnel dosimeters, should be done only under a broader context ensuring that capabilities are in place to monitor and record personnel exposure both for compliance and for potential litigation. As noted in NCRP Report No. 114, personnel dosimetry programs are conducted to meet four major objectives: radiation safety program control and evaluation; regulatory compliance; epidemiological research; and litigation. A change to Article 511(3) is proposed that would require that minimizing the assignment of personnel dosimeters take place only following full evaluation of overall capabilities (e.g., access control, area dosimetry, etc.) to meet the NCRP objectives

Current personnel dosimetry practices at DOE facilities

International Nuclear Information System (INIS)

Fix, J.J.

1981-05-01

Only three parameters were included in the personnel occupational exposure records by all facilities. These are employee name, social security number, and whole body dose. Approximate percentages of some other parameters included in the record systems are sex (50%), birthdate (90%), occupation (26%), previous employer radiation exposure (74%), etc. Statistical analysis of the data for such parameters as sex versus dose distribution, age versus dose distribution, cumulative lifetime dose, etc. was apparently seldom done. Less than 50% of the facilities reported having formal documentation for either the dosimeter, records system, or reader. Slightly greater than 50% of facilities reported having routine procedures in place. These are considered maximum percentages because some respondents considered computer codes as formal documentation. The repository receives data from DOE facilities regarding the (a) distribution of annual whole body doses, (b) significant internal depositions, and (c) individual doses upon termination. It is expected that numerous differences exist in the dose data submitted by the different facilities. Areas of significant differences would likely include the determination of non-measurable doses, the methods used to determine previous employer radiation dose, the methods of determining cumulative radiation dose, and assessment of internal doses. Undoubtedly, the accuracy of the different dosimetry systems, especially at low doses, is very important to the credibility of data summaries (e.g., man-rem) provided by the repository

Guidelines for the calibration of personnel dosimeters

International Nuclear Information System (INIS)

Roberson, P.L.; Holbrook, K.L.

1984-01-01

This guide describes minimum acceptable performance levels for personnel dosimetry systems used at Department of Energy (DOE) facilities. The goal is to improve both the quality of radiological calibrations and the methods of comparing reported occupational doses between DOE facilities. Reference calibration techniques are defined. A standard for evaluation of personnel dosimetry systems and recommended design parameters for personnel dosimeters are also included. Approximate intervals for the radiation energies for which these guidelines are appropriate are 15 keV to 2 MeV for photons; above 0.3 MeV for beta particles; and 1 keV to 2 MeV for neutrons. An analysis of ANSI N13.11 was completed using performance evaluations of selected personnel dosimetry systems in use at DOE facilities. The results of this analysis are incorporated in the guidelines

Tenth DOE workshop on personnel neutron dosimetry

International Nuclear Information System (INIS)

1984-06-01

The purpose of this workshop is to promote the international exchange of information on neutron dosimetry. The development of an accurate real-time dosemeter is an immediate need which must be met. Assessment of the neutron dose equivalent at low doses with a reasonable degree of accuracy must be accomplished to provide validity to exposure records. These and other aspects of personal neutron dosimetry are discussed. Separate abstracts have been prepared for each paper for inclusion in the Energy Data Base

Dose-equivalent response CR-39 track detector for personnel neutron dosimetry

International Nuclear Information System (INIS)

Oda, K.; Ito, M.; Yoneda, H.; Miyake, H.; Yamamoto, J.; Tsuruta, T.

1991-01-01

A dose-equivalent response detector based on CR-39 has been designed to be applied for personnel neutron dosimetry. The intrinsic detection efficiency of bare CR-39 was first evaluated from irradiation experiments with monoenergetic neutrons and theoretical calculations. In the second step, the radiator effect was investigated for the purpose of sensitization to fast neutrons. A two-layer radiator consisting of deuterized dotriacontane (C 32 D 66 ) and polyethylene (CH 2 ) was designed. Finally, we made the CR-39 detector sensitive to thermal neutrons by doping with orthocarbone (B 10 H 12 C 2 ), and also estimated the contribution of albedo neutrons. It was found that the new detector - boron-doped CR-39 with the two-layer radiator - would have a flat response with an error of about 70% in a wide energy region, ranging from thermal to 15 MeV. (orig.)

Eleventh ORNL personnel dosimetry intercomparison study, May 22-23, 1985

International Nuclear Information System (INIS)

Swaja, R.E.; Oyan, R.; Sims, C.S.

1986-07-01

The Eleventh Personnel Dosimetry Intercomparison Study was conducted at the Oak Ridge National Laboratory (ORNL) during May 22-23, 1985. Dosimeter badges from 44 participating organizations were mounted on Lucite block phantoms and exposed to four mixed-radiation fields with neutron dose equivalents around 5 mSv and gamma dose equivalents between 0.1 and 0.7 mSv. Results of this study indicated that no participants had difficulty obtaining measurable indication of neutron exposure at the provided dose equivalent levels, and very few had difficulty obtaining indication of gamma exposure at dose equivalents as low as 0.10 mSv. Average neutron results for all dosimeter types were within 20% of reference values with no obvious spectrum dependence. Different dosimeter types (albedo, direct interaction TLD, film, recoil track, and combination albedo-track) with 10 or more reported measurements provided average results within 35% of reference values for all spectra. With regard to precision, about 80% of the reported neutron results had single standard deviations within 10% at the means which indicates that precision is not a problem relative to accuracy for most participants. Average gamma results were greater than reference values by factors of 1.07 to 1.52 for the four exposures with TLD systems being more accurate than film. About 80% of all neutron results and 67% of all gamma results met regulatory standards for measurement accuracy and approximately 70% of all neutron data satisfied national dosimetry accreditation criteria for accuracy plus precision. In general, neutron dosimeter performance observed in this intercomparison was much improved compared to that observed in the prior studies while gamma dosimeter performance was about the same

Personnel Monitoring Department - DEMIN

International Nuclear Information System (INIS)

1989-01-01

The activities and purposes of the Personnel Monitoring Dept. of the Institute of Radioprotection and Dosimetry of the Brazilian CNEN are presented. A summary of the personnel monitoring service is given, such as dosemeters supply, laboratorial inspections, and so on. The programs of working, publishing, courses and personnel interchange are also presented. (J.A.M.M.)

Measurement protocols for performance testing of dosimetry services for external radiations

International Nuclear Information System (INIS)

1993-01-01

In the Health and Safety Executive's ''Requirements for the Approval of Dosimetry Services under the Ionising Radiations Regulations 1985'', it is stipulated that dosimetry services seeking approval must show that they have successfully completed a performance test. The services must arrange for the tests to be carried out on application and thereafter every 18 months, by a laboratory which has received accreditation from the National Measurement Accreditation Service (NAMAS) for the whole performance testing activity. The performance tests must be carried out to published protocols and the purpose here is to provide protocols for external, whole body film and TLD dosimetry services, and for skin and extremity dosimetry services. (Author)

A system for measuring and processing personnel dosimetric data

International Nuclear Information System (INIS)

Neetzel, C.R.; Rochetti, Luis

1981-01-01

An operative system for the measurement and on-line processing of personnel dosimetry data is described. The aim is to organize and rationalize the work involved in a personnel dosimetry service. The method considers the application to other areas of radiation protection, as well as the connection and exchange of files among the different personnel monitoring groups. The system can be interfaced with different computers (M.E.L.) [es

Fast neutron personnel dosimetry by CR-39 plastics a new electrochemical etching procedure

International Nuclear Information System (INIS)

Djeffal, S.

1984-07-01

In the first part of this work a brief description of solid state nuclear track detectors, the principles of track registration and the different reading techniques are given. In the experimental part of the present work we systematically analysed different etching procedures and set a new electrochemical etching method, which enables us to develop a new fast neutron dosimeter. This fast neutron dosimeter makes possible the measurement of low neutron doses in the energy range from 10 Kev to 20 Mev with a reasonably flat energy response. These new developments are very attractive in personnel neutron dosimetry where nuclear emulsions are still used despite their insensitivity to neutron energies down to 500 Kev (i.e. the energy range one often encounters around nuclear facilities)

Third conference on radiation protection and dosimetry

International Nuclear Information System (INIS)

1991-01-01

This conference has been designed with the objectives of promoting communication among applied, research, regulatory, and standards personnel involved in radiation protection and providing them with sufficient information to evaluate their programs. To partly fulfill these objectives, a technical program consisting of more than 75 invited and contributed oral presentations encompassing all aspects of radiation protection has been prepared. General topics include external dosimetry, internal dosimetry, instruments, regulations and standards, accreditation and test programs, research advances, and applied program experience. This publication provides a summary of the technical program and a collection of abstracts of the oral presentations

11. International conference on solid radiation dosimetry

International Nuclear Information System (INIS)

Krylova, I.V.

1996-01-01

The main problems discussed during the international conference on solid radiation dosimetry which took place in June 1995 in Budapest are briefly considered. These are the basic physical processes, materials applied for dosimetry, special techniques, personnel monitoring, monitoring of environmental effects, large-dose dosimetry, clinic dosimetry, track detector used for dosimetry, dosimetry in archaeology and geology, equipment and technique for dosimetric measurements. The special attention was paid to superlinearity in the TLD-100 (LiF, Mg, Ti) response function when determining doses of gamma radiation, heavy charged particles, low-energy particle fluxes in particular. New theoretical models were considered

Historical review of personnel dosimetry development and its use in radiation protection programs at Hanford 1944 to the 1980s

Energy Technology Data Exchange (ETDEWEB)

Wilson, R.H.

1987-02-01

This document is an account of the personnel dosimetry programs as they were developed and practiced at Hanford from their inception in 1943 to 1944 to the 1980s. This history is divided into sections covering the general categories of external and internal measurement methods, in vivo counting, radiation exposure recordkeeping, and calibration of personnel dosimeters. The reasons and circumstances surrounding the inception of these programs at Hanford are discussed. Information about these programs was obtained from documents, letters, and memos that are available in our historical records; the personnel files of many people who participated in these programs; and from the recollections of many long-time, current, and past Hanford employees. For the most part, the history of these programs is presented chronologically to relate their development and use in routine Hanford operations. 131 refs., 38 figs., 23 tabs.

Mathematical operations in cytogenetic dosimetry: Dosgen

International Nuclear Information System (INIS)

Garcia L, O.; Zequera J, T.

1996-01-01

Handling of formulas and mathematical procedures for fitting and using of dose-response relationships in cytogenetic dosimetry is often difficulted by the absence of collaborators specialized in mathematics and computation. DOSGEN program contains the main mathematical operations which are used in cytogenetic dosimetry. It is able to run in IBM compatible Pc's by non-specialized personnel.The program possibilities are: Poisson distribution fitting test for the number of aberration per cell, dose assessment for whole body irradiation, dose assessment for partial irradiation and determination of irradiated fraction. The program allows on screen visualization and printing of results. DOSGEN has been developed in turbo pascal and is 33Kb of size. (authors). 4 refs

Personal dosimetry performance testing in the United States

International Nuclear Information System (INIS)

Soares, Christopher G.

2008-01-01

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)

Automating the personnel dosimeter monitoring program

International Nuclear Information System (INIS)

Compston, M.W.

1982-12-01

The personnel dosimetry monitoring program at the Portsmouth uranium enrichment facility has been improved by using thermoluminescent dosimetry to monitor for ionizing radiation exposure, and by automating most of the operations and all of the associated information handling. A thermoluminescent dosimeter (TLD) card, worn by personnel inside security badges, stores the energy of ionizing radiation. The dosimeters are changed-out periodically and are loaded 150 cards at a time into an automated reader-processor. The resulting data is recorded and filed into a useful form by computer programming developed for this purpose

Nuclear Test Personnel Review

Science.gov (United States)

FOIA Electronic Reading Room Privacy Impact Assessment DTRA No Fear Act Reporting Nuclear Test Personnel Review NTPR Fact Sheets NTPR Radiation Dose Assessment Documents US Atmospheric Nuclear Test History Documents US Underground Nuclear Test History Reports NTPR Radiation Exposure Reports Enewetak

Evaluation of different polymers for fast neutron personnel dosimetry using electrochemical etching

International Nuclear Information System (INIS)

Gammage, R.B.; Cotter, S.J.

1977-01-01

There is considerable optimism for the enhancement by electrochemical etching of fast neutron-induced recoil tracks in polycarbonate for the purpose of personnel dosimetry. The threshold energy, however, is rather high. A desirable improvement would be to lower this energy below 1 MeV. With this objective in mind, we have commenced an investigation of cellulose acetate, triacetate, and acetobutyrate in addition to polycarbonate. These cellulose derivatives are chemically more reactive and physically weaker than polycarbonate. It might, therefore, be possible to initiate the electrochemical amplification at the sites of shorter recoil atom damage tracks than is possible with polycarbonate. Some characteristics important for electrochemically etching in aqueous electrolytes are listed. Chemical etching is combined with treeing, an electrical breakdown process that starts when the dielectric strength is exceeded. These mechanical and electrical properties pertain to the dry plastics. The absorption of water molecules and electrolyte ions will cause these values to be reduced. Results and conclusions of the study are presented

Implementation of a dosimetry service for the occupationally exposed personnel of the ESFM-IPN

International Nuclear Information System (INIS)

Hernandez A, Y.; Sanchez R, A. A.; Ceron R, P. V.; Rivera M, T.; Vega C, H. R.

2014-10-01

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)

Present status of fast neutron personnel dosimetry system based on CR-39 solid state nuclear track detectors

International Nuclear Information System (INIS)

Pal, Rupali; Sathian, Deepa; Jayalakshmi, V.; Bakshi, A.K.; Chougaonkar, M.P.; Mayya, Y.S.; Kumar, Valli; Babu, Rajesh; Kar, S.; Joshi, V.M.

2011-08-01

Neutron sources are of different types depending upon the method of production such as nuclear reactors, particle accelerators and laboratory sources. Neutron sources depending upon their energy, flux, size etc. are used for variety of applications in basic and applied sciences, neutron scattering experiments and in industry such as oil well - digging, coal mining and processing, ore processing etc. Personnel working in nuclear installations such as reactors, accelerators, spent fuel processing plants, nuclear fuel cycle operations and those working in various industries such as oil refining, oil well-digging, coal mining and processing, ore processing, etc. need to be monitored for neutron exposures, if any. Neutron monitoring is especially necessary in view of the fact that the radiation weighting factor for neutron is much higher than gamma rays and also it varies with energy. Radiological Physics and Advisory Division is involved in monitoring of personnel working in neutron fields. Around 2100 workers from 70 institutions (DAE and Non-DAE) are monitored on a quarterly basis. Neutron personnel monitoring, carried out in the country is based on Solid State Nuclear Track Detection (SSNTD) technique. In this technique, neutrons interact with hydrogen in CR-39 polymer to produce recoil protons. These protons create damages in the polymer, which are enlarged and appear as tracks when subjected to electrochemical etching (ECE). These tracks are counted in an optical system to evaluate the neutron dose. The neutron dosimetry system based on SSNTD has undergone a significant development, since it was started in 1990. The development includes upgradation of image analysis system for counting tracks, introduction of chemical etching (CE) at elevated temperatures for evaluation of dose equivalents above 10 mSv and use of carbon laser for cutting of CR-39 detectors. The entire dose evaluation process has been standardized, which includes calibration and performance tests

The LLNL CR-39 personnel neutron dosimeter

International Nuclear Information System (INIS)

Hankins, D.E.; Homann, S.; Westermark, J.

1987-01-01

We developed a personnel neutron dosimetry system based on the electrochemical etching of CR-39 plastic at elevated temperatures. The doses obtained using this dosimeter system are more accurate than those obtained using other dosimetry systems, especially when varied neutron spectra are encountered. This CR-39 dosimetry system does not have the severe energy dependence that exists with albedo neutron dosimeters or the fading and reading problems encountered with NTA film. 3 refs., 4 figs

Selected references on thermoluminescent dosemeters for personnel monitoring

International Nuclear Information System (INIS)

Lawson, Helen

1976-08-01

This bibliography contains references on: specific thermoluminescent dosemeters used for personnel dosimetry; comparisons of thermoluminescent and other dosemeters for personnel monitoring and read-out apparatus for thermoluminescent dosemeters. An appendix contains selected foreign language references. (author)

Non-conventional personal dosimetry techniques

International Nuclear Information System (INIS)

Regulla, D.F.

1984-01-01

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

Thermoluminescence dosimetry of gamma rays from the fallout of the Semipalatinsk nuclear tests

International Nuclear Information System (INIS)

Takada, J.; Hoshi, M.; Endo, S.; Yamamoto, M.; Nagatomo, T.; Gusev, B.I.; Rozenson, R.I.; Apsalikov, K.N.; Tchaijunusova, N.J.

1996-01-01

Field missions were sent to several settlements near the Semipalatinsk nuclear test site out in order to investigate dosimetry for the residents in 1995. The results of measurements of environmental radiation doses and thermoluminescence dosimetry in some villages near the Semipalatinsk nuclear test site are presented. The radiation levels in several villages are the natural background level in 1995, 6 years after the final nuclear explosion. On the other hand, thermoluminescence dosimetry revealed significant radiation exposure to residents in this area due to nuclear tests. (author)

INDIVIDUAL DOSIMETRY SERVICE

CERN Multimedia

2000-01-01

Personnel in the distribution groups Aleph, Delphi, L3, Opal who also work for other experiments than at LEP, should contact their dispatchers to explain their activities for the future, after LEP dismantling in order to be maintained on the regular distribution list at Individual DosimetryWe inform all staff and users under regular dosimetric control that the dosimeters for the monitoring period MAY/JUNE will be available from their usual dispatchers on Tuesday 2 May.Please have your films changed before the 12 May.The colour of the dosimeter valid in is MAY/JUNE is YELLOW.Individual Dosimetry Service will be closed on Friday 28 April.

Database to manage personal dosimetry Hospital Universitario de La Ribera

International Nuclear Information System (INIS)

Melchor, M.; Martinez, D.; Asensio, M.; Candela, F.; Camara, A.

2011-01-01

For the management of professionally exposed personnel dosimetry, da La are required for the use and return of dosimeters. in the Department of Radio Physics and Radiation Protection have designed and implemented a database management staff dosimetry Hospital and Area Health Centers. The specific objectives were easily import data from the National Center dosimetric dosimetry, consulting records in a simple dosimetry, dosimeters allow rotary handle, and also get reports from different periods of time to know the return data for users, services, etc.

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

International Nuclear Information System (INIS)

Sierra C, B. Y.; Jimenez, Y.; Plazas, M. C.; Eslava S, J.; Groot R, H.

2014-08-01

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)

Personal dosimetry performance testing in the United States

International Nuclear Information System (INIS)

Soares, C.G.

2005-01-01

Full text: The basis for personal dosimetry performance testing in the United States is ANSI/HPS N13.11 (2002). 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 Department of Energy (DOE) also maintains a testing program for its laboratories and contractors, administered by the Department 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 harmonization to US personal dosimeter processing testing. The testing philosophy of ANSI 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. This unique 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. (author)

Cytogenetic diagnostic of 3 populations of occupationally exposed personnel

International Nuclear Information System (INIS)

Guerrero C, C.; Arceo M, C.

2013-10-01

In the year 2000 the first service of biological dosimetry was requested to the Instituto Nacional de Investigaciones Nucleares (ININ), and until the year 2012 have been assisted 52 cases approximately. Most of the cases correspond to workers dedicated to the industrial radiography, followed by the occupationally exposed personnel either in the hospital area or health services and the minority corresponds to individuals linked to research institutions. The incident with more serious consequences to the individual happened to workers that ingested I-131 in the year 2003. Using the biological dosimetry to estimate exposure dose by damage in the lymphocyte chromosomes of each worker has been possible to establish the exposure dose in each one of them, or also to discard the supposed exposure. The dosimetry demonstrates to be an useful tool for situations with exposure suspicion, for example when the reading of thermoluminescent dosimeter of a occupationally exposed personnel does not correspond to the event, or when the personnel forgets to carry his dosimeter, the exposure dose can be determined. (Author)

Qualification tests for a dosimetry system

International Nuclear Information System (INIS)

Anon.

2005-01-01

The report of qualification tests for personnel dosemeters is detailed. Qualification test for the energy response and the incidence angle is given. The procedure of test is resumed. Different coefficients of conversion used in these tests are given in tables. (N.C.)

Personnel β-dosimetry method for reducing energy dependence

International Nuclear Information System (INIS)

Gesell, T.F.; Jones, D.E.; Gupta, V.P.; Kalbeitzer, F.L.; Cusimano, J.P.

1979-03-01

Current practices for the measurement of skin dose are reviewed and found to be inadequate. The current INEL dosimeter was examined for systematic and random error. Systematic (i.e., variation with energy) error was found to range over a factor of 10 while the random error was reasonably small for the larger β/γ ratios. Other designs with thicker windows as is more common would show even larger systematic errors. Various methods for improving beta dosimetry were reviewed. A new dosimeter design utilizing three chips, each having a window of difference thickness, was proposed. According to the calculations, this dosimeter should markedly reduce systematic error but will introduce somewhat more random error. Preliminary measurements were carried out related to angular dependence and charged particle equilibrium. The proposed dosimeter design was tested with betas from a uranium slab. The average of the seven results was in excellent agreement with the known dose rate and the standard deviation of the result was 16%

Annual course of retraining for the occupational exposure personnel of the laboratory of internal dosimetry; Curso anual de reentrenamiento para el POE del laboratorio de dosimetria interna

Energy Technology Data Exchange (ETDEWEB)

Alfaro L, M.M. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2002-09-15

The general objective of this report is to instruct the personnel in the basic concepts of radiological protection and in the Manual of Procedures of Radiological Safety of the Laboratory of Internal Dosimetry. Also, to exchange experiences during the activities that are carried out in the laboratory and in the knowledge of abnormal situations. The referred Manual consists of 14 procedures and 5 instructions which are listed in annex of this document. The content of this course consists of three topics: 1. Basic principles of radiological protection to reduce the received dose equivalent. 2. Use of radiation measurer equipment. 3. Emergency procedures of the laboratory of internal dosimetry. (Author)

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.

Report on high energy neutron dosimetry workshop

International Nuclear Information System (INIS)

Alvar, K.R.; Gavron, A.

1993-01-01

The workshop was called to assess the performance of neutron dosimetry per the responses from ten DOE accelerator facilities to an Office of Energy Research questionnaire regarding implementation of a personnel dosimetry requirement in DRAFT DOE 5480.ACC, ''Safety of Accelerator Facilities''. The goals of the workshop were to assess the state of dosimetry at high energy accelerators and if such dosimetry requires improvement, to reach consensus on how to proceed with such improvements. There were 22 attendees, from DOE Programs and contract facilities, DOE, Office of Energy Research (ER), Office of Environmental Safety and Health (EH), Office of Fusion Energy, and the DOE high energy accelerator facilities. A list of attendees and the meeting agenda are attached. Copies of the presentations are also attached

Dosimetry and Calibration Section

International Nuclear Information System (INIS)

Otto, T.

1998-01-01

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

Eurados trial performance test for neutron personal dosimetry

DEFF Research Database (Denmark)

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

2001-01-01

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...

Dosimetry system 1986

International Nuclear Information System (INIS)

Woolson, William A.; Egbert, Stephen D.; Gritzner, Michael L.

1987-01-01

In May 1983, the authors proposed a dosimetry system for use by the Radiation Effects Research Foundation (RERF) that would incorporate the new findings and calculations of the joint United States - Japan working groups on the reassessment of A-bomb dosimetry. The proposed dosimetry system evolved from extensive discussions with RERF personnel, numerous meetings of the scientists from Japan and the United States involved in the dosimetry reassessment research, and requirements expressed by epidemiologists and radiobiologists on the various review panels. The dosimetry system proposed was based on considerations of the dosimetry requirements for the normal work of RERF and for future research in radiobiology, the computerized input data on A-bomb survivors available in the RERF data base, the level of detail, precision, and accuracy of various components of the dosimetric estimates, and the computer resources available at RERF in Hiroshima. These discussions and our own experience indicated that, in light of the expansion of computer and radiation technologies and the desire for more detail in the dosimetry, an entirely new approach to the dosimetry system was appropriate. This resulted in a complete replacement of the T65D system as distinguished from a simpler approach involving a renormalization of T65D parameters to reflect the new dosimetry. The proposed dosimetry system for RERF and the plan for implementation was accepted by the Department of Energy (DOE) Working Group on A-bomb Dosimetry chaired by Dr. R.F. Christy. The dosimetry system plan was also presented to the binational A-bomb dosimetry review groups for critical comment and was discussed at joint US-Japan workshop. A prototype dosimetry system incorporating preliminary dosimetry estimates and applicable to only a limited set of A-bomb survivors was installed on the RERF computer system in the fall of 1984. This system was successfully operated at RERF and provided an initial look at the impact of

Interest of numerical dosimetry in radiation protection: mean of substitution or measurements consolidation?; Interet de la dosimetrie numerique en radioprotection: moyen de substitution ou de consolidation des mesures?

Energy Technology Data Exchange (ETDEWEB)

Lahaye, T.; Chau, Q. [Institut de Radioprotection et de Surete Nucleaire (IRSN/DPHD/SDOS), Service Dosimetrie, 92 - Fontenay-aux-Roses (France); Ferragut, A.; Gillot, J.Y. [SAPHYMO, 91 - Massy (France)

2003-07-01

The use of calculation codes allows to reduce the costs and the time limits. These codes brings to operators elements to reinforce their projected dosimetry. In the cases of accidental overexposure, the numerical dosimetry comes in complement of clinical and biological investigations to give an estimation as precise as possible of the received dose. For particular situations where it does not exist an adapted instrumentation, the numerical dosimetry can substitute to conventional techniques used by regulatory dosimetry (project for aviation personnel). (N.C.)

The personal dosimetry in Mexico

International Nuclear Information System (INIS)

Salazar, M.A.

2006-01-01

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

Skin dose assessment in routine personnel beta/gamma dosimetry

International Nuclear Information System (INIS)

Christensen, P.

1980-01-01

The International Commission on Radiological Protection (Publication 26) has recommended a tissue depth of 5 to 10 mg.cm -2 for skin dose assessments. This requirement is generally not fulfilled by routine monitoring procedures because of practical difficulties in using very thin dosemeters with low sensitivity and therefore a high minimum detectable dose. Especially for low-energy beta-ray exposures underestimations of the skin dose by a factor of more than ten may occur. Low-transparent graphite-mixed sintered LiF and Li 2 B 4 0 7 : Mn dosemeters were produced which show a skin-equivalent response to beta and gamma exposures over a wide range of energies. These have found wide-spread application for extremity dosimetry but have not yet been generally introduced in routine personnel beta/gamma monitoring. The following adaptations of existing routine monitoring systems for improved skin dose assessments have been investigated: 1) Placement of a supplementary, thin, skin-dose equivalent dosemeter in the TLD badge to give additional information on low-energy exposures. 2) Introduction of a second photomultiplier in the read-out chamber which enables a simultaneous determination of emitted TL from both sides of the dosemeter separately. This method makes use of the selfshielding of the dosemeter to give information on the low-energy dose contribution. 3) By diffusion of Li 2 B 4 0 7 into solid LiF-dosemeters it was possible to produce a surface layer with a new distinct glow-peak at about 340 deg C which is not present in the undiffused part of the LiF chip, and which can be utilized for the assessment of the skin-dose. Data on energy response and accuracy of dose measurement for beta/gamma exposures are given for the three methods and advantages and disadvantages are discussed (H.K.)

Personal dosimetry and information platforms

International Nuclear Information System (INIS)

Sanchez Hidalgo, M.; Galan Montenegro, P.; Bodineau Gil, C.; Hernandez Rodriguez, R.; Jimenez Nartin, A.; Cano Sanchez, J. J.

2011-01-01

One question often raised by the hospital personnel dosimetry is the high incidence in the no monthly turnover of dosimeters, which is currently a high number of administrative dose assignments. The high number of workers with personal dosimetry and in many cases, the dispersion of workplaces makes it impossible to personalized management. To make a more direct and personal, and transmit information quickly and with guaranteed reception, has developed and implemented a system of personalized dosimetric information through messaging Short Message Service (SMS) and access to the history of dosimetric dosimetric and management through web space Service Hospital Radio physics.

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...

Interest of numerical dosimetry in radiation protection: mean of substitution or measurements consolidation?

International Nuclear Information System (INIS)

Lahaye, T.; Chau, Q.; Ferragut, A.; Gillot, J.Y.

2003-01-01

The use of calculation codes allows to reduce the costs and the time limits. These codes brings to operators elements to reinforce their projected dosimetry. In the cases of accidental overexposure, the numerical dosimetry comes in complement of clinical and biological investigations to give an estimation as precise as possible of the received dose. For particular situations where it does not exist an adapted instrumentation, the numerical dosimetry can substitute to conventional techniques used by regulatory dosimetry (project for aviation personnel). (N.C.)

History of personal dosimetry performance testing in the United States

International Nuclear Information System (INIS)

Soares, C. G.

2007-01-01

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)

Internal dosimetry, past and future

International Nuclear Information System (INIS)

Johnson, J.R.

1989-03-01

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 226 Ra, 228 Ra, and 224 Ra 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 226 Ra 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 224 Ra, 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

Personnel dosimetry of fast neutrons by silver activation in nuclear emulsions

International Nuclear Information System (INIS)

Francois, H.; Heilmann, C.; Jung, M.; Kappler, A.; Oppel, R.; Demoulin, R.

1982-01-01

This neutron dosimetry method may be extended to the radiological monitoring of a large number of workers. It uses photographic emulsion, a detector with long-established properties. The reproducibility of the detection characteristics is guaranteed by industrial manufacture. The method has been thoroughly tested and is now sufficiently under control for the application stage to be contemplated. The activation method has shown moreover that the optical counting technique accounts for only half the signal available. Owing to its sensitivity, energy response from 100 keV onwards, capacity to measure the neutron and electromagnetic (γ or X) doses simultaneously and complete automation the method may now be considered ready for extensive use in radioprotection [fr

New ISO standard - personnel photographic film dosemeters

International Nuclear Information System (INIS)

Brabec, D.

1980-01-01

The ISO Standard 1757 ''Personnel Photographic Film Dosemeters'', issued in June 1980, is briefly described. UVVVR's own dosemeter developed for use in the national film dosimetry service in Czechoslovakia is evaluated in relation to this ISO Standard. (author)

The use of film badges for personnel monitoring

International Nuclear Information System (INIS)

Ehrlich, M.

1962-01-01

Photographic film is fairly inexpensive and durable and as a result of irradiation its radiosensitive components undergo relatively permanent changes. With proper calibration the optical density of the development and fixed photographic film can be related to radiation exposure. Personnel monitoring with photographic film is the method of choice in many laboratories, and this manual gives guidelines for the use of photographic film in personnel dosimetry.

Personnel monitoring of radiations with thermoluminescent dosemeters

International Nuclear Information System (INIS)

Miano, S.C.

1987-01-01

The basics of personnel dosimetry technics, used by the Radiologic Protetion and Assessorie Service (SAPRA) are presented, consisting on use of thermoluminescent and CaSO 4 :Dy monitors in aggregated pellets by Teflon. The characteristics of this dosemeters, relating to the sensitivity, energetic dependence, spike temperature, characteristic emission curve, decay and light effect are shown. The thermoluminescent dosemeter measure system and the personnel monitoring system are also described. (C.G.C.) [pt

5th symposium on neutron dosimetry

Energy Technology Data Exchange (ETDEWEB)

Spurny, F

1985-03-01

The symposium was held in Neuherberg near Munich on September 17-20, 1984 and was attended by 200 specialists from 20 coutries. The participants discussed the following areas of neutron dosimetry: basic concept and analysis of irradiation, basic data, proportional counters in radiation protection, detector response and spectrometry, enviromental monitoring, radiobiology and biophysical models, analysis of neutron fields, thermoluminescent detectors, personnel monitoring, calibration, measurement in the environment of /sup 252/Cf sources, analysis of fields and detector response, standardization dosimetry, ionization chambers, planning of therapeutical irradiation study of depth dose distribution, facilities for neutron therapy and international comparison. (E.S.).

5th symposium on neutron dosimetry

International Nuclear Information System (INIS)

Spurny, F.

1985-01-01

The symposium was held in Neuherberg near Munich on September 17-20, 1984 and was attended by 200 specialists from 20 coutries. The participants discussed the following areas of neutron dosimetry: basic concept and analysis of irradiation, basic data, proportional counters in radiation protection, detector response and spectrometry, enviromental monitoring, radiobiology and biophysical models, analysis of neutron fields, thermoluminescent detectors, personnel monitoring, calibration, measurement in the environment of 252 Cf sources, analysis of fields and detector response, standardization dosimetry, ionization chambers, planning of therapeutical irradiation study of depth dose distribution, facilities for neutron therapy and international comparison. (E.S.)

Severe accident testing of a personnel airlock

International Nuclear Information System (INIS)

Clauss, D.B.; Parks, M.B.; Julien, J.T.; Peters, S.W.

1988-01-01

Sandia National Laboratories (Sandia) is investigating the leakage potential of mechanical penetrations as part of a research program on containment integrity under severe accident loads for the U.S. Nuclear Regulatory Commission (NRC). Barnes et al. (1984) and Shackelford et al. (1985) identified leakage from personnel airlocks as an important failure mode of containments subject to severe accident loads. However, these studies were based on relatively simple analysis methods. The complex structural interaction between the door, gasket, and bulkhead in personnel airlocks makes analytical evaluation of leakage difficult. In order to provide data to validate methods for evaluating the leakage potential, a full-size personnel airlock was subject to simulated severe accident loads consisting of pressure and temperature up to 300 psig and 800 degrees F. The test was conducted at Chicago Bridge and Iron under contract to Sandia. The authors provide a detailed report on the test program

JENDL Dosimetry File

International Nuclear Information System (INIS)

Nakazawa, Masaharu; Iguchi, Tetsuo; Kobayashi, Katsuhei; Iwasaki, Shin; Sakurai, Kiyoshi; Ikeda, Yujiro; Nakagawa, Tsuneo.

1992-03-01

The JENDL Dosimetry File based on JENDL-3 was compiled and integral tests of cross section data were performed by the Dosimetry Integral Test Working Group of the Japanese Nuclear Data Committee. Data stored in the JENDL Dosimetry File are the cross sections and their covariance data for 61 reactions. The cross sections were mainly taken from JENDL-3 and the covariances from IRDF-85. For some reactions, data were adopted from other evaluated data files. The data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-5 format. In order to confirm reliability of the data, several integral tests were carried out; comparison with the data in IRDF-85 and average cross sections measured in fission neutron fields, fast reactor spectra, DT neutron fields and Li(d, n) neutron fields. As a result, it has been found that the JENDL Dosimetry File gives better results than IRDF-85 but there are some problems to be improved in future. The contents of the JENDL Dosimetry File and the results of the integral tests are described in this report. All of the dosimetry cross sections are shown in a graphical form. (author) 76 refs

JENDL Dosimetry File

Energy Technology Data Exchange (ETDEWEB)

Nakazawa, Masaharu; Iguchi, Tetsuo [Tokyo Univ. (Japan). Faculty of Engineering; Kobayashi, Katsuhei [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.; Iwasaki, Shin [Tohoku Univ., Sendai (Japan). Faculty of Engineering; Sakurai, Kiyoshi; Ikeda, Yujior; Nakagawa, Tsuneo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1992-03-15

The JENDL Dosimetry File based on JENDL-3 was compiled and integral tests of cross section data were performed by the Dosimetry Integral Test Working Group of the Japanese Nuclear Data Committee. Data stored in the JENDL Dosimetry File are the cross sections and their covariance data for 61 reactions. The cross sections were mainly taken from JENDL-3 and the covariances from IRDF-85. For some reactions, data were adopted from other evaluated data files. The data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-5 format. In order to confirm reliability of the data, several integral tests were carried out; comparison with the data in IRDF-85 and average cross sections measured in fission neutron fields, fast reactor spectra, DT neutron fields and Li(d,n) neutron fields. As a result, it has been found that the JENDL Dosimetry File gives better results than IRDF-85 but there are some problems to be improved in future. The contents of the JENDL Dosimetry File and the results of the integral tests are described in this report. All of the dosimetry cross sections are shown in a graphical form.

Standard practice for analysis and interpretation of physics dosimetry results for test reactors

International Nuclear Information System (INIS)

Anon.

1984-01-01

This practice describes the methodology summarized in Annex Al to be used in the analysis and interpretation of physics-dosimetry results from test reactors. This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods that are in various stages of completion (see Fig. 1). Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, exposure units, and neutron spectrum adjustment methods. This practice is directed towards the development and application of physics-dosimetrymetallurgical data obtained from test reactor irradiation experiments that are performed in support of the operation, licensing, and regulation of LWR nuclear power plants. It specifically addresses the physics-dosimetry aspects of the problem. Procedures related to the analysis, interpretation, and application of both test and power reactor physics-dosimetry-metallurgy results are addressed in Practice E 853, Practice E 560, Matrix E 706(IE), Practice E 185, Matrix E 706(IG), Guide E 900, and Method E 646

Proceedings of the second conference on radiation protection and dosimetry

International Nuclear Information System (INIS)

Swaja, R.E.; Sims, C.S.

1988-11-01

The Second Conference on Radiation Protection and Dosimetry was held during October 31--November 3, 1988, at the Holiday Inn, Crowne Plaza Hotel in Orlando, Florida. This meeting was designed with the objectives of promoting communication among applied, research, regulatory, and standards personnel involved in radiation protection and providing them with sufficient information to evaluate their programs. To facilitate meeting these objectives, a technical program consisting of more than 75 invited and contributed oral presentations encompassing all aspects of radiation protection was prepared. General topics considered in the technical sessions included external dosimetry, internal dosimetry, calibration, standards and regulations, instrumentation, accreditation and test programs, research advances, and applied program experience. In addition, special sessions were held to afford attendees the opportunity to make short presentations of recent work or to discuss topics of general interest. This document provides a summary of the conference technical program and a partial collection of full papers for the oral presentations in order of delivery. Individual papers were processed separately for the data base

Proceedings of the second conference on radiation protection and dosimetry

Energy Technology Data Exchange (ETDEWEB)

Swaja, R. E.; Sims, C. S. [eds.

1988-11-01

The Second Conference on Radiation Protection and Dosimetry was held during October 31--November 3, 1988, at the Holiday Inn, Crowne Plaza Hotel in Orlando, Florida. This meeting was designed with the objectives of promoting communication among applied, research, regulatory, and standards personnel involved in radiation protection and providing them with sufficient information to evaluate their programs. To facilitate meeting these objectives, a technical program consisting of more than 75 invited and contributed oral presentations encompassing all aspects of radiation protection was prepared. General topics considered in the technical sessions included external dosimetry, internal dosimetry, calibration, standards and regulations, instrumentation, accreditation and test programs, research advances, and applied program experience. In addition, special sessions were held to afford attendees the opportunity to make short presentations of recent work or to discuss topics of general interest. This document provides a summary of the conference technical program and a partial collection of full papers for the oral presentations in order of delivery. Individual papers were processed separately for the data base.

Use of data libraries in dosimetry control systems

International Nuclear Information System (INIS)

Babenko, V.V.; Babenko, M.I.; Kazimirov, A.S.

2002-01-01

Analysis, prediction and planning of dose loads, adequacy in dose management of personnel, evaluation of expediency and sufficiency of existing radiation protection system can be realized with the help of database system of dosimetry control in 'Ukrytie'-shelter

INDIVIDUAL DOSIMETRY SERVICE

CERN Multimedia

1999-01-01

Personnel in the distribution groups Aleph, Delphi, L3, Opal who also work for other experiments than at LEP, should contact the Individual Dosimetry ServiceWe inform all staff and users under regular dosimetric control that the dosimeters for the monitoring period JANUARY/FEBRUARY will be available from their usual dispatchers on Monday the third of January 2000.Please have your films changed:before the 12 January.The colour of the dosimeter valid in JANUARY/FEBRUARY is WHITE.

INDIVIDUAL DOSIMETRY SERVICE

CERN Multimedia

2000-01-01

Personnel in the distribution groups Aleph, Delphi, L3, Opal who also work for other experiments than at LEP, should contact the Individual Dosimetry Service.We inform all staff and users under regular dosimetric control that the dosimeters for the monitoring period MARCH/APRIL will be available from their usual dispatchers on the third of March 2000.Please have your films changed before the 13th of March.The colour of the dosimeter valid in MARCH/APRIL is BLUE.

Some aspects on neutron dosimetry

International Nuclear Information System (INIS)

Henaish, B.A.; Youssef, S.K.

1988-01-01

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

Dosimetry of x-ray beams: The measure of the problem

International Nuclear Information System (INIS)

de Castro, T.M.

1986-08-01

This document contains the text of an oral presentation on dosimetry of analytical x-ray equipment presented at the Denver X-Ray Conference. Included are discussions of sources of background radiation, exposure limits from occupational sources, and the relationship of these sources to the high dose source of x-rays found in analytical machines. The mathematical basis of x-ray dosimetry is reviewed in preparation for more detailed notes on personnel dosimetry and the selection of the most appropriate dosimeter for a specific application. The presentation concludes with a discussion common to previous x-ray equipment accidents. 2 refs

Personnel dosimetry in fluoroscopy

International Nuclear Information System (INIS)

Baechler, S.; Gardon, M.; Bochud, F.; Sans-Merce, M.; Verdun, F.R.; Trueb, Ph.

2006-01-01

Physicians who frequently perform fluoroscopic examinations are exposed to high intensity radiation fields and should use protective equipment such as lead aprons, thyroid shields and lead glasses. Standard individual dosimeters are worn under the lead apron in order to measure a dose that is representative of effective dose. However, large parts of the body are not protected by the apron (e.g. arms, head). Given a protection factor for the apron of about 100, an important irradiation of a body part not under the apron could go undetected. A study was conducted to analyse this situation by measuring dose using two dosimeters, one over-apron and one under-apron, for radiologists performing frequent fluoroscopic examinations. Measurements made over six-month period show that, indeed, the use of a single under-apron dosimeter is inadequate for personnel monitoring. Large doses to the head and arms are going undetected by this technique. A method for weighting the doses measured by under- and over-apron dosimeters to obtain a value better representative of the effective dose will be proposed. (authors)

Development of optically stimulated luminescence technology for personnel monitoring applications at Bhabha Atomic Research Centre

International Nuclear Information System (INIS)

Kulkarni, M.S.

2012-01-01

element OSL dosimeter (OSLD) badge for personnel and environmental monitoring application has been designed and developed using Al 2 O 3 :C dosimeters. The first prototype OSLD badge reader system was also developed for the readout of the four element OSLD card. This OSL dosimetry system covers a wide dynamic dose range of 20 μSv to 1 Sv, with an added advantage of fast and accurate readouts. Currently, the four element OSLD badge and two versions of the OSLD badge reader are being field tested in research and power reactors. The talk covers the issues related to the development of OSL dosimetry system for personnel monitoring applications in India. (author)

Implementation of the International Code of Practice on Dosimetry in Diagnostic Radiology (TRS 457): Review of Test Results

International Nuclear Information System (INIS)

2011-01-01

In 2007, the IAEA published Dosimetry in Diagnostic Radiology: An International Code of Practice (IAEA Technical Reports Series No. 457). This publication recommends procedures for calibration and dosimetric measurement for the attainment of standardized dosimetry. It also addresses requirements both in standards dosimetry laboratories, especially Secondary Standards Dosimetry Laboratories (SSDLs), and in clinical centres for radiology, as found in most hospitals. The implementation of TRS No. 457 decreases the uncertainty in the dosimetry of diagnostic radiology beams and provides Member States with a unified and consistent framework for dosimetry in diagnostic radiology, which previously did not exist. A coordinated research project (CRP E2.10.06) was established in order to provide practical guidance to professionals at SSDLs and to clinical medical physicists on the implementation of TRS No. 457. This includes the calibration of radiological dosimetry instrumentation, the dissemination of calibration coefficients to clinical centres and the establishment of dosimetric measurement processes in clinical settings. The main goals of the CRP were to: Test the procedures recommended in TRS No. 457 for calibration of radiation detectors in different types of diagnostic beams and measuring instruments for varying diagnostic X ray modalities; Test the clinical dosimetry procedures, including the use of phantoms and patient dose surveys; Report on the practical implementation of TRS No. 457 at both SSDLs and hospital sites. Testing of TRS No. 457 was performed by a group of medical physicists from hospitals and SSDLs from various institutions worldwide

Dosimetry in nuclear power plants

International Nuclear Information System (INIS)

Lastra B, J. A.

2008-12-01

To control the occupationally exposed personnel dose working at the Laguna Verde nuclear power plant, two types of dosemeters are used, the thermoluminescent (TLD) which is processed monthly, and the direct reading dosemeter that is electronic and works as daily control of personal dose. In the case of the electronic dosemeters of direct reading conventional, the readings and dose automatic registers and the user identity to which he was assigned to each dosemeter was to carry out the restricted area exit. In activities where the ionizing radiation sources are not fully characterized, it is necessary to relocate the personal dosemeter or assigned auxiliary dosemeters (TLDs and electronics) to determine the dose received by the user to both whole body and in any specific area of it. In jobs more complicated are used a tele dosimetry system where the radiation protection technician can be monitoring the user dose to remote control, the data transmission is by radio. The dosimetry activities are documented in procedures that include dosemeter inventories realization, the equipment and dosemeters calibration, the dosimetry quality control and the discrepancies investigation between the direct reading and TLD systems. TLD dosimetry to have technical expertise in direct and indirect dosimetry and two technicians in TLD dosimetry; electronic dosimetry to have 4 calibration technicians. For the electronic dosemeters are based on a calibrator source of Cesium-137. TLD dosemeters to have an automatic radiator, an automatic reader which can read up to 100 TLD dosemeters per hour and a semiautomatic reader. To keep the equipment under a quality process was development a process of initial entry into service and carried out a periodic verification of the heating cycles. It also has a maintenance contract for the equipment directly with the manufacturer to ensure their proper functioning. The vision in perspective of the dosimetry services of Laguna Verde nuclear power plant

Photographic film dosimetry for high-energy accelerator radiation

International Nuclear Information System (INIS)

Komochkov, M.M.; Salatskaya, M.I.

1981-01-01

A technique for personnel photographic film dosimetry (PPFDN) of wide energy spectrum neutrons intended for measuring the effect of accelerating device radiation on personnel is described. Procedures of data measurement and processing as well as corrections to hadron contribution are presented. It is noted that the PPFDN method permits to measure a neutron dose equivalent for personnel in the range from 0.01 to 0.02 up to 100 rem, if the relativistic neutron contribution to a total dose does not exceed 5%. The upper limit of the measured dose reduced several times for a greater contribution of relativistic neutrons to the total dose [ru

Computer aided dosimetry and verification of exposure to radiation. Technical report

International Nuclear Information System (INIS)

Waller, D.; Stodilka, R.Z.; Leach, K.E.; Prud'homme-Lalonde, L.

2002-06-01

In the timeframe following the September 11th attacks on the United States, increased emphasis has been placed on Chemical, Biological, Radiological and Nuclear (CBRN) preparedness. Of prime importance is rapid field assessment of potential radiation exposure to Canadian Forces field personnel. This work set up a framework for generating an 'expert' computer system for aiding and assisting field personnel in determining the extent of radiation insult to military personnel. Data was gathered by review of the available literature, discussions with medical and health physics personnel having hands-on experience dealing with radiation accident victims, and from experience of the principal investigator. Flow charts and generic data fusion algorithms were developed. Relationships between known exposure parameters, patient interview and history, clinical symptoms, clinical work-ups, physical dosimetry, biological dosimetry, and dose reconstruction as critical data indicators were investigated. The data obtained was examined in terms of information theory. A main goal was to determine how best to generate an adaptive model (i.e. when more data becomes available, how is the prediction improved). Consideration was given to determination of predictive algorithms for health outcome. In addition, the concept of coding an expert medical treatment advisor system was developed. (author)

TestDose: A nuclear medicine software based on Monte Carlo modeling for generating gamma camera acquisitions and dosimetry

Energy Technology Data Exchange (ETDEWEB)

Garcia, Marie-Paule, E-mail: marie-paule.garcia@univ-brest.fr; Villoing, Daphnée [UMR 1037 INSERM/UPS, CRCT, 133 Route de Narbonne, 31062 Toulouse (France); McKay, Erin [St George Hospital, Gray Street, Kogarah, New South Wales 2217 (Australia); Ferrer, Ludovic [ICO René Gauducheau, Boulevard Jacques Monod, St Herblain 44805 (France); Cremonesi, Marta; Botta, Francesca; Ferrari, Mahila [European Institute of Oncology, Via Ripamonti 435, Milano 20141 (Italy); Bardiès, Manuel [UMR 1037 INSERM/UPS, CRCT, 133 Route de Narbonne, Toulouse 31062 (France)

2015-12-15

Purpose: The TestDose platform was developed to generate scintigraphic imaging protocols and associated dosimetry by Monte Carlo modeling. TestDose is part of a broader project (www.dositest.com) whose aim is to identify the biases induced by different clinical dosimetry protocols. Methods: The TestDose software allows handling the whole pipeline from virtual patient generation to resulting planar and SPECT images and dosimetry calculations. The originality of their approach relies on the implementation of functional segmentation for the anthropomorphic model representing a virtual patient. Two anthropomorphic models are currently available: 4D XCAT and ICRP 110. A pharmacokinetic model describes the biodistribution of a given radiopharmaceutical in each defined compartment at various time-points. The Monte Carlo simulation toolkit GATE offers the possibility to accurately simulate scintigraphic images and absorbed doses in volumes of interest. The TestDose platform relies on GATE to reproduce precisely any imaging protocol and to provide reference dosimetry. For image generation, TestDose stores user’s imaging requirements and generates automatically command files used as input for GATE. Each compartment is simulated only once and the resulting output is weighted using pharmacokinetic data. Resulting compartment projections are aggregated to obtain the final image. For dosimetry computation, emission data are stored in the platform database and relevant GATE input files are generated for the virtual patient model and associated pharmacokinetics. Results: Two samples of software runs are given to demonstrate the potential of TestDose. A clinical imaging protocol for the Octreoscan™ therapeutical treatment was implemented using the 4D XCAT model. Whole-body “step and shoot” acquisitions at different times postinjection and one SPECT acquisition were generated within reasonable computation times. Based on the same Octreoscan™ kinetics, a dosimetry

INDIVIDUAL DOSIMETRY SERVICE

CERN Multimedia

2000-01-01

Personnel in the distribution groups Aleph, Delphi, L3, Opal who also work for other experiments than at LEP, should contact their dispatchers to explain their activities for the future, after LEP dismantling in order to be maintained on the regular distribution list at Individual Dosimetry ServiceWe inform all staffs and users under regular dosimetric control that the dosimeters for the monitoring period JULY/AUGUST are available from their usual dispatchers.Please have your films changed before the 10th of July.The colour of the dosimeter valid in JULY/AUGUST is PINK.

Proceedings of the third conference on radiation protection and dosimetry

Energy Technology Data Exchange (ETDEWEB)

Swaja, R.E.; Sims, C.S.; Casson, W.H. [eds.

1991-10-01

The Third Conference on Radiation Protection and Dosimetry was held during October 21--24, 1991, at the Sheraton Plaza Hotel in Orlando, Florida. This meeting was designed with the objectives of promoting communication among applied, research, regulatory, and standards personnel involved in radiation protection, and providing them with sufficient information to evaluate their programs. To meet these objectives, a technical program consisting of more than 75 invited and contributed oral presentations encompassing all aspects of radiation protection was prepared. General topics considered in the technical session included external dosimetry, internal dosimetry, instruments, accident dosimetry, regulations and standards, research advances, and applied program experience. In addition, special sessions were held to afford attendees the opportunity to make short presentations of recent work or to discuss topics of general interest. Individual reports are processed separately on the database.

Proceedings of the third conference on radiation protection and dosimetry

International Nuclear Information System (INIS)

Swaja, R.E.; Sims, C.S.; Casson, W.H.

1991-10-01

The Third Conference on Radiation Protection and Dosimetry was held during October 21--24, 1991, at the Sheraton Plaza Hotel in Orlando, Florida. This meeting was designed with the objectives of promoting communication among applied, research, regulatory, and standards personnel involved in radiation protection, and providing them with sufficient information to evaluate their programs. To meet these objectives, a technical program consisting of more than 75 invited and contributed oral presentations encompassing all aspects of radiation protection was prepared. General topics considered in the technical session included external dosimetry, internal dosimetry, instruments, accident dosimetry, regulations and standards, research advances, and applied program experience. In addition, special sessions were held to afford attendees the opportunity to make short presentations of recent work or to discuss topics of general interest. Individual reports are processed separately on the database

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

International Nuclear Information System (INIS)

Rathbone, Bruce A.

2006-01-01

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL's Hanford External Dosimetry Program which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL's Electronic Records & Information Capture Architecture (ERICA) database

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2005-02-25

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database.

Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Bradley, E.W.; Wu, C.F.; Goff, T.E.

1993-01-01

The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report

10 CFR 26.125 - Licensee testing facility personnel.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Licensee testing facility personnel. 26.125 Section 26.125 Energy NUCLEAR REGULATORY COMMISSION FITNESS FOR DUTY PROGRAMS Licensee Testing Facilities § 26.125... reports, if any; results of tests that establish employee competency for the position he or she holds...

Status of data testing of ENDF/B-V reactor dosimetry file

International Nuclear Information System (INIS)

Magurno, B.A.

1979-01-01

The ENDF/B-V Reactor Dosimetry File was released August 1979, and Phase II data testing started. The results presented here are from Brookhaven National Laboratory only, and are considered preliminary. The tests include calculated spectrum-averaged cross sections using 235 U fission spectrum (Watt), 252 Cf spontaneous fission spectrum (Watt and Maxwellian), and the Coupled Fast Reactor Measurement Facility (CFRMF) spectrum. 6 tables

ALGORITHM VERIFICATION FOR A TLD PERSONAL DOSIMETRY SYSTEM

International Nuclear Information System (INIS)

SHAHEIN, A.; SOLIMAN, H.A.; MAGHRABY, A.

2008-01-01

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 vigorously tested prior to the 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

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

International Nuclear Information System (INIS)

Queiroz, Carlos E.B.; Gerber Junior, Walmoli; Jahn, Tiago R.; Hahn, Tiago T.; Fontana, Thiago S.; Bolzan, Vagner

2013-01-01

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

Evaluation of Personnel Dosimetry data in Guatemala

International Nuclear Information System (INIS)

Guillen, J.A.

2002-01-01

The purpose of this report is to present the evaluated data from external exposures of 1268 radiation workers in Guatemala carried out in the period of 1997-2000. The collective dose in medicine, industry and other applications shown a tendency to increase in the period of study, radiology is the practice that shown a trend to decrease, that could be explained as a result of inspections and personnel training carried out in this practice

Personal nuclear accident dosimetry at Sandia National Laboratories

International Nuclear Information System (INIS)

Ward, D.C.; Mohagheghi, A.H.; Burrows, R.

1996-09-01

DOE installations possessing sufficient quantities of fissile material to potentially constitute a critical mass, such that the excessive exposure of personnel to radiation from a nuclear accident is possible, are required to provide nuclear accident dosimetry services. This document describes the personal nuclear accident dosimeter (PNAD) used by SNL and prescribes methodologies to initially screen, and to process PNAD results. In addition, this report describes PNAD dosimetry results obtained during the Nuclear Accident Dosimeter Intercomparison Study (NAD23), held during 12-16 June 1995, at Los Alamos National Laboratories. Biases for reported neutron doses ranged from -6% to +36% with an average bias of +12%

Integrating the DLD dosimetry system into the Almaraz NPP Corporative Database

International Nuclear Information System (INIS)

Gonzalez Crego, E.; Martin Lopez-Suevos, C.

1996-01-01

The article discusses the experience acquired during the integration of a new MGP Instruments DLD Dosimetry System into the Almaraz NPP corporative database and general communications network, following a client-server philosophy and taking into account the computer standards of the Plant. The most important results obtained are: Integration of DLD dosimetry information into corporative databases, permitting the use of new applications Sharing of existing personnel information with the DLD dosimetry application, thereby avoiding the redundant work of introducing data and improving the quality of the information. Facilitation of maintenance, both software and hardware, of the DLD system. Maximum explotation, from the computer point of view, of the initial investment. Adaptation of the application to the applicable legislation. (Author)

Computer aided dosimetry and verification of exposure to radiation. Technical report

Energy Technology Data Exchange (ETDEWEB)

Waller, D. [SAIC Canada (Canada); Stodilka, R.Z.; Leach, K.E.; Prud' homme-Lalonde, L. [Defence R and D Canada (DRDC), Radiation Effects Group, Space Systems and Technology, Ottawa, Ontario (Canada)

2002-06-15

In the timeframe following the September 11th attacks on the United States, increased emphasis has been placed on Chemical, Biological, Radiological and Nuclear (CBRN) preparedness. Of prime importance is rapid field assessment of potential radiation exposure to Canadian Forces field personnel. This work set up a framework for generating an 'expert' computer system for aiding and assisting field personnel in determining the extent of radiation insult to military personnel. Data was gathered by review of the available literature, discussions with medical and health physics personnel having hands-on experience dealing with radiation accident victims, and from experience of the principal investigator. Flow charts and generic data fusion algorithms were developed. Relationships between known exposure parameters, patient interview and history, clinical symptoms, clinical work-ups, physical dosimetry, biological dosimetry, and dose reconstruction as critical data indicators were investigated. The data obtained was examined in terms of information theory. A main goal was to determine how best to generate an adaptive model (i.e. when more data becomes available, how is the prediction improved). Consideration was given to determination of predictive algorithms for health outcome. In addition, the concept of coding an expert medical treatment advisor system was developed. (author)

Storage of radioactive material - accidents - precipitation - personnel monitoring

International Nuclear Information System (INIS)

Matijasic, A.; Gacinovic, O.

1961-12-01

This volume covers the reports on four routine tasks concerned with safe handling of radioactive material and influence of nuclear facilities on the environment. The tasks performed were as follows: Storage of solid and liquid radioactive material; actions in case of accidents; radiation monitoring of the fallout, water and ground; personnel dosimetry

Individual monitoring dosimetry in Europe

International Nuclear Information System (INIS)

Menzel, H.G.

1991-01-01

This report discusses the various types of individual monitoring systems presently in use within the European community and neutron dosimetry research being coordinated by the EURADOS working group. Research is currently being conducted on nuclear track dosimeters, primarily with CR-39 (TM), and TLD-albedo dosimeters. Studies are being conducted on the energy and angular response of each type of dosimeter. Because the response of dosimeters depends on the energy of the neutrons, it is necessary to have spectral information to accurately assess the dose. Neutron energy spectrum measurements are being performed in typical work place environments. Work is also progressing on development of calibration sources which will be representative of the neutron energy spectrum found in typical neutron exposure situations. This work utilizes 14 MeV neutrons incident on a uranium block with various other filters. Research is also continuing on neutron dosimetry using tissue equivalent proportional counters and microdosimetric techniques. The results of intercomparisons between several different instruments are discussed. In addition to personnel dosimetry, these systems are being used to record the dose to passengers and flight crews aboard commercial aircraft

Graphite mixed magnesium borate TL dosemeters for beta ray dosimetry

DEFF Research Database (Denmark)

Prokic, M; Christensen, Poul

1984-01-01

Sintered MgB4O7:Dy dosemeters with graphite contents from 1 to 10% were investigated for application for personnel dosimetry. Data are given on dose response, dose threshold, reproducibility, beta energy response and fading. Furthermore, results from practical field experiments are presented...

Dosimetry of the Occupational Exposure Personnel and not exposure of the INNSZ

International Nuclear Information System (INIS)

Ruiz J, A.

1999-01-01

In this work, was measured the equivalent dose of all the personnel of Nuclear medicine and personnel of the Institute which by its activities remain in the Department, by time determined, through thermoluminescent dosemeters and the results were that the personnel presents variable equivalent dose and it is proportional to the time and radionuclide type which use for their work. By this it is allowed to secure what the work watched with respect to radiological protection to fulfil with the International Standards standing for personnel in the Institute. (Author)

Radiation dosimetry of computed tomography x-ray scanners

International Nuclear Information System (INIS)

Poletti, J.L.; Williamson, B.D.P.; Le Heron, J.C.

1983-01-01

This report describes the development and application of the methods employed in National Radiation Laboratory (NRL) surveys of computed tomography x-ray scanners (CT scanners). It includes descriptions of the phantoms and equipment used, discussion of the various dose parameters measured, the principles of the various dosimetry systems employed and some indication of the doses to occupationally exposed personnel

Energy response study of modified CR-39 neutron personnel dosimeter

International Nuclear Information System (INIS)

Sathian, Deepa; Bakshi, A.K.; Datta, D.; Nair, Sreejith S.; Sathian, V.; Mishra, Jitendra; Sen, Meghnath

2018-01-01

Personnel neutron dosimetry is an integral part of radiation protection. No single dosimeter provides the satisfactory energy response, sensitivity, angular dependence characteristics and accuracy necessary to meet the requirement of an ideal personnel neutron dosimeter. The response of a personnel neutron dosimeter is critically dependent upon the energy distribution of the neutron field. CR-39 personnel neutron dosimeters were typically calibrated in the standard neutron field of 252 Cf and 241 Am-Be in our laboratory, although actual neutron fields may vary from the calibration neutron spectrum. Recently the badge cassette of the personnel neutron dosimeter was changed due to frequent damage of the PVC badge used earlier. This paper discusses energy response of CR-39 solid state nuclear track detector loaded in this modified badge cassette as per latest ISO recommendation

A relational database for personnel radiation exposure management

International Nuclear Information System (INIS)

David, W.; Miller, P.D.

1993-01-01

In-house utility personnel developed a relational data base for personnel radiation exposure management computer system during a 2 1/2 year period. The (PREM) Personnel Radiation Exposure Management System was designed to meet current Nuclear Regulatory Commission (NRC) requirements related to radiological access control, Radiation Work Permits (RWP) management, automated personnel dosimetry reporting, ALARA planning and repetitive job history dose archiving. The system has been operational for the past 18 months which includes a full refueling outage at Clinton Power Station. The Radiation Protection Department designed PREM to establish a software platform for implementing future revisions to 10CFR20 in 1993. Workers acceptance of the system has been excellent. Regulatory officials have given the system high marks as a radiological tool because of the system's ability to track the entire job from start to finish

Interactive and automated systems for nuclear track measurements with applications to fast neutron dosimetry

International Nuclear Information System (INIS)

Roberts, J.H.; Gold, R.; McNeece, J.P.; Preston, C.C.; Ruddy, F.H.

1983-12-01

Interactive and automatic track measuring systems have been developed primarily for fast neutron dosimetry in and around reactors. The interactive system is used for proton recoil measurements in nuclear research emulsions and the automatic systems for counting fission fragment tracks in Muscovite mica. The status of these systems, along with illustrative applications, are presented, particularly with regard to their relationship to neutron personnel dosimetry. 16 references, 12 figures

Dosimetry; La dosimetrie

Energy Technology Data Exchange (ETDEWEB)

Le Couteulx, I.; Apretna, D.; Beaugerie, M.F. [Electricite de France (EDF), 75 - Paris (France)] [and others

2003-07-01

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.)

Improving neutron dosimetry using bubble detector technology

International Nuclear Information System (INIS)

Buckner, M.A.

1993-02-01

Providing accurate neutron dosimetry for a variety of neutron energy spectra is a formidable task for any dosimetry system. Unless something is known about the neutron spectrum prior to processing the dosimeter, the calculated dose may vary greatly from that actually encountered; that is until now. The entrance of bubble detector technology into the field of neutron dosimetry has eliminated the necessity of having an a priori knowledge of the neutron energy spectra. Recently, a new approach in measuring personnel neutron dose equivalent was developed at Oak Ridge National Laboratory. By using bubble detectors in combination with current thermoluminescent dosimeters (TLDs) as a Combination Personnel Neutron Dosimeter (CPND), not only is it possible to provide accurate dose equivalent results, but a simple four-interval neutron energy spectrum is obtained as well. The components of the CPND are a Harshaw albedo TLD and two bubble detectors with theoretical energy thresholds of 100 key and 1500 keV. Presented are (1) a synoptic history surrounding emergence of bubble detector technology, (2) a brief overview of the current theory on mechanisms of interaction, (3) the data and analysis process involved in refining the response functions, (4) performance evaluation of the original CPND and a reevaluation of the same data under the modified method, (5) the procedure used to determine the reference values of component fluence and dose equivalent for field assessment, (6) analysis of the after-modification results, (7) a critique of some currently held assumptions, offering some alternative explanations, and (8) thoughts concerning potential applications and directions for future research

Design, comparison, and testing of a new user-friendly extremity dosimetry system

Energy Technology Data Exchange (ETDEWEB)

Stadtmann, H.; Schmitzer, C.; Michler, E. [Austrian Research Centre, Seibersdorf (Austria); Fellinger, J.; Velbeck, K.J.; Rotunda, J.E. [BICRON RMP, Solon (United States)

2000-05-01

A new extremity TLD system has been developed and tested that provides for user convenience and automated processing while meeting various accreditation requirements. The design is a result of successful collaboration among organisational entities in different countries and included research centres, users, and the manufacturer. The primary consideration was to meet the needs of the medical market, without losing sight of the needs of research laboratories and power plants. This dosimetry system design provides various detector designs based on the need to measure photons or betas. Beyond the fundamental need for accurate dosimetry, the system meets the customers need for a versatile and comfortable ring and provides for both hot and cold sterilisation. The system represents a unique integration of components comprising the finger ring, dosimeter and dosimeter identification system, and TLD Instruments. The dosimeter identification system in the TLD Reader incorporates a CCD Camera and Machine Vision Technology to interpret the circular bar codes used to quickly and accurately identifies each individual dosimeter. Portability of this dosimetry system has been realised with the adaptation into multiple TLD Instruments. (author)

Design, comparison, and testing of a new user-friendly extremity dosimetry system

International Nuclear Information System (INIS)

Stadtmann, H.; Schmitzer, C.; Michler, E.; Fellinger, J.; Velbeck, K.J.; Rotunda, J.E.

2000-01-01

A new extremity TLD system has been developed and tested that provides for user convenience and automated processing while meeting various accreditation requirements. The design is a result of successful collaboration among organisational entities in different countries and included research centres, users, and the manufacturer. The primary consideration was to meet the needs of the medical market, without losing sight of the needs of research laboratories and power plants. This dosimetry system design provides various detector designs based on the need to measure photons or betas. Beyond the fundamental need for accurate dosimetry, the system meets the customers need for a versatile and comfortable ring and provides for both hot and cold sterilisation. The system represents a unique integration of components comprising the finger ring, dosimeter and dosimeter identification system, and TLD Instruments. The dosimeter identification system in the TLD Reader incorporates a CCD Camera and Machine Vision Technology to interpret the circular bar codes used to quickly and accurately identifies each individual dosimeter. Portability of this dosimetry system has been realised with the adaptation into multiple TLD Instruments. (author)

Cytogenetic diagnostic of 3 populations of occupationally exposed personnel; Diagnostico citogenetico de 3 poblaciones de personal ocupacionalmente expuesto

Energy Technology Data Exchange (ETDEWEB)

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

2013-10-15

In the year 2000 the first service of biological dosimetry was requested to the Instituto Nacional de Investigaciones Nucleares (ININ), and until the year 2012 have been assisted 52 cases approximately. Most of the cases correspond to workers dedicated to the industrial radiography, followed by the occupationally exposed personnel either in the hospital area or health services and the minority corresponds to individuals linked to research institutions. The incident with more serious consequences to the individual happened to workers that ingested I-131 in the year 2003. Using the biological dosimetry to estimate exposure dose by damage in the lymphocyte chromosomes of each worker has been possible to establish the exposure dose in each one of them, or also to discard the supposed exposure. The dosimetry demonstrates to be an useful tool for situations with exposure suspicion, for example when the reading of thermoluminescent dosimeter of a occupationally exposed personnel does not correspond to the event, or when the personnel forgets to carry his dosimeter, the exposure dose can be determined. (Author)

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

Dosimetry of internal emitting: principles and perspectives of the MIRD technology

International Nuclear Information System (INIS)

Ferro F, G.

1999-01-01

The development of the radiopharmaceutical technology have multiplied the number of radioisotopes with applications in therapeutical nuclear medicine so known as Directed radiotherapy. Assuming the radiation is capable to produce noxious effects in the biological systems, it is important to evaluate appropriately the risks and benefits of the administration of radioactive agents in the patient. The outstanding parameter in this evaluation is the absorbed dose, which is product of the radiation emitted by a radionuclide that is localized or distributed to the interior of the human body in study and whose its estimation helps to predict the efficacy of the treatment. The scheme generalized of MIRD, it was formulated from thirty years ago for evaluating the interior dosimetry at level of organs.The finality of this work is to show the basic principles of the MIRD methodology and its perspectives using innovator tools as the dosimetry for dynamic masses, in particular the personnel dosimetry for the organs of each patient, the dosimetry for the small structures inside the organs (sub organic dosimetry), the distributions of doses in three dimensions (S voxel), the dosimetry at cellular level and the quantitative acquisition of pharmaceutical data. (Author)

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)

Nineteenth nuclear accident dosimetry intercomparison study, August 9-13, 1982

International Nuclear Information System (INIS)

Greene, R.T.; Sims, C.C.; Swaja, R.E.

1983-11-01

The Nineteenth Nuclear Accident Dosimetry Intercomparison Study was held August 9 to 13, 1982, at the Oak Ridge National Laboratory using the Health Physics Research Reactor operated in the pulse mode to simulate nuclear criticality accidents. Participants from eight organizations measured neutron and gamma doses at air stations and on phantoms for three different shielding conditions. Measured results were compared to nuclear industry guidelines for criticality accident dosimeters which suggest accuracies of +-25% for neutron dose and +-20% for gamma dose. Seventy-two percent of the neutron dose measurements using foil activation, sodium activation, hair sulfur activation, and thermoluminescent methods met the guidelines while less than 40% of the gamma dose measurements were within +-20% of reference values. The softest neutron energy spectrum (also lowest neutron/gamma dose ratio) provided the most difficulty in measuring neutron and gamma doses. Results of this study indicate the need for continued intercomparison and testing of nuclear accident dosimetry systems and for training of evaluating personnel. 14 references, 7 figures, 16 tables

Contribution of the operational dosimetry in the radiation protection optimization in a nuclear medicine service

International Nuclear Information System (INIS)

Herit, S.; Cosculluela, S.; Lambert, B.; Gras, H.

2007-01-01

Beyond its contribution in the personnel dosimetric surveillance, the operational dosimetry is a very efficient educational tool, of easy use. This study is lengthened by the setting up in 2007 of a job study in order to redefine the service zoning and by an evaluation of the extremities dosimetry with the help of thermoluminescent rings, in order to optimize the practices during the phase of preparation and injection. (N.C.)

The thermoluminscent dosimetry service of the radiation protection bureau

International Nuclear Information System (INIS)

1978-12-01

Thermoluminescent materials have been used in radiation dosimetry for many years, but their application to nationwide personnel dosimetry has been scarce. An undertaking of this nature requires that methods be established for identification of dosimeters and for fast interpretation and communication of dose to the users across the country. It is also necessary that records of cumulative dose of individual radiation workers be continuously updated, and such records be maintained for a prolonged period. To do this many problems pertinent to associated equpment, vis. the computer, TL reader, their interfacing, and to the operational procedures of the service had to be resolved. Since April 1977, the Radiation Protection Bureau has been providing a Thermoluminescent Dosimetry Service to Canadian radiation workers. This document describes the RPB dosimeter, its characteristics, various aspects of the service, objectives of the service, and how the objective goals of the service are achieved. (auth)

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2009-08-28

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document.

Dosimetry of hands and human factor

International Nuclear Information System (INIS)

Harr, R.

2008-12-01

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)

Fifteenth nuclear accident dosimetry intercomparison study: August 14--22, 1978

International Nuclear Information System (INIS)

Sims, C.S.

1979-05-01

The fifteenth in the continuing series of Nuclear Accident Dosimetry Intercomparison Studies was held August 14--22, 1978 at the Oak Ridge National Laboratory. The Health Physics Research Reactor, operated in the pulse mode, served as the radiation source. Using different shielding configurations, nuclear accidents with three different neutron and gamma spectra were simulated. Participants from 19 organizations, the most in the history of the studies, exposed dosimeters set up as area monitors as well as dosimeters mounted on phantoms for personnel monitoring. Although many participants performed accurate measurements, the composite dose results, in the majority of cases, failed to meet established nuclear criticality accident dosimetry guidelines which suggest accuracies of +- 25% for neutron dose and +- 20% for gamma dose. This indicates that many participants need to improve their dosimetry systems, their analytical techniques, or both

Results from 2010 Caliban Criticality Dosimetry Intercomparison

Energy Technology Data Exchange (ETDEWEB)

Veinot, K. G.

2011-10-12

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.

Dosicard: on-site evaluation of a new individual dosimetry system

International Nuclear Information System (INIS)

Delacroix, D.; Guelin, M.; Lyron, C.; Feraud, J.P.

1995-01-01

Dosicard is a new individual dosimetry system developed to monitor personnel working in the following fields: civil and military nuclear applications, medical environments and research centres: it can also be used to monitor mobile personnel. The system is based on the use of a credit-card sized format electronic badge. The associated computer environment enables management of the dosimetric data acquired. The characteristics of the system are presented in this paper together with an evaluation of the results of six month's use in a nuclear research centre. (author)

Nuclear accident dosimetry. Revision of emergency data sheets

International Nuclear Information System (INIS)

Delafield, H.J.

1976-09-01

The Emergency Data Sheets on Nuclear Accident Dosimetry have been revealed following the publication of a three part manual on this subject (Delafield, Dennis and Gibson, AERE-R 7485/6/7, 1973). This memo provides an explanation of the action levels adopted for the initial segregation of irradiated persons following a criticality accident, by monitoring the activity of indium foils contained in personnel dosimeters and the induced body sodium activity. The data sheets are given as an Appendix. They provide basic information on; the segregation of irradiated persons, the estimation of radiation exposure, and the assessment of personnel γ-ray and neutron doses. (author)

PSF blind test SSC, SPVC, and SVBC physics-dosimetry-metallurgy data packages

International Nuclear Information System (INIS)

1984-01-01

Information is presented concerning the final PSF radiometric data; calculated spectral fluences and dosimeter activities for the metallurgical blind test irradiations at the ORR-PSF; fabrication data package for HEDL dosimetry in the ORNL Poolside Facility LWR pressure vessel mock-up irradiation; SSC-1; NUREG-CR-3457; and NUREG-CR-3295

Health of Australian atomic test personnel

International Nuclear Information System (INIS)

Donovan, J.

1984-01-01

This paper briefly summarises the results of a survey of the health of Australian personnel who took part in the U.K. atomic weapons tests between 1952 and 1957. The study identified indications of radiation exposure among participants and examined their health in relation to the answers they gave. For example, the study compared the health of those participants who said they cleaned up radioactive areas after tests with the health of those who said they had not. There was no excess of disease or death for any disease group studied in those members of the workforce who had film badge evidence of exposure to radiation

An extended role for thermoluminescent phosphors in personnel, environmental and accident dosimetry using sensitisation, re-estimation and fast fading

International Nuclear Information System (INIS)

Charles, M.W.

1983-01-01

This paper summarises some techniques for extending the usefulness of conventional phosphors in personnel, environmental and accident dosimetry. An optimised procedure for utilising radiation sensitisation and UV re-estimation in thermoluminescent LiF is presented. In particular it is shown that optimum performance is achieved by using a UV wavelength of 250 +- 10 nm for both the UV/thermal anneal following sensitisation, and for the UV re-estimation procedure. In the case of Harshaw Lif Chips (3x3x0.9 mm 3 ) the sensitivity is increased by a factor of 4-5 to achieve a minimum detectable dose of approx.=10 μGy (2sigma) and a minimum re-estimable dose of 50-100 mGy (2sigma), dependent on batch. Sensitized LiF also exhibits improved tissue equivalence, extended linearity and improved precision at low doses. The information from fast-fading glow peaks, which is normally rejected, is shown to have a useful application to the evaluation of short-term increases in environmental dose rates such as may occur following accidental releases of radioactivity. (orig.)

Tritium dosimetry and standardization

International Nuclear Information System (INIS)

Balonov, M.I.

1983-01-01

Actual problem of radiation hygiene such as an evaluation of human irradiation hazard due to a contact with tritium compounds both in industrial and public spheres is under discussion. Sources of tritium release to environment are characterized. Methods of tritium radiation monitoring are discussed. Methods of dosimetry of internal human exposure resulted from tritium compounds are developed on the base of modern representations on metbolism and tritium radiobiological effect. A system of standardization of permissible intake of tritium compounds for personnel and persons of population is grounded. Some protection measures are proposed as applied to tritium overdosage

Doses of personnel employed in the manufacture of radioisotope thickness gages

International Nuclear Information System (INIS)

Kostenetskij, M.I.

1981-01-01

Doses of the personnel of one of the plants manifacturing radioisotope thickness gages of different types are determined. Annual doses to the body protected by shielding screens are low and according to the data of individual dosimetry constitute 5x10 -3 -6x10 -3 J/kg (0.5-0.6 rem). A table of radiation doses to hands obtained during all kind of operations, is given. Measures for the further reduction of radiation doses of the personnel are suggested [ru

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

Calibration of instrument and personnel monitoring in radiological protection

International Nuclear Information System (INIS)

Abdul Aziz Mohamad Ramli; Wan Saffiey Wan Abdullah

1987-01-01

It is difficult to choose radioprotection equipments that are not too expensive and suit the purpose. Some of the dosimetric characteristics of good dosemeters outlined by ISO 4071-1978 (E) namely scale linearity, energy dependence, radiation quality dependence and angular dependence for some of the commercially available dosemeters are discussed. The calibration procedures practised at the National Secondary Standard Dosimetry Laboratory (SSDL), of the Nuclear Energy Unit (NEU) is also explained. The radiological equipments for personnel monitoring such as film badge and TLD are widely used to estimate the radiation dose delivered to the whole or partial body of a personnel. Both of the personnel monitoring procedures have been established at the NEU. The objective, use and maintenance of the devices are also discussed in detail. The evaluation of the monthly dose received by a personnel from various establishments in the country are also presented. (author). 17 figs

Harmonization of internal dosimetry procedures in Latin America - ARCAL/IAEA project

Energy Technology Data Exchange (ETDEWEB)

Melo, D.; Dantas, B.M.; Juliao, L. [Instituto de Radioprotecao e Dosimetria - Av. Salvador Allende S/N, Recreio dos Bandeirantes, RJ 22780-160 (Brazil); Cruz Suarez, R. [International Atomic Energy Agency, Vienna (Austria); Rojo, A.; Serdero, N. [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina); Videla, R. [Comision Chilena de Energia Nuclear, Santiago (Chile); Puerta, J.A. [Universidad Nacional de Colombia, Medellin (Colombia); Lopez, G. [Centro de Proteccion e Higiene de las Radiaciones, Ciudad de la Habana (Cuba); Alfaro, M.M. [Instituto nacional de Investigaciones Nucleares (Mexico); Gonzales, S. [Instituto Peruano de Energia Nuclear, Lima (Peru); Hermida, J.C. [Hospital de Clinicas, Montevideo (Uruguay); Navarro, T. [Centro de Investigaciones Energeticas, Mediciones Ambientales y Tecnologicas - CIEMAT, Madrid (Spain)

2007-07-01

Under the auspices of the Regional Coordination Agreement for Latin America, representatives of the eight member states have participated in a project to improve radiological protection for workers exposed to unsealed sources of radiation. The design of the project was based on information obtained from a questionnaire circulated among the participants, from which the initial status of internal dosimetry services in each country was characterised. The objective of the project is to harmonize internal dosimetry procedures, with reference to International Atomic Energy Agency recommendations. After the implementation of new procedures and personnel training, four intercomparison exercises were carried out: measurement of iodine in thyroid phantoms, measurement of gamma emitters in urine samples, measurement of beta emitters in urine samples and internal dose assessments. This project has resulted in important improvements in internal dosimetry services in the region. (authors)

Internal dosimetry and control

International Nuclear Information System (INIS)

Rich, B.L.

1990-05-01

This internal dosimetry and control report provides guidance for EG ampersand G Idaho, Inc., field programs in detecting, evaluating, and controlling personnel exposure resulting from uptake of radionuclides by the body. Procedures specific to each program or facility are required to define the details of guidance from this report. Fundamental principles related to philosophy, policies, monitoring guidelines, and dose evaluation are discussed. Specific numerical guides and action levels are developed to guide the programs in evaluating the significance of specific analytical results. The requirement to thoroughly document the results and provide a formal technical base for each policy and/or practice is outlined and explained. 8 refs., 3 figs., 7 tabs

A review of lyoluminescence dosimetry and a new readout method using liquid scintillation techniques

International Nuclear Information System (INIS)

Ziemer, P.L.; Hanig, R.; Fayerman, L.K.

1978-01-01

Lyoluminescence dosimetry is useful as a personnel monitor and also as a neutron dosimeter. A review of lyoluminescence is given including readout systems, the machanisms of light emission, radiometric characteristics of lyoluminescence dosimeters, factor affecting response and liquid scintillation lyoluminscence readout

Specification ''E'' of the CEFRI concerning the enterprises employing personnel of A or B category working in nuclear facilities

CERN Document Server

Int. At. Energy Agency, Wien

2002-01-01

This document aims to specify the organization dispositions which have to bee taken by the enterprises employing personnel of A or B category to work in nuclear facilities. These dispositions should allow to respect the demands of the CEFRI in matter of formation, medical control and personnel dosimetry. (A.L.B.)

The qualification requirements for personnel carry out the testing for the pressure equipment materials

International Nuclear Information System (INIS)

Wojas, M.; Walczak, M.

2006-01-01

The article contains information about qualification requirements for personnel carry out the destructive and non-destructive testing for the pressure equipment materials based on the Directive 97/23/CE(PED). Competence laboratory carry out the testing. The responsibility lies with producer / employer. The producer / employer could elaborate the written practice procedure for qualification and certification testing personnel. (authors)

Dosimetry and Calibration Section

International Nuclear Information System (INIS)

Otto, T.

1999-01-01

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

The DOE Laboratory Accreditation Program 8 years later

International Nuclear Information System (INIS)

Cummings, R.; Kershisnik, R.; Taylor, T.; Grothaus, G.; Loesch, R.M.

1994-01-01

The DOE Laboratory Accreditation Program was implemented in 1986. Currently, the program is conducting its seventeenth performance testing session for whole body personnel dosimeters. All but two DOE laboratories have gained accreditation for their whole body personnel dosimetry systems. Several test situations which were anticipated in the early stages of DOELAP have not materialized. In addition, the testing standard for whole body personnel dosimetry systems is under review and revision. In the near future, the accreditation programs for extremity dosimetry and bioassay will be implemented. This presentation summarizes the status and anticipated direction of the DOE whole body and extremity dosimetry and bioassay laboratory accreditation program

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2010-04-01

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2011-04-04

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision

Automated personal dosimetry monitoring system for NPP

International Nuclear Information System (INIS)

Chanyshev, E.; Chechyotkin, N.; Kondratev, A.; Plyshevskaya, D.

2006-01-01

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 thermoluminescent

Standard Practice for Dosimetry of Proton Beams for use in Radiation Effects Testing of Electronics

Energy Technology Data Exchange (ETDEWEB)

McMahan, Margaret A.; Blackmore, Ewart; Cascio, Ethan W.; Castaneda, Carlos; von Przewoski, Barbara; Eisen, Harvey

2008-07-25

Representatives of facilities that routinely deliver protons for radiation effect testing are collaborating to establish a set of standard best practices for proton dosimetry. These best practices will be submitted to the ASTM International for adoption.

Standard Practice for Dosimetry of Proton Beams for use in Radiation Effects Testing of Electronics

International Nuclear Information System (INIS)

McMahan, Margaret A.; Blackmore, Ewart; Cascio, Ethan W.; Castaneda, Carlos; von Przewoski, Barbara; Eisen, Harvey

2008-01-01

Representatives of facilities that routinely deliver protons for radiation effect testing are collaborating to establish a set of standard best practices for proton dosimetry. These best practices will be submitted to the ASTM International for adoption

Study on personnel qualification for non-destructive tests in the field of reactor safety

International Nuclear Information System (INIS)

Trusch, K.; Wuestenberg, H.

1977-01-01

The training system for non-destructive testing is described, and the available and necessary personnel is analyzed; the personnel required for reactor safety problems is treated separately. On this basis, the subjects discussed in the study - available personnel, personnel requirements, training, training requirements, and suggestions for realisation - are treated in a general manner to begin with and afterwards with a view to specific problems of reactor safety. The methods employed are adapted to this situation. To obtain the necessary empirical data, questionnaires were set up and distributed, and experts in selected business companies and institutions were interviewed who work in the field of reactor safety or do same training in non-destructive testing. (orig.) [de

Analysis of quality control tests done by the Canadian power utilities on their external dosimetry systems (June 1985 to May 1988)

International Nuclear Information System (INIS)

Poirier, G.S.

1989-04-01

The Canadian nuclear power utilities, Hydro Quebec, New Brunswick Electric Power Commission and Ontario Hydro, use thermoluminescent dosimetry systems to perform their own external beta/gamma dosimetry. In order to help ensure that these systems perform satisfactorily, they are subjected to routine quality control testing by their parent organizations. The test results for the period of June 1985 to May 1988 have been analyzed, at the AECB, using the pass criterion which was originally agreed upon by the organizations involved. The present analysis offers a comparison of the performance of the different sites which operate such a service. Finally, recommendations are made in the hope that they will help the organizations in refining their dosimetry

Personnel radiation exposure in the Asse saltmine repository during 1967 to 2008. Health monitoring Asse

International Nuclear Information System (INIS)

2011-02-01

The health monitoring Asse includes the following chapters: Introduction, background information including handling of radioactive materials and radiation protection issues, data on radiation exposure (personnel dosimetry, incorporation surveillance, local dose rate measurements, exhaust monitoring, radioactivity in the salt mine air and in the brine, contamination), concept of the data base, interrogation of the personnel, quantification of the individual radiation doses, results of the radiation exposure quantification; significance of the results and perspectives.

Cross sections required for FMIT dosimetry

International Nuclear Information System (INIS)

Gold, R.; McElroy, W.N.; Lippincott, E.P.; Mann, F.M.; Oberg, D.L.; Roberts, J.H.; Ruddy, F.H.

1980-01-01

The Fusion Materials Irradiation Test (FMIT) facility, currently under construction, is designed to produce a high flux of high energy neutrons for irradiation effects experiments on fusion reactor materials. Characterization of the flux-fluence-spectrum in this rapidly varying neutron field requires adaptation and extension of currently available dosimetry techniques. This characterization will be carried out by a combination of active, passive, and calculational dosimetry. The goal is to provide the experimenter with accurate neutron flux-fluence-spectra at all positions in the test cell. Plans have been completed for a number of experimental dosimetry stations and provision for these facilities has been incorporated into the FMIT design. Overall needs of the FMIT irradiation damage program delineate goal accuracies for dosimetry that, in turn, create new requirements for high energy neutron cross section data. Recommendations based on these needs have been derived for required cross section data and accuracies

Qualification and certification of nondestructive testing personnel. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

Aly, E A [Quality Assurance Department, national Center for Nuclear Safety and Radiation Control, Atomic Energy Authority, Cairo, (Egypt)

1996-03-01

Nondestructive testing and inspection are functions in achieving the goals of quality and efficiency at an acceptable cost. All quality assurance systems necessitate that engineers, technicians and craftsmen are able to demonstrate that they have the required level of knowledge and skill. This applies particularly to nondestructive testing (NDT) and inspection. The paper presented highlights most important national and international standards and guidelines addressing training, qualification and certification of NDT personnel.

Qualification and certification of nondestructive testing personnel. Vol. 1

International Nuclear Information System (INIS)

Aly, E.A.

1996-01-01

Nondestructive testing and inspection are functions in achieving the goals of quality and efficiency at an acceptable cost. All quality assurance systems necessitate that engineers, technicians and craftsmen are able to demonstrate that they have the required level of knowledge and skill. This applies particularly to nondestructive testing (NDT) and inspection. The paper presented highlights most important national and international standards and guidelines addressing training, qualification and certification of NDT personnel

End-to-end tests using alanine dosimetry in scanned proton beams

Science.gov (United States)

Carlino, A.; Gouldstone, C.; Kragl, G.; Traneus, E.; Marrale, M.; Vatnitsky, S.; Stock, M.; Palmans, H.

2018-03-01

This paper describes end-to-end test procedures as the last fundamental step of medical commissioning before starting clinical operation of the MedAustron synchrotron-based pencil beam scanning (PBS) therapy facility with protons. One in-house homogeneous phantom and two anthropomorphic heterogeneous (head and pelvis) phantoms were used for end-to-end tests at MedAustron. The phantoms were equipped with alanine detectors, radiochromic films and ionization chambers. The correction for the ‘quenching’ effect of alanine pellets was implemented in the Monte Carlo platform of the evaluation version of RayStation TPS. During the end-to-end tests, the phantoms were transferred through the workflow like real patients to simulate the entire clinical workflow: immobilization, imaging, treatment planning and dose delivery. Different clinical scenarios of increasing complexity were simulated: delivery of a single beam, two oblique beams without and with range shifter. In addition to the dose comparison in the plastic phantoms the dose obtained from alanine pellet readings was compared with the dose determined with the Farmer ionization chamber in water. A consistent systematic deviation of about 2% was found between alanine dosimetry and the ionization chamber dosimetry in water and plastic materials. Acceptable agreement of planned and delivered doses was observed together with consistent and reproducible results of the end-to-end testing performed with different dosimetric techniques (alanine detectors, ionization chambers and EBT3 radiochromic films). The results confirmed the adequate implementation and integration of the new PBS technology at MedAustron. This work demonstrates that alanine pellets are suitable detectors for end-to-end tests in proton beam therapy and the developed procedures with customized anthropomorphic phantoms can be used to support implementation of PBS technology in clinical practice.

Quo vadis, personnel monitoring

International Nuclear Information System (INIS)

Becker, K.

1975-01-01

With the increasing use of nuclear power and radiation sources, the selection of optimum systems for personnel monitoring is becoming a matter of worldwide concern. The present status of personnel dosimetry, sometimes characterized by unstable and inaccurate detectors and oversimplified interpretation of the results, leaves much to be desired. In particular, photographic film, although having certain advantages with regard to economics and information content, undergoes rapid changes in warm and humid climates. Careful sealing reduces, but does not prevent, these problems. The replacement of film by solid-state dosimeters, primarily thermoluminescence dosimeters, is in progress or being considered by an increasing number of institutions and requires a number of decisions concerning the choice of the optimum detector(s), badge design, and evaluation system; organizational matters, such as the desirability of automation and computerized bookkeeping; etc. The change also implies the potential use of such advanced concepts as different detectors and monitoring periods for the large number of low-risk persons and the small number of high-risk radiation workers. (auth)

Thermally stimulated current in PTFE and its application in radiation dosimetry

International Nuclear Information System (INIS)

Ozdemir, S.

1985-01-01

Thermally Stimulated Current (TSC) measurement was made on PTFE (Polytetrafluoro ethylene) in an attempt to develop an integrating radiation dosimeter material and the system. TSC spectra, dose response, energy response, fading and background charge stability characteristics were used as a measure of suitability of various untreated and heat treated PTFE samples for dosimetry applications. For practical TSC dosimetry system, it was discovered that the PTFE samples should be subjected to a specific heat treatment in order to produce samples with better dosimeter characteristics. A treatment at a temperature of 240 C produces a high dose response and low fading characteristics. It was found that the spurious charges due to storage and low sensitivity to irradiation caused the limitation in the measurement of low doses with PTFE samples for personnel protection. However, a TSC Dosimetry system using PTFE is proposed which is suitable for radiation doses in the radiotherapy range from *approx* 50 to *approx* 800 mGy. (author)

Status of neutron dosimetry cross sections

International Nuclear Information System (INIS)

Griffin, P.J.; Kelly, J.G.

1992-01-01

Several new cross section libraries, such as ENDF/B-VI(release 2), IRDF-90,JEF-2.2, and JENDL-3 Dosimetry, have recently been made available to the dosimetry community. the Sandia National Laboratories (SNL) Radiation Metrology Laboratory (RML) has worked with these libraries since pre-release versions were available. this paper summarizes the results of the intercomparison and testing of dosimetry cross sections. As a result of this analysis, a compendium of the best dosimetry cross sections was assembled from the available libraries for use within the SNL RML. this library, referred to as the SNLRML Library, contains 66 general dosimetry sensors and 3 special dosimeters unique to the RML sensor inventory. The SNLRML cross sections have been put into a format compatible with commonly used spectrum determination codes

Type tests to the automatic system of thermoluminescent dosimetry acquired by the CPHR for personnel dosimetry

International Nuclear Information System (INIS)

Molina P, D.; Pernas S, R.

2005-01-01

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)

Level of occupational irradiation to medical personnel in Latvia

Energy Technology Data Exchange (ETDEWEB)

Gubatova, D.Ya.; Kostenko, I.V.; Nemiro, Ye.A.; Pustovit, I.A.; Semyonov, R.A.; Trautman, N.F. (Latvian Medical Academy, Riga (Latvia))

1992-06-01

An automated system for the recording and analysis of mass personal dosimetry data was developed. The results obtained with this system show that the average annual dose for X-ray laboratory assistants in Latvia gradually decreased before 1979 and that since then it has fluctuated without exceeding 5 mSv. The average annual dose for the republic's physicians has amounted to 4 mSv. The contribution of doses in excess of 15 mSv to the collective dose received by the republic's physicians has accounted for about 30 to 40%, which testifies to the fact that working conditons cannot be considered as being quite favourable; these conditions have to be further improved, and personal dosimetry of this category of personnel has to be conducted on a systematic basis. (orig.).

Level of occupational irradiation to medical personnel in Latvia

International Nuclear Information System (INIS)

Gubatova, D.Ya.; Kostenko, I.V.; Nemiro, Ye.A.; Pustovit, I.A.; Semyonov, R.A.; Trautman, N.F.

1992-01-01

An automated system for the recording and analysis of mass personal dosimetry data was developed. The results obtained with this system show that the average annual dose for X-ray laboratory assistants in Latvia gradually decreased before 1979 and that since then it has fluctuated without exceeding 5 mSv. The average annual dose for the republic's physicians has amounted to 4 mSv. The contribution of doses in excess of 15 mSv to the collective dose received by the republic's physicians has accounted for about 30 to 40%, which testifies to the fact that working conditons cannot be considered as being quite favourable; these conditions have to be further improved, and personal dosimetry of this category of personnel has to be conducted on a systematic basis. (orig.) [de

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

International Nuclear Information System (INIS)

Rathbone, Bruce A.

2007-01-01

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL's Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL's Electronic Records and Information Capture Architecture (ERICA) database. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Minor

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2007-03-12

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Minor

Deployment Efficiency and Barrier Effectiveness Testing of a Temporary Anti-Personnel (TAP) Barrier System.

Energy Technology Data Exchange (ETDEWEB)

Allen, David James [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hedrick, Charles D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Martinez, Ruben [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-02-01

This report documents tests conducted by Sandia National Laboratories (SNL) on behalf of the U.S. Department of State to evaluate a temporary anti-personnel (TAP) barrier system developed by Mitigation Technologies. For this, the SNL Denial and Structural Assessment department developed a test protocol for the evaluation of the TAP barrier system on the basis of deployment efficiency and barrier effectiveness against a riotous/mob attack threat. The test protocol was then executed by SNL personnel and the results of the testing are documented.

The dielectric track and thermoluminescent detectors applied to neutron dosimetry in personnel monitoring

International Nuclear Information System (INIS)

Mebhah, D.

1984-03-01

The personnal dosimeter for neutron based on the detection of fission fragments from 237 Np and 232 Th by a polycarbonate 10 gm, and lithium fluorite 6 LIF/ 7 LIF, allow to cover an energy spectrum from 0.05 eV to 14 MeV with a easy neutron gamma discrimination. In criticality dosimetry, the energy spectrum of the incident neutrons can be defined by two components: the fast component by E b exp(-ae) with E between 0.1 and 14 MeV, a and b determined by a combination of 237 Np and 232 Th track detector responses, and the epithermal component in 1/E, the thermal component having a minor contribution to the total equivalent dose. We took into account the body influence on the detectors response by introducing effective cross section. The equivalent dose obtained by this dosimeter is 20% overestimated in low doses dosimetry. The interpretation of the detectors responses is based on the definition of a factor and a calibration parameter for each zone in which the spectrum is constant. The knowledge of this parameter for individual dosimeters allows to account for the variations of the conditions of calibration

Training and certification of personnel who perform in-place filter tests at nuclear facilities

International Nuclear Information System (INIS)

First, M.W.

1977-01-01

Preoperational testing and periodic retesting of high efficiency filtration systems installed at nuclear facilities are well-accepted safety procedures and are a requirement of regulatory agencies. In-Place Filter Testing Workshops, conducted periodically by the Harvard Air Cleaning Laboratory, provide the only available organized instructional programs for training testing personnel and supervisors. The curriculum, of one week duration, consists of approximately equal parts devoted to classroom theory and to 'hands-on' practice in the Laboratory. The current curriculum will be outlined for purposes of discussion. Many testing personnel who have had no formal instruction in this technology are actively engaged in this activity. Therefore, steps are underway to organize a certifying body and to introduce certification as an essential qualifying step for personnel engaged in this activity. Current progress toward certification requirements and examination procedures will be reviewed for purposes of discussion

The application of an automated thermoluminescence dosimetry system to environmental γ-dosimetry

International Nuclear Information System (INIS)

Jones, A.R.

1977-07-01

A personnel monitoring system comprising thermoluminescent dosimeters (TLDs) and an automatic TLD reader has been applied to environmental gamma dosimetry. For this purpose the accuracy of measurement at low exposures (10 to 100 mR) acquired over long periods (3 or 12 months) is important. To improve the accuracy and reliability of the system for this application the following steps were taken: the dosimeters were sensitized by irradiation with γ-rays and annealed while being irradiated with UV light; the sensitivity of each, identified dosimeter was measured and used to correct exposure measurements; the gasketted holders were modified to contain TLDs mounted on two identified plaques. Measurements of linearity, variability (with and without individual calibration) fading and energy dependence are presented. (author)

Design characteristics of a three-component AEOI Neutriran Albedo Neutron Personnel Dosimeter

International Nuclear Information System (INIS)

Sohrabi, M.; Katouzi, M.

1991-01-01

In establishing a national personnel neutron dosimetry service in Iran, different parameters of the AEOI Neutriran Albedo Neutron Personnel Dosimeter (NANPD) have been optimized. A NANPD was designed with three dosimetry components to measure (a) direct thermal neutrons, (b) direct fast neutrons and (C) direct neutrons by the detection of the albedo neutrons reflected from the body. The dosimeter consists of one or more Lexan polycarbonate and/or CR-39 foils and two 10 B (n,α) 7 Li converters in a cadmium cover so arranged as to efficiently measure the three neutron dose components separately. The boron converter thickness, its position relative to the beam direction and its distance from the PC foil were studied and the results were incorporated into the design. The dose response of the dosimeter, its lower detection limit as well as the correction factors related to the field neutrons and albedo neutrons were also determined for a 238 Pu-Be, an 241 Am-Be and a 252 Cf sources. In this paper, the dosimeter design and its dosimetric characteristics are presented and discussed. (author)

Personnel dosimetry in internal radiation exposure by excretory radionuclide measurement

International Nuclear Information System (INIS)

Balonov, M.I.; Bruk, G.Ya.; Korelina, N.F.; Likhtarev, I.A.; Repin, V.S.

1986-01-01

The collaboration with the SAAS resulted in the development of a mathematical method to calculate radiation doses in human tissues attributed to inhaled radionuclides concerning their retention dynamics in the respiratory system and their uptake into the blood as well as the metabolic pathways in the organs. 'Sanep-stations' and radiation protection service elaborated nomograms for the determination of the commitment doses in the critical organs based on the radionuclide content of a 24-hours urinalysis without intermediate calculations. Recommendations for the use of the method and the nomograms for various radionuclides (solubility classes D and N with MAAD of 1 and 10 μm) are given in the methodological document: 'Indirect dosimetry of inhaled radionuclides in workers'. A calculation method for the annual dose of internal irradiation in tritium workers is also cited

Chemical dosimetry principles in high dose dosimetry

International Nuclear Information System (INIS)

Mhatre, Sachin G.V.

2016-01-01

In radiation processing, activities of principal concern are process validation and process control. The objective of such formalized procedures is to establish documentary evidence that the irradiation process has achieved the desired results. The key element of such activities is inevitably a well characterized reliable dosimetry system that is traceable to recognized national and international dosimetry standards. Only such dosimetry systems can help establish the required documentary evidence. In addition, industrial radiation processing such as irradiation of foodstuffs and sterilization of health careproducts are both highly regulated, in particular with regard to dose. Besides, dosimetry is necessary for scaling up processes from the research level to the industrial level. Thus, accurate dosimetry is indispensable

Experience from cooperation of medical surveillance personnel and hygiene services in North Moravian Region

International Nuclear Information System (INIS)

Hillova, J.

1988-01-01

Surveillance in health car institutions with sources of ionizing radiation is discussed. A special group of workers who sat for examinations and were trained in special courses was selected. A number of special publications are put out in the field of radiation protection. Surveillance personnel visit the individual workplaces and point out any shortcomings in the observance of radiation protection principles. Demonstration dosimetry is carried out in the vicinity of radiation sources. Attention is also devoted to radiation technology, and significant exposures of personnel are examined. Also mentioned are the problems of radiaton protection in the region and possible improvement of the work of surveillance personnel. (M.D.)

A quality control program for the thermoluminescence dosimeter (TLD) in personnel radiation monitoring

International Nuclear Information System (INIS)

Seo, Kyung Won; Kim, Jang Lyul; Lee, Sang Yoon; Lee, Hyung Sub

1994-01-01

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 ministry of science and technology (MOST) issued a ministerial ordinance (No 199-15) about the technical criteria on personnel dosimeter processors on 1992. The purpose of this quality control program is to prescribe the procedures approved by the management of KAERI for implementing a quality badge service by means of TLD for personnel working in an area where they may be exposed to ionization radiation. (Author) 10 refs

How good is the education of the test personnel in radiography?

International Nuclear Information System (INIS)

Pittlik, A.; Soelter, B.

1999-01-01

The education of the test personnel in Radiography intends to ensure the responsible use of radioactive sources by a high quality consciousness and a good technical knowledge. The German Society for Non-Destructive Testing (DGZfP) arranges relevant courses that are described in detail. (orig.) [de

100 years of solid state dosimetry and radiation protection dosimetry

International Nuclear Information System (INIS)

Bartlett, David T.

2008-01-01

The use of solid state detectors in radiation dosimetry has passed its 100th anniversary. The major applications of these detectors in radiation dosimetry have been in personal dosimetry, retrospective dosimetry, dating, medical dosimetry, the characterization of radiation fields, and also in microdosimetry and radiobiology research. In this introductory paper for the 15th International Conference, I shall speak of the history of solid state dosimetry and of the radiation measurement quantities that developed at the same time, mention some landmark developments in detectors and applications, speak a bit more about dosimetry and measurement quantities, and briefly look at the past and future

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

International Nuclear Information System (INIS)

Ma, N.

2006-01-01

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

Specification ''I'' of the CEFRI concerning the interim job enterprises proposing personnel of A or B category to work in nuclear facilities

CERN Document Server

Int. At. Energy Agency Wien

2002-01-01

This document aims to specify the organization dispositions which have to bee taken by the interim job enterprises proposing personnel of A or B category to work in nuclear facilities. These dispositions should allow to respect the demands of the CEFRI in matter of formation, medical control and personnel dosimetry. (A.L.B.)

Standardized physics-dosimetry for US pressure vessel cavity surveillance programs

International Nuclear Information System (INIS)

Ruddy, F.H.; McElroy, W.N.; Lippincott, E.P.

1984-01-01

Standardized Physics-Dosimetry procedures and data are being developed and tested for monitoring the neutron doses accumulated by reactor pressure vessels (PV) and their support structures. These procedures and data are governed by a set of 21 ASTM standard practices, guides, and methods for the prediction of neutron-induced changes in light water reactor (LWR) PVs and support structure steels throughout the service life of the PV. This paper summarizes the applications of these standards to define the selection and deployment of recommended dosimetry sets, the selection of dosimetry capsules and thermal neutron shields, the placement of dosimetry, the methods of measurement of dosimetry sensor reaction products, data analysis procedures, and uncertainty evaluation procedures. It also describes the validation of these standards both by in-reactor testing of advanced PV cavity surveillance physics-dosimetry and by data development. The use of these standards to guide selection and deployment of advanced dosimetry sets for commercial reactors is also summarized

New solid-state effects used in neutron detection and dosimetry. 1

International Nuclear Information System (INIS)

Doerschel, B.; Hahn, G.

1981-01-01

A review is given of radiation effects on solids and their usability for personnel neutron dosimetry. Part 1 covers mechanical effects on the crystal lattice of solids (dislocations in copper foils and changes in the bulk modulus, unclear effects in quartz connected with changes in the oscillation frequency), thermal effects of metals embedded in type I superconductors (superheated colloid detectors) or other materials (superheated drop detectors)

Energy dependence of fast neutron dosimetry using electrochemical etching

International Nuclear Information System (INIS)

Su, S.J.; Morgan, K.Z.

1978-01-01

Registration of fast-neutron induced recoil tracks by the electrochemical etching technique as applied to sensitive Lexan polycarbonate foils provides a simple and inexpensive means of fast neutron personnel dosimetry. The sensitivity (tracks/neutron) of recoil particle registration is given as a function of neutron energy. Neutrons of 7 Li (p,n) 7 Be, 3 T (d,n) 4 He and 9 B, respectively. Results are compared with other studies using other neutron sources and conventional etching method

A personnel TLD system with person identification

International Nuclear Information System (INIS)

Widell, C.O.

1974-01-01

The TLD system uses Li 2 B 4 O 7 :Mn, Si sintered tablets which are heated by hot nitrogen. The slide which holds the tablets is coded by a self adhesive polyester-aluminium tape. This tape is BCD coded in an ordinary tape punch. The information on the punched tape includes a ten digit social-security number and a two digit information on location and type of dosimetry. By this system dosimetric data is directly transfered into a central dose register for Sweden. All personnel doses are there stored on social-security numbers. (author)

Personnel neutron dosimetry using TLD elements at PNC

International Nuclear Information System (INIS)

Ishiguro, Hideharu

1985-01-01

The evaluation method of neutron dose equivalent was studied on the basis of the albedo type neutron dosimetory to design the personnel dosimeter. The dosimeter was composed of three 6 Li 2 10 B 4 O 7 (Cu) TL elements and one 7 Li 2 11 B 4 O 7 (Cu) element. The equations for assessing thermal, epithermal and fast neutron dose equivalents were derived by 252 Cf, 241 Am-Be and PuO 2 neutron sources. The minimum detectable amount of 6 Li 2 10 B 4 O 7 (Cu) element to thermal neutron was 0.02 m rem. The neutron dose equivalent and the gamma one were evaluated separately within about 20 % error in the mixed radiation field. (author)

Evaluation of the external radiation exposure dosimetry and calculation of maximum permissible concentration values for airborne materials containing 18F, 15O, 13N, 11C and 133Xe

International Nuclear Information System (INIS)

Piltingsrud, H.V.; Gels, G.L.

1985-01-01

To better understand the dose equivalent (D.E.) rates produced by airborne releases of gaseous positron-emitting radionuclides under various conditions of cloud size, a study of the external radiation exposure dosimetry of these radionuclides, as well as negatron, gamma and x-ray emitting 133Xe, was undertaken. This included a calculation of the contributions to D.E. as a function of cloud radii, at tissue depths of 0.07 mm (skin), 3 mm (lens of eye) and 10 mm (whole body) from both the particulate and photon radiations emitted by these radionuclides. Estimates of maximum permissible concentration (MPC) values were also calculated based on the calculated D.E. rates and current regulations for personnel radiation protection (CFR84). Three continuous air monitors, designed for use with 133Xe, were evaluated for applications in monitoring air concentrations of the selected positron emitters. The results indicate that for a given radionuclide and for a cloud greater than a certain radius, personnel radiation dosimeters must respond acceptably to only the photon radiations emitted by the radionuclide to provide acceptable personnel dosimetry. For clouds under that radius, personnel radiation dosimeters must also respond acceptably to the positron or negatron radiations to provide acceptable personnel dosimetry. It was found that two out of the three air concentration monitors may be useful for monitoring air concentrations of the selected positron emitters

Radiation dosimetry and standards at the austrian dosimetry laboratory

International Nuclear Information System (INIS)

Leitner, A.

1984-10-01

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 60 Co teletherapy unit, a circular exposure system for routine batch calibration of personnel dosemeters with four gamma ray sources ( 60 Co and 137 Cs) and a reference source system with six gamma ray sources ( 60 Co and 137 Cs). In addition a set of calibrated beta ray sources are provided ( 147 Pm, 204 Tl and 90 Sr). 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 137 Cs and 60 Co 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)

Three new projects for the CERN Dosimetry Service

CERN Multimedia

CERN Bulletin

2011-01-01

The measures for the protection of personnel against ionising radiation at CERN are very strict. As soon as a new directive is issued by EURATOM, the Laboratory ensures it is adopted quickly. Since every system can be perfected, Pierre Carbonez and the Dosimetry Service team are working on three new projects aimed at improving the safety of workers exposed to ionising radiation in the course of their work on the CERN sites.       The two types of dosimeters currently in use at CERN. 4,700 people at CERN have a dosimeter. Every month, they have to have their dosimeter scanned by one of the 45 readers installed at various strategic locations around the Laboratory. Each month, the dosimetry team led by Pierre Carbonez exchanges around 450 dosimeters to recalibrate them and prepare them for further use. “These dosimeters are passive detectors which record the doses caused by beta, gamma and neutron radiation," explains Pierre Carbonez. &a...

Thermocurrent dosimetry with high purity aluminum oxide

Energy Technology Data Exchange (ETDEWEB)

Fullerton, G.D.; Cameron, J.R.; Moran, P.R.

1976-01-01

The application of thermocurrent (TC) to ionizing radiation dosimetry was studied. It was shown that TC in alumina (Al/sub 2/O/sub 3/) has properties that are suited to personnel dosimetry and environmental monitoring. TC dosimeters were made from thin disks of alumina. Aluminum electrodes were evaporated on each side: on one face a high voltage electrode and on the opposite face a measuring electrode encircled by a guard ring. Exposure to ionizing radiation resulted in stored electrons and holes in metastable trapping sites. The signal was read-out by heating the dosimeter with a voltage source and picnometer connected in series between the opposite electrodes. The thermally remobilized charge caused a transient TC. The thermogram, TC versus time or temperature, is similar to a TL glow curve. Either the peak current or the integrated current is a measure of absorbed dose. Six grades of alumina were studied from a total of four commercial suppliers. All six materials displayed radiation induced TC signals. Sapphire of uv-grade quality from the Adolf Meller Co. (AM) had the best dosimetry properties of those investigated. Sources of interference were studied. Thermal fading, residual signal and radiation damage do not limit TC dosimetry. Ultraviolet light can induce a TC response but it is readily excluded with uv-opaque cladding. Improper surface preparation prior to electrode evaporation was shown to cause interference. A spurious TC signal resulted from polarization of surface contaminants. Spurious TC was reduced by improved cleaning prior to electrode application. Polished surfaces resulted in blocking electrodes and caused a sensitivity shift due to radiation induced thermally activated polarization. This was not observed with rough cut surfaces.

Thermocurrent dosimetry with high purity aluminum oxide

International Nuclear Information System (INIS)

Fullerton, G.D.; Cameron, J.R.; Moran, P.R.

1976-01-01

The application of thermocurrent (TC) to ionizing radiation dosimetry was studied. It was shown that TC in alumina (Al 2 O 3 ) has properties that are suited to personnel dosimetry and environmental monitoring. TC dosimeters were made from thin disks of alumina. Aluminum electrodes were evaporated on each side: on one face a high voltage electrode and on the opposite face a measuring electrode encircled by a guard ring. Exposure to ionizing radiation resulted in stored electrons and holes in metastable trapping sites. The signal was read-out by heating the dosimeter with a voltage source and picnometer connected in series between the opposite electrodes. The thermally remobilized charge caused a transient TC. The thermogram, TC versus time or temperature, is similar to a TL glow curve. Either the peak current or the integrated current is a measure of absorbed dose. Six grades of alumina were studied from a total of four commercial suppliers. All six materials displayed radiation induced TC signals. Sapphire of uv-grade quality from the Adolf Meller Co. (AM) had the best dosimetry properties of those investigated. Sources of interference were studied. Thermal fading, residual signal and radiation damage do not limit TC dosimetry. Ultraviolet light can induce a TC response but it is readily excluded with uv-opaque cladding. Improper surface preparation prior to electrode evaporation was shown to cause interference. A spurious TC signal resulted from polarization of surface contaminants. Spurious TC was reduced by improved cleaning prior to electrode application. Polished surfaces resulted in blocking electrodes and caused a sensitivity shift due to radiation induced thermally activated polarization. This was not observed with rough cut surfaces

The method validation step of biological dosimetry accreditation process

International Nuclear Information System (INIS)

Roy, L.; Voisin, P.A.; Guillou, A.C.; Busset, A.; Gregoire, E.; Buard, V.; Delbos, M.; Voisin, Ph.

2006-01-01

One of the missions of the Laboratory of Biological Dosimetry (L.D.B.) of the Institute for Radiation and Nuclear Safety (I.R.S.N.) is to assess the radiological dose after an accidental overexposure suspicion to ionising radiation, by using radio-induced changes of some biological parameters. The 'gold standard' is the yield of dicentrics observed in patients lymphocytes, and this yield is converted in dose using dose effect relationships. This method is complementary to clinical and physical dosimetry, for medical team in charge of the patients. To obtain a formal recognition of its operational activity, the laboratory decided three years ago, to require an accreditation, by following the recommendations of both 17025 General Requirements for the Competence of Testing and Calibration Laboratories and 19238 Performance criteria for service laboratories performing biological dosimetry by cyto-genetics. Diagnostics, risks analysis were realized to control the whole analysis process leading to documents writing. Purchases, personnel department, vocational training were also included in the quality system. Audits were very helpful to improve the quality system. One specificity of this technique is that it is not normalized therefore apart from quality management aspects, several technical points needed some validations. An inventory of potentially influent factors was carried out. To estimate their real effect on the yield of dicentrics, a Placket-Burman experimental design was conducted. The effect of seven parameters was tested: the BUdr (bromodeoxyuridine), PHA (phytohemagglutinin) and colcemid concentration, the culture duration, the incubator temperature, the blood volume and the medium volume. The chosen values were calculated according to the uncertainties on the way they were measured i.e. pipettes, thermometers, test tubes. None of the factors has a significant impact on the yield of dicentrics. Therefore the uncertainty linked to their use was considered as

The method validation step of biological dosimetry accreditation process

Energy Technology Data Exchange (ETDEWEB)

Roy, L.; Voisin, P.A.; Guillou, A.C.; Busset, A.; Gregoire, E.; Buard, V.; Delbos, M.; Voisin, Ph. [Institut de Radioprotection et de Surete Nucleaire, LDB, 92 - Fontenay aux Roses (France)

2006-07-01

One of the missions of the Laboratory of Biological Dosimetry (L.D.B.) of the Institute for Radiation and Nuclear Safety (I.R.S.N.) is to assess the radiological dose after an accidental overexposure suspicion to ionising radiation, by using radio-induced changes of some biological parameters. The 'gold standard' is the yield of dicentrics observed in patients lymphocytes, and this yield is converted in dose using dose effect relationships. This method is complementary to clinical and physical dosimetry, for medical team in charge of the patients. To obtain a formal recognition of its operational activity, the laboratory decided three years ago, to require an accreditation, by following the recommendations of both 17025 General Requirements for the Competence of Testing and Calibration Laboratories and 19238 Performance criteria for service laboratories performing biological dosimetry by cyto-genetics. Diagnostics, risks analysis were realized to control the whole analysis process leading to documents writing. Purchases, personnel department, vocational training were also included in the quality system. Audits were very helpful to improve the quality system. One specificity of this technique is that it is not normalized therefore apart from quality management aspects, several technical points needed some validations. An inventory of potentially influent factors was carried out. To estimate their real effect on the yield of dicentrics, a Placket-Burman experimental design was conducted. The effect of seven parameters was tested: the BUdr (bromodeoxyuridine), PHA (phytohemagglutinin) and colcemid concentration, the culture duration, the incubator temperature, the blood volume and the medium volume. The chosen values were calculated according to the uncertainties on the way they were measured i.e. pipettes, thermometers, test tubes. None of the factors has a significant impact on the yield of dicentrics. Therefore the uncertainty linked to their use was

Dosimetry

International Nuclear Information System (INIS)

Anon.

1990-01-01

The purpose of ionizing radiation dosimetry is the measurement of the physical and biological consequences of exposure to radiation. As these consequences are proportional to the local absorption of energy, the dosimetry of ionizing radiation is based on the measurement of this quantity. Owing to the size of the effects of ionizing radiation on materials in all of these area, dosimetry plays an essential role in the prevention and the control of radiation exposure. Its use is of great importance in two areas in particular where the employment of ionizing radiation relates to human health: radiation protection, and medical applications. Dosimetry is different for various reasons: owing to the diversity of the physical characteristics produced by different kinds of radiation according to their nature (X- and γ-photons, electrons, neutrons,...), their energy (from several keV to several MeV), the orders of magnitude of the doses being estimated (a factor of about 10 5 between diagnostic and therapeutic applications); and the temporal and spatial variation of the biological parameters entering into the calculations. On the practical level, dosimetry poses two distinct yet closely related problems: the determination of the absorbed dose received by a subject exposed to radiation from a source external to his body (external dosimetry); and the determination of the absorbed dose received by a subject owing to the presence within his body of some radioactive substance (internal dosimetry)

Standardized physics-dosimetry for US pressure vessel cavity surveillance programs

International Nuclear Information System (INIS)

Ruddy, F.H.; McElroy, W.N.; Lippincott, E.P.

1984-01-01

This paper summarizes the applications of ASTM standard methods, guides and practices to define the selection and deployment of recommended dosimetry sets, the selection of dosimetry capsules and thermal neutron shields, the placement of dosimetry, the methods of measurement of dosimetry sensor reaction products, data analysis procedures, and uncertainty evaluation procedures. It also describes the validation of these standards both by in-reactor testing of advanced PV cavity surveillance physics-dosimetry and by data development. The use of these standards to guide selection and development of advanced dosimetry sets for commercial reactors is also summarized. (Auth.)

Test of an albedo neutron dosimetry system: TLD calibration and readout procedure, neutron calibration, dosimetry properties, routine application

International Nuclear Information System (INIS)

Piesch, E.; Burgkhardt, B.

1988-03-01

The two-component albedo dosemeter in use consists of an universal boron-loaded plastic encapsulation, the beta and albedo neutron windows of which are adopted to the corresponding TLD system of the manufacturers Alnor, Harshaw, Panasonic and Vinten. Beside the TLD detectors the capsule may contain also track etch detectors. Within a BMU project the system was investigated by four governmental measurement services in the FRG with respect to its qualification for personnel monitoring with emphasis in the readout and calibration procedures for the TLD system, the evaluation technique for the estimation of the photon and neutron dose equivalent in routine monitoring and the calibration of the personnel dosemeter in stray neutron fields. The test has shown the readiness of the system to act in the application areas of nuclear power reactors and linacs behind heavy shieldings, in the fuel element cycle, use of fissile materials, criticality, use of radionuclide sources, high energy particle accelerators. The uncertainty due to energy dependence was found to be within a factor of 2 for a single application area. In the case of irradiations from the front half space the dose equivalent H'(10) is indicated sufficiently independent of the direction of the radiation incidence. After completion of the test the albedo dosemeter became the official neutron personnel dosemeter in the FRG. It allows the separate estimation of the dose equivalent of hard beta radiation, photon radiation and neutrons. (orig./HP) [de

The accreditation programs and proficiency test in Taiwan for personnel dosimeter services (1991-1998)

International Nuclear Information System (INIS)

Lee, B.T.; Hwang, W.S.; Su, S.H.

2000-01-01

According to the ionizing radiation safety regulation approved by the ROC Atomic Energy Council (AEC), personnel dosimeter processors shall be accredited by the Chinese National Laboratory Accreditation (CNLA) program before offering dosimeter services and shall be accredited every two years (now has been rescheduled to be every three years since 1996). The aim of this program is to secure quality and technical capability of personnel dosimeters, and to provide systematic improvement for the internal calibration and testing laboratory applying for accreditation by means of assessment procedures. The criteria used to evaluate the capability at laboratories are ISO/IEC 25 (1990) and technical guide in different accreditation fields. The Institute of Nuclear Energy Research (INER) was entrusted by CNLA as the central laboratory to perform the proficiency test of personnel dosimeters for laboratory accreditation in December 1990. Such proficiency tests, based on ANSI N13.11 (1983), which is mainly separated to accident categories and protection categories which consists of eight parts of tests including single and mixture radiation of x-ray, gamma, beta and neutron, have been conducted four times, in 1991, 1993, 1995 and 1998. This paper deals with the test procedures and results of proficiency tests of personnel dosimeters from 1991 until 1998. The results of the four proficiency tests showed that, for accident categories, the pass rate is about 91%; for protection categories, the pass rate is about 98%. Meanwhile, the central laboratory will adopt a new version of HPS N13.11 (1993) to replace ANSI N13.11 (1983) as new criteria for the next proficiency test to be conducted in 2001. (author)

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

Qualification tests for shift personnel in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Fechner, J B [Bundesministerium des Innern, Bonn (Germany, F.R.)

1978-02-01

The selection of personnel for training as shift supervisors or reactor operators so far used to be made by a plant operator mainly on the basis of such criteria as examinations, diplomas and other documents verifying the educational background, the type of activity exercised, and professional success. In addition, there are the opininons of trainers and supervisors based on personal observation of future shift personnel on training for specific plants at a training center, at the manufacturer's, the operator's or in activities in the construction and commissioning of the respective nuclear power plant. In the course of this phase, which normally takes several years, supervisors asses not only the professional capabilities of a trainee, but also bis psychic and physical performance and aptitude, e.g., with respect to decision making, leadership qualifications or behavior unter stress. The advisability of introducing psychological aptitude tests was also studied. However, a decision was recently taken to defer such psychological tests for the time being. Yet, nuclear power plant operators are required to submit a statement to their responsible authorities about industrial medical checkups and qualification assessments by supervisors.

Qualification tests for shift personnel in nuclear power plants

International Nuclear Information System (INIS)

Fechner, J.B.

1978-01-01

The selection of personnel for training as shift supervisors or reactor operators so far used to be made by a plant operator mainly on the basis of such criteria as examinations, diplomas and other documents verifying the educational background, the type of activity exercised, and professional success. In addition, there are the opininons of trainers and supervisors based on personal observation of future shift personnel on training for specific plants at a training center, at the manufacturer's, the operator's or in activities in the construction and commissioning of the respective nuclear power plant. In the course of this phase, which normally takes several years, supervisors asses not only the professional capabilities of a trainee, but also bis psychic and physical performance and aptitude, e.g., with respect to decision making, leadership qualifications or behavior unter stress. The advisability of introducing psychological aptitude tests was also studied. However, a decision was recently taken to defer such psychological tests for the time being. Yet, nuclear power plant operators are required to submit a statement to their responsible authorities about industrial medical checkups and qualification assessments by supervisors. (orig.) [de

Radiochromic film calibration for dosimetry in computed tomography tests

International Nuclear Information System (INIS)

Costa, K. C.; Prata M, A.; Ladino G, A. M.; Costa, K. L.

2017-10-01

Radiochromic film applications in dosimetry have become increasingly significant for studies on radiotherapy and diagnostic tests. Due to sensitivity to exposure to ionizing radiation, radiochromic films are commonly used to obtain dose distribution maps. The objective of this study is to obtain the calibration curves of the radiographic film for exposure with X-ray beam in a computerized tomography (CT) scanner to realize measures of typical doses found in radiodiagnosis tests. It was used Gafchromic Xr-AQ2 film, which shows little sensitivity to visible light and a response in the range of 0.1 to 20 Gy for X-ray beam in a tube voltage supply range ranging from 20 kV to 200 kV. In the experiments, a head polymethylmethacrylate (PMMA) phantom, with a cylindrical shape with five openings was used. This phantom was placed in the CT scanner isocenter and radiochromic film strips were placed into two openings. The irradiations were performed in a Toshiba Asteion scanner that allows making acquisitions in helical mode. The central slice of the head phantom was irradiated to obtain the values of air kerma in PMMA measured with a pencil ionization chamber. Thereafter, radiochromic film strips were placed into the central and one peripheral opening and 10 cm long scans of the central region of the phantom were carried out with feed voltage of 120 kV. The strips irradiated with different X-ray tube currents were scanned and processed using the ImageJ software to obtain the intensity values resulting from the absorbed radiation by optical density analysis. The calibration curves were obtained for both region, central and peripheral corresponding to the values of air kerma in PMMA measured with ionization chamber. With the curves in hand, CT experiments with applied beams can use radiochromic films as a dosimetry method and then seek the generation of images with lower dose deposition and higher diagnostic quality. (Author)

Radiochromic film calibration for dosimetry in computed tomography tests

Energy Technology Data Exchange (ETDEWEB)

Costa, K. C.; Prata M, A. [Federal Center for Technological Education of Minas Gerais, Biomedical Engineering Center, Av. Amazonas 5253, Nova Suica, 30421-169 Belo Horizonte, Minas Gerais (Brazil); Ladino G, A. M. [Federal University of Minas Gerais, Department of Nuclear Engineering, Av. Antonio Carlos 6627, Pampulha, 31270-90 Belo Horizonte, Minas Gerais (Brazil); Costa, K. L., E-mail: apratabhz@gmail.com [University of Itauna, Medicine Department, Rodovia Mg 431 Km 45 s/n, El Dorado, 35680-142 Itauna, Minas Gerais (Brazil)

2017-10-15

Radiochromic film applications in dosimetry have become increasingly significant for studies on radiotherapy and diagnostic tests. Due to sensitivity to exposure to ionizing radiation, radiochromic films are commonly used to obtain dose distribution maps. The objective of this study is to obtain the calibration curves of the radiographic film for exposure with X-ray beam in a computerized tomography (CT) scanner to realize measures of typical doses found in radiodiagnosis tests. It was used Gafchromic Xr-AQ2 film, which shows little sensitivity to visible light and a response in the range of 0.1 to 20 Gy for X-ray beam in a tube voltage supply range ranging from 20 kV to 200 kV. In the experiments, a head polymethylmethacrylate (PMMA) phantom, with a cylindrical shape with five openings was used. This phantom was placed in the CT scanner isocenter and radiochromic film strips were placed into two openings. The irradiations were performed in a Toshiba Asteion scanner that allows making acquisitions in helical mode. The central slice of the head phantom was irradiated to obtain the values of air kerma in PMMA measured with a pencil ionization chamber. Thereafter, radiochromic film strips were placed into the central and one peripheral opening and 10 cm long scans of the central region of the phantom were carried out with feed voltage of 120 kV. The strips irradiated with different X-ray tube currents were scanned and processed using the ImageJ software to obtain the intensity values resulting from the absorbed radiation by optical density analysis. The calibration curves were obtained for both region, central and peripheral corresponding to the values of air kerma in PMMA measured with ionization chamber. With the curves in hand, CT experiments with applied beams can use radiochromic films as a dosimetry method and then seek the generation of images with lower dose deposition and higher diagnostic quality. (Author)

Image in nuclear dosimetry using thermoluminescent dosimetry

International Nuclear Information System (INIS)

Guinsburg, G.; Matsuoka, M.; Watanabe, S.

1987-01-01

A low cost methodology to produce images of internal sick organs by radioisotopic intake, is presented. Dosimetries of thermoluminescent material and Teflon (ratio:50%) in bidimensional matrix shape are used with a Pb collimator. This collimator-bidimensional matrix system was tested ''in vivo'' and in thyroid phantoms using 99m Tc. A comparative evaluation between this method and the scintigraphy one is presented. (M.A.C.) [pt

A system for personnel qualification of non-destructive testing procedures from testing and and qualification system in Sweden

International Nuclear Information System (INIS)

Kuna, M.; Kubis, S.; Plasek, J.

1999-01-01

The method for qualification of non-destructive testing personnel carrying out inspections by means of ultrasonic and eddy-current tests to inspect cladding in BWR reactor pressure vessel and core shroud lid. Development of procedures tests with real artificial cracks, blind tests. Evaluation of results by the Swedish Qualification Commission. Performance of the tests at Oskarshamn-1

Development of Chinese Military Personnel Social Support Scale and tests for its reliability and validity

Directory of Open Access Journals (Sweden)

Kai-hong TANG

2013-01-01

Full Text Available Objective 　To develop Chinese Military Personnel Social Support Scaleand verify its reliability and validity. Methods 　The Chinese Military Personnel Social Support Scalewas initiated, organized and compiled based upon open-ended questionnaire survey done in a systematic manner, and previous researches were taken as references. A total of 630 military personnel were chosen by random cluster sampling and tested with the Scale, among them 50 were tested with Social Support Rating Scale(SSRS and Chinese Military Psychosomatic Health Scale(CMPHS simultaneously, and the test was done solely a second time with CMPHS 2 weeks later. The reliability and validity were assessed and verified by exploratory factor analysis, confirmatory factor analysis and correlation analysis. Results 　The Chinese Military Personnel Social Support Scalecomprised three factors, namely subjective support, objective support and utility of social support. Eighteen items were left in official scale after amendment by factor analysis, and one lying subscale was added. The correlation coefficients between the public factors ranged from 0.477 to 0.589 (P<0.01, and the correlation coefficients between factors and total scale ranged from 0.721 to 0.823 (P<0.01. The test-retest correlation coefficients of total scale and subscales ranged from 0.622 to 0.803 (P<0.01, the Cronbach α coefficients ranged from 0.624 to 0.874, and the split-half correlation coefficients ranged from 0.551 to 0.828. Significant correlation existed between this Scale and two criterion scales, namely SSRS and CMPHS. Conclusion 　It is verified that the Chinese Military Personnel Social Support Scalehas excellent reliability and validity, and complying with psychometric standards, it may be used to evaluate the social support level of Chinese military personnel.

Qualification of nuclear power plant inspection, examination, and testing personnel. Revision 1, September 1980

International Nuclear Information System (INIS)

Anon.

1981-01-01

Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, requires that the quality assurance program provide for indoctrination and training of personnel performing activities affecting quality as necessary to ensure that quality assurance personnel achieve and maintain suitable proficiency. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification of inspection, examination, and testing personnel for all types of nuclear power plants

Storage of radioactive material - accidents - precipitation - personnel monitoring; Stokiranje radioaktivnih materijala - akcidenti - padavine - kontrola osoblja

Energy Technology Data Exchange (ETDEWEB)

Matijasic, A; Gacinovic, O [Institute of Nuclear Sciences Boris Kidric, Radioloska zastita, Vinca, Beograd (Serbia and Montenegro)

1961-12-15

This volume covers the reports on four routine tasks concerned with safe handling of radioactive material and influence of nuclear facilities on the environment. The tasks performed were as follows: Storage of solid and liquid radioactive material; actions in case of accidents; radiation monitoring of the fallout, water and ground; personnel dosimetry.

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)

Individual monitoring of medical staff working in interventional radiology in Switzerland using double dosimetry

International Nuclear Information System (INIS)

Damet, J.; Bailat, C.; Bize, P.; Buchillier, Th.; Tosic, M.; Verdun, F.R.; Baechler, S.

2011-01-01

Physicians who frequently perform fluoroscopic examinations are exposed to high intensity radiation fields. The exposure monitoring is performed with a regular personal dosimeter under the apron in order to estimate the effective dose. However, large parts of the body are not protected by the apron (e.g. arms, head). Therefore, it is recommended to wear a supplemental dosimeter over the apron to obtain a better representative estimate of the effective dose. The over-apron dosimeter can also be used to estimate the eye lens dose. The goal of this study was to investigate the relevance of double dosimetry in interventional radiology. First the calibration procedure of the dosimeters placed over the apron was tested. Then, results of double dosimetry during the last five years were analyzed. We found that the personal dose equivalent measured over a lead apron was underestimated by ∼20% to ∼40% for X-ray beam qualities used in radiology. Measurements made over five-year period confirm that the use of a single under-apron dosimeter is inadequate for personnel monitoring. Relatively high skin dose (>10 mSv/month) would have remained undetected without a second dosimeter placed on the apron.

Analysis of quality control tests done by the Canadian power utilities on their external dosimetry systems (June 1988 to May 1993)

International Nuclear Information System (INIS)

Butt, K.A.; Poirier, G.S.

1995-09-01

The Canadian nuclear power utilities, Hydro-Quebec, New Brunswick Electric Power Commission and Ontario Hydro, use thermoluminescent dosimetry systems to perform their own external beta/gamma dosimetry. In order to help ensure that these systems perform satisfactorily, they are subjected to routine quality control testing by their parent organizations. The test results for the period of June 1988 to May 1993 have been analyzed, at the Atomic Energy Control Board (AECB), using the pass criterion which was originally agreed upon the organizations involved and which is described in section 2.3 of this document. The present analysis offers an indication of the performance of the different sites which operate such a service. Comparisons are made each site's performance during the period June 1985 to May 1988 which has been summarized previously (INFO--0301). Finally, recommendations are made in the hope that they will help the organizations in refining their dosimetry. (author) 1 ref., 7 tabs

OSL Based Anthropomorphic Phantom and Real-Time Organ Dosimetry

Energy Technology Data Exchange (ETDEWEB)

David E. Hintenlang, Ph.D

2009-02-10

The overall objective of this project was the development of a dosimetry system that provides the direct measurement of organ does in real-time with a sensitivity that makes it an effective tool for applications in a wide variety of health physics applications. The system included the development of a real-time readout system for fiber optic coupled (FOC) dosimeters that is integrated with a state-of-art anthropomorphic phantom to provide instantaneous measures of organ doses throughout the phantom. The small size of the FOC detectors and optical fibers allow the sensitive volume of the detector to be located at organ centroids (or multiple locations distributed through the organ) within a tissue equivalent, anthropomorphic phantom without perturbing the tissue equivalent features of the phantom. The developed phantom/dosimetry system can be used in any environment where personnel may be exposed to gamma or x-ray radiations to provide the most accurate determinations of organ and effective doses possible to date.

OSL Based Anthropomorphic Phantom and Real-Time Organ Dosimetry

International Nuclear Information System (INIS)

Hintenlang, David E.

2009-01-01

The overall objective of this project was the development of a dosimetry system that provides the direct measurement of organ doses in real-time with a sensitivity that makes it an effective tool for applications in a wide variety of health physics applications. The system included the development of a real-time readout system for fiber optic coupled (FOC) dosimeters that is integrated with a state-of-art anthropomorphic phantom to provide instantaneous measures of organ doses throughout the phantom. The small size of the FOC detectors and optical fibers allow the sensitive volume of the detector to be located at organ centroids (or multiple locations distributed through the organ) within a tissue equivalent, anthropomorphic phantom without perturbing the tissue equivalent features of the phantom. The developed phantom/dosimetry system can be used in any environment where personnel may be exposed to gamma or x-ray radiations to provide the most accurate determinations of organ and effective doses possible to date

Status of neutron cross sections for reactor dosimetry

International Nuclear Information System (INIS)

Vlasov, M.F.; Fabry, A.; McElroy, W.N.

1977-03-01

The status of current international efforts to develop standardized sets of evaluated energy-dependent (differential) neutron cross sections for reactor dosimetry is reviewed. The status and availability of differential data are considered, some recent results of the data testing of the ENDF/B-IV dosimetry file using 252 Cf and 235 U benchmark reference neutron fields are presented, and a brief review is given of the current efforts to characterize and identify dosimetry benchmark radiation fields

The U.S. food and drug administration's dosimetry program

International Nuclear Information System (INIS)

Baratta, E.

2005-01-01

Full text: The U. S. Public Health Service's (PHS) Food and Drug Administration (FDA) (part of the PHS) has had a Dosimetry Program at the Winchester Engineering and Analytical Center (WEAC) (formerly the Northeastern Radiological Health Laboratory). This Dosimetry Program has been in place since 1961. In 1967 it was augmented by the construction of a Whole Body Counter at WEAC for measuring internal dose. The FDA's Center for Medical Devices and Radiological Health had been handling these dosimeters since 1961 and in 2000 the WEAC took over total responsibility for this program for the FDA's Office of Regulatory affairs. This program was originally setup for the radiation workers (analysts and support personnel) and later included investigators personnel working in the medical and dental x-ray field. The field laboratories began using radionuclides in 1972 and were also issued radiation dosimeters. Investigators station at border import station alter 2003 were issued as well as radiation pages as a precaution when checking imported food and other FDA regulated products. This paper will discuss the results of radiation exposure received by analyst (including whole body measurements) at WEAC and field laboratories. Also discussed will be exposures to investigators in the medical and dental field. The exposure to the investigators at the import border stations will be included even though they have not been carrying dosimeters for slightly more than a year. In general, the exposures have been well below the Nuclear Regulatory Commission regulations for radiation workers. (author)

Dosimetry program for characterization of the FMIT facility

International Nuclear Information System (INIS)

Gold, R.; McElroy, W.N.; Fuller, J.L.; Sheen, E.M.; Dierckx, R.

1979-01-01

The environmental characterization program for the Fusion Materials Irradiaton Test (FMIT) facility is presented. Requirements for the development and testing of Magnetic Fusion Energy (MFE) materials together with the complexity of the FMIT (d,Li) generated radiation field warrant a multifaceted dosimetric approach. Specific passive, active and calculational dosimetry efforts comprising this multifaceted approach are described. Special emphasis is given to those dosimetry capabilities uniquely required to characterize FMIT

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

International Nuclear Information System (INIS)

Deme, S.; Apathy, I.; Bodnar, L.; Csoke, A.; Feher, I.; Pazmandi, T.

2005-01-01

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)

Technical recommendations for the use of thermoluminescence for dosimetry in individual monitoring for photons and electrons from external sources

International Nuclear Information System (INIS)

1975-01-01

The principles of thermoluminescence dosimetry and the role it may play in the field of personnel dosimetry are presented. Technical recommendations are made as an indication of what is generally regarded as good practice and they are intended to be of assistance in avoiding the common sources of error. Errors due to: the detector; the evaluation procedure; the thermal treatment; at the sensitivity of the detector to neutrons. The recommendations are concerned with: the choice of detector material; design of thermoluminescent dosemeters; read-out procedure; reader; handling procedures; dose evaluations; automation; documentation and data handling

Internal Dosimetry for Nuclear Power Program

International Nuclear Information System (INIS)

Wo, Y.M.

2011-01-01

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)

Individual Dosimetry for High Energy Radiation Fields

International Nuclear Information System (INIS)

Spurny, F.

1999-01-01

The exposure of individuals on board aircraft increased interest in individual dosimetry in high energy radiation fields. These fields, both in the case of cosmic rays as primary radiation and at high energy particle accelerators are complex, with a large diversity of particle types, their energies, and linear energy transfer (LET). Several already existing individual dosemeters have been tested in such fields. For the component with high LET (mostly neutrons) etched track detectors were tested with and without fissile radiators, nuclear emulsions, bubble detectors for both types available and an albedo dosemeter. Individual dosimetry for the low LET component has been performed with thermoluminescent detectors (TLDs), photographic film dosemeters and two types of electronic individual dosemeters. It was found that individual dosimetry for the low LET component was satisfactory with the dosemeters tested. As far as the high LET component is concerned, there are problems with both the sensitivity and the energy response. (author)

Personal hygiene among military personnel: developing and testing a self-administered scale.

Science.gov (United States)

Saffari, Mohsen; Koenig, Harold G; Pakpour, Amir H; Sanaeinasab, Hormoz; Jahan, Hojat Rshidi; Sehlo, Mohammad Gamal

2014-03-01

Good personal hygiene (PH) behavior is recommended to prevent contagious diseases, and members of military forces may be at high risk for contracting contagious diseases. The aim of this study was to develop and test a new questionnaire on PH for soldiers. Participants were all male and from different military settings throughout Iran. Using a five-stage guideline, a panel of experts in the Persian language (Farsi) developed a 21-item self-administered questionnaire. Face and content validity of the first-draft items were assessed. The questionnaire was then translated and subsequently back-translated into English, and both the Farsi and English versions were tested in pilot studies. The consistency and stability of the questionnaire were tested using Cronbach's alpha and the test-retest strategy. The final scale was administered to a sample of 502 military personnel. Explanatory and confirmatory factor analyses evaluated the structure of the scale. Both the convergent and discriminative validity of the scale were also determined. Cronbach's alpha coefficients were >0.85. Principal component analysis demonstrated a uni-dimensional structure that explained 59 % of the variance in PH behaviors. Confirmatory factor analysis indicated a good fit (goodness-of-fit index = 0.902; comparative fitness index = 0.923; root mean square error of approximation = 0.0085). The results show that this new PH scale has solid psychometric properties for testing PH behaviors among an Iranian sample of military personnel. We conclude that this scale can be a useful tool for assessing PH behaviors in military personnel. Further research is needed to determine the scale's value in other countries and cultures.

Calibration of the indium foil used for criticality accident dosimetry in the UCC-ND employee identification badge

International Nuclear Information System (INIS)

Ryan, M.T.; Butler, H.M.; Gupton, E.D.; Sims, C.S.

1982-05-01

The UCC-ND Employee Identification Badge contains an indium foil disc that is intended for use as a dosimetry screening device in the event of a criticality accident. While it is recognized that indium is not a precise mixed neutron-gamma dosimeter, its activation by neutrons provides adequate means for separating potentially exposed persons into three groups. These groups are: (1) personnel exposed below annual dose limits, (2) personnel exposed above annual dose limits but below 25 rem, and (3) personnel exposed above 25 rem. This screening procedure is designed to facilitate dosimeter processing in order to meet regulatory reporting requirements. A quick method of interpreting induced activity measurements is presented and discussed

Dosimetry standards for radiation processing

International Nuclear Information System (INIS)

Farrar, H. IV

1999-01-01

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)

Occupational exposure to the personnel regarded by NRB-76/87 to B category

Energy Technology Data Exchange (ETDEWEB)

Gubatova, D; Balode, G; Nemiro, E [Medical Institute, Riga (USSR)

1990-01-01

During the decades use of radioactive sources in all branches of national economy has increased. Due to this tendency the number of exposed individuals from artificial sources including those exposed only occasionally (the so-called B category) increases. For this category the personnel dosimetry is not obligatory, and radioactive monitoring of their working and living places would do. Nevertheless, the thermoluminescent personnel monitoring data derived by us show that occupational exposure of this category is near, and occasionally even higher than B category exposure limit. So, for example, anesthesiologists annual exposure makes 4.5 mSv, that of surgeons 6.5 mSv, of anesthetic nurses 4.0 mSv (Traumatological and Orthopedic Institute personnel). Annual exposure of 'Medtekhnika' factory electromechanics ought to repair, set up and check up X-ray devices in 1987 was 5 mSv. (author).

Organization of the internal dosimetry in the Spanish nuclear facilities

International Nuclear Information System (INIS)

Manchena, P.; Soliet, E.

1998-01-01

From the beginning of the exploitation of the nuclear energy of Espanna, the nuclear facilities have had Services of Personal Dosimetry with the appropriate means to determine the dose. so much internal as external, of the personnel that mentioned facilities works. All the nuclear power stations use advanced systems of teams with object of detecting the radionuclides incorporation in the organism and calculation programs based on the recent recommendations of the International Commission of Radiological Protection (ICRP) for the determination of the derived doses

Dosimetry

International Nuclear Information System (INIS)

Rezende, D.A.O. de

1976-01-01

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 [pt

Ten years experience with a large computerized TLD-personnel monitoring system

International Nuclear Information System (INIS)

Duftschmid, K.E.

1986-01-01

It is now ten years since our Institute for Radiation Protection has fully replaced its filmdosimetry service by a computerized automated TLD system. Presently more than 13000 radiation workers are monthly monitored by three automated TLD readers linked to the computer center. The paper describes system hardware and software and experience gained in long-term routine operation. In particular the introduction of the new ICRU quantities for personnel dosimetry in the existing TLD system is discussed. (Author)

Impact of ANSI 2009 criteria for performance testing in TLD personnel monitoring

International Nuclear Information System (INIS)

MeenaI, P.; Rakesh, R.B.; Srivastava, Kshama; KoIambe, D.H.; Sapra, B.K.

2014-01-01

External Quality Assurance in TLD Personnel Monitoring Service was initiated in 1985, for periodic performance evaluation of various TLD Laboratories through postal exercise. Presently, all the 16 laboratories involved in Personnel Monitoring Service are covered under QA exercise. Since beginning, American National Standards Institute (ANSI) criteria have been adopted for performance testing in QA exercise. Presently, ANSI 2001 performance criteria along with ISO trumpet curve analysis method are being used for performance evaluation. In 2009, ANSI modified the performance evaluation criteria and this study evaluates its impact and feasibility of implementation of ANSI 2009 criteria in the quality assurance program for personnel monitoring. The performance of some laboratories evaluated using both ANSI 2001 and ANSI 2009 criteria have been discussed. The study shows that the ANSI 2009 criteria is more stringent and encourages even distribution of bias and standard deviation. This can be implemented with suitable modifications for performance evaluation

Use of CR-39 foils for personnel neutron dosimetry: improved electrochemical etching chambers and procedures

International Nuclear Information System (INIS)

Hankins, D.E.; Homann, S.G.; Westermark, J.

1986-01-01

The electrochemical etching procedures for the new dosimetry system that uses foils of CR-39 plastic has been improved. During 1985, the etching chambers were modified to correct several problems and the changes to the etching procedures were studied, which gave a more uniform track density and size. The currently recommended etch parameters are given. A new generation of CR-39 material from the manufacturer proved to have a considerably lower background track density and a higher sensitivity; the new foils are also more uniform in thickness, which eliminates the need to numerically compensate for thickness variations. The energy dependence of the CR-39 using monoenergetic neutrons from accelerators at Battelle Northwest Laboratories and at Los Alamos National Laboratory was determined. Some variation was found in the energy dependence, but it is believed this was caused by changes in the etching procedures and by uncertainties in the fluences of the neutrons from the accelerators. A means by which the counting of CR-39 tracks may be automated is suggested; this would be very useful in adapting the CR-39 dosimetry system to large-scale use

Health surveillance of medical personnel occupationally exposed to ionizing radiation sources: Biomonitoring and dosimetry

International Nuclear Information System (INIS)

Brumen, V.; Prlic, I.; Radalj, Z.; Horvat, D.; Cerovac, H.

1996-01-01

The aim of this work is to present the complete results of periodical health surveillance of medical personnel occupationally exposed to ionizing radiation sources, conducted according to established law regulations in Croatia. The report comprises a total of 21 examinees (11 female, 10 male), mean age 43,19 ± 9,85 years, originating from different professional groups and working in a radiation zone 14,7 ± 8,27 years on the average. Within the framework of this study, the results of their biomonitoring, including haematological parameters (whole blood count), ophthalmological findings (fundus oculi), cytogenetic test (conventional structural chromosomal aberration analysis) and peripheral blood flow survey (capillaroscopy and dermothermometry) will be presented. Filmdosimetric data for the referred period will also be reported. (author)

Introduction [International Reactor Dosimetry File 2002 (IRDF-2002)

International Nuclear Information System (INIS)

Paviotti-Corcuera, R.; Zolnay, E.M.

2006-01-01

The most recently tested version of the International Reactor Dosimetry File, IRDF-90 Version 2 (IRDF-90.2), was released in 1993. Most of the evaluations used in this file were prepared in the mid-1980s, and in the meantime a large amount of new experimental data has become available, along with two new national reactor dosimetry libraries (the Russian Reactor Dosimetry File (RRDF-98) and the Japanese Evaluated Nuclear Data Library (JENDL/D-99)). The cross-sections and related uncertainties for several reactions in these libraries may be of better quality than the data in the older IRDF-90 file. These developments have resulted in different cross-section values being applied to the evaluation of experimental data, creating difficulties in comparing the results of reactor dosimetry calculations from the same types of nuclear facility. Therefore, there has been a strong demand from the reactor dosimetry community for an updated and standardized version of the IRDF. The IAEA has in the past supported similar efforts to improve the quality of data for reactor dosimetry applications. A major objective of the present data development project was to prepare and distribute a standardized, updated and tested reactor dosimetry cross-section library accompanied by uncertainty information (IRDF-2002) for use in service life assessments of nuclear power reactors. In order to achieve this objective, two technical meetings were organized. Both meetings were held at the IAEA in Vienna. The first meeting took place from 27 to 29 August 2002, the second from 1 to 3 October 2003. Recommendations were made concerning the following topics and the preparation of the library: reactions to be included, requirements for new evaluations or revisions, nuclear decay data, radiation damage data, testing of the data in benchmark fields and inclusion of computer codes. The participants emphasized that good quality nuclear data for reactor dosimetry are essential to improve assessments of the

TEST OF ENGLISH FOR AVIATION PERSONNEL TO MEET ICAO LANGUAGE PROFICIENCY REQUIREMENTS

Directory of Open Access Journals (Sweden)

Olena Petrashchuk

2012-10-01

Full Text Available  The article is devoted to the actual problem of the assessment of English language proficiency of aviation personnel. The paper presents an English language test, which is used for professional pilots and air traffic controllers.

Quality Control in the Dosimetric System of the Personnel Dosimetry Service of the Spanish National Health Service

Energy Technology Data Exchange (ETDEWEB)

Casal, E.; Gil, J.A.; Roig, F.; Soriano, A. [Valencia (Spain)

1999-07-01

The main operating and quality control procedures implemented at the Centro Nacional de Dosimetria (CND) of the Spanish National Health Service to ensure the acceptance of the dosimetry service are described. The operating procedures are routinely performed at every step, since the dosemeters are received from the manufacturer until the doses are assigned to the dosimetric history and their main aim is to ensure the traceability of the doses. They make use of control and background dosemeters and frequent cross reference (automatic and manual) of different sources of data. The control procedures are performed at the end of each monthly process to detect possible errors or systematic bias in the dosimetry service and include analysis of the measurements of quality control dosemeters irradiated at the CND's laboratory and randomly read. The results of this analysis since 1996 are presented. (author)

Quality Control in the Dosimetric System of the Personnel Dosimetry Service of the Spanish National Health Service

International Nuclear Information System (INIS)

Casal, E.; Gil, J.A.; Roig, F.; Soriano, A.

1999-01-01

The main operating and quality control procedures implemented at the Centro Nacional de Dosimetria (CND) of the Spanish National Health Service to ensure the acceptance of the dosimetry service are described. The operating procedures are routinely performed at every step, since the dosemeters are received from the manufacturer until the doses are assigned to the dosimetric history and their main aim is to ensure the traceability of the doses. They make use of control and background dosemeters and frequent cross reference (automatic and manual) of different sources of data. The control procedures are performed at the end of each monthly process to detect possible errors or systematic bias in the dosimetry service and include analysis of the measurements of quality control dosemeters irradiated at the CND's laboratory and randomly read. The results of this analysis since 1996 are presented. (author)

Intercomparison of high energy neutron personnel dosimeters

International Nuclear Information System (INIS)

McDonald, J.C.; Akabani, G.; Loesch, R.M.

1993-03-01

An intercomparison of high-energy neutron personnel dosimeters was performed to evaluate the uniformity of the response characteristics of typical neutron dosimeters presently in use at US Department of Energy (DOE) accelerator facilities. It was necessary to perform an intercomparison because there are no national or international standards for high-energy neutron dosimetry. The testing that is presently under way for the Department of Energy Laboratory Accreditation Program (DOELAP) is limited to the use of neutron sources that range in energy from about 1 keV to 2 MeV. Therefore, the high-energy neutron dosimeters presently in use at DOE accelerator facilities are not being tested effectively. This intercomparison employed neutrons produced by the 9 Be(p,n) 9 B interaction at the University of Washington cyclotron, using 50-MeV protons. The resulting neutron energy spectrum extended to a maximum of approximately 50-MeV, with a mean energy of about 20-MeV. Intercomparison results for currently used dosimeters, including Nuclear Type A (NTA) film, thermoluminescent dosimeter (TLD)-albedo, and track-etch dosimeters (TEDs), indicated a wide variation in response to identical doses of high-energy neutrons. Results of this study will be discussed along with a description of plans for future work

Testing of portal monitors for personnel contamination control

International Nuclear Information System (INIS)

Johnson, L.O.; Gupta, V.P.; Stevenson, R.L.; Stalker, A.C.; Baker, K.R.; Littleton, M.L.; Rich, B.L.

1983-04-01

This is a report of an INPO-funded evaluation of state-of-the-art portal monitors used to detect personnel contamination. The project developed techniques and procedures to evaluate the performance and sensitivity of the portal monitors which provided data for intercomparison. An additional accomplishment was development of a methodology to assist manufacturers and users to optimize the monitor settings, and to provide technical basis for the eventual use of fixed monitors to replace frisking for contamination control. The monitors tested utilize thin-window gas-flow proportional counters sensitive to beta and gamma radiation. Various tests were performed: (1) background count rate and the statistical variability, (2) detector efficiency at different distances, (3) moving source sensitivity for various size sources and speeds, and (4) false alarm rates at different background levels. A model has been developed for the moving source measurements to compare the experimental data, and to test whether it is possible to adequately model the behavior of a portal monitor response to a moving source. The model results with the actual test results are compared

Aircrew personnel dosimetry at airline companies in the Czech Republic. Selection of the method and its experimental testing

International Nuclear Information System (INIS)

Spurny, F.; Malusek, A.; Kovar, I.; Turek, K.; Vlcek, B.; Hlavaty, V.; Kolar, B

2002-01-01

The report gives the results of the first stages of analysis of the problem, performed based on a contract between the Czech airline company CSA and the Radiation Dosimetry Department, Institute of Nuclear Physics, Academy of Sciences of the Czech Republic. First, the contributions of the aircraft type and of the flight route to the aircrew radiation burden was investigated based on 1997 and 1998 data. At the same time, the effect of variations in the flight parameters on the exposure level was examined based on calculations by using an internationally recognized computer code. In the next part of the report, the results of measurement of the aircrew exposure level performed during the period of March to November 1999 are given and analyzed. The measurements encompassed 8 European flight routes, 2 routes over the northern regions of the Atlantic and one route to south-eastern Asia. Data were obtained for the low-LET component (mostly high-energy electrons and protons) as well as the high-LET component (mostly neutrons). To refine the interpretation of the data, calibration measurements were performed in the reference fields of high energy radiations at CERN. The results of measurement were compared with the results of calculation by the CARI code. The data provided by the latest CARI 6 version approach the observed values reasonably closely. (author)

Technical basis for nuclear accident dosimetry at the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Kerr, G.D.; Mei, G.T.

1993-08-01

The Oak Ridge National Laboratory (ORNL) Environmental, Safety, and Health Emergency Response Organization has the responsibility of providing analyses of personnel exposures to neutrons and gamma rays from a nuclear accident. This report presents the technical and philosophical basis for the dose assessment aspects of the nuclear accident dosimetry (NAD) system at ORNL. The issues addressed are regulatory guidelines, ORNL NAD system components and performance, and the interpretation of dosimetric information that would be gathered following a nuclear accident

Dosimetry quality assurance in Martin Marietta Energy Systems' centralized external dosimetry system

International Nuclear Information System (INIS)

Souleyrette, M.L.

1992-01-01

External dosimetry needs at the four Martin Marietta Energy Systems facilities are served by Energy Systems Centralized External Dosimetry System (CEDS). The CEDS is a four plant program with four dosimeter distribution centers and two dosimeter processing centers. Each plant has its own distribution center, while processing centers are located at ORNL and the Y-12 Plant. The program has been granted accreditation by the Department of Energy Laboratory Accreditation Program (DOELAP). The CEDS is a TLD based system which is responsible for whole-body beta-gamma, neutron, and extremity monitoring. Beta-gamma monitoring is performed using the Harshaw/Solon Technologies model 8805 dosimeter. Effective October 1, 1992 the standard silver mylar has been replaced with an Avery mylar foil blackened on the underside with ink. This was done in an effort to reduce the number of light induced suspect readings. At this time we have little operational experience with the new blackened mylars-The CEDS neutron dosimeter is the Harshaw model 8806B. This card/holder configuration contains two TLD-600/TLD-700 chip pairs; one pair is located beneath a cadmium filter and one pair is located beneath a plastic filter. In routine personnel monitoring the CEDS neutron dosimeter is always paired with a CEDS beta-gamma dosimeter.The CEDS extremity dosimeter is composed of a Harshaw thin TLD-700 dosiclip placed inside a Teledyne RB-4 finger sachet. The finger sachet provides approximately 7 mg/cm 2 filtration over the chip. A teflon ring surrounds the dosiclip to help prevent tearing of the vinyl sachet

Polymer gel dosimetry

Energy Technology Data Exchange (ETDEWEB)

Baldock, C [Institute of Medical Physics, School of Physics, University of Sydney (Australia); De Deene, Y [Radiotherapy and Nuclear Medicine, Ghent University Hospital (Belgium); Doran, S [CRUK Clinical Magnetic Resonance Research Group, Institute of Cancer Research, Surrey (United Kingdom); Ibbott, G [Radiation Physics, UT M D Anderson Cancer Center, Houston, TX (United States); Jirasek, A [Department of Physics and Astronomy, University of Victoria, Victoria, BC (Canada); Lepage, M [Centre d' imagerie moleculaire de Sherbrooke, Departement de medecine nucleaire et de radiobiologie, Universite de Sherbrooke, Sherbrooke, QC (Canada); McAuley, K B [Department of Chemical Engineering, Queen' s University, Kingston, ON (Canada); Oldham, M [Department of Radiation Oncology, Duke University Medical Center, Durham, NC (United States); Schreiner, L J [Cancer Centre of South Eastern Ontario, Kingston, ON (Canada)], E-mail: c.baldock@physics.usyd.edu.au, E-mail: yves.dedeene@ugent.be

2010-03-07

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 gradients exist such as in intensity-modulated radiation therapy (IMRT) and stereotactic radiosurgery. Polymer gel dosimeters also have specific advantages for brachytherapy dosimetry. Potential dosimetry applications include those for low-energy x-rays, high-linear energy transfer (LET) and proton therapy, radionuclide and boron capture neutron therapy dosimetries. These 3D dosimeters are radiologically soft-tissue equivalent with properties that may be modified depending on the application. The 3D radiation dose distribution in polymer gel dosimeters may be imaged using magnetic resonance imaging (MRI), optical-computerized tomography (optical-CT), x-ray CT or ultrasound. The fundamental science underpinning polymer gel dosimetry is reviewed along with the various evaluation techniques. Clinical dosimetry applications of polymer gel dosimetry are also presented. (topical review)

Study of the positioning of the films of the MLC by a Test of bands and your influence in the clinic dosimetry in IMRT

International Nuclear Information System (INIS)

Serrano Zabaleta, S.; Millan Cebrian, E.; Calvo Carrillo, S.; Alba Escorihuela, V.; Garcia Romero, A.; Ortega Pardina, P.; Canella Anoz, M.; Hernandez Vitoria, A.

2015-01-01

We performed a test of adjacent bands inspired by the proposed in AAPM Report No. 72, we provides a parameter characterizing the state of the MLC as to the actual position of its blades. This test has been validated by studying repeatability and reproducibility and has found the correlation between the parameter and creep detected by the ILD. Subsequently it has studied the impact of changes in the positioning of the blades on clinical dosimetry in IMRT patients, reconstructing the patient dose by Matrix Evolution team and Compass software, IBA Dosimetry. (Author)

External audit in radiotherapy dosimetry

International Nuclear Information System (INIS)

Thwaites, D.I.; Western General Hospital, Edinburgh

1996-01-01

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)

Radiation protection and dosimetry: basis. 9. ed.

International Nuclear Information System (INIS)

Tauhata, Luiz; Salati, Ivan; Di Prinzio, Renato; Di Prinzio, Antonieta R.

2013-11-01

A revised book 'Radiation Protection and Dosimetry: Fundamentals , prepared to meet the training courses offered by the Instituto de Radioprotecao e Dosimetria - IRD, Rio de Janeiro, RJ, Brazil and people interested in the subject, is presented. Concepts have been updated, especially the chapter on Radiological Magnitudes, due to upgrade of Standard CNEN-NN-3.01-Basic Guidelines on Radiological Protection, published in the Diario Oficial da Uniao on September 1, 2011. A chapter related to Waste Management, another on the Transport of Radioactive Materials and three annexes on: Standards of CNEN, Ionizing Radiation and Personnel Legislation and Determination of shields in Radiotherapy were included. Were also added several tables for use in radiological protection, to facilitate consultation

Performance testing of personal dosemeters from eleven dosimetry services in Sweden

International Nuclear Information System (INIS)

Lund, E.; Kylloenen, J.-E.; Grindborg, J.-E.; Lindborg, L.

2001-01-01

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 H p (10) and some of them to determine H p (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 H p (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)

Passive Dosimetry Of Nuclear Medicine Service Staff, Ibn Sina Hospital

International Nuclear Information System (INIS)

Sebihi, R.; Talsmat, K.; Cherkaoui, R.; Ben Rais, N.

2010-01-01

Full text: Since the implementation of Law No. 00571 of 21 Chaabane 1391 on protection against ionizing radiation and its decrees 2: 2-97-30 and 2-97-132 28 October 1997, surveillance of workers has the subject of major regulatory developments in Morocco, including individual registration delayed for dosimetry. As part of optimizing the protection of medical personnel, a dosimetric study was performed for the first time at the national level, the Nuclear Medicine Service of the Ibn Sina hospital in collaboration with the National Center for Energy Sciences and Nuclear Techniques (CNESTEN). Dosimetric monitoring was conducted for 2 weeks with the use of passive thermoluminescent dosimeters, (GR200A), covering all categories of staff. The administration of samarium (β emitter with energy substantially higher than the energies encountered in conventional nuclear medicine) has been studied, given his first service. Other cases of people concerned our study: a pregnant woman doctor, whose exposure of the unborn child must be reduced as much as possible, and a woman from a private company, working without dosimeter, handles maintenance of premises. To control the conditions imposed on all activities requiring exposure to ionizing radiation, we evaluated the dose at the extremities of operators with the use of ring dosimeters (GR200A) and the dose on the ambient environment of staff (dosimeters ALNOR). This experiment has shown exposure levels below legal limits, without been negligible for certain post. The evaluation results equivalent doses manipulators justify the wearing of dosimeter rings as a complementary dosimeter in Nuclear Medicine service and a way of controlling the normal working conditions. Finally Monitoring ambient dosimetry showed that the environment is low radiation doses. Lessons learned from this study, for the protection of personnel are as follows: from the simple awareness of staff and means of optimizing radiation can maintain a dosimetry annual

SU-E-P-46: Clinical Acceptance Testing and Implementation of a Portable CT Unit

International Nuclear Information System (INIS)

LaFrance, M; Marsh, S; Hicks, R; O’Donnell-Moran, G

2015-01-01

Purpose: Planning for the first installation in New England of a new portable CT unit to be used in the Operating Room required the integration of many departments including Surgery, Neurosurgery, Information Services, Clinical Engineering, Radiology and Medical Physics/Radiation Safety. Acceptance testing and the quality assurance procedures were designed to optimize image quality and patient and personnel radiation exposure. Methods: The vendor’s protocols were tested using the CT Dosimetry phantoms. The system displayed the CTDIw instead of the CTDIvol while testing the unit. Radiation exposure was compared to existing CT scanners from installed CT units throughout the facility. Brainlab measures all 4 periphery slots on the CT Dosimetry phantom. The ACR measures only the superior slot for the periphery measurement. A comprehensive radiation survey was also performed for several locations. Results: The CTDIvol measurements were comparable for the following studies: brain, C-Spine, and sinuses. However, the mobile CT measurements were slightly higher than other CT units but within acceptable tolerance if measured using the ACR method.Based on scatter measurements, it was determined if any personnel were to stay in the OR Suite during image acquisition that the appropriate lead apron and thyroid shields had to be worn.In addition, to reduce unnecessary scatter, there were two mobile 6 foot wide shields (1/16″ lead equivalent) available to protect personnel in the room and adjacent areas. Conclusion: Intraoperative CT provides the physician new opportunities for evaluation of the progression of surgical resections and device placement at the cost of increasing the amount of trained personnel required to perform this procedure. It also brings with it challenges to keep the radiation exposure to the patients and staff within reasonable limits

SU-E-P-46: Clinical Acceptance Testing and Implementation of a Portable CT Unit

Energy Technology Data Exchange (ETDEWEB)

LaFrance, M; Marsh, S; Hicks, R; O’Donnell-Moran, G [Baystate Health Systems, Inc., Springfield, MA (United States)

2015-06-15

Purpose: Planning for the first installation in New England of a new portable CT unit to be used in the Operating Room required the integration of many departments including Surgery, Neurosurgery, Information Services, Clinical Engineering, Radiology and Medical Physics/Radiation Safety. Acceptance testing and the quality assurance procedures were designed to optimize image quality and patient and personnel radiation exposure. Methods: The vendor’s protocols were tested using the CT Dosimetry phantoms. The system displayed the CTDIw instead of the CTDIvol while testing the unit. Radiation exposure was compared to existing CT scanners from installed CT units throughout the facility. Brainlab measures all 4 periphery slots on the CT Dosimetry phantom. The ACR measures only the superior slot for the periphery measurement. A comprehensive radiation survey was also performed for several locations. Results: The CTDIvol measurements were comparable for the following studies: brain, C-Spine, and sinuses. However, the mobile CT measurements were slightly higher than other CT units but within acceptable tolerance if measured using the ACR method.Based on scatter measurements, it was determined if any personnel were to stay in the OR Suite during image acquisition that the appropriate lead apron and thyroid shields had to be worn.In addition, to reduce unnecessary scatter, there were two mobile 6 foot wide shields (1/16″ lead equivalent) available to protect personnel in the room and adjacent areas. Conclusion: Intraoperative CT provides the physician new opportunities for evaluation of the progression of surgical resections and device placement at the cost of increasing the amount of trained personnel required to perform this procedure. It also brings with it challenges to keep the radiation exposure to the patients and staff within reasonable limits.

Operational comparison of bubble (super heated drop) dosimetry with routine albedo thermoluminescent dosimetry for a selected group of Pu-238 workers at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Romero, L.L.; Hoffman, J.M.; Foltyn, E.M.; Buhl, T.E.

1999-01-01

This paper is an operational study that compares the use of albedo thermoluminescent dosimeters with bubble dosimeters to determine whether bubble dosimeters do provide a useful daily ALARA tool that can yield measurements close to the dose-of-record. A group of workers at the Los Alamos National Laboratory (LANL) working on the Radioactive Thermoelectric Generators (RTG) for the NASA Cassini space mission wore both bubble dosimeters and albedo dosimeters over a period from 1993 through 1996. The bubble dosimeters were issued and read on a daily basis and the data were used as an ALARA tool. The personnel albedo dosimeter was processed on monthly basis and used as the dose-of-record. The results of this study indicated that cumulative bubble dosimetry results agreed with whole-body albedo dosimetry results within about 37% on average. However it was observed that there is a significant variability of the results on an individual basis both month-to-month and from one individual to another

Radiation dosimetry and radiation biophysics

International Nuclear Information System (INIS)

Anon.

1981-01-01

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

Radiation dosimetry and radiation biophysics

International Nuclear Information System (INIS)

Anon.

1979-01-01

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

Integral test of International Reactor Dosimetry and Fusion File with Li{sub 2}O assembly and DT neutron source at JAEA/FNS

Energy Technology Data Exchange (ETDEWEB)

Sato, Satoshi, E-mail: sato.satoshi92@jaea.go.jp [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki-ken (Japan); Kwon, Saerom; Ohta, Masayuki [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki-ken (Japan); Ochiai, Kentaro [Japan Atomic Energy Agency, Rokkasho-mura, Kamikita-gun, Aomori-ken (Japan); Konno, Chikara [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki-ken (Japan)

2016-11-01

In order to validate a new library of dosimetry cross section data, International Reactor Dosimetry and Fusion File release 1.0 (IRDFF 1.0), not only for DT neutrons but also for neutrons with energy of less than 14 MeV, we perform an integral test with a Li{sub 2}O rectangular assembly of 60.7 cm in thickness and a DT neutron source at JAEA/FNS. We place a lot of activation foils at depths of 10.1 cm and 30.4 cm for measurements of dosimetry reaction rates in small space along the central axis in the assembly, measure decay gamma-rays from the activation foils with high-purity Ge detectors after the DT neutron irradiation by the foil activation technique, and deduce a variety of dosimetry reaction rates. We calculate the reaction rates by using a Monte Carlo code MCNP5-1.40 and the nuclear data library ENDF/B-VII.1 with the IRDFF-v.1.05 as the response functions for the dosimetry reactions. The calculation results generally show good agreements with the measured ones, and it can be confirmed that most of the data in IRDFF-v.1.05 are valid for the neutron field in the Li{sub 2}O assembly with the DT neutrons.

SEVENTH DOE WORKSHOP ON PERSONNEL NEUTRON DOSIMETRY

Energy Technology Data Exchange (ETDEWEB)

Vallario, E J

1978-10-24

This workshop was the seventh of a series and was held on October 23-24. 1978, at the Central Electricity Generating Board, HQ, London, England. Typically~ attendees at the Workshop were concerned with one of three activities: studying and refining existing techniques in an attempt to quantify already-known parameters with greater precision, looking for ways to apply existing neutron dosirr:etry techniques to a specific local problem, identifying the needs and weaknesses of existing systems, with the goal of improving and passibly simplifying field measurements. The types of neutron dosimetry techniques discussed by participants included albedo dosimeters, track etch, and TLD. One speaker reported on NTA film, noting that fading could be eliminated by drying the emulsion in dry nitrogen before field use. There were no reports on tissue equivalent proportional counters or activation analysis. One participant discussed a metal oxide silicon dosimeter. The need to develop a consistent standard terminology, as well as calibration sources and techniques, on both the national and international level was evident. The need for standardization is particularly acute in the U.S. Techniques for evaluating dosimeter response in the field should he standardized, since several different instruments with widely different response characteristics are currently being used. The choice of instruments is often parochial. Also. the type and use of phantoms should be standardized. Neutron dose assignment is significantly affected by the position of the dosimeter on the body. for example, a typical albedo dosimeter may give differences of up to 20% depending on whether it is worn on the belt or chest. Larger errors are encountered with front-to-back (angular} orientation. 1n an attempt to minimize such errors~ at least two European facilities are using neutron dosimeter belts, which provide dosimeters both in front and in back of the wearer. The gamma-to-neutron ratio around nuclear power

Dosimetry of internal emitting: principles and perspectives of the MIRD technology; Dosimetria de emisores internos: principios y perspectivas de la metodologia MIRD

Energy Technology Data Exchange (ETDEWEB)

Ferro F, G [Gerencia de Aplicaciones Nucleares en la Salud, Instituto Nacional de Investigaciones Nucleares, Salazar, Estado de Mexico C.P. 52045 (Mexico)

1999-07-01

The development of the radiopharmaceutical technology have multiplied the number of radioisotopes with applications in therapeutical nuclear medicine so known as Directed radiotherapy. Assuming the radiation is capable to produce noxious effects in the biological systems, it is important to evaluate appropriately the risks and benefits of the administration of radioactive agents in the patient. The outstanding parameter in this evaluation is the absorbed dose, which is product of the radiation emitted by a radionuclide that is localized or distributed to the interior of the human body in study and whose its estimation helps to predict the efficacy of the treatment. The scheme generalized of MIRD, it was formulated from thirty years ago for evaluating the interior dosimetry at level of organs.The finality of this work is to show the basic principles of the MIRD methodology and its perspectives using innovator tools as the dosimetry for dynamic masses, in particular the personnel dosimetry for the organs of each patient, the dosimetry for the small structures inside the organs (sub organic dosimetry), the distributions of doses in three dimensions (S voxel), the dosimetry at cellular level and the quantitative acquisition of pharmaceutical data. (Author)

Internal sources dosimetry

International Nuclear Information System (INIS)

Savio, Eduardo

1994-01-01

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 .

Recent developments in detectors/phantoms for dosimetry, X-ray quality assurance and imaging

International Nuclear Information System (INIS)

Sankaran, A.

2009-01-01

During the past years, many new developments have taken place in detectors/phantoms for high energy photon and electron dosimetry (for radiotherapy), protection monitoring, X-ray quality assurance and X-ray imaging (for radiodiagnosis). A variety of detectors and systems, quality assurance (QA) gadgets and special phantoms have been developed for diverse applications. This paper discusses the important developments with some of which the author was actively associated in the past. For dosimetry and QA of 60 Co and high energy X-ray units, state-of-the-art radiation field analyzers, matrix ion chambers, MOSFET devices and Gafchromic films are described. OSL detectors find wide use in radiotherapy dosimetry and provide a good alternative for personnel monitoring. New systems introduced for QA/dosimetry of X-ray units and CT scanners include: multi-function instruments for simultaneous measurement of kVp, dose, time, X-ray waveform and HVT on diagnostic X-ray units; pencil chamber with head and body phantoms for CTDI check on CT scanners. Examples of phantoms used for dosimetry and imaging are given. Advancements in the field of diagnostic X-ray imaging (with applications in portal imaging/dosimetry of megavoltage X-ray units) have led to emergence of: film-replacement systems employing CCD-scintillator arrays, computed radiography (CR) using storage phosphor plate; digital radiography (DR), using a pixel-matrix of amorphous selenium, or amorphous silicon diode coupled to scintillator. All these provide (a) in radiotherapy, accurate dose delivery to tumour, saving the surrounding tissues and (b) in radiodiagnosis, superior image quality with low patient exposure. Lastly, iPODs and flash drives are utilized for storage of gigabyte-size images encountered in medical and allied fields. Although oriented towards medical applications, some of these have been of great utility in other fields, such as industrial radiography as well as a host of other research areas. (author)

3D dosimetry by optical-CT scanning

Science.gov (United States)

Oldham, Mark

2006-12-01

The need for an accurate, practical, low-cost 3D dosimetry system is becoming ever more critical as modern dose delivery techniques increase in complexity and sophistication. A recent report from the Radiological Physics Center (RPC) (1), revealed that 38% of institutions failed the head-and-neck IMRT phantom credentialing test at the first attempt. This was despite generous passing criteria (within 7% dose-difference or 4mm distance-to-agreement) evaluated at a half-dozen points and a single axial plane. The question that arises from this disturbing finding is - what percentage of institutions would have failed if a comprehensive 3D measurement had been feasible, rather than measurements restricted to the central film-plane and TLD points? This question can only be adequately answered by a comprehensive 3D-dosimetry system, which presents a compelling argument for its development as a clinically viable low cost dosimetry solution. Optical-CT dosimetry is perhaps the closest system to providing such a comprehensive solution. In this article, we review the origins and recent developments of optical-CT dosimetry systems. The principle focus is on first generation systems known to have highest accuracy but longer scan times.

VALIDATION OF HANFORD PERSONNEL AND EXTREMITY DOSIMETERS IN PLUTONIUM ENVIRONMENTS

Energy Technology Data Exchange (ETDEWEB)

Scherpelz, Robert I.; Fix, John J.; Rathbone, Bruce A.

2000-02-10

A study was performed in the Plutonium Finishing Plant to assess the performance of Hanford personnel neutron dosimetry. The study was assessed whole body dosimetry and extremity dosimetry performance. For both parts of the study, the TEPC was used as the principle instrument for characterizing workplace neutron fields. In the whole body study, 12.7-cm-diameter TEPCs were used in ten different locations in the facility. TLD and TED personnel dosimeters were exposed on a water-filled phantom to enable a comparison of TEPC and dosimeter response. In the extremity study, 1.27-cm-diameter TEPCs were exposed inside the fingers of a gloveboxe glove. Extremity dosimeters were wrapped around the TEPCs. The glove was then exposed to six different cans of plutonium, simulating the exposure that a worker's fingers would receive in a glovebox. The comparison of TEPC-measured neutron dose equivalent to TLD-measured gamma dose equivalent provided neutron-to-gamma ratios that can be used to estimate the neutron dose equivalent received by a worker's finger based on the gamma readings of an extremity dosimeter. The study also utilized a Snoopy and detectors based on bubble technology for assessing neutron exposures, providing a comparison of the effectiveness of these instruments for workplace monitoring. The study concludes that the TLD component of the HCND performs adequately overall, with a positive bias of 30%, but exhibits excessive variability in individual results due to instabilities in the algorithm. The TED response was less variable but only 20% of the TEPC reference dose on average because of the low neutron energies involved. The neutron response of the HSD was more variable than the TLD component of the HCND and biased high by a factor of 8 overall due to its calibration to unmoderated 252Cf. The study recommends further work to correct instabilities in the HCND algorithm and to explore the potential shown by the bubble-based dosimeters.

Suitability of Israeli Household Salt for Retrospective Dosimetry

International Nuclear Information System (INIS)

Datz, H.; Druzhyna, S.; Oster, L.; Orion, I.; Darras, I.; Hershkovich, D.; Horowitz, Y.

2014-01-01

Following a nuclear accident or a terror attack involving the dispersal of radioactive material, radiation dose assessment to first responders and the members of the public is essential. This information may be used by medical personnel to decide whether to refer the exposed individual for medical treatment or not. Few people, if any, will be wearing standard dosimeters at the exposure scene, so the need for a retrospective assessment of the radiation dose is an acute necessity. Previously developed methods for retrospective dosimetry (RD) have suggested various types of materials such as tiles, bricks, CDs, electronic components, mobile phones, electron paramagnetic resonance of tooth enamel, hair, nails, biological dosimetry techniques etc. These techniques involve significant disadvantages such as: the long time required to prepare the samples for measurement the considerable expense of the measuring equipment, invasive procedure and others. The need for an RD technique which will be fast, inexpensive, reliable, non-invasive and, if possible, portable, remains an on-going challenge. The ideal retrospective dosimeter must fulfill the following basic criteria: a) Availability in the contaminated area, b) Adequate dose measurement capability in the relevant range of dose levels, c) Negligible or known fading between exposure and measurement

Leak rate test of containment personnel lock

International Nuclear Information System (INIS)

Julien, J.T.; Peters, S.W.

1988-01-01

As part of the US NRC Containment Integrity Program, a leak rate test was performed on a full size personnel airlock for a nuclear containment building. The airlock was subjected to conditions simulating severe accident conditions. The objective of the test was to characterize the performance of airlock door seals when subjected to conditions that exceeded design. The seals tested were a double dog-ear configuration and made from EPDM E603. The data obtained from this test will be used by SNL as a benchmark for development of analytical methods. In addition to leak rate information, strain, temperature, displacements, and pressure data were measured and recorded from over 330 transducers. The test lasted approximately 60 hours. Data were recorded at regular intervals and during heating, pressurization and depressurization. The inner airlock door and bulkhead were exposed to a maximum air temperature of 850 F and a maximum air pressure of 300 psig. The airlock was originally designed for 340 F and 60 psig. Two heating and pressurization cycles were planned; one to heat to 400 F and pressurize to 300 psig, and the second to heat to 800 F and pressurize to 300 psig. No significant leakage was recorded during these two cycles. A third cycle was added to the test program. The air temperature was increased to 850 F and held at this temperature for approximately 10 hours. The inner door seal failed quickly at a pressure of 150.5 psig. The maximum leak rate was 706 SCFM

Pulmonary function test in traffic police personnel in Pondicherry.

Science.gov (United States)

Pal, Pravati; John, Robert A; Dutta, T K; Pal, G K

2010-01-01

Traffic policemen working in the busy traffic signal areas get exposed to the vehicular emissions for years together. The fumes, chemicals and particles present in the emission are reported to be damaging to the lung functions of these individuals. Since there were no data available on the PFT parameters of traffic police personnel of Pondicherry, this study was taken up to assess the effect of traffic air pollution on their pulmonary functions. PFT parameters were recorded in age- and BMI-matched 30 traffic police personnel (study group) and 30 general police personnel (control group) of male gender. As chronic smoking is known to be a critical factor in altering lung function, PFT parameters were compared between the smokers as well as nonsmokers of both the groups. In nonsmokers, there was significant decrease in VC (P traffic police personnel compared to the general police personnel. This may be due to exposure to vehicular pollution for several hours in a day for many years causing decreased functional capacity of the lungs and chronic smoking worsens the condition.

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)

EPR Dosimetry - Present and Future

International Nuclear Information System (INIS)

Regulla, D.F.

1999-01-01

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)

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)

Ferrufino, G.A.; Discacciatti, P.A.; Lopez, F.O.

2013-01-01

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)

Patient and personnel occupationally exposed in diagnosis; Del paciente y el POE en diagnostico

Energy Technology Data Exchange (ETDEWEB)

Garcia A, J. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2008-12-15

N. Gentner, UNSCEAR officer declared during the 11 Congress of the IRPA, that the collective dose to patients due to diagnostic radiology represents 150 times the collective dose due to occupational exposures, which can give an idea of the need to dose control in the Radiodiagnosis. The practice types involved as traditional radiography appear to be in reasonable dose, however, computerized tomography and interventional cardiology have dose levels that are a challenge for the community. According to the international conference for the patient radiation protection held in 2001, the risk would be higher for patients undergoing computerized tomography of kidney and liver. Although not normally be expected that the deterministic effects dose are exceeded, in case of multiple tests as computed tomography combined with other procedures (interventional, by example), so if you can reach levels of deterministic effects. The dose indicators are obtained from various parameters such as the radiation output from X-ray tube, the dose-area product, the dose index in computerized tomography and the dose entrance in surface. The dose indices in computerized tomography have several types of indicators. The radiation measurement output of the tubes is in turn based on different conditions and parameters. Personnel occupationally exposed also shrinks risks in proportion to that of the patients, such as interventional radiologists and cardiologists. In the diagnosis also needs to be done, and may include the development of procedures to standardize and normalize the patient dosimetry for all the techniques, implement dosimetry staff at all facilities, recommend the appropriate medical surveillance of personnel occupationally exposed to each practices, create and improve the regulatory framework, particularly in the intervention areas and hybrid images, and establish and improve the census and resources control involved in the medical applications in radiodiagnostic and interventional

Techniques for radiation measurements: Micro-dosimetry and dosimetry

International Nuclear Information System (INIS)

Waker, A. J.

2006-01-01

Experimental Micro-dosimetry is concerned with the determination of radiation quality and how this can be specified in terms of the distribution of energy deposition arising from the interaction of a radiation field with a particular target site. This paper discusses various techniques that have been developed to measure radiation energy deposition over the three orders of magnitude of site-size; nano-meter, micrometer and millimetre, which radiation biology suggests is required to fully account for radiation quality. Inevitably, much of the discussion will concern the use of tissue-equivalent proportional counters and variants of this device, but other technologies that have been studied, or are under development, for their potential in experimental Micro-dosimetry are also covered. Through an examination of some of the quantities used in radiation metrology and dosimetry the natural link with Micro-dosimetric techniques will be shown and the particular benefits of using Micro-dosimetric methods for dosimetry illustrated. (authors)

Scanning personnel for internal deposition of radioactive material with personnel contamination whole body friskers and portal monitors

International Nuclear Information System (INIS)

Lobdell, J.L.

1996-01-01

The potential for using personnel contamination devices such as whole body friskers and portal monitors for internal contamination monitoring was evaluated. Internally deposited radioactive material is typically determined with whole body counting systems. Whole body counts have traditionally been performed on personnel when they report for work, on a periodic basis (i.e., annually), when an uptake is suspected, and on termination. These counts incur significant expense. The monitored personnel pass through whole body friskers and portal monitors daily. This investigation was performed to determine if the external contamination monitors could provide an alternative to the more Costly whole body counting. The ability to detect 1% of a DAC for critical radioisotopes was applied as a detection criteria for this investigation. The results of whole body counts were used to identify the typical internal contamination radionuclides. From this list, the radioisotopes that would be the most difficult to measure were identified. From this review, 60 Co and 131 I were determined to be the critical radionuclides. One percent of a DAC for each isotope was placed, one at a time, in a humanoid phantom. The phantom was placed in the whole body frisker and open-quotes countedclose quotes. The phantom was carried through the portal monitor at a speed equivalent to a person walking through the monitor. Frequency of detection was derived for both systems. Practical aspects of integrating this screening system with traditional internal dosimetry programs are discussed

Reactor Dosimetry State of the Art 2008

Science.gov (United States)

Voorbraak, Wim; Debarberis, Luigi; D'Hondt, Pierre; Wagemans, Jan

2009-08-01

Oral session 1: Retrospective dosimetry. Retrospective dosimetry of VVER 440 reactor pressure vessel at the 3rd unit of Dukovany NPP / M. Marek ... [et al.]. Retrospective dosimetry study at the RPV of NPP Greifswald unit 1 / J. Konheiser ... [et al.]. Test of prototype detector for retrospective neutron dosimetry of reactor internals and vessel / K. Hayashi ... [et al.]. Neutron doses to the concrete vessel and tendons of a magnox reactor using retrospective dosimetry / D. A. Allen ... [et al.]. A retrospective dosimetry feasibility study for Atucha I / J. Wagemans ... [et al.]. Retrospective reactor dosimetry with zirconium alloy samples in a PWR / L. R. Greenwood and J. P. Foster -- Oral session 2: Experimental techniques. Characterizing the Time-dependent components of reactor n/y environments / P. J. Griffin, S. M. Luker and A. J. Suo-Anttila. Measurements of the recoil-ion response of silicon carbide detectors to fast neutrons / F. H. Ruddy, J. G. Seidel and F. Franceschini. Measurement of the neutron spectrum of the HB-4 cold source at the high flux isotope reactor at Oak Ridge National Laboratory / J. L. Robertson and E. B. Iverson. Feasibility of cavity ring-down laser spectroscopy for dose rate monitoring on nuclear reactor / H. Tomita ... [et al.]. Measuring transistor damage factors in a non-stable defect environment / D. B. King ... [et al.]. Neutron-detection based monitoring of void effects in boiling water reactors / J. Loberg ... [et al.] -- Poster session 1: Power reactor surveillance, retrospective dosimetry, benchmarks and inter-comparisons, adjustment methods, experimental techniques, transport calculations. Improved diagnostics for analysis of a reactor pulse radiation environment / S. M. Luker ... [et al.]. Simulation of the response of silicon carbide fast neutron detectors / F. Franceschini, F. H. Ruddy and B. Petrović. NSV A-3: a computer code for least-squares adjustment of neutron spectra and measured dosimeter responses / J. G

Beta calibration and dosimetry at IPEN

International Nuclear Information System (INIS)

Caldas, L.V.E.

1983-01-01

A commercial extrapolation chamber (PTW, Germany) was tested in different beta radiation fields and its properties investigated. Its usefullness for beta radiation calibration and dosimetry was demonstrated. (Author) [pt

Measurements of integrated components' parameters versus irradiation doses gamma radiation (60Co) dosimetry-methodology-tests

International Nuclear Information System (INIS)

Fuan, J.

1991-01-01

This paper describes the methodology used for the irradiation of the integrated components and the measurements of their parameters, using Quality Insurance of dosimetry: - Measurement of the integrated dose using the competences of the Laboratoire Central des Industries Electriques (LCIE): - Measurement of irradiation dose versus source/component distance, using a calibrated equipment. - Use of ALANINE dosimeters, placed on the support of the irradiated components. - Assembly and polarization of components during the irradiations. Selection of the irradiator. - Measurement of the irradiated components's parameters, using the competences of the societies: - GenRad: GR130 tests equipement placed in the DEIN/SIR-CEN SACLAY. - Laboratoire Central des Industries Electriques (LCIE): GR125 tests equipment and this associated programmes test [fr

Dosimetry in patients and exposed personnel in endoscopic retrograde cholangio-pancreaticography

Energy Technology Data Exchange (ETDEWEB)

Steinbach, W; Ulrich, F; Richter, K; Schulz, H J [Akademie der Wissenschaften der DDR, Berlin-Buch. Forschungszentrum fuer Molekularbiologie und Medizin

1983-01-01

The gonadal dose for males and the radiation dose of the personnel in endoscopic retrograde cholangio-pancreaticography were determined. The equipment used was a DIAGNOST 70 (Philips-Mueller) with X-ray generator TuR D 1500. Doses were measured with a Kondiometer (Phys. techn. Werkstaetten Dr. Pychlau) using several cylinder and sphere chambers. The gonadal dose per investigation measured for 30 male patients was (124 +- 66) ..mu..Gy or (12.4 +- 6.6) mR, what is appreciably lower than values given by other authors. It is equivalent to a dose value quoted by Radtke for oral or infusion cholegraphy. Additional measurements for smaller groups of patients allow the following conclusions: Radiation burden in the scrotal region of an image-intensifier fluorograph, screen film radiograph and one minute of fluoroscopy are related as 1:10:60. This rule of thumb can be useful for the radiologist for estimating the radiation burden. A calculation of gonadal doses using the procedure-specific mean values of doses shows an agreement by approximately 10%. The fluoroscopy dose fraction was 84% while the intensifier-fluorograms added only 5%. The values for personnel are generally lower than comparable values from the literature, except for the upper arm of the physician handling the endoscope. They are in accordance with hand doses in other types of X-ray investigations.

Dosimetry in patients and exposed personnel in endoscopic retrograde cholangio-pancreaticography

International Nuclear Information System (INIS)

Steinbach, W.; Ulrich, F.; Richter, K.; Schulz, H.J.

1983-01-01

The gonadal dose for males and the radiation dose of the personnel in endoscopic retrograde cholangio-pancreaticography were determined. The equipment used was a DIAGNOST 70 (Philips-Mueller) with X-ray generator TuR D 1500. Doses were measured with a Kondiometer (Phys. techn. Werkstaetten Dr. Pychlau) using several cylinder and sphere chambers. The gonadal dose per investigation measured for 30 male patients was (124 +- 66) μGy or (12.4 +- 6.6) mR, what is appreciably lower than values given by other authors. It is equivalent to a dose value quoted by Radtke for oral or infusion cholegraphy. Additional measurements for smaller groups of patients allow the following conclusions: Radiation burden in the scrotal region of an image-intensifier fluorograph, screen film radiograph and one minute of fluoroscopy are related as 1:10:60. This rule of thumb can be useful for the radiologist for estimating the radiation burden. A calculation of gonadal doses using the procedure-specific mean values of doses shows an agreement by approximately 10%. The fluoroscopy dose fraction was 84% while the intensifier-fluorograms added only 5%. The values for personnel are generally lower than comparable values from the literature, except for the upper arm of the physician handling the endoscope. They are in accordance with hand doses in other types of X-ray investigations. (author)

Thermoluminescence albedo-neutron dosimetry

International Nuclear Information System (INIS)

Strand, T.; Storruste, A.

1986-10-01

The report discusses neutron detection with respect to dosimetry and compares different thermoluminescent dosimetry materials for neutron dosimetry. Construction and calibration of a thermoluminescence albedo neutron dosemeter, developed by the authors, is described

Type test of the Rados MTS-N thermoluminescent dosimetry system for individual monitoring of whole body photons in HP (10)

International Nuclear Information System (INIS)

Ferreira, M.S.; Silva, E.R. da; Maurício, C.L.P.

2017-01-01

The Institute of Radioprotection and Dosimetry (IRD/CNEN-RJ), uses an automatic thermoluminescent dosimetry (TL) system for evaluation of whole body for photons with individual monitors RADOS MTS-N, with TLF detector of LiF: Mg, Ti. The objective of this work was to characterize this system for the evaluation of H P (10) operating magnitude. The measuring range is 0.2 mSv to 2 Sv, for photon energies from 20 keV to 1250 keV. Performance tests were done for the following characteristics: homogeneity of the monitors, system reproducibility, linearity, temperature and humidity effect, energy and angular dependence and fading. The acceptance requirements used to test system performance have been drawn from national and international documents. The results obtained prove that the system can be used to measure the occupational dose of photons in H P (10)

An experience in the management of personal dosimetry and Information and Communication Technologies; Una experiencia en la gestión de la dosimetría personal y las Tecnologías de la Información y las Comunicaciones

Energy Technology Data Exchange (ETDEWEB)

Galán Montenegro, P.; Sánchez Hidalgo, M.; Bodineau, C.; Oliveros Fernández, B.

2015-07-01

One of the most frequently issues raised within the management of hospital personnel dosimetry service is the high incidence of the rate evidencing the lack of dosimeter badges replacement in personnel dosimetry on monthly basis. In this respect and following the enforcement of the dispositions ordered by the CSN (Spanish Nuclear Safety Council as Regulatory Agency) concerning the assignment of “administrative dose”, such rate turns currently into a high number of these doses assigned, thus leading to an inefficient monitoring of the personnel dosimetry. In order to achieve a more suitable dosimetry monitoring it is required a more direct and tailored management of personnel dosimetry in every occupationally exposed workers as well as providing with personal and fluent information. The total number of occupationally exposed workers and the diversity and geographical dispersion of the centers under dosimetry monitoring make impossible a customized management without involving substantial resources. With the aim of achieving a more tailored management in an scenario as the one described above as well as reducing the lack of replacement of dosimeter badges in personnel dosimetry on monthly basis and the administrative doses assigned, some measures were implemented in 2009 by applying Communications and Information Technology platforms and further employees management giving as a result a 75% reduction in the rate of non replacement of dosimeter badges in personnel dosimetry. [Spanish] Una de las cuestiones habitualmente planteada en la gestión de la dosimetría personal hospitalaria es la alta incidencia en la tasa de no recambio mensual de los dosímetros personales y desde la aplicación de la instrucción del Consejo de Seguridad Nuclear (CSN) sobre la asignación de la dosis administrativa, esto supone en la actualidad un alto número de las mencionadas asignaciones; lo que conlleva un deficiente control de la dosimetría personal. Para un mejor control dosim

Applications of gel dosimetry

International Nuclear Information System (INIS)

Ibbott, Geoffrey S

2004-01-01

Gel dosimetry has been examined as a clinical dosimeter since the 1950s. During the last two decades, however, a rapid increase in the number of investigators has been seen, and the body of knowledge regarding gel dosimetry has expanded considerably. Gel dosimetry is still considered a research project, and the introduction of this tool into clinical use is proceeding slowly. This paper will review the characteristics of gel dosimetry that make it desirable for clinical use, the postulated and demonstrated applications of gel dosimetry, and some complications, set-backs, and failures that have contributed to the slow introduction into routine clinical use

Round Robin Test for Performance Demonstration System of Ultrasound Examination Personnel in Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, Young Ho; Yang, Seung Han; Kim, Yong Sik; Yoon, Byung Sik; Lee, Hee Jong

2005-01-01

Ultrasound testing performance during in-service inspection for the main components of NPPs is strongly affected by each examination person. Therefore, ASME established a more strict qualification requirement in Sec. XI Appendix VIII for the ultrasound testing personnel in nuclear power plants. The Korean Performance Demonstration (KPD) System according to the ASME code for the ultrasonic testing personnel, equipments, and procedures to apply to the Class 1 and 2 piping ultrasound examination of nuclear power plants in Korea was established. And a round robin test was conducted in order to verify the effectiveness of PD method by comparing the examination results from the method of Performance Demonstration (PD) and a traditional ASME code dB-drop method. The round robin test shows that the reliability of the PD method is better than that of the dB-drop method. As a result, application of the PD method to the in-service inspection of the nuclear power plants will improve the performance of ultrasound testing

Benefits of online in vivo dosimetry for single-fraction total body irradiation

Energy Technology Data Exchange (ETDEWEB)

Eaton, David J., E-mail: davideaton@nhs.net [Department of Radiotherapy, Royal Free Hospital, London (United Kingdom); Warry, Alison J. [Department of Radiotherapy Physics, University College London Hospital, London (United Kingdom); Trimble, Rachel E.; Vilarino-Varela, Maria J.; Collis, Christopher H. [Department of Radiotherapy, Royal Free Hospital, London (United Kingdom)

2014-01-01

Use of a patient test dose before single-fraction total body irradiation (TBI) allows review of in vivo dosimetry and modification of the main treatment setup. However, use of computed tomography (CT) planning and online in vivo dosimetry may reduce the need for this additional step. Patients were treated using a supine CT-planned extended source-to-surface distance (SSD) technique with lead compensators and bolus. In vivo dosimetry was performed using thermoluminescent dosimeters (TLDs) and diodes at 10 representative anatomical locations, for both a 0.1-Gy test dose and the treatment dose. In total, 28 patients were treated between April 2007 and July 2013, with changes made in 10 cases (36%) following test dose results. Overall, 98.1% of measured in vivo treatment doses were within 10% of the prescribed dose, compared with 97.0% of test dose readings. Changes made following the test dose could have been applied during the single-fraction treatment itself, assuming that the dose was delivered in subportions and online in vivo dosimetry was available for all clinically important anatomical sites. This alleviates the need for a test dose, saving considerable time and resources.

Benefits of online in vivo dosimetry for single-fraction total body irradiation

International Nuclear Information System (INIS)

Eaton, David J.; Warry, Alison J.; Trimble, Rachel E.; Vilarino-Varela, Maria J.; Collis, Christopher H.

2014-01-01

Use of a patient test dose before single-fraction total body irradiation (TBI) allows review of in vivo dosimetry and modification of the main treatment setup. However, use of computed tomography (CT) planning and online in vivo dosimetry may reduce the need for this additional step. Patients were treated using a supine CT-planned extended source-to-surface distance (SSD) technique with lead compensators and bolus. In vivo dosimetry was performed using thermoluminescent dosimeters (TLDs) and diodes at 10 representative anatomical locations, for both a 0.1-Gy test dose and the treatment dose. In total, 28 patients were treated between April 2007 and July 2013, with changes made in 10 cases (36%) following test dose results. Overall, 98.1% of measured in vivo treatment doses were within 10% of the prescribed dose, compared with 97.0% of test dose readings. Changes made following the test dose could have been applied during the single-fraction treatment itself, assuming that the dose was delivered in subportions and online in vivo dosimetry was available for all clinically important anatomical sites. This alleviates the need for a test dose, saving considerable time and resources

MO-B-BRB-04: 3D Dosimetry in End-To-End Dosimetry QA

Energy Technology Data Exchange (ETDEWEB)

Ibbott, G. [UT MD Anderson Cancer Center (United States)

2016-06-15

Full three-dimensional (3D) dosimetry using volumetric chemical dosimeters probed by 3D imaging systems has long been a promising technique for the radiation therapy clinic, since it provides a unique methodology for dose measurements in the volume irradiated using complex conformal delivery techniques such as IMRT and VMAT. To date true 3D dosimetry is still not widely practiced in the community; it has been confined to centres of specialized expertise especially for quality assurance or commissioning roles where other dosimetry techniques are difficult to implement. The potential for improved clinical applicability has been advanced considerably in the last decade by the development of improved 3D dosimeters (e.g., radiochromic plastics, radiochromic gel dosimeters and normoxic polymer gel systems) and by improved readout protocols using optical computed tomography or magnetic resonance imaging. In this session, established users of some current 3D chemical dosimeters will briefly review the current status of 3D dosimetry, describe several dosimeters and their appropriate imaging for dose readout, present workflow procedures required for good dosimetry, and analyze some limitations for applications in select settings. We will review the application of 3D dosimetry to various clinical situations describing how 3D approaches can complement other dose delivery validation approaches already available in the clinic. The applications presented will be selected to inform attendees of the unique features provided by full 3D techniques. Learning Objectives: L. John Schreiner: Background and Motivation Understand recent developments enabling clinically practical 3D dosimetry, Appreciate 3D dosimetry workflow and dosimetry procedures, and Observe select examples from the clinic. Sofie Ceberg: Application to dynamic radiotherapy Observe full dosimetry under dynamic radiotherapy during respiratory motion, and Understand how the measurement of high resolution dose data in an

Dosimetry Measurements around the Angiography Units Using Thermoluminescence Detectors (TLD)

International Nuclear Information System (INIS)

Salah El-den, T.; Shahein, A.Y.; Gomaa, M.A.

2008-01-01

The thermoluminescent dosimeters (TLDs) are widely used not only in the field of personnel monitoring (dosimetry) service for ionizing radiation to medical, and research communities, but also for measurements of X-rays emitted from different angiography's unit. Measurements ionizing radiation around the bed area during cardiac catheterization procedures using X-rays was measured. TLD Badges used to determine the annual effective doses, the safe distance for the staff to minimize radiation exposure and the effectiveness of shield and used leaded apron. The results indicated that annual effective dose for by angiography cardiac Catheterization room may exceed the limits

Impact to non-destructive testing (NDT) companies of PNRI/PSNT trained NDT personnel

International Nuclear Information System (INIS)

De Jesus, Teresita G.

2002-12-01

This research discusses the impact to non-destructive testing (NDT) companies of PNRI/PSNT trained NDT personnel to the individual and to the organization that the individual belongs in the midst of competitive, demanding and fast-paced workplace in the NDT industry. Related literature and studies were carefully chosen and reviewed to validate the consistencies of the research design and data gathering relationship to the present undertaking to previous studies were also discussed and analyzed. The research design used were the descriptive-normative survey method together with a questionnaire consisting of six (6) parts. The first part includes queries on personal/demographic profiles of respondents. The second part contains queries on the level of expectation of the respondents of the job-related variables. The third part contains queries on the levels of adequacy of the organization-related variables. The fourth part consists of questions on the impact of the PNRI/PSNT trained NDT personnel before and after the training. It is divided into two sections, first was for the organization and second was for the individual development. The fifth part was on the analysis of the personal-related factors that influence the impact of the PNRI/PSNT trained NDT personnel. The last part was to find out the significant differences on the impact of the training as to methods. A five-point scale was used to quantify the degree of respondents' responses to queries in the questionnaires. In addition, the following statistical formula were used for treatment of gathered data were frequency percentage, ranking, wilcoxon signed ranks test and spearman rho. The null hypotheses that were presented for acceptance or rejection were also tested. Presentation of findings, analysis and interpretations were presented based on the data gathered and the computations. Recommendations were discussed based on the findings. It is recommended that training of NDT personnel in the different NDT

Radiation protection of medical staff: a coordinated action by EURADOS on extremely dosimetry and the use of active personnel dosemeters (CONRAD)

International Nuclear Information System (INIS)

Struelens, L.; Vanhavere, F.

2009-01-01

Monitoring of workers constitutes an integral part of any radiological protection program. However, unresolved issues in radiation protection of medical staff still remain. Research and establishment of guidelines are necessary on a variety of issues such as extremity dosimetry (fingers, eye lenses, etc), the use of double dosimetry above and below lead aprons, or the use of electronic personal dosimeters in interventional procedures. Medical practices are also evolving fast, and new techniques with ionising radiation emerge very regularly, thus implying the need of radiation protection measures for medical staff, and the implementation of new monitoring programs. In some medical applications of radiation there is an increased risk of high local exposures because of direct handling of sources or the use of beta-emitters. However, despite the large number of workers that are exposed in the medical field worldwide, only few measurements of extremity doses have been reported in the literature. Some activities of EURADOS Working Group 9 (WG9) were sponsored by the European Commission in the CONRAD project. This CONRAD project was aiming at the coordination of research on radiation protection at the workplace. Working group 9 has been involved in the coordination and promotion of European research in the field of Radiation Protection Dosimetry for Medical Staff. One of the objectives of this working group was to formulate the state of the art and to identify areas in which improvements were needed. For some of these medical applications the skin of the fingers is the limiting organ from the point of view of individual monitoring of external radiation. The wide variety of radiation field characteristics in a medical environment, and the difficulty of measuring a local dose that is representative for the maximum skin dose (usually with one single detector), makes it difficult to perform extremity dosimetry with an accuracy similar to whole-body dosimetry. Therefore a

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2010-01-01

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the

Comparisons between direct ion storage and thermoluminescence dosimetry individual monitoring systems, and internet reporting

International Nuclear Information System (INIS)

Kiuru, A.; Kahilainen, J.; Hyvoenen, H.; Vartiainen, E.

2001-01-01

A new electronic direct ion storage (DIS) dosemeter allows accumulated personal dose equivalent H p (d) at depths of 10 mm and 0.07 mm to be monitored in a few seconds by inserting the dosemeter into a local reader without deleting the accumulated dose. The DIS system meets general requirements on individual monitoring of hospital personnel using ionising radiation. It differs greatly from off-line thermoluminescence dosimetry systems and offers many additional benefits. The non-volatile reading takes only 5 s, is taken as often as needed, and the data are collected into a dose database, where background radiation is subtracted. Individual personnel doses are reported in Intranet as well as on the Internet at regular intervals to the National Regulatory Authorities. (author)

Some aspects of the use of proton recoil proportional counters for fast neutron personnel dosimeters

International Nuclear Information System (INIS)

Yule, T.J.; Bennett, E.F.

1984-01-01

Gas-filled proton recoil proportional counters have been used extensively for the measurement of neutron spectra in degraded fission-spectrum environments. Some considerations relating to the use of these counters for personnel dosimetry are here described. High sensitivity and good accuracy in the determination of dose-equivalent can be obtained if relatively high pressure hydrogen-filled proportional counters are used as the active element in a dosimeter system

Accuracy in HIV Rapid Testing among Laboratory and Non-laboratory Personnel in Zambia: Observations from the National HIV Proficiency Testing System.

Directory of Open Access Journals (Sweden)

Sheila Mwangala

Full Text Available Despite rapid task-shifting and scale-up of HIV testing services in high HIV prevalence countries, studies evaluating accuracy remain limited. This study aimed to assess overall accuracy level and factors associated with accuracy in HIV rapid testing in Zambia.Accuracy was investigated among rural and urban HIV testing sites participating in two annual national HIV proficiency testing (PT exercises conducted in 2009 (n = 282 sites and 2010 (n = 488 sites. Testers included lay counselors, nurses, laboratory personnel and others. PT panels of five dry tube specimens (DTS were issued to testing sites by the national reference laboratory (NRL. Site accuracy level was assessed by comparison of reported results to the expected results. Non-parametric rank tests and multiple linear regression models were used to assess variation in accuracy between PT cycles and between tester groups, and to examine factors associated with accuracy respectively.Overall accuracy level was 93.1% (95% CI: 91.2-94.9 in 2009 and 96.9% (95% CI: 96.1-97.8 in 2010. Differences in accuracy were seen between the tester groups in 2009 with laboratory personnel being more accurate than non-laboratory personnel, while in 2010 no differences were seen. In both PT exercises, lay counselors and nurses had more difficulties interpreting results, with more occurrences of false-negative, false-positive and indeterminate results. Having received the standard HIV rapid testing training and adherence to the national HIV testing algorithm were positively associated with accuracy.The study showed an improvement in tester group and overall accuracy from the first PT exercise to the next. Average number of incorrect test results per 1000 tests performed was reduced from 69 to 31. Further improvement is needed, however, and the national HIV proficiency testing system seems to be an important tool in this regard, which should be continued and needs to be urgently strengthened.

Nuclear accident dosimetry systems: U.K. measurements at the sixteenth intercomparison at O.R.N.L. August 1979

International Nuclear Information System (INIS)

Delafield, H.J.; Gibson, J.A.B.; Holt, P.D.; Harrison, K.G.

1980-04-01

The results are presented of the measurements made by the A.E.R.E., Harwell participants at the Intercomparison of Nuclear Accident Dosimetry Systems held at the Dosimetry Applications Research Facility (DOSAR) of the Oak Ridge National Laboratory, USA from 13 - 17 August 1979. The source of pulsed radiation used was the Health Physics Research Reactor which was operated bare for pulse 1, and shielded by concrete (20cm thickness) and steel (5cm thickness) for pulses 2 and 3 respectively. Measurements are reported which were made using personnel dosimeters (both in free-air and on phantoms) and a threshold detector system and compared with the provisional results given by the DOSAR group at the meeting. (U.K.)

Hybrid GPU-CPU adaptive precision ray-triangle intersection tests for robust high-performance GPU dosimetry computations

International Nuclear Information System (INIS)

Perrotte, Lancelot; Bodin, Bruno; Chodorge, Laurent

2011-01-01

Before an intervention on a nuclear site, it is essential to study different scenarios to identify the less dangerous one for the operator. Therefore, it is mandatory to dispose of an efficient dosimetry simulation code with accurate results. One classical method in radiation protection is the straight-line attenuation method with build-up factors. In the case of 3D industrial scenes composed of meshes, the computation cost resides in the fast computation of all of the intersections between the rays and the triangles of the scene. Efficient GPU algorithms have already been proposed, that enable dosimetry calculation for a huge scene (800000 rays, 800000 triangles) in a fraction of second. But these algorithms are not robust: because of the rounding caused by floating-point arithmetic, the numerical results of the ray-triangle intersection tests can differ from the expected mathematical results. In worst case scenario, this can lead to a computed dose rate dramatically inferior to the real dose rate to which the operator is exposed. In this paper, we present a hybrid GPU-CPU algorithm to manage adaptive precision floating-point arithmetic. This algorithm allows robust ray-triangle intersection tests, with very small loss of performance (less than 5 % overhead), and without any need for scene-dependent tuning. (author)

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

Methods and Models of the Hanford Internal Dosimetry Program, PNNL-MA-860

Energy Technology Data Exchange (ETDEWEB)

Carbaugh, Eugene H.; Bihl, Donald E.; Maclellan, Jay A.; Antonio, Cheryl L.; Hill, Robin L.

2009-09-30

The Hanford Internal Dosimetry Program (HIDP) provides internal dosimetry support services for operations at the Hanford Site. The HIDP is staffed and managed by the Radiation and Health Technology group, within the Pacific Northwest National Laboratory (PNNL). Operations supported by the HIDP include research and development, the decontamination and decommissioning of facilities formerly used to produce and purify plutonium, and waste management activities. Radioelements of particular interest are plutonium, uranium, americium, tritium, and the fission and activation product radionuclides 137Cs, 90Sr, and 60Co. This manual describes the technical basis for the design of the routine bioassay monitoring program and for assessment of internal dose. The purposes of the manual are as follows: • Provide assurance that the HIDP derives from a sound technical base. • Promote the consistency and continuity of routine program activities. • Provide a historical record. • Serve as a technical reference for radiation protection personnel. • Aid in identifying and planning for future needs.

Thermoluminescence in medical dosimetry

International Nuclear Information System (INIS)

Rivera, T.

2011-10-01

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)

Neutron dosimetry - A review

Energy Technology Data Exchange (ETDEWEB)

Baum, J W

1955-03-29

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)

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

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

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...... 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 leading...

EPR dosimetry - present and future

International Nuclear Information System (INIS)

Regulla, D.F.

1999-01-01

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)

LWR surveillance dosimetry improvement program: PSF metallurgical blind test results

International Nuclear Information System (INIS)

Kam, F.B.K.; Maerker, R.E.; Stallmann, F.W.

1984-01-01

The metallurgical irradiation experiment at the Oak Ridge Research Reactor Poolside Facility (ORR-PSF) was designed as a benchmark to test the accuracy of radiation embrittlement predictions in the pressure vessel wall of light water reactors on the basis of results from surveillance capsules. The PSF metallurgical Blind Test is concerned with the simulated surveillance capsule (SSC) and the simulated pressure vessel capsule (SPVC). The data from the ORR-PSF benchmark experiment are the basis for comparison with the predictions made by participants of the metallurgical ''Blind Test''. The Blind Test required the participants to predict the embrittlement of the irradiated specimen based only on dosimetry and metallurgical data from the SSC1 capsule. This exercise included both the prediction of damage fluence and the prediction of embrittlement based on the predicted fluence. A variety of prediction methodologies was used by the participants. No glaring biases or other deficiencies were found, but neither were any of the methods clearly superior to the others. Closer analysis shows a rather complex and poorly understood relation between fluence and material damage. Many prediction formulas can give an adequate approximation, but further improvement of the prediction methodology is unlikely at this time given the many unknown factors. Instead, attention should be focused on determining realistic uncertainties for the predicted material changes. The Blind Test comparisons provide some clues for the size of these uncertainties. In particular, higher uncertainties must be assigned to materials whose chemical composition lies outside the data set for which the prediction formula was obtained. 16 references, 14 figures, 5 tables

Dosimetry for audit and clinical trials: challenges and requirements

International Nuclear Information System (INIS)

Kron, T; Haworth, A; Williams, I

2013-01-01

Many important dosimetry audit networks for radiotherapy have their roots in clinical trial quality assurance (QA). In both scenarios it is essential to test two issues: does the treatment plan conform with the clinical requirements and is the plan a reasonable representation of what is actually delivered to a patient throughout their course of treatment. Part of a sound quality program would be an external audit of these issues with verification of the equivalence of plan and treatment typically referred to as a dosimetry audit. The increasing complexity of radiotherapy planning and delivery makes audits challenging. While verification of absolute dose delivered at a reference point was the standard of external dosimetry audits two decades ago this is often deemed inadequate for verification of treatment approaches such as Intensity Modulated Radiation Therapy (IMRT) and Volumetric Modulated Arc Therapy (VMAT). As such, most dosimetry audit networks have successfully introduced more complex tests of dose delivery using anthropomorphic phantoms that can be imaged, planned and treated as a patient would. The new challenge is to adapt this approach to ever more diversified radiotherapy procedures with image guided/adaptive radiotherapy, motion management and brachytherapy being the focus of current research.

Alanine dosimetry for clinical applications. Proceedings

International Nuclear Information System (INIS)

Anton, M.

2006-05-01

The following topics are dealt with: Therapy level alanine dosimetry at the UK Nationational Physical Laboratory, alanine as a precision validation tool for reference dosimetry, composition of alanine pellet dosimeters, the angular dependence of the alanine ESR spectrum, the CIAE alanine dosimeter for radiotherapy level, a correction for temporal evolution effects in alanine dosimetry, next-generation services foe e-traceability to ionization radiation national standards, establishing e-traceability to HIST high-dose measurement standards, alanine dosimetry of dose delivery from clinical accelerators, the e-scan alanine dosimeter reader, alanine dosimetry at ISS, verification of the integral delivered dose for IMRT treatment in the head and neck region with ESR/alanine dosimetry, alanine dosimetry in helical tomotherapy beams, ESR dosimetry research and development at the University of Palermo, lithium formate as a low-dose EPR radiation dosimeter, sensitivity enhancement of alanine/EPR dosimetry. (HSI)

Developments in physical dosimetry and radiation protection; Entwicklungen in der physikalischen Dosimetrie im Strahlenschutz

Energy Technology Data Exchange (ETDEWEB)

Fiebich, Martin [Technische Hochschule Mittelhessen, Giessen (Germany). Inst. fuer Medizinische Physik und Strahlenschutz

2017-07-01

In the frame of physical dosimetry new dose units have been defined: the depth personal dose (equivalent dose in 10 mm depth) and the surface personal dose (equivalent dose in 0.07 mm depth). Physical dosimetry is applied for the determination of occupational radiation exposure, the radiation protected area control, the estimation of radiation exposure of patients during radiotherapy, for quality assurance and in research projects and optimization challenges. Developments have appeared with respect to punctual measuring chambers, eye lens dosimetry, OSL (optically stimulated luminescence) dosimetry, real-time dosimetry and Monte Carlo methods. New detection limits of about 1 micro Gy were reached.

A transferability study of the EPR-tooth-dosimetry technique

International Nuclear Information System (INIS)

Sholom, S.; Chumak, V.; Desrosiers, M.; Bouville, A.

2006-01-01

The transferability of a measurement protocol from one laboratory to another is an important feature of any mature, standardised protocol. The electron paramagnetic resonance (EPR)-tooth dosimetry technique that was developed in Scientific Center for Radiation Medicine, AMS (Ukraine) (SCRM) for routine dosimetry of Chernobyl liquidators has demonstrated consistent results in several inter-laboratory measurement comparisons. Transferability to the EPR dosimetry laboratory at the National Inst. of Standards and Technology (NIST) was examined. Several approaches were used to test the technique, including dose reconstruction of SCRM-NIST inter-comparison samples. The study has demonstrated full transferability of the technique and the possibility to reproduce results in a different laboratory environment. (authors)

1983 international intercomparison of nuclear accident dosimetry systems at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Swaja, R.E.; Greene, R.T.; Sims, C.S.

1985-04-01

An international intercomparison of nuclear accident dosimetry systems was conducted during September 12-16, 1983, at Oak Ridge National Laboratory (ORNL) using the Health Physics Research Reactor operated in the pulse mode to simulate criticality accidents. This study marked the twentieth in a series of annual accident dosimetry intercomparisons conducted at ORNL. Participants from ten organizations attended this intercomparison and measured neutron and gamma doses at area monitoring stations and on phantoms for three different shield conditions. Results of this study indicate that foil activation techniques are the most popular and accurate method of determining accident-level neutron doses at area monitoring stations. For personnel monitoring, foil activation, blood sodium activation, and thermoluminescent (TL) methods are all capable of providing accurate dose estimates in a variety of radiation fields. All participants in this study used TLD's to determine gamma doses with very good results on the average. Chemical dosemeters were also shown to be capable of yielding accurate estimates of total neutron plus gamma doses in a variety of radiation fields. While 83% of all neutron measurements satisfied regulatory standards relative to reference values, only 39% of all gamma results satisfied corresponding guidelines for gamma measurements. These results indicate that continued improvement in accident dosimetry evaluation and measurement techniques is needed

Skin dosimetry - radiological protection aspects of skin dosimetry

International Nuclear Information System (INIS)

Dennis, J.A.

1991-01-01

Following a Workshop in Skin Dosimetry, a summary of the radiological protection aspects is given. Aspects discussed include routine skin monitoring and dose limits, the need for careful skin dosimetry in high accidental exposures, techniques for assessing skin dose at all relevant depths and the specification of dose quantities to be measured by personal dosemeters and the appropriate methods to be used in their calibration. (UK)

Czech results at criticality dosimetry intercomparison 2002.

Science.gov (United States)

Frantisek, Spurný; Jaroslav, Trousil

2004-01-01

Two criticality dosimetry systems were tested by Czech participants during the intercomparison held in Valduc, France, June 2002. The first consisted of the thermoluminescent detectors (TLDs) (Al-P glasses) and Si-diodes as passive neutron dosemeters. Second, it was studied to what extent the individual dosemeters used in the Czech routine personal dosimetry service can give a reliable estimation of criticality accident exposure. It was found that the first system furnishes quite reliable estimation of accidental doses. For routine individual dosimetry system, no important problems were encountered in the case of photon dosemeters (TLDs, film badge). For etched track detectors in contact with the 232Th or 235U-Al alloy, the track density saturation for the spark counting method limits the upper dose at approximately 1 Gy for neutrons with the energy >1 MeV.

Analysis of Personal Dosimetry for Nuclear Medicine Staff in Ten-Year Period

International Nuclear Information System (INIS)

Poropat, M.; Dodig, D.; Ciglar, M.; Tezak, S.

2011-01-01

The aim of this study was to assess the value of personal dosimetry for nuclear medicine personnel in our department in a ten-year period. We have analyzed personal doses for 80 employees in nuclear medicine in a ten year period that we divided into two five year periods (from 2000 to 2004 and from 2005 to 2009). The personnel was dived into 8 groups according to their working assignments due to different radiation exposure from various radioisotopes in different wards in nuclear medicine: nuclear medicine specialists, technologists in scintigraphy ward, personnel of physics ward, ward for radiochemistry and radioimmunology, clinical ward and ultrasound ward, cleaning personnel, administrative personnel. We have compared average dose per person in particular ward in two five year periods. All doses for all personnel were in the permissible limits prescribed by the authorities. Higher average dose per person in a first five year period was detected in two wards, scintigraphy ward and ward for radiochemistry and radioimmunology due to the nature of their working assignments (preparation and application of radiopharmaceuticals, contact with patients who have received radiopharmaceutical). The decrease in the average dose per person was noticed in a second five-year period, especially in the wards with personnel that had no prior education in ionizing radiation protection. The decrease of dose was from 7.5 % to 84.2 %. We think that the decrease of average dose per person in a second five-year period was not only the result of the increased personal protection measures but also the result of continuing education of nuclear medicine personnel that is obligatory by the Law for ionizing radiation protection from year 1999, and the results from a ten-year period show its positive effect on radiation protection. (author)

ESR Dosimetry

International Nuclear Information System (INIS)

Baffa, Oswaldo; Rossi, Bruno; Graeff, Carlos; Kinoshita, Angela; Chen Abrego, Felipe; Santos, Adevailton Bernardo dos

2004-01-01

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

Film badge personnel monitoring and dose distribution of industrial and medical workers in the country (1994-1998)

International Nuclear Information System (INIS)

Mittal, Hariom; Pandey, R.L.; Massand, O.P.

2001-03-01

Personnel Monitoring Section, Bhabha Atomic Research Centre, Mumbai, is entrusted with the responsibility of providing a countrywide personnel monitoring to radiation workers using extemal radiation like X, beta, gamma and neutron. As per Radiation Protection Rules (RPR) of 1971 promulgated by the competent authority the personnel monitoring service is mandatory for all the workers working with radiation. The radiation exposures received by them should be within the limits stipulated by AERB. Nearly 43,000 radiation workers in about 3000 DAE and non DAE institutions using radiation and radioisotopes are monitored, using both the Film Badges and the Thermoluminescent dosimeters. This report presents various aspects of film dosimetry which was introduced more than four decades ago in the country and also analysis of doses received by the radiation workers in the five year block 1994-1998 covered by film badge service. (author)

Experiences and performance of the Harshaw dosimetry system at two major processing centres

International Nuclear Information System (INIS)

Tawil, R.A.; Olhalber, T.; Rathbone, B.

1996-01-01

The installations, operating practice, dose algorithms and results and maintenance experience at two major dosimetry processing centres are described. System selection considerations and a comprehensive quality programme are described in the light of the publication of testing requirements by various dosimetry regulatory organisations. Reported information from Siemens Dosimetry Services comprises their selection of dosemeters and processing equipment including service history, a description of their dose computation algorithm, and detailed results of their testing against DOELAP standards. Battelle Pacific Northwest Laboratories (PNL) provides a description of their dosemeters and equipment with service history; in addition, a discussion of their new neural network approach to a dose computation algorithm and test results from that algorithm are presented. (Author)

Clinical application of in vivo dosimetry for external telecobalt machine

International Nuclear Information System (INIS)

Mohammed, H. H. M.

2011-01-01

In external beam radiotherapy quality assurance is carried out on the individual components of treatment chain. The patient simulating device, planning system and treatment machine are tested regularly according to set protocols developed by national and international organizations. Even thought these individual systems are not tested for errors which can be made in the transfer between the systems. The best quality assurance for the treatment planning chain. In vivo dosimetry is used as a quality assurance tool for verifying dosimetry as either the entrance or exit surface of the patient undergoing external beam radiotherapy. It is a proven reliable method of checking overall treatment accuracy, allowing verification of dosimetry and dose calculation as well as patient treatment setup. Accurate in vivo dosimetry is carried out if diodes and thermoluminescence dosimeters (TLDs). the main detector types in use for in vivo dosimetry, are carefully calibrated and the factors influencing their sensitivity are taken into account. The aim of this study was to verify the response of TLDs type (LiF: Mg, Cu, p) use in radiotherapy, to establish calibration procedure for TLDs and to evaluate entrance dose obtained by the treatment planning system with measured dose using thermoluminescence detectors. Calibration of TLDs was done using Cobalt-60 teletherapy machine, linearity and calibration factors were determined. Measurements were performed in random phantom for breast irradiation (for the breast irradiation ( For the breast irradiation technique considered, wedge field was used). All TLDs were processed and analyzed at RICK. In vivo dosimetry represents a technique that has been widely employed to evaluate the dose to the patient mainly in radiotherapy. Thermoluminescent dosimeters are considered the gold stander for in vivo dosimetry and do not require cables for measurements which makes them ideal for mail based studies and have no dose rate or temperature dependence

Nuclear radiation monitoring instruments for personnel in nuclear disaster for defence needs

International Nuclear Information System (INIS)

Bhatnagar, P.K.; Vaijapurkar, S.G.; Yadav, Ashok

2005-01-01

Ever since the tragedy of nuclear device exploding over Japan by USA in 1945 awareness exists amongst the armed forces personnel all over the world that a requirement of implementing radiological protection is imminent. Towards this adoption of radiological safety programme is a criterion. In a nuclear war disaster scenario, one encounters initial nuclear radiation (gamma and neutron radiations), gamma radiations from fallout, heat and blast. At certain distances Tanks/ armoured vehicles will survive and 4 R/s radiation level sensing to actuate relays for closing the ports of vehicles is essential, leading to reduction in inhalation, ingestion of fallout radioactivity and reduction in radiation dose received by occupants of the vehicle. Towards this sturdy radiation monitors to indicate gamma dose rate of the order of 1000 R/h, gamma and neutron dosimeters of the order of 1000 cGy with reading instruments are to be developed. These must work in harsh environment and sustain JSS 55555 conditions of army. Defence Laboratory, Jodhpur over past one decade has been involved in developing personnel, area and field monitoring instruments like dosimeters, survey meters, which are useful, acceptable to army personnel, armoured and personnel carrier vehicles, field structures/shelters. Technology transfer after satisfaction of armed forces, product ionisation and supply, maintenance, training has been the endeavor of the DRDO. Herein it is proposed to highlight the techno electronics nuclear radiation monitoring sensors and associated electronics systems developed first time in the country and productionised in bulk for Services for implementing personnel protection. The sensors developed and described are - Radiophotoluminescent Glass (RPLG) for gamma radiation dosimetry , neutron sensitive PIN diode for fast neutron dosimetry, gamma radiation sensitive PIN diode, superheated liquid neutron and gamma sensors. The dosimeter, dose rate meter and field/area instruments are

Accreditation and training on internal dosimetry in a laboratory network in Brazil: an increasing demand.

Science.gov (United States)

Dantas, B M; Dantas, A L A; Acar, M E D; Cardoso, J C S; Julião, L M Q C; Lima, M F; Taddei, M H T; Arine, D R; Alonso, T; Ramos, M A P; Fajgelj, A

2011-03-01

In recent years, Brazilian Nuclear Programme has been reviewed and updated by government authorities in face of the demand for energy supply and its associated environmental constraints. The immediate impact of new national programmes and projects in nuclear field is the increase in the number of exposed personnel and the consequent need for reliable dosimetry services in the country. Several Technical Documents related to internal dosimetry have been released by the International Atomic Energy Agency and International Commission on Radiological Protection. However, standard bioassay procedures and methodologies for bioassay data interpretation are still under discussion and, in some cases, both in routine and emergency internal monitoring, procedures can vary from one laboratory to another and responses may differ markedly among Dosimetry Laboratories. Thus, it may be difficult to interpret and use bioassay data generated from different laboratories of a network. The main goal of this work is to implement a National Network of Laboratories aimed to provide reliable internal monitoring services in Brazil. The establishment of harmonised in vivo and in vitro radioanalytical techniques, dose assessment methods and the implementation of the ISO/IEC 17025 requirements will result in the recognition of technical competence of the network.

Dosimetry of ionizing radiation

International Nuclear Information System (INIS)

Musilek, L.; Seda, J.; Trousil, J.

1992-01-01

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

Tissue equivalence in neutron dosimetry

International Nuclear Information System (INIS)

Nutton, D.H.; Harris, S.J.

1980-01-01

A brief review is presented of the essential features of neutron tissue equivalence for radiotherapy and gives the results of a computation of relative absorbed dose for 14 MeV neutrons, using various tissue models. It is concluded that for the Bragg-Gray equation for ionometric dosimetry it is not sufficient to define the value of W to high accuracy and that it is essential that, for dosimetric measurements to be applicable to real body tissue to an accuracy of better than several per cent, a correction to the total absorbed dose must be made according to the test and tissue atomic composition, although variations in patient anatomy and other radiotherapy parameters will often limit the benefits of such detailed dosimetry. (U.K.)

Clinical dosimetry

International Nuclear Information System (INIS)

Rassow, J.

1973-01-01

The main point of this paper on clinical dosimetry which is to be understood here as application of physical dosimetry on accelerators in medical practice, is based on dosimetric methodics. Following an explanation of the dose parameters and description of the dose distribution important for clinical practice as well as geometric irradiation parameters, the significance of a series of physical parameters such as accelerator energy, surface energy of average stopping power etc. is dealt with in detail. Following a section on field homogenization with bremsstrahlung and electron radiation, details on dosimetry in clinical practice are given. Finally, a few problems of dosemeter or monitor calibration on accelerators are described. The explanations are supplemented by a series of diagrams and tables. (ORU/LH) [de

Fast neutron spectrometry and dosimetry; Spectrometrie et dosimetrie des neutrons rapides

Energy Technology Data Exchange (ETDEWEB)

Blaize, S; Ailloud, J; Mariani, J; Millot, J P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

We have studied fast neutron spectrometry and dosimetry through the recoil protons they produce in hydrogenated samples. In spectrometric, we used nuclear emulsions, in dosimetric, we used polyethylene coated with zinc sulphide and placed before a photomultiplier. (author)Fren. [French] Nous avons etudie la spectrometrie et la dosimetrie des neutrons rapides en utilisant les protons de recul qu'ils produisent dans une matiere hydrogenee. En spectrometrie, nous avons employe des emulsions nucleaires, en dosimetrie, du polyethylene recouvert de sulfure de zinc place devant un photomultiplicateur. (auteur)

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

International Nuclear Information System (INIS)

Lyutsko, A.M.; Nesterenko, V.B.; Chudakov, V.A.; Konoplya, E.F.; Milyutin, A.A.

1997-10-01

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

Neutron dosimetry at commercial nuclear plants. Final report of Subtask B: dosimeter response

Energy Technology Data Exchange (ETDEWEB)

Cummings, F.M.; Endres, G.W.R.; Brackenbush, L.W.

1983-03-01

As part of a larger program to evaluate personnel neutron dosimetry at commercial nuclear power plants, this study was designed to characterize neutron dosimeter responses inside the containment structure of commercial nuclear plants. In order to characterize those responses, dosimeters were irradiated inside containment at 2 pressurized water reactors and at pipe penetrations outside the biological shield at two boiling water reactors. The reactors were operating at full power during the irradiations. Measurements were also performed with electronic instruments, the tissue equivalent proportional counter (TEPC), and portable remmeters, SNOOPY, RASCAL and PNR-4.

Neutron dosimetry at commercial nuclear plants. Final report of Subtask B: dosimeter response

International Nuclear Information System (INIS)

Cummings, F.M.; Endres, G.W.R.; Brackenbush, L.W.

1983-03-01

As part of a larger program to evaluate personnel neutron dosimetry at commercial nuclear power plants, this study was designed to characterize neutron dosimeter responses inside the containment structure of commercial nuclear plants. In order to characterize those responses, dosimeters were irradiated inside containment at 2 pressurized water reactors and at pipe penetrations outside the biological shield at two boiling water reactors. The reactors were operating at full power during the irradiations. Measurements were also performed with electronic instruments, the tissue equivalent proportional counter (TEPC), and portable remmeters, SNOOPY, RASCAL and PNR-4

The PADE dosimetry system at the Brokdorf nuclear power station

International Nuclear Information System (INIS)

Poetter, Karl-Friedrich; Eckelmann, Joerg; Kuegow, Mario; Spahn, Werner; Franz, Manfred

2002-01-01

The PADE program system is used in nuclear power plants for personnel and workplace dosimetry and for managing access to the controlled area. On-line interfaces with existing dose determination systems allow collection, surveillance and evaluation functions to be achieved for person-related and workplace-related dose data. This is managed by means of open, non-proprietary communication of PADE with the computer system coupled via interfaces. In systems communication, PADE is limited to main interventions into outside systems, thus ensuring flexible adaptation to existing systems. As a client-server solution, PADE has been developed on the basis of an ORACLE-8 database; the version presented here runs on a Windows NT server. The system described has been used at the Brokdorf Nuclear Power Station since early 2000 and has so far reliably managed more than one million individual access movements of more than 6 000 persons. It is currently being integrated into a comprehensive plant operations management system. Among other things, PADE offers a considerable development potential for a tentatively planned future standardization of parts of the dosimetry systems in German nuclear power plants and for the joint management of in-plant and official dose data. (orig.) [de

Dosimetry for radiation processing

International Nuclear Information System (INIS)

McLaughlin, W.L.; Boyd, A.W.; Chadwick, K.H.; McDonald, J.C.; Miller, A.

1989-01-01

Radiation processing is a relatively young industry with broad applications and considerable commercial success. Dosimetry provides an independent and effective way of developing and controlling many industrial processes. In the sterilization of medical devices and in food irradiation, where the radiation treatment impacts directly on public health, the measurements of dose provide the official means of regulating and approving its use. In this respect, dosimetry provides the operator with a means of characterizing the facility, of proving that products are treated within acceptable dose limits and of controlling the routine operation. This book presents an up-to-date review of the theory, data and measurement techniques for radiation processing dosimetry in a practical and useful way. It is hoped that this book will lead to improved measurement procedures, more accurate and precise dosimetry and a greater appreciation of the necessity of dosimetry for radiation processing. (author)

Thin film tritium dosimetry

Science.gov (United States)

Moran, Paul R.

1976-01-01

The present invention provides a method for tritium dosimetry. A dosimeter comprising a thin film of a material having relatively sensitive RITAC-RITAP dosimetry properties is exposed to radiation from tritium, and after the dosimeter has been removed from the source of the radiation, the low energy electron dose deposited in the thin film is determined by radiation-induced, thermally-activated polarization dosimetry techniques.

JENDL dosimetry file 99 (JENDL/D-99)

International Nuclear Information System (INIS)

Kobayashi, Katsuhei; Iwasaki, Shin

2002-01-01

The JENDL Dosimetry File 99 (JENDL/D-99), which is a revised version of the JENDL Dosimetry File 91 (JENDL/D-91), has been compiled and released for the determination of neutron flux and energy spectra. This work was undertaken to remove the inconsistency between the cross sections and their covariances in JENDL/D-91 since the covariances were mainly taken from IRDF-85 although the cross sections were based on JENDL-3. Dosimetry cross sections have been evaluated for 67 reactions on 47 nuclides together with covariances. The cross sections for 34 major reactions and their covariances were simultaneously generated, and the remaining 33 reaction data were mainly taken from JENDL/D-91. Latest measurements were taken into account in the evaluation. The resultant evaluated data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-6 format. In order to confirm the reliability of the evaluated data, several integral tests have been carried out: comparisons with average cross sections measured in fission neutron fields, fast/thermal reactor spectra, DT neutron fields and Li(d,n) neutron fields. It was found from the comparisons that the cross sections calculated from JENDL/D-99 are generally in good agreement with the measured data. The contents of JENDL/D-99 and the results of the integral tests are described in this report. All of the dosimetry cross sections are shown in a graphical form in the Appendix. (author)

Enlisted Personnel Individualized Career System (EPICS) Test and Evaluation

Science.gov (United States)

1984-01-01

The EPICS program, which was developed using an integrated personnel systems approach ( IPSA ), delays formal school training until after personnel have...received shipboard on-job training complemented by job performance aids (3PAs). Early phases of the program, which involved developing the IPSA EPICS...detailed description of the conception and development of the EPICS IPSA model, the execution of the front-end job design analyses, 3PA and instructional

Development of a drift tissue equivalent proportional counter for radiation protection personnel dosimetry

International Nuclear Information System (INIS)

Bordy, J.M.

1992-04-01

A new multicellular geometry for proportional counter has been developed. It is made of several drift regions which are some holes drilled in the cathode in front of anodes wires. The present work is made of 3 parts: 1) A theoretical evaluation of the multicellular counter characteristics: the sensitivity increases by a factor 15 vs the Tinelli Merlin-Gerin counter; the chord length distribution study shows the possibility to use a Dirac function for the dosimetry calculations; a tissue equivalent gas mixture based on argon and propane is designed. 2) The production of a monocellular prototype made of a hole and a needle shaped anode. 3) An experimental study of the prototype electrical characteristics and a computation of the electrical field in the counter. The focalization and the electron drift into the hole, the proportional operating mode are shown. Irradiations in front of photon and neutron sources verify these results

Direct ion storage dosimetry systems for photon, beta and neutron radiation with instant readout capabilities

International Nuclear Information System (INIS)

Wernli, C.; Kahilainen, J.

2001-01-01

The direct ion storage (DIS) dosemeter is a new type of electronic dosemeter from which the dose information for both H p (10) and H p (0.07) can be obtained instantly at the workplace by using an electronic reader unit. The number of readouts is unlimited and the stored information is not affected by the readout procedure. The accumulated dose can also be electronically reset by authorised personnel. The DIS dosemeter represents a potential alternative for replacing the existing film and thermoluminescence dosemeters (TLDs) used in occupational monitoring due to its ease of use and low operating costs. The standard version for normal photon and beta dosimetry, as well as a developmental version for neutron dosimetry, have been characterised in several field studies. Two new small size variations are also introduced including a contactless readout device and a militarised version optimised for field use. (author)

I.R.D. annual report - 1988. Institute of Radioprotection and Dosimetry of Brazilian Nuclear Energy Commission (CNEN)

International Nuclear Information System (INIS)

1989-01-01

This is the annual report of the activities developed by the Institute of Radioprotection and Dosimetry -IRD/CNEN-Brazil, in the year of 1988. It is composed by the individual reports of its several divisions, describing the main activities and personnel: DEPRO - Occupational and Radiological Protection Dept.; DEPRA - Environmental and Radiological Protection Dept.; DEMET - Metrology Dept.; DEPAT - Technical Support Dept.; DETAC - Scientific Support and Training Dept.; DEPAD -Administrative Support Dept. (J.A.M.M.)

High energy dosimetry

International Nuclear Information System (INIS)

Ruhm, W.

2010-01-01

Full text: Currently, quantification of doses from high-energy radiation fields is a topical issue. This is so because high-energy neutrons play an important role for radiation exposure of air crew members and personnel outside the shielding of ion therapy facilities. In an effort to study air crew exposure from cosmic radiation in detail, two Bonner Sphere Spectrometers (BSSs) have recently been installed to measure secondary neutrons from cosmic radiation, one at the environmental research station 'Schneefernerhaus' at an altitude of 2650 m on the Zugspitze mountain, Germany, the other at the Koldewey station close to the North Pole on Spitsbergen. Based on the measured neutron fluence distributions and on fluence-to-dose conversion coefficients, mean ambient dose equivalent rate values of 75.0 ± 2.9 nSv/h and 8.7 ± 0.6 nSv/h were obtained for October 2008, respectively. Neutrons with energies above about 20 MeV contribute about 50% to dose, at 2650 m. Ambient dose equivalent rates measured by means of a standard rem counter and an extended rem counter at the Schneefernerhaus confirm this result. In order to study the response of state-of-the-art radiation instrumentation in such a high-energy radiation field, a benchmark exercise that included both measurements in and simulation of the stray neutron radiation field at the high-energy particle accelerator at GSI, Germany, were performed. This CONRAD (COordinated Network for RAdiation Dosimetry) project was funded by the European Commission, and the organizational framework was provided by the European Radiation Dosimetry Group, EURADOS. The Monte Carlo simulations of the radiation field and the experimental determination of the neutron spectra with various Bonner Sphere Spectrometers suggest the neutron fluence distributions to be very similar to those of secondary neutrons from cosmic radiation. The results of this intercomparison exercise in terms of ambient dose equivalent are also discussed

Criticality accident dosimetry with ESR spectroscopy.

Science.gov (United States)

d'Errico, F; Fattibene, P; Onori, S; Pantaloni, M

1996-01-01

The suitability of the ESR alanine and sugar detectors for criticality accident dosimetry was experimentally investigated during an intercomparison of dosimetry techniques. Tests were performed irradiating detectors both free-in-air and on-phantom during controlled critcality excursions at the SILENE reactor in Valduc, France. Several grays of absorbed dose were imparted in neutron gamma-ray fields of various relative intensities and spectral distributions. Analysed results confirmed the potential of these systems which can immediately provide an acute dose assessment with an average underestimate of 30%in the various fields. This performance allows for the screening of severely exposed individuals and meets the IAEA recommendations on the early estimate of accident absorbed doses.

Report test scores assessment of the functioning of dosimetry service staff of the CNLV

International Nuclear Information System (INIS)

Alvarez R, J.T.; Tovar M, V.M.

2002-12-01

The ININ realized the evaluation of the service of personal dosimetry in the CNLV, in the categories: IV. (Photons of high energy of 137 CS) and the VA. (Particles beta of 90 Sr/ 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)

Fundamentals of x-ray dosimetry

International Nuclear Information System (INIS)

Roesch, W.C.

1976-01-01

Fundamental information about x-ray dosimetry is presented. Definitions are given and expanded on for dose, absorbed dose including microdosimetry, radiation physics (properties of the radiation that are important to dosimetry), and dosimetry (how the properties are dealt with in determining dose). 5 figs, 12 refs

Some questions of optimization in the personnel dosimetry at NPP

International Nuclear Information System (INIS)

Liberman, A.N.; Petrov, V.I.; Bronshtejn, I.Eh.

1978-01-01

Some possible ways of optimizing the radiation monitoring of personnel of nuclear power plants (NPP) are considered. For premises within the zone of a strict operating regime, it is proposed that the intervals between periods of monitoring be shortened if the operating conditions are normal. To improve the monitoring of activity of water in the primary circuit, it is considered desirable to provide all NPP with a system of automatic radiation monitoring having input to the control panel. Where the work involves opening of primary circuit communications or deactivation of equipment and also in cases of emergency, it is proposed that, in addition to routine monitoring, gamma-spectrometric or radiochemical analysis of the isototip composition of contaminants be carried out. Because of the absence of measurable quantities of incorporated radionuclides in the vast majority of those working in the strict regime zone, it is suggested that the number of persons subject to systematic individual monitoring of internal radiation be limited

Fiber-coupled Al_2O_3:C radioluminescence dosimetry for total body irradiations

International Nuclear Information System (INIS)

Buranurak, S.; Andersen, C.E.

2016-01-01

In vivo dosimetry can be important and relevant in radiotherapy, especially when commissioning new treatment techniques at hospitals. This study investigates the potential use of fiber-coupled radioluminescence (RL) dosimetry based on Al_2O_3:C or organic plastic scintillators for this purpose in the context of Total Body Irradiations (TBIs) where patients are treated with large fields of 6 or 18 MV photons at an extended source-to-surface distance (SSD). The study shows that Al_2O_3:C dosimetry using the saturated-RL protocol may be suitable for real-time in vivo dosimetry during TBI treatments from the perspective of the good agreement with alanine dosimetry and other critical phantom tests, including the ability to cope with the large stem signal experienced during TBI treatments at extended SSD. In contrast, the chromatic stem removal technique often used for organic plastic scintillators did not work well in large fields with the tested calibration procedure and instrumentation. An apparent dose-rate effect discussed in a previous study of the RL properties of Al_2O_3:C (Andersen et al., 2011) was found to have resulted from an overlooked dead time problem in the counting system, and this potential caveat can therefore be removed from the list of potential problems associated with fiber-coupled Al_2O_3:C dosimetry using the saturated-RL protocol. This further has implications for TBI dosimetry using the RL Al_2O_3:C system due to large dose-rate differences between calibrations at the iso-center and in vivo measurements at extended source-to-surface distances. - Highlights: • Fiber-coupled dosimetry can be used for measurements during total body irradiations. • An apparent dose-effect associated with radioluminescence from Al2O3:C was resolved. • The gated-counting stem removal procedure worked well for Al2O3:C in pulsed accelerator beams. • The chromatic stem removal procedure did not work well with the tested instrumentation and organic plastic

Environmental dosimetry

International Nuclear Information System (INIS)

Gold, R.

1977-01-01

For more than 60 years, natural radiation has offered broad opportunities for basic research as evidenced by many fundamental discoveries. Within the last decade, however, dramatic changes have occurred in the motivation and direction of this research. The urgent need for economical energy sources entailing acceptably low levels of environmental impact has compelled the applied aspects of our radiation environment to become overriding considerations. It is within this general framework that state-of-the-art environmental dosimetry techniques are reviewed. Although applied motivation and relevance underscores the current milieu for both reactor and environmental dosimetry, a perhaps even more unifying force is the broad similarity of reactor and environmental radiation fields. In this review, a comparison of these two mixed radiation fields is presented stressing the underlying similarities that exist. On this basis, the evolution of a strong inner bond between dosimetry methods for both reactor and environmental radiation fields is described. The existence of this bond will be illustrated using representative examples of observed spectra. Dosimetry methods of particularly high applicability for both of these fields are described. Special emphasis is placed on techniques of high sensitivity and absolute accuracy which are capable of resolving the components of these mixed radiation fields

Fast neutron dosimetry: Progress summary

International Nuclear Information System (INIS)

DeLuca, P.M. Jr.

1988-01-01

The purpose was to investigate the radiological physics and biology of very low energy photons derived from a 1-GeV electron synchrotron storage ring. An extensive beam line and irradiation apparatus was designed, developed, and constructed. Dosimetry measurements required invention and testing of a miniature absolute calorimeter and a cell irradiation fixture suitable for scanning exposures under computer control. Measurements of the kerma factors of oxygen, aluminum and silicon for 14-20 MeV neutrons. Custom designed miniature proportional counters of cylindrical symmetry were employed in these determinations. The oxygen kerma factor was found significantly lower than values calculated from microscopic cross sections. We also tested Mg and Fe walled conventional spherical counters. The direct neutron-counting gas interaction is significant enough for these counters that a correction is needed. We also investigated the application of Nuclear Magnetic Resonance spectroscopy to radiation dosimetry. Our purpose was to take advantage of recent development of very high-field magnets, complex RF-pulse techniques for solvent suppression, and improved spectral analysis techniques

Nuclear accident dosimetry

International Nuclear Information System (INIS)

1982-01-01

The film presents statistical data on criticality accidents. It outlines past IAEA activities on criticality accident dosimetry and the technical documents that resulted from this work. The film furthermore illustrates an international comparison study on nuclear accident dosimetry conducted at the Atomic Energy Research Establishment, Harwell, United Kingdom

Nuclear accident dosimetry

Energy Technology Data Exchange (ETDEWEB)

NONE

1983-12-31

The film presents statistical data on criticality accidents. It outlines past IAEA activities on criticality accident dosimetry and the technical documents that resulted from this work. The film furthermore illustrates an international comparison study on nuclear accident dosimetry conducted at the Atomic Energy Research Establishment, Harwell, United Kingdom

Quantitative relations between beta-gamma mixed-field dosimeter responses and dose-equivalent conversion factors according to the testing standard

International Nuclear Information System (INIS)

Gupta, V.P.

1982-08-01

The conventional two-element personnel dosimeters, usually having two thick TLD (thermoluminescent dosimetry) ribbons, are used extensively for radiation protection dosimetry. Many of these dosimeters are used for the measurement of beta and gamma radiation doses received in mixed beta-gamma fields. Severe limitations exist, however, on the relative magnitudes and energies of these fields that may be measured simultaneously. Moreover, due to a well-known energy dependence of these dosimeters, particularly for the beta-radiations, systematic errors will occur whenever the differences in workplaces and calibration radiation energies exist. A simple mathematical approach is presented to estimate the deep and shallow dose equivalent values at different energies for such dosimeters. The formulae correlate the dosimeter responses and dose equivalent conversion factors at different energies by taking into account the guidelines of the adopted ANSI Standard N13.11 and the dosimetry practices followed by most dosimeter processors. This standard is to be used in a mandatory testing program in the United States

Quantitative imaging for clinical dosimetry

Energy Technology Data Exchange (ETDEWEB)

Bardies, Manuel [INSERM U601, 9 Quai Moncousu, 44093 Nantes (France)]. E-mail: manu@nantes.inserm.fr; Flux, Glenn [Department of Physics, Royal Marsden NHS Trust, Sutton (United Kingdom); Lassmann, Michael [Department of Nuclear Medicine, Julis-Maximilians University, Wuerzburg (Germany); Monsieurs, Myriam [Department of Health Physics, University of Ghent, 9000 Ghent (Belgium); Savolainen, Sauli [Department of Physical Sciences, University of Helsinki and HUS, Helsinki Medical Imaging Center, Helsinki University Central Hospital (Finland); Strand, Sven-Erik [Medical Radiation Physics, Department of Clinical Sciences Lund, Lund University (Sweden)

2006-12-20

Patient-specific dosimetry in nuclear medicine is now a legal requirement in many countries throughout the EU for targeted radionuclide therapy (TRT) applications. In order to achieve that goal, an increased level of accuracy in dosimetry procedures is needed. Current research in nuclear medicine dosimetry should not only aim at developing new methods to assess the delivered radiation absorbed dose at the patient level, but also to ensure that the proposed methods can be put into practice in a sufficient number of institutions. A unified dosimetry methodology is required for making clinical outcome comparisons possible.

Summary remarks and recommended reactions for an international data file for dosimetry applications for LWR, FBR, and MFR reactor research, development and testing programs

International Nuclear Information System (INIS)

McElroy, W.N.; Lippincott, E.P.; Grundl, J.A.; Fabry, A.; Dierckx, R.; Farinelli, U.

1979-01-01

The need for the use of an internationally accepted data file for dosimetry applications for light water reactor (LWR), fast breeder reactor (FBR), and magnetic fusion reactor (MFR) research, development, and testing programs continues to exist for the Nuclear Industry. The work of this IAEA meeting, therefore, will be another important step in achieving consensus agreement on an internationally recommended file and its purpose, content, structure, selected reactions, and associated uncertainy files. Summary remarks and a listing of recommended reactions for consideration in the formulation of an ''International Data File for Dosimetry Applications'' are presented in subsequent sections of this report

Competency assessments for nuclear industry personnel

International Nuclear Information System (INIS)

2004-04-01

In 1996, the IAEA published Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation: A Guidebook. This publication provides guidance for the development, implementation and evaluation of training programmes for all nuclear power plant personnel using the systematic approach to training (SAT) methodology. The SAT methodology has since been adopted and used for the development and implementation of training programmes for all types of nuclear facility and activities in the nuclear industry. The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared to provide further guidance concerning competency assessments used for measuring the knowledge, skills and attitudes of personnel as the result of training. This publication has been prepared in response to that recommendation. A critical component of SAT (as part of the implementation phase) is the assessment of whether personnel have achieved the standards identified in the training objectives. The nuclear industry spends a significant amount of resources conducting competency assessments. Competency assessments are used for employee selection, trainee assessment, qualification, requalification and authorization (in some Member States the terminology may be 'certification' or 'licensing'), and job advancement and promotion. Ineffective testing methods and procedures, or inappropriate interpretation of test results, can have significant effects on both human performance and nuclear safety. Test development requires unique skills and, as with any skill, training and experience are needed to develop and improve them. Test item and examination development, use, interpretation of results and examination refinement, like all other aspects of SAT, should be part of an ongoing, systematic process. This publication is primarily intended for use by personnel responsible for developing and administering

Electrochemical etching amplification of low-let recoil particle tracks in polymers for fast neutron dosimetry

International Nuclear Information System (INIS)

Sohrabi, M.; Morgan, K.Z.

1975-11-01

An electrochemical etching method for the amplification of fast-neutron-induced recoil particle tracks in polymers was investigated. The technique gave superior results over those obtained by conventional etching methods especially when polycarbonate foils were used for recoil particle track amplification. Electrochemical etching systems capable of multi-foil processing were designed and constructed to demonstrate the feasibility of the techniques for large-scale neutron dosimetry. Electrochemical etching parameters were studied including the nature or type of the polymer foil used, foil thickness and its effect on etching time, the applied voltage and its frequency, the chemical composition, concentration, and temperature of the etchant, distance and angle between the electrodes, and the type of particles such as recoil particles including protons. Recoil particle track density, mean track diameter, and optical density as functions of the mentioned parameters were determined. Each parameter was found to have a distinct effect on the etching results in terms of the measured responses. Several new characteristics of this fast neutron dosimetry method were studied especially for personnel dosimetry using various radiation sources such as nuclear reactors, medical cyclotrons, and isotopic neutron sources. The dose range, neutron energy dependence, directional response, fading characteristics, neutron threshold energy, etc. were investigated

Establishing working standards of chromosome aberrations analysis for biological dosimetry

International Nuclear Information System (INIS)

Bui Thi Kim Luyen; Tran Que; Pham Ngoc Duy; Nguyen Thi Kim Anh; Ha Thi Ngoc Lien

2015-01-01

Biological dosimetry is an dose assessment method using specify bio markers of radiation. IAEA (International Atomic Energy Agency) and ISO (International Organization for Standardization) defined that dicentric chromosome is specify for radiation, it is a gold standard for biodosimetry. Along with the documents published by IAEA, WHO, ISO and OECD, our results of study on the chromosome aberrations induced by radiation were organized systematically in nine standards that dealing with chromosome aberration test and micronucleus test in human peripheral blood lymphocytes in vitro. This standard addresses: the reference dose-effect for dose estimation, the minimum detection levels, cell culture, slide preparation, scoring procedure for chromosome aberrations use for biodosimetry, the criteria for converting aberration frequency into absorbed dose, reporting of results. Following these standards, the automatic analysis devices were calibrated for improving biological dosimetry method. This standard will be used to acquire and maintain accreditation of the Biological Dosimetry laboratory in Nuclear Research Institute. (author)

Comparative survey of site and personnel monitoring characteristics for operation of various types of diagnostic-X ray equipment

International Nuclear Information System (INIS)

Lyarskij, P.P.; Zol'nikova, N.I.

1977-01-01

Diagnostic X-ray machines in present use at medical facilities differ in design and operating parameters, this diversity producing, in turn, a variety of local radiological situations and levels of personnel exposure. Based on radiological safety characterization of working conditions, the authors present a breakdown of contemporary diagnostic X-ray equipment types, based on detailed examination of each group in terms of their associated site monitoring and dosimetry patterns. The paper reports data on personnel exposure levels not only as a function of equipment design and operating characteristics but also according to types of occupational activities for particular medical personnel groups (radiologists, surgeons, anesthesiologists, etc.). Included are health physics data for domestic and foreign X-ray equipment, levels of local and absorbed doses for radiologists, cardiovascular surgeons, neurosurgeons, urologists, traumatologists, anesthesiologists, etc. Measures are recommended for optimizing their activities from the standpoint of radiation safety. (author)

Summary Report of the 1. Research Coordination Meeting on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF)

International Nuclear Information System (INIS)

Trkov, A.; Greenwood, L.R.; Simakov, S.P.

2013-09-01

In accordance with the recommendations of the International Nuclear Data Committee in May 2012, the Nuclear Data Section of IAEA has initiated a new Coordinated Research Project (CRP number F41031) with the main goal to test, validate and improve the international dosimetry library for fission and fusion (IRDFF). The output of this CRP will be a reference dosimetry database of cross sections and decay data with corresponding documentation. It will serve to the needs of fission, fusion and accelerator applications. The first Research Coordination Meeting (RCM) was held 1 to 5 July 2013 in IAEA. At this meeting, the attendees discussed the objectives of the whole CRP, presented their contributions and elaborated on consolidated recommendations and actions for implementation over the next 1.5 year period. This Summary Report documents the individual contributions and joint decisions made during this meeting. (author)

Alanine EPR dosimetry of therapeutic irradiators

International Nuclear Information System (INIS)

Bugay, O.; Bartchuk, V.; Kolesnik, S.; Mazin, M.; Gaponenko, H.

1999-01-01

The high-dose alanine EPR dosimetry is a very precise method in the dose range 1-100 kGy. The system is used generally as the standard high-dose transfer dosimetry in many laboratories. This is comparatively expensive technique so it is important to use it as a more universal dosimetry system also in the middle and low dose ranges. The problems of the middle-dose alanine dosimetry are discussed and the solution of several problems is proposed. The alanine EPR dosimetry has been applied to the dose measurements of medical irradiators in the Kiev City Oncology Center. (author)

Comparison of Real-Time Intraoperative Ultrasound-Based Dosimetry With Postoperative Computed Tomography-Based Dosimetry for Prostate Brachytherapy

International Nuclear Information System (INIS)

Nag, Subir; Shi Peipei; Liu Bingren; Gupta, Nilendu; Bahnson, Robert R.; Wang, Jian Z.

2008-01-01

Purpose: To evaluate whether real-time intraoperative ultrasound (US)-based dosimetry can replace conventional postoperative computed tomography (CT)-based dosimetry in prostate brachytherapy. Methods and Materials: Between December 2001 and November 2002, 82 patients underwent 103 Pd prostate brachytherapy. An interplant treatment planning system was used for real-time intraoperative transrectal US-guided treatment planning. The dose distribution was updated according to the estimated seed position to obtain the dose-volume histograms. Postoperative CT-based dosimetry was performed a few hours later using the Theraplan-Plus treatment planning system. The dosimetric parameters obtained from the two imaging modalities were compared. Results: The results of this study revealed correlations between the US- and CT-based dosimetry. However, large variations were found in the implant-quality parameters of the two modalities, including the doses covering 100%, 90%, and 80% of the prostate volume and prostate volumes covered by 100%, 150%, and 200% of the prescription dose. The mean relative difference was 38% and 16% for doses covering 100% and 90% of the prostate volume and 10% and 21% for prostate volumes covered by 100% and 150% of the prescription dose, respectively. The CT-based volume covered by 200% of the prescription dose was about 30% greater than the US-based one. Compared with CT-based dosimetry, US-based dosimetry significantly underestimated the dose to normal organs, especially for the rectum. The average US-based maximal dose and volume covered by 100% of the prescription dose for the rectum was 72 Gy and 0.01 cm 3 , respectively, much lower than the 159 Gy and 0.65 cm 3 obtained using CT-based dosimetry. Conclusion: Although dosimetry using intraoperative US-based planning provides preliminary real-time information, it does not accurately reflect the postoperative CT-based dosimetry. Until studies have determined whether US-based dosimetry or

Around Semipalatinsk nuclear test site: progress of dose estimations relevant to the consequences of nuclear tests (a summary of 3rd Dosimetry Workshop on the Semipalatinsk nuclear test site area, RIRBM, Hiroshima University, Hiroshima, 9-11 of March, 2005).

Science.gov (United States)

Stepanenko, Valeriy F; Hoshi, Masaharu; Bailiff, Ian K; Ivannikov, Alexander I; Toyoda, Shin; Yamamoto, Masayoshi; Simon, Steven L; Matsuo, Masatsugu; Kawano, Noriyuki; Zhumadilov, Zhaxybay; Sasaki, Masao S; Rosenson, Rafail I; Apsalikov, Kazbek N

2006-02-01

The paper is an analytical overview of the main results presented at the 3rd Dosimetry Workshop in Hiroshima(9-11 of March 2005), where different aspects of the dose reconstruction around the Semipalatinsk nuclear test site(SNTS) were discussed and summarized. The results of the international intercomparison of the retrospective luminescence dosimetry(RLD) method for Dolon' village(Kazakhstan) were presented at the Workshop and good concurrence between dose estimations by different laboratories from 6 countries (Japan, Russia, USA, Germany, Finland and UK) was pointed out. The accumulated dose values in brick for a common depth of 10mm depth obtained independently by all participating laboratories were in good agreement for all four brick samples from Dolon' village, Kazakhstan, with the average value of the local gamma dose due to fallout (near the sampling locations) being about 220 mGy(background dose has been subtracted).Furthermore, using a conversion factor of about 2 to obtain the free-in-air dose, a value of local dose approximately 440 mGy is obtained, which supports the results of external dose calculations for Dolon': recently published soil contamination data, archive information and new models were used for refining dose calculations and the external dose in air for Dolon village was estimated to be about 500 mGy. The results of electron spin resonance(ESR) dosimetry with tooth enamel have demonstrated the notable progress in application of ESR dosimetry to the problems of dose reconstruction around the Semipalatinsk nuclear test site. At the present moment, dose estimates by the ESR method have become more consistent with calculated values and with retrospective luminescence dosimetry data, but differences between ESR dose estimates and RLD/calculation data were noted. For example mean ESR dose for eligible tooth samples from Dolon' village was estimated to be about 140 mGy(above background dose), which is less than dose values obtained by RLD and

Dosimetry for radiation processing

International Nuclear Information System (INIS)

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 international organizations (IAEA) and national laboratories have helped to improve the reliability of dose measurements. In this paper the special features of radiation processing dosimetry are discussed, several commonly used dosimeters are reviewed, and factors leading to traceable and reliable dosimetry are discussed. (author)

Radiochromic film dosimetry

International Nuclear Information System (INIS)

Xu Zhiyong

2002-01-01

Radiochromic film dosimetry was developed to measure ionization irradiation dose for industry and medicine. At this time, there are no comprehensive guideline on the medical application, calibration method and densitometer system for medicine. The review gives update on Radiochromic film dosimetry used for medicine, including principles, film model and material, characteristics, calibration method, scanning densitometer system and medical application

In vivo dosimetry with silicon diodes in total body irradiation

International Nuclear Information System (INIS)

Oliveira, F.F.; Amaral, L.L.; Costa, A.M.; Netto, T.G.

2014-01-01

The aim of this work is the characterization and application of silicon diode detectors for in vivo dosimetry in total body irradiation (TBI) treatments. It was evaluated the diode response with temperature, dose rate, gantry angulations and field size. A maximum response variation of 2.2% was obtained for temperature dependence. The response variation for dose rate and angular was within 1.2%. For field size dependence, the detector response increased with field until reach a saturation region, where no more primary radiation beam contributes for dose. The calibration was performed in a TBI setup. Different lateral thicknesses from one patient were simulated and then the calibration factors were determined by means of maximum depth dose readings. Subsequent to calibration, in vivo dosimetry measurements were performed. The response difference between diode readings and the prescribed dose for all treatments was below 4%. This difference is in agreement as recommended by the International Commission on Radiation Units and Measurements (ICRU), which is ±5%. The present work to test the applicability of a silicon diode dosimetry system for performing in vivo dose measurements in TBI techniques presented good results. These measurements demonstrated the value of diode dosimetry as a treatment verification method and its applicability as a part of a quality assurance program in TBI treatments. - Highlights: ► Characterization of a silicon diode dosimetry system. ► Application of the diodes for in vivo dosimetry in total body irradiation treatments. ► Implementation of in vivo dosimetry as a part of a quality assurance program in radiotherapy

Computational methods in several fields of radiation dosimetry

International Nuclear Information System (INIS)

Paretzke, Herwig G.

2010-01-01

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

Gamma response characterizations of optically stimulated luminescence (OSL) affects personal dosimetry

Science.gov (United States)

Monthonwattana, S.; Esor, J.; Rungseesumran, T.; Intang, A.

2017-06-01

Optically Stimulated Luminescence (OSL) is the current technique of personal dosimetry changed by Nuclear Technology Service Center instead of Thermoluminescence dosimetry (TLD) because OSL has more advantages, such as repeat reading and elimination of heating process. In this study, OSL was used to test the gamma response characterizations. Detailed OSL investigation on personal dosimetry was carried out in the dose range of 0.2 - 3.0 mSv. The batch homogeneity was 7.66%. R2 value of the linear regression was 0.9997. The difference ratio of angular dependence at ± 60° was 8.7%. Fading of the reading was about 3%.

Personnel neutron dosimetry applications of track-size distributions on electrochemically etched CR-39 foils

International Nuclear Information System (INIS)

Hankins, D.E.; Homann, S.G.; Westermark, J.

1988-01-01

The track-size distribution on electrochemically etched CR-39 foils can be used to obtain some limited information on the incident neutron spectra. Track-size distributions on CR-39 foils can also be used to determine if the tracks were caused by neutrons or if they are merely background tracks (which have a significantly different track-size distribution). Identifying and discarding the high-background foils reduces the number of foils that must be etched. This also lowers the detection limit of the dosimetry system. We have developed an image analyzer program that can more efficiently determine the track density and track-size distribution, as well as read the laser-cut identification numbers on each foil. This new image analyzer makes the routine application of track-size distributions on CR-39 foils feasible. 2 refs., 3 figs

A microcomputer controlled thermoluminescence dosimetry system

International Nuclear Information System (INIS)

Huyskens, C.J.; Kicken, P.J.H.

1980-01-01

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)

Characterising an aluminium oxide dosimetry system.

Science.gov (United States)

Conheady, Clement F; Gagliardi, Frank M; Ackerly, Trevor

2015-09-01

In vivo dosimetry is recommended as a defence-in-depth strategy in radiotherapy treatments and is currently employed by clinics around the world. The characteristics of a new optically stimulated luminescence dosimetry system were investigated for the purpose of replacing an aging thermoluminescence dosimetry system for in vivo dosimetry. The stability of the system was not sufficient to satisfy commissioning requirements and therefore it has not been released into clinical service at this time.

Double dosimetry procedures for the determination of occupational effective dose in interventional radiology

International Nuclear Information System (INIS)

Jaervinen, H.; Buls, N.; Clerinx, P.; Miljanic, S.; Ranogajec-Komor, M.; Nikodemova, D.; D'Errico, F.

2008-01-01

Full text: In interventional radiology, for an accurate determination of occupational effective dose, measurements with two dosemeters ('double dosimetry', DD) have been recommended, one dosemeter located above and one under the protective apron. In this paper, based on an extensive literature search, the most recent algorithms developed for the determination of effective dose from the dosimeter readings have been compared for a few practical interventional procedures. Recommendations on the practices and algorithms are given on the basis of the results. For the comparison of algorithms, dosemeter readings and the effective dose were obtained both experimentally and by calculation. Further, data from published Monte Carlo calculations have been applied. The literature review has indicated that very few regulations for DD exist and the DD practices have not been harmonized. There is no firm consensus on the most suitable calculation algorithms. Single dosemeter (SD) measurements are still mostly used for the calculation of effective dose. Most DD and SD algorithms overestimate effective dose significantly, sometimes by over ten times. However, SD algorithms can significantly underestimate effective dose in certain interventional radiology conditions. Due to the possibility of underestimating effective dose, DD is generally recommended. The results suggest that there might not be a single DD algorithm which would be optimum for all interventional radiology procedures. However, the selection of a precise DD algorithm for each individual condition is not practical and compromises must be made. For accurate personnel dosimetry, the accuracy of the algorithm selected should be tested for typical local interventional radiology condition. Personnel dosemeters should be used in the recommended positions. The dosemeter above the apron should be on a collar and its reading also used to assess the risk of lens injuries. The dosemeter under the apron can be on the chest or

Dosimetry optimization at COGEMA-La Hague

International Nuclear Information System (INIS)

Kalimbadjian, J.

2000-01-01

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

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.

Secondary standard dosimetry laboratory (SSDL)

International Nuclear Information System (INIS)

Md Saion bin Salikin.

1983-01-01

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)

Worldwide QA networks for radiotherapy dosimetry

International Nuclear Information System (INIS)

Izewska, J.; Svensson, H.; Ibbott, G.

2002-01-01

A number of national or international organizations have developed various types and levels of external audits for radiotherapy dosimetry. There are three major programmes who make available external audits, based on mailed TLD (thermoluminescent dosimetry), to local radiotherapy centres on a regular basis. These are the IAEA/WHO TLD postal dose audit service operating worldwide, the European Society for Therapeutic Radiology and Oncology (ESTRO) system, EQUAL, in European Union (EU) and the Radiological Physics Center (RPC) in North America. The IAEA, in collaboration with WHO, was the first organization to initiate TLD audits on an international scale in 1969, using mailed system, and has a well-established programme for providing dose verification in reference conditions. Over 32 years, the IAEA/WHO TLD audit service has checked the calibration of more than 4300 radiotherapy beams in about 1200 hospitals world-wide. Only 74% of those hospitals who receive TLDs for the first time have results with deviation between measured and stated dose within acceptance limits of ±5%, while approximately 88% of the users that have benefited from a previous TLD audit are successful. EQUAL, an audit programme set up in 1998 by ESTRO, involves the verification of output for high energy photon and electron beams, and the audit of beam parameters in non-reference conditions. More than 300 beams are checked each year, mainly in the countries of EU, covering approximately 500 hospitals. The results show that although 98% of the beam calibrations are within the tolerance level of ±5%, a second check was required in 10% of the participating centres, because a deviation larger than ±5% was observed in at least one of the beam parameters in non-reference conditions. EQUAL has been linked to another European network (EC network) which tested the audit methodology prior to its application. The RPC has been funded continuously since 1968 to monitor radiation therapy dose delivery at

Electron paramagnetic resonance dosimetry using synthetic hydroxyapatite

Energy Technology Data Exchange (ETDEWEB)

Choi, Kwon; Kim, Hwi Young; Ye, Sung Joon [Seoul National University, Seoul (Korea, Republic of); Hirata, Hiroshi [Hokkaido University, Sapporo (Japan); Park, Jong Min [Seoul National University Hospital, Seoul (Korea, Republic of)

2014-11-15

The victims exposed doses under 3.5-4.0 Gy have chance to survive if treated urgently. To determine the priority of treatment among a large number of victims, the triage – distinguishing patients who need an urgent treatment from who may not be urgent – is necessary based on radiation biodosimetry. A current gold standard for radiation biodosimetry is the chromosomal assay using human lymphocytes. But this method requires too much time and skilled labors to cover the mass victims in radiation emergencies. Electron paramagnetic resonance (EPR) has been known for its capability of quantifying radicals in matters. EPR dosimetry is based on the measurement of stable radiation-induced radicals in tooth enamel. Hydroxyapatite (HAP) (Ca10(PO4)6(OH)2) contained in tooth enamel is a major probe for radiation dose reconstruction. This HAP dosimetry study was performed using a novel EPR spectrometer in Hokkaido University, Japan. The EPR dose-response curve was made using HAP samples. The blind test using 250 cGy samples showed the feasibility of EPR dosimetry for the triage purpose.

ASTM Standards for Reactor Dosimetry and Pressure Vessel Surveillance

International Nuclear Information System (INIS)

GRIFFIN, PATRICK J.

1999-01-01

The ASTM standards provide guidance and instruction on how to field and interpret reactor dosimetry. They provide a roadmap towards understanding the current ''state-of-the-art'' in reactor dosimetry, as reflected by the technical community. The consensus basis to the ASTM standards assures the user of an unbiased presentation of technical procedures and interpretations of the measurements. Some insight into the types of standards and the way in which they are organized can assist one in using them in an expeditious manner. Two example are presented to help orient new users to the breadth and interrelationship between the ASTM nuclear metrology standards. One example involves the testing of a new ''widget'' to verify the radiation hardness. The second example involves quantifying the radiation damage at a pressure vessel critical weld location through surveillance dosimetry and calculation

Performance of a parallel plate ionization chamber in beta radiation dosimetry

International Nuclear Information System (INIS)

Antonio, Patricia L.; Caldas, Linda V.E.

2011-01-01

A homemade parallel plate ionization chamber with graphite collecting electrode, and developed for use in mammography beams, was tested in relation to its usefulness in beta radiation dosimetry at the Calibration Laboratory of IPEN. Characterization tests of this ionization chamber were performed, using the Sr-90 + Y-90, Kr-85 and Pm-147 sources of a beta secondary standard system. The results of saturation, leakage current, stabilization time, response stability, linearity, angular dependence, and calibration coefficients are within the recommended limits of international recommendations that indicate that this chamber may be used for beta radiation dosimetry. (author)

Performance of a parallel plate ionization chamber in beta radiation dosimetry

Energy Technology Data Exchange (ETDEWEB)

Antonio, Patricia L.; Caldas, Linda V.E., E-mail: patrilan@ipen.b, E-mail: lcaldas@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

A homemade parallel plate ionization chamber with graphite collecting electrode, and developed for use in mammography beams, was tested in relation to its usefulness in beta radiation dosimetry at the Calibration Laboratory of IPEN. Characterization tests of this ionization chamber were performed, using the Sr-90 + Y-90, Kr-85 and Pm-147 sources of a beta secondary standard system. The results of saturation, leakage current, stabilization time, response stability, linearity, angular dependence, and calibration coefficients are within the recommended limits of international recommendations that indicate that this chamber may be used for beta radiation dosimetry. (author)

Basic requirements for personnel monitoring. 1980 ed

International Nuclear Information System (INIS)

1980-01-01

This Code of Practice sets forth the objectives of an adequate system of personnel monitoring for radiation workers. It covers individual dosimetry, including internal radiation monitoring, and area monitoring to the extent required for the assessment of individual radiation doses. The responsibilities of authorities for organizing monitoring of radiation workers are discussed, together with brief descriptions of monitoring methods and the rules governing their application. The general principles to be considered in selecting instrumentation and the appropriate monitoring techniques are described, as well as calibration techniques, methods of data handling and record keeping. Current concepts and recommendations of the International Commission on Radiological Protection, as presented in ICRP Publication No.26, have been incorporated. New developments in techniques and instruments have been reflected, and several sections such as calibration and record keeping have been elaborated. The bibliography has been updated and new annexes added.

The neutron and low-energy gamma operational dosimetry in Melox plant

International Nuclear Information System (INIS)

Devita, A.D.

2006-01-01

M.E.L.O.X., subsidiary of A.R.E.V.A., produce M.O.X. fuels, a mixture of uranium and plutonium oxides. With the use in the process of plutonium oxide, there is a risk of external exposure to neutrons and low -energy gamma rays. By their characteristics, both these types of radiation are difficult to measure. The difficulty in measuring neutron doses lies in the fact that the fluence -to-dose equivalent conversion factor varies with the neutron energy level. In low -energy gamma (between 20 and 60 keV) dose measurement, the problem is detection using an electronic system. Just some years ago, very few industrial players were tempted to develop dosimeters in these areas in view of the poor demand and market prospects. Furthermore, radiation protection specialists needed a highly functional and robust direct reading dosimeters or, in other words, a device that was simple, reliable, inexpensive, small, and quick and easy to use in a wide range of working environments that could vary in terms of both the workstation and external exposure. In addition, at sites such as Melox, where company employees work alongside personnel from outside companies, the same types of dosimeters must be used so that dose -related data can be managed globally in one data base. Two technical solutions are available for neutron operational dosimetry - spectrometer-dosimeters and calibration dosimeters. Melox has opted for the use of calibration dosimeters. The reasons for this choice (technical, financial and organizational criteria) are given in this presentation. Before and during the various campaigns of M.O.X. fuels, the spectral characteristics relating to neutron fluence at different workstations and representative of personnel exposure levels were determined. A reference spectrometer was then used to determine the transfer function between fluence and dose in order to calibrate passive and operational dosimeters appropriately.The methodology to be set up should guarantee good

Theoretical basis for dosimetry

International Nuclear Information System (INIS)

Carlsson, G.A.

1985-01-01

Radiation dosimetry is fundamental to all fields of science dealing with radiation effects and is concerned with problems which are often intricate as hinted above. A firm scientific basis is needed to face increasing demands on accurate dosimetry. This chapter is an attempt to review and to elucidate the elements for such a basis. Quantities suitable for radiation dosimetry have been defined in the unique work to coordinate radiation terminology and usage by the International Commission on Radiation Units and Measurements, ICRU. Basic definitions and terminology used in this chapter conform with the recent ''Radiation Quantities and Units, Report 33'' of the ICRU

Neutron Dosimetry and Irradiation of Solids; Dosimetrie des neutrons et irradiation des solides

Energy Technology Data Exchange (ETDEWEB)

Perriot, G; Schmitt, A P [Commissariat a l' Energie Atomique. Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

1962-07-01

Results of work at C.E.A. from 1958 to 1960 are reviewed. The possibilities offered by classical dosimetry methods are discussed. The tests which led to the utilization, for fast neutron dosimetry, of resistivity variations induced in solid W by such neutrons are described. Experimental W irradiation results led to a definition of neutron efficiency which describes the relations between neutron energy and their effects on materials. Possibilities offered by detectors which make use of radiation damage and are sensitive to neutrons at keV energies were explored. In other work, the principal French reactors were classified according to their ability to produce damage in materials such as W. (authors) [French] Dans ce rapport on a presente les resultats essentiels de travaux qui ont ete effectues de 1958 a 1980 par des chercheurs du CEA issus de differents services. En meme temps qu'une revue des possibilites offertes a l'epoque par les methodes classiques de dosimetrie (utilisation des detecteurs par activation), on a decrit les essais qui devaient permettre d'utiliser, a la dosimetrie les neutrons rapides, les variations de resistivite qu'ils creent dans un corps solide (tungstene). L'irradiation du tungstene a montre l'importance qu'il y avait a definir 'l'efficacite' des neutrons, c'est-a-dire leur aptitude plus ou moins grande, selon leur energie, a creer des defauts dans les materiaux. L'efficacite d'un emplacement d'irradiation se trouvant liee au spectre neutronique, on a vu les difficultes qu'il y avait a utiliser les detecteurs par activation des qu'on n'avait plus affaire a un spectre en 1/E ou de fission et on a pu entrevoir les possibilites offertes par les detecteurs utilisant la creation des defauts qui repondent a tous les neutrons d'energies, superieures a quelques keV. Enfin, on a classe les principaux types de Piles Francaises selon leur aptitude a creer plus ou moins rapidement des dommages dans des materiaux comme le tungstene. (auteur)

How can bio dosimetry measurements be used to improve radiation epidemiologic studies?

International Nuclear Information System (INIS)

Simon, Steven L.; Bouville, Andre; Kleinerman, Ruth

2008-01-01

Full text: Bio dosimetry measurements can be used potentially to improve radiation epidemiologic studies by providing a means to corroborate analytical or model-based dose estimates, to assess bias in models and their dose estimates, and reduce uncertainty in individual or group-average doses. Radiation epidemiologic studies typically rely on accurate estimation of doses to the whole body or to specific organs for numerous individuals in order to derive reliable estimates of risk of cancer or other medical conditions. However, dose estimates whether based on analytical dose reconstruction (i.e., models) or personnel monitoring measurements, e.g., film-badges, are associated with considerable and varying degrees of uncertainty. Uncertainty is a product of many factors; persons were exposed many years or decades earlier and usually only inadequate data or measurements are available. While bio dosimetry has begun to play a more significant role in long-term health risk studies, its use is still limited in that context, primarily due sometimes to inadequate limits of detection, inter-individual variability of the signal measured, and high per-sample cost. Presently, the most suitable bio dosimetry methods for epidemiologic studies are chromosome aberration frequencies from fluorescence in situ hybridization (FISH) of peripheral blood lymphocytes and electron paramagnetic resonance (EPR) measurements made on tooth enamel, with detection limits of approximately 0.3 to 0.5 Gy, and as low as 0.03 Gy for FISH and EPR, respectively. Presently, both methods are invasive and require obtaining either blood or teeth. Though both FISH and EPR have been used in a variety of large long-term health risk studies including those of a-bomb survivors and various occupational and environmental exposures, only recently has considerable thought been given to how these data can be used in epidemiologic studies in any but rudimentary ways. Key issues to consider are the representativeness of

Dosimetry in mixed (n,gamma) fields in relation to personnel monitoring

International Nuclear Information System (INIS)

Nikodemova, D.; Hrabovcova, A.; Kubu, M.

1987-01-01

Neutron spectra were determined using neutron detection with a set of moderating spheres and the SAND computer method. A 6 LiI crystal or a pair of 6 LiF- 7 LiF thermoluminescence detectors was placed in the centre of 7 moderating spheres of 5 to 30 cm in diameter. 252 Cf and 241 Am-Be source were used in the calibration of the multisphere spectrometer. Neutron scattering from the walls, floor and ceiling was taken into consideration. The contribution of scattered neutrons was also determined for the case of measuring the 241 Am-Be spectrum with the source placed behind a water wall 10 cm thick. It is shown how the neutron energy distribution and the values of dose quantities altered as a result of the presence of scattered neutrons. The result of the presence of scattered neutrons. The results are discussed with respect to personnel monitoring. (author)

The Third International Intercomparison on EPR Tooth Dosimetry: Part 2, final analysis

International Nuclear Information System (INIS)

Wieser, A.; Debuyst, R.; Fattibene, P.; Meghzifene, A.; Onori, S.; Bayankin, S. N.; Brik, A.; Bugay, A.; Chumak, V.; Ciesielski, B.; Hoshi, M.; Imata, H.; Ivannikov, A.; Ivanov, D.; Junczewska, M.; Miyazawa, C.; Penkowski, M.; Pivovarov, S.; Romanyukha, A.; Romanyukha, L.; Schauer, D.; Scherbina, O.; Schultka, K.; Sholom, S.; Skvortsov, V.; Stepanenko, V.; Thomas, J. A.; Tielewuhan, E.; Toyoda, S.; Trompier, F.

2006-01-01

The objective of the Third International Intercomparison on EPR Tooth Dosimetry was to evaluate laboratories performing tooth enamel dosimetry <300 mGy. Final analysis of results included a correlation analysis between features of laboratory dose reconstruction protocols and dosimetry performance. Applicability of electron paramagnetic resonance (EPR) tooth dosimetry at low dose was shown at two applied dose levels of 79 and 176 mGy. Most (9 of 12) laboratories reported the dose to be within 50 mGy of the delivered dose of 79 mGy, and 10 of 12 laboratories reported the dose to be within 100 mGy of the delivered dose of 176 mGy. At the high-dose tested (704 mGy) agreement within 25% of the delivered dose was found in 10 laboratories. Features of EPR dose reconstruction protocols that affect dosimetry performance were found to be magnetic field modulation amplitude in EPR spectrum recording, EPR signal model in spectrum deconvolution and duration of latency period for tooth enamel samples after preparation. (authors)

Dosimetry tools and techniques for IMRT

International Nuclear Information System (INIS)

Low, Daniel A.; Moran, Jean M.; Dempsey, James F.; Dong Lei; Oldham, Mark

2011-01-01

Intensity modulated radiation therapy (IMRT) poses a number of challenges for properly measuring commissioning data and quality assurance (QA) radiation dose distributions. This report provides a comprehensive overview of how dosimeters, phantoms, and dose distribution analysis techniques should be used to support the commissioning and quality assurance requirements of an IMRT program. The proper applications of each dosimeter are described along with the limitations of each system. Point detectors, arrays, film, and electronic portal imagers are discussed with respect to their proper use, along with potential applications of 3D dosimetry. Regardless of the IMRT technique utilized, some situations require the use of multiple detectors for the acquisition of accurate commissioning data. The overall goal of this task group report is to provide a document that aids the physicist in the proper selection and use of the dosimetry tools available for IMRT QA and to provide a resource for physicists that describes dosimetry measurement techniques for purposes of IMRT commissioning and measurement-based characterization or verification of IMRT treatment plans. This report is not intended to provide a comprehensive review of commissioning and QA procedures for IMRT. Instead, this report focuses on the aspects of metrology, particularly the practical aspects of measurements that are unique to IMRT. The metrology of IMRT concerns the application of measurement instruments and their suitability, calibration, and quality control of measurements. Each of the dosimetry measurement tools has limitations that need to be considered when incorporating them into a commissioning process or a comprehensive QA program. For example, routine quality assurance procedures require the use of robust field dosimetry systems. These often exhibit limitations with respect to spatial resolution or energy response and need to themselves be commissioned against more established dosimeters. A chain of

Radiation processing dosimetry - past, present and future

International Nuclear Information System (INIS)

McLaughlin, W.L.

1999-01-01

Since the two United Nations Conferences were held in Geneva in 1955 and 1958 on the Peaceful Uses of Atomic Energy and the concurrent foundation of the International Atomic Energy Agency in 1957, the IAEA has fostered high-dose dosimetry and its applications. This field is represented in industrial radiation processing, agricultural programmes, and therapeutic and preventative medicine. Such dosimetry is needed specifically for pest and quarantine control and in the processing of medical products, pharmaceuticals, blood products, foodstuffs, solid, liquid and gaseous wastes, and a variety of useful commodities, e.g. polymers, composites, natural rubber and elastomers, packaging, electronic, and automotive components, as well as in radiotherapy. Improvements and innovations of dosimetry materials and analytical systems and software continue to be important goals for these applications. Some of the recent advances in high-dose dosimetry include tetrazolium salts and substituted polydiacetylene as radiochromic media, on-line real-time as well as integrating semiconductor and diamond-detector monitors, quantitative label dosimeters, photofluorescent sensors for broad dose range applications, and improved and simplified parametric and computational codes for imaging and simulating 3D radiation dose distributions in model products. The use of certain solid-state devices, e.g. optical quality LiF, at low (down to 4K) and high (up to 500 K) temperatures, is of interest for materials testing. There have also been notable developments in experimental dose mapping procedures, e.g. 2D and 3D dose distribution analyses by flat-bed optical scanners and software applied to radiochromic and photofluorescent images. In addition, less expensive EPR spectrometers and new EPR dosimetry materials and high-resolution semiconductor diode arrays, charge injection devices, and photostimulated storage phosphors have been introduced. (author)

42 CFR 493.1423 - Standard; Testing personnel qualifications.

Science.gov (United States)

2010-10-01

..., or bachelor's degree in a chemical, physical, biological or clinical laboratory science, or medical... stability and storage; (F) The skills required to implement the quality control policies and procedures of... HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Personnel for Nonwaived...

Preliminry results of the 1975 international personnel monitoring survey

International Nuclear Information System (INIS)

Becker, K.

1975-11-01

About 70 detailed questions have been answered in mid-1975 by 83 personnel monitoring services in 33 countries, representing almost half a million, or approximately 28 percent, of the world's total radiation workers, as well as by 11 customers of U. S. commercial services. Extensive data are given on many questions regarding the current system in use, future plans, and experiences, for example on the type(s) of TLD, film and readout instrumentation; monitoring period; applications for extremity and environmental monitoring; advantages and disadvantages of various systems; R and D projects; experience with beta and neutron dosimetry; intentional fake exposures; lower and upper dose limits; recordkeeping; and reporting of the results. The larger services in the advanced countries lead in the transition from film to TLD. More than half of the radiation workers already wear TLDs, or will do so within about two years. Important unsolved problems are fast neutron monitoring and the low information content and high initial cost of TLD. The trend is towards large, centralized, automatic services and recordkeeping, with extensive computer use for evaluation and data handling. There is a need for better performance standards and testing, and more information exchange and cooperation between services. (auth)

Personal dosimetry in Kazakhstan

International Nuclear Information System (INIS)

Khvoshnyanskaya, I.R.; Vdovichenko, V.G.; Lozbin, A.Yu.

2003-01-01

KATEP-AE Radiation Laboratory is the first organization in Kazakhstan officially licensed by the Kazakhstan Atomic Energy Committee to provide individual dosimetry services. The Laboratory was established according to the international standards. Nowadays it is the largest company providing personal dosimetry services in the Republic of Kazakhstan. (author)

Maintenance Personnel Performance Simulation (MAPPS) model: description of model content, structure, and sensitivity testing. Volume 2

International Nuclear Information System (INIS)

Siegel, A.I.; Bartter, W.D.; Wolf, J.J.; Knee, H.E.

1984-12-01

This volume of NUREG/CR-3626 presents details of the content, structure, and sensitivity testing of the Maintenance Personnel Performance Simulation (MAPPS) model that was described in summary in volume one of this report. The MAPPS model is a generalized stochastic computer simulation model developed to simulate the performance of maintenance personnel in nuclear power plants. The MAPPS model considers workplace, maintenance technician, motivation, human factors, and task oriented variables to yield predictive information about the effects of these variables on successful maintenance task performance. All major model variables are discussed in detail and their implementation and interactive effects are outlined. The model was examined for disqualifying defects from a number of viewpoints, including sensitivity testing. This examination led to the identification of some minor recalibration efforts which were carried out. These positive results indicate that MAPPS is ready for initial and controlled applications which are in conformity with its purposes

Establishing personal dosimetry procedure using optically stimulated luminescence dosimeters in photon and mixed photon-neutron radiation fields

International Nuclear Information System (INIS)

Le Ngoc Thiem; Bui Duc Ky; Trinh Van Giap; Nguyen Huu Quyet; Ho Quang Tuan; Vu Manh Khoi; Chu Vu Long

2017-01-01

According to Vietnamese Law on Atomic Energy, personal dosimetry (PD) for radiation workers is required periodically in order to fulfil the national legal requirements on occupational radiation dose management. Since the radiation applications have become popular in Vietnamese society, the thermal luminescence dosimeters (TLDs) have been used as passive dosimeters for occupational monitoring in the nation. Together with the quick increase in radiation applications and the number of personnel working in radiation fields, the Optically Stimulated Luminescence Dosimeters (OSLDs) have been first introduced since 2015. This work presents the establishment of PD measuring procedure using OSLDs which are used for measuring photons and betas known as Inlight model 2 OSL (OSLDs-p,e) and for measuring mixed radiations of neutrons, photons and betas known as Inlight LDR model 2 (OSLDs-n,p,e). Such following features of OSLDs are investigated: detection limit, energy response, linearity, reproducibility, angular dependency and fading with both types of OSLDs-p,e and OSLDs-n,p,e. The result of an intercomparison in PD using OSLDs is also presented in the work. The research work also indicates that OSL dosimetry can be an alternative method applied in PD and possibly become one of the most popular personal dosimetry method in the future. (author)

MO-B-BRB-00: Three Dimensional Dosimetry

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-06-15

Full three-dimensional (3D) dosimetry using volumetric chemical dosimeters probed by 3D imaging systems has long been a promising technique for the radiation therapy clinic, since it provides a unique methodology for dose measurements in the volume irradiated using complex conformal delivery techniques such as IMRT and VMAT. To date true 3D dosimetry is still not widely practiced in the community; it has been confined to centres of specialized expertise especially for quality assurance or commissioning roles where other dosimetry techniques are difficult to implement. The potential for improved clinical applicability has been advanced considerably in the last decade by the development of improved 3D dosimeters (e.g., radiochromic plastics, radiochromic gel dosimeters and normoxic polymer gel systems) and by improved readout protocols using optical computed tomography or magnetic resonance imaging. In this session, established users of some current 3D chemical dosimeters will briefly review the current status of 3D dosimetry, describe several dosimeters and their appropriate imaging for dose readout, present workflow procedures required for good dosimetry, and analyze some limitations for applications in select settings. We will review the application of 3D dosimetry to various clinical situations describing how 3D approaches can complement other dose delivery validation approaches already available in the clinic. The applications presented will be selected to inform attendees of the unique features provided by full 3D techniques. Learning Objectives: L. John Schreiner: Background and Motivation Understand recent developments enabling clinically practical 3D dosimetry, Appreciate 3D dosimetry workflow and dosimetry procedures, and Observe select examples from the clinic. Sofie Ceberg: Application to dynamic radiotherapy Observe full dosimetry under dynamic radiotherapy during respiratory motion, and Understand how the measurement of high resolution dose data in an

Dosimetry and shielding

International Nuclear Information System (INIS)

Farinelli, U.

1977-01-01

Today, reactor dosimetry and shielding have wide areas of overlap as concerns both problems and methods. Increased interchange of results and know-how would benefit both. The areas of common interest include calculational methods, sensitivity studies, theoretical and experimental benchmarks, cross sections and other nuclear data, multigroup libraries and procedures for their adjustment, experimental techniques and damage functions. This paper reviews the state-of-the-art and the latest development in each of these areas as far as shielding is concerned, and suggests a number of interactions that could be profitable for reactor dosimetry. Among them, re-evaluation of the potentialities of calculational methods (in view of the recent developments) in predicting radiation environments of interest; the application of sensitivity analysis to dosimetry problems; a common effort in the field of theoretical benchmarks; the use of the shielding one-material propagation experiments as reference spectra for detector cross sections; common standardization of the detector nuclear data used in both fields; the setting up of a common (or compatible) multigroup structure and library applicable to shielding, dosimetry and core physics; the exchange of information and experience in the fields of cross section errors, correlations and adjustment; and the intercomparison of experimental techniques

The Latin American Biological Dosimetry Network (LBDNet)

International Nuclear Information System (INIS)

Garcia, O.; Lamadrid, A.I.; Gonzalez, J.E.; Romero, I.; Mandina, T.; Di Giorgio, M.; Radl, A.; Taja, M.R.; Sapienza, C.E.; Deminge, M.M.; Fernandez Rearte, J.; Stuck Oliveira, M.; Valdivia, P.; Guerrero-Carbajal, C.; Arceo Maldonado, C.; Cortina Ramirez, G.E.; Espinoza, M.; Martinez-Lopez, W.; Di Tomasso, M.

2016-01-01

Biological Dosimetry is a necessary support for national radiation protection programmes and emergency response schemes. The Latin American Biological Dosimetry Network (LBDNet) was formally founded in 2007 to provide early biological dosimetry assistance in case of radiation emergencies in the Latin American Region. Here are presented the main topics considered in the foundational document of the network, which comprise: mission, partners, concept of operation, including the mechanism to request support for biological dosimetry assistance in the region, and the network capabilities. The process for network activation and the role of the coordinating laboratory during biological dosimetry emergency response is also presented. This information is preceded by historical remarks on biological dosimetry cooperation in Latin America. A summary of the main experimental and practical results already obtained by the LBDNet is also included. (authors)

Integral test of JENDL dosimetry file using fast neutron field in the Experimental Fast Reactor JOYO

International Nuclear Information System (INIS)

Aoyama, Takafumi; Sekine, Takashi

1999-09-01

In order to evaluate the applicability of the JENDL dosimetry file, an integral test using a fast neutron spectrum field in the Experimental Fast Reactor JOYO Mark-II core was performed. The dosimeter set consisting of eight reactions of 46 Ti(n,p) 46 Sc, 54 Fe(n,p) 54 Mn, 58 Fe(n,γ) 59 Fe, 58 Ni(n,p) 58 Co, 59 Co(n,γ) 60 Co, 63 Cu(n,α) 60 Co, 238 U fission and 237 Np fission was irradiated for approximately 30 days near the core center of the JOYO Mk-II. Neutron flux at the dosimeter position was calculated using the two dimensional discrete ordinate transport code 'DORT'. The core configuration was modeled in XY geometry, and the 100 group cross section set of JSD-J2 / JFT-J2, which was processed from JENDL-2, was utilized. The absolute value of neutron flux was normalized so that the 235 U fission rate using the calculated neutron spectrum agreed with the measured reaction rate. The 103 group cross section data were processed by 'NJOY' code for nuclides to be used in the JOYO dosimetry. As the results of integral test for JENDL/D-99 (new file) and JENDL/D-91 (previous file), calculated values by JENDL/D-99 agreed well with the experimental values, and the C/E ratios ranged from 0.95 to 1.22. By comparing the results between JENDL/D-99 and JENDL/D-91, small differences exist, except for 58 Fe(n, γ) 59 Fe reaction, which was improved significantly in JENDL/D-99. (author)

The use of polymer gel dosimetry to measure dose distribution around metallic implants

International Nuclear Information System (INIS)

Nagahata, Tomomasa; Yamaguchi, Hajime; Monzen, Hajime; Nishimura, Yasumasa

2014-01-01

A semi-solid polymer dosimetry system using agar was developed to measure the dose distribution close to metallic implants. Dosimetry of heterogeneous fields where electron density markedly varies is often problematic. This prompted us to develop a polymer gel dosimetry technique using agar to measure the dose distribution near substance boundaries. Varying the concentration of an oxygen scavenger (tetra-hydroxymethyl phosphonium chloride) showed the absorbed dose and transverse relaxation rate of the magnetic resonance signal to be linear between 3 and 12 Gy. Although a change in the dosimeter due to oxidization was observed in room air after 24 hours, no such effects were observed in the first 4 hours. The dose distribution around the metal implants was measured using agar dosimetry. The metals tested were a lead rod, a titanium hip joint, and a metallic stent. A maximum 30% dose increase was observed near the lead rod, but only a 3% increase in the absorbed dose was noted near the surface of the titanium hip joint and metallic stent. Semi-solid polymer dosimetry using agar thus appears to be a useful method for dosimetry around metallic substances. (author)

[The use of polymer gel dosimetry to measure dose distribution around metallic implants].

Science.gov (United States)

Nagahata, Tomomasa; Yamaguchi, Hajime; Monzen, Hajime; Nishimura, Yasumasa

2014-10-01

A semi-solid polymer dosimetry system using agar was developed to measure the dose distribution close to metallic implants. Dosimetry of heterogeneous fields where electron density markedly varies is often problematic. This prompted us to develop a polymer gel dosimetry technique using agar to measure the dose distribution near substance boundaries. Varying the concentration of an oxygen scavenger (tetra-hydroxymethyl phosphonium chloride) showed the absorbed dose and transverse relaxation rate of the magnetic resonance signal to be linear between 3 and 12 Gy. Although a change in the dosimeter due to oxidization was observed in room air after 24 hours, no such effects were observed in the first 4 hours. The dose distribution around the metal implants was measured using agar dosimetry. The metals tested were a lead rod, a titanium hip joint, and a metallic stent. A maximum 30% dose increase was observed near the lead rod, but only a 3% increase in the absorbed dose was noted near the surface of the titanium hip joint and metallic stent. Semi-solid polymer dosimetry using agar thus appears to be a useful method for dosimetry around metallic substances.

Features of application of test techniques in selection and certification of personnel

Directory of Open Access Journals (Sweden)

Levina E.V.

2017-04-01

Full Text Available this article investigates the problem of use of test techniques in the course of selection and certification of personnel, and also for detection of features of formation of social and psychological climate in small groups and labor collectives. The group dynamics including individual preferences of players in the choice of strategy of behavior in a conflict situation in definition of the most acceptable social role, in identification of the most constructive and effective type of the administrative decision has the special importance. The author of the article offers a set of the test methods allowing to define social and psychological type of the individual at a stage of staff recruitment and to reveal its individual behavioral preferences that can structurally influence on team work.

Dosimetry quality audit of high energy photon beams in greek radiotherapy centers

International Nuclear Information System (INIS)

Hourdakis, Constantine J.; Boziari, A.

2008-01-01

Background and purpose: Dosimetry quality audits and intercomparisons in radiotherapy centers is a useful tool in order to enhance the confidence for an accurate therapy and to explore and dissolve discrepancies in dose delivery. This is the first national comprehensive study that has been carried out in Greece. During 2002 - 2006 the Greek Atomic Energy Commission performed a dosimetry quality audit of high energy external photon beams in all (23) Greek radiotherapy centers, where 31 linacs and 13 Co-60 teletherapy units were assessed in terms of their mechanical performance characteristics and relative and absolute dosimetry. Materials and Methods: The quality audit in dosimetry of external photon beams took place by means of on-site visits, where certain parameters of the photon beams were measured, calculated and assessed according to a specific protocol and the IAEA TRS 398 dosimetry code of practice. In each radiotherapy unit (Linac or Co-60), certain functional parameters were measured and the results were compared to tolerance values and limits. Doses in water under reference and non reference conditions were measured and compared to the stated values. Also, the treatment planning systems (TPS) were evaluated with respect to irradiation time calculations. Results: The results of the mechanical tests, dosimetry measurements and TPS evaluation have been presented in this work and discussed in detail. This study showed that Co-60 units had worse performance mechanical characteristics than linacs. 28% of all irradiation units (23% of linacs and 42% of Co-60 units) exceeded the acceptance limit at least in one mechanical parameter. Dosimetry accuracy was much worse in Co60 units than in linacs. 61% of the Co60 units exhibited deviations outside ±3% and 31% outside ±5%. The relevant percentages for the linacs were 24% and 7% respectively. The results were grouped for each hospital and the sources of errors (functional and human) have been investigated and

Dosimetry quality audit of high energy photon beams in greek radiotherapy centers.

Science.gov (United States)

Hourdakis, Constantine J; Boziari, A

2008-04-01

Dosimetry quality audits and intercomparisons in radiotherapy centers is a useful tool in order to enhance the confidence for an accurate therapy and to explore and dissolve discrepancies in dose delivery. This is the first national comprehensive study that has been carried out in Greece. During 2002--2006 the Greek Atomic Energy Commission performed a dosimetry quality audit of high energy external photon beams in all (23) Greek radiotherapy centers, where 31 linacs and 13 Co-60 teletherapy units were assessed in terms of their mechanical performance characteristics and relative and absolute dosimetry. The quality audit in dosimetry of external photon beams took place by means of on-site visits, where certain parameters of the photon beams were measured, calculated and assessed according to a specific protocol and the IAEA TRS 398 dosimetry code of practice. In each radiotherapy unit (Linac or Co-60), certain functional parameters were measured and the results were compared to tolerance values and limits. Doses in water under reference and non reference conditions were measured and compared to the stated values. Also, the treatment planning systems (TPS) were evaluated with respect to irradiation time calculations. The results of the mechanical tests, dosimetry measurements and TPS evaluation have been presented in this work and discussed in detail. This study showed that Co-60 units had worse performance mechanical characteristics than linacs. 28% of all irradiation units (23% of linacs and 42% of Co-60 units) exceeded the acceptance limit at least in one mechanical parameter. Dosimetry accuracy was much worse in Co60 units than in linacs. 61% of the Co60 units exhibited deviations outside +/-3% and 31% outside +/-5%. The relevant percentages for the linacs were 24% and 7% respectively. The results were grouped for each hospital and the sources of errors (functional and human) have been investigated and discussed in details. This quality audit proved to be a

Dosimetry for Crystals Irradiation

CERN Document Server

Lecomte, Pierre

2005-01-01

Before shipment to CMS, all PbWO4 crystals produced in China are irradiated there with 60 Co , in order to insure that the induced absorption coefficient is within specifications. Acceptance tests at CERNand at ENEA also include irradiation with gamma rays from 60 Co sources. There were initially discrepancies in quoted doses and doserates as well as in induced absorption coefficients. The present work resolves the discrepancies in irradiation measurements and defines common dosimetry methods for consistency checks between irradiation facilities.

The Hiroshima neutron dosimetry enigma: Missing puzzle piece No. 6

International Nuclear Information System (INIS)

Gold, Raymond

1999-01-01

More than a decade has elapsed since the serious nature of the discrepancy between neutron dosimetry experiments (E) and neutron transport calculations (C) for the Hiroshima site was identified. Since that time extensive efforts to resolve this Hiroshima neutron dosimetry enigma have not only failed, but now demonstrate that the magnitude of this discrepancy is much greater than initially estimated. The currently evaluated E/C ratio for thermal neutron fluence at the Hiroshima site increases rapidly with increasing slant range from the epicenter. In the slant range region beyond 1000 m, E/C exceeds unity by one to two orders of magnitude depending on the specific dosimetry data that are utilized. Principal features that characterize the Hiroshima neutron dosimetry enigma are summarized. Puzzle Piece No. 6: In-situ production and Prompt fallout of radionuclides from Little Boy is advanced as a possible contributory phenomenon to this enigma. (The atom bomb detonated over Hiroshima was called Little Boy.) Measurements of 60 Co and 152 Eu specific activity at the Hiroshima site are used to obtain order of magnitude numerical estimates that show this conjecture is plausible. Comparison of different 60 Co measurements at the Hiroshima site reveals that the variation of E/C with slant range depends on the method used to quantify 60 Co specific activity as well as the type of dosimetry samples that are employed. These 60 Co comparisons lend additional qualitative credence to this conjecture. Within the limits of presently available data, these assessments show that Puzzle Piece No. 6 qualitatively satisfies the principal features that characterize the Hiroshima neutron dosimetry enigma. Nevertheless, current lack of data prevent this conjecture from being conclusively confirmed or refuted. Consequently, specific recommendations are advanced to resolve the Hiroshima neutron dosimetry enigma with emphasis on experimental tests that can quantitatively evaluate Puzzle Piece

SU-F-T-562: Validation of EPID-Based Dosimetry for FSRS Commissioning

International Nuclear Information System (INIS)

Song, Y; Saleh, Z; Obcemea, C; Chan, M; Tang, X; Lim, S; Lovelock, D; Ballangrud, A; Mueller, B; Zinovoy, M; Gelblum, D; Mychalczak, B; Both, S

2016-01-01

Purpose: The prevailing approach to frameless SRS (fSRS) small field dosimetry is Gafchromic film. Though providing continuous information, its intrinsic uncertainties in fabrication, response, scan, and calibration often make film dosimetry subject to different interpretations. In this study, we explored the feasibility of using EPID portal dosimetry as a viable alternative to film for small field dosimetry. Methods: Plans prescribed a dose of 21 Gy were created on a flat solid water phantom with Eclipse V11 and iPlan for small static square fields (1.0 to 3.0 cm). In addition, two clinical test plans were computed by employing iPlan on a CIRS Kesler head phantom for target dimensions of 1.2cm and 2.0cm. Corresponding portal dosimetry plans were computed using the Eclipse TPS and delivered on a Varian TrueBeam machine. EBT-XD film dosimetry was performed as a reference. The isocenter doses were measured using EPID, OSLD, stereotactic diode, and CC01 ion chamber. Results: EPID doses at the center of the square field were higher than Eclipse TPS predicted portal doses, with the mean difference being 2.42±0.65%. Doses measured by EBT-XD film, OSLD, stereotactic diode, and CC01 ion chamber revealed smaller differences (except OSLDs), with mean differences being 0.36±3.11%, 4.12±4.13%, 1.7±2.76%, 1.45±2.37% for Eclipse and −1.36±0.85%, 2.38±4.2%, −0.03±0.50%, −0.27±0.78% for iPlan. The profiles measured by EPID and EBT-XD film resembled TPS (Eclipse and iPlan) predicted ones within 3.0%. For the two clinical test plans, the EPID mean doses at the center of field were 2.66±0.68% and 2.33±0.32% higher than TPS predicted doses. Conclusion: We found that results obtained with EPID portal dosimetry were slightly higher (∼2%) than those obtained with EBT-XD film, diode, and CC01 ion chamber with the exception of OSLDs, but well within IROC tolerance (5.0%). Therefore, EPID has the potential to become a viable real-time alternative method to film dosimetry.

SU-F-T-562: Validation of EPID-Based Dosimetry for FSRS Commissioning

Energy Technology Data Exchange (ETDEWEB)

Song, Y; Saleh, Z; Obcemea, C; Chan, M; Tang, X; Lim, S; Lovelock, D; Ballangrud, A; Mueller, B; Zinovoy, M; Gelblum, D; Mychalczak, B; Both, S [Memorial Sloan Kettering Cancer Center, NY (United States)

2016-06-15

Purpose: The prevailing approach to frameless SRS (fSRS) small field dosimetry is Gafchromic film. Though providing continuous information, its intrinsic uncertainties in fabrication, response, scan, and calibration often make film dosimetry subject to different interpretations. In this study, we explored the feasibility of using EPID portal dosimetry as a viable alternative to film for small field dosimetry. Methods: Plans prescribed a dose of 21 Gy were created on a flat solid water phantom with Eclipse V11 and iPlan for small static square fields (1.0 to 3.0 cm). In addition, two clinical test plans were computed by employing iPlan on a CIRS Kesler head phantom for target dimensions of 1.2cm and 2.0cm. Corresponding portal dosimetry plans were computed using the Eclipse TPS and delivered on a Varian TrueBeam machine. EBT-XD film dosimetry was performed as a reference. The isocenter doses were measured using EPID, OSLD, stereotactic diode, and CC01 ion chamber. Results: EPID doses at the center of the square field were higher than Eclipse TPS predicted portal doses, with the mean difference being 2.42±0.65%. Doses measured by EBT-XD film, OSLD, stereotactic diode, and CC01 ion chamber revealed smaller differences (except OSLDs), with mean differences being 0.36±3.11%, 4.12±4.13%, 1.7±2.76%, 1.45±2.37% for Eclipse and −1.36±0.85%, 2.38±4.2%, −0.03±0.50%, −0.27±0.78% for iPlan. The profiles measured by EPID and EBT-XD film resembled TPS (Eclipse and iPlan) predicted ones within 3.0%. For the two clinical test plans, the EPID mean doses at the center of field were 2.66±0.68% and 2.33±0.32% higher than TPS predicted doses. Conclusion: We found that results obtained with EPID portal dosimetry were slightly higher (∼2%) than those obtained with EBT-XD film, diode, and CC01 ion chamber with the exception of OSLDs, but well within IROC tolerance (5.0%). Therefore, EPID has the potential to become a viable real-time alternative method to film dosimetry.

Individual neutron dosimetry

International Nuclear Information System (INIS)

Mauricio, C.L.P.

1987-01-01

The most important concepts and development in individual neutron dosimetry are presented, especially the dosimetric properties of the albedo technique. The main problem in albedo dosimetry is to calibrate the dosemeter in the environs of each neutron source. Some of the most used calibration techniques are discussed. The IRD albedo dosemeter used in the routine neutron individual monitoring is described in detail. Its dosimetric properties and calibration methods are discussed. (Author) [pt

Neutron dosimetry. Environmental monitoring in a BWR type reactor

International Nuclear Information System (INIS)

Tavera D, L.; Camacho L, M.E.

1991-01-01

The measurements carried out on reactor dosimetry are applied mainly to the study on the effects of the radiation in 108 materials of the reactor; little is on the environmental dosimetry outside of the primary container of BWR reactors. In this work the application of a neutron spectrometer formed by plastic detectors of nuclear traces manufactured in the ININ, for the environmental monitoring in penetrations around the primary container of the unit I of the Laguna Verde central is presented. The neutron monitoring carries out with purposes of radiological protection, during the operational tests of the reactor. (Author)

Advantages and disadvantages of luminescence dosimetry

Energy Technology Data Exchange (ETDEWEB)

Olko, Pawel, E-mail: Pawel.Olko@ifj.edu.p [Institute of Nuclear Physics Polish Academy of Science (IFJ PAN), Krakow (Poland)

2010-03-15

Owing to their excellent dosimetric properties, luminescence detectors of ionizing radiation are now extensively applied in individual dosimetry services. The most frequently used personal dosemeters are based on Optically Stimulated Luminescence (OSL), radiophotoluminescence (RPL) or thermoluminescence (TL). Luminescence detectors have also found several applications in clinical dosimetry, especially around new radiation modalities in radiotherapy, such as Intensity Modulated Radiotherapy (IMRT) or ion beam radiotherapy. Requirements of luminescence detectors applied in individual and clinical dosimetry and some recent developments in luminescence of detectors and techniques leading to significant improvements of the functionality and accuracy of dosimetry systems are reviewed and discussed.

Twenty new ISO standards on dosimetry for radiation processing

International Nuclear Information System (INIS)

Farrar IV, H.

2000-01-01

Twenty standards on essentially all aspects of dosimetry for radiation processing were published as new ISO standards in December 1998. The standards are based on 20 standard practices and guides developed over the past 14 years by Subcommittee E10.01 of the American Society for Testing and Materials (ASTM). The transformation to ISO standards using the 'fast track' process under ISO Technical Committee 85 (ISO/TC85) commenced in 1995 and resulted in some overlap of technical information between three of the new standards and the existing ISO Standard 11137 Sterilization of health care products - Requirements for validation and routine control - Radiation sterilization. Although the technical information in these four standards was consistent, compromise wording in the scopes of the three new ISO standards to establish precedence for use were adopted. Two of the new ISO standards are specifically for food irradiation applications, but the majority apply to all forms of gamma, X-ray, and electron beam radiation processing, including dosimetry for sterilization of health care products and the radiation processing of fruit, vegetables, meats, spices, processed foods, plastics, inks, medical wastes, and paper. 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 using the new ISO Type A and Type B evaluations. Unfortunately, nine of the 20 standards just adopted by the ISO are not the most recent versions of these standards and are therefore already out of date. To help solve this problem, efforts are being made to develop procedures to coordinate the ASTM and ISO development and revision processes for these and future ASTM-originating dosimetry standards. In the meantime, an additional four dosimetry standards have recently been published by the ASTM but have

The implementation of the operational dose quantities into radiation protection dosimetry (NRPB Association)

International Nuclear Information System (INIS)

O'Riordan, M.C.; Chartier, J.L.

1993-01-01

The main objectives of this project are to improve the measurement of spectral and angular distributions of external radiations in the workplace and to examine the implications of these measurements for personal dosimetry. They include measurement techniques for X-ray, γ-radiation and neutron radiation, performance testing of personal dosemeters, the implications of spectral and spatial distributions measurements on personal dosimetry. (R.P.)

Accidental and retrospective dosimetry using TL method

International Nuclear Information System (INIS)

Mesterházy, D.; Osvay, M.; Kovács, A.; Kelemen, A.

2012-01-01

Retrospective dosimetry is one of the most important tools of accidental dosimetry for dose estimation when dose measurement was not planned. In the affected area many objects can be applied as natural dosimeters. The paper discusses our recent investigations on various electronic components and common salt (NaCl) having useful thermoluminescence (TL) properties. Among materials investigated the electronic components of cell phones seem promising for retrospective dosimetry purposes, having high TL responses, proper glow curve peaks and the intensity of TL peaks vs. gamma dose received provided nearly linear response in the dose range of 10 mGy–1.5 Gy. - Highlights: ► Electronic components and common salt were investigated for accidental and retrospective dosimetry. ► SMD resistors seem promising for retrospective dosimetry purposes. ► Table salt can be used effectively for accidental dosimetry purposes, as well.

Radiophotoluminescence light scope for high-dose dosimetry

International Nuclear Information System (INIS)

Sato, Fuminobu; Zushi, Naoki; Sakiyama, Tomoki; Kato, Yushi; Murata, Isao; Shimizu, Kikuo; Yamamoto, Takayoshi; Iida, Toshiyuki

2015-01-01

A radiophotoluminescence (RPL) light scope is a remote-sensing technique for measuring in situ the radiation dose in an RPL detector placed at a distance. The RPL light scope is mainly composed of an ultraviolet (UV) pulse laser, telescopic lenses, a photomultiplier tube, and camera modules. In a performance test, some RPL detectors were placed at distances up to 30 m and were illuminated with a pulsed UV laser beam. The photoluminescence responses of the RPL detectors were analyzed using this scope. Their radiation doses were determined from the amplitude of the given component of the photoluminescence responses. The RPL readout could be repeated without fading, and its amplitude exhibited good linearity at a dose ranging from 0.1 to 60 Gy. Furthermore, a two-dimensional distribution of radiation dose was obtained by laser scanning on an RPL detector. It was confirmed that the RPL light scope was a useful remote-sensing tool for high-dose dosimetry. - Highlights: • A radiophotoluminescence (RPL) light scope was developed for high-dose dosimetry. • The RPL light scope has high sensitivity and accuracy in high-dose dosimetry. • Two-dimensional radiation dose distribution was obtained by the RPL light scope.

SSDL personel dosimetry system: migration from a client - server system into a web-based system

International Nuclear Information System (INIS)

Maizura Ibrahim; Rosnah Shariff; Ahmad Bazlie Abdul Kadir; John Konsoh Sangau; Mohd Amin Sharifuldin Salleh; Taiman Kadni; Noriah Mod Ali

2007-01-01

Personnel Dosimetry System has been used by the Secondary Standard Dosimetry Laboratory (SSDL), Nuclear Malaysia since ten years ago. The system is a computerized database system with a client-server concept. This system has been used by Film Badge Laboratory, SSDL to record details of clients, calculation of Film Badge dosage, management of radiation workers data's, generating of dosage report, retrieval of statistical reports regarding film badge usage for the purpose of reporting to monitoring bodies such as Atomic Energy Licensing Board (AELB), Ministry of Health and others. But, due to technical problems that frequently occurs, the system is going to be replaced by a newly developed web- based system called e-SSDL. This paper describe the problems that regularly occurs in the previous system, explains how the process of replacing the client-server system with a web-based system is done and the differences between the previous and current system. This paper will also present details architecture of the new system and the new process introduced in processing film badges. (Author)

Experiences with alanine dosimetry in afterloading brachytherapy

International Nuclear Information System (INIS)

Eberhardt, H.-J.; Gohs, U.

1996-01-01

At the present, the most commonly used dosimetry for radiotherapy applications are ionisation chambers and thermoluminescent dosimeters (TLD). However, there are some undesirable characteristics of these dosimetry systems, such as large detection volume (ionisation chamber) as well as fading of the radiation induced signal with time and destructive readout (TLG). The present study is an investigation into the use of the alanine/ESR dosimetry in fractionated afterloading brachytherapy during the whole radiotherapy course. There are some qualities which make alanine dosimetry attractive. These are the linear energy response, low fading under standard conditions, and the nondestructive readout. Thus the alanine dosimetry makes possible cumulative dose measurements during the radiotherapy course and an archival storage. By ionizing radiation (gamma, e, n, p, charged particles) free radicals (unpaired electrons) are produced in the amino acid alanine. The continuous wave electron spin resonance (ESR) spectroscopy is used to determine the number of free radicals, which is proportional to the absorbed dose and the alanine content of the dosimeter. The ESR measurements were made at room temperature using a Bruker EPR analyzer EMS-104. The dosimeters used in the test are alanine pellets (23.72 mg weight, 4.9 mm diameter, 1 mm height) as well as flexible alanine film dosimeters (thickness about 500 μm). The dosimeters consist of a blend of L-alpha-alanine and a binder. The alanine content of the pellets and the film dosimeters is about 88 % and 50 % by weight, respectively. The dosimeters for the calculation of the dose-effect-relationship were irradiated at the Physical-Technical Bundesanstalt in Braunschweig by a standard 60Co source. The maximum deviation from the calculated linear function is about 0.12 Gy in the dose range up to 80 Gy. The goal of medical applications was the superficial dose measurement in afterloading brachytherapy during the radiotherapy course in

Personal dosimetry service of VF, a.s. company

International Nuclear Information System (INIS)

Prasek, P.

2009-01-01

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 Al 2 O 3 :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)

Personal dosimetry service of VF, a.s. company

International Nuclear Information System (INIS)

Prasek, P.

2008-01-01

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 Al 2 O 3 :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)

Personnel neutron dose assessment upgrade: Volume 2, Field neutron spectrometer for health physics applications

International Nuclear Information System (INIS)

Brackenbush, L.W.; Reece, W.D.; Miller, S.D.

1988-07-01

Both the (ICRP) and the (NCPR) have recommended an increase in neutron quality factors and the adoption of effective dose equivalent methods. The series of reports entitled Personnel Neutron Dose Assessment Upgrade (PNL-6620) addresses these changes. Volume 1 in this series of reports (Personnel Neutron Dosimetry Assessment) provided guidance on the characteristics, use, and calibration of personnel neutron dosimeters in order to meet the new recommendations. This report, Volume 2: Field Neutron Spectrometer for Health Physics Applications describes the development of a portable field spectrometer which can be set up for use in a few minutes by a single person. The field spectrometer described herein represents a significant advance in improving the accuracy of neutron dose assessment. It permits an immediate analysis of the energy spectral distribution associated with the radiation from which neutron quality factor can be determined. It is now possible to depart from the use of maximum Q by determining and realistically applying a lower Q based on spectral data. The field spectrometer is made up of two modules: a detector module with built-in electronics and an analysis module with a IBM PC/reg sign/-compatible computer to control the data acquisition and analysis of data in the field. The unit is simple enough to allow the operator to perform spectral measurements with minimal training. The instrument is intended for use in steady-state radiation fields with neutrons energies covering the fission spectrum range. The prototype field spectrometer has been field tested in plutonium processing facilities, and has been proven to operate satisfactorily. The prototype field spectrometer uses a 3 He proportional counter to measure the neutron energy spectrum between 50 keV and 5 MeV and a tissue equivalent proportional counter (TEPC) to measure absorbed neutron dose