WorldWideScience

Sample records for radiation dosimetry study

  1. Radiation dosimetry

    International Nuclear Information System (INIS)

    Harper, M.W.; Thomas, B.; Conway, J.

    1977-01-01

    A dosemeter is described that is based on the TSCD principle (thermally stimulated current dosimetry). Basically this involves irradiating a responsive material and then heating it,whereby an electric current is produced. If the material is heated in an electric field the peak value of the thermally stimulated current or alternatively the total charge released by heating, can be related to the radiation dose received. The instrument described utilises a sheet coated with a thermoplastic polymer, such as a poly4-methylpent-l-ene. The polymer should have a softening point not lower than 150 0 C with an electrical resistivity of at least 10 16 chms/cm at 150 0 C. The polymer may also be PTFE. Heating should be in the range 150 0 C to 200 0 C and the electric field in the range 50 to 10,000V/mm. (U.K.)

  2. Dosimetry studies during breast cancer radiation treatment

    International Nuclear Information System (INIS)

    Ahmed, M. O. M.

    2005-06-01

    Previous studies indicated that breast cancer is wildly spread especially in women as compared to men. It is increased after an age of thirty five years in women so it is important to study the effect of exposure to the radiation on the intact breast during the treatment of the breast suffering from cancer. In this work the scattered doses for the intact breast during the treatment of the breast suffering from cancer were measured and also the probability of inducing cancer in it is also discussed. The study was performed for a group of patients composed of twenty five females. Also the backscattered doses to the intact breast were measured for thirteen female patients. During the treatment using gamma rays from Co-60 source the two tangential fields (lateral and medial) were selected for the measurements. The results of exposure to gamma radiation for the lateral and medial fields showed that the mean scattered and backscattered doses to the intact breast were (241.26 cGY,47.49 cGY) and (371.6 cGY,385.4 cGY), respectively. Beside that the somatic risk of induced cancer to the intact breast was found to be (6 .1X10 -3 ,1.2X10 -3 ) and (9.29X10 -3 , 9.63X10 -3 ), respectively. From the results obtained it was concluded that the intact breast received small amounts of radiation doses which may lead to breast cancer for the healthy breast. The recommendations from the present study are to take care of radiation protection to the patient, and also to take care of the patient treatment conditions like temperature, pressure and humidity during the radiation exposure.(Author)

  3. 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

  4. 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...

  5. Comparative study of Si diodes for gamma radiation dosimetry

    International Nuclear Information System (INIS)

    Pascoalino, Kelly Cristina da Silva

    2010-01-01

    In this work it is presented the comparative study of Si diodes response for gamma radiation dosimetry. The diodes investigated, grown by float zone (Fz) and magnetic Czochralski (MCz) techniques, were processed at the Physics Institute of Helsinki University in the framework of the research and development of rad-hard silicon devices. To study the dosimetric response of these diodes they were connected in the photovoltaic mode to the input of a digital electrometer to measure the photocurrent signal due to the incidence of gamma-rays from a 60 Co source (Gammacell 220). The dosimetric parameter utilized to study the response of these devices was the charge, obtained trough the integration of the current signals, as a function of the absorbed dose. Studies of the influence of the pre-irradiation procedures on both sensitivity and stability of these diodes showed that the sensitivity decreased with the total absorbed dose but after a preirradiation of about 873 kGy they became more stable. Radiation damage effects eventually produced in the devices were monitored trough dynamic current and capacitance measurements after each irradiation step. Both samples also exhibited good response reproducibility, 2,21% (Fz) and 2,94% (MCz), obtained with 13 consecutive measurements of 15 kGy compared with the equivalent 195 kGy absorbed dose in one step of irradiation. It is important to note that these results are better than those obtained with routine polymethylmethacrylate (PMMA) dosimeters used in radiation processing dosimetry. (author)

  6. Application of Apollo cosmic radiation dosimetry to lunar colonization studies

    International Nuclear Information System (INIS)

    English, R.A.; Bailey, J.V.; Brown, R.D.

    1972-01-01

    The radiation data gathered from the lunar landing missions of Apollo 11 through Apollo 15 are presented. These data have been analyzed to provide dosimetry evaluation of the ambient radiation and radiation from potential solar particle events for the planning of safe, long-term stays of relatively large numbers of individuals upon the moon. (U.S.)

  7. Dosimetry study for electron beam irradiation in radiation processing

    International Nuclear Information System (INIS)

    Sunaga, Hiromi; Haruyama, Yasuyuki; Takizawa, Haruki; Kojima, Takuji; Yotsumoto, Keiichi

    1995-01-01

    For certain critical applications such as medical device sterilization and food irradiation, accurate calibration of electron energy and absorbed dose is required to assure the quality of irradiated products. To meet this requirement, TRCRE, JAERI has carried out research and development on high dose radiation dosimetry for electron beams in the energy range used in radiation processing (0.15 - 3.0 MeV). JAERI has developed a simultaneous electron beam energy and dosimeter calibration system that consist of a total absorption calorimeter, an electron current density meter, and a stacked thin-film dosimeter set. For low energy electrons, where it is important to measure the depth-dose profile in materials with high depth resolution, we studied the feasibility of a method using Gafchromic film dosimeters. This film, which has an 8-μm thick sensitive layer, is combined with a stepped array of absorber films of the same thickness to produce a high-resolution depth-dose profile on the Gafchromic film. The depth-dose profile obtained in this manner has about five times greater resolution than conventional radiochromic film dosimetry. (author)

  8. 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

  9. Radiation dosimetry

    International Nuclear Information System (INIS)

    Aymar A, J.; Medina G, H.

    1988-01-01

    Film is one of the most simple ways to detect radiation although for film as dosimeters a careful attention is required in many aspects, such as emulsion characteristics, film response capacity processing techniques and interpretation of the exposition. Surpassing these factors the film dosimeter is the most reliable

  10. 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)

  11. 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)

  12. Group: radiation dosimetry

    International Nuclear Information System (INIS)

    Caldas, L.V.E.

    1990-01-01

    The main activities of the radiation dosimetry group is described, including the calibration of instruments, sources and radioactive solutions and the determination of neutron flux; development, production and market dosimetric materials; development radiation sensor make the control of radiation dose received by IPEN workers; development new techniques for monitoring, etc. (C.G.C.)

  13. Solid state radiation dosimetry

    International Nuclear Information System (INIS)

    Moran, P.R.

    1976-01-01

    Important recent developments provide accurate, sensitive, and reliable radiation measurements by using solid state radiation dosimetry methods. A review of the basic phenomena, devices, practical limitations, and categories of solid state methods is presented. The primary focus is upon the general physics underlying radiation measurements with solid state devices

  14. 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

  15. 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

  16. Nuclear medicine radiation dosimetry

    CERN Document Server

    McParland, Brian J

    2010-01-01

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

  17. Dosimetry for radiation processing

    International Nuclear Information System (INIS)

    Kumar, A.; Reddy, A.R.

    1994-01-01

    The last few years have seen a significant increase in the use of ionising radiation in industrial processes and also international trade in irradiated products. With this, the demand for internationally accepted dosimetric techniques, accredited to international standards has also increased which is further stimulated by the emergence of ISO-9000 series of standards in industries. The present paper describes some of the important dosimetric techniques used in radiation processing, the role of IAEA in evolving internationally accepted standards and work carried out at the Defence Laboratories, Jodhpur in the development of a cheap, broad dose range and simple dosimeter for routine dosimetry. For this polyhydroxy alcohols viz., mannitol, sorbitol and inositol were studied using the spectrophotometric read out method. Out of the alcohols studied mannitol was found to be most promising covering a dose range of 0.01 kGy - 100 kGy. (author). 26 refs., 3 figs., 1 tab

  18. WIPP radiation dosimetry program

    International Nuclear Information System (INIS)

    Wu, C.F.

    1991-01-01

    Radiation dosimetry is the process by which various measurement results and procedures are applied to quantify the radiation exposure of an individual. Accurate and precise determination of radiation dose is a key factor to the success of a radiation protection program. The Waste Isolation Pilot Plant (WIPP), a Department of Energy (DOE) facility designed for permanent repository of transuranic wastes in a 2000-foot-thick salt bed 2150 feet underground, has established a dosimetry program developed to meet the requirements of DOE Order 5480.11, ''Radiation Protection for Occupational Workers''; ANSI/ASME NQA-1, ''Quality Assurance Program Requirements for Nuclear Facilities''; DOE Order 5484.1, ''Environmental Protection, Safety, and Health Protection Information Reporting Requirements''; and other applicable regulations

  19. Metabolomics in Radiation-Induced Biological Dosimetry: A Mini-Review and a Polyamine Study

    Directory of Open Access Journals (Sweden)

    Changhyun Roh

    2018-05-01

    Full Text Available In this study, we elucidate that polyamine metabolite is a powerful biomarker to study post-radiation changes. Metabolomics in radiation biodosimetry, the application of a metabolomics analysis to the field of radiobiology, promises to increase the understanding of biological responses by ionizing radiation (IR. Radiation exposure triggers a complex network of molecular and cellular responses that impacts metabolic processes and alters the levels of metabolites. Such metabolites have potential as biomarkers for radiation dosimetry. Among metabolites, polyamine is one of many potential biomarkers to estimate radiation response. In addition, this review provides an opportunity for the understanding of a radiation metabolomics in biodosimetry and a polyamine case study.

  20. Study of radiation dosimetry for child in dentistry, 1. Examination survey on radiation dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Tateno, H; Shinji, H; Higaki, M; Kanno, M; Higashi, T [Kanagawa Dental Coll., Yokosuka (Japan)

    1980-09-01

    Patients in pedodontics usually do not appropriately report the symptoms of their own disease because of their immaturity. For this reason X-ray inspection plays a big part in diagnosis. It is considered that radiation injury for children is generally more severe than that for adults under the same exposure dose. Therefore it is necessary to detect the effective minimum exposure dose as accurately as possible for protection. The exposure dose was surveyed by use of TLD combined with the 6-films technique for children (child intraoral technique) currently used in the dental clinic. First, the reliability of TLD, the effect of scattered rays and indicator dependence etc. were tested. Second, the distribution of exposure dose in the intraoral technique for children was examined by water phantom. The following results were obtained. 1. It was necessary to select the stabilized TLD as the measuring values were comparatively scattered. 2. Measuring of the effect of scattered rays showed that it was the least in use of Pb, value of which was 101 for air dose 100. This indicated that Pb was the best for scatter protection. 3. For the indicator dependence it was unnecessary to adjust the glancing angle in case it was below 60 degrees. 4. TLD showed a stable result even in the increased time of exposure, and at the same time there was no error with the electric timer. 5. The result of the basic experiment of water phantom required further investigation as to the overlapped exposure in treatment of child patients with much smaller dental arches where the irradiation field was bigger than in that of adult patients with larger dental arches.

  1. Measurement assurance studies of high-energy electron and photon dosimetry in radiation-therapy applications

    Energy Technology Data Exchange (ETDEWEB)

    Ehrlich, M; Soares, C G [National Bureau of Standards, Washington, DC (USA)

    1981-08-01

    This is a brief review of surveys on the dosimetry of radiation-therapy beams by the National Bureau of Standards (NBS). Covered are the NBS ferrous-sulfate (Fricke) dosimetry service, a recently completed survey carried out with thermoluminescence dosimeters (TLD) on the dosimetry in cobalt-60 teletherapy beams, and plans for a TLD survey of dosimetry in high-energy bremsstrahlung beams.

  2. 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)

  3. 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.

  4. Radiation dosimetry in nuclear medicine

    International Nuclear Information System (INIS)

    Stabin, M.G.; Tagesson, M.; Ljungberg, M.; Strand, S.E.; Thomas, S.R.

    1999-01-01

    Radionuclides are used in nuclear medicine in a variety of diagnostic and therapeutic procedures. A knowledge of the radiation dose received by different organs in the body is essential to an evaluation of the risks and benefits of any procedure. In this paper, current methods for internal dosimetry are reviewed, as they are applied in nuclear medicine. Particularly, the Medical Internal Radiation Dose (MIRD) system for dosimetry is explained, and many of its published resources discussed. Available models representing individuals of different age and gender, including those representing the pregnant woman are described; current trends in establishing models for individual patients are also evaluated. The proper design of kinetic studies for establishing radiation doses for radiopharmaceuticals is discussed. An overview of how to use information obtained in a dosimetry study, including that of the effective dose equivalent (ICRP 30) and effective dose (ICRP 60), is given. Current trends and issues in internal dosimetry, including the calculation of patient-specific doses and in the use of small scale and microdosimetry techniques, are also reviewed

  5. Foundations of ionizing radiation dosimetry

    International Nuclear Information System (INIS)

    Denisenko, O.N.; Pereslegin, I.A.

    1985-01-01

    Foundations of dosimetry in application to radiotherapy are presented. General characteristics of ionizing radiations and main characteristics of ionizing radiation sources, mostly used in radiotherapy, are given. Values and units for measuring ionizing radiation (activity of a radioactive substance, absorbed dose, exposure dose, integral dose and dose equivalent are considered. Different methods and instruments for ionizing radiation dosimetry are discussed. The attention is paid to the foundations of clinical dosimetry (representation of anatomo-topographic information, choice of radiation conditions, realization of radiation methods, corrections for a configuration and inhomogeneity of a patient's body, account of biological factors of radiation effects, instruments of dose field formation, control of irradiation procedure chosen)

  6. Measurement assurance studies of high-energy electron and photon dosimetry in radiation-therapy applications

    International Nuclear Information System (INIS)

    Ehrlich, M.; Soares, C.G.

    1981-01-01

    This is a brief review of surveys on the dosimetry of radiation-therapy beams by the National Bureau of Standards (NBS). Covered are the NBS ferrous-sulfate (Fricke) dosimetry service, a recently completed survey carried out with thermoluminescence dosimeters (TLD) on the dosimetry in cobalt-60 teletherapy beams, and plans for a TLD survey of dosimetry in high-energy bremsstrahlung beams. (author)

  7. 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

  8. Dosimetry of high energy radiation

    CERN Document Server

    Sahare, P D

    2018-01-01

    High energy radiation is hazardous to living beings and a threat to mankind. The correct estimation of the high energy radiation is a must and a single technique may not be very successful. The process of estimating the dose (the absorbed energy that could cause damages) is called dosimetry. This book covers the basic technical knowledge in the field of radiation dosimetry. It also makes readers aware of the dangers and hazards of high energy radiation.

  9. Outline of recent studies on dosimetry for external radiations

    International Nuclear Information System (INIS)

    Yamaguchi, Yasuhiro; Iwai, Satoshi.

    1995-01-01

    On the opportunity of adopting the new basic recommendation of ICRP in 1990, the research on the method of evaluating external radiation exposure dose has become to be carried out actively. In this recommendation, the definition of the dose used for radiation protection was changed largely, accordingly, the necessity to prepare the dose conversion factor based on the new definition and so on has arisen. Also in Japan, the research for this purpose has been carried out, and in January, 1995, the workshop on the recent method for evaluating external radiation exposure dose was held at Japan Atomic Energy Research Institute. In this report, the contents discussed at the workshop and the outline of the recent studies on this subject are described. As the international trend of dose evaluation, the recommendation of ICRP in 1990, the ICRU report 51 and the ICRP publication 71 by the joint ICRP/ICRU task group are introduced. In Japan, the studies have been advanced centering around the reassessment of dose conversion factors for photons, electrons and neutrons. The dose evaluation for photons, electrons and neutrons, and the dose evaluation around high energy accelerators are explained. Many problems to be solved still remain as the subjects of research for hereafter. (K.I.)

  10. Use of thermoluminescent dosimetry in gamma radiation fields studies

    International Nuclear Information System (INIS)

    Carron, W.

    1987-01-01

    The depth-dose curves for gamma rays in material of interest to agronomy were obtained using lithium fluoride thermoluminescent dosimeters. The dose conversion factors for LiF were determined from curves of the absorved dose versus depth in water, wood and soil. Mathematics equations were chosen to best fit these curves. In the view of the results we came to the conclusion that in the studied materials the absorved radiation dose presents a great variation to the depth and could be correlated through of the exponential regression. (author)

  11. Study the Effect of Gamma Radiation on some Solid and Polymeric Materials and Its Possible Applications in Radiation Dosimetry

    International Nuclear Information System (INIS)

    El-Shawadfy, E.R.

    2015-01-01

    Dyed solid materials (films and gels) and dyed solutions dosimeters have wide-spread applications in radiation processing for installation process qualification and routine dose control for both gamma rays and electron beam irradiation. These film dosimeters have been introduced for low- and high-dose monitoring. The introduction of new types of dosimeters is due to the effort of seeking for more reliable, more stable, simpler and cheaper systems as routine dosimeters and/or label dosimeters. The main objective of this work is to study the possibility of preparing dyed solid polymeric materials (dyed films- dyed gels) and dyed solutions, and study the dosimetric studies for the prepared materials. The results obtained in this work can be summarized in the following: Section (1): Deals with the investigation of prepared three dosimetry systems based on Toludine Blue O (TBO) dye, to make them readily usable in high and low-radiation dosimetry applications (e.g. sterilization of medical products, sterilization of pharmaceutical products and polymer modification). This section is divided into three parts: Part I: This part includes the preparation and development of polymeric films for high-dose dosimetry applications, these films are based on poly (vinyl alcohol) dyed with TBO. These flexible plastic film dosimeters are bleached when exposed to gamma-ray photons (i.e. from blue to colorless) at λmax=633 nm. The radiation chemical yield (G-Value) for different concentrations of the dye as well as the dye with additive substances (chloral hydrate) was calculated. It was found that these films are highly stable for long time before and after irradiation under different storage conditions. The response of these films is not affected by humidity change in the range of relative humidity (0-56%). PVA films dyed with TBO are suitable in the dose range from 1-150 kGy. These properties suggest them to be useful for routine and dose mapping in sterilization range of radiation

  12. Studies on (Eu2+/Ce3+) activated fluoroperovskites for radiation dosimetry

    International Nuclear Information System (INIS)

    Joseph Daniel, D.; Ramasamya, P.; Madhusoodanan, U.; Annalakshmi, O.

    2014-01-01

    Thermoluminescence dosimetry is based on the principle that the amount of light released by the phosphor material, which has been previously exposed to ionizing radiation, will depend on the radiation dose received by the material. KMgF 3 and NaMgF 3 belongs to a family of fluoroperovskites, ABX 3 , (where A-alkali metal, B-alkali earth X-halide ions). In this paper, we present the results of TL induced by β - irradiation in co-doped ( Eu 2+ Ce 3+ ) fluoride single crystals. TL dose response and fading at room temperature have also been studied

  13. Dosimetry systems for radiation processing

    International Nuclear Information System (INIS)

    McLaughlin, W.L.; Desrosiers, M.F.

    1995-01-01

    Dosimetry serves important functions in radiation processing, where large absorbed doses and dose rates from photon and electron sources have to be measured with reasonable accuracy. Proven dosimetry systems are widely used to perform radiation measurements in development of new processes, validation, qualification and verification (quality control) of established processes and archival documentation of day-to-day and plant-to-plant processing uniformity. Proper calibration and traceability of routine dosimetry systems to standards are crucial to the success of many large-volume radiation processes. Recent innovations and advances in performance of systems that enhance radiation measurement assurance and process diagnostics include dose-mapping media (new radiochromic film and solutions), optical waveguide systems for food irradiation, solid-state devices for real-time and passive dosimetry over wide dose-rate and dose ranges, and improved analytical instruments and data acquisition. (author)

  14. Bayesian Methods for Radiation Detection and Dosimetry

    CERN Document Server

    Groer, Peter G

    2002-01-01

    We performed work in three areas: radiation detection, external and internal radiation dosimetry. In radiation detection we developed Bayesian techniques to estimate the net activity of high and low activity radioactive samples. These techniques have the advantage that the remaining uncertainty about the net activity is described by probability densities. Graphs of the densities show the uncertainty in pictorial form. Figure 1 below demonstrates this point. We applied stochastic processes for a method to obtain Bayesian estimates of 222Rn-daughter products from observed counting rates. In external radiation dosimetry we studied and developed Bayesian methods to estimate radiation doses to an individual with radiation induced chromosome aberrations. We analyzed chromosome aberrations after exposure to gammas and neutrons and developed a method for dose-estimation after criticality accidents. The research in internal radiation dosimetry focused on parameter estimation for compartmental models from observed comp...

  15. Study of radiation-induced paramagnetic centers in quartz and its possible use in radiation dosimetry

    International Nuclear Information System (INIS)

    Mansour, A.M.E.

    2008-01-01

    A new EPR dosimetry system has been developed based on the radiation-formed stable paramagnetic centers in quartz. The first part of the thesis includes the preparation of quartz rods (diameter = 3 mm, length = 10 mm) where quartz powder was mixed with molten mixture of paraffin wax and ethylene vinyl acetate copolymer (EVA). The binding-mixture EVA / paraffin do not present interference or noise in the EPR signal before or after irradiation to high doses. The quartz rods were prepared by different concentrations (5, 10, 20, 30 and 50 %). The rods (30 %) show good mechanical properties for safe and multi-use handling. The second part is concerned with studying the dosimetric characteristics of gamma irradiation sensitive rods where the radiation-formed stable free radicals (E-center, peroxy radical and non-bridging oxygen hole center) which analyzed by using electron paramagnetic resonance (EPR) spectrometer. Unirradiated rods have no EPR signals. The useful dose range of these rods was found to range from 0.1 to 80 kGy depending on concentration of quartz powder, indicating their suitability for low and high dose gamma radiation applications. Also it was found that quartz rod exhibits a linear dose response in the dose regions 0.1-2.34 and 2.34-26 kGy at optimum EPR parameters. The dosimeter response was assessed using the peak-to-peak amplitude of the first-derivatives EPR spectrum. Its EPR signal was found unchanged in shape with different doses and different concentrations. A signal line spectrum attributed to the E-center was observed after irradiation, and this radical is insensitive to temperature, light independence as well as it have a very low decay (4.768 % per year). The overall uncertainty for quartz rod dosimeters at 2σ (σ is standard deviation) was found to be 3.8436 %. The dosimetric parameters, e. g. dose response, effect of temperature during irradiation on response as well as pre- and post-irradiation stability at different storage conditions

  16. Study on the establishment of retrospective dosimetry system for nuclear radiation accident(II)

    Energy Technology Data Exchange (ETDEWEB)

    Jun, Jae Shik; Chai, Ha Seok; Lee, Jong Ok [Chungnam National Univ., Taejon (Korea, Republic of)

    1999-03-15

    This study was driven forward centering around physical techniques in retrospective dosimetry system for encountering nuclear radiation accident. The results obtained through this study are summarized as follow : the minimal facilities based on physical techniques should be assured at KINS for appropriate operation and establishment of retrospective accident dosimetry system, the necessary apparatus and man power for retrospective dose assessment by physical techniques might be operated flexibly, however, CL and TL/OSL readers should be equipped with the highest priority, a series of comparative examination of several physical techniques for retrospective dose assessment revealed that most of the irradiated materials around accident sites are usable for the dose assessment, if a priori study on the dosimetrical characteristics of those materials is preceded in accordance with the species of the collectable samples, the results of the study on the CL-dose response and radiation energy dependence of sugar and sorbitol, showed the nonlinearity in CL-dose relationship at the range of low dose(less than 5 Gy), and it led us to perform a study on the correction of the nonlinearity, and in the later study, CL output showed heavy dependence on radiation energy in the energy below around 100 keV and accordingly, a study on the correction for the energy dependence was also carried out, ve were able to obtain good results as a first attempt to carry out such corrections.

  17. A study of radiation dosimetry for child in dentistry, 1

    International Nuclear Information System (INIS)

    Tateno, Hidemi; Shinji, Hisaaki; Higaki, Morio; Kanno, Masanori; Higashi, Tomomitsu

    1980-01-01

    Patients in pedodontics usually do not appeal appropriately the symptom of their own disease because of their immaturness. For this reason X-ray inspection plays a big part in diagnosis. It is considered that radiation injury for children is generally more severe than that for adults under the same exposure dose. Therefore it is necessary to detect the effective minimum exposure dose as accurately as possible for protection. The exposure dose was surveyed by use of TLD combined with the 6-films technique for children (child intraoral technique) currently used in the dental clinic. Firstry the reliability of TLD, the effect of scattered rays and indicator dependence etc. were tested. Secondly the distribution of exposure dose in the intraoral technique for children was examined by water phantom. The following results were obtained. 1. It was necessary to select the stabilized TLD as the measuring values were comparatively scattered. 2. Measuring of the effect of scattered rays showed that it was the least in use of Pb, value of which was 101 for air dose 100. This indicated that Pb was the best for scatter protection. 3. For the indicator dependence it was unnecessary to adjust the glancing angle in case it was below 60 degrees. 4. TLD showed a stable result even in the increased time of exposure, and at the same time there was no error with the electric timer. 5. The result of the basic experiment of water phantom required further investigation as to the overlapped exposure in treatment of child patients with much smaller dental arches where the irradiation field was bigger than in that of adult patients with larger dental arches. (author)

  18. 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

  19. Calorimetric dosimetry of reactor radiation

    International Nuclear Information System (INIS)

    Radak, B.; Markovic, V.; Draganic, I.

    1961-01-01

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

  20. Study of carbon-doped micro and nano sized alumina for radiation dosimetry applications

    International Nuclear Information System (INIS)

    Fontainha, C. C. P.; Alves, N.; Ferraz, W. B.; Faria, L. O.

    2017-10-01

    New materials have been widely investigated for ionizing radiation dosimetry for medical procedures. Carbon-doped doped alumina (Al 2 O 3 :C) have been proposed as thermoluminescent and photo luminescent dosimeters. In the present study nano and micro-sized alumina doped with different percentages of carbon, sintered under different atmosphere conditions, at temperatures ranging from 1300 to 1750 degrees Celsius, were sintered and their dosimetric characteristics for gamma fields were investigated. Among the investigated sample preparation methods, the micro-sized alumina doped with 0.01% of carbon and sintered at 1700 degrees Celsius under reducing atmosphere has presented the best Tl output, comparable to the best Tl sensitivities ever reported to alumina and better efficiency than the nano-sized alumina synthesized in this study. The influence of humidity in the Tl signal has been evaluated to be -4.0%. The micro-sized alumina obtained by the methodology used in this work is a suitable candidate for application in X and gamma radiation dosimetry. (Author)

  1. Thermoluminescent measurement in space radiation dosimetry

    International Nuclear Information System (INIS)

    Chen Mei; Qi Zhangnian; Li Xianggao; Huang Zengxin; Jia Xianghong; Wang Genliang

    1999-01-01

    The author introduced the space radiation environment and the application of thermoluminescent measurement in space radiation dosimetry. Space ionization radiation is charged particles radiation. Space radiation dosimetry was developed for protecting astronauts against space radiation. Thermoluminescent measurement is an excellent method used in the spaceship cabin. Also the authors mentioned the recent works here

  2. Survey of international personnel radiation dosimetry programs

    International Nuclear Information System (INIS)

    Swaja, R.E.

    1985-04-01

    In September of 1983, a mail survey was conducted to determine the status of external personnel gamma and neutron radiation dosimetry programs at international agencies. A total of 130 agencies participated in this study including military, regulatory, university, hospital, laboratory, and utility facilities. Information concerning basic dosimeter types, calibration sources, calibration phantoms, corrections to dosimeter responses, evaluating agencies, dose equivalent reporting conventions, ranges of typical or expected dose equivalents, and degree of satisfaction with existing systems was obtained for the gamma and neutron personnel monitoring programs at responding agencies. Results of this survey indicate that to provide the best possible occupational radiation monitoring programs and to improve dosimetry accuracy in performance studies, facility dosimetrists, regulatory and standards agencies, and research laboratories must act within their areas of responsibility to become familiar with their radiation monitoring systems, establish common reporting guidelines and performance standards, and provide opportunities for dosimetry testing and evaluation. 14 references, 10 tables

  3. Personnel radiation dosimetry

    International Nuclear Information System (INIS)

    1987-01-01

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

  4. 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)

  5. Ultraviolet germicidal efficacy as a function of pulsed radiation parameters studied by spore film dosimetry.

    Science.gov (United States)

    Bauer, Stefan; Holtschmidt, Hans; Ott, Günter

    2018-01-01

    Disinfection by pulsed ultraviolet (UV) radiation is a commonly used method, e.g. in industry or medicine and can be carried out either with lasers or broadband UV radiation sources. Detrimental effects to biological materials depending on parameters such as pulse duration τ or pulse repetition frequency f p are well-understood for pulsed coherent UV radiation, however, relatively little is known for its incoherent variant. Therefore, within this work, it is the first time that disinfection rates of pulsed and continuous (cw) incoherent UV radiation studied by means of spore film dosimetry are presented, compared with each other, and in a second step further investigated regarding two pulse parameters. After analyzing the dynamic range of the Bacillus subtilis spore films with variable cw radiant exposures H=5-100Jm -2 a validation of the Bunsen-Roscoe law revealed its restricted applicability and a 28% enhanced detrimental effect of pulsed compared to cw incoherent UV radiation. A radiant exposure H=50Jm -2 and an irradiance E=0.5Wm -2 were found to be suitable parameters for an analysis of the disinfection rate as a function of τ=0.5-10ms and f p =25-500Hz unveiling that shorter pulses and lower frequencies inactivate more spores. Finally, the number of applied pulses as well as the experiment time were considered with regard to spore film disinfection. Copyright © 2017 Elsevier B.V. All rights reserved.

  6. Radiation exposure and dosimetry in transplant patients due to Nuclear Medicine studies

    International Nuclear Information System (INIS)

    El-Maghraby, T. A. F.; Cairo Univ., Cairo; Camps, J. A. J.; Geleyns, J.; Pauwels, E. K. J.

    2000-01-01

    Organ transplantation is now an accepted method of therapy for treating patients with end stage failure of kidneys, liver, heart or lung. Nuclear Medicine may provide functional data and semi-quantitative parameters. However, one serious factor that hampers the use of nuclear medicine procedures in transplant patients is the general clinical concern about radiation exposure to the patient. This lead the researcher to discuss the effective doses and radiation dosimetry associated with radionuclide procedures used in the management and follow-up of transplant patients. A simple way to place the risk associated with Nuclear Medicine studies in an appropriate context is to compare the dose with that received from more familiar source of exposure such as from a diagnostic X-ray procedure. The radiation dose for the different radiopharmaceuticals used to study transplant organ function ranges between 0.1 and 5.3 mSv which is comparable to X-ray procedures with the exception of 201 Tl and 111 In-antimyosin. Thus Nuclear Medicine studies do not bear a higher radiation risk than the often used X-ray studies in transplant patients

  7. Ionizing radiations, detection, dosimetry, spectrometry

    International Nuclear Information System (INIS)

    Blanc, D.

    1997-10-01

    A few works in French language are devoted to the detection of radiations. The purpose of this book is to fill a gap.The five first chapters are devoted to the properties of ionizing radiations (x rays, gamma rays, leptons, hadrons, nuclei) and to their interactions with matter. The way of classification of detectors is delicate and is studied in the chapter six. In the chapter seven are studied the statistics laws for counting and the spectrometry of particles is treated. The chapters eight to thirteen study the problems of ionization: charges transport in a gas, ionization chambers (theory of Boag), counters and proportional chambers, counters with 'streamers', chambers with derive, spark detectors, ionization chambers in liquid medium, Geiger-Mueller counters. The use of a luminous signal is the object of the chapters 14 to 16: conversion of a luminous signal in an electric signal, scintillators, use of the Cerenkov radiation. Then, we find the neutron detection with the chapter seventeen and the dosimetry of particles in the chapter eighteen. This book does not pretend to answer to specialists questions but can be useful to physicians, engineers or physics teachers. (N.C.)

  8. External dosimetry - Applications to radiation protection

    International Nuclear Information System (INIS)

    Faussot, Alain

    2011-01-01

    Dosimetry is the essential component of radiation protection. It allows to determine by calculation and measurement the absorbed dose value, i.e. the energy amounts deposited in matter by ionizing radiations. It deals also with the irradiation effects on living organisms and with their biological consequences. This reference book gathers all the necessary information to understand and master the external dosimetry and the metrology of ionizing radiations, from the effects of radiations to the calibration of radiation protection devices. The first part is devoted to physical dosimetry and allows to obtain in a rigorous manner the mathematical formalisms leading to the absorbed dose for different ionizing radiation fields. The second part presents the biological effects of ionizing radiations on living matter and the determination of a set of specific radiation protection concepts and data to express the 'risk' to develop a radio-induced cancer. The third part deals with the metrology of ionizing radiations through the standardized study of the methods used for the calibration of radiation protection equipments. Some practical exercises with their corrections are proposed at the end of each chapter

  9. 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

  10. High-accuracy dosimetry study for intensity-modulated radiation therapy(IMRT) commissioning

    International Nuclear Information System (INIS)

    Jeong, Hae Sun

    2010-02-01

    Intensity-modulated radiation therapy (IMRT), an advanced modality of high-precision radiotherapy, allows for an increase in dose to the tumor volume without increasing the dose to nearby critical organs. In order to successfully achieve the treatment, intensive dosimetry with accurate dose verification is necessary. A dosimetry for IMRT, however, is a challenging task due to dosimetric ally unfavorable phenomena such as dramatic changes of the dose at the field boundaries, dis-equilibrium of the electrons, non-uniformity between the detector and the phantom materials, and distortion of scanner-read doses. In the present study, therefore, the LEGO-type multi-purpose dosimetry phantom was developed and used for the studies on dose measurements and correction. Phantom materials for muscle, fat, bone, and lung tissue were selected after considering mass density, atomic composition, effective atomic number, and photon interaction coefficients. The phantom also includes dosimeter holders for several different types of detectors including films, which accommodates a construction of different designs of phantoms as necessary. In order to evaluate its performance, the developed phantom was tested by measuring the point dose and the percent depth dose (PDD) for small size fields under several heterogeneous conditions. However, the measurements with the two types of dosimeter did not agree well for the field sizes less than 1 x 1 cm 2 in muscle and bone, and less than 3 x 3 cm 2 in air cavity. Thus, it was recognized that several studies on small fields dosimetry and correction methods for the calculation with a PMCEPT code are needed. The under-estimated values from the ion chamber were corrected with a convolution method employed to eliminate the volume effect of the chamber. As a result, the discrepancies between the EBT film and the ion chamber measurements were significantly decreased, from 14% to 1% (1 x 1 cm 2 ), 10% to 1% (0.7 x 0.7 cm 2 ), and 42% to 7% (0.5 x 0

  11. High-accuracy dosimetry study for intensity-modulated radiation therapy(IMRT) commissioning

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Hae Sun

    2010-02-15

    Intensity-modulated radiation therapy (IMRT), an advanced modality of high-precision radiotherapy, allows for an increase in dose to the tumor volume without increasing the dose to nearby critical organs. In order to successfully achieve the treatment, intensive dosimetry with accurate dose verification is necessary. A dosimetry for IMRT, however, is a challenging task due to dosimetric ally unfavorable phenomena such as dramatic changes of the dose at the field boundaries, dis-equilibrium of the electrons, non-uniformity between the detector and the phantom materials, and distortion of scanner-read doses. In the present study, therefore, the LEGO-type multi-purpose dosimetry phantom was developed and used for the studies on dose measurements and correction. Phantom materials for muscle, fat, bone, and lung tissue were selected after considering mass density, atomic composition, effective atomic number, and photon interaction coefficients. The phantom also includes dosimeter holders for several different types of detectors including films, which accommodates a construction of different designs of phantoms as necessary. In order to evaluate its performance, the developed phantom was tested by measuring the point dose and the percent depth dose (PDD) for small size fields under several heterogeneous conditions. However, the measurements with the two types of dosimeter did not agree well for the field sizes less than 1 x 1 cm{sup 2} in muscle and bone, and less than 3 x 3 cm{sup 2} in air cavity. Thus, it was recognized that several studies on small fields dosimetry and correction methods for the calculation with a PMCEPT code are needed. The under-estimated values from the ion chamber were corrected with a convolution method employed to eliminate the volume effect of the chamber. As a result, the discrepancies between the EBT film and the ion chamber measurements were significantly decreased, from 14% to 1% (1 x 1 cm{sup 2}), 10% to 1% (0.7 x 0.7 cm{sup 2}), and 42

  12. Study of some thermoluminescent phosphors for the dosimetry of ionizing radiations

    International Nuclear Information System (INIS)

    Jaafari, M.

    1983-01-01

    Thermoluminescence dosimetry techniques are reviewed and interactions radiation matter are recalled. The need for new phosphors is evidenced. Numerous phosphors are examined and calcium, strontium and barium sulfides are synthetized and deposited on glass supports. The thermoluminescence of the dosimeters obtained with these materials is analyzed [fr

  13. Study of runaway electrons using dosimetry of hard x-ray radiations in Damavand tokamak

    Energy Technology Data Exchange (ETDEWEB)

    Rasouli, C.; Pourshahab, B.; Rasouli, H. [Plasma Physics and Nuclear Fusion Research School, Nuclear Science and Technology Research Institute, AEOI, PO Box 14155-1339, Tehran (Iran, Islamic Republic of); Hosseini Pooya, S. M.; Orouji, T. [Radiation Application Research School, Nuclear Science and Technology Research Institute, AEOI, PO Box 14155-1339, Tehran (Iran, Islamic Republic of)

    2014-05-15

    In this work several studies have been conducted on hard x-ray emissions of Damavand tokamak based on radiation dosimetry using the Thermoluminescence method. The goal was to understand interactions of runaway electrons with plasma particles, vessel wall, and plasma facing components. Total of 354 GR-200 (LiF:Mg,Cu,P) thermoluminescence dosimeter (TLD) crystals have been placed on 118 points – three TLDs per point – to map hard x-ray radiation doses on the exterior of the vacuum vessel. Results show two distinctive levels of x-ray radiations doses on the exterior of the vessel. The low-dose area on which measured dose is about 0.5 mSv/shot. In the low-dose area there is no particular component inside the vessel. On the contrary, on high-dose area of the vessel, x-ray radiations dose exceeds 30 mSv/shot. The high-dose area coincides with the position of limiters, magnetic probe ducts, and vacuum vessel intersections. Among the high-dose areas, the highest level of dose is measured in the position of the limiter, which could be due to its direct contact with the plasma column and with runaway electrons. Direct collisions of runaway electrons with the vessel wall and plasma facing components make a major contribution for production of hard x-ray photons in Damavand tokamak.

  14. Comparison of two methods of quantitation in human studies of biodistribution and radiation dosimetry

    International Nuclear Information System (INIS)

    Smith, T.

    1992-01-01

    A simple method of quantitating organ radioactivity content for dosimetry purposes based on relationships between organ count rate and the initial whole body count rate, has been compared with a more rigorous method of absolute quantitation using a transmission scanning technique. Comparisons were on the basis of organ uptake (% administered activity) and resultant organ radiation doses (mGy MBq -1 ) in 6 normal male volunteers given a 99 Tc m -labelled myocardial perfusion imaging agent intravenously at rest and following exercise. In these studies, estimates of individual organ uptakes by the simple method were in error by between +24 and -16% compared with the more accurate method. However, errors on organ dose values were somewhat less and the effective dose was correct to within 3%. (Author)

  15. Dosimetry studies with TLDs for stereotactic radiation techniques for intraocular tumours

    International Nuclear Information System (INIS)

    Ertl, A.; Schoeggl, A.; Zehetmayer, M.; Kindl, P.; Hartl, R.

    1997-01-01

    Between March 1993 and January 1997, stereotactic radiation techniques were used to irradiate 66 intraocular tumour patients with the Gamma Knife (Leksell Gamma Knife, model B unit) at the University of Vienna, Austria. This study investigates the dosimetry for stereotactic irradiation of ocular structures. For the dosimetry program KULA 4.4, Gamma Knife stereotactic irradiation of the eye represents an extreme frontal skull position. In addition, irradiation of the eye may be performed in the usual supine position in exceptional cases only. With the patient in the prone position, the dose planning program has to calculate with a significantly large number of single-beam extrapolations. In our first experiment we measured the isocentre dose for eight different γ-angle positions, both in prone and supine positions, using TLD measurements in an Alderson head phantom. We found a maximum deviation of ±1.6% using these individually calibrated TLDs. In the second experiment we examined the dose cross profiles for the two most frequently used treatment positions (supine position, γ = 65 deg., and prone position, γ = 140 deg.). For this purpose we implanted a specially designed TLD array into the orbit of a human cadaver head. We found excellent agreement of the dose values measured for the isocentre as well as the posterior part of the eye with orbit with deviations of less than -2.7%. However, for the anterior part of the eye, deviations between computer-generated calculations and the TLD measurements were found to range up to -30%. These differences were noticed both for supine and prone positions. For the Gamma Knife stereotactic irradiation of ocular tumours or pathologies, precautions should be taken to avoid significant underdosage in the anterior part of the radiation field. (author)

  16. Development of technology for biological dosimetry -A study on the radiation and environmental safety-

    International Nuclear Information System (INIS)

    Lee, Kang Suk; Cheon, Ki Jeong; Kim, Kook Chan; Kim, Jin Kyu; Kim, Sang Bok; Kim, In Kyu; Park, Hyo Kook

    1994-07-01

    α-amylase showed a significant increase in its activity when exposed to radiation of 0.1 Gy. However it had no relationship with radiation dose. Enzyme activities in liver tissue showed similar changes to those in serum. Among others, changes in acid phosphatase activity were highly related to radiation dose. Of acute phase proteins in serum, CRP, ceruloplasmin and haptoglobin positively responded to radiation while albumin did negatively. ELISA proved to be an efficient method to detect changes in serum protein level. Finally the measurements of changes in APRs using ELISA could provide an useful tools for biological dosimetry. (Author)

  17. Radiation protection dosimetry and calibrations

    International Nuclear Information System (INIS)

    Verhavere, Ph.

    2007-01-01

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

  18. Radiation dosimetry in radiotherapy with internal emitters

    International Nuclear Information System (INIS)

    Stabin, Michael G.

    1997-01-01

    Full text. Radiation dosimetry radionuclides are currently being labeled to various biological agents used in internal emitter radiotherapy. This talk will review the various technologies and types of radiolabel in current use, with focus on the characterization of the radiation dose to the various important tissues of the body. Methods for obtaining data, developing kinetic models, and calculating radiation doses will be reviewed. Monoclonal antibodies are currently being labeled with both alpha and beta emitting radionuclides in attempts to find effective agents against cancer. Several radionuclides are also being used as bone pain palliation agents. These agents must be studied in clinical trials to determine the biokinetics and radiation dosimetry prior to approval for general use. In such studies, it is important to ensure the collection of the appropriate kinds of data and to collect the data at appropriate time intervals. The uptake and retention of activity in all significant source organs and in excreta be measured periodically (with at least 2 data points phase of uptake or clearance). Then, correct dosimetry methods must be applied - the best available methods for characterizing the radionuclide kinetic and for estimating the dosimetry in the various organs of the body especially the marrow, should be used. Attempts are also under way to develop methods for estimating true patient-specific dosimetry. Cellular and animal studies are also. Valuable in evaluating the efficacy of the agents in shrinking or eliminating tumors; some results from such studies will also be discussed. The estimation of radiation doses to patients in therapy with internal emitters involves several complex phases of analysis. Careful attention to detail and the use of the best available methods are essential to the protection of the patient and a successful outcome

  19. Bayesian Methods for Radiation Detection and Dosimetry

    International Nuclear Information System (INIS)

    Peter G. Groer

    2002-01-01

    We performed work in three areas: radiation detection, external and internal radiation dosimetry. In radiation detection we developed Bayesian techniques to estimate the net activity of high and low activity radioactive samples. These techniques have the advantage that the remaining uncertainty about the net activity is described by probability densities. Graphs of the densities show the uncertainty in pictorial form. Figure 1 below demonstrates this point. We applied stochastic processes for a method to obtain Bayesian estimates of 222Rn-daughter products from observed counting rates. In external radiation dosimetry we studied and developed Bayesian methods to estimate radiation doses to an individual with radiation induced chromosome aberrations. We analyzed chromosome aberrations after exposure to gammas and neutrons and developed a method for dose-estimation after criticality accidents. The research in internal radiation dosimetry focused on parameter estimation for compartmental models from observed compartmental activities. From the estimated probability densities of the model parameters we were able to derive the densities for compartmental activities for a two compartment catenary model at different times. We also calculated the average activities and their standard deviation for a simple two compartment model

  20. Radiation Protection Dosimetry

    International Nuclear Information System (INIS)

    Kramer, H.M.; Schnuer, K.

    1992-01-01

    The contributions presented during the seminar provided clear evidence that radiation protection of the patient plays an increasingly important role for manufacturers of radiological equipment and for regulatory bodies, as well as for radiologists, doctors and assistants. The proceedings of this seminar reflect the activities and work in the field of radiation protection of the patient and initiate further action in order to harmonize dosimetric measurements and calculations, to ameliorate education and training, to improve the technical standards of the equipment and to give a push to a more effective use of ionising radiation in the medical sector

  1. Workshop Report on Atomic Bomb Dosimetry--Residual Radiation Exposure: Recent Research and Suggestions for Future Studies

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-06-06

    There is a need for accurate dosimetry for studies of health effects in the Japanese atomic bomb survivors because of the important role that these studies play in worldwide radiation protection standards. International experts have developed dosimetry systems, such as the Dosimetry System 2002 (DS02), which assess the initial radiation exposure to gamma rays and neutrons but only briefly consider the possibility of some minimal contribution to the total body dose by residual radiation exposure. In recognition of the need for an up-to-date review of the topic of residual radiation exposure in Hiroshima and Nagasaki, recently reported studies were reviewed at a technical session at the 57th Annual Meeting of the Health Physics Society in Sacramento, California, 22-26 July 2012. A one-day workshop was also held to provide time for detailed discussion of these newer studies and to evaluate their potential use in clarifying the residual radiation exposures to the atomic-bomb survivors at Hiroshima and Nagasaki. Suggestions for possible future studies are also included in this workshop report.

  2. Techniques of radiation dosimetry

    International Nuclear Information System (INIS)

    Mahesk, K.

    1985-01-01

    A text and reference with an interdisciplinary approach to physics, atomic energy, radiochemistry, and radiobiology. Chapters examine basic principles, experimental techniques, the methodology of dose experiments, and applications. Treats 14 different dosimetric techniques, including ionization chamber, thermoluminescence, and lyoluminescence. Considers the conceptual aspects and characteristic features of radiation

  3. A preliminary clinic dosimetry study for synchrotron radiation therapy at SSRF

    International Nuclear Information System (INIS)

    Li Zhaobin; Shi Zeliang; Zhang Qing; Wang Yong; Fu Shen

    2013-01-01

    Synchrotron radiation (SR) represents a unique and innovative anti-cancer treatment due to its unique physical features, including high flux density, and tunable and collimated radiation generation. The aim of this work is to assess the dosimetric properties of SR in Shanghai Synchrotron Radiation Facility (SSRF) for potential applications to clinical radiation oncology. The experiments were performed with 34 and 50 keV X-rays on the BL13W biomedical beamline of SSRF and the 6 MV X-rays from ARTISTE linac for the dosimetry study. The percentage depth dose (PDD) and the surface dose of the SR X-rays and the 6 MV photon beams were performed in solid water phantom with Gafchromic EBT3 films. All curves are normalized to the maximum calculated dose, The depth of full dose buildup is about 10 μm deeper for the monoenergetic X-ray beams of 34 and 50 keV. The beam transmits through the phantom, with a linear attenuation coefficient. The profile in the horizontal plane shows that the dose distribution is uniform within the facula, while the vertical profile shows a Gaussian distribution of the dose. The penumbra is less than 0.2 mm in the horizontal profile. Gafchromic EBT film may be a useful and convenient tool for dose measurement and quality control for the high space and density resolution. It is therefore important to gain a thorough understanding about the physical features of SR before this novel technology can be applied to clinical practice. (authors)

  4. Radiation accidents and dosimetry

    International Nuclear Information System (INIS)

    Sagstuen, E.; Theisen, H.; Henriksten, T.

    1982-12-01

    On September 2nd 1982 one of the employees of the gamma-irradiation facility at Institute for Energy Technology, Kjeller, Norway entered the irradiation cell with a 65.7 kCi *sp60*Co- source in unshielded position. The victim received an unknown radiation dose and died after 13 days. Using electron spin resonance spectroscopy, the radiation dose in this accident was subsequently determined based on the production of longlived free radicals in nitroglycerol tablets borne by the operator during the accident. He used nitroglycerol for heart problems and free radical are easily formed and trapped in sugar which is the main component of the tablets. Calibration experiments were carried out and the dose given to the tablets during the accident was determined to 37.2 +- 0.5 Gy. The general use of free radicals for dose determinations is discussed. (Auth.)

  5. Space Radiation Dosimetry

    International Nuclear Information System (INIS)

    Deme, S.

    2003-01-01

    Although partly protected from galactic and solar cosmic radiation by the Earth's magnetosphere in Low Earth Orbit (LEO) astronauts exposure levels during long-term missions (90 days to 180 days) by far exceed with exposures of up to more than 100 mSv the annual exposure limits set for workers in the nuclear industry, but are still below the yearly exposure limits of 500 mSv for NASA astronauts. During solar particle events the short-term limits (300 mSv) may be approached or even exceeded. In the interplanetary space, outside the Earth's magnetic field even relatively benign Solar Particle Events (SPEs) can produce 1 Sv skin-absorbed doses. Although new rocket technologies could reduce astronauts' total exposure to space radiation during a human Mars mission, the time required for the mission, which is now in the order of years. Therefore mission planners will need to consider a variety of countermeasures for the crew members including physical protection (e.g. shelters), active protection (e.g. magnetic protection), pharmacological protection, local protection (extra protection for critical areas of the body) etc. With full knowledge of these facts, accurate personal dose measurement will become increasingly important during human missions to Mars. The new dose limits for radiation workers correspond to excess lifetime risk of 3% (NCRP) and 4% (ICRP). While astronauts accept the whole variety of flight risks they are taking in mission, there is concern about risks that may occur later in life. A risk no greater than the risk of radiation workers would be acceptable. (author)

  6. A comparative study of some aspects of radiation protection and dosimetry procedures. Pt. 1 and 2

    International Nuclear Information System (INIS)

    Drexler, G.; Goeksu, H.Y.; Johns, T.F.

    1987-10-01

    A study has been made of the procedures used in the Member States of the European Communities for dealing with certain practical and administrative aspects of radiation protection of occupationally exposed persons, and especially of the methods and procedures used in personnel dosimetry. It was found that the different states have adopted quite different methods for dealing with some of these problems, the method chosen seeming to depend on the size of the country and the extent and timing of its involvement with nuclear power developments; but although the different countries have adopted different methods of control, as far as we can judge they have all been reasonably effective in achieving adequate control of occupational exposures. Nevertheless, there are still issues that each country could probably learn and perhaps improve its own procedure by making a more careful study of the way in which other countries deal with these problems. Therefore the study was extended to cover the USA and Japan in order to facilitate such comparisons and improvements. (orig.)

  7. Detectors for radiation dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Perez-Mendez, V.

    1979-09-01

    For our purposes in this review, we note the following points: (1) for charged particle detection, these counters can be filled with any noble gas-quenching gas mixture that produces satisfactory electrical signals; (2) neutron counters, in which the neutrons are detected by their interaction with the specific filling of the chamber to yield an ionizing particle, require special gas mixtures containing /sup 3/He or BF/sub 3/, an alternative approach is to coat the inner surface of the cathode with a boron or lithium compound; (3) proportional counters are used if there is any need to discriminate between different types of radiation incident on the chamber by the magnitude of the ionizing energy retained within the sensitive volume of the counter; (4) proportional counters can operate at higher speeds than Geiger counters, typically up to 10/sup 7/ cts/sec versus less than 10/sup 5//sec for the Geiger counters; and (5) Geiger counters produce very large uniform pulses which can be scaled by very simple electronics, hence, they are often used in survey meters and other portable monitoring instruments.

  8. Radiation-damage studies, irradiations and high-dose dosimetry for LHC detectors

    CERN Document Server

    Coninckx, F; León-Florián, E; Leutz, H; Schönbacher, Helmut; Sonderegger, P; Tavlet, Marc; Sopko, B; Henschel, H; Schmidt, H U; Boden, A; Bräunig, D; Wulf, F; Cramariuc, R; Ilie, D; Fattibene, P; Onori, S; Miljanic, S; Paic, G; Razen, B; Razem, D; Rendic, D; CERN. Geneva. Detector Research and Development Committee

    1991-01-01

    The proposal is divided into a main project and special projects. The main project consists of a service similar to the one given in the past to accelerator construction projects at CERN (ISR,SPS,LEP) on high-dose dosimetry, material irradiations, irradiations tests, standardization of test procedures and data compilations. Large experience in this field and numerous radiation damage test data of insulating and structural materials are available. The special projects cover three topics which are of specific interest for LHC detector physicists and engineers at CERN and in other high energy physics institutes, namely: Radiation effects in scintillators; Selection of radiation hard optical fibres for data transmission; and Selection and testing of radiation hard electronic components.

  9. Development of radiation biological dosimetry

    International Nuclear Information System (INIS)

    Cho, Chul Koo; Kim, Tae Hwan; Lee, Yun Sil; Son, Young Sook; Kim, Soo Kwan; Jang, Won Suk; Le, Sun Joo; Jee, Young Heun; Jung, Woo Jung

    1999-04-01

    Up until now, only a few methods have been developed for radiation biological dosimetry such as conventional chromosome aberration and micronucleus in peripheral blood cell. However, because these methods not only can be estimated by the expert, but also have a little limitation due to need high technique and many times in the case of radiation accident, it is very difficult to evaluate the absorbed dose of victims. Therefore, we should develop effective, easy, simple and rapid biodosimetry and its guideline (triage) to be able to be treated the victims as fast as possible. We established the premature chromosome condensation assay and apoptotic fragment assay which was the significant relationship between dose and cell damages to evaluate the irradiation dose as correct and rapid as possible using lymphocytes and crypt cells, and compared with conventional chromosome aberration assay and micronuclei assay

  10. Radiation Litigation and Internal Dosimetry

    International Nuclear Information System (INIS)

    Jose, D.E.

    1987-01-01

    Radiation Litigation refers to those lawsuits filed by individuals who claim to have been injured by some past exposure to ionizing radiation. Law classifies these cases as personal injury or tort cases. However, they are a new breed of such cases and the law is presently struggling with whether these cases can be resolved using the traditional methods of legal analysis or whether new forms of analysis, such as probability of causation, need to be applied. There are no absolutely certain rules concerning how these particular lawsuits will be tried and analyzed. The United States presently is defending cases filed by approximately 7000 plaintiffs. The private nuclear industry is defending cases filed by over 2000 plaintiffs. While not all of these cases will actually be tried on their merits, at least some will and internal dosimetry will play a very important part in many of these trials

  11. Development of radiation biological dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Chul Koo; Kim, Tae Hwan; Lee, Yun Sil; Son, Young Sook; Kim, Soo Kwan; Jang, Won Suk; Le, Sun Joo; Jee, Young Heun; Jung, Woo Jung

    1999-04-01

    Up until now, only a few methods have been developed for radiation biological dosimetry such as conventional chromosome aberration and micronucleus in peripheral blood cell. However, because these methods not only can be estimated by the expert, but also have a little limitation due to need high technique and many times in the case of radiation accident, it is very difficult to evaluate the absorbed dose of victims. Therefore, we should develop effective, easy, simple and rapid biodosimetry and its guideline (triage) to be able to be treated the victims as fast as possible. We established the premature chromosome condensation assay and apoptotic fragment assay which was the significant relationship between dose and cell damages to evaluate the irradiation dose as correct and rapid as possible using lymphocytes and crypt cells, and compared with conventional chromosome aberration assay and micronuclei assay.

  12. Bio-dosimetry of ionizing radiation

    International Nuclear Information System (INIS)

    Hadjidekova, V.; Kristova, R.; Stainova, A.; Deleva, S.; Popova, L.; Georgieva, D.

    2013-01-01

    Full text: Introduction: The impact of ionizing radiation in medical, occupational and accidental human exposure leads to adverse side effects such as increased mortality and carcinogenesis. Information about the level of absorbed dose is important for risk assessment and for implementation of appropriate therapy. In most cases of actual or suspected exposure to ionizing radiation biological dosimetry is the only way to assess the absorbed dose. What you will learn: In this work we discuss the methods for biodosimetry and technological developments in their application in various emergency situations. The application of biological dosimetry and assessment of the influence of external factors in the conduct of epidemiological studies of radiation effects in protracted low-dose ionizing radiation on humans is presented. Discussion: The results of cytogenetic analysis and biological evaluation of absorbed dose based on the analysis of dicentrics in peripheral blood lymphocytes of five people injured in a severe radiation accident in Bulgaria in 2011 are presented. The assessed individual doses of the injured persons are in the range of 1.2 to 5,2 Gy acute homogeneous irradiation and are in line with the estimates of international experts. Conclusion: An algorithm to conduct a biological assessment of the dose in limited radiation accidents and in large scale radiation accidents with large number irradiated or suspected for exposure persons is proposed

  13. Rational system of radiation dosimetry

    International Nuclear Information System (INIS)

    Katoh, K.; Tada, J.

    1996-01-01

    Radiation doses are the most important subject to the sciences relating to the effects of ionizing radiation on matter. Since any science at all must stand on the quantitative description of causality, uses of physical quantities as the measures are indispensable. The current system of radiation dosimetry is built on the fundamental dose of the absorbed dose, which is defined as the 'energy imparted' density, and for practical convenience various weighted absorbed doses are introduced as subsidiary. However, it has been pointed out that these quantities lack adequacy inherently as a measure of causes, in addition to the insufficiency of the specification of the concept. Firstly, separation of the quantities of radiation field and of the dose is not possible, since both quantities are deeply related to the same microscopic constituents, i.e., electrons. Secondly, the value of the absorbed dose cannot be fixed at the moment of irradiation. Since the absorbed dose is a quantity of interaction product of radiation and matter, the values of the dose cannot be fixed instantaneously. Thirdly, it is not easy to envision the physical entity of the quantity from the definition. The form of existence of the 'imparted' energy is not clear in the current definition. These defects can not be removed as long as an interaction product is adopted as the dose quantity. In this paper, the authors present a prescription to solve these problems. (author)

  14. Potential of Hybrid Computational Phantoms for Retrospective Heart Dosimetry After Breast Radiation Therapy: A Feasibility Study

    Energy Technology Data Exchange (ETDEWEB)

    Moignier, Alexandra, E-mail: alexandra.moignier@irsn.fr [Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); Derreumaux, Sylvie; Broggio, David; Beurrier, Julien [Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); Chea, Michel; Boisserie, Gilbert [Groupe Hospitalier Pitie Salpetriere, Service de Radiotherapie, Paris (France); Franck, Didier; Aubert, Bernard [Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); Mazeron, Jean-Jacques [Groupe Hospitalier Pitie Salpetriere, Service de Radiotherapie, Paris (France)

    2013-02-01

    Purpose: Current retrospective cardiovascular dosimetry studies are based on a representative patient or simple mathematic phantoms. Here, a process of patient modeling was developed to personalize the anatomy of the thorax and to include a heart model with coronary arteries. Methods and Materials: The patient models were hybrid computational phantoms (HCPs) with an inserted detailed heart model. A computed tomography (CT) acquisition (pseudo-CT) was derived from HCP and imported into a treatment planning system where treatment conditions were reproduced. Six current patients were selected: 3 were modeled from their CT images (A patients) and the others were modelled from 2 orthogonal radiographs (B patients). The method performance and limitation were investigated by quantitative comparison between the initial CT and the pseudo-CT, namely, the morphology and the dose calculation were compared. For the B patients, a comparison with 2 kinds of representative patients was also conducted. Finally, dose assessment was focused on the whole coronary artery tree and the left anterior descending coronary. Results: When 3-dimensional anatomic information was available, the dose calculations performed on the initial CT and the pseudo-CT were in good agreement. For the B patients, comparison of doses derived from HCP and representative patients showed that the HCP doses were either better or equivalent. In the left breast radiation therapy context and for the studied cases, coronary mean doses were at least 5-fold higher than heart mean doses. Conclusions: For retrospective dose studies, it is suggested that HCP offers a better surrogate, in terms of dose accuracy, than representative patients. The use of a detailed heart model eliminates the problem of identifying the coronaries on the patient's CT.

  15. Dosimetry for occupational exposure to cosmic radiation

    International Nuclear Information System (INIS)

    Bartlett, D.T.; McAulay, I.R.; Schrewe, U.J.

    1997-01-01

    Aircraft crew and frequent flyers are exposed to elevated levels of cosmic radiation of galactic and solar origin and secondary radiation produced in the atmosphere, aircraft structure, etc. This has been recognised for some time and estimates of the exposure of aircraft crew have been made previously and included in, for example, UNSCEAR (United Nations Scientific Committee on the Effects of Atomic Radiation) publications. The recent increased interest has been brought about by several factors - the consideration that the relative biological effectiveness of the neutron component was being underestimated; the trend towards higher cruising altitudes for subsonic commercial aircraft and business jet aircraft; and most importantly, the recommendations of the International Commission on Radiological Protection (ICRP) in Publication 60, and the revision of the Euratom Basic Safety Standards Directive (BSS). In 1992, the European Dosimetry Group (EURADOS) established a Working Group to consider the exposure to cosmic radiation of aircraft crew, and the scientific and technical problems associated with radiation protection dosimetry for this occupational group. The Working Group was composed of fifteen scientists (plus a corresponding member) involved in this field of study and with knowledge of radiation measurement at aviation altitudes. This paper is based on the findings of this Working Group. (author)

  16. Quality assurance study for dosimetry of Radiation Therapy equipment in Saudi Arabia

    International Nuclear Information System (INIS)

    Al-Mokhlef, Jazi M.; Nabaz, Noori

    2003-01-01

    International standards address the accuracy of dose delivery for radiation therapy machines as well as quality assurance and staffing levels for radiation therapy centers. We performed absolute calibrations of gamma ,X-ray and electron radiotherapy beams in all radiation therapy centers in Saudi Arabia. We also assessed quality assurance and staffing levels Dosimetric measurements were made with a portable dosimetry system, which consisted of a calibrated Farmer ionization chamber and an electrometer, small water phantom, barometer and thermometer. Differences between the measured and the expected output (c Gy/MU or c Gy/min) were found to be in the range of -11%+5%. About 17% of radiotherapy beams were not within the acceptable tolerance level (+/-3%). Quality assurance in some radiation centers was poor and staffing levels were inadequate. We found poor compliance with internationally accepted tolerance levels for dose calibration of radiotherapy beams at radiation therapy centers in Saudi Arabia. Analysis of medical physics staffing revealed severe discrepancies from those recommended by international guidelines .We recommend that radiation therapy centers be adequately staffed with qualified medical physics personnel and that periodic audit programs be required a governmental body. (author)

  17. A series of Chinese mathematic phantom and study of its external radiation dosimetry character

    International Nuclear Information System (INIS)

    Geng Changran; Tang Xiaobin; Chen Da; Xie Qin

    2012-01-01

    On the discussion of effect on dosimetry by different races, different postures, and different weighting factors, a series of Chinese reference human including two genders and three postures were constructed in according with GBZ/T 200. With Monte-Carlo method, absorbed dose of each organ and effective dose of several energy and geometries were calculated. With different tissue weighting factors, difference can be found in lower energies with all geometries. Also different races and different postures can bring about the different doses with the shielding of human organs, especially for the lower energy. As a conclusion, corresponding situation should be considered in radiation protection, especially in radiology and complexity radiation field. (authors)

  18. Advanced materials in radiation dosimetry

    CERN Document Server

    Bruzzi, M; Nava, F; Pini, S; Russo, S

    2002-01-01

    High band-gap semiconductor materials can represent good alternatives to silicon in relative dosimetry. Schottky diodes made with epitaxial n-type 4 H SiC and Chemical Vapor Deposited diamond films with ohmic contacts have been exposed to a sup 6 sup 0 Co gamma-source, 20 MeV electrons and 6 MV X photons from a linear accelerator to test the current response in on-line configuration in the dose range 0.1-10 Gy. The released charge as a function of the dose and the radiation-induced current as a function of the dose-rate are found to be linear. No priming effects have been observed using epitaxial SiC, due to the low density of lattice defects present in this material.

  19. Whole-body radiation dosimetry of 2-[18F]Fluoro-A-85380 in human PET imaging studies

    International Nuclear Information System (INIS)

    Obrzut, Sebastian L.; Koren, Andrei O.; Mandelkern, Mark A.; Brody, Arthur L.; Hoh, Carl K.; London, Edythe D.

    2005-01-01

    2-[ 18 F]Fluoro-A-85380 (2-[ 18 F]fluoro-3-(2(S)-azetidinylmethoxy)pyridine, 2-[ 18 F]FA) is a recently developed PET radioligand for noninvasive imaging of nicotinic acetylcholine receptors. Previous radiation absorbed dose estimates for 2-[ 18 F]FA were limited to evaluation of activity in only several critical organs. Here, we performed 2-[ 18 F]FA radiation dosimetry studies on two healthy human volunteers to obtain data for all important body organs. Intravenous injection of 2.9 MBq/kg of 2-[ 18 F]FA was followed by dynamic PET imaging. Regions of interest were placed over images of each organ to generate time-activity curves, from which we computed residence times. Radiation absorbed doses were calculated from the residence times using the MIRDOSE 3.0 program (version 3.0, ORISE, Oak Ridge, TN). The urinary bladder wall receives the highest radiation absorbed dose (0.153 mGy/MBq, 0.566 rad/mCi, for a 2.4-h voiding interval), followed by the liver (0.0496 mGy/MBq, 0.184 rad/mCi) and the kidneys (0.0470 mGy/MBq, 0.174 rad/mCi). The mean effective dose equivalent is estimated to be 0.0278 mSv/MBq (0.103 rem/mCi), indicating that radiation dosimetry associated with 2-[ 18 F]FA is within acceptable limits

  20. Pharmacokinetics and radiation dosimetry of 99mTc-3PRGD2 in healthy individuals: A pilot study

    International Nuclear Information System (INIS)

    Cheng Guanghui; Gao Shi; JI Tiefeng; Ma Qingjie; Wang Qing; Jia Bing; Chen Zuowei

    2012-01-01

    99m Tc-3PRGD 2 is a new SPECT radiotracer for several tumor imaging with high uptake where integrin α v β 3 is highly expressed. This pilot study was to assess the safety, biodistribution and radiation dosimetry of 99m Tc-3PRGD 2 in healthy volunteers. The 10 healthy male volunteers were injected with 99m Tc-3PRGD 2 (786.7±55.8 MBq, 19.1-24.2 mCi). Baseline measurements of vital signs, laboratory safety tests and 12-lead electrocardiogram were recorded before and after injection. Blood and urine samples were collected and radiation counts were obtained at various time points. Whole-body scans and ROIs of identified organs were used for visual analysis and estimating the radiation dosimetry. No adverse reactions were found during the study. 99m Tc-3PRGD 2 exhibited a rapid clearance from the blood with less than 45% of the initial dosage at 10 min after injection and gradual increasing radioactivity in urine with (52.9±6)% of original dose at 1440 min. The whole-body imaging showed high radioactive accumulation in bladder. And the highest 99m Tc-3PRGD 2 uptake was found in the kidneys (3.50×10 -2 mSv/MBq). The 99m Tc-3PRGD 2 exhibited good pharmacokinetic properties and little radiation burden. This study showed that 99m Tc-3PRGD 2 would be a safe and attractive SPECT agent in clinic applications. (authors)

  1. Study of radiation effects on some glasses and their applications in radiation dosimetry

    International Nuclear Information System (INIS)

    Mohammad, A.El.

    2008-01-01

    This thesis comprises a study of the X-ray diffraction, thermal, electrical, ESR and optical properties of lead lithium tetra borate glass. The objective of this thesis is to prepare glass dosimeter and study the effect of several gamma-irradiation doses on Lead lithium tetra borate glasses doped with Cu O. The two glasses were prepared from chemical reagents; Li 2 B 4 O 7 from ready package, lead and copper oxide were added in fixed Proportions. The glass melting was made in porcelain crucibles, using electrically heated furnace at temperature of 1000 -1100 degree C. The melts rapidly quenched in air by pressing between two stainless-steel plates mould kept at room temperature. The resultant glasses were colorless for LPTB and transparent greenish sheet of LPTB Cu glass about 0.8 mm thick and where polished to meet the requirements for optical and electrical measurements. The obtained results can be summarized as follows:- Density It is observed that, for unirradiated samples, the addition of copper to LPTB leads to the increase of the number of ions in the sample which decreases the inter-ionic distance. As a result, the molar volume of LPTB Cu decreased and consequently its density increased in the range of 10 ± 1 %. Irradiation with gamma rays is assumed to create displacements, electronic defects and /or breaks in the network bonds. Irradiation can cause the compaction of B 2 O 3 by breaking of the bonds between trigonal elements, allowing the formation of different configuration. Irradiating the LPTB glass with growing gamma doses up to 25 kGy decreased its molar volume with in 4.07 % and consequently increased the density with the same percentage. For the glass LPTB Cu, the effect of gamma rays appeared as a decrease in the molar volume and increase in density with the same percentage (12.9%). The addition traces of copper (0.01 weight %) to LPTB enhanced the effect of gamma radiation on it. Crystallization Behavior: - X-ray diffraction The results show

  2. Direct comparison of radiation dosimetry of six PET tracers using human whole-body imaging and murine biodistribution studies

    International Nuclear Information System (INIS)

    Sakata, Muneyuki; Oda, Keiichi; Toyohara, Jun; Ishii, Kenji; Nariai, Tadashi; Ishiwata, Kiichi

    2013-01-01

    We investigated the whole-body biodistributions and radiation dosimetry of five 11 C-labeled and one 18 F-labeled radiotracers in human subjects, and compared the results to those obtained from murine biodistribution studies. The radiotracers investigated were 11 C-SA4503, 11 C-MPDX, 11 C-TMSX, 11 C-CHIBA-1001, 11 C-4DST, and 18 F-FBPA. Dynamic whole-body positron emission tomography (PET) was performed in three human subjects after a single bolus injection of each radiotracer. Emission scans were collected in two-dimensional mode in five bed positions. Regions of interest were placed over organs identified in reconstructed PET images. The OLINDA program was used to estimate radiation doses from the number of disintegrations of these source organs. These results were compared with the predicted human radiation doses on the basis of biodistribution data obtained from mice by dissection. The ratios of estimated effective doses from the human-derived data to those from the mouse-derived data ranged from 0.86 to 1.88. The critical organs that received the highest absorbed doses in the human- and mouse-derived studies differed for two of the six radiotracers. The differences between the human- and mouse-derived dosimetry involved not only the species differences, including faster systemic circulation of mice and differences in the metabolism, but also measurement methodologies. Although the mouse-derived effective doses were roughly comparable to the human-derived doses in most cases, considerable differences were found for critical organ dose estimates and pharmacokinetics in certain cases. Whole-body imaging for investigation of radiation dosimetry is desirable for the initial clinical evaluation of new PET probes prior to their application in subsequent clinical investigations. (author)

  3. VIII. national symposium on radiation dosimetry

    International Nuclear Information System (INIS)

    1990-07-01

    The publication contains abstracts of 107 contributions, dealing mainly with general problems of radiation dosimetry and with its practical applications, particularly in nuclear power industry and in medicine. (Z.M.)

  4. Introduction to radiological physics and radiation dosimetry

    CERN Document Server

    Attix, Frank Herbert

    2004-01-01

    A straightforward presentation of the broad concepts underlying radiological physics and radiation dosimetry for the graduate-level student. Covers photon and neutron attenuation, radiation and charged particle equilibrium, interactions of photons and charged particles with matter, radiotherapy dosimetry, as well as photographic, calorimetric, chemical, and thermoluminescence dosimetry. Includes many new derivations, such as Kramers X-ray spectrum, as well as topics that have not been thoroughly analyzed in other texts, such as broad-beam attenuation and geometrics, and the reciprocity theorem

  5. Monte Carlo design, dosimetry and radiation protection studies for a new mobile electron accelerator for intraoperative radiation therapy (IORT)

    International Nuclear Information System (INIS)

    Wysocka-Rabin, A.

    2013-01-01

    Intraoperative radiation therapy (IORT) delivers a large, single fraction dose of radiation to a surgically exposed tumor or tumor bed. This presentation reviews the design concept and dosimetry characteristics of an electron beam forming system for an IORT accelerator, with special emphasis on beam flatness, X-ray contamination and protecting personnel from dose delivered outside the treatment field. The Monte Carlo code, BEAMnrc/EGSnrc, was used to design, verify and optimize the electron beam forming system for two different docking methods with circular metallic applicators. Calculations of therapeutic beam characteristics were performed at the patient surface. Findings were obtained for initially mono-energetic electron beams with an energy range from 4 to 12 MeV, SSD equal to 60 cm, and circular applicators with diameters from 3 to 12 cm. The aim was to build an electron beam forming system (collimators, scattering-flattening foils, applicators) that is universal for all beam energy and field diameters described above

  6. Research and innovation in radiation dosimetry

    International Nuclear Information System (INIS)

    Delgado, A.

    1999-01-01

    In this article some relevant lines of research in radiation dosimetry are presented. In some of them innovative approaches have been recently proposed in recent years. In others innovation is still to come as it is necessary in view of the insufficiency of the actual methods and techniques. mention is made to Thermoluminescence Dosimetry an to the improvement produced by new computational methods for the analysis of the usually complex TL signals. A solid state dosimetric technique recently proposed, Optically Stimulated Luminescence, OSL, is briefly presented. This technique promises advantages over TLD for personal and environmental dosimetry. The necessity of improving the measurement characteristics of neutron personal dosemeters is commented, making reference to some very recent developments. The situation of the dosimetry in connection with radiobiology research is overviewed, commenting the controversy on the adequacy and utility of the quality absorbed dose for these activities. Finally the special problematic of internal dosimetry is discussed. (Author) 25 refs

  7. Implications of radiation risk for practical dosimetry

    International Nuclear Information System (INIS)

    Dennis, J.A.

    1984-01-01

    Radiobiological experiments with animals and cells have led to an expectation that the risks of cancer and hereditary effects are reduced at low doses and low dose rates of low LET radiation. Risk estimates derived from human exposures at high doses and dose rates usually contain an allowance for low dose effects in comparison with high dose effects, but no allowance may have been made for low dose rate effects. Although there are reasons for thinking that leukaemia risks may possibly have been underestimated, the total cancer risk assumed by ICRP for occupational exposures is reasonably realistic. For practical dosimetry the primary dose concepts and limits have to be translated into secondary quantities that are capable of practical realisation and measurement, and which will provide a stable and robust system of metrology. If the ICRP risk assumptions are approximately correct, it is extremely unlikely that epidemiological studies of occupational exposures will detect the influence of radiation. Elaboration of dosimetry and dose recording for epidemiological purposes is therefore unjustified except possibly in relation to differences between high and low LET radiations. (author)

  8. Accuracy Requirements in Medical Radiation Dosimetry

    International Nuclear Information System (INIS)

    Andreo, P.

    2011-01-01

    The need for adopting unambiguous terminology on 'accuracy in medical radiation dosimetry' which is consistent with international recommendations for metrology is emphasized. Uncertainties attainable, or the need for improving their estimates, are analysed for the fields of radiotherapy, diagnostic radiology and nuclear medicine dosimetry. This review centres on uncertainties related to the first step of the dosimetry chain in the three fields, which in all cases involves the use of a detector calibrated by a standards laboratory to determine absorbed dose, air kerma or activity under reference conditions in a clinical environment. (author)

  9. Dosimetry of low-energy beta radiation

    International Nuclear Information System (INIS)

    Borg, J.

    1996-08-01

    Useful techniques and procedures for determination of absorbed doses from exposure in a low-energy β radiation field were studied and evaluated in this project. The four different techniques included were β spectrometry, extrapolation chamber dosimetry, Monte Carlo (MC) calculations, and exoelectron dosimetry. As a typical low-energy β radiation field a moderated spectrum from a 14 C source (E β , max =156 keV) was chosen for the study. The measured response of a Si(Li) detector to photons (bremsstrahlung) showed fine agreement with the MC calculated photon response, whereas the difference between measured and MC calculated responses to electrons indicates an additional dead layer thickness of about 12 μm in the Si(Li) detector. The depth-dose profiles measured with extrapolation chambers at two laboratories agreed very well, and it was confirmed that the fitting procedure previously reported for 147 Pm depth-dose profiles is also suitable for β radiation from 14 C. An increasing difference between measured and MC calculated dose rates for increasing absorber thickness was found, which is explained by limitations of the EGS4 code for transport of very low-energy electrons (below 10-20 keV). Finally a study of the thermally stimulated exoelectron emission (TSEE) response of BeO thin film dosemeters to β radiation for radiation fields with maximum β energies ranging from 67 keV to 2.27 MeV is reported. For maximum β energies below approximately 500 keV, a decrease in the response amounting to about 20% was observed. It is thus concluded that a β dose higher than about 10 μGy can be measured with these dosemeters to within 0 to -20% independently of the βenergy for E β , max values down to 67 keV. (au) 12 tabs., 38 ills., 71 refs

  10. The status of the seventh report in the series Biological Effects of Ionizing Radiations and a revised dosimetry for the Radiation Effects Research Foundation's A-bomb studies

    International Nuclear Information System (INIS)

    Douple, Evan; Jostes, Rick

    2002-01-01

    Results of a National Academies workshop and feasibility study led US Governmental agencies to request the Board on Radiation Effects Research of the National Research Council to commence a risk assessment study in 1998 as the seventh report in the series Biological Effects of Ionizing Radiations (BEIR VII). Originally targeted for completion in the autumn of 2001, the study Potential Health Effects of Exposure to Low Dose, Low-LET Ionizing Radiation was extended until the autumn of 2003 at the request of the sponsors. Two factors contributing to this decision are discussed: a revised dosimetry to update DS86 for the Radiation Effects Research Foundation's A-bomb-survivor studies and the potential for new information to become available from low-dose studies that are under way. Epidemiological and biological data since BEIR V are being considered by a BEIR VII committee composed of 17 members. The committee's statement of task is reviewed along with the major recommendations of the recent National Research Council report on the status of DS86 - recommendations that are being implemented by US and Japan dosimetry working groups. (author)

  11. On the radiation dosimetry in space

    International Nuclear Information System (INIS)

    Doke, Tadayoshi

    2005-01-01

    The radiation dosimetry in space is considerably different from that on the earth surface, because, on the earth surface, the quality factor for radiation is roughly given for its energy but, in space, it is defined as a continuous function of LET. Thus, the contribution to the dose equivalent from heavy charged particles included in galactic cosmic rays is more than 50%, because of their high LET values. To evaluate such dose equivalent within an uncertainty of 30%, we must determine the true LET distribution. This paper describes the essence of such a new radiation dosimetry in space. (author)

  12. Dosimetry and process control for radiation processing

    International Nuclear Information System (INIS)

    Mod Ali, N.

    2002-01-01

    Complete text of publication follows. Accurate radiation dosimetry can provide quality assurance in radiation processing. Considerable relevant experiences in dosimetry by the SSDL-MINT has necessitate the development of methods making measurement at gamma plant traceable to the national standard. It involves the establishment of proper calibration procedure and selection of appropriate transfer system/technique to assure adequate traceability to a primary radiation standard. The effort forms the basis for irradiation process control, the legal approval of the process by the public health authorities (medical product sterilization and food preservation) and the safety and acceptance of the product

  13. Lyoluminescence dosimetry of the radiation in industrial doses

    International Nuclear Information System (INIS)

    Vigna Filho, E. del.

    1984-01-01

    The γ-rays lyoluminescence (LL) dosimetry study is presented. The basic principles involved, both in the method and radiation dosimetry, the equivalence between water and lyoluminescent materials, apparatus, irradiation technique and calibration method are discussed. The LL response dependence with environmental conditions are presented. These were temperature, humidity, storage time and the dependence on dissolved mass. A pre-reading thermal treatment was developed to overcome previous difficulties. The developed technique was applied to dose intercomparisons. (M.A.C.) [pt

  14. Physico-chemical Study of Some Prepared Dyed Films and Possible Application as Radiation Dosimetry Monitors

    International Nuclear Information System (INIS)

    Salem, A.S.A.

    2015-01-01

    Radiation processing, a relatively young industry dating from the mid 1950s, has prospered and continues to grow rapidly. The sterilization of medical products by radiation was demonstrated earlier and accounts for a considerable proportion of the industry establishing itself soundly during the 1970s. The radiation processing of polymers and food treatment by radiation have been thoroughly investigated and are important aspects of study. Radiation technology is now well established and is contributing to the industrial development, thus playing its legitimate role, taking into account the total value of the products treated with ionizing radiation, the economic scale of this technology is enormous. Some well established applications like sterilization, and polymers and semiconductors modification are in common use. This is especially true for health care products in industrial countries like the USA and Canada, where it is estimated that more than half of these products is currently sterilized using ionizing radiation

  15. New materials for radiation dosimetry

    International Nuclear Information System (INIS)

    Madatov, R.S.; Necefov, A.I.; Qabulov, I.A.; Seferova, S.

    2002-01-01

    Full text: The utilization of nuclear energy and beginning the production of radioactive nuclides are the reasons for radiation safety problems actualization. As a result of this, a new specific peculiar properties such as environmental, psychological, biological and etc. that are originated due to radioactive irradiation have been observed. Dosimetric equipment is used with the purpose of environmental protection, radiation detection, radiation safety assessment and distribution of information. The principle of operation of this equipment is based on the ionization effect. However, the equipment is differed one from another by the registration method. The main imperfections of dosimetric equipment are a narrowness of irradiation range as well as small values of energy sensitivity and stability. Taking into account of all above-stated imperfections, the obtaining of a new radiation-resistant materials and production of modern dosimetric detectors on their basis are one of the actual problems in dosimetry. At present the detectors on the basis of semiconductor materials such as Ge, Si, CdTe, CdS and etc. are widespread. Their principle of operation is also based on the ionization process, but the mechanism of its is differ from gas detectors. It is connected with that the carrier mobility for electrons in semiconductors is varied from 1400 up to 4000 cm 2 /(V·sec), and for holes from 400 up to 2000 cm 2 /(V·sec). It provides high level of detection for detectors on the basis of semiconductors. Initial conductivity of semiconductors differs one from another and it restricts the efficiency of detectors. The investigations on two directions have been carried out by this reason. The first direction is the increasing of radiation resistance of existing materials. The second direction is the obtaining of a new materials with high radiation resistance. It is known that the laminated materials on the basis of tellurium, for instance TeInS 2 are high sensitivity to X-radiation

  16. Medical radiation dosimetry with radiochromic film

    International Nuclear Information System (INIS)

    Butson, M.J.; Cancer Services, NSW; Cheung, T.; Yu, P.K.N.; Metcalfe, P.

    2004-01-01

    Full text: Photon, electron and proton radiation are used extensively for medical purposes in diagnostic and therapeutic procedures. Dosimetry of these radiation sources can be performed with radiochromic films, devices that have the ability to produce a permanent visible colour change upon irradiation. Within the last ten years, the use of radiochromic films has expanded rapidly in the medical world due to commercial products becoming more readily available, higher sensitivity films and technology advances in imaging which have allowed scientists to use two-dimensional dosimetry more accurately and inexpensively. Radiochromic film dosimeters are now available in formats, which have accurate dose measurement ranges from less than 1 Gy up to many kGy. A relatively energy independent dose response combined with automatic development of radiochromic film products has made these detectors most useful in medical radiation dosimetry. Copyright (2004) Australasian College of Physical Scientists and Engineers in Medicine

  17. 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)

  18. Role of dosimetry in radiation processing applications

    International Nuclear Information System (INIS)

    Mehta, Kishor

    2001-01-01

    Today, radiation processing is a growing technology offering potential technological advantages as well as enhanced safety and economy. It is expanding on two fronts: the variety of applications is exploding as well as the sources of radiation. And with that comes the necessary advances in dosimetry. However, the success of the technology still depends on the assertion that the irradiated products are reliable and safe, whether they are health care products or cables and wires. And this is best assured through quality assurance programmes. The key element in QA in radiation processing is a well-characterised, reliable dosimetry that is traceable to the international measurement system. Traceability is the foundation for international acceptance of the irradiated products; and with international trade of irradiated products on the rise, it becomes absolutely critical. It is thus vital that the industry recognises this pivotal position of good dosimetry and the role a national standards laboratory plays in that connection. (author)

  19. High sensitive radiation detector for radiology dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Valente, M.; Malano, F. [Instituto de Fisica Enrique Gaviola, Oficina 102 FaMAF - UNC, Av. Luis Medina Allende, Ciudad Universitaria, 5000 Cordoba (Argentina); Molina, W.; Vedelago, J., E-mail: valente@famac.unc.edu.ar [Laboratorio de Investigaciones e Instrumentacion en Fisica Aplicada a la Medicina e Imagenes por Rayos X, Laboratorio 448 FaMAF - UNC, Ciudad Universitaria, 5000 Cordoba (Argentina)

    2014-08-15

    Fricke solution has a wide range of applications as radiation detector and dosimetry. It is particularly appreciated in terms of relevant comparative advantages, like tissue equivalence when prepared in aqueous media like gel matrix, continuous mapping capability, dose rate recorded and incident direction independence as well as linear dose response. This work presents the development and characterization of a novel Fricke gel system, based on modified chemical compositions making possible its application in clinical radiology. Properties of standard Fricke gel dosimeter for high dose levels are used as starting point and suitable chemical modifications are introduced and carefully investigated in order to attain high resolution for low dose ranges, like those corresponding to radiology interventions. The developed Fricke gel radiation dosimeter system achieves the expected typical dose dependency, actually showing linear response in the dose range from 20 up to 4000 mGy. Systematic investigations including several chemical compositions are carried out in order to obtain a good enough dosimeter response for low dose levels. A suitable composition among those studied is selected as a good candidate for low dose level radiation dosimetry consisting on a modified Fricke solution fixed to a gel matrix containing benzoic acid along with sulfuric acid, ferrous sulfate, xylenol orange and ultra-pure reactive grade water. Dosimeter samples are prepared in standard vials for its in phantom irradiation and further characterization by spectrophotometry measuring visible light transmission and absorbance before and after irradiation. Samples are irradiated by typical kV X-ray tubes and calibrated Farmer type ionization chamber is used as reference to measure dose rates inside phantoms in at vials locations. Once sensitive material composition is already optimized, dose-response curves show significant improvement regarding overall sensitivity for low dose levels. According to

  20. High sensitive radiation detector for radiology dosimetry

    International Nuclear Information System (INIS)

    Valente, M.; Malano, F.; Molina, W.; Vedelago, J.

    2014-08-01

    Fricke solution has a wide range of applications as radiation detector and dosimetry. It is particularly appreciated in terms of relevant comparative advantages, like tissue equivalence when prepared in aqueous media like gel matrix, continuous mapping capability, dose rate recorded and incident direction independence as well as linear dose response. This work presents the development and characterization of a novel Fricke gel system, based on modified chemical compositions making possible its application in clinical radiology. Properties of standard Fricke gel dosimeter for high dose levels are used as starting point and suitable chemical modifications are introduced and carefully investigated in order to attain high resolution for low dose ranges, like those corresponding to radiology interventions. The developed Fricke gel radiation dosimeter system achieves the expected typical dose dependency, actually showing linear response in the dose range from 20 up to 4000 mGy. Systematic investigations including several chemical compositions are carried out in order to obtain a good enough dosimeter response for low dose levels. A suitable composition among those studied is selected as a good candidate for low dose level radiation dosimetry consisting on a modified Fricke solution fixed to a gel matrix containing benzoic acid along with sulfuric acid, ferrous sulfate, xylenol orange and ultra-pure reactive grade water. Dosimeter samples are prepared in standard vials for its in phantom irradiation and further characterization by spectrophotometry measuring visible light transmission and absorbance before and after irradiation. Samples are irradiated by typical kV X-ray tubes and calibrated Farmer type ionization chamber is used as reference to measure dose rates inside phantoms in at vials locations. Once sensitive material composition is already optimized, dose-response curves show significant improvement regarding overall sensitivity for low dose levels. According to

  1. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

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

  3. Radiation dosimetry activities in the Netherlands

    International Nuclear Information System (INIS)

    Broerse, J.J.; Mijnheer, B.J.

    1986-07-01

    The Netherlands Commission for Radiation Dosimetry (NCS) was officially established on 3 September 1982 with the aim of promoting the appropriate use of dosimetry of ionizing radiation both for scientific research and practical applications. The present report provides a compilation of the dosimetry acitivities and expertise available in the Netherlands, based on the replies to a questionnaire mailed under the auspices of the NCS and might suffer from some incompleteness in specific details. The addresses of the Dutch groups with the names of the scientists are given. Individual scientists, not connected with a scientific group, hospital or organization have not been included in this list. Also the names of commercial firms producing dosimetric systems have been omitted. (Auth.)

  4. Dosimetry control for radiation processing - basic requirements and standards

    International Nuclear Information System (INIS)

    Ivanova, M.; Tsrunchev, Ts.

    2004-01-01

    A brief review of the basic international codes and standards for dosimetry control for radiation processing (high doses dosimetry), setting up a dosimetry control for radiation processing and metrology control of the dosimetry system is made. The present state of dosimetry control for food processing and the Bulgarian long experience in food irradiation (three irradiation facilities are operational at these moment) are presented. The absence of neither national standard for high doses nor accredited laboratory for calibration and audit of radiation processing dosimetry systems is also discussed

  5. 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)

  6. Dosimetry and control of radiation processing

    International Nuclear Information System (INIS)

    1988-01-01

    Eight invited papers on the general theme of 'Dosimetry and Control of Radiation Processing', presented at a one day symposium held at the National Physical Laboratory, are collected together in this document. Seven of the papers are selected and indexed separately. (author)

  7. EPR-dosimetry of ionizing radiation

    Science.gov (United States)

    Popova, Mariia; Vakhnin, Dmitrii; Tyshchenko, Igor

    2017-09-01

    This article discusses the problems that arise during the radiation sterilization of medical products. It is propose the solution based on alanine EPR-dosimetry. The parameters of spectrometer and methods of absorbed dose calculation are given. In addition, the problems that arise during heavy particles irradiation are investigated.

  8. Applied physics of external radiation exposure dosimetry and radiation protection

    CERN Document Server

    Antoni, Rodolphe

    2017-01-01

    This book describes the interaction of living matter with photons, neutrons, charged particles, electrons and ions. The authors are specialists in the field of radiation protection. The book synthesizes many years of experiments with external radiation exposure in the fields of dosimetry and radiation shielding in medical, industrial and research fields. It presents the basic physical concepts including dosimetry and offers a number of tools to be used by students, engineers and technicians to assess the radiological risk and the means to avoid them by calculating the appropriate shields. The theory of radiation interaction in matter is presented together with empirical formulas and abacus. Numerous numerical applications are treated to illustrate the different topics. The state of the art in radiation protection and dosimetry is presented in detail, especially in the field of simulation codes for external exposure to radiation, medical projects and advanced research. Moreover, important data spread in differ...

  9. Low-energy x-ray dosimetry studies (7 to 17.5 keV) with synchroton radiation

    International Nuclear Information System (INIS)

    Ipe, N.E.; Bellamy, H.; Flood, J.R.

    1995-06-01

    Unique properties of synchrotron radiation (SR), such as its high intensity, brightness, polarization, and broad spectral distribution (extending from x-ray to infra-red wavelengths) make it an attractive light source for numerous experiments. As SR facilities are rapidly being built all over the world, they introduce the need for low-energy x-ray dosemeters because of the potential radiation exposure to experimenters. However, they also provide a unique opportunity for low-energy x-ray dosimetry studies because of the availability of monochromatic x-ray beams. Results of such studies performed at the Stanford Synchrotron Radiation Laboratory are described. Lithium fluoride TLDs (TLD-100) of varying thicknesses (0.015 to 0.08 cm) were exposed free in air to monochromatic x-rays (7 to 17.5 keV). These exposures were monitored with ionization chambers. The response (nC/Gy) was found to increase with increasing TLD thickness and with increasing beam energy. A steeper increase in response with increasing energy was observed with the thicker TLDs. The responses at 7 and 17.5 keV were within a factor of 2.3 and 5.2 for the 0.015 and 0.08 cm-thick TLDs, respectively. The effects of narrow (beam size smaller than the dosemeter) and broad (beam size larger than the dosemeter) beams on the response of the TLDs are also reported

  10. Radiation fields, dosimetry, biokinetics and biophysical models for cancer induction by ionising radiation 1996-1999. Executive summary

    International Nuclear Information System (INIS)

    Jacob, P.; Paretzke, H.G.; Roth, P.

    2000-01-01

    The Association Contract covers a range of research domains that are important to the Radiation Protection Research Action, especially in the areas 'Evaluation of Radiation Risks' and 'Understanding Radiation Mechanisms and Epidemiology'. Three research projects concentrate on radiation dosimetry research and two projects on the modelling of radiation carcinogenesis. The following list gives an overview on the topics and responsible scientific project leaders of the Association Contract: Study of radiation fields and dosimetry at aviation altitudes. Biokinetics and dosimetry of incorporated radionuclides. Dose reconstruction. Biophysical models for the induction of cancer by radiation. Experimental data for the induction of cancer by radiation of different qualities. (orig.)

  11. 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.

  12. Reconstructive dosimetry for cutaneous radiation syndrome

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-10-15

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

  13. High level radiation dosimetry in biomedical research

    International Nuclear Information System (INIS)

    Inada, Tetsuo

    1979-01-01

    The physical and biological dosimetries relating to cancer therapy with radiation were taken up at the first place in the late intercomparison on high LET radiation therapy in Japan-US cancer research cooperative study. The biological dosimetry, the large dose in biomedical research, the high dose rate in biomedical research and the practical dosimeters for pulsed neutrons or protons are outlined with the main development history and the characteristics which were obtained in the relating experiments. The clinical neutron facilities in the US and Japan involved in the intercomparison are presented. Concerning the experimental results of dosimeters, the relation between the R.B.E. compared with Chiba (Cyclotron in National Institute of Radiological Sciences) and the energy of deuterons or protons used for neutron production, the survival curves of three cultured cell lines derived from human cancers, after the irradiation of 250 keV X-ray, cyclotron neutrons of about 13 MeV and Van de Graaff neutrons of about 2 MeV, the hatchability of dry Artemia eggs at the several depths in an absorber stack irradiated by 60 MeV proton beam of 40, 120 and 200 krad, the peak skin reaction of mouse legs observed at various sets of average and instantaneous dose rates, and the peak skin reaction versus three instantaneous dose rates at fixed average dose rate of 7,300 rad/min are shown. These actual data were evaluated numerically and in relation to the physical meaning from the viewpoint of the fundamental aspect of cancer therapy, comparing the Japanese measured values to the US data. The discussion record on the high dose rate effect of low LET particles on biological substances and others is added. (Nakai, Y.)

  14. Dosimetry systems for radiation processing in Japan

    International Nuclear Information System (INIS)

    Tamura, Naoyuki

    1995-01-01

    The present situation of dosimetry systems for radiation processing industry in Japan is reviewed. For gamma-rays irradiation the parallel-plate ionization chamber in TRCRE, JAERI has been placed as a reference standard dosimeter for processing-level dose. Various solid and liquid chemical dosimeters are used as routine dosimeters for gamma processing industries. Alanine dosimeters is used for the irradiation purpose which needs precise dosimetry. For electron-beam irradiation the electron current density meter and the total absorption calorimeter of TRCRE are used for the calibration of routine dosimeters. Plastic film dosimeters, such as cellulose triacetate and radiochromic dye are used as routine dosimeters for electron processing industries. When the official traceability systems for processing-level dosimetry now under investigation is completed, the ionization chamber of TRCRE is expected to have a role of the primary standard dosimeter and the specified alanine dosimeter will be nominated for the secondary or reference standard dosimeter. (author)

  15. Radiation dosimetry for the space shuttle program

    International Nuclear Information System (INIS)

    Jones, K.L.; Richmond, R.G.; Cash, B.L.

    1985-01-01

    Radiation measurements aboard the Space Shuttle are made to record crew doses for medical records, to verify analytical shielding calculations used in dose predictions and to provide dosimetry support for radiation sensitive payloads and experiments. Low cost systems utilizing thermoluminescent dosimeters, nuclear track detectors and activation foils have been developed to fulfill these requirements. Emphasis has been placed on mission planning and dose prediction. As a result, crew doses both inside the orbiter and during extra-vehicular activities have been reasonable low. Brief descriptions of the space radiation environment, dose prediction models, and radiation measurement systems are provided, along with a summary of the results for the first fourteen Shuttle flights

  16. 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)

  17. Film Dosimetry for Intensity Modulated Radiation Therapy

    International Nuclear Information System (INIS)

    Benites-Rengifo, J.; Martinez-Davalos, A.; Celis, M.; Larraga, J.

    2004-01-01

    Intensity Modulated Radiation Therapy (IMRT) is an oncology treatment technique that employs non-uniform beam intensities to deliver highly conformal radiation to the targets while minimizing doses to normal tissues and critical organs. A key element for a successful clinical implementation of IMRT is establishing a dosimetric verification process that can ensure that delivered doses are consistent with calculated ones for each patient. To this end we are developing a fast quality control procedure, based on film dosimetry techniques, to be applied to the 6 MV Novalis linear accelerator for IMRT of the Instituto Nacional de Neurologia y Neurocirugia (INNN) in Mexico City. The procedure includes measurements of individual fluence maps for a limited number of fields and dose distributions in 3D using extended dose-range radiographic film. However, the film response to radiation might depend on depth, energy and field size, and therefore compromise the accuracy of measurements. In this work we present a study of the dependence of Kodak EDR2 film's response on the depth, field size and energy, compared with those of Kodak XV2 film. The first aim is to devise a fast and accurate method to determine the calibration curve of film (optical density vs. doses) commonly called a sensitometric curve. This was accomplished by using three types of irradiation techniques: Step-and-shoot, dynamic and static fields

  18. An optically stimulated luminescence study of porcelain related to radiation dosimetry

    DEFF Research Database (Denmark)

    Poolton, N.R.J.; Bøtter-Jensen, L.; Jungner, H.

    1995-01-01

    Stokes and anti-Stokes shifted in energy. Glazing is shown in some cases to be considerably more sensitive as a radiation dosemeter than the main porcelain ceramic. By comparison with the properties of artifical phosphors, the principal luminescent matrix is identified as being Al2O3......This article describes the essential features regarding the photo-stimulated luminescence of porcelain: both the main ceramic and glazing materials are studied. In each case, radiation dose dependent signals are observed, superimposed on dose independent luminescence transitions that are both...

  19. MOSFET dosimetry on modern radiation oncology modalities

    International Nuclear Information System (INIS)

    Rosenfeld, A.B.

    2002-01-01

    The development of MOSFET dosimetry is presented with an emphasis on the development of a scanning MOSFET dosimetry system for modern radiation oncology modalities. Fundamental aspects of MOSFETs in relation to their use as dosemeters are briefly discussed. The performance of MOSFET dosemeters in conformal radiotherapy, hadron therapy, intensity-modulated radiotherapy and microbeam radiation therapy is compared with other dosimetric techniques. In particular the application of MOSFET dosemeters in the characterisation and quality assurance of the steep dose gradients associated with the penumbra of some modern radiation oncology modalities is investigated. A new in vivo, on-line, scanning MOSFET read out system is also presented. The system has the ability to read out multiple MOSFET dosemeters with excellent spatial resolution and temperature stability and minimal slow border trapping effects. (author)

  20. Criticality accidents in solution (CRAC and SILENE programmes) and complementary studies of accidents; radiation dosimetry in human organism during the CRAC programme

    International Nuclear Information System (INIS)

    Barbry, M.; Dousset, M.

    C.R.A.C. (CRiticality occurring ACcidentally) programme is intended to study experimentally the development of a criticality accident as it could occur when handling solutions of fissile material as well as the radiological consequences of such an accident. The fissile matter solutions have been chosen (a) for practical considerations of use and (b) because the probability of an accident occurring seems greater with this type of environment, as the known accidents have shown. The programme is twofold: study of accident physics: form of the evolution (peak, plateau, oscillations, boil up of solutions) the most probable maximum power, minimal power, flux and radiation spectra emitted, freed energy, associated effects, radiolysis, constraints, etc., study of radiological consequences: area dosimetry, individual dosimetry, radiobiological studies, etc. Additional criticality Accident experiments have been and continue to be made on the SILENE reactor in the following principal domains: determination of the emission rate of gaseous fission products and aerosols, area dosimetry and health dosimetry in the presence of shields around the core to vary the neutron and gamma components of the radiation field. Improvement in the knowledge of certain particular aspects of the power excursion, radiolysis gas and pressure wave, experiments of the ''boiling'' type [fr

  1. 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)

  2. Radiation, cancer risk, and the new dosimetry

    International Nuclear Information System (INIS)

    Mole, R.H.

    1987-01-01

    This letter discusses revision of risk estimates in the light of the new dosimetry (DS86) and concludes that direct observation is more to be relied on than the extrapolation from A-bomb survivors' experience. X-ray treatment for ankylosing spondylitis, cervical cancer data, and figures observed from 50,000 workers occupationally exposed to radiation are used as examples. (U.K.)

  3. Radiation dosimetry and spectrometry with superheated emulsions

    International Nuclear Information System (INIS)

    D'Errico, Francesco

    2001-01-01

    Detectors based on emulsions of overexpanded halocarbon droplets in tissue equivalent aqueous gels or soft polymers, known as 'superheated drop detectors' or 'bubble (damage) detectors', have been used in radiation detection, dosimetry and spectrometry for over two decades. Recent technological advances have led to the introduction of several instruments for individual and area monitoring: passive integrating meters based on the optical or volumetric registration of the bubbles, and active counters detecting bubble nucleations acoustically. These advances in the instrumentation have been matched by the progress made in the production of stable and well-specified emulsions of superheated droplets. A variety of halocarbons are employed in the formulation of the detectors, and this permits a wide range of applications. In particular, halocarbons with a moderate degree of superheat, i.e. a relatively small difference between their operating temperature and boiling point, can be used in neutron dosimetry and spectrometry since they are only nucleated by energetic heavy ions such as those produced by fast neutrons. More recently, halocarbons with an elevated degree of superheat have been utilised to produce emulsions that nucleate with much smaller energy deposition and detect low linear energy transfer radiations, such as photons and electrons. This paper reviews the detector physics of superheated emulsions and their applications in radiation measurements, particularly in neutron dosimetry and spectrometry

  4. Medical radiation dosimetry theory of charged particle collision energy loss

    CERN Document Server

    McParland, Brian J

    2014-01-01

    Accurate radiation dosimetry is a requirement of radiation oncology, diagnostic radiology and nuclear medicine. It is necessary so as to satisfy the needs of patient safety, therapeutic and diagnostic optimisation, and retrospective epidemiological studies of the biological effects resulting from low absorbed doses of ionising radiation. The radiation absorbed dose received by the patient is the ultimate consequence of the transfer of kinetic energy through collisions between energetic charged particles and atoms of the tissue being traversed. Thus, the ability of the medical physicist to both measure and calculate accurately patient dosimetry demands a deep understanding of the physics of charged particle interactions with matter. Interestingly, the physics of charged particle energy loss has an almost exclusively theoretical basis, thus necessitating an advanced theoretical understanding of the subject in order to apply it appropriately to the clinical regime. ​ Each year, about one-third of the worl...

  5. Environmental dosimetry and radiation effects

    International Nuclear Information System (INIS)

    Woodhead, D.S.

    1997-01-01

    Specific assessment of the potential effects on wild organisms of increased radiation exposure arising from the authorized disposal of radioactive wastes to the environment requires two interrelated sets of information. First, an estimate is required of the incremental radiation exposure; and second, dose rate-response relationships are necessary to predict the potential impact of the estimated incremental exposure. Each of these aspects will be discussed in detail. (author)

  6. Personal dosimetry at the radiation accidents

    International Nuclear Information System (INIS)

    Perevoznikov, O.N.; Klyuchnikov, A.A.; Kanchenko, V.A.

    2007-01-01

    The radiation accidents of different types and the methods of the dosimetry used at the consequences liquidation are considered. The long-term experience of the population personal instrumental dosimetric control carrying out at the ChNPP accident consequences liquidation is widely covered in details. The concepts are stated out and the results are presented on the functioning of the created system for personal dose monitoring of the population of Ukraine irradiation. The use of the person radiation counters at the internal irradiation population and personal dose assessment is considered in details

  7. Preclinical acute toxicity, biodistribution, pharmacokinetics, radiation dosimetry and microPET imaging studies of ["1"8F]fluorocholine in mice

    International Nuclear Information System (INIS)

    Silveira, Marina B.; Ferreira, Soraya M.Z.M.D.; Nascimento, Leonardo T.C.; Costa, Flávia M.; Mendes, Bruno M.; Ferreira, Andrea V.; Malamut, Carlos; Silva, Juliana B.; Mamede, Marcelo

    2016-01-01

    ["1"8F]Fluorocholine (["1"8F]FCH) has been proven to be effective in prostate cancer. Since ["1"8F]FCH is classified as a new radiopharmaceutical in Brazil, preclinical safety and efficacy data are required to support clinical trials and to obtain its approval. The aim of this work was to perform acute toxicity, biodistribution, pharmacokinetics, radiation dosimetry and microPET imaging studies of ["1"8F]FCH. The results could support its use in nuclear medicine as an important piece of work for regulatory in Brazil. - Highlights: • Data demonstrated the high quality, safety and effectiveness of ["1"8F]FCH. • ["1"8F]FCH preclinical profile is in accordance with previously published. • Toxicity, distribution, kinetics and radiation dosimetry were well characterized. • The results are important for regulatory issues in Brazil and other countries.

  8. A study on the real-time radiation dosimetry measurement system based on optically stimulated luminescence

    International Nuclear Information System (INIS)

    Liu Yanping; Du Yanzhao; Chen Zhaoyang; Ba Weizhen; Fan Yanwei; Pan Shilie; Guo Qi

    2008-01-01

    The optically stimulated luminescent (OSL) radiation dosimeter technically surveys a wide dynamic measurement range and a high sensitivity. Optical fiber dosimeters provide capability for remote monitoring of the radiation in the locations which are difficult-to-access and hazardous. In addition, optical fiber dosimeters are immune to electrical and radio-frequency interference. In this paper, a novel remote optical fiber radiation dosimeter is described. The optical fiber dosimeter takes advantage of the charge trapping materials CaS:Ce, Sm that exhibit OSL. The measuring range of the dosimeter is from 0.1 to 100 Gy. The equipment is relatively simple and small in size, and has low power consumption. This device is suitable for measuring the space radiation dose and also can be used in high radiation dose condition and other dangerous radiation occasions. (authors)

  9. Autoradiographic studies of the distribution of radium-226 in rat bone: their implications for human radiation dosimetry and toxicity

    International Nuclear Information System (INIS)

    Priest, N.D.; Haines, J.W.; Howells, G.; Green, D.

    1983-01-01

    A solution containing 226 Ra chloride was injected into young female rats via the saphenous vein. Subsequently, the distribution and retention of the 226 Ra in the skeleton was studied. The results show that 226 Ra is initially deposited in the rat femur as a volume deposit and is fairly evenly distributed throughout the bone matrix. Much of the 226 Ra initially deposited in the skeleton is lost within a few days of its administration. During the first week 226 Ra gradually accumulates at sites of bone deposition including accreting surfaces. Subsequent bone growth results in the burial of contaminated bone surfaces. Following bone resorption some of the 226 Ra released from individual bones is recycled systemically so that all skeletal components tend towards a uniform 226 Ra concentration per unit of bone mineral. Of the two models conventionally used for radiation dosimetry purposes, these results reported for rats suggest that though neither is ideal, the volume distribution model is preferable to the surface model at all times after the uptake of radium by the skeleton. (author)

  10. X radiations dosimetry in pulmonary radiographs: study of a non standard room

    International Nuclear Information System (INIS)

    Bied, J.C.; Philippon, B.

    1998-01-01

    A radiograph room can present a default of radiation protection. But it is possible that the radiation protection is here only to mask a protection of an other type. For the case of a lungs type radiograph room, the monitoring does not reveal any problem of radiation protection. These results do not bring to the fore any high radiations doses. But they are an illustration of operators positions, and these ones should be better protected at the extremity of the room, that should allow a correct vision of lungs radiographs and a more important limitation of irradiation. (N.C.)

  11. Radiation protection dosimetry - From amateur to professional

    International Nuclear Information System (INIS)

    Goldfinch, E. P.

    2006-01-01

    Radiation Protection Dosimetry was founded in 1981 and there has been a close link between the journal and the solid state dosimetry series of conferences from 1983 to the present day. The background to and the creation and development of the journal is described, having started as one volume of four issues per year in 1981 rising to six volumes in 1994. During the period of development there have been considerable advances in all forms of technology, requiring continued attention to the introduction of this new technology. Some of the changes in the world of publishing over the past 25 y are quite dramatic. Whilst simplistic approaches have been adequate within a small publishing house for a considerable time, further progressive technology changes that are required in the future mean that the necessary resources are only realistically available to large publishers. The journal thus moved to Oxford Univ. Press at the beginning of 2004. It will celebrate its 25. year in 2005. (authors)

  12. Dosimetry practices at the Radiation Technology Centre (Ghana)

    International Nuclear Information System (INIS)

    Emi-Reynolds, G.; Banini, G.K.; Ennison, I.

    1997-01-01

    Dosimetry practices undertaken to support research and pilot scale gamma irradiation activities at the Radiation Technology Centre of the Ghana Atomic Energy Commission are presented. The Fricke dosemeter was used for calibrating the gamma field of the gammacell-220. The Fricke system and the gammacell-220 were then used to calibrate the ethanol chlorobenzene (ECB) dosemeter. The Fricke and ECB dosemeter systems have become routine dosemeters at the centre. Dosimetry work has covered a wide range of research specimens and pilot scale products to establish the relevant irradiation protocol and parameters for routine treatment. These include yams, pineapple explants, blood for feeding tsetseflies, cocoa bud wood and cassava sticks. Pilot scale dosimetry studies on maize, medical devices like intravenous infusion sets and surgical gauze have also been completed. The results and observations made on some of these products are reported. (author). 4 refs., 5 figs

  13. 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

  14. Optimization of the preparation method of LiF: Mg, Cu, P and study of its thermoluminescent properties to be used in ionizing radiation dosimetry

    International Nuclear Information System (INIS)

    Gonzalez M, P.R.

    1995-01-01

    In this thesis the preparation and dosimetric properties of the thermoluminescence phosphor LiF doped with magnesium, copper and phosphorus are studied. In chapter 1 luminescence phenomenon in solids is described, emphasizing the importance of thermally stimulated luminescence known as thermoluminescence (TL) as well as its application in ionizing radiation dosimetry. The models used to determine the kinetics parameters in the TL phenomenon are described in chapter 2. In chapter 3, the dosimetric characteristics of a TL materials and its requirements for dosimetry are analyzed. The preparation method of LiF: Mg, Cu, P is presented in chapter 4 studying its general characteristics for dosimetry. The concentrations of dopants, glow curve structure, TL response to gamma, beta and alpha exposures are studied along with those of LiF: Mg, Cu, P prepared for other authors and with those of LiF: Mg, Ti (TLD-100). The kinetic parameters of the phosphor were determined by the deconvolution method. Pellets of this new phosphor powder were made by pressing it at room temperature and sintering in inert atmosphere at 700 Centigrade degrees. Dosimetric characteristics of these pellets were also studied. Chapter 5 presents the results and conclusions of this study. The new dosimeter exhibited three peaks in its glow curve at 140, 180 and 220 Centigrade degrees respectively. Its TL response to gamma radiation was linear from 43.5 μ Gy to 100 Gy. This dosimeter is reusable and stable without significant loss of sensitivity. Its sensitivity was about 30 times higher than that of TLD-100. Fading of this dosimeter was negligible at room temperature as well as at body temperature (37 Centigrade degrees), and 65% at 60 Centigrade degrees. In conclusion, this dosimeter meets all the requirements of the ANSI standard. These and other characteristics render this dosimeter useful in diverse applications of radiation dosimetry. (Author)

  15. Recent developments in neutron dosimetry and radiation damage calculations for fusion-materials studies

    International Nuclear Information System (INIS)

    Greenwood, L.R.

    1983-01-01

    This paper is intended as an overview of activities designed to characterize neutron irradiation facilities in terms of neutron flux and energy spectrum and to use these data to calculate atomic displacements, gas production, and transmutation during fusion materials irradiations. A new computerized data file, called DOSFILE, has recently been developed to record dosimetry and damage data from a wide variety of materials test facilities. At present data are included from 20 different irradiations at fast and mixed-spectrum reactors, T(d,n) 14 MeV neutron sources, Be(d,n) broad-spectrum sources, and spallation neutron sources. Each file entry includes activation data, adjusted neutron flux and spectral data, and calculated atomic displacements and gas production. Such data will be used by materials experimenters to determine the exposure of their samples during specific irradiations. This data base will play an important role in correlating property changes between different facilities and, eventually, in predicting materials performance in fusion reactors. All known uncertainties and covariances are listed for each data record and explicit references are given to nuclear decay data and cross sections

  16. Radiation Dosimetry Management: Quality Assurance and Investigations

    International Nuclear Information System (INIS)

    Perle, S.

    2001-01-01

    Full text: In a litigation-prone society, it is prudent for any business to evaluate its potential exposure to legal action, initiated by either an employee or a member of the general public. This potential is exacerbated when the phobia of radiation exposure and radioactive materials is interjected into the equation. This phobia is fuelled by the perceived risks of radiation exposure, be they fact or fantasy. With the current cancer incidence rate being approximately 1 in every 2.5 individuals (for all types of cancer), it is imperative that all facilities take a proactive look at their business vulnerability. When radiation exposure is the issue, records documentation is a critical factor, and a significant amount of effort should be expended to implement a comprehensive records management system. A comprehensive Radiation Dosimetry Management Program is essential if a business is going to mitigate any regulatory or legal intervention. This lecture will address appropriate Records Quality Assurance, and, the appropriate requirements for investigations of dosimetry results. (author)

  17. Dosimetry as an integral part of radiation processing

    International Nuclear Information System (INIS)

    Zagorski, Z.P.

    1999-01-01

    Different connections between high-dose dosimetry and radiation processing are discussed. Radiation processing cannot be performed without proper dosimetry. Accurate high dose and high dose rate dosimetry exhibits several aspects: first of all it is the preservation of the quality of the product, then fulfillment of legal aspects and last but not the least the safety of processing. Further, seldom discussed topics are as follow: dosimetric problems occurring with double-side EB irradiations, discussed in connection with the deposition of electric charge during electron beam irradiation. Although dosimetry for basic research and for medical purposes are treated here only shortly, some conclusions reached from these fields are considered in dosimetry for radiation processing. High-dose dosimetry of radiation has become a separate field, with many papers published every year, but applied dosimetric projects are usually initiated by a necessity of particular application. (author)

  18. Proton-beam radiation therapy dosimetry standardization

    International Nuclear Information System (INIS)

    Gall, K.P.

    1995-01-01

    Beams of protons have been used for radiation therapy applications for over 40 years. In the last decade the number of facilities treating patients and the total number of patients being treated has begun go grow rapidly. Due to the limited and experimental nature of the early programs, dosimetry protocols tended to be locally defined. With the publication of the AAPM Task Group 20 report open-quotes Protocol for Dosimetry of Heavy Charged Particlesclose quotes and the open-quotes European Code of Practice for Proton-Beam Dosimetryclose quotes the practice of determining dose in proton-beam therapy was somewhat unified. The ICRU has also recently commissioned a report on recommendations for proton-beam dosimetry. There have been three main methods of determining proton dose; the Faraday cup technique, the ionization chamber technique, and the calorimeter technique. For practical reasons the ionization chamber technique has become the most widely used. However, due to large errors in basic parameters (e.g., W-value) is also has a large uncertainty for absolute dose. It has been proposed that the development of water calorimeter absorbed dose standards would reduce the uncertainty in absolute proton dose as well as the relative dose between megavoltage X-ray beams and proton beams. The advantages and disadvantages are discussed

  19. Role of secondary standard dosimetry laboratory in radiation protection program

    International Nuclear Information System (INIS)

    Rahman, Sohaila; Ali, Noriah Mohd.

    2008-01-01

    Full text: The radiation dosimetry program is an important element of operational radiation protection. Dosimetry data enable workers and radiation protection professionals to evaluate and control work practices to eliminate unnecessary exposure to ionizing radiation. The usefulness of the data produced however depends on its quality and traceability. The emphasis of the global dosimetry program is focused through the IAEA/WHO network of secondary standard dosimetry laboratories (SSDLs), which aims for the determination of SI quantities through proper traceable calibration of radiation protection equipment. The responsibility of SSDL-NUCLEAR MALAYSIA to guarantee a reliable dosimetry service, which is traceable to international standards, is elucidated. It acts as the basis for harmonized occupational radiation monitoring in Malaysia.

  20. Preliminary Study on Hybrid Computational Phantom for Radiation Dosimetry Based on Subdivision Surface

    International Nuclear Information System (INIS)

    Jeong, Jong Hwi; Choi, Sang Hyoun; Cho, Sung Koo; Kim, Chan Hyeong

    2007-01-01

    The anthropomorphic computational phantoms are classified into two groups. One group is the stylized phantoms, or MIRD phantoms, which are based on mathematical representations of the anatomical structures. The shapes and positions of the organs and tissues in these phantoms can be adjusted by changing the coefficients of the equations in use. The other group is the voxel phantoms, which are based on tomographic images of a real person such as CT, MR and serially sectioned color slice images from a cadaver. Obviously, the voxel phantoms represent the anatomical structures of a human body much more realistically than the stylized phantoms. A realistic representation of anatomical structure is very important for an accurate calculation of radiation dose in the human body. Consequently, the ICRP recently has decided to use the voxel phantoms for the forthcoming update of the dose conversion coefficients. However, the voxel phantoms also have some limitations: (1) The topology and dimensions of the organs and tissues in a voxel model are extremely difficult to change, and (2) The thin organs, such as oral mucosa and skin, cannot be realistically modeled unless the voxel resolution is prohibitively high. Recently, a new approach has been implemented by several investigators. The investigators converted their voxel phantoms to hybrid computational phantoms based on NURBS (Non-Uniform Rational B-Splines) surface, which is smooth and deformable. It is claimed that these new phantoms have the flexibility of the stylized phantom along with the realistic representations of the anatomical structures. The topology and dimensions of the anatomical structures can be easily changed as necessary. Thin organs can be modeled without affecting computational speed or memory requirement. The hybrid phantoms can be also used for 4-D Monte Carlo simulations. In this preliminary study, the external shape of a voxel phantom (i.e., skin), HDRK-Man, was converted to a hybrid computational

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

    International Nuclear Information System (INIS)

    2009-01-01

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

  2. Internal radiation dosimetry of F-18-5-fluorouracil

    International Nuclear Information System (INIS)

    Shani, J.; Schlesinger, T.; Wolf, W.

    1980-01-01

    The projected internal radiations dose to different human organs per millicurie of injected F-18-5-Fluorouracil is calculated from rat distribution studies and human urinary excretion data. The calculations assume a similar distribution of labelled drug in humans as in rats, inasmuch as preliminary human distribution studies appeared to validate the use of the rat model for human dosimetry calculations. (U.K.)

  3. Research Laboratory of Mixed Radiation Dosimetry

    International Nuclear Information System (INIS)

    2002-01-01

    Full text: Two main topics of the research work in the Laboratory of Mixed Radiation Dosimetry in 2001 were: development of recombination methods for dosimetry of mixed radiation fields and maintenance and development of unique in Poland reference neutron fields. Additionally research project on internal dosimetry were carried out in collaboration with Division of Radiation Protection Service. RECOMBINATION METHODS Recombination methods make use of the fact that the initial recombination of ions in the gas cavity of the ionization chamber depends on local ionization density. The later can be related to linear energy transfer (LET) and provides information on radiation quality of the investigated radiation fields. Another key feature of the initial recombination is that it does not depend of dose rate. Conditions of initial (local) recombination can be achieved in specially designed high pressure tissue-equivalent ionization chambers, called the recombination chambers. They are usually parallel-plate ionization chambers filled with a tissue-equivalent gas mixture under a pressure of order 1 MPa. The spacing between electrodes is of order of millimeters. At larger spacing, the volume recombination limits the maximum dose rate at which the chamber can be properly operated. The output of the chamber is the ionization current (or collected charge) as a function of collecting voltage. All the recombination methods require the measurement of the ionization current (or charge) at least at two values of the collecting voltage applied to the chamber. The highest voltage should provide the conditions close to saturation (but below discharge or multiplication). The ionization current measured at maximum applied voltage is proportional to the absorbed dose, D, (some small corrections for lack of saturation can be introduced when needed). Measurements at other voltages are needed for the determination of radiation quality. The total dose equivalent in a mixed radiation field is

  4. Radiation risk assessment in neonatal radiographic examinations of the chest and abdomen: a clinical and Monte Carlo dosimetry study

    International Nuclear Information System (INIS)

    Makri, T; Yakoumakis, E; Papadopoulou, D; Gialousis, G; Theodoropoulos, V; Sandilos, P; Georgiou, E

    2006-01-01

    Seeking to assess the radiation risk associated with radiological examinations in neonatal intensive care units, thermo-luminescence dosimetry was used for the measurement of entrance surface dose (ESD) in 44 AP chest and 28 AP combined chest-abdominal exposures of a sample of 60 neonates. The mean values of ESD were found to be equal to 44 ± 16 μGy and 43 ± 19 μGy, respectively. The MCNP-4C2 code with a mathematical phantom simulating a neonate and appropriate x-ray energy spectra were employed for the simulation of the AP chest and AP combined chest-abdominal exposures. Equivalent organ dose per unit ESD and energy imparted per unit ESD calculations are presented in tabular form. Combined with ESD measurements, these calculations yield an effective dose of 10.2 ± 3.7 μSv, regardless of sex, and an imparted energy of 18.5 ± 6.7 μJ for the chest radiograph. The corresponding results for the combined chest-abdominal examination are 14.7 ± 7.6 μSv (males)/17.2 ± 7.6 μSv (females) and 29.7 ± 13.2 μJ. The calculated total risk per radiograph was low, ranging between 1.7 and 2.9 per million neonates, per film, and being slightly higher for females. Results of this study are in good agreement with previous studies, especially in view of the diversity met in the calculation methods

  5. Radiation risk assessment in neonatal radiographic examinations of the chest and abdomen: a clinical and Monte Carlo dosimetry study

    Science.gov (United States)

    Makri, T.; Yakoumakis, E.; Papadopoulou, D.; Gialousis, G.; Theodoropoulos, V.; Sandilos, P.; Georgiou, E.

    2006-10-01

    Seeking to assess the radiation risk associated with radiological examinations in neonatal intensive care units, thermo-luminescence dosimetry was used for the measurement of entrance surface dose (ESD) in 44 AP chest and 28 AP combined chest-abdominal exposures of a sample of 60 neonates. The mean values of ESD were found to be equal to 44 ± 16 µGy and 43 ± 19 µGy, respectively. The MCNP-4C2 code with a mathematical phantom simulating a neonate and appropriate x-ray energy spectra were employed for the simulation of the AP chest and AP combined chest-abdominal exposures. Equivalent organ dose per unit ESD and energy imparted per unit ESD calculations are presented in tabular form. Combined with ESD measurements, these calculations yield an effective dose of 10.2 ± 3.7 µSv, regardless of sex, and an imparted energy of 18.5 ± 6.7 µJ for the chest radiograph. The corresponding results for the combined chest-abdominal examination are 14.7 ± 7.6 µSv (males)/17.2 ± 7.6 µSv (females) and 29.7 ± 13.2 µJ. The calculated total risk per radiograph was low, ranging between 1.7 and 2.9 per million neonates, per film, and being slightly higher for females. Results of this study are in good agreement with previous studies, especially in view of the diversity met in the calculation methods.

  6. Dosimetry study on the conventional and three dimensional conformal radiation treatment planning protocols for rectal cancer

    International Nuclear Information System (INIS)

    Cai Yong; He Yuxiang; Han Shukui; Wu Hao; Gong Jian; Xu Bo

    2007-01-01

    Objective: To compare the dose distribution of clinical target volume (CTV), in normal tissues and organs for patients with rectal cancer on the conventional radiotherapy (2D) and three dimension- al conformal radiation treatment (3DCRT). Methods: The CT image data of 36 rectal cancer patients treated with 3DCRT were studied. The CTV, small bowel, colon, bladder, pelvic bone marrow, and femoral head and neck were contoured on consecutive axial slices of CT images. Two 3DCRT and three conventional treatment planning protocols were simulated using three dimensional treatment planning system (CMS Focus 2.31), were defined as 3D-3, 3D-4, 2D-2, 2D-3, 2D-4. The difference of five treatment planning protocols on the CTV and normal structure by analysis of dose-volume histograms (DVHs) were compared. Results: The D 95 and V 95 of these five protocols all exceeded 97%. The conformity index(CI) of 3D was obviously larger than that of 2D protocol. The dose inhomogeneity(DI) in 4 DCRT was less than that of 3 DCRT. The 3D as compared with the 2D, significantly reduced the mean dose of 45 Gy to the small bowel and colon. The 3D-3 as compared with the 2D-3, the 3D-4 as compared with the 2D-4, the mean dose of small bowel and colon was reduced by 28.5% and 25.7%, respectively. The 3D-3 as compared with the 2D-2, the 3D-3 as compared with the 2D-3 and the 3D4 as compared with the 2D-4, the percentage volume of small bowel and colon which received 45 Gy was reduced by 80.8% , 51.1% and 54.7% , respectively. Either the mean dose, or the percentage volume receiving 35 Gy and 45 Gy to the pelvic bone and bladder, the 3D planning protocols had advanage over the 2D planning protocols. The V 45 of bladder in 2D-2 planning proto- col was the highest in all planning protocols, exceeding 98%, but the highest V 45 of bladder was only 50% in the other planning protocols. Conclusions: Even though the difference in pelvic CTV of rectal cancer patients between the conventional radiotherapy and 3

  7. A study on the radiation and environment safety -Development of technology for biological dosimetry-

    International Nuclear Information System (INIS)

    Lee, Kang Suk; Kim, Kook Chan; Kim, In Kyoo; Kim, Jin Kyoo; Chun Kee Jung; Park, Hyo Kook; Kim, Sang Bok; Park Sun Yung

    1995-07-01

    Adult rats were treated a single, whole body exposure to a dose of 0.1, 0.5, 1.0, 2.0, 3.0 Gy. The animals were sacrificed 6, 24, 48, 72, 96 hours following exposure. The amount of serum acute phase proteins(haptoglobin, ceruloplasmin, C-reactive protein, alpha-1 antitrypsin, alpha-1 acid glycoprotein, transferrin) were measured by competitive ELISA. In the 0.1 Gy irradiated rats, serum haptoglobin, C-reactive protein and alpha-1 antitrypsin were 400% higher and serum transferrin was 50% lower as compared to controls, 96 hours after irradiation. Ceruloplasmin increased by 400%, 24 hours after irradiation, but 96 hours after irradiation, the concentration of this protein in rat returned to normal level. On the other hand, no changes were observed in the case of alpha-1 acid glycoprotein. In the group of the 3.0 Gy irradiated rats, transferrin increased by 200%, 96 hours after irradiation. These biochemical responses to radiation did not show dose-dependent relation, but the sensitivity of the indicators was high enough to detect absorbed dose of 0.1 Gy. The above results can be applied to the measurements of acute phase reactants in human serum for the assessment of exposure doses in radiation workers and patients under radiation therapy. 39 figs, 72 refs. (Author)

  8. Radiation therapy: dosimetry study of the effect of the composition of Pb alloys by PENELOPE

    Directory of Open Access Journals (Sweden)

    Jose McDonnell

    2011-02-01

    Full Text Available Radiotherapy is a widely used treatment for cancer. Currently applying the technique of Intensity Modulated Radiation Therapy, in which an important aspect is the modulation of the radiation beam to generate a non-uniform dose distribution in the tumor. One way to achieve the above non-uniform dose distribution is using solid compensators. In the market there are a number of materials used to manufacture compensators. Pb alloys on the market are: Cerromatrix, Rose, Wood, Newton, Darcet, whose compositions vary with respect to the composition of the lipowitz metal. This paper quantifies the dosimetric effects of the composition of commercial alloys, routinely used in radiotherapy. This quantification is important because of its impact on the total uncertainty of treatment accepted in the dosimetric calculations. To investigate the dosimetric effect of the composition of commercial alloys in the market we used the PENELOPE code, code that allows the simulation of radiation transport in different media by Monte Carlo method.The results show that there is a difference dosimetric respect lipowitz material, ranging from 7 % to 9 % for the materials investigated. These values indicate the importance of knowing exactly the dosimetric characteristics of the material used as compensator for their implications in the dose calculation.

  9. A study on the radiation and environment safety -Development of technology for biological dosimetry-

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kang Suk; Kim, Kook Chan; Kim, In Kyoo; Kim, Jin Kyoo; Jung, Chun Kee; Park, Hyo Kook; Kim, Sang Bok; Yung, Park Sun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    Adult rats were treated a single, whole body exposure to a dose of 0.1, 0.5, 1.0, 2.0, 3.0 Gy. The animals were sacrificed 6, 24, 48, 72, 96 hours following exposure. The amount of serum acute phase proteins(haptoglobin, ceruloplasmin, C-reactive protein, alpha-1 antitrypsin, alpha-1 acid glycoprotein, transferrin) were measured by competitive ELISA. In the 0.1 Gy irradiated rats, serum haptoglobin, C-reactive protein and alpha-1 antitrypsin were 400% higher and serum transferrin was 50% lower as compared to controls, 96 hours after irradiation. Ceruloplasmin increased by 400%, 24 hours after irradiation, but 96 hours after irradiation, the concentration of this protein in rat returned to normal level. On the other hand, no changes were observed in the case of alpha-1 acid glycoprotein. In the group of the 3.0 Gy irradiated rats, transferrin increased by 200%, 96 hours after irradiation. These biochemical responses to radiation did not show dose-dependent relation, but the sensitivity of the indicators was high enough to detect absorbed dose of 0.1 Gy. The above results can be applied to the measurements of acute phase reactants in human serum for the assessment of exposure doses in radiation workers and patients under radiation therapy. 39 figs, 72 refs. (Author).

  10. Dosimetry and Shielding of X and Gamma Radiation

    International Nuclear Information System (INIS)

    Oncescu, M.; Panaitescu, I.

    1992-01-01

    This book covers the following problems: 1. X and Gamma radiations, 2. Interaction of X-ray and gamma radiations with matter, 3. Interaction of electrons with matter, 4. Principles and basic concepts of dosimetry, 5. Ionization dosimetry, 6. Calorimetric chemical and photographic dosimetry, 7. Solid state dosimetry, 8. Computation of dosimetric quantities, 9. Dosimetry in radiation protection, 10. Shielding of X and gamma radiations. The authors, well-known Romanian experts in Radiation Physics and Engineering, gave an up-dated, complete and readable account of this subject matter. The analyses of physical principles and concepts, of materials and instruments and of computational methods and applications are all well balanced to meat the needs of a broad readership

  11. Collection of abstracts. 6. national symposium on radiation dosimetry

    International Nuclear Information System (INIS)

    1983-08-01

    Abstracts are given of the total of 137 papers presented at the symposium. The papers discussed radiation dosimetry methods, dosemeters and detectors, the metrology and calibration of radiation sources, calibration standards, and radioactivity monitoring. (J.P.)

  12. Radiation dosimetry in nuclear medicine - recent developments

    International Nuclear Information System (INIS)

    Hetherington, E.L.R.; Wood, N.R.

    1976-01-01

    This paper reviews developments in radiation dosimetry in Nuclear Medicine over the past few years. The practical scope of the Medical Internal Radiation Dose (MIRD) Committee's Schema for dose determination has been extended by the development of more realistic mathematical models of the human body, together with the improvement in basic physical data used in dose calculations. Apart from the use of the Adult Human Phantom as the basis for dose determination, models have been developed for the estimation of doses to children and to the developing foetus. The Schema has been extended to permit calculations of the dose to dynamic organs, particularly the bladder. The principle of Monte Carlo photon history simulation, which forms the basis of much of the MIRD Schema's published data, has been used at the Australian Atomic Energy Commission for the determination of complete photon dose distributions. These are more meaningful in many cases than the average doses determined by the absorbed fraction method. (author)

  13. Beta-particle dosimetry in radiation synovectomy

    International Nuclear Information System (INIS)

    Johnson, L.S.; Barnes, C.L.; Spitzer, A.I.; Sledge, C.B.

    1995-01-01

    Beta-particle dosimetry of various radionuclides used in the treatment of rheumatoid arthritis was estimated using Monte Carlo radiation transport simulation coupled with experiments using reactor-produced radionuclides and radiachromic film dosimeters inserted into joint phantoms and the knees of cadavers. Results are presented as absorbed dose factors (cGy-cm 2 /MBq-s) versus depth in a mathematical model of the rheumatoid joint which includes regions of bone, articular cartilage, joint capsule, and tissue (synovium) found in all synovial joints. The factors can be used to estimate absorbed dose and dose rate distributions in treated joints. In particular, guidance is provided for those interested in (a) a given radionuclide's therapeutic range, (b) the amount of radioactivity to administer on a case-by-case basis, (c) the expected therapeutic dose to synovium, and (d) the radiation dose imparted to other, nontarget components in the joint, including bone and articular cartilage. (orig.). With 6 figs., 6 tabs

  14. 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

  15. Progress in high-dose radiation dosimetry

    International Nuclear Information System (INIS)

    Ettinger, K.V.; Nam, J.W.; McLaughlin, W.L.; Chadwick, K.H.

    1981-01-01

    The last decade has witnessed a deluge of new high-dose dosimetry techniques and expanded applications of methods developed earlier. Many of the principal systems are calibrated by means of calorimetry, although production of heat is not always the final radiation effect of interest. Reference systems also include a number of chemical dose meters: ferrous sulphate, ferrous-cupric sulphate, and ceric sulphate acidic aqueous solutions. Requirements for stable and reliable transfer dose meters have led to further developments of several important high-dose systems: amino acids and saccharides analysed by ESR or lyoluminescence, thermoluminescent materials, radiochromic dyes and plastics, ceric-cerous solutions analysed by potentiometry, and ethanol-chlorobenzene solutions analysed by high-frequency oscillometry. A number of other prospective dose meters are also treated in this review. In addition, an IAEA programme of high-dose standardization and intercomparison for industrial radiation processing is described. (author)

  16. Quality control through dosimetry at a contract radiation processing facility

    International Nuclear Information System (INIS)

    Du Plessis, T.A.; Roediger, A.H.A.

    1985-01-01

    Reliable dosimetry procedures constitute a very important part of process control and quality assurance at a contract gamma radiation processing facility that caters for a large variety of different radiation applications. The choice, calibration and routine intercalibration of the dosimetry systems employed form the basis of a sound dosimetry policy in radiation processing. With the dosimetric procedures established, detailed dosimetric mapping of the irradiator upon commissioning (and whenever source modifications take place) is carried out to determine the radiation processing characteristics and peformance of the plant. Having established the irradiator parameters, routine dosimetry procedures, being part of the overall quality control measures, are employed. In addition to routine dosimetry, independent monitoring of routine dosimetry is performed on a bi-monthly basis and the results indicate a variation of better than 3%. On an annaul basis the dosimetry systems are intercalibrated through at least one primary standard dosimetry laboratory and to date a variation of better than 5% has been experienced. The company also participates in the Pilot Dose Assurance Service of the International Atomic Energy Agency, using the alanine/ESR dosimetry system. Routine calibration of the instrumentation employed is carried out on a regular basis. Detailed permanent records are compiled on all dosimetric and instrumentation calibrations, and the routine dosimetry employed at the plant. Certificates indicating the measured absorbed radiation doses are issued on request and in many cases are used for the dosimetric release of sterilized medical and pharmaceutical products. These procedures, used by Iso-Ster at its industrial gamma radiation facility, as well as the experience built up over a number of years using radiation dosimetry for process control and quality assurance are discussed. (author)

  17. EURADOS strategic research agenda: vision for dosimetry of ionising radiation

    International Nuclear Information System (INIS)

    Ruehm, W.; Woda, C.; Fantuzzi, E.; Harrison, R.; Schuhmacher, H.; Neumaier, S.; Vanhavere, F.; Alves, J.; Bottollier Depois, J.F.; Fattibene, P.; Knezevic, Z.; Miljanic, S.; Lopez, M. A.; Mayer, S.; Olko, P.; Stadtmann, H.; Tanner, R.

    2016-01-01

    Since autumn 2012, the European Radiation Dosimetry Group (EURADOS) has been developing its Strategic Research Agenda (SRA), which is intended to contribute to the identification of future research needs in radiation dosimetry in Europe. The present article summarises-based on input from EURADOS Working Groups (WGs) and Voting Members-five visions in dosimetry and defines key issues in dosimetry research that are considered important for the next decades. The five visions include scientific developments required towards (a) updated fundamental dose concepts and quantities, (b) improved radiation risk estimates deduced from epidemiological cohorts, (c) efficient dose assessment for radiological emergencies, (d) integrated personalised dosimetry in medical applications and (e) improved radiation protection of workers and the public. The SRA of EURADOS will be used as a guideline for future activities of the EURADOS WGs. A detailed version of the SRA can be downloaded as a EURADOS report from the EURADOS web site (www.eurados.org). (authors)

  18. Radiochromic dye film for ionizing and non ionizing radiation dosimetry

    International Nuclear Information System (INIS)

    Said, F.I.; Elbahay, A.Z.

    1984-01-01

    During the present study different types of radiochromic dye films have been investigated for γ-ray as well as ultraviolet radiation dosimetry. The technique is based on the change in absorption spectra for dosed samples with special emphasis at optical absorption bands observed at 510nm and 605nm. Dose response of different types of radiochromic dye films was determined in the range between 1 to 40 KGy γ rays. The technique is used for γ-ray dosimetry in processing with high quality. The increasing use of U.V. light in industry and medicine makes it necessary to have simple practical methods for U.V. dosimetry. To this purpose radiochromic dye films are suggested for the first time. The response was investigated for emission consisted mainly of 254 and 366nm photons over the range from 50-700 m W.S. cm -2 . The experimental results indicate that radiochromic dye films are practical and simple technique for γ-ray and U.V. dosimetry for industrial and medical applications

  19. Energy and entropy in radiation dosimetry and protection

    International Nuclear Information System (INIS)

    Oliveira, A.D.

    2006-01-01

    In this work we present and discuss a proposal to describe the degradation of the energy of photons when they interact with matter, which can be applied in radiation dosimetry and protection. Radiation dosimetry is founded in the well known physical approach of field theory as showed by Roesch and Rossi. Fluence and energy deposited are the most fundamental quantities in radiation dosimetry allowing us to calculate absorbed dose. One of the main characteristics of absorbed dose, sometimes ignored, is that it is an intensive quantity pushing radiation dosimetry into the field of statistical physics. In radiation dosimetry it is often used what we can call collective or macroscopic concepts, such as, for example, effective energy, beam quality or beam hardening and absorbed dose. Some of these concepts are trials to describe macroscopically and with simplicity what happens microscopically with a rather higher degree of complexity. In other words, is a tentative to make a bridge between the non continuous world of atoms and photons to the continuous world of radiation protection dosimetry. In computer simulations, that allow to known accurately the energy deposited in matter, absorbed dose (or fluence) is still a very useful and used quantity; however, some issues are still open problems, source of many discussions in conferences and journals in spite of the development of microdosimetry and nano-dosimetry. In spite of that, macroscopic quantities like absorbed dose are still important quantities. One of the important and controversial open question in biological effects at low doses is the linear no threshold concept (L.N.T.). In our opinion this problem is directly related with the problem mentioned above of the bridge between microscopic and macroscopic concepts. Actually, the extrapolation to low dose region is a good expression of the challenge we have to deal in order to make the connections between both worlds, the discrete micro-world to the continuous macro

  20. Dissolution rate and radiation dosimetry of metal tritides

    International Nuclear Information System (INIS)

    Jow, Hong-Nian; Cheng, Yung-Sung

    1993-01-01

    Metal tritides including titanium tritide (Ti 3 H x ) and erbium tritide (Er 3 H x ) have been used as components of neutron generators. These compounds can be released to the air as aerosols during fabrication, assembling and testing of components or in accidental or fugitive releases. As a result, workers could be exposed to these compounds by inhalation. A joint research project between SNL and ITRI (Inhalation Toxicology Research Institute) was initiated last fall to investigate the solubility of metal tritides, retention and translocation of inhaled particles and internal dosimetry of metal tritides. The current understanding of metal tritides and their radiation dosimetry for internal exposure are very limited. There is no provision in the ICRP-30 for tritium dosimetry in metal tritide form. However, a few papers in the literature suggested that the solubility of metal tritide could be low. The current radiation protection guidelines for metal tritide particles are based on the assumption that the biological behavior is similar to tritiated water which behaves like body fluid with a relative short biological half life (10 days). If the solubility of metal tritide is low, the biological half life of metal tritide particles and the dosimetry of inhalation exposure to these particles could be quite different from tritiated water. This would have major implications in current radiation protection guidelines for metal tritides Including annual limits of intakes and derived air concentrations. The preliminary results of metal tritide dissolution study at ITRI indicate that the solubility of titanium tritide is low. The outlines of the project, the preliminary results and future work will be discussed in presentation

  1. Semiconductor dosimetry system for gamma and neutron radiation

    International Nuclear Information System (INIS)

    Savic, Z.; Pavlovic, Z.

    1995-01-01

    The semiconductor dosimetry system for gamma and neutron radiation based on pMOS transistor and PIN diode is described. It is intended for tactical or accidental personal dosimetry. The production steps are given. The temperature, dose and time (fading) response are reported. Hardware and software requirements which are needed for obtaining the desired measurement error are pointed. (author)

  2. Present status and expected progress in radiation processing dosimetry

    DEFF Research Database (Denmark)

    Kovács, A.; Miller, A.

    2004-01-01

    The paper describes the present status of radiation processing dosimetry including the methods used most widely in gamma- and electron processing as well as the new methods under development or introduction. The recent trends with respect to calibrationof routine dosimetry systems as well...

  3. Reassessment of the atomic bomb radiation dosimetry for Hiroshima and Nagasaki. Dosimetry system 2002. DS02. Volume 1

    International Nuclear Information System (INIS)

    Young, Robert W.; Kerr, George D.

    2005-01-01

    The extensive efforts to review the dosimetry of the atomic-bomb survivors and formulate the new dosimetry system DS02 have been greatly welcomed by the Radiation Effects Research Foundation (RERF). This accomplishment is a fine tribute to the importance of the epidemiological studies being conducted at RERF. No other study is so informative of the effects of radiation on human health. The gracious participation in the RERF program by the atomic-bomb survivors allows us to contribute to the well being of these individuals, and the high quality of the data obtained allows the RERF results to feature so prominently in the formulation of international guidelines for radiation protection. Such a great effort to improve and substantiate the dosimetry would not otherwise have been justified. RERF greatly appreciates the independent work of the U.S. and Japanese Working Groups on the atomic-bomb dosimetry and the review by the Joint Senior Review Group of this overall effort. We are assured that unbiased development of the new dosimetry system will reflect well in its application in the RERF epidemiology study. The documentation included in this report will serve as reference for the many deliberations concluded. The title publications are divided into 2 volumes. This is the first volume. The 8 of the reports in each chapter are indexed individually. (J.P.N.)

  4. Reassessment of the atomic bomb radiation dosimetry for Hiroshima and Nagasaki. Dosimetry system 2002. DS02. Volume 2

    International Nuclear Information System (INIS)

    Young, Robert W.; Kerr, George D.

    2005-01-01

    The extensive efforts to review the dosimetry of the atomic-bomb survivors and formulate the new dosimetry system DS02 have been greatly welcomed by the Radiation Effects Research Foundation (RERF). This accomplishment is a fine tribute to the importance of the epidemiological studies being conducted at RERF. No other study is so informative of the effects of radiation on human health. The gracious participation in the RERF program by the atomic-bomb survivors allows us to contribute to the well being of these individuals, and the high quality of the data obtained allows the RERF results to feature so prominently in the formulation of international guidelines for radiation protection. Such a great effort to improve and substantiate the dosimetry would not otherwise have been justified. RERF greatly appreciates the independent work of the U.S. and Japanese Working Groups on the atomic-bomb dosimetry and the review by the Joint Senior Review Group of this overall effort. We are assured that unbiased development of the new dosimetry system will reflect well in its application in the RERF epidemiology study. The documentation included in this report will serve as reference for the many deliberations concluded. The title publications are divided into 2 volumes. This is the second volume. The 29 of the reports in each chapter are indexed individually. (J.P.N.)

  5. Electron paramagnetic resonance biophysical radiation dosimetry with tooth enamel

    International Nuclear Information System (INIS)

    Khan, Rao F.H.

    2003-01-01

    This thesis deals with the advancements made in the field of Electron Paramagnetic Resonance (EPR) for biophysical dosimetry with tooth enamel for accident, emergency, and retrospective radiation dose reconstruction. A methodology has been developed to measure retrospective radiation exposures in human tooth enamel. This entails novel sample preparation procedures with minimum mechanical treatment to reduce the preparation induced uncertainties, establish optimum measurement conditions inside the EPR cavity, post-process the measured spectrum with functional simulation of dosimetric and other interfering signals, and reconstruct dose. By using this technique, retrospective gamma exposures as low as 80±30 mGy have been successfully deciphered. The notion of dose modifier was introduced in EPR biodosimetry for low dose measurements. It has been demonstrated that by using the modified zero added dose (MZAD) technique for low radiation exposures, doses in 100 mGy ranges can be easily reconstructed in teeth that were previously thought useless for EPR dosimetry. Also, the use of a dose modifier makes robust dose reconstruction possible for higher radiation exposures. The EPR dosimetry technique was also developed for tooth samples extracted from rodents, which represent small tooth sizing. EPR doses in the molars, extracted from the mice irradiated with whole body exposures, were reassessed and shown to be correct within the experimental uncertainty. The sensitivity of human tooth enamel for neutron irradiation, obtained from the 3 MV McMaster K.N. Van de Graaff accelerator, was also studied. For the first time this work has shown that the neutron sensitivity of the tooth enamel is approximately 1/10th of the equivalent gamma sensitivity. Parametric studies for neutron dose rate and neutron energy within the available range of the accelerator, showed no impact on the sensitivity of the tooth enamel. Therefore, tooth enamel can be used as a dosimeter for both neutrons

  6. Proceedings of the recent developments in radiation dosimetry

    International Nuclear Information System (INIS)

    Bhat, Nagesh; Palani Selvan, T.

    2016-01-01

    Whilst 'Dosimetry' in its original sense deals with methods for a quantitative determination of energy deposited in a given medium by directly or indirectly ionizing radiations, the term is better known as a scientific sub-specialty in the fields of health physics and medical physics, where it is the calculation and assessment of the radiation dose received by the human body. Dosimetry is used extensively for radiation protection and is routinely applied to ensure radiological safety of occupational radiation workers. Internal dosimetry due to the ingestion or inhalation of radioactive materials relies on a variety of physiological or imaging techniques. External dosimetry, due to irradiation from an external source is based on measurements with a dosimeter, or inferred from other radiological protection instruments. Radiation dosimetry is one of the important research areas of Department of Atomic Energy (DAE). This research work is centered on the facilities such as nuclear reactors, reprocessing plants, high energy accelerators (research/industry/medical), radiation standards, food processing, radiation technology development, etc. In each of these facilities, radiation field environment is different and the associated dosimetry concepts are different. Papers relevant to INIS are indexed separately

  7. Advances on radiation protection dosimetry research, development and services at AEOI

    International Nuclear Information System (INIS)

    Sohrabi, M.

    1993-01-01

    Radiation dosimetry is the main counterpart of an effective national radiation protection program to protect radiation workers, public and the environment against harmful effects of radiation. Research and development on radiation dosimetry are of vital needs to support national dosimetry services. The National Radiation Protection Department (NRPD) of the Atomic Energy Organization of Iran (AEOI) being a National Authority on radiation protection is also responsible for radiation dosimetry research, development and services. Some highlights of such activities at NRPD are reviewed and discussed

  8. Fourier transform Raman spectroscopy of polyacrylamide gels for radiation dosimetry

    International Nuclear Information System (INIS)

    Baldock, C.; Murry, P.; Pope, J.; Rintoul, L.; George, G.

    1998-01-01

    Polyacrylamide (PAG) gels are used in magnetic resonance imaging radiation dosimetry. The PAG dosimeter is based on the radiation-induced co-polymerisation and cross-linking of acrylic monomers infused in a gel matrix. PAG was manufactured with a composition of 5% gelatine, 3% acrylamide and 3% N,N'methylene-bis-acrylamide by mass, with distilled water as the remaining constituent [Baldock, 1998]. FT-Raman spectroscopy studies were undertaken to investigate cross-linking changes during the co-polymerisation of PAG in the spectral range of 200 - 3500 cm -1 . Vibrational bands of 1285 cm -1 and 1256 cm -1 were assigned to the acrylamide and bis-acrylamide single CH 2 δ CH2 binding modes. These bands were found to decrease in amplitude with increasing absorbed radiation dose, as a result of co-polymerisation. Principal Component Regression was performed on FT-Raman spectra of PAG samples irradiated to 50 Gy and two components were found to be sufficient to account for 98.7% of variance in the data. Cross validation was used to establish the absorbed radiation dose of an unknown PAG sample from the FT-Raman spectra. The calculated correlation coefficient between measured and predictive samples was 0.997 with a standard error of estimate of 0.976 and a standard error of prediction of 1.140. These results demonstrate the potential of FT-Raman spectroscopy for ionising radiation dosimetry using polyacrylamide gels

  9. Dosimetry services for internal and external radiation sources

    International Nuclear Information System (INIS)

    1988-01-01

    The Canadian Atomic Energy Control Board (AECB) sets radiation dose limits for the operation of nuclear facilities and the possession of prescribed substances within Canada. To administer these regulations the AECB must be satisfied that the dosimetry services used by a licensee meet adequate standards. Licensees are required to use the Occupational Dosimetry Service operated by the Bureau of Radiation and Medical Devices, Department of National Health and Welfare (BRMD) to determine doses from external sources of radiation, except where a detailed rationale is given for using another service. No national dosimetry service exists for internal sources of radiation. Licensees who operate or use a dosimetry service other than the BRMD must provide the AECB with evidence of the competence of the staff and adequacy of the equipment, techniques and procedures; provide the AECB with evidence that a quality assurance program has been implemented; and send individual dose or exposure data to the National Dose Registry. (L.L.)

  10. In vivo dosimetry in radiation therapy in Sweden; In vivo-dosimetri inom straalbehandling i Sverige

    Energy Technology Data Exchange (ETDEWEB)

    Eriksson, Jacob; Blomquist, Michael (Norrlands universitetssjukhus, Umeaa (Sweden))

    2010-07-15

    A prerequisite for achieving high radiation safety for patients receiving external beam radiation therapy is that the hospitals have a quality assurance program. The program should include include monitoring of the radiation dose given to the patient. Control measurements are performed both at the system level and at the individual level. Control measurement is normally performed using in vivo dosimetry, e.g. a method to measure the radiation dose at the individual level during the actual radiation treatment time. In vivo dosimetry has proven to be an important tool to detect and prevent serious errors in patient treatment. The purpose of this research project was to identify the extent to which vivo dosimetry is used and the methods available for this at Swedish radiation therapy clinics. The authority also wanted to get an overall picture of how hospitals manage results of in vivo dosimetry, and how clinics control radiation dose when using modern treatment techniques. The report reflects the situation in Swedish radiotherapy clinics 2007. The report shows that all hospitals use some form of in vivo dosimetry. The instruments used are mainly diodes and termoluminiscence dosimeters

  11. Biodistribution, toxicity and radiation dosimetry studies of the serotonin transporter radioligand 4-[{sup 18}F]-ADAM in rats and monkeys

    Energy Technology Data Exchange (ETDEWEB)

    Huang, Ya-Yao [Tri-Service General Hospital, PET Center, Department of Nuclear Medicine, Taipei (China); National Tsing Hua University, Department of Biomedical Engineering and Environmental Sciences, Hsinchu (China); Ma, Kuo-Hsing [National Defense Medical Center, Department of Biology and Anatomy, Taipei (China); Tseng, Ta-Wei; Chou, Ta-Kai; Huang, Wen-Sheng [Tri-Service General Hospital, PET Center, Department of Nuclear Medicine, Taipei (China); Ng, Hanna; Mirsalis, Jon C. [SRI International, Menlo Park, CA (United States); Fu, Ying-Kai [Institute of Nuclear Energy Research, Taoyuan (China); Chung Yuan Christian University, Department of Chemistry, Chung-Li (China); Chu, Tieh-Chi [National Tsing Hua University, Department of Biomedical Engineering and Environmental Sciences, Hsinchu (China); Yuanpei University, Department of Radiological Technology, Hsinchu (China); Shiue, Chyng-Yann [Tri-Service General Hospital, PET Center, Department of Nuclear Medicine, Taipei (China); University of Pennsylvania, Department of Radiology, Philadelphia, PA (United States)

    2010-03-15

    4-[{sup 18}F]-ADAM is a potent serotonin transport imaging agent. We studied its toxicity in rats and radiation dosimetry in monkeys before human studies are undertaken. Single and multiple-dosage toxicity studies were conducted in Sprague-Dawley rats. Male and female rats were injected intravenously with 4-F-ADAM as a single dose of 1,023.7 {mu}g/kg (1,000 times the human dose) or as five consecutive daily doses of 102.37 {mu}g/kg (100 times the human dose). PET/CT scans were performed in seven Formosa Rock monkeys (four males and three females) using a Siemens Biograph scanner. After injection of 4-[{sup 18}F]-ADAM (182{+-}8 MBq), a low dose CT scan and a series of eight whole-body PET scans were performed. Whole-body images were acquired in 3-D mode. Time-activity data of source organs were used to calculate the residence times and estimate the absorbed radiation dose using OLINDA/EXM software. In the rats neither the single dose nor the five daily doses of 4-F-ADAM produced overt adverse effects clinically. In the monkeys the radiation doses received by most organs ranged between 7.1 and 35.7 {mu}Gy/MBq, and the urinary bladder was considered to be the critical organ. The effective doses extrapolated to male and female adult humans were 17.4 and 21.8 {mu}Sv/MBq, respectively. Toxicity studies in Sprague-Dawley rats and radiation dosimetry studies in Formosa Rock monkeys suggested that 4-[{sup 18}F]-ADAM is safe for use in human PET imaging studies. (orig.)

  12. Radiation dosimetry by neutron or X ray fluorescence activation of residual silver in ionographic emulsions

    International Nuclear Information System (INIS)

    Heilmann, C.

    1987-01-01

    A global measuring technique which is sensitive enough to detect small silver contents in films for dosimetry applications is presented. The applications studied are neutron dosimetry by measuring residual silver due to recoil protons in developed emulsions and high dose dosimetry by the detection of photolytic silver in fixed emulsions. An individual fast neutron dosimeter which can be used in radiation protection was developed, along with an automatic data analysis and readout system. Application of this technique to the measurement of high radiation doses (100 to 1 million Gy) via the measurement of photolytic silver in fixed, but undeveloped, emulsions confirms the usefulness of the method [fr

  13. Physicochemical studies on some new thin films based on diacetylene materials for possible use in radiation processing dosimetry

    International Nuclear Information System (INIS)

    Bayomi, A.M.M.

    2014-01-01

    The aim of the present thesis was to develop new thin radiochromic films, self-adhesive labels, radiation indicators, and gel dosimeters based on some conjugated diacetylene derivatives, as radiation-sensitive components, for radiation processing dosimetry. The diacetylene derivatives used were synthesized first in the laboratory then they were introduced in various mixtures to prepare the dosimeters and labels. The first part of the present thesis includes the synthesis of conjugated diacetylene monomer of 2,4-hexadiyne-1,6-bis(n-butyl urethane) (HDDBU) and the introduction of this monomer into poly(vinyl butyral) (PVB) organic solutions with different concentrations (chapter 4.1.). The prepared PVB solutions were then coated on flexible polyester sheets to prepare a thin film dosimeter. This film was investigated in the dose range of 3-150 kGy by UV-Vis spectrophotometer in the spectrum range of 200-400 nm for potential use in radiation dose process control. Additionally, the x-ray diffraction (XRD) analysis of the synthesized HDDBU monomer and the PVB film containing HDDBU has been performed. In PVB film, HDDBU monomer polymerizes under gamma radiation inducing change in the UV-Vis absorption spectra of the film. The spectrum of unirradiated films featured three absorption bands at 233 nm, 245 nm, and 259 nm, which are characteristic of the diacetylene chromofore. The intensity of these bands grows with the radiation dose without any shift in their position. In addition, two new absorption bands, namely, 273 nm and 285 nm develop upon irradiation, and their intensities increase proportionally with increasing absorbed dose. According to XRD spectroscopy, HDDBU monomer was in a non-crystalline state when it was mixed into PVB film. The PVB film with appropriate concentrations of HDDBU can be used for dose measurements in the range 3 - 150 kGy. They are suitable for use in monitoring various industrial processes, such as food irradiation, radiation sterilization of

  14. Dosimetry studies in Japan

    International Nuclear Information System (INIS)

    Maruyama, T.; Kumamoto, Y.; Hashizume, T.

    1982-01-01

    In 1967 the National Institute of Radiological Sciences in Chiba estimated the radiation doses in air from the atomic bombing of Hiroshima and Nagasaki by using some building materials exposed to the nuclear explosions in both cities. These estimated doses were in good agreement with the doses estimated on the basis of the Ichiban project by the research group at Oak Ridge National Laboratory which were the basis for the Atomic Bomb Casualty Commission's tentative 1965 radiation dose (T65D). Recently the radiation doses in Hiroshima and Nagasaki have been reevaluated by Lawrence Livermore National Laboratory and Oak Ridge National Laboratory. In Japan a new research group was started last August, with the intention of making new estimates of doses from the atomic bombs in cooperation with US research groups

  15. 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.

  16. Review of retrospective dosimetry techniques for external ionising radiation exposures

    International Nuclear Information System (INIS)

    Ainsbury, E. A.; Bakhanova, E.; Barquinero, J. F.; Brai, M.; Chumak, V.; Correcher, V.; Darroudi, F.; Fattibene, P.; Gruel, G.; Guclu, I.; Horn, S.; Jaworska, A.; Kulka, U.; Lindholm, C.; Lloyd, D.; Longo, A.; Marrale, M.; Monteiro Gil, O.; Oestreicher, U.; Pajic, J.; Rakic, B.; Romm, H.; Trompier, F.; Veronese, I.; Voisin, P.; Vral, A.; Whitehouse, C. A.; Wieser, A.; Woda, C.; Wojcik, A.; Rothkamm, K.

    2011-01-01

    The current focus on networking and mutual assistance in the management of radiation accidents or incidents has demonstrated the importance of a joined-up approach in physical and biological dosimetry. To this end, the European Radiation Dosimetry Working Group 10 on 'Retrospective Dosimetry' has been set up by individuals from a wide range of disciplines across Europe. Here, established and emerging dosimetry methods are reviewed, which can be used immediately and retrospectively following external ionising radiation exposure. Endpoints and assays include dicentrics, translocations, premature chromosome condensation, micronuclei, somatic mutations, gene expression, electron paramagnetic resonance, thermoluminescence, optically stimulated luminescence, neutron activation, haematology, protein biomarkers and analytical dose reconstruction. Individual characteristics of these techniques, their limitations and potential for further development are reviewed, and their usefulness in specific exposure scenarios is discussed. Whilst no single technique fulfils the criteria of an ideal dosemeter, an integrated approach using multiple techniques tailored to the exposure scenario can cover most requirements. (authors)

  17. 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

  18. Quality audit service of the IAEA for radiation processing dosimetry

    International Nuclear Information System (INIS)

    Mehta, K.; Girzikowsky, R.

    1996-01-01

    The mandate of the International Atomic Energy Agency includes assistance to Member States to establish nuclear technologies safely and effectively. In pursuit of this, a quality audit service for dosimetry relevant to radiation processing was initiated as a key element of the High-Dose Standardization Programme of the IAEA. The standardization of dosimetry for radiation processing provides a justification for the regulatory approval of irradiated products and their unrestricted international trade. In recent times, the Agency's Dosimetry Laboratory has placed concentrated effort towards establishing a quality assurance programme based on the ISO 9000 series documents. The need for reliable and accurate dosimetry for radiation processing is increasing in Member States and we can envisage a definite role for the SSDLs in such a programme. (author). 10 refs, 3 figs

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

    International Nuclear Information System (INIS)

    Lee, Sang Yoon

    2000-02-01

    High quality radiation dosimetry is for workers who rely upon personal dosimeters to record the amount of radiation to which they are exposed. Radiation physicists have been exploring thermoluminescence dosimeter (TLD) for personal monitoring since the mid 1960s, although, widespread use has only occurred in the last 20 years as automated analytical systems and high quality TLD crystals became commercially available. nowadays, multiple TLD (thermoluminescence dosimeter) chips with appropriate physical filters are generally used for measurements of the personal dose equivalent quantities, H p (d). Though the TLD offers several advantages not possessed by radiological film, it does not offer the some type of advantages as films: re-analysis of an exposure situation is prohibited because the analysis process clears all of the useful dosimetric traps and a record of the luminescence intensity in the form of a glow curve is all that is available after analysis. In addition, the high heating temperatures restrict packaging methods and prevent competitively priced thin films of TLD crystal powders. Optically stimulated luminescence (OSL) technology avoids many engineering limitations imposed by the high heating temperatures used for TLD technology. OSL crystalline powders can be dispersed in various plastics unable to withstand the TLD heating regimen. With uniform dispersion in the plastic, mass-manufacturing techniques can produce large quantities of identically performing detectors. The first proposal conducted by Markey et al. for applications and potentials of α-AI 2 O 3 :C for OSL dosimetry opened a new era for this phosphor. Pulsed and continuous wave OSL studies carried out on α-AI 2 O 3 :C have shown that the material seems to be the most promising for routine application of OSL for dosimetric purposes. The main objective of this study is to develop a multi-area personal OSL dosimetry system using α-AI 2 O 3 :C by taking advantage of its optical properties and

  20. Ionizing radiations dosimetry: new results in the megagray range

    International Nuclear Information System (INIS)

    Balian, P.

    1989-01-01

    Industrial irradiation for food preservation, medical sterilization and plastic processing is in great expansion and an accurate dosimetry in the megagray range is required. It is also required for safety purposes around nuclear reactors or waste storage sites. The study of photon-matter interaction leads us to consider high-dose dosimeters among the solids in which radiolysis occurs. Organic conductors are indeed good candidates for high-dose dosimetry. These materials show original properties due to the great anisotropy of their electronic system. Radiation effects, especially on the resistivity and on the (E.S.R.) Electron Spin Resonance linewidth, are very important. We show that a simple resistance measurement allows an accurate monitoring of the absorbed dose, in the range 0.01 - 50 MGy, for X-rays, gamma-rays and electron irradiations. The E.S.R. linewidth measurements permits the use of small dosimeters between 1 and 100 MGy. Finally, some organic conductors are proposed as high-temperature dosimeters for irradiation performed up to 120 0 C. The irradiated pure silica contains a large variety of defects. Only the E' center seems helpful for dosimetry purposes, and its electron spin resonance (E.S.R.) signal is simply related to the absorbed dose in the range 0.1 - 3 MGy or even, 0.5 kGy - 5 MGy [fr

  1. Modelling of a holographic interferometry based calorimeter for radiation dosimetry

    Science.gov (United States)

    Beigzadeh, A. M.; Vaziri, M. R. Rashidian; Ziaie, F.

    2017-08-01

    In this research work, a model for predicting the behaviour of holographic interferometry based calorimeters for radiation dosimetry is introduced. Using this technique for radiation dosimetry via measuring the variations of refractive index due to energy deposition of radiation has several considerable advantages such as extreme sensitivity and ability of working without normally used temperature sensors that disturb the radiation field. We have shown that the results of our model are in good agreement with the experiments performed by other researchers under the same conditions. This model also reveals that these types of calorimeters have the additional and considerable merits of transforming the dose distribution to a set of discernible interference fringes.

  2. General specifications for silicon semiconductors for use in radiation dosimetry

    International Nuclear Information System (INIS)

    Rikner, G.; Grusell, E.

    1987-01-01

    Silicon semiconductor detectors used in radiation dosimetry have different properties, just as e.g. ionisation chambers, affecting the interaction of radiation with matter in the vicinity of the sensitive volume of the detector, e.g. wall materials, and also the collection of the charges liberated in the detector by the radiation. The charge collection depends on impurities, lattice imperfections and other properties of the semiconductor crystal. In this paper the relevant parameters of a silicon semiconductor detector intended for dosimetry are reviewed. The influence of doping material, doping level, various effects of radiation damage, mechanical construction, detector size, statistical noise and connection to the electrometer are discussed. (author)

  3. Properties of an extrapolation chamber for beta radiation dosimetry

    International Nuclear Information System (INIS)

    Caldas, L.V.E.

    The properties of a commercial extrapolation chamber were studied, and the possibility is shown of its use in beta radiation dosimetry. The chamber calibration factors were determined for several sources ( 90 Sr, 90 Y- 204 Tl and 147 Pm) making known the dependence of its response on the energy of the incident radiation. Extrapolation curves allow to obtain independence on energy for each source. One of such curves, shown for the 90 Sr- 90 Y source at 50 cm from the detector, is obtained through the variation of the chamber window thickness and the extrapolation to the null distance (determined graphically). Different curves shown also: 1) the dependence of the calibration factor on the average energy of beta radiation; 2) the variation of ionization current with the distance between the chamber and the sources; 3) the effect of the collecting electrode area on the value of calibration factors for the different sources. (I.C.R.) [pt

  4. In vivo dosimetry in radiation therapy in Sweden

    International Nuclear Information System (INIS)

    Eriksson, Jacob; Blomquist, Michael

    2010-07-01

    A prerequisite for achieving high radiation safety for patients receiving external beam radiation therapy is that the hospitals have a quality assurance program. The program should include include monitoring of the radiation dose given to the patient. Control measurements are performed both at the system level and at the individual level. Control measurement is normally performed using in vivo dosimetry, e.g. a method to measure the radiation dose at the individual level during the actual radiation treatment time. In vivo dosimetry has proven to be an important tool to detect and prevent serious errors in patient treatment. The purpose of this research project was to identify the extent to which vivo dosimetry is used and the methods available for this at Swedish radiation therapy clinics. The authority also wanted to get an overall picture of how hospitals manage results of in vivo dosimetry, and how clinics control radiation dose when using modern treatment techniques. The report reflects the situation in Swedish radiotherapy clinics 2007. The report shows that all hospitals use some form of in vivo dosimetry. The instruments used are mainly diodes and termoluminiscence dosimeters

  5. Human biodistribution and radiation dosimetry of 82Rb.

    Science.gov (United States)

    Senthamizhchelvan, Srinivasan; Bravo, Paco E; Esaias, Caroline; Lodge, Martin A; Merrill, Jennifer; Hobbs, Robert F; Sgouros, George; Bengel, Frank M

    2010-10-01

    Prior estimates of radiation-absorbed doses from (82)Rb, a frequently used PET perfusion tracer, yielded discrepant results. We reevaluated (82)Rb dosimetry using human in vivo biokinetic measurements. Ten healthy volunteers underwent dynamic PET/CT (6 contiguous table positions, each with separate (82)Rb infusion). Source organ volumes of interest were delineated on the CT images and transferred to the PET images to obtain time-integrated activity coefficients. Radiation doses were estimated using OLINDA/EXM 1.0. The highest mean absorbed organ doses (μGy/MBq) were observed for the kidneys (5.81), heart wall (3.86), and lungs (2.96). Mean effective doses were 1.11 ± 0.22 and 1.26 ± 0.20 μSv/MBq using the tissue-weighting factors of the International Commission on Radiological Protection (ICRP), publications 60 and 103, respectively. Our current (82)Rb dosimetry suggests reasonably low radiation exposure. On the basis of this study, a clinical (82)Rb injection of 2 × 1,480 MBq (80 mCi) would result in a mean effective dose of 3.7 mSv using the weighting factors of the ICRP 103-only slightly above the average annual natural background exposure in the United States (3.1 mSv).

  6. Applications of Cherenkov Light Emission for Dosimetry in Radiation Therapy

    Science.gov (United States)

    Glaser, Adam Kenneth

    Since its discovery in the 1930's, the Cherenkov effect has been paramount in the development of high-energy physics research. It results in light emission from charged particles traveling faster than the local speed of light in a dielectric medium. The ability of this emitted light to describe a charged particle's trajectory, energy, velocity, and mass has allowed scientists to study subatomic particles, detect neutrinos, and explore the properties of interstellar matter. However, only recently has the phenomenon been considered in the practical context of medical physics and radiation therapy dosimetry, where Cherenkov light is induced by clinical x-ray photon, electron, and proton beams. To investigate the relationship between this phenomenon and dose deposition, a Monte Carlo plug-in was developed within the Geant4 architecture for medically-oriented simulations (GAMOS) to simulate radiation-induced optical emission in biological media. Using this simulation framework, it was determined that Cherenkov light emission may be well suited for radiation dosimetry of clinically used x-ray photon beams. To advance this application, several novel techniques were implemented to realize the maximum potential of the signal, such as time-gating for maximizing the signal to noise ratio (SNR) and Cherenkov-excited fluorescence for generating isotropic light release in water. Proof of concept experiments were conducted in water tanks to demonstrate the feasibility of the proposed method for two-dimensional (2D) projection imaging, three-dimensional (3D) parallel beam tomography, large field of view 3D cone beam tomography, and video-rate dynamic imaging of treatment plans for a number of common radiotherapy applications. The proposed dosimetry method was found to have a number of unique advantages, including but not limited to its non-invasive nature, water-equivalence, speed, high-resolution, ability to provide full 3D data, and potential to yield data in-vivo. Based on

  7. Study of the personal dosimetry service by thermoluminiscence

    International Nuclear Information System (INIS)

    Penaherrera, Patricio; Buitron, Susana; Prado, Elizabeth; Ceron Fabiola

    1992-01-01

    This paper is concerned with the personal dosimetry service given by the Ecuadorian Atomic Energy Commission to radiation exposed workers in Ecuador. The study has taken in consideration the number of professionals working in Ecuador by province and by area of work, and also the radiation doses received by them during the period 1987-1990

  8. Studies in dosimetry using stimulated exoelectron emission

    International Nuclear Information System (INIS)

    Petel, Maurice.

    1976-06-01

    Some applications of the stimulated exoelectron emission in radiation dosimetry are discussed. The principles which govern the phenomenon are presented. The apparatus, in particular the counter, used to monitor the emission is discussed with reference to both optical and thermal stimulation. The correlation existing between thermoluminescence and thermally stimulated exoelectron emission were studied in both lithium fluoride and aluminium oxide. Furthermore, aluminium oxides from different sources were examined, and one of these, chosen to investigate the dosimetric properties of this material using both methods of stimulation [fr

  9. 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)

  10. Radiation dosimetry using magnetic resonance imaging

    International Nuclear Information System (INIS)

    Olsson, L.E.

    1991-01-01

    A new dosimetry system for 3D dose distribution measurements based on the Fricke dosimeter and magnetic resonance imaging (MRI) has been developed. The dosimeter consists of a ferrous sulphate solution incorporated in an agarose gel, which together constitute the dosimeter gel. The absorbed dose to the gel is measured by means of the proton spin-lattice relaxation rate, 1/T1 in an MR scanner. The dose distribution to an arbitrary slice within a dosimeter gel phantom can thus be determined. The chemical yield of the dosimeter gel is significantly higher than that of the for Fricke solution, and is strongly dependent of the initial ferrous sulphate concentration, assuming that the gel is bubbled with oxygen during preparation. A gel of 1.5 mM [Fe 2+ ] and 50 mM [H 2 SO 4 ] has a sensitivity of 0.108 s -1 Gy -1 and is linear up to 50 Gy. The dosimeter gel has uniform dose response over large volumes. Above 50 mM[H 2 SO 4 ] the yield increases only slightly, but the gel strength decreases and results in gel phantoms with non-uniform dose response. Below 50 mM[H 2 SO 4 ] the sensitivity of the dosimeter falls rapidly due to the decreased relaxivity of the ferric ions. The high chemical yield can be explained by a chain reaction and a reaction scheme is accordingly proposed. The dosimeter gel shows no dependence on dose rate or radiation quality and can be regarded as water-equivalent with respect to the interaction of the radiation. The diffusion coefficient of the ferric ions in the agarose gel is 1.19x10 -2 cm 2 /h. The diffusion blurs the dosimeteric image, but poses only a minor problem if the MR measurements are completed within the first two hours after irradiation. Dose distribution data from external radiation therapy units have been determined using the dosimeter gel and MRI with good accuracy, but the precision is poor, about 5-10%. (au) (84 refs.)

  11. Radiation dosimetry onboard the International Space Station ISS

    Energy Technology Data Exchange (ETDEWEB)

    Berger, Thomas [German Aerospace Center - DLR, Inst. of Aerospace Medicine, Radiation Biology, Cologne (Germany)

    2008-07-01

    Besides the effects of the microgravity environment, and the psychological and psychosocial problems encountered in confined spaces, radiation is the main health detriment for long duration human space missions. The radiation environment encountered in space differs in nature front that on earth, consisting mostly of high energetic ions from protons up to iron, resulting in radiation levels far exceeding the ones encountered on earth for occupational radiation workers. Therefore the determination and the control of the radiation load on astronauts is a moral obligation of the space faring nations. The requirements for radiation detectors in space are very different to that on earth. Limitations in mass, power consumption and the complex nature of the space radiation environment define and limit the overall construction of radiation detectors. Radiation dosimetry onboard the International Space Station (ISS) is accomplished to one part as 'operational' dosimetry aiming for area monitoring of the radiation environment as well as astronaut surveillance. Another part focuses on 'scientific' dosimetry aiming for a better understanding of the radiation environment and its constitutes. Various research activities for a more detailed quantification of the radiation environment as well as its distribution in and outside the space station have been accomplished in the last years onboard the ISS. The paper will focus on the current radiation detectors onboard the ISS, their results, as well as on future planned activities. (orig.)

  12. Radiation dosimetry onboard the International Space Station ISS

    International Nuclear Information System (INIS)

    Berger, Thomas

    2008-01-01

    Besides the effects of the microgravity environment, and the psychological and psychosocial problems encountered in confined spaces, radiation is the main health detriment for long duration human space missions. The radiation environment encountered in space differs in nature front that on earth, consisting mostly of high energetic ions from protons up to iron, resulting in radiation levels far exceeding the ones encountered on earth for occupational radiation workers. Therefore the determination and the control of the radiation load on astronauts is a moral obligation of the space faring nations. The requirements for radiation detectors in space are very different to that on earth. Limitations in mass, power consumption and the complex nature of the space radiation environment define and limit the overall construction of radiation detectors. Radiation dosimetry onboard the International Space Station (ISS) is accomplished to one part as ''operational'' dosimetry aiming for area monitoring of the radiation environment as well as astronaut surveillance. Another part focuses on ''scientific'' dosimetry aiming for a better understanding of the radiation environment and its constitutes. Various research activities for a more detailed quantification of the radiation environment as well as its distribution in and outside the space station have been accomplished in the last years onboard the ISS. The paper will focus on the current radiation detectors onboard the ISS, their results, as well as on future planned activities. (orig.)

  13. Progress in reassessment of atomic bomb radiation dosimetry

    International Nuclear Information System (INIS)

    Kerr, G.D.

    1985-01-01

    Studies for reassessment of A-bomb radiation dosimetry in Hiroshima and Nagasaki are underway in both Japan and the US. The progress made in various reassessment studies has been reported at several US-Japan joint workshops. The medical follow-up studies by the RERF provide data on dose-related parameters such as the location of the survivors and their shielding by surrounding structures at the times of the bombings. To make accurate estimates of the radiation dose for individual survivors in the two cities, they need reliable information concerning (a) the hypocenters and burst heights of the bombs, (b) the energy yields of the bombs and the source terms for the initial radiations from the bombs, (c) the atmospheric radiation transport to determine the initial radiation fields at the location of the survivors, (d) the attenuation factors for shielding afforded by structures and terrain, and (e) the shielding of specific organs by overlying tissues of the body. A computer code combining the above elements has been installed at the RERF and used in a preliminary reassessment of radiation doses to survivors who were indoors, shielded by houses at the times of the bombings. These results will be presented and discussed. The discussions will be focused, however, on specific areas where binational agreement has been reached and on specific areas where additional work is needed before the reassessment can be considered final

  14. Radiation dosimetry by ESR in bone

    Energy Technology Data Exchange (ETDEWEB)

    Gallegos, R. (Universidad de San Agustin de Arequipa (Peru)); Marticorena, B. (Instituto Peruano de Energia Nuclear, Lima)

    1983-05-01

    The absorption speed in bovine bone samples irradiated with a /sup 90/Sr ..beta..-source of 45 mCi is studied with ESR. The signal changes linearly with the absorbed quantity of radiation to a maximum dose of 1.5 x 10/sup 6/ rads. This positive result allows to foresee the use of bone as a radiation dosimeter.

  15. Radiation dosimetry by ESR in bone

    International Nuclear Information System (INIS)

    Gallegos, R.; Marticorena, B.

    1983-01-01

    The absorption speed in bovine bone samples irradiated with a 90 Sr β-source of 45 mCi is studied with ESR. The signal changes linearly with the absorbed quantity of radiation to a maximum dose of 1.5 x 10 6 rads. This positive result allows to foresee the use of bone as a radiation dosimeter

  16. 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

  17. Radiation dosimetry of [(18)F]VAT in nonhuman primates.

    Science.gov (United States)

    Karimi, Morvarid; Tu, Zhude; Yue, Xuyi; Zhang, Xiang; Jin, Hongjun; Perlmutter, Joel S; Laforest, Richard

    2015-12-01

    The objective of this study is to determine the radiation dosimetry of a novel radiotracer for vesicular acetylcholine transporter (-)-(1-((2R,3R)-8-(2-[(18)F]fluoro-ethoxy)-3-hydroxy-1,2,3,4-tetrahydronaphthalen-2-yl)piperidin-4-yl)(4-fluorophenyl)-methanone ([(18)F]VAT) based on PET imaging in nonhuman primates. [(18)F]VAT has potential for investigation of neurological disorders including Alzheimer's disease, Parkinson's disease, and dystonia. Three macaque fascicularis (two males, one female) received 185.4-198.3 MBq [(18)F]VAT prior to whole-body imaging in a MicroPET-F220 scanner. Time activity curves (TACs) were created from regions of interest (ROIs) that encompassed the entire small organs or samples with the highest activity within large organs. Organ residence times were calculated based on the TACs. We then used OLINDA/EXM 1.1 to calculate human radiation dose estimates based on scaled organ residence times. Measurements from directly sampled arterial blood yielded a residence time of 0.30 h in agreement with the residence time of 0.39 h calculated from a PET-generated time activity curve measured in the left ventricle. Organ dosimetry revealed the liver as the critical organ (51.1 and 65.4 μGy/MBq) and an effective dose of 16 and 19 μSv/MBq for male and female, respectively. The macaque biodistribution data showed high retention of [(18)F]VAT in the liver consistent with hepatobiliary clearance. These dosimetry data support that relatively safe doses of [(18)F]VAT can be administered to obtain imaging in humans.

  18. Implementation of MRI gel dosimetry in radiation therapy

    International Nuclear Information System (INIS)

    Baeck, S.Aa.J.

    1998-12-01

    Gel dosimetry was used together with magnetic resonance imaging (MRI) to measure three-dimensional absorbed dose distributions in radiation therapy. Two different dosimeters were studied: ferrous- and monomer gel, based on the principles of radiation-induced oxidation and polymerisation, respectively. Single clinical electron and photon beams were evaluated and gel dose distributions were mainly within 2% of conventional detector results. The ferrous-gel was also used for clinical proton beams. A decrease in signal per absorbed dose was found close to the end of the range of the protons (15-20%). This effect was explained as a linear energy transfer dependence, further supported with Monte Carlo simulations. A method for analysing and comparing data from treatment planning system (TPS) and gel measurements was developed. The method enables a new pixel by pixel evaluation, isodose comparison and dose volume histogram verification. Two standard clinical radiation therapy procedures were examined using the developed TPS verification method. The treatment regimes included several beams of different radiation qualities. The TPS calculated data were in very good agreement with the dose distribution measured by the ferrous-gel. However, in a beam abutment region, larger dose difference was found. Beam adjustment errors and a minor TPS underestimation of the lateral scatter contribution outside the primary electron beam may explain the discrepancy. The overall uncertainty in the ferrous-gel dose determination was considerably reduced using an optimised MRI acquisition protocol and a new MRI scanner. The relative dose uncertainty was found to be better than 3.3% for all dose levels (95% confidence level). Using the method developed for comparing measured gel data with calculated treatment plans, the gel dosimetry method was proven to be a useful tool for radiation treatment planning verification

  19. Implementation of MRI gel dosimetry in radiation therapy

    Energy Technology Data Exchange (ETDEWEB)

    Baeck, S.Aa.J

    1998-12-01

    Gel dosimetry was used together with magnetic resonance imaging (MRI) to measure three-dimensional absorbed dose distributions in radiation therapy. Two different dosimeters were studied: ferrous- and monomer gel, based on the principles of radiation-induced oxidation and polymerisation, respectively. Single clinical electron and photon beams were evaluated and gel dose distributions were mainly within 2% of conventional detector results. The ferrous-gel was also used for clinical proton beams. A decrease in signal per absorbed dose was found close to the end of the range of the protons (15-20%). This effect was explained as a linear energy transfer dependence, further supported with Monte Carlo simulations. A method for analysing and comparing data from treatment planning system (TPS) and gel measurements was developed. The method enables a new pixel by pixel evaluation, isodose comparison and dose volume histogram verification. Two standard clinical radiation therapy procedures were examined using the developed TPS verification method. The treatment regimes included several beams of different radiation qualities. The TPS calculated data were in very good agreement with the dose distribution measured by the ferrous-gel. However, in a beam abutment region, larger dose difference was found. Beam adjustment errors and a minor TPS underestimation of the lateral scatter contribution outside the primary electron beam may explain the discrepancy. The overall uncertainty in the ferrous-gel dose determination was considerably reduced using an optimised MRI acquisition protocol and a new MRI scanner. The relative dose uncertainty was found to be better than 3.3% for all dose levels (95% confidence level). Using the method developed for comparing measured gel data with calculated treatment plans, the gel dosimetry method was proven to be a useful tool for radiation treatment planning verification 103 refs, 20 figs, 6 tabs

  20. Radiation protection and dosimetry issues in the medical applications of ionizing radiation

    International Nuclear Information System (INIS)

    Vaz, Pedro

    2014-01-01

    The technological advances that occurred during the last few decades paved the way to the dissemination of CT-based procedures in radiology, to an increasing number of procedures in interventional radiology and cardiology as well as to new techniques and hybrid modalities in nuclear medicine and in radiotherapy. These technological advances encompass the exposure of patients and medical staff to unprecedentedly high dose values that are a cause for concern due to the potential detrimental effects of ionizing radiation to the human health. As a consequence, new issues and challenges in radiological protection and dosimetry in the medical applications of ionizing radiation have emerged. The scientific knowledge of the radiosensitivity of individuals as a function of age, gender and other factors has also contributed to raising the awareness of scientists, medical staff, regulators, decision makers and other stakeholders (including the patients and the public) for the need to correctly and accurately assess the radiation induced long-term health effects after medical exposure. Pediatric exposures and their late effects became a cause of great concern. The scientific communities of experts involved in the study of the biological effects of ionizing radiation have made a strong case about the need to undertake low dose radiation research and the International System of Radiological Protection is being challenged to address and incorporate issues such as the individual sensitivities, the shape of dose–response relationship and tissue sensitivity for cancer and non-cancer effects. Some of the answers to the radiation protection and dosimetry issues and challenges in the medical applications of ionizing radiation lie in computational studies using Monte Carlo or hybrid methods to model and simulate particle transport in the organs and tissues of the human body. The development of sophisticated Monte Carlo computer programs and voxel phantoms paves the way to an accurate

  1. Some methods for calibration and beta radiation dosimetry

    International Nuclear Information System (INIS)

    Caldas, Linda V. Ehlin

    1980-01-01

    The calibration of beta radiation was studied from the point of view of primary and secondary standardization, using extrapolation chambers and examining several effects. The properties of a commercial ionization chamber were investigated, and the possibility of its use in calibration and dosimetry of 90 Sr- 90 Y beta radiation was demonstrated . A secondary standard calibration facility was developed and the results obtained with this facility were compared with those obtained from a primary system directly or indirectly. Nearly energy independent response was obtained in.the range 60 keV to 0,8 MeV with this secondary standard. Two solid state techniques namely thermoluminescence (TL) and thermally stimulated exoelectron emission (TSEE) were also used for beta dosimetry. Various characteristics like reproducibility, response with dose,energy dependence, etc. were studied for the materials: LiF, CaF 2 ,Li 2 B 4 O 7 , Be O, CaSO 4 and Al 2 O 3 . TL detectors of thickness 0,9 mm underestimate the dose 60 μm thick CaSO 4 :Tm embedded on a thin aluminium plate gave energy independent response behind skin layers of 7 mg/cm 2 . Mixed field of beta, X and gamma radiation was analysed using this detector. Quartz based Be O and graphite based alpha beta-Al 2 O 3 were found to be good beta radiation detectors when the TSEE technique is used. Energy independent CaSO 4 :Tm TL dosimeters were used in international comparison for dose measurements and the results obtained were in agreement with the actual given doses within 10%. The TL detectors were also used for dose rate measurements from glazed painted tiles used in construction industry and a 85 Kr source used in textile and metal industries. Results obtained in the later case were Q compared with those using the secondary standard facility. (author)

  2. EURADOS strategic research agenda: vision for dosimetry of ionising radiation.

    Science.gov (United States)

    Rühm, W; Fantuzzi, E; Harrison, R; Schuhmacher, H; Vanhavere, F; Alves, J; Bottollier Depois, J F; Fattibene, P; Knežević, Ž; Lopez, M A; Mayer, S; Miljanić, S; Neumaier, S; Olko, P; Stadtmann, H; Tanner, R; Woda, C

    2016-02-01

    Since autumn 2012, the European Radiation Dosimetry Group (EURADOS) has been developing its Strategic Research Agenda (SRA), which is intended to contribute to the identification of future research needs in radiation dosimetry in Europe. The present article summarises-based on input from EURADOS Working Groups (WGs) and Voting Members-five visions in dosimetry and defines key issues in dosimetry research that are considered important for the next decades. The five visions include scientific developments required towards (a) updated fundamental dose concepts and quantities, (b) improved radiation risk estimates deduced from epidemiological cohorts, (c) efficient dose assessment for radiological emergencies, (d) integrated personalised dosimetry in medical applications and (e) improved radiation protection of workers and the public. The SRA of EURADOS will be used as a guideline for future activities of the EURADOS WGs. A detailed version of the SRA can be downloaded as a EURADOS report from the EURADOS website (www.eurados.org). © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  3. Radiation chemical dosimetry by means of nitrate-nitrite

    International Nuclear Information System (INIS)

    Tormo Ferrero, M.J.

    1977-01-01

    The different chemical systems used in dosimetry and the selection criteria for them are described. The general topics in dosimetry with alkali nitrates as well as the phenomena occurring in their radiolisis are also treated. The possibility of application in dosimetric areas useful in radiosterilization and industrial processes is studied too. (author) [es

  4. Radiation chemical dosimetry by means of nitrate-nitrite

    International Nuclear Information System (INIS)

    Tormo Ferrero, M. J.

    1977-01-01

    The different chemical systems used in dosimetry and the selection criteria for them are described. The general topics in dosimetry with alkali nitrates as well as the phenomena occurring in their radiolysis are also treated. The possibility of application in dosimetric areas useful in radiosterilization and industrial processes is studied too. (Author) 22 refs

  5. 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

  6. A portable organic plastic scintillator dosimetry system for low energy X-rays: a feasibility study using an intraoperative X-ray unit as the radiation source

    International Nuclear Information System (INIS)

    Williams, Kerry; Robinson, Neil; Trapp, Jamie; Geso, Moshi; Ackerly, Trevor; Das, Ram; Kemp, Penny

    2007-01-01

    The effective use of near water equivalent organic plastic scintillators (OPS) for radiation dosimetry with high-energy sources under laboratory conditions is recognized. In this work, an OPS-based dosimeter using a photodiode combined with improved solid state detection and signal processing techniques has been developed; it offers the potential for the construction of a stable and fully portable dosimeter which will extend the useful range of measurement beyond the usual MeV area and provide reliable readings down to sub-100 keV X-ray energy levels. In these experiments, the instrument described has been used for the dosimetry of INTRABEAM intraoperative radiotherapy (IORT) equipment at distances as low as 1.8 mm from the effective source, i.e., 0.2 mm from the X-ray probe surface. Comparison is shown with dosimetry measurements made using the calibrated reference ion chamber supplied by the IORT equipment manufacturer. (author)

  7. Application of TL dosimetry in epidemiological studies in HBRAs

    International Nuclear Information System (INIS)

    Chougaonkar, M.P.

    2006-01-01

    Luminescence as a phenomenon has been extensively used in radiation dosimetry, using thermoluminescence. The nuclear industry all over the world over uses TL dosimetry in radiation protection since they have to ensure that the radiation workers and workers involved in industrial applications of radiation sources are not exposed beyond limits set by international monitoring bodies. They have also to ensure that the nuclear applications do not give rise to elevated radiation levels in the environs. In addition, epidemiologists and radiobiologists world over have been working over the past few decades, to study health effects of chronic radiation exposures in populations living in the elevated natural radiation environment. This paper discusses the importance of dosimetric studies, in the normal as well as high background radiation areas (HBRAs), due to the radiation effects on the humans. The application of thermoluminescent dosimeters (TLDs) in population dosimetry with the end point of epidemiological studies is then discussed. The paper outlines the construction of TLDs, methodology of deployment and retrieval and analysis to arrive the dose. To obtain total dose, dosimetric techniques suitable for external gamma radiation, inhalation dose due to radon, thoron and their progenies and radiological analysis of the food items is required. The techniques arriving at the effective dose are outlined. Basics of epidemiological analysis, particularly using case-control methodology and its advantages/ disadvantages are also discussed. Using the previous work by the author, the paper also reviews various analyses that can be carried out the dosimetric data. (author)

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

    International Nuclear Information System (INIS)

    Vanhavere, F.; Struelens, L.; Bordy, J.M.; Daures, J.; Denozieres, M.; Buls, N.; Clerinx, P.; Carinou, E.; Clairand, I.; Debroas, J.; Donadille, L.; Itie, C.; Ginjaume, M.; Jansen, J.; Jaervinen, H.; Miljanic, S.; Ranogajec-Komor, M.; Nikodemova, D.; Rimpler, A.; Sans Merce, M.; D'Errico, F.

    2008-01-01

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

  9. Standards in radiation protection at the IAEA Dosimetry Laboratory

    International Nuclear Information System (INIS)

    Czap, L.; Pernicka, F.; Matscheko, G.; Andreo, P.

    1999-01-01

    Approximately 90% of the Secondary Standard Dosimetry Laboratories (SSDLs) provide users with calibrations of radiation protection instruments, and the Agency is making every necessary effort to insure that SSDLs measurements in radiation protection are traceable to Primary Standards. The IAEA provides traceable calibrations of ionization chambers in terms of air kerma at radiation protection levels and ambient dose equivalent calibrations. SSDLs are encouraged to use the calibrations available from the Agency to provide traceability for their radiation protection measurements. Measurements on diagnostic X ray generators have become increasingly important in radiation protection and some SSDLs are involved in such measurements. The IAEA has proper radiation sources available to provide traceable calibrations to the SSDLs in this field, including an X ray unit specifically for mammography dedicated to standardization procedures. The different photon beam qualities and calibration procedures available in the Agency's Dosimetry Laboratory will be described. (author)

  10. Personnel radiation monitoring by thermoluminescence dosimetry (2000-2001)

    International Nuclear Information System (INIS)

    Mi-Cho-Cho, Daw; Hla-Hla-Win, Daw; Thin-Thin-Kraing

    2001-01-01

    Thermoluminescence dosimetry service was introduced in 1991. Personnel who exposed directly or indirectly to radiation is monitored by thermoluminescent dosimeter. TL materials used for thermoluminescent dosimeter are in the form of thin disc. Personnel whole-body and extremity doses are measured by thermoluminescence dosimetry. The Harshaw Model 4500 TLD reader and Vinten 654E TLD reader are used for TLD evaluation. At present about 600 radiation workers are provided with TLD for routine monitoring. It was found that most personnel had received within permissible dose recommended by the International Commission on Radiological Protection (ICRP). (author)

  11. Optical study of radiation damage in A-SI02 and problems of selective dosimetry of fast neutrons

    International Nuclear Information System (INIS)

    Abdukadyrova, I.Kh.

    1991-01-01

    The present work deals with the optical study of the processes of radiation damage and structural phase transitions (PT) accumulation in α-SiO 2 monocrystals undergoing various influences of fast neutrons (F) and with the possibility of dosimetrical utilization of radiation-sensitive characteristics of the oxide. It has been found that when F grows within the limits of 10 18 -10 20 cm -2 the optical activity var-phi of the crystal changes; the influence of flux density, temperature, surroundings, mixed reactor irradiation components, and thickness change. The process of radiation damage of crystals by spectroscopic methods has been studied. In the course of the neutron irradiation of the α-SiO 2 structure transformation phenomena were studied by means of IR-spectrometry

  12. 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)

  13. Neutron dosimetry for radiation damage in fission and fusion reactors

    International Nuclear Information System (INIS)

    Smith, D.L.

    1979-01-01

    The properties of materials subjected to the intense neutron radiation fields characteristic of fission power reactors or proposed fusion energy devices is a field of extensive current research. These investigations seek important information relevant to the safety and economics of nuclear energy. In high-level radiation environments, neutron metrology is accomplished predominantly with passive techniques which require detailed knowledge about many nuclear reactions. The quality of neutron dosimetry has increased noticeably during the past decade owing to the availability of new data and evaluations for both integral and differential cross sections, better quantitative understanding of radioactive decay processes, improvements in radiation detection technology, and the development of reliable spectrum unfolding procedures. However, there are problems caused by the persistence of serious integral-differential discrepancies for several important reactions. There is a need to further develop the data base for exothermic and low-threshold reactions needed in thermal and fast-fission dosimetry, and for high-threshold reactions needed in fusion-energy dosimetry. The unsatisfied data requirements for fission reactor dosimetry appear to be relatively modest and well defined, while the needs for fusion are extensive and less well defined because of the immature state of fusion technology. These various data requirements are examined with the goal of providing suggestions for continued dosimetry-related nuclear data research

  14. Dosimetry techniques of thermal neutrons and {gamma} radiation in reactor cores; Techniques de dosimetrie des neutrons thermiques et du rayonnement {gamma} dans les piles

    Energy Technology Data Exchange (ETDEWEB)

    Sutton, J; Draganic, I; Hering, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    Chemical studies under radiation done in the reactor cores require to be followed by dosimetry. When the irradiations are done in the reflector, one can limit to the measure of the {gamma} and the neutron radiation. For the dosimetry of the {gamma} radiation, a dosimeter of ferrous sulfate is convenient until doses of about 10{sup 6} rep. The use of aired oxalic acid solutions permits to reach 10{sup 7} rep. The dosimetry of thermal neutrons has been made with solutions of cobalt sulphate or paper filter impregnated with this salt. The total chemical effect of the {gamma} and of the slow neutrons radiation is obtained with solutions of ferrous sulfate added with lithium sulphate. (M.B.) [French] Les etudes de chimie sous radiation faites dans les piles exigent d'etre suivies par dosimetrie. Lorsque les irradiations sont effectues dans le reflecteur, on peut se limiter a doser le rayonnement {gamma} et les neutrons. Pour la dosimetrie du rayonnement {gamma}, un dosimetre a sulfate ferreux convient jusqu'a des doses d'environ 10{sup 6} rep. L'emploi de solutions aerees d'acide oxalique permet d'atteindre 10{sup 7} rep. La dosimetrie des neutrons thermiques a ete faite avec des solutions de sulfate de cotalt ou du papier filtre impregne de ce sel. L'effet chimique total du rayonnement {gamma} et des neutrons lents est obtenu avec des solutions de sulfate ferreux additionne de sulfate de lithium. (M.B.)

  15. 9th International Conference on 3D Radiation Dosimetry

    International Nuclear Information System (INIS)

    2017-01-01

    IC3DDose 2016 - 9th International Conference on 3D Radiation Dosimetry Preface It was a great pleasure to welcome participants to IC3DDose 2016, the 9th International Conference on 3D Radiation Dosimetry, held from 7–10 November 2016 in Galveston, Texas. The series of conferences has evolved considerably during its history. At the first conference, DOSGEL’99, the discussion centered around gel dosimetry. Held in Lexington, Kentucky in 1999, it was timed to coincide with the American Association of Physicists in Medicine (AAPM) Annual Meeting in Nashville, Tennessee. It was my honour to organize that first conference, and it was once again my honour to organize the 9th conference in the series now known as IC3DDose which was held in Galveston, Texas. As was the case with recent IC3DDose conferences, the topic has broadened considerably beyond gel dosimetry. Not only have newer 3D volumetric dosimeters appeared on the scene, but novel electronic dosimetry systems and software that generate quasi-3D dose information have also. These changes have tracked advances in radiation oncology as techniques such as IMRT, VMAT, and IGRT have become almost ubiquitous. At the same time, dynamic treatments including gating and tracking now enjoy widespread use. Novel treatment technologies have appeared with perhaps the most disruptive being combined MR imaging-treatment units such as the ViewRay MR-cobalt unit and the Elekta/Philips MR-Linac. The potential benefits offered by 3D dosimetry were explored, compared and evaluated during IC3DDose 2016. Novel and improved readout techniques, some of which take advantage of the contemporary treatment environment and new QA systems and procedures, as well as other aspects of clinical dosimetry were well represented in the program. Over the past several years, the importance of safety in radiation therapy has been highlighted. The benefits of 3D dosimetry in contributing to safe and accurate treatments cannot be overstated. The

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

    International Nuclear Information System (INIS)

    Hadid, Lama

    2011-01-01

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

  17. 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.

  18. 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

  19. Dosimetry of beams for negative pi-meson radiation therapy

    International Nuclear Information System (INIS)

    Dicello, J.F.

    1976-01-01

    Several new facilities have been built in the last few years which can produce high intensity beams of pions. As a result, a significant amount of new data related to pion dosimetry is available. Results of beam composition, beam shaping, and collimation are given along with depth dose curves and isodose contours. Experimental data which describe the radiation quality of pion beams and the change in radiation quality with position are presented. Experimental data determining the fraction of the dose resulting from neutrons are discussed. The present techniques used in pion dosimetry are summarized, and those areas of pion dosimetry which require additional effort in order to achieve routine treatment planning for patients are reviewed

  20. Radiation Protection and Dosimetry An Introduction to Health Physics

    CERN Document Server

    Stabin, Michael G

    2007-01-01

    This comprehensive text provides an overview of all relevant topics in the field of radiation protection (health physics). Radiation Protection and Dosimetry serves as an essential handbook for practicing health physics professionals, and is also ideal as a teaching text for courses at the university level. The book is organized to introduce the reader to basic principles of radiation decay and interactions, to review current knowledge and historical aspects of the biological effects of radiation, and to cover important operational topics such as radiation shielding and dosimetry. In addition to presenting the most up to date treatment of the topics and references to the literature, most chapters contain numerical problems with their solutions for use in teaching or self assessment. One chapter is devoted to Environmental Health Physics, which was written in collaboration with leading professionals in the area.

  1. Dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Hurst, G S; Ritchie, R H; Sanders, F W; Reinhardt, P W; Auxier, J A; Wagner, E B; Callihan, A D; Morgan, K Z [Health Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1962-03-15

    The methods of dosimetry used for investigation of the doses received by the individuals exposed in the Yugoslav accident were essentially those used in connection with the Oak Ridge Y-12 accident. An outline of the general scheme is as follows: When fast neutrons enter the human body, most of these are moderated to thermal energy and a small fraction of these are captured by a (n, gamma) process in Na sup 2 sup 3 , giving rise to Na sup 2 sup 4 , which by virtue of its emission of high-energy gamma rays with a half life of 14.8 h, is easily detected. It has been shown that the probability of capture, making Na sup 2 sup 4 , is not a strong function of the energy of the fast neutrons and that the probability of capture for neutrons is higher in the fast region than in the thermal region. Thus, the uniform distribution of Na sup 2 sup 3 in the human body provides an excellent means of normalizing the neutron exposure of an individual. in particular, for a given neutron energy spectrum the fast neutron dose is proportional to the ratio Na sup 2 sup 4 /Na sup 2 sup 3 in the body or in the blood system. This method of normalization is quite important in the dosimetry of radiation accidents since no assumptions need be made about the exact location of an individual at the time of the energy release. The importance of this fact can be made clear by reference to the Y-12 accident where it was shown by calculation of the neutron dose based on the known number of fissions and the stated location of the individual that one of the surviving individuals would have received a dose several times the lethal value. To accomplish the measurements described, the zero power R sub B reactor was operated in two ranges of power level, 'low' power and 'high 'power. Neutron leakage spectrum was obtained by multigroup approximation of the Boltzmann transport equation. Prompt gamma rays from fission products, from capture in the moderator and fuel cladding as well as in tank walls are given

  2. Dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Hurst, G S; Ritchie, R H; Sanders, F W; Reinhardt, P W; Auxier, J A; Wagner, E B; Callihan, A D; Morgan, K Z [Health Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1962-03-01

    The methods of dosimetry used for investigation of the doses received by the individuals exposed in the Yugoslav accident were essentially those used in connection with the Oak Ridge Y-12 accident. An outline of the general scheme is as follows: When fast neutrons enter the human body, most of these are moderated to thermal energy and a small fraction of these are captured by a (n, {gamma}) process in Na{sup 23}, giving rise to Na{sup 24}, which by virtue of its emission of high-energy gamma rays with a half life of 14.8 h, is easily detected. It has been shown that the probability of capture, making Na{sup 24}, is not a strong function of the energy of the fast neutrons and that the probability of capture for neutrons is higher in the fast region than in the thermal region. Thus, the uniform distribution of Na{sup 23} in the human body provides an excellent means of normalizing the neutron exposure of an individual. in particular, for a given neutron energy spectrum the fast neutron dose is proportional to the ratio Na{sup 24}/Na{sup 23} in the body or in the blood system. This method of normalization is quite important in the dosimetry of radiation accidents since no assumptions need be made about the exact location of an individual at the time of the energy release. The importance of this fact can be made clear by reference to the Y-12 accident where it was shown by calculation of the neutron dose based on the known number of fissions and the stated location of the individual that one of the surviving individuals would have received a dose several times the lethal value. To accomplish the measurements described, the zero power R{sub B} reactor was operated in two ranges of power level, 'low' power and 'high 'power. Neutron leakage spectrum was obtained by multigroup approximation of the Boltzman transport equation. Prompt gamma rays from fission products, from capture in the moderator and fuel cladding as well as in tank walls are given. A summary of the 4{pi

  3. Computational hybrid anthropometric paediatric phantom library for internal radiation dosimetry

    DEFF Research Database (Denmark)

    Xie, Tianwu; Kuster, Niels; Zaidi, Habib

    2017-01-01

    for children demonstrated that they follow the same trend when correlated with age. The constructed hybrid computational phantom library opens up the prospect of comprehensive radiation dosimetry calculations and risk assessment for the paediatric population of different age groups and diverse anthropometric...

  4. 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

  5. Radiation Dosimetry for Quality Control of Food Preservation and Disinfestation

    DEFF Research Database (Denmark)

    McLaughlin, W.L.; Miller, Arne; Uribe, R.M.

    1983-01-01

    In the use of x and gamma rays and scanned electron beams to extend the shelf life of food by delay of sprouting and ripening, killing of microbes, and control of insect population, quality assurance is provided by standardized radiation dosimetry. By strategic placement of calibrated dosimeters...

  6. Study and development of radiothermoluminescent dosimetry

    International Nuclear Information System (INIS)

    Portal, Guy.

    1978-11-01

    After briefly reviewing bibliography concerning the mechanism of radiothermoluminescence and its use in dosimetry, we have concentrated on studies of three thermoluminescent products: magnesium activated lithium fluoride, alumina and calcium sulfate activated with either dysprosium or thulium. In particular, the preparation and singular properties of a new type of lithium fluoride stabilised with sodium, created especially for dosimetric purposes, is described. The physical characteristics of these three products, their emission spectra and their trap parameters, have been studied and we have analysed, both theoretically and experimentally, their dosimetric properties, paying particular attention to their relative chromatic sensitivity to photons and neutrons. It is shown that alumina exhibits an exceptional neutron thermoluminescent yield which points to a potential interest in this material which is little used to date. The deep trapping levels of these products have been studied and some levels found appearing at temperatures above 600 0 C: these can be used for radiation dosimetry in enclosures at temperatures between 400 and 450 0 C. Finally, a brief outline of radiothermoluminescent applications of these products in the radioprotection, medical, biological, archeological and industrial fields is presented [fr

  7. radiation dosimetry in cases of normal and emergency situations

    International Nuclear Information System (INIS)

    Morsi, T.M.

    2010-01-01

    The use of radioactive materials in various fields of medicine, industry, agriculture and researches has been increasing steadily during the last few decades. A lot of radiation sources, radiopharmaceuticals, labeled compounds and other radioactive materials are sold and used throughout the world each year. Historically, accidents have occurred during the production, transport and use of radioactive materials. If an accident does occur, it is necessary to cope with it as soon as possible in order to control radiological human exposures and contamination of the environment and to restore normal conditions. Examination of individuals that deal with radioactive isotopes should be carried out in cases of nuclear medicine units, and in other applications including radiotherapy unit and gamma irradiation facility. Identification of the feasibility and efficiency of the counting detectors of internal and external radiation dosimetry, and preparedness in normal and emergency situations are included in the present work. Furthermore, this study also deals with the use of thermoluminescent dosimeters for radiation dose estimation for applications of gamma irradiation, and cobalt-60 treatment unit. Hence, operator dose can be estimated in case of malfunction or stuck of the radioactive source. Three methods were used to measure the radiation dose: (1) TL dosimeters with Harshaw (TLD- 4000) reader were used for measurement of external exposures. (2) FASTSCAN and (3) ACUUSCAN II whole body counters were used for measurement of internal exposures.

  8. Retrospective dosimetry using salted snacks and nuts: a feasibility study

    International Nuclear Information System (INIS)

    Christiansson, M.; Geber-Bergstrand, T.; Bernhardsson, C.; Mattsson, S.; Raeaef, C.L.

    2017-01-01

    The possibility of using ordinary household table salt for dosimetry is suggested by its high sensitivity to ionising radiation, which generates a readout of optically stimulated luminescence (OSL). However, to exploit this finding for retrospective human dosimetry, it would be needed to find salt in close proximity to the exposed individual. Finding salty snacks frequently tucked into handbags, backpacks or pockets seemed to be a possibility; these items therefore became the test materials of the present study. The aluminium or cardboard packages used to exclude the moisture that makes crisps and nuts go soft and stale also helps to retain the induced OSL signal. Therefore, different snacks, either their salt component alone or mixed with the snack, are exposed to ionising radiation and then were assessed for their dosimetric properties. The results indicate the feasibility of using some salty snacks for dosimetry, with a minimum detectable dose as low as 0.2 mGy (authors)

  9. Thermoluminescent characteristics of diopside-teflon composites for radiation dosimetry

    International Nuclear Information System (INIS)

    Melo, A.P.; Caldas, L.V.E.

    2006-01-01

    Diopside - Teflon composites were been studied in relation to their dosimetric properties for high-dose dosimetry. Diopside from Minas Gerais, Brazil, CaMg(Si 2 O 6 ), was obtained in form of rude mineral with inclusions of quartz. The samples were prepared and only Diopside grains obtained. Pellets of Diopside-Teflon composites were prepared in the proportion of 2(Teflon): 1 (Diopside).The TL response repeatability presented a maximum coefficient of variation of 7.5%. The calibration curve is linear between 0.5 Gy and 1 kGy. TL emission spectra present three emissions of similar intensities at 570 nm, 590 nm and between 610-635 nm. The results suggest that the material presents good characteristics for use as high-dose radiation detectors. (Author)

  10. Biological dosimetry of ionizing radiation by chromosomal aberration analysis

    International Nuclear Information System (INIS)

    Gonzalez-Castano, S.; Silva, A.; Navlet, J.

    1990-01-01

    Biological dosimetry consists of estimating absorbed doses for people exposed to radiation by mean biological methods. Several indicators used are based in haematological, biochemical, and cytogenetic data, although nowadays without doubt, the cytogenetic method is considered to be the most reliable. In this case, the study ol chromosomal aberrations, normally dicentric chromosomes, in peripheral lymphocytes can be related to absorbed dose through an experimental calibration curve. An experimental dose-response curve, using dicentric chromosomes analysis, X-rays at 300 kVp, 114 rad/min and temperature 37 degree celsius has been produced. Experimental data is fitted to model Y =α + β 1 D + β 2 D 2 , where Y is the number of dicentrics per cell and D the dose. The curve is compared with those produced elsewhere. (Author) 14 refs

  11. Biological dosimetry of ionizing radiation by chromosomal aberration analysis

    International Nuclear Information System (INIS)

    Navlet Armenta, J.M.; Gonzalez, S.; Silva, A.

    1990-01-01

    Biological dosimetry consists of estimating absorbed doses for people exposed to radiation by mean biological methods. Several indicators used are based in haemathological, biochemical, and cytogenetic data, although nowadays without doubt, the cytogenetic method is considered to be the most reliable. In this case, the study of chromosomal aberrations, normally dicentric chromosomes, in peripheral lymphocytes can be related to absorbed dose through an experimental calibration curve. An experimental dose-response curve using dicentric chromosomes analysis, X-rays at 300 kVp, 114 rad/min and temperature 37 o C has been produced. Experimental data is fitted to model Y = α+β 1 D+β 2 D 2 , where Y is the number of dicentrics per cell and D the dose. The curve is compared with those produced elsewhere. (Author)

  12. Monte Carlo technique applications in field of radiation dosimetry at ENEA radiation protection institute: A Review

    International Nuclear Information System (INIS)

    Gualdrini, G.F.; Casalini, L.; Morelli, B.

    1994-12-01

    The present report summarizes the activities concerned with numerical dosimetry as carried out at the Radiation Protection Institute of ENEA (Italian Agency for New Technologies, Energy and the Environment) on photon dosimetric quantities. The first part is concerned with MCNP Monte Carlo calculation of field parameters and operational quantities for the ICRU sphere with reference photon beams for the design of personal dosemeters. The second part is related with studies on the ADAM anthropomorphic phantom using the SABRINA and MCNP codes. The results of other Monte Carlo studies carried out on electron conversion factors for various tissue equivalent slab phantoms are about to be published in other ENEA reports. The report has been produced in the framework of the EURADOS WG4 (numerical dosimetry) activities within a collaboration between the ENEA Environmental Department and ENEA Energy Department

  13. Dosimetry of ionizing radiation. Fundamentals and applications. Dosimetrie ionisierender Strahlen. Grundlagen und Anwendungen

    Energy Technology Data Exchange (ETDEWEB)

    Reich, H [ed.

    1990-01-01

    In the first chapter of the book, a brief description is given of the historical development of dosimetry, of its objectives and special role within the context of general physical metrology, followed by detailed explanations of the physical fundamentals of this science: the sources and fields of radiation, interactions between radiation and matter as well as radiation detectors. The terminology and units of measurement used in dosimetry are explained in a separate chapter. Chapters 7 and 8, which outline the various theoretical and experimental methods of dose determination, are the most essential contributions to this volume. Chapter 9 deals with the ways in which dosimetry is used in special cases in radiotherapy as well as in the measurement of very small or very large doses. Chapter 10 gives a survey of recently introduced units of measurements and methods to calculate the body dose with reference to the particular type of exposure used. Appendix A contains tables of measuring units, physical constants and measuring techniques along with at-a-glance information on the legal regulations concerning the calibration of dosimeters. Appendix B gives practical guidance on the handling of hardware-related inaccuracies of measurement in dose determination procedures and appendix C embraces 22 pages of tables showing data on radiation physics. (orig./HP) With 150 figs., 50 tabs. in the text, and annex with tables.

  14. Thermoluminescent phosphors for ultraviolet radiation dosimetry - a review

    International Nuclear Information System (INIS)

    Nagpal, J.S.

    2001-01-01

    Intrinsic TL response of CaSO 4 , CaF 2 , Al 2 O 3 (Si,Ti), Mg 2 SiO 4 : Tb and lamp phosphors to ultraviolet radiation is reviewed. Taking into consideration the characteristics such as afterglow at RT, rate/flux dependence, linearity of response, useful range, spectral dependence and effect of sequential/tandem UV exposures CaF 2 :Eu 2+ is an ideal TL dosemeter for UV radiation dosimetry. (author)

  15. 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)

  16. Cosmic radiation dosimetry in international flights argentine airlines

    International Nuclear Information System (INIS)

    Ciancio, Vicente R.; Oliveri, Pedro V.; Di Giovan B, Gustavo; Ciancio, Vanina L.; Lewis, Brent J.; Green, Anna R.; Bennet, L.

    2008-01-01

    Full text: Introduction: In commercial aviation the most important determinants of radiation exposure in humans are the altitude, latitude, flight duration and the solar cycle's period. This study was conducted to address this type of exposure trough radiation dosimetry. Method: The study was performed in the business-class cabin of an Airbus 340-200 aircraft, provided by Argentine Airlines, during 2 flights routes: New York-Miami-Buenos Aires (trans equatorial) and Buenos Aires-Auckland (circumpolar). Measurements addressed the electromagnetic spectrum or low Linear Energy Transfer (LET) and corpuscular radiation (High LET). The instruments used were an Ion Chamber (IC), to measure the ionizing component of radiation (i.e., gamma radiation), the SWENDI, to measure only the neutron component, and the Tissue Equivalent Proportional Counter (TEPC) for measuring all radiation types. Results: The routes' dose rates are presented in the table. TEPC rates agreed with the LET findings. The total dose rates of high latitude flights were higher than those of low latitude flights. The SWENDI (High LET) results for the flights over the equator, at low latitude, represented only 1/3 of the total radiation. The New York-Miami and Buenos Aires-Auckland flights, at high latitude, represented just under 1/2 of the Total radiation (-45%). Conclusion: Based on the results of this study, the annual dose rates of radiation exposure of air crew personnel serving on international flights offered by Argentine Airlines is between 3 and 7 mSv. This rate is higher than the maximum recommended for the general population by the International Commission on Radiological Protection (ICRP), which is 1 milli Sv./y. Therefore, these personnel must be officially considered 'Occupationally Exposed to Radiation' in way to provide the appropriate measures that must be implemented for their protection in accordance to ICRP guidelines. Dose(uSv): Route N Y-Miami, IC 6.07, SWENDI 5.07, TEPC 11.04; Route

  17. Dosimetry of external radiation: Recent developments. Advanced training course

    International Nuclear Information System (INIS)

    Ambrosi, P.; Boehm, J.; Doerschel, B.

    1999-02-01

    Between February 24 and 26, 1999, the Fachverband fuer Strahlenschutz e.V. held an advanced training course in Tabarz/Thuringia on the subject 'Dosimetry of external radiation: Recent developments'. The following subject matters were dealt with: New concepts and measurands; Present national and international rules; Measurement of the body dose; Exposure conditions at workplaces; and Present state of dosimetric metrology. In correspondence with the subject, the course was organized by the working group 'Dosimetry of external radiation'. Target groups of the course were persons bearing responsibility in the radiation protection sector and interested persons with basic knowledge of this field. The present report comprises the written versions of lectures delivered at the meeting. (orig.) [de

  18. Introduction to the special issue of Radiation Protection Dosimetry

    International Nuclear Information System (INIS)

    Anon.

    2016-01-01

    This special issue is a collection of peer-reviewed articles derived from presentations at the fourth EPR BioDose Meeting, held in Hanover, NH, USA in 4-8 October 2015. Organised by The International Association of Biological and EPR Radiation Dosimetry (IABERD), this meeting was held in combination with two international conferences (The International Symposium on EPR Dosimetry and Dating and The International Conference on Biodosimetry) and a symposium (The International EPR Society). The primary focus of this conference was on medical response to events in which large numbers of individuals may be exposed to significant levels of ionising radiation; topics included biodosimetry techniques, radiation mitigators, model systems to develop countermeasures, new data from different exposure events and the implication of these methods in a radiological emergency or in terrorist attack scenarios. (authors)

  19. Air-crew radiation dosimetry - last development

    International Nuclear Information System (INIS)

    Spurny, F.

    2001-01-01

    Exposure to cosmic radiation increases rapidly with the altitude. At the flight levels of commercial aircraft it is of the order of several μSv per hour. The most of air-crew are exposed regularly to the effective dose exceeding 1 mSv per year, the limit of exposure of non-professionals defined in ICRP 60 recommendation. That is why this problem has been intensively studied from many aspects since the beginning of 90's. This contribution summarises new developments in the field during last two years. First, new international activities are presented, further, new achievement obtained mainly in the author's laboratory are presented and discussed. (authors)

  20. Biodistribution and radiation dosimetry of the 18 kDa translocator protein (TSPO) radioligand [{sup 18}F]FEDAA1106: a human whole-body PET study

    Energy Technology Data Exchange (ETDEWEB)

    Takano, Akihiro; Gulyas, Balazs; Varrone, Andrea; Karlsson, Per; Sjoholm, Nils; Halldin, Christer [Karolinska Institutet, Department of Clinical Neuroscience, Psychiatry Section, Stockholm (Sweden); Larsson, Stig; Jonsson, Cathrine; Odh, Richard [Karolinska Institutet, Department of Nuclear Medicine, Stockholm (Sweden); Sparks, Richard [CDE Dosimetry Services, Inc., Knoxville, TN (United States); Tawil, Nabil Al [Karolinska University Hospital, Karolinska Trial Alliance, Stockholm (Sweden); Hoffmann, Anja; Zimmermann, Torsten; Thiele, Andrea [Bayer Schering Pharma AG, Berlin (Germany)

    2011-11-15

    [{sup 18}F]FEDAA1106 is a recently developed positron emission tomography (PET) radioligand for in vivo quantification of the 18 kDa translocator protein [TSPO or, as earlier called, the peripheral benzodiazepine receptor (PBR)]. TSPO imaging is expected to be useful for the clinical evaluation of neuroinflammatory diseases. The aim of this study was to provide dosimetry estimates for [{sup 18}F]FEDAA1106 based on human whole-body PET measurements. PET scans were performed for a total of 6.6 h after the injection of 183.8 {+-} 9.1 MBq of [{sup 18}F]FEDAA1106 in six healthy subjects. Regions of interest were drawn on coronal images. Estimates of the absorbed doses of radiation were calculated using the OLINDA software. Peak uptake was largest in lungs, followed by liver, small intestine, kidney, spleen and other organs. Peak values of the percent injected dose (%ID) at a time after radioligand injection were calculated for the lungs (27.1%ID at 0.2 h), liver (21.1%ID at 0.6 h), small intestine (10.4%ID at 6.3 h), kidney (4.9%ID at 1.8 h) and spleen (4.6%ID at 0.6 h). The largest absorbed dose was found in the spleen (0.12 mSv/MBq), followed by kidneys (0.094 mSv/MBq). The calculated mean effective dose was 0.036 mSv/MBq. Based on the distribution and dose estimates, the estimated radiation burden of [{sup 18}F]FEDAA1106 is moderately higher than that of [{sup 18}F]fluorodeoxyglucose (FDG). In clinical studies, the administered activity of this radioligand ought to be adjusted in line with regional regulations. This result would be helpful for further clinical TSPO imaging studies. (orig.)

  1. Radiation dosimetry for medical management in nuclear/radiological disaster

    International Nuclear Information System (INIS)

    Narayan, Pradeep

    2012-01-01

    Medical Management of radiation exposed victims depends on the amount of radiation doses received in their body and individual organs. The severity of radiation sickness; and early/late biological effects of radiation can be judged on the basis of absorbed dose level of the exposed individual. Radiation Dosimetry is a scientific technique for estimating radiation doses in material and living being. It is an important task for managing radiation effects/injuries to the living being in case of radiological accidents/disasters. In such scenario occupational radiation workers as well as public in general may be exposed with ionizing radiations such as; gamma, alpha, beta and neutron. Radiation dosimetric equipment's are available for occupational radiation workers, however, public in general may not have any dosimetry system with them. Therefore, absorbed dose estimation to the public on individual basis is a challenge to the society. The ambient environment materials in close proximity to the exposed individual may be analyzed using scientific techniques to estimate their personal radiation doses. The blood sample from exposed individual can be examined in laboratory using citometry techniques for dose estimation, however these techniques are very time consuming and may not be suitable for quick radiation management. The other human biological material such as; tooth, hair, and bone etc., can be examined using Electron Spin Resonance (ESR) spectrometry techniques. This technique is very efficient and capable in measuring radiation doses of the order of 20-30 mGy in very less time typically 2-3 min. In reality, this technique is costly affair and available mostly in developed countries. Thermoluminescence (TL) technique is very versatile and cost effective for routine personal dose estimation, This technique has been found suitable for measuring TL in many accidentally exposed environmental materials. The radiation exposed natural environmental materials, such as

  2. International cooperative effort to establish dosimetry standardization for radiation processing

    International Nuclear Information System (INIS)

    Farrar, Harry IV

    1990-01-01

    Radiation processing is a rapidly developing technology with numerous applications in food treatment, sterilization, and polymer modification. The effectiveness of the process depends, however, on the proper application of dose and its measurement. These aspects are being considered by a wide group of experts from around the world who have joined together to write a comprehensive set of standards for dosimetry for radiation processing. Originally formed in 1984 to develop standards for food processing dosimetry, the group has now expanded into a full subcommittee of the American Society for Testing and Materials (ASTM), with 97 members from 19 countries. The scope of the standards now includes dosimetry for all forms and applications of radiation processing. To date, the group has completed and published four standards, and is working on an additional seven. Three are specifically for food applications and the others are for all radiation applications, including food processing. Together, this set of standards will specify acceptable guidelines and methods for accomplishing the required irradiation treatment. This set will be available for adoption by national regulatory agencies or other standards-setting organizations for their procedures and protocols. (author)

  3. International cooperative effort to establish dosimetry standardization for radiation processing

    International Nuclear Information System (INIS)

    Farrar, H. IV.

    1989-01-01

    Radiation processing is a rapidly developing technology with numerous applications in food treatment, sterilization, and polymer modification. The effectiveness of the process depends, however, on the proper application of dose and its measurement. These aspects are being considered by a wide group of experts from around the world who have joined together to write a comprehensive set of standards for dosimetry for radiation processing. Originally formed in 1984 to develop standards for food processing dosimetry, the group has now expanded into a full subcommittee of the American Society for Testing and Materials (ASTM), with 97 members from 19 countries. The scope of the standards now includes dosimetry for all forms of radiation processing. The group has now completed and published four standards, and is working on an additional seven. Three are specifically for food applications and the others are for all radiation applications, including food processing. Together, this set of standards will specify acceptable guidelines and methods for accomplishing the required irradiation treatment, and will be available for adoption by national regulatory agencies in their procedures and protocols. 1 tab

  4. Comparison of radiation dosimetry for several potential myocardial imaging agents

    International Nuclear Information System (INIS)

    Watson, E.E.; Stabin, M.G; Goodman, M.M.; Knapp, F.F. Jr.; Srivastava, P.C.

    1986-01-01

    Although myocardial imaging is currently dominated by Tl-201, several alternative agents with improved physiologic or radionuclidic properties have been proposed. Based on human and animal studies in the literature, the metabolism of several of these compounds was studied for the purpose of generating radiation dose estimates. Dose estimates are listed for several I-123-labeled free fatty acids, an I-123-labeled phosphonium compound, Rb-82, Cu-64, F-18 FDG (all compounds which are taken up by the normal myocardium), and for Tc-99m pyrophosphate (PYP) (which localizes in myocardial infarcts). Dose estimates could not be generated for C-11 palmitate, but his compound was included in a comparison of myocardial retention times. For the I-123-labeled compounds, I-124 was included as a contaminant in generating the dose estimates. Radiation doses were lowest for Rb-82 (gonads 0.3-0.4 Gy/MBq, kidneys 8.6 Gy/MBq). Doses for the I-123-labeled fatty acids were similar to one another, with IPPA being the lowest (gonads 15 Gy/MBq, heart wall 18 Gy/MBq). Doses for Tc-99m PYP were also low (gonads 4-7 Gy/MBq, heart wall 4 Gy/MBq, skeleton 15 Gy/MBq). The desirability of these compounds is discussed briefly, considering half-life, imaging mode and energy, and dosimetry, including a comparison of the effective whole body dose equivalents. 37 references, 11 tables

  5. Radiation accident dosimetry: TL properties of mobile phone screen glass

    International Nuclear Information System (INIS)

    Bassinet, C.; Pirault, N.; Baumann, M.; Clairand, I.

    2014-01-01

    Mobile phones are carried by a large part of the population and previous studies have shown that they may be able to function as individual fortuitous dosimeters in case of radiological accident. This study deals with thermoluminescence (TL) properties of mobile phone screen glass. The presence of a significant background signal which partially overlaps with the radiation-induced signal is a serious issue for dose reconstruction. A mechanical method to reduce this signal using a diamond grinding bit is presented. An over-response at low energy (∼50 keV) is observed for two investigated glasses. The results of a dose recovery test using a single-aliquot regenerative-dose (SAR) procedure are discussed. - Highlights: • Mobile phone screen glass is a promising material for retrospective dosimetry. • The TL non-radiation induced background signal can be significantly reduced by a mechanical method. • A dose recovery test using an SAR procedure was successfully carried out for the investigated glass

  6. Cytogenetics for dosimetry in cases of radiation accidents and assessing the safety of irradiated food material

    International Nuclear Information System (INIS)

    Natarajan, A.T.; Kesavan, P.C.

    2005-01-01

    One of the many areas of research initiated by Swaminathan at the Botany Division of the Indian Agricultural Research Institute, New Delhi was radiation cytogenetics, which involves study of induced chromosomal aberrations. These studies had impact not only on elucidating basic mechanisms involved in the formation of chromosomal aberrations, but also several practical applications related to human health. In this review, we briefly summarize two applications, namely biological dosimetry following radiation accidents and safety of irradiated food material. (author)

  7. EPR dosimetry of radiation background in the Urals region

    Energy Technology Data Exchange (ETDEWEB)

    Shishkina, E.A.; Degteva, M.O.; Shved, V.A. [Urals Research Center for Radiation Medicine, 48-A Vorovsky, Chelyabinsk 454076 (Russian Federation); Fattibene, P.; Onori, S. [Istituto Superiore di Sanita and Istituto Nazionale di Fisica Nucleare (Italy); Wieser, A. [GSF, Forschungszentrum fuer Umwelt und Gesundheit, Ingolstaedter Landstr (Germany); Ivanov, D.V.; Bayankin, S.N. [Institute of Metal Physics, Russian Academy of Sciences (Russian Federation); Knyazev, V.A.; Vasilenko, E.I.; Gorelov, M. [ZAO, Closed Corporation ' Company GEOSPETSECOLOGIA' (Russian Federation)

    2006-07-01

    Method of Electron Paramagnetic Resonance is extensively applied to individual retrospective dosimetry. The background dose is unavoidable component of cumulative absorbed dose in the tooth enamel accumulated during the lifetime of donor. Estimation of incidental radiation dose using tooth enamel needs in extraction of background dose. Moreover, the variation of background doses in the population is a limited factor for reliable detection of additional irradiation especially for low dose level. Therefore the accurate knowledge of the natural background radiation dose is a critical element of EPR studies of exposed populations. In the Urals region the method applies for such two large cohorts as the workers of Mayak (Ozersk citizens) and Techa River riverside inhabitants (rural population). Current study aimed to investigate the Urals radiation background detected by EPR spectrometry. For this aim two group of unexposed Urals residents were separated, viz: citizens of Ozersk and rural inhabitants of Chelyabinsk region. Comparison of two investigated territories has demonstrated that from the point of view of radiation background it is impossible to assume the Urals population as uniform. The reliable difference between the urban and rural residents has been found. The average background doses of Ozersk donors is in average 50 mGy higher than those detected for rural residents. The individual variability of background doses for Osersk has been higher than in the rural results. The difference in background dose levels between two population results in different limits of accidental dose detection and individualization. The doses for 'Mayak' workers (Ozyorsk citizens) can be classed as anthropogenic if the EPR measurements exceed 120 mGy for teeth younger than 40 years, and 240 mGy for teeth older than 70 years. The anthropogenic doses for Techa River residents (rural population) would be higher than 95 mGy for teeth younger than 50 years and 270 mGy for

  8. EPR dosimetry of radiation background in the Urals region

    International Nuclear Information System (INIS)

    Shishkina, E.A.; Degteva, M.O.; Shved, V.A.; Fattibene, P.; Onori, S.; Wieser, A.; Ivanov, D.V.; Bayankin, S.N.; Knyazev, V.A.; Vasilenko, E.I.; Gorelov, M.

    2006-01-01

    Method of Electron Paramagnetic Resonance is extensively applied to individual retrospective dosimetry. The background dose is unavoidable component of cumulative absorbed dose in the tooth enamel accumulated during the lifetime of donor. Estimation of incidental radiation dose using tooth enamel needs in extraction of background dose. Moreover, the variation of background doses in the population is a limited factor for reliable detection of additional irradiation especially for low dose level. Therefore the accurate knowledge of the natural background radiation dose is a critical element of EPR studies of exposed populations. In the Urals region the method applies for such two large cohorts as the workers of Mayak (Ozersk citizens) and Techa River riverside inhabitants (rural population). Current study aimed to investigate the Urals radiation background detected by EPR spectrometry. For this aim two group of unexposed Urals residents were separated, viz: citizens of Ozersk and rural inhabitants of Chelyabinsk region. Comparison of two investigated territories has demonstrated that from the point of view of radiation background it is impossible to assume the Urals population as uniform. The reliable difference between the urban and rural residents has been found. The average background doses of Ozersk donors is in average 50 mGy higher than those detected for rural residents. The individual variability of background doses for Osersk has been higher than in the rural results. The difference in background dose levels between two population results in different limits of accidental dose detection and individualization. The doses for 'Mayak' workers (Ozyorsk citizens) can be classed as anthropogenic if the EPR measurements exceed 120 mGy for teeth younger than 40 years, and 240 mGy for teeth older than 70 years. The anthropogenic doses for Techa River residents (rural population) would be higher than 95 mGy for teeth younger than 50 years and 270 mGy for teeth older

  9. 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)

  10. Fostering a culture of interprofessional education for radiation therapy and medical dosimetry students

    International Nuclear Information System (INIS)

    Lavender, Charlotte; Miller, Seth; Church, Jessica; Chen, Ronald C.; Muresan, Petronella A.; Adams, Robert D.

    2014-01-01

    A less-studied aspect of radiation therapy and medical dosimetry education is experiential learning through attendance at interprofessional conferences. University of North Carolina radiation therapy and medical dosimetry students regularly attended morning conferences and daily pretreatment peer review, including approximately 145 hours of direct interaction with medical attending physicians and residents, medical physicists, and other faculty. We herein assessed the effect of their participation in these interprofessional conferences on knowledge and communication. The students who graduated from our radiation therapy and medical dosimetry programs who were exposed to the interprofessional education initiative were compared with those who graduated in the previous years. The groups were compared with regard to their knowledge (as assessed by grades on end-of-training examinations) and team communication (assessed via survey). The results for the 2 groups were compared via exact tests. There was a trend for the examination scores for the 2012 cohort to be higher than for the 2007 to 2011 groups. Survey results suggested that students who attended the interprofessional education sessions were more comfortable speaking with attending physicians, residents, physicists, and faculty compared with earlier students who did not attend these educational sessions. Interprofessional education, particularly vertical integration, appears to provide an enhanced educational experience both in regard to knowledge (per the examination scores) and in building a sense of communication (via the survey results). Integration of interprofessional education into radiation therapy and medical dosimetry educational programs may represent an opportunity to enrich the learning experience in multiple ways and merits further study

  11. Fostering a culture of interprofessional education for radiation therapy and medical dosimetry students

    Energy Technology Data Exchange (ETDEWEB)

    Lavender, Charlotte, E-mail: charlavender@gmail.com; Miller, Seth; Church, Jessica; Chen, Ronald C.; Muresan, Petronella A.; Adams, Robert D.

    2014-04-01

    A less-studied aspect of radiation therapy and medical dosimetry education is experiential learning through attendance at interprofessional conferences. University of North Carolina radiation therapy and medical dosimetry students regularly attended morning conferences and daily pretreatment peer review, including approximately 145 hours of direct interaction with medical attending physicians and residents, medical physicists, and other faculty. We herein assessed the effect of their participation in these interprofessional conferences on knowledge and communication. The students who graduated from our radiation therapy and medical dosimetry programs who were exposed to the interprofessional education initiative were compared with those who graduated in the previous years. The groups were compared with regard to their knowledge (as assessed by grades on end-of-training examinations) and team communication (assessed via survey). The results for the 2 groups were compared via exact tests. There was a trend for the examination scores for the 2012 cohort to be higher than for the 2007 to 2011 groups. Survey results suggested that students who attended the interprofessional education sessions were more comfortable speaking with attending physicians, residents, physicists, and faculty compared with earlier students who did not attend these educational sessions. Interprofessional education, particularly vertical integration, appears to provide an enhanced educational experience both in regard to knowledge (per the examination scores) and in building a sense of communication (via the survey results). Integration of interprofessional education into radiation therapy and medical dosimetry educational programs may represent an opportunity to enrich the learning experience in multiple ways and merits further study.

  12. Irrigoscopy - irrigography method, dosimetry and radiation shielding

    International Nuclear Information System (INIS)

    Zubanov, Z.; Kolarevic, G.

    1999-01-01

    Use of patient's radiation shielding during radiology diagnostic procedures in our country is insufficiently represent, so patients needlessly receive very high entrance skin doses in body areas which are not in direct x-ray beam. During irrigoscopy, patient's radiation shielding is very complex problem, because of the organs position. In the future that problem must be solved. We hope that some of our suggestions about patient's radiation shielding during irrigoscopy, can be a small step in that way. (author)

  13. Dosimetry of ionizing radiations by Electron paramagnetic resonance

    International Nuclear Information System (INIS)

    Azorin N, J.

    2005-01-01

    In this work, some historical and theoretical aspects about the Electron Paramagnetic Resonance (EPR), its characteristics, the resonance detection, the paramagnetic species, the radiation effects on inorganic and organic materials, the diagrams of the instrumentation for the EPR detection, the performance of an EPR spectrometer, the coherence among EPR and dosimetry and, practical applications as well as in the food science there are presented. (Author)

  14. Gamma radiation processing dosimetry with commercial silicon diodes

    International Nuclear Information System (INIS)

    Ferreira, Danilo Cardenuto

    2009-01-01

    This work envisages the development of dosimeters based on Si diodes for gamma radiation dosimetry from 1 Gy up to 100 Gy. This dose range is frequently utilized in radiation processing of crystal modifications, polymers crosslinking and biological studies carried out in the Radiation Technology Center at IPEN-CNEN/SP. The dosimeter was constructed by a commercial SFH00206 (Siemens) Si diode, operating in a photovoltaic mode, whose electrical characteristics are suitable for this application. The current generated in the device by the Cobalt-60 gamma radiation from the Irradiators types I and II was registered with a digital electrometer and stored during the exposure time. In all measurements, the current signals of the diode registered as a function of the exposure time were very stable. Furthermore, the device photocurrent was linearly dependent on the dose rate within a range of 6.1x10 -2 Gy/min up to 1.9x10 2 Gy/min. The calibration curves of the dosimeters, e.g., the average charge registered as a function of the absorbed dose were obtained by the integration of the current signals as a function of the exposure time. The results showed a linear response of the dosimeter with a correlation coefficient better than 0.998 for total absorbed dose up to 120 Gy. Finally, due to the small experimental errors 5 % it was also possible to measure the transit dose due to the movement of the Cobalto- 60 radioactive sources in irradiation facilities used in this work. (author)

  15. 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

  16. 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.

  17. Biodistribution and radiation dosimetry of [18F]-5-fluorouracil

    International Nuclear Information System (INIS)

    Hino-Shishikura, Ayako; Suzuki, Akiko; Minamimoto, Ryogo; Shizukuishi, Kazuya; Oka, Takashi; Tateishi, Ukihide; Sugae, Sadatoshi; Ichikawa, Yasushi; Horiuchi, Choichi; Inoue, Tomio

    2013-01-01

    Purpose: To estimate the radiation dose and biodistribution of 18 F-5-fluorouracil ([ 18 F]-5-FU) from positron emission tomography/computed tomography (PET/CT) data, and to extrapolate mouse data to human data in order to evaluate cross-species consistency. Methods: Fifteen cancer patients (head and neck cancer (n=11), colon cancer (n=4)) were enrolled. Sequential PET/CT images were acquired for 2 h after intravenous administration of [ 18 F]-5-FU, and the percent of the injected dose delivered to each organ was derived. For comparison, [ 18 F]-5-FU was administered to female BALB/cAJcl-nu/nu nude mice (n=19), and the percent of the injected dose delivered to mouse organs was extrapolated to the human model. Absorbed radiation dose was calculated using OLINDA/EXM 1.0 software. Results: In human subjects, high [ 18 F]-5-FU uptake was seen in the liver, gallbladder and kidneys. The absorbed dose was highest in the gallbladder wall. In mice, the biodistribution of [ 18 F]-5-FU corresponded to that of humans. Estimated absorbed radiation doses for all organs were moderately correlated, and doses to organs (except the gallbladder and urinary bladder) were significantly correlated between mice and humans. The mean effective [ 18 F]-5-FU dose was higher in humans (0.0124 mSv/MBq) than in mice (0.0058 mSv/MBq). Conclusion: Biodistribution and radiation dosimetry of [ 18 F]-5-FU were compared between humans and mice: biodistribution in mice and humans was similar. Data from mice underestimated the effective dose in humans, suggesting that clinical measurements are needed for more detailed dose estimation in order to ensure radiation safety. The observed effective doses suggest the feasibility of [ 18 F]-5-FU PET/CT for human studies. - Highlights: ► The radiation dose and biodistribution of [ 18 F]-5-FU were estimated from mouse and human data. ► The biodistribution of [ 18 F]-5-FU of mouse and human was corresponded. ► Estimated absorbed radiation doses for organs

  18. CT dosimetry computer codes: Their influence on radiation dose estimates and the necessity for their revision under new ICRP radiation protection standards

    International Nuclear Information System (INIS)

    Kim, K. P.; Lee, J.; Bolch, W. E.

    2011-01-01

    Computed tomography (CT) dosimetry computer codes have been most commonly used due to their user friendliness, but with little consideration for potential uncertainty in estimated organ dose and their underlying limitations. Generally, radiation doses calculated with different CT dosimetry computer codes were comparable, although relatively large differences were observed for some specific organs or tissues. The largest difference in radiation doses calculated using different computer codes was observed for Siemens Sensation CT scanners. Radiation doses varied with patient age and sex. Younger patients and adult females receive a higher radiation dose in general than adult males for the same CT technique factors. There are a number of limitations of current CT dosimetry computer codes. These include unrealistic modelling of the human anatomy, a limited number of organs and tissues for dose calculation, inability to alter patient height and weight, and non-applicability to new CT technologies. Therefore, further studies are needed to overcome these limitations and to improve CT dosimetry. (authors)

  19. The use of polyvinyl chloride dyed with bromo cresol purple in radiation dosimetry

    International Nuclear Information System (INIS)

    Kattan, M.; Al-Kassiri, H.; Daher, Y.

    2010-09-01

    In this work,the use of polyvinyl chloride (PVC) dyed with Bromo cresol purple in high dose radiation dosimetry has been studied according to the radio chromic change using visible spectrophotometry. The results show linear relationship between the relative absorbance (response) and the absorbed dose at the wavelength 417 nm in the range of 0-50 kGy. Dose rate, irradiation temperature, dye intensity have been investigated and found to be independent of the response. The effects of post-irradiation storage in dark and indirect daylight conditions on dosimetry performance are discussed. (Author)

  20. Radiation dosimetry using nano-BaSO{sub 4}:Eu

    Energy Technology Data Exchange (ETDEWEB)

    Pandey, A.; Sharma R, K. [University of Delhi, Department of Physics, Sri Venkateswara College, Benito Juarez Road, Dhaula Kuan, 110021 New Delhi (India); Bahl, S.; Kumar, P. [Medical Physics Unit, IRCH, AIIMS, 110029 New Delhi (India); Pal L, S., E-mail: apandey@svc.ac.in [Inter-University Accelerator Centre, Aruna Asaf Ali Marg, 110067 New Delhi (India)

    2015-10-15

    Nanocrystalline barium sulfate doped with europium (BaSO{sub 4}:Eu) was successfully prepared by the chemical co-precipitation technique and its thermoluminescence (Tl) dosimetry characteristics were studied for gamma radiation. Initially the dopant (Eu) concentration was varied, starting from 0.05 mol % to up to 1.00 mol %, and it was found that the nano phosphor BaSO{sub 4}:Eu with the dopant concentration of 0.2 mol % had the highest sensitivity within the given lot. The nano phosphor was also optimized for its annealing temperature in order to obtain the best results and was thereafter tested for its reusability and fading features. Further the nano phosphor was compared with the commercially available standard Tl dosimeter material LiF:Mg,Ti (popularly referred to as TLD-100) and it was found that the nano phosphor not only had a higher Tl sensitivity compared to the standard material over a wide range of doses but also had a Tl response which was linear even beyond the dose of 1 kGy. Linearity in Tl response to up to such high doses (∼1 kGy) is typical of nanocrystalline Tl phosphors. All the samples were irradiated by Co-60 source (having 1.25 MeV average energy) of gamma radiation. In order to test the energy independence of the nano phosphor (an important characteristic of an ideal Tl dosimeter) further studies are being carried out to examine the response of the nano phosphor to ionizing radiations of different energies. (Author)

  1. Radiation processing and high-dose dosimetry at ANSTO

    International Nuclear Information System (INIS)

    Gant, G.J.; Saunders, M.; Banos, C.; Mo, L.; Davies, J.; Evans, O.

    2001-01-01

    The Radiation Technology group at ANSTO is part of the Physics Division and provides services and advice in the areas of gamma irradiation and high-dose dosimetry. ANSTO's irradiation facilities are designed for maximum dose uniformity and provide a precision irradiation service unique in Australia. Radiation Technology makes and sells reference and transfer standard dosimeters which are purchased by users and suppliers of commercial irradiation services in Australia and the Asia-Pacific region. A calibration service is also provided for dosimeters purchased from other suppliers

  2. Radiation dosimetry in Hiroshima and Nagasaki atomic bomb survivors

    Energy Technology Data Exchange (ETDEWEB)

    Arakawa, E T

    1959-01-01

    This report summarizes the present state of knowledge in dosimetry of the Hiroshima-Nagasaki A-bomb survivors. Data have been presented on the physical factors involved in the two cities and on attenuation of radiation by various shielding situations. This information is being used to estimate a tentative radiation dose to individual A-bomb survivors. It should be emphasized that many important problems remain to be solved before accurate doses can be assigned to individual survivors. Such information will greatly strengthen investigation of biological consequences of instantaneous doses of gamma and neutron irradiation in men. 18 references, 9 figures.

  3. Computer codes in nuclear safety, radiation transport and dosimetry

    International Nuclear Information System (INIS)

    Bordy, J.M.; Kodeli, I.; Menard, St.; Bouchet, J.L.; Renard, F.; Martin, E.; Blazy, L.; Voros, S.; Bochud, F.; Laedermann, J.P.; Beaugelin, K.; Makovicka, L.; Quiot, A.; Vermeersch, F.; Roche, H.; Perrin, M.C.; Laye, F.; Bardies, M.; Struelens, L.; Vanhavere, F.; Gschwind, R.; Fernandez, F.; Quesne, B.; Fritsch, P.; Lamart, St.; Crovisier, Ph.; Leservot, A.; Antoni, R.; Huet, Ch.; Thiam, Ch.; Donadille, L.; Monfort, M.; Diop, Ch.; Ricard, M.

    2006-01-01

    The purpose of this conference was to describe the present state of computer codes dedicated to radiation transport or radiation source assessment or dosimetry. The presentations have been parted into 2 sessions: 1) methodology and 2) uses in industrial or medical or research domains. It appears that 2 different calculation strategies are prevailing, both are based on preliminary Monte-Carlo calculations with data storage. First, quick simulations made from a database of particle histories built though a previous Monte-Carlo simulation and secondly, a neuronal approach involving a learning platform generated through a previous Monte-Carlo simulation. This document gathers the slides of the presentations

  4. Quality management system in the CIEMAT Radiation Dosimetry Service.

    Science.gov (United States)

    Martín, R; Navarro, T; Romero, A M; López, M A

    2011-03-01

    This paper describes the activities realised by the CIEMAT Radiation Dosimetry Service (SDR) for the implementation of a quality management system (QMS) in order to achieve compliance with the requirements of ISO/IEC 17025 and to apply for the accreditation for testing measurements of radiation dose. SDR has decided the accreditation of the service as a whole and not for each of its component laboratories. This makes it necessary to design a QMS common to all, thus ensuring alignment and compliance with standard requirements, and simplifying routine works as possible.

  5. Dosimetry Methods for Human Exposure to Non-Ionising Radiation

    International Nuclear Information System (INIS)

    Poljak, D.; Sarolic, A.; Doric, V.; Peratta, C.; Peratta, A.

    2011-01-01

    The paper deals with human exposure to electromagnetic fields from extremely low frequencies (ELF) to GSM frequencies. The problem requires (1) the assessment of external field generated by electromagnetic interference (EMI) source at a given frequency (incident field dosimetry) and then (2) the assessment of corresponding fields induced inside the human body (internal field dosimetry). Several methods used in theoretical and experimental dosimetry are discussed within this work. Theoretical dosimetry models at low frequencies are based on quasistatic approaches, while analyses at higher frequencies use the full-wave models. Experimental techniques involve near and far field measurement. Human exposure to power lines, transformer substations, power line communication (PLC) systems, Radio Frequency Identification (RFID) antennas and GSM base station antenna systems is analyzed. The results o are compared to the exposure limits proposed by relevant safety guidelines. Theoretical incident dosimetry used in this paper is based on the set of Pocklington integro-differential equations for the calculation of the current distribution and subsequently radiated field from power lines. Experimental incident dosimetry techniques involve measurement techniques of fields radiated by RFID antennas and GSM base station antennas. First example set of numerical results is related to the internal dosimetry of realistic well-grounded body model exposed to vertical component of the electric field E = 10 kV/m generated by high voltage power line. The results obtained via the HNA model exceed the ICNIRP basic restrictions for public exposure (2 mA/m 2 ) in knee (8.6 mA/m 2 ) and neck (9.8 mA/m 2 ) and for occupational exposure (10 mA/m 2 ) in ankle (32 mA/m 2 ). In the case of a conceptual model of a realistic human body inside a transformer substation room touching a control panel at the potential φ0 = 400 V and with two scenarios for dry-air between worker's hand and panel, the values

  6. 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.)

  7. Plastic scintillation dosimetry for radiation therapy: minimizing capture of Cerenkov radiation noise

    International Nuclear Information System (INIS)

    Beddar, A Sam; Suchowerska, Natalka; Law, Susan H

    2004-01-01

    Over the last decade, there has been an increased interest in scintillation dosimetry using small water-equivalent plastic scintillators, because of their favourable characteristics when compared with other more commonly used detector systems. Although plastic scintillators have been shown to have many desirable dosimetric properties, as yet there is no successful commercial detector system of this type available for routine clinical use in radiation oncology. The main factor preventing this new technology from realizing its full potential in commercial applications is the maximization of signal coupling efficiency and the minimization of noise capture. A principal constituent of noise is Cerenkov radiation. This study reports the calculated capture of Cerenkov radiation by an optical fibre in the special case where the radiation is generated by a relativistic particle on the fibre axis and the fibre axis is parallel to the Cerenkov cone. The fraction of radiation captured is calculated as a function of the fibre core refractive index and the refractive index difference between the core and the cladding of the fibre for relativistic particles. This is then used to deduce the relative intensity captured for a range of fibre core refractive indices and fibre core-cladding refractive index differences. It is shown that the core refractive index has little effect on the amount of radiation captured compared to the refractive index difference. The implications of this result for the design of radiation therapy plastic scintillation dosimeters are considered

  8. Gamma Radiation Dosimetry Using Tellurium Dioxide Thin Film Structures

    Directory of Open Access Journals (Sweden)

    Olga Korostynska

    2002-08-01

    Full Text Available Thin films of Tellurium dioxide (TeO2 were investigated for γ-radiation dosimetry purposes. Samples were fabricated using thin film vapour deposition technique. Thin films of TeO2 were exposed to a 60Co γ-radiation source at a dose rate of 6 Gy/min at room temperature. Absorption spectra for TeO2 films were recorded and the values of the optical band gap and energies of the localized states for as-deposited and γ-irradiated samples were calculated. It was found that the optical band gap values were decreased as the radiation dose was increased. Samples with electrical contacts having a planar structure showed a linear increase in current values with the increase in radiation dose up to a certain dose level. The observed changes in both the optical and the electrical properties suggest that TeO2 thin film may be considered as an effective material for room temperature real time γ-radiation dosimetry.

  9. Radiolabeled blood cells: radiation dosimetry and significance

    International Nuclear Information System (INIS)

    Thakur, M.L.

    1986-01-01

    Over the past few years blood cells labeled with In-111 have become increasingly useful in clinical diagnosis and biomedical research. Indium-111 by the virtue of its physical characteristics and ability to bind to cell cytoplasmic components, provides an excellent cell tracer and thereby, allows investigators to monitor in vivo cell distribution by external imaging and help determine a course of regimen in treating life threatening diseases. Due to natural phenomena such as margination, blood pool, and reticuloendothelial cell activity, in the normal state, depending upon the cell type and the quality of cell preparations, 30%-50% of the administered radioactivity is immediately distributed in the liver, spleen and bone marrow. Over a period of time the radioactivity in these organs slightly increases and decays with a physical half-life of In-111. The resulting radiation dose to these organs ranges between 1-25 rads/mCi In-111 administered. The authors have developed a new In-111 labeling technique which preserves platelet ultrastructure and shown that human lymphocytes labeled with In-111 in mixed leukocytes preparations a) are only 0.003% of the total -body lymphocytes population and b) are killed. The consequence if any may be considered insignificant, particularly because 5.6% metaphases from normal men and 6.5% metaphases from normal women in the US have at least one chromosome aberration. Calculations have shown that the risk of fatal hematological malignancy, over a 30 year period, in recipients of 100 million lymphocytes labeled with 100 μCi In-111 is 1/million patients studied. This risk is less than 0.025% of the 1981 spontaneous cancer patient rate in the country. 32 references, 10 tables

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

    International Nuclear Information System (INIS)

    Talpalariu, Corneliu; Talpalariu, Jeni; Matei, Corina; Lita, Ioan; Popescu, Oana

    2010-01-01

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

  11. Effect of respiratory motion on internal radiation dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Xie, Tianwu [Division of Nuclear Medicine and Molecular Imaging, Geneva University Hospital, Geneva 4 CH-1211 (Switzerland); Zaidi, Habib, E-mail: habib.zaidi@hcuge.ch [Division of Nuclear Medicine and Molecular Imaging, Geneva University Hospital, Geneva 4 CH-1211 (Switzerland); Geneva Neuroscience Center, Geneva University, Geneva CH-1205 (Switzerland); Department of Nuclear Medicine and Molecular Imaging, University of Groningen, University Medical Center Groningen, Groningen 9700 RB (Netherlands)

    2014-11-01

    Purpose: Estimation of the radiation dose to internal organs is essential for the assessment of radiation risks and benefits to patients undergoing diagnostic and therapeutic nuclear medicine procedures including PET. Respiratory motion induces notable internal organ displacement, which influences the absorbed dose for external exposure to radiation. However, to their knowledge, the effect of respiratory motion on internal radiation dosimetry has never been reported before. Methods: Thirteen computational models representing the adult male at different respiratory phases corresponding to the normal respiratory cycle were generated from the 4D dynamic XCAT phantom. Monte Carlo calculations were performed using the MCNP transport code to estimate the specific absorbed fractions (SAFs) of monoenergetic photons/electrons, the S-values of common positron-emitting radionuclides (C-11, N-13, O-15, F-18, Cu-64, Ga-68, Rb-82, Y-86, and I-124), and the absorbed dose of {sup 18}F-fluorodeoxyglucose ({sup 18}F-FDG) in 28 target regions for both the static (average of dynamic frames) and dynamic phantoms. Results: The self-absorbed dose for most organs/tissues is only slightly influenced by respiratory motion. However, for the lung, the self-absorbed SAF is about 11.5% higher at the peak exhale phase than the peak inhale phase for photon energies above 50 keV. The cross-absorbed dose is obviously affected by respiratory motion for many combinations of source-target pairs. The cross-absorbed S-values for the heart contents irradiating the lung are about 7.5% higher in the peak exhale phase than the peak inhale phase for different positron-emitting radionuclides. For {sup 18}F-FDG, organ absorbed doses are less influenced by respiratory motion. Conclusions: Respiration-induced volume variations of the lungs and the repositioning of internal organs affect the self-absorbed dose of the lungs and cross-absorbed dose between organs in internal radiation dosimetry. The dynamic

  12. Classical microdosimetry in radiation protection dosimetry and monitoring

    International Nuclear Information System (INIS)

    Waker, A.J.; Schrewe, U.; Burmeister, J.; Dubeau, J.; Surette, R.A.

    2002-01-01

    Classical microdosimetry concerns the measurement and analysis of the spectrum of radiation energy deposition events in simulated microscopic tissue-equivalent sites. Over the past three decades, classical microdosimetry has been extensively applied for the direct measurement of dosimetric quantities, such as the ambient dose equivalent, and for the spectroscopic properties of tissue-equivalent proportional counters that have led to the methods of mixed-field analysis and particle identification. This paper reviews some of the special applications of classical microdosimetry such as the determination of kerma coefficients, differential dosimetry and aviation dosimetry. Also reviewed are some of the technological innovations related to the application of microdosimetry in operational health physics and in particular the development of multi-element proportional counters and detectors based on gas microstrip technology. (author)

  13. Handbook of anatomical models for radiation dosimetry

    CERN Document Server

    Eckerman, Keith F

    2010-01-01

    Covering the history of human model development, this title presents the major anatomical and physical models that have been developed for human body radiation protection, diagnostic imaging, and nuclear medicine therapy. It explores how these models have evolved and the role that modern technologies have played in this development.

  14. Optically stimulated luminescence dosimetry performance of natural Brazilian topaz exposed to beta radiation

    International Nuclear Information System (INIS)

    Bernal, R.; Souza, D. N.; Valerio, M. E. G.; Cruz-Vazquez, C.; Barboza-Flores, M.

    2006-01-01

    Optically stimulated luminescence (OSL) has become the technique of choice in many areas of dosimetry. Natural materials like topaz are available in large quantities in Brazil and other countries. They have been studied to investigate the possibility of use its thermoluminescence (TL) properties for dosimetric applications. In this work, we investigate the possibility of utilising the OSL properties of natural Brazilian topaz in dosimetry. Bulk topaz samples were exposed to doses up to 100 Gy of beta radiation and the integrated OSL as a function of the dose showed linear behaviour. The fading occurs in the first 20 min after irradiation but it is <6% of the integrated OSL measured shortly after exposure. We conclude that natural colourless topaz is a very suitable phosphor for OSL dosimetry. (authors)

  15. A practical three-dimensional dosimetry system for radiation therapy

    International Nuclear Information System (INIS)

    Guo Pengyi; Adamovics, John; Oldham, Mark

    2006-01-01

    There is a pressing need for a practical three-dimensional (3D) dosimetry system, convenient for clinical use, and with the accuracy and resolution to enable comprehensive verification of the complex dose distributions typical of modern radiation therapy. Here we introduce a dosimetry system that can achieve this challenge, consisting of a radiochromic dosimeter (PRESAGE trade mark sign ) and a commercial optical computed tomography (CT) scanning system (OCTOPUS trade mark sign ). PRESAGE trade mark sign is a transparent material with compelling properties for dosimetry, including insensitivity of the dose response to atmospheric exposure, a solid texture negating the need for an external container (reducing edge effects), and amenability to accurate optical CT scanning due to radiochromic optical contrast as opposed to light-scattering contrast. An evaluation of the performance and viability of the PRESAGE trade mark sign /OCTOPUS, combination for routine clinical 3D dosimetry is presented. The performance of the two components (scanner and dosimeter) was investigated separately prior to full system test. The optical CT scanner has a spatial resolution of ≤1 mm, geometric accuracy within 1 mm, and high reconstruction linearity (with a R 2 value of 0.9979 and a standard error of estimation of ∼1%) relative to independent measurement. The overall performance of the PRESAGE trade mark sign /OCTOPUS system was evaluated with respect to a simple known 3D dose distribution, by comparison with GAFCHROMIC[reg] EBT film and the calculated dose from a commissioned planning system. The 'measured' dose distribution in a cylindrical PRESAGE trade mark sign dosimeter (16 cm diameter and 11 cm height) was determined by optical-CT, using a filtered backprojection reconstruction algorithm. A three-way Gamma map comparison (4% dose difference and 4 mm distance to agreement), between the PRESAGE trade mark sign , EBT and calculated dose distributions, showed full agreement in

  16. Review of the correlation between results of cytogenetic dosimetry from blood lymphocytes and EPR dosimetry from tooth enamel for victims of radiation accidents

    International Nuclear Information System (INIS)

    Khvostunov, I.K.; Ivannikov, A.I.; Skvortsov, V.G.; Golub, E.V.; Nugis, V. Yu.

    2015-01-01

    The goal of this study was to compare dose estimates from electron paramagnetic resonance (EPR) dosimetry with teeth and cytogenetic dosimetry with blood lymphocytes for 30 victims of radiation accidents. The whole-body exposures estimated by tooth enamel EPR dosimetry were ranging from 0.01 to 9.3 Gy. Study group comprised victims exposed to acute and prolonged irradiation at high and low dose rate in different accidents. Blood samples were taken from each of them for cytogenetic analysis. Aberrations were scored and analysed according to International Atomic Energy Agency (IAEA) guidelines for conventional and FISH analysis. Tooth samples were collected in dental clinics after they had been extracted during ordinary practice. EPR dosimetry was performed according to the IAEA protocol. EPR dosimetry showed good correlation with dosimetry based on chromosomal analysis. All estimations of cytogenetic dose below detection limit coincide with EPR dose estimates within the ranges of uncertainty. The differences between cytogenetic and EPR assays may occur in a case of previous unaccounted exposure, non-homogeneous irradiation and due to contribution to absorbed dose from neutron irradiation. (authors)

  17. Role of cytogenetic techniques in biological dosimetry of absorbed radiation

    International Nuclear Information System (INIS)

    Rao, B.S.

    2016-01-01

    In most of the radiation accidents, physical dosimetric information is rarely available. Further, most of the accidental exposures are non-uniform involving either partial body or localized exposure to significant doses. In such situations, physical dosimetry does not provide reliable dose estimate. It has now been realized that biological dosimetric techniques can play an important role in the assessment of absorbed dose. In recent years, a number of biological indicators of radiation have been identified. These include the kinetics of onset and persistence of prodromal syndromes (radiation sickness), cytogenetic changes in peripheral blood lymphocytes, hematological changes, biochemical indicators, ESR spectroscopy of biological samples, induction of gene mutations in red blood cells, cytogenetic and physiological changes in skin and neurophysiological changes. In general, dosimetric information is derived by a combination of several different methods, as they have potential to serve as prognostic indicators. The role of cytogenetic techniques in peripheral blood lymphocytes (PBL) as biological indicators of absorbed radiation is reviewed here

  18. Numerical analysis for complex thermoluminiscence glow curves.Application to the study of LiF: Ti, Mg and its in radiation dosimetry

    International Nuclear Information System (INIS)

    Gomez Ros, J.M.

    1989-01-01

    A method for the numerical analysis of complex termoluminiscence glow curves based in a modified Marquard Levenberg minimization algorithm is presented. Differents analytical expresions are employed for the individual glow peaks in the cases of first, second and mixed order kinetics, developping aproximated expresions for everyone. These procedures are applied to the caracterization of Lithium Fluoride studying the kinetic order of peaks IV and V. The results obtained permits an interpretation of the complex isothermal decay observed at 165 0 C compatible whith first order kinetics process for both peaks. The aplication to thermoluminiscent dosimetry (TLD) is also described. Other numerical methods are specifically developped to operate whith LiF 8TLD-100) in specific dosimetric aplications of TLD, such environ mental monitoring and mailed dosimetry systems for quality assurance in radiotherapy facilities. The reduction in the minimun detectable dose and the increment in the fiability of the meassurements are some of the advantages obtained over conventional evaluation systems. (Author)

  19. Dye film dosimetry for radiation processing

    International Nuclear Information System (INIS)

    Humphreys, J.C.; McLaughlin, W.L.

    1981-01-01

    Commercially available plastic films containing dyes or dye precursors are convenient dosimeters and imaging media for electron beams or photons used for industrial radiation processing. As ''grainless'' imaging systems having thicknesses down to a few micrometers, they provide high spatial resolution for determining detailed absorbed dose distributions through microdensitometric analysis. The radiation absorption properties of these systems are adjusted by changing film composition so that the dosimeter materials can be made to simulate the material of interest undergoing irradiation. Other advantages include long-term stability, dose-rate independence, and ease of use and calibration. Radiochromic dye films with thicknesses varying from 0.005 to 1 mm are presently used to monitor electron-beam or gamma-ray doses from 10 to 10 5 Gy (10 3 to 10 7 rad), typical of those encountered in medical applications, radiation curing of polymeric composites, wire and cable insulation, shrinkable plastic tubing and film, as well as sterilization of medical supplies and treatment of municipal and industrial wastes. An NBS calibration service to industry involves the traceability of standard 60 Co gamma ray absorbed dose measurements by means of these films employed as transfer standards

  20. 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

  1. Study of TL and optically stimulated luminescence of K{sub 2}Ca{sub 2}(SO{sub 4}){sub 3}:Cu nanophosphor for radiation dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Mandlik, Nandkumar [Department of Physics, University of Pune, Pune 411007 (India); Department of Physics, Ferguson College, Pune 411004 (India); Sahare, P.D. [Department of Physics and Astrophysics, University of Delhi, Delhi 110007 (India); Kulkarni, M.S. [Radiological Physics and Advisory Division, BARC, Mumbai 400085, Maharashtra (India); Bhatt, B.C. [Radiation Safety Systems Division, BARC, Mumbai 400085, Maharashtra (India); Bhoraskar, V.N. [Department of Physics, University of Pune, Pune 411007 (India); Dhole, S.D., E-mail: sanjay@physics.unipune.ac.in [Department of Physics, University of Pune, Pune 411007 (India)

    2014-02-15

    Nanocrytstalline K{sub 2}Ca{sub 2}(SO{sub 4}){sub 3}:Cu phosphor was synthesized by the chemical co-precipitation method and annealed at different temperatures (400–900 °C) for 2 h. The XRD spectrum shows the cubic structure with crystallite size ∼20 nm. The same was also confirmed from the TEM image which shows the formation of nanorods having diameter ∼20 nm and length of ∼200 nm. They are found to be quite uniform in shapes and sizes. These samples were irradiated with gamma radiation for the doses varying from 0.01 Gy to 10 kGy and their thermoluminescence (TL) characteristics and continuous wave optically stimulated luminescence (CW-OSL) have been studied. The sample annealed at 700 °C was found to be most sensitive than others. The glow curves of the nanophosphor show a major peak at around 175 °C and other two peaks of low intensity at around 85 °C and 305 °C. The traps responsible for the three thermoluminescence peaks in K{sub 2}Ca{sub 2}(SO{sub 4}){sub 3}:Cu are also found to be sensitive to the OSL. The qualitative correlation between TL peaks and CW-OSL response is established. The TL response of the sample annealed at 700 °C for 2 h and irradiated with different gamma doses shows a linear behavior from 0.01 up to 300 Gy and become sublinear in the range of 300 Gy–1 kGy before it saturates with further increase in the dose, while, the OSL response of the same sample shows linearity up to 1 kGy. Simple glow curve structure, easy method of synthesis, and linear dose response make the nanocrystalline phosphor a good candidate for radiation dosimetry, especially for the estimation of high doses of gamma rays where the microcrystalline phosphors generally saturate. -- Highlights: • Nanocrytstalline K{sub 2}Ca{sub 2}(SO{sub 4}){sub 3}:Cu phosphor was synthesized by the chemical co-precipitation method. • Thermoluminescence (TL) and continuous wave optically stimulated luminescence (CW-OSL) characteristics have been studied. • The TL glow

  2. Radiation dosimetry in human bone using electron paramagnetic resonance

    International Nuclear Information System (INIS)

    Breen, S.L.

    1995-01-01

    Accurate measurements of dose in bone are required in order to improve the dosimetry of systemic radiotherapy for osseous metastases. Bone is an integrating dosimeter which records the radiation history of the skeleton. During irradiation, electrons become trapped in the crystalline component of bone mineral (hydroxyapatite). The traps are very stable; at room temperature, emptying of the traps occurs with a half-life of many years. The population of trapped unpaired electrons is proportional to the radiation dose administered to the bone and can be measured in excised bone samples using electron paramagnetic resonance (EPR). EPR spectra of synthetic hydroxyapatite, irradiated with Co-60, were obtained at room temperature and at 77 K. At room temperature, the radiation-induced signal, with a g-value of 2.001 ± 0.001 increased linearly with absorbed dose above a lower threshold of 3 Gy, up to doses of 200 Gy. In contrast with pure hydroxyapatite, EPR spectra of excised human bone showed a broad 'native' signal, due to the organic component of bone, which masks the dosimetrically important signal. This native signal is highly variable from sample to sample and precludes the use of EPR as an absolute dosimetry technique. However, after subtraction of the background signal, irradiated human bone showed a linear response with a lower limit of measurement similar to that of synthetic hydroxyapatite. Bone is an in vivo linear dosimeter which can be exploited to develop accurate estimates of the radiation dose delivered during systemic radiotherapy and teletherapy. However, improved sensitivity of the EPR dosimetry technique is necessary before it can be applied reliably in clinical situations. (author)

  3. Computational anthropomorphic phantoms for radiation protection dosimetry: evolution and prospects

    International Nuclear Information System (INIS)

    Lee, Choonsik; Lee, Jaiki

    2006-01-01

    Computational anthropomorphic phantoms are computer models of human anatomy used in the calculation of radiation dose distribution in the human body upon exposure to a radiation source. Depending on the manner to represent human anatomy, they are categorized into two classes: stylized and tomographic phantoms. Stylized phantoms, which have mainly been developed at the Oak Ridge National Laboratory (ORNL), describe human anatomy by using simple mathematical equations of analytical geometry. Several improved stylized phantoms such as male and female adults, pediatric series, and enhanced organ models have been developed following the first hermaphrodite adult stylized phantom, Medical Internal Radiation Dose (MIRD)-5 phantom. Although stylized phantoms have significantly contributed to dosimetry calculation, they provide only approximations of the true anatomical features of the human body and the resulting organ dose distribution. An alternative class of computational phantom, the tomographic phantom, is based upon three-dimensional imaging techniques such as Magnetic Resonance (MR) imaging and Computed Tomography (CT). The tomographic phantoms represent the human anatomy with a large number of voxels that are assigned tissue type and organ identity. To date, a total of around 30 tomographic phantoms including male and female adults, pediatric phantoms, and even a pregnant female, have been developed and utilized for realistic radiation dosimetry calculation. They are based on MRI/CT images or sectional color photos from patients, volunteers or cadavers. Several investigators have compared tomographic phantoms with stylized phantoms, and demonstrated the superiority of tomographic phantoms in terms of realistic anatomy and dosimetry calculation. This paper summarizes the history and current status of both stylized and tomographic phantoms, including Korean computational phantoms. Advantages, limitations, and future prospects are also discussed

  4. Application of monomer/polymer gel dosimetry to study the effects of tissue inhomogeneities on intensity-modulated radiation therapy (IMRT) dose distributions.

    Science.gov (United States)

    Vergote, Koen; De Deene, Yves; Claus, Filip; De Gersem, Werner; Van Duyse, Bart; Paelinck, Leen; Achten, Eric; De Neve, Wilfried; De Wagter, Carlos

    2003-04-01

    When planning an intensity-modulated radiation therapy (IMRT) treatment in a heterogeneous region (e.g. the thorax), the dose computation algorithm of a treatment planning system may need to account for these inhomogeneities in order to obtain a reliable prediction of the dose distribution. An accurate dose verification technique such as monomer/polymer gel dosimetry is suggested to verify the outcome of the planning system. The effects of low-density structures: (a) on narrow high-energy (18 MV) photon beams; and (b) on a class-solution IMRT treatment delivered to a thorax phantom have been examined using gel dosimetry. The used phantom contained air cavities that could be filled with water to simulate a homogeneous or heterogeneous configuration. The IMRT treatment for centrally located lung tumors was delivered on both cases, and gel derived dose maps were compared with computations by both the GRATIS and Helax-TMS planning system. Dose rebuildup due to electronic disequilibrium in a narrow photon beam is demonstrated. The gel measurements showed good agreement with diamond detector measurements. Agreement between measured IMRT dose maps and dose computations was demonstrated by several quantitative techniques. An underdosage of the planning target volume (PTV) was revealed. The homogeneity of the phantom had only a minor influence on the dose distribution in the PTV. An expansion of low-level isodoses in the lung volume was predicted by collapsed cone computations in the heterogeneous case. For the class-solution described, the dose in centrally located mediastinal tumors can be computed with sufficient accuracy, even when neglecting the lower lung density. Polymer gel dosimetry proved to be a valuable technique to verify dose calculation algorithms for IMRT in 3D in heterogeneous configurations.

  5. Transient impedance changes in venous endothelial monolayers as a biological radiation dosimetry response

    Directory of Open Access Journals (Sweden)

    Erik Fossum Young

    2012-10-01

    Full Text Available In March of 2011, a magnitude 9.0 earthquake and subsequent 14 m-high tsunami caused major damage to the Fukushima Daiichi nuclear power plant in Japan.  While cancer incidence in the radiation-exposed population is a logical concern, the complex effects of radiation on the heart and cardiovascular system are also of interest.  Immediate and early vascular radiation effects could be exploited as a dosimetry modality.  To test whether non-coronary vasculature exhibited transient perturbation in barrier function, video microscopy studies and Electric Cell Substrate Impedance Sensing technology were used to probe very subtle changes in primary human vascular endothelium.  Human umbilical vein endothelial cell (HUVEC monolayers exhibit a transient, statistically significant decrease (P = 0.017 in monolayer resistance 3 h after irradiation with 5.0 Gy of g rays.  Radiation induced perturbations in HUVEC monolayer permeability are similar in magnitude and kinetics to those observed in coronary arterial endothelium.  Therefore, at least two types of vasculature respond to radiation on ECIS arrays with an early transient disruption in permeability.  The finding supports the use of early passage HUVECs for use in bioelectric dosimetry studies of vasculature and suggests that permeability of vessels could potentially serve as a biological dosimetry tool.

  6. Patient dosimetry in intravascular radiation therapy

    International Nuclear Information System (INIS)

    Putte, S. van de; Thierens, H.; Taeymans, Y.

    2001-01-01

    Percutaneous transluminal coronary angioplasty is a well-accepted method for nonsurgical myocardial revascularization. However, the long-term success of this method is limited by the occurrence of restenosis. Endovascular brachytherapy has been put forward as a means to avoid restenosis. Since this technique involves the placement of a radioactive source in a catheter in the patient's arteries, the possible radiation risk should be considered. In this paper the effective dose of the patient associated with the use of Iridium-192 for IRT treatment has been calculated using Monte Carlo techniques. To put the results into perspective the effective dose form the PTCA procedure was also calculated using the same techniques. Calculations were based on the measurement of DAP (Dose Area Product) for the procedure. We found a mean effective dose of 9 mSv for both the PTCA procedures as for the IRT treatment. Thus leading to the conclusion that, from the perspective of radiation burden, the elimination of one PTCA procedure through the use of IRT is a benefit for the patient. (author)

  7. Radiation dosimetry for bolus administration of oxygen-15-water

    International Nuclear Information System (INIS)

    Brihaye, C.; Depresseux, J.C.; Comar, D.

    1995-01-01

    The authors describe the development of a biokinetic model which permits an estimation of organ activities and the dosimetry of a bolus of 15 O-water. The aim of this study was to estimate time-activity functions and deduce the cumulated activities in different organs so that the radiation absorbed dose values can be estimated. The model used includes the right heart chambers, lungs, left heart chambers, brain, liver, kidneys, muscles, gasrointestinal tract and the remainder of the body. Activity in an organ will decay by physical decay with the decay constant, γ, and can diffuse in the organ. An exception is the heart, where blood is ejected from the heart chambers. Depending on the location of the organ in relation to the blood sampling point, organ activities can be calculated by convolution or deconvolution. The radiation absorbed dose values were estimated and an effective dose equivalent H E of 1.16 μSv/MBq (4.32 mrem/mCi) as well as an effective dose E of 1.15 μSv/MBq (4.25 mrem/mCi) were calculated. The cumulated activities in select organs measured by PET gave good agreement with the values calculated by this model. The values of effective dose equivalent and effective dose for bolus administration of 15 O-water calculated from the absorbed doses estimated by the proposed kinetic model are almost three times higher than those previously published. A total of 8700 MBq (235 mCi) of 15 O-water can be administered if an effective dose of 10 mSv (1 rem) is accepted. 32 refs., 5 figs., 2 tabs

  8. Comparisons of radiation dosimetry between Louvain (Belgium) and Edinburgh (UK)

    International Nuclear Information System (INIS)

    Law, J.; Prignot, M.; Wambersie, A.

    1975-01-01

    A comparison of radiation dosimetry performed between Edinburgh and Louvain using the FeSO 4 system, was reported. The procedure adopted provided comparisons both of solution response and of spectrophotometer calibration, and also provided a comparison of ionization dosimetry and irradiation techniques at the two centres. Therefore dosimeter solutions were prepared in both centres, FeSO 4 samples were irradiated either in Edinburgh (4 MV X-rays) or in Louvain ( 60 Co), finally optical densities were measured using the spectrophotometer of either centre. For these different comparisons, the samples were transported once of twice. An agreement between the two centres better than 1% was observed, both for ionization dosimetry and irradiation techniques and for spectrophotometer calibration. The ratio of Louvain to Edinburgh solution response was found close to 1 (0.998+-0.004). However, a previous comparison showed a discrepancy of 2% which illustrates the care needed in checking the purity of the solution components and mainly of the distilled water

  9. Application of an alanine dosimetry system for industrial irradiation and radiation protection

    International Nuclear Information System (INIS)

    Gohs, U.

    1996-01-01

    This paper reports the application of alanine dosimetry in radiation processing. Continuous checks of the EPR measuring conditions as well as using high-quality alanine dosimeters and consistent technique for dose determination guarantee an accuracy of about ± 3% intermediate dose levels. The alanine dosimetry system was applied for dose mapping measurements during irradiator qualification and performance qualification of different products, routine dosimetry, and special radiation protection applications within the gamma irradiator. (author)

  10. Canadian space agency discipline working group for space dosimetry and radiation science

    International Nuclear Information System (INIS)

    Waker, Anthony; Waller, Edward; Lewis, Brent; Bennett, Leslie; Conroy, Thomas

    2008-01-01

    Full text: One of the great technical challenges in the human and robotic exploration of space is the deleterious effect of radiation on humans and physical systems. The magnitude of this challenge is broadly understood in terms of the sources of radiation, however, a great deal remains to be done in the development of instrumentation, suitable for the space environment, which can provide real-time monitoring of the complex radiation fields encountered in space and a quantitative measure of potential biological risk. In order to meet these research requirements collaboration is needed between experimental nuclear instrumentation scientists, theoretical scientists working on numerical modeling techniques and radiation biologists. Under the auspices of the Canadian Space Agency such a collaborative body has been established as one of a number of Discipline Working Groups. Members of the Space Dosimetry and Radiation Science working group form a collaborative network across Canada including universities, government laboratories and the industrial sector. Three central activities form the core of the Space Dosimetry and Radiation Science DWG. An instrument sub-group is engaged in the development of instruments capable of gamma ray, energetic charged particle and neutron dosimetry including the ability to provide dosimetric information in real-time. A second sub-group is focused on computer modeling of space radiation fields in order to assess the performance of conceptual designs of detectors and dosimeters or the impact of radiation on cellular and sub-cellular biological targets and a third sub-group is engaged in the study of the biological effects of space radiation and the potential of biomarkers as a method of assessing radiation impact on humans. Many working group members are active in more than one sub-group facilitating communication throughout the whole network. A summary progress-report will be given of the activities of the Discipline Working Group and the

  11. Calorimetric dosimetry of reactor radiation; Kalorimetriska dozimetrija reaktorskog zracenja

    Energy Technology Data Exchange (ETDEWEB)

    Radak, B; Markovic, V; Draganic, I [Institute of Nuclear Sciences Boris Kidric, Odeljenje za radijacionu hemiju, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Calorimetric dosimetry of reactor radiation is relatively new reactor dosimetry method and the number of relevant papers is rather small. Some difficulties in applying standard methods (chemical dosemeters, ionization chambers) exist because of the complexity of radiation. In general application of calorimetric dosemeters for measuring absorbed doses is most precise. In addition to adequate choice of calorimetric bodies there is a possibility of determining the yields of each component of the radiation mixture in the total absorbed dose. This paper contains a short review of the basic calorimetry methods and some results of measurements at the RA reactor in Vinca performed by isothermal calorimeter. Kalorimetrijska dozimetrija reaktorskog zracenja je relativno nova metoda dozimetrije reaktora i broj do sada objavljenih radova je vrlo skroman. S obzirom na slozenu prirodu zracenja postoje neke teskoce pri radu sa standardnim metodama (hemijski dozimetri, jonizacione komere). U principu, upotreba kalorimetra za merenje apsorbovanih doza je najegzaktnija. Osim toga, uz pogodni izbor kalorimetrijskih tela postoji mogucnost za odredjivanje doprinosa pojedinih komponenti smese zracenja u totalnoj apsorbovanoj dozi. U tekstu je dat kratak pregled osnovnih metoda kalorimetrije i neki rezultati merenja sa izotermskim kalorimetrom na reaktoru RA u Vinci.

  12. 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

  13. Activities of the Institute of Radiation Protection and Dosimetry on radiation overexposure analysis - results from 1994 to 1997

    International Nuclear Information System (INIS)

    Silva, Francisco C.A. da; Ramalho, Adriana

    1999-01-01

    Since 1985 the Institute of Radiation Protection and Dosimetry has operated a service carried out by a multi-disciplinary Group called Radiation Overexposure analysis Group - GADE. It is composed of specialists in radiation protection and dosimetry and has the main objective of taking coordinated actions on radiation overexposure cases. This paper shows mainly the results got from 1984 to 1997 with the methodology used. It was observed that the cases are falling down due to radiation protection activities in the installation. (author)

  14. Dosimetry of environmental radiations (cosmic ray)

    International Nuclear Information System (INIS)

    Yamasaki, Keizo

    1978-01-01

    Cosmic ray is dominant as environmental radiation, though the experimental determination made on cosmic ray doses is few in Japan. The free air ionization intensity at sea level due to cosmic ray has been estimated in the Bay of Wakasa, Japan, at middle geomagnetic latitude (25 deg. N), in October 1977. The ionization chambers used were two air and one argon types. Where the responses to cosmic and terrestrial gamma rays were equal, the ionization intensity due to cosmic ray was obtained by subtracting the ionization intensity due to terrestrial gamma ray from the total ionization intensity. As the terrestrial gamma ray, (1) U-238 series, Th-232 series, and K-40 in seawater, (2) K-40 in the material of a wooden ship, and (3) Rn-222 and its daughter products in the atmosphere were considered. The result of free air ionization due to cosmic ray with the argon chamber was slightly smaller than those with the other two air chambers; however, both were in good agreement within standard errors. (JPN.)

  15. Application of MOSFET radiation detector for patient dosimetry

    International Nuclear Information System (INIS)

    Soubra, M.; Cygler, J.; Szanto, J.

    1996-01-01

    Purpose: A new direct reading Metal Oxide-Silicon Field Effect Transistor (MOSFET) based radiation detector system has been investigated in a variety of clinical radiotherapy procedures. The aim of this study is to report on the clinical applicability of such a device, its ease of use and on its dosimetric properties that include precision angular and energy dependence. Comparisons of patient dose measurements obtained by the MOSFET based system and the commonly used thermoluminescence dosimeters (TLD) and diodes are discussed. Material and Methods: A commercially available MOSFET dosimetry system that employs dual MOSFET dual bias arrangements has been used in this study. The detector is bonded with the epoxy to the end of a long (1.5 m) flexible cable whose other end is connected to a bias supply box operated by a battery. The bias box can accommodate up to 5 MOSFETs and after radiation exposure the dose can be determined by connecting the detectors to a pre calibrated reader. For the clinical evaluation 5 MOSFETs were used on patients undergoing total body irradiation (TBI) and high dose rate brachytherapy (HDR). The MOSFET detectors were taped to patient surface adjacent to the routinely used TLDs and/or diodes. To examine energy dependence the MOSFET sensitivity (mV/Gy) was determined in relation to a calibrated dose from 6 and 18 MV photon beams. The directional dependence was investigated by placing a MOSFET during irradiation in a special polystyrene insert that can be manually rotated to the required angle. Precision (reproducibility) measurements were made by exposing MOSFETs to multiple fractions of dose in the range of 3 x 10 -2 to 2 Gy. Results: In 3 of TBI trials the diodes measured average dose was within 1.0% of the prescribed dose compared to 3.7% for TLDs and 1.8% for MOSFETs. The MOSFETs average sensitivity for 6 MV was within 2% of the 18 MV photon beam. The reproducibility of MOSFET response was better than 3 % provided the dose per fraction is

  16. EURADOS. A success story for European cooperation in the dosimetry of ionizing radiation

    Energy Technology Data Exchange (ETDEWEB)

    Ruehm, Werner [Helmholtz Zentrum Muenchen, Neuherberg (Germany). German Research Center for Environmental Health (GMBH); Schuhmacher, Helmut [Physikalisch-Technische Bundesanstalt, Braunschweig (Germany)

    2017-10-01

    EURADOS (European Radiation Dosimetry Group) is a European research platform aiming at the promotion of research and development and European cooperation in the field of the dosimetry of ionizing radiation (www.eurados.org). Initially founded in 1982, it was established in 2008 as a non-profit registered society under German law and is currently based in Neuherberg, Germany.

  17. Spectroscopic studies of irradiated glasses: Application in nuclear dosimetry

    International Nuclear Information System (INIS)

    Farah, Khaled

    2010-01-01

    The present work aims to study the effects of ionizing radiation on silicate glasses in order to develop a new dosimetry system simple, precise, stable and inexpensive. Indeed, changes in mechanical properties, optical and paramagnetic glasses when subjected to ionizing radiation. The prediction of long-term behavior, physical aging under irradiation, the glass is paramount. many studies have brought many ways to avoid obscuring glass windows used in nuclear reactors or hot cells and optical devices. Recently, much work has concentrated on the application of the color induced by irradiation for developing a recyclable glass in the glass industry is of great interest economically and environmentally.

  18. Guide for selection and calibration of dosimetry systems for radiation processing

    International Nuclear Information System (INIS)

    2002-01-01

    This guide covers the basis for selecting and calibrating dosimetry systems used to measure absorbed dose in gamma ray or X-ray fields and in electron beams used for radiation processing. It discusses the types of dosimetry systems that may be employed during calibration or on a routine basis as part of quality assurance in commercial radiation processing of products. This guide also discusses interpretation of absorbed dose and briefly outlines measurements of the uncertainties associated with the dosimetry. The details of the calibration of the analytical instrumentation are addressed in individual dosimetry system standard practices. The absorbed-dose range covered is up to 1 MGy (100 Mrad). Source energies covered are from 0.1 to 50 MeV photons and electrons. This guide should be used along with standard practices and guides for specific dosimetry systems and applications covered in other standards. Dosimetry for radiation processing with neutrons or heavy charged particles is not covered in this guide

  19. A Chinese Visible Human-based computational female pelvic phantom for radiation dosimetry simulation

    International Nuclear Information System (INIS)

    Nan, H.; Jinlu, S.; Shaoxiang, Z.; Qing, H.; Li-wen, T.; Chengjun, G.; Tang, X.; Jiang, S. B.; Xiano-lin, Z.

    2010-01-01

    Accurate voxel phantom is needed for dosimetric simulation in radiation therapy for malignant tumors in female pelvic region. However, most of the existing voxel phantoms are constructed on the basis of Caucasian or non-Chinese population. Materials and Methods: A computational framework for constructing female pelvic voxel phantom for radiation dosimetry was performed based on Chinese Visible Human datasets. First, several organs within pelvic region were segmented from Chinese Visible Human datasets. Then, polygonization and voxelization were performed based on the segmented organs and a 3D computational phantom is built in the form of a set of voxel arrays. Results: The generated phantom can be converted and loaded into treatment planning system for radiation dosimetry calculation. From the observed dosimetric results of those organs and structures, we can evaluate their absorbed dose and implement some simulation studies. Conclusion: A voxel female pelvic phantom was developed from Chinese Visible Human datasets. It can be utilized for dosimetry evaluation and planning simulation, which would be very helpful to improve the clinical performance and reduce the radiation toxicity on organ at risk.

  20. Space radiation dosimetry in low-Earth orbit and beyond

    International Nuclear Information System (INIS)

    Benton, E.R.; Benton, E.V.

    2001-01-01

    Space radiation dosimetry presents one of the greatest challenges in the discipline of radiation protection. This is a result of both the highly complex nature of the radiation fields encountered in low-Earth orbit (LEO) and interplanetary space and of the constraints imposed by spaceflight on instrument design. This paper reviews the sources and composition of the space radiation environment in LEO as well as beyond the Earth's magnetosphere. A review of much of the dosimetric data that have been gathered over the last four decades of human space flight is presented. The different factors affecting the radiation exposures of astronauts and cosmonauts aboard the International Space Station (ISS) are emphasized. Measurements made aboard the Mir Orbital Station have highlighted the importance of both secondary particle production within the structure of spacecraft and the effect of shielding on both crew dose and dose equivalent. Roughly half the dose on ISS is expected to come from trapped protons and half from galactic cosmic rays (GCRs). The dearth of neutron measurements aboard LEO spacecraft and the difficulty inherent in making such measurements have led to large uncertainties in estimates of the neutron contribution to total dose equivalent. Except for a limited number of measurements made aboard the Apollo lunar missions, no crew dosimetry has been conducted beyond the Earth's magnetosphere. At the present time we are forced to rely on model-based estimates of crew dose and dose equivalent when planning for interplanetary missions, such as a mission to Mars. While space crews in LEO are unlikely to exceed the exposure limits recommended by such groups as the NCRP, dose equivalents of the same order as the recommended limits are likely over the course of a human mission to Mars

  1. Possible application of an imaging plate to space radiation dosimetry

    International Nuclear Information System (INIS)

    Ohuchi, Hiroko; Yamadera, Akira

    2002-01-01

    Fading correction plays an important role in the application of commercially available BaBrF:Eu 2+ phosphors: imaging plates (IP) to dosimetry. We successfully determined a fading correction equation, which is a function of elapsed time and absolute temperature, as the sum of several exponentially decaying components having different half-lives. In this work, a new method was developed to eliminate a short half-life component by annealing the IP and estimating the radiation dose with the long half-life components. Annealing decreases the effect of fading on the estimated dose, however, it also causes the loss of photo-stimulated luminescence (PSL). Considering an IP as an integral detector for a specific period of up to one month, the practically optimum conditions for quantitative measurement with two types of IP (BAS-TR and BAS-MS) were evaluated by using the fading correction equation, which was obtained after irradiation with a 244 Cm source as the alpha-ray source having a specific radioactivity of 1,638.5 Bq/cm 2 including beta and gamma-ray (alpha energy of 5.763 and 5.805 MeV). Annealing at 80 deg C for 24 hours after irradiation for one month using BAS-MS should minimize the effect of the elapsed time, resulting in sufficient sensitivity. The results demonstrate new possibilities for radiation dosimetry offered by the use of an IP. (author)

  2. Clinical application of radiation dosimetry on X-ray radiotherapy

    International Nuclear Information System (INIS)

    Mizutani, Takeo

    1995-01-01

    In the case of radiotherapy, it is important to give proper dose for a tumor, to be treated with the objective of therapy, and to evaluate the dose, considering dose for other organs at risk to a sufficient extent. To provide an exposure dose at the target volume of tumor parts, it should be required to get a good understanding of the correct dosimetric method and also to apply this to clinical application in practice. All over the country, so as not to produce any difference in the given dose, 'A practical code for the dosimetry of high energy X-rays in radiotherapy' was issued by the Japanese Associations of radiological physicists in 1972. In 1986, it was revised. At about 85% of therapeutic facilities in the country, radiation engineers perform dose measurements and controls. Therefore, I have explained the process of measurement and dose calculation, with the main objective directed at the engineers in charge of the radiotherapy so as to easily radiation dosimetry of X-ray with dosemeters and phantom used at each facility according to the 'practical code'. (author)

  3. Calculation codes in radiation protection, radiation physics and dosimetry

    International Nuclear Information System (INIS)

    2003-01-01

    These scientific days had for objective to draw up the situation of calculation codes of radiation transport, of sources estimation, of radiation doses managements and to draw the future perspectives. (N.C.)

  4. An intercomparison of Canadian external dosimetry processors for radiation protection

    International Nuclear Information System (INIS)

    1989-10-01

    The five Canadian external dosimetry processors have participated in a two-stage intercomparison. The first stage involved dosimeters to known radiation fields under controlled laboratory conditions. The second stage involved exposing dosimeters to radiation fields in power reactor working environments. The results for each stage indicated the dose reported by each processor relative to an independently determined dose and relative to the others. The results of the intercomparisons confirm the original supposition: namely that the average differences in reported dose among five processors are much less than the uncertainty limits recommended by the ICRP. This report provides a description of the experimental methods as well as a discussion of the results for each stage. The report also includes a set of recommendations

  5. Statistical methods to evaluate thermoluminescence ionizing radiation dosimetry data

    International Nuclear Information System (INIS)

    Segre, Nadia; Matoso, Erika; Fagundes, Rosane Correa

    2011-01-01

    Ionizing radiation levels, evaluated through the exposure of CaF 2 :Dy thermoluminescence dosimeters (TLD- 200), have been monitored at Centro Experimental Aramar (CEA), located at Ipero in Sao Paulo state, Brazil, since 1991 resulting in a large amount of measurements until 2009 (more than 2,000). The data amount associated with measurements dispersion, since every process has deviation, reinforces the utilization of statistical tools to evaluate the results, procedure also imposed by the Brazilian Standard CNEN-NN-3.01/PR- 3.01-008 which regulates the radiometric environmental monitoring. Thermoluminescence ionizing radiation dosimetry data are statistically compared in order to evaluate potential CEA's activities environmental impact. The statistical tools discussed in this work are box plots, control charts and analysis of variance. (author)

  6. 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

  7. Dosimetry of electron and gamma radiation with DL-alanine

    International Nuclear Information System (INIS)

    Costa, Z.M. da; Campos, L.L.

    1996-01-01

    A dosimetric method based on the quantitative determination of stabilised free radicals in irradiated crystalline DL-alanine by electron spin resonance (ESR) spectroscopy was proposed as early in 1962. Since then, alanine dosemeters owing to their unique properties have been investigated by many authors and used in dosimetry of various types of radiation, namely gamma rays, electron and neutrons. Alanine is a simple aminoacid, on irradiation at room temperature predominantly free paramagnetic radicals of the type CH 3 -CH-COOH are produced. This paper reports the application of powder DL-alanine/ESR dosemeter for measurement of absorbed dose of gamma radiation from 60 Co sources and reactor nucleus and electron beams from accelerator. The obtained results give useful information about the instrumental care necessary to obtain the needed overall accuracy in determination of absorbed dose. (author)

  8. The MCART radiation physics core: the quest for radiation dosimetry standardization.

    Science.gov (United States)

    Kazi, Abdul M; MacVittie, Thomas J; Lasio, Giovanni; Lu, Wei; Prado, Karl L

    2014-01-01

    Dose-related radiobiological research results can only be compared meaningfully when radiation dosimetry is standardized. To this purpose, the National Institute of Allergy and Infectious Diseases (NIAID)-sponsored Medical Countermeasures Against Radiological Threats (MCART) consortium recently created a Radiation Physics Core (RPC) as an entity to assume responsibility of standardizing radiation dosimetry practices among its member laboratories. The animal research activities in these laboratories use a variety of ionizing photon beams from several irradiators such as 250-320 kVp x-ray generators, Cs irradiators, Co teletherapy machines, and medical linear accelerators (LINACs). In addition to this variety of sources, these centers use a range of irradiation techniques and make use of different dose calculation schemes to conduct their experiments. An extremely important objective in these research activities is to obtain a Dose Response Relationship (DRR) appropriate to their respective organ-specific models of acute and delayed radiation effects. A clear and unambiguous definition of the DRR is essential for the development of medical countermeasures. It is imperative that these DRRs are transparent between centers. The MCART RPC has initiated the establishment of standard dosimetry practices among member centers and is introducing a Remote Dosimetry Monitoring Service (RDMS) to ascertain ongoing quality assurance. This paper will describe the initial activities of the MCART RPC toward implementing these standardization goals. It is appropriate to report a summary of initial activities with the intent of reporting the full implementation at a later date.

  9. Internal dosimetry for epidemiologic studies

    International Nuclear Information System (INIS)

    Groer, P.G.

    1987-01-01

    In traditional epidemiologic analyses, a single valued summary index, the standardized mortality ratio (SMR), is quite popular. The SMR is simply the ratio of the number of deaths observed in the study population to the number of deaths expected if the study population were subject to the age-specific rates of a standard population. SMRs for all causes or specific causes can be calculated. For such a simple analysis an exposed cohort is often characterized by an average organ or whole body dose or dose interval, and the necessary dose estimation effort is relatively minor. Modern statistical methods focus on the estimation of the cause-specific mortality rate λ for study populations exposed to ionizing radiations or toxic chemicals. The dependence of λ on factors other than demographic characteristics, such as race and sex, is usually described through a parametric model. Such factors, often called covariates or covariables, are incorporated in the mathematical expression for the hazard rate. The external gamma dose or the internal lung dose from inhaled uranium are good examples for covariates. This type of analysis permits the use of individual doses and gives a detailed and quantitative description of the mortality rate as a function of the covariables, but at the cost of a major dosimetric effort. The generation of the necessary dose information and also the calculational efforts become especially taxing for time-dependent covariates such as an internal, cumulative organ dose. 4 refs

  10. Radiation Dosimetry of a Novel Adenosine A(2A) Receptor Radioligand [C-11]Preladenant Based on PET/CT Imaging and Ex Vivo Biodistribution in Rats

    NARCIS (Netherlands)

    Zhou, Xiaoyun; Elsinga, Philip H.; Khanapur, Shivashankar; Dierckx, Rudi A. J. O.; de Vries, Erik F. J.; de Jong, Johan R.

    [C-11]Preladenant was developed as a novel adenosine A(2A) receptor PET radioligand. The aim of this study was to determine the radiation dosimetry of [C-11]preladenant and to investigate whether dosimetry estimation based on organ harvesting can be replaced by positron emission tomography

  11. In vitro dissolution and radiation dosimetry of metal tritides

    International Nuclear Information System (INIS)

    Cheng, Y.S.; Dahl, A.R.; Jow, H.N.

    1993-01-01

    It has been completed to investigate the dissolution behavior of both titanium and erbium tritide particles in simulated biological fluids and in rats. Data from these studies will provide information to estimate the dosimetry of inhaled metal tritides. The dosimetric model can then be used as the technical basis for setting health protection limits, including the annual limit on intake and the derived air concentration for DOE facilities. (3 figs.)

  12. Genetic and molecular dosimetry of HZE radiation (US-1 RADIAT)

    Science.gov (United States)

    Nelson, Gregory A.; Schubert, W. W.; Kazarians, G. A.; Richards, G. F.; Benton, E. V.; Benton, E. R.; Henke, R. P.

    1995-01-01

    In order to estimate radiation exposure in space, experiments were conducted during the 1st International Microgravity Laboratory (IML-1) mission in order to isolate genetic changes in animal cells caused by cosmic rays. The space measurements were evaluated against results from synthetic cosmic rays produced by particle accelerators on the ground. The biological material used was the tiny soil nematode, Caenorhabditis elegans. The measurements were made by thermoluminescent detectors and plastic nuclear track detectors. The development and the chromosome mechanics in microgravity were studied, and the mutagenesis induced by radiation exposure was analyzed. The results showed that there are no obvious differences in the development, behavior and chromosome mechanics, as a function of gravity unloading (reproduction, self-fertilization and mating of males with hermaphrodites, gross anatomy, symmetry and gametogenesis, pairing, disjoining and recombination of chromosomes). A variety of mutants were isolated, and it was noted that mutants isolated from regions of identified high particles were more severely affected than those isolated by random screening. Linear energy transfer particles seem to favor large scale genetic lesions.

  13. Development of transmission dose estimation algorithm for in vivo dosimetry in high energy radiation treatment

    International Nuclear Information System (INIS)

    Yun, Hyong Geun; Shin, Kyo Chul; Hun, Soon Nyung; Woo, Hong Gyun; Ha, Sung Whan; Lee, Hyoung Koo

    2004-01-01

    In vivo dosimetry is very important for quality assurance purpose in high energy radiation treatment. Measurement of transmission dose is a new method of in vivo dosimetry which is noninvasive and easy for daily performance. This study is to develop a tumor dose estimation algorithm using measured transmission dose for open radiation field. For basic beam data, transmission dose was measured with various field size (FS) of square radiation field, phantom thickness (Tp), and phantom chamber distance (PCD) with a acrylic phantom for 6 MV and 10 MV X-ray. Source to chamber distance (SCD) was set to 150 cm. Measurement was conducted with a 0.6 cc Farmer type ion chamber. By using regression analysis of measured basic beam data, a transmission dose estimation algorithm was developed. Accuracy of the algorithm was tested with flat solid phantom with various thickness in various settings of rectangular fields and various PCD. In our developed algorithm, transmission dose was equated to quadratic function of log(A/P) (where A/P is area-perimeter ratio) and the coefficients of the quadratic functions were equated to tertiary functions of PCD. Our developed algorithm could estimate the radiation dose with the errors within ±0.5% for open square field, and with the errors within ±1.0% for open elongated radiation field. Developed algorithm could accurately estimate the transmission dose in open radiation fields with various treatment settings of high energy radiation treatment. (author)

  14. Radiation dosimetry for commissioning Egypt's 'ega-gamma I' facility for radiation processing

    International Nuclear Information System (INIS)

    El-Behay, A.Z.; Rageh, S.I.; El-Assy, N.B.; Roushdy, H.

    1981-01-01

    The use of ionizing radiation for sterilization of medical products and biological tissues has become an alternative to autoclaving or gas treatment by ethylene oxide. Moreover, large radiation facilities are now increasing for processing many industrial products, such as rubber, textiles, plastics, coatings, films, wire and cable. For quality control of irradiated products released to the public, greater consideration is now being given to the use of physical radiation dosimetry, since it is simple, reliable, and reproducible. This work describes dosimetry for the new 60 Co irradiation plant, located at the National Center for Radiation Research and Technology of Egypt. Detailed measurements of absorbed dose extremes in product boxes processed in the plant were made using commercially supplied dyed plastic dosimeters (Red Acrylic and Red Perspex). These physical dosimeters were calibrated against the yield of cerous ion due to γ-ray irradiation of ceric sulphate solution as a standard chemical dosimeter. (author)

  15. UV dosimetry in pollen of Pinus silvestris and stimulation studies of pollen tube growth after irradiation with UV and ionizing radiations

    International Nuclear Information System (INIS)

    Seibold, H.W.

    1976-01-01

    Pollen tube growth after exposure to UV- and ionizing radiation was investigated in Pinus silvestris as a function of different parameters. The preconditions for this are an exact UV dosimetry and the conversion of the UV dose of [erg] into [rad]. In spite of the fact that the calculation methods are theoretically already well known, the experimental determination of the absorbed energy dose, in particular the absorption factors, was complicated by the morphological structure of the pollen. The total-irradiation experiments showed that the stimulation and inhibition of pollen tube growth is highly dependent on the dose/dose rate region chosen. Stimulation is highly dependent on the dose rate after UV irradiation as well as after exposure to ionizing radiation. When the dose rates are very small, the values are practically the same as in non-irradiated controls; with increasing doses rate, stimulation increases, whereas at very high dose rates only growth inhibition is observed. After exposure to ionizing radiation, the quantum energy or wavelength of the radiation has no effect on tube growth; after UV irradiation, on the other hand, there is hardly any stimulation at short wavelengths. As these observations were not sufficient for drawing conclusions on the site of the stimulatory action, partial UV exposure with separate irradiation of the two nuclei and the cytoplasm was also carried out. Stimulation was found in each of the three irradiation sites; although nuclei and cytoplasma react differently and also differ in the initial reaction stages, there is always an anhancement of pollen tube growth. These findings are compared with some of the current hypotheses for an explanation of the stimulatory effect. (orig.) [de

  16. Protocol for X-ray dosimetry and exposure arrangements employed in studies of late somatic effects in mammals

    International Nuclear Information System (INIS)

    Zoetelief, J.; Kogel, A.J. van der; Broerse, J.J.; Scarpa, G.; Dixon-Brown, A.

    1985-01-01

    A number of European laboratories studying the late effects of ionizing radiation in animals have established an effective cooperation within the European Late Effects Project Group (EULEP) since 1970. To facilitate the exchange of biological results several techniques, including quality control of the experimental animals, pathology and dosimetry, have to be standardized. The most important aspects of the procedures for X-irradiation and dosimetry of small animals are summarized. These include recommendations on irradiation conditions, dosimetry methods, characteristics of phantoms and factors affecting X-ray dosimetry. X-irradiation procedures employed by the participating institutes are described and the results of five X-ray dosimetry intercomparisons are reported. The introduction of a common dosimetry protocol has resulted in improvements in exposure arrangements and absolute dosimetry. (author)

  17. Study of a 3D dosimetry system response: ARCCHECK®

    Energy Technology Data Exchange (ETDEWEB)

    Mazer, Amanda C.; Yoriyaz, Hélio, E-mail: amandamazer18@gmail.com, E-mail: hyoriyaz@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil); Nakandakari, Marcos V.N., E-mail: marcos.sake@gmail.com [Beneficência Portuguesa de São Paulo, SP (Brazil)

    2017-07-01

    Ionizing radiation therapies have improved over the years, becoming more specific for each patient. Thereby as the treatment planning system (TPS) complexities increases, the quality assurance (QA) methods have to be in a constant evolution. One of the techniques that demand great complexity is the Volumetric Modulated Arc Therapy (VMAT). One possible way to VMAT commissioning is using 3D dosimetry systems and recently a new 3D dosimetry system called ArcCheck had been developed and commercialized mainly for VMAT quality assurance. It is water-equivalent and composed by an array of 1386 diodes arranged in a spiral pattern. Since simulation methods, like Monte Carlo method, ensure highly accurate results, MCNP (A General Monte Carlo N-Particle Transport Code System) is totally reliable for problems that involve radiation transport. This work presents a preliminary study of the 3D dosimetry system ArcCheck by developing two computational models in MCNP6. In addition, experimental measures were acquired using the ArcCheck in a Linear Accelerator and then these values were compared with the results obtained by simulations of both models. The comparisons showed good reproducibility. (author)

  18. FDA's requirements for radiation dosimetry of radiopharmaceutical drug products

    International Nuclear Information System (INIS)

    Abel, N.M.

    1986-01-01

    The primary concern of the Office of Drug Research and Review of the Food and Drug Administration in the field of radiation dosimetry is to ensure that radiopharmaceutical drug products are safe when used as investigational drugs (INDs) and are both safe and effective when a new drug application (NDA) is approved. In order to accomplish this, the sponsor of either an IND or applicant in the case of NDA must provide information that clearly describes the radiation dose that a patient will receive from the administration of the drug. The submitted numerical estimates of the radiation dose should be based on an absorbed fraction method of radiation dose calculation, such as the system set forth by the Medical Internal Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine or the system set forth by the International Commission on Radiological Protection (ICRP). This presentation will describe in detail the data that a sponsor of an IND needs to submit to satisfy the regulatory requirements. Examples will be given of common mistakes and omissions by sponsors in their presentation of data

  19. Conventional radiation-biological dosimetry using frequencies of unstable chromosome aberrations

    International Nuclear Information System (INIS)

    Ramalho, Adriana T.; Costa, Maria Lucia P.; Oliveira, Monica S.

    1998-01-01

    Frequency of chromosome aberrations detected by conventional cytogenetics is a very useful parameter in biological radiodosimetry. It can be used for estimating absorbed doses in individuals working with radioactive sources and individuals accidentally exposed to radiation. In the first case subjects wear physical dosimeters as a routine safety habit. The laboratory at the Institute of Radioprotection and Dosimetry (IRD, Brazil) has been using conventional cytogenetic analysis to complement data obtained by physical dosimetry since 1983. Until now, more than one hundred cases were investigated where individual physical dosimeters detected occupational exposure (above the safety limits allowed). In total, only 34% of these cases were confirmed by conventional cytogenetic dosimetry. Also, conventional cytogenetic analysis following the radiation accident of Goiania (Brazil) in 1987 have been used. Peripheral lymphocytes from 129 exposed or potentially exposed individuals were analyzed for the frequencies of unstable chromosomal aberrations (dicentrics, centric rings and acentrics fragments) to estimate absorbed radiation doses. During the emergency period, doses were estimated to help immediate medical treatment using in vitro calibration curves produced before the accident. Later on, doses were assessed once more using new in vitro calibration curves. A drawback of this technique is that unstable aberrations are lost after exposure. To investigate the mean lifespan of lymphocytes containing dicentric and ring aberrations, we have followed 15 victims of the Goiania accident over all these years. Results suggest that the disappearance of unstable aberrations is dose-dependent. This could explain the variation in the results found among studies in this field

  20. Conventional radiation-biological dosimetry using frequencies of unstable chromosome aberrations

    Energy Technology Data Exchange (ETDEWEB)

    Ramalho, Adriana T.; Costa, Maria Lucia P.; Oliveira, Monica S. [Institute of Radioprotection and Dosimetry (IRD), National Commission of Nuclear Energy (CNEN), Av. Salvador Allende, Cx. P. 37750, Rio de Janeiro 22.780-160 (Brazil)

    1998-08-03

    Frequency of chromosome aberrations detected by conventional cytogenetics is a very useful parameter in biological radiodosimetry. It can be used for estimating absorbed doses in individuals working with radioactive sources and individuals accidentally exposed to radiation. In the first case subjects wear physical dosimeters as a routine safety habit. The laboratory at the Institute of Radioprotection and Dosimetry (IRD, Brazil) has been using conventional cytogenetic analysis to complement data obtained by physical dosimetry since 1983. Until now, more than one hundred cases were investigated where individual physical dosimeters detected occupational exposure (above the safety limits allowed). In total, only 34% of these cases were confirmed by conventional cytogenetic dosimetry. Also, conventional cytogenetic analysis following the radiation accident of Goiania (Brazil) in 1987 have been used. Peripheral lymphocytes from 129 exposed or potentially exposed individuals were analyzed for the frequencies of unstable chromosomal aberrations (dicentrics, centric rings and acentrics fragments) to estimate absorbed radiation doses. During the emergency period, doses were estimated to help immediate medical treatment using in vitro calibration curves produced before the accident. Later on, doses were assessed once more using new in vitro calibration curves. A drawback of this technique is that unstable aberrations are lost after exposure. To investigate the mean lifespan of lymphocytes containing dicentric and ring aberrations, we have followed 15 victims of the Goiania accident over all these years. Results suggest that the disappearance of unstable aberrations is dose-dependent. This could explain the variation in the results found among studies in this field

  1. Techniques used in CAPRI for the dosimetry of γ radiations and electron beams

    International Nuclear Information System (INIS)

    Laizier, J.

    1980-01-01

    The radiation sources of CAPRI are: Pagure - 60 Co - 20Kcie, Poseidon - 60 Co - 1MCie (presently the activity is 200 Kcie), Vulcain - e - - 3MeV (variable from 0.5 MeV) - 1mA, Promethee - e - - 300 kV - 100 mA. The activities of CAPRI are research and development in industrial applications of irradiation, pilot and small scale production, irradiation (sterilization), nuclear qualification. Dosimetry techniques are: plastic dosimetry, chemical dosimetry, films [fr

  2. Optical fiber detectors as in-vivo dosimetry method of quality assurance in radiation therapy

    International Nuclear Information System (INIS)

    Plazas, M.C.; Justus, B.L.; Falkenstein, P.; Huston, A.L.; Ning, H.; Miller, R.

    2004-01-01

    A new in-vivo dosimetry system has been under development for some time using radio luminescent phosphors. These phosphors are activated, metal ion doped glasses (Ex: Cu 1± doped quartz fiber), have excellent optical transparency and offer several potential advantages for radiation dosimetry; including: small size, high sensitivity, linearity of dose response insensitivity to electromagnetic interference. The utility of these phosphors as a detection modality has been limited in real-time dosimetry applications due to the production of Cerenkov radiation in the carrier fiber, which produces a contaminant signal proportional to dose rate as well as the size of the radiation field. One possible method for eliminating this signal is using an electronic gating signal from the accelerator to delay data acquisition during the actual beam pulse, when Cerenkov radiation is produced. Due to the intrinsic properties of our particular scintillator, this method offers the best mechanism for eliminating Cerenkov noise, while retaining the ability to detect individual beam pulses. The dosimeter was tested using an external beam radiotherapy machine that provided pulses of 6 MeV x-rays. Gated detection was used to discriminate the signal collected during the radiation pulses, which included contributions from Cerenkov radiation and native fiber fluorescence, from the signal collected between the radiation pulses, which contained only the long-lived phosphorescence from the Cu 1± doped fused quartz detector. Gated detection of the phosphorescence provided accurate, real-time dose measurements that were linear with absorbed dose, independent of dose rate and that were accurate for all field sizes studied. (author)

  3. Variable transformation of calibration equations for radiation dosimetry

    International Nuclear Information System (INIS)

    Watanabe, Yoichi

    2005-01-01

    For radiation dosimetry, dosimetric equipment must be calibrated by using known doses. The calibration is done to determine an equation that relates the absorbed dose to a physically measurable quantity. Since the calibration equation is accompanied by unavoidable uncertainties, the doses estimated with such equations suffer from inherent uncertainties. We presented mathematical formulation of the calibration when the calibration relation is either linear or nonlinear. We also derived equations for the uncertainty of the estimated dose as a function of the uncertainties of the parameters in the equations and the measured physical quantity. We showed that a dosimeter with a linear calibration equation with zero dose-offset enables us to perform relative dosimetry without calibration data. Furthermore, a linear equation justifies useful data manipulations such as rescaling the dose and changing the dose-offset for comparing dose distributions. Considering that some dosimeters exhibit linear response with a large dose-offset or often nonlinear response, we proposed variable transformations of the measured physical quantity, namely, linear- and log-transformation methods. The proposed methods were tested with Kodak X-Omat V radiographic film and BANG (registered) polymer gel dosimeter. We demonstrated that the variable transformation methods could lead to linear equations with zero dose-offset and could reduce the uncertainty of the estimated dose

  4. Consistency of external dosimetry in epidemiologic studies of nuclear workers

    International Nuclear Information System (INIS)

    Fix, J.J.; Gilbert, E.S.

    1992-01-01

    Efforts are underway to pool data from epidemiologic studies of nuclear workers to obtain more precise estimates of radiation risk than would be possible from any single study. The International Agency for Research on Cancer (IARC) is coordinating combined analyses of data from studies in the United States, Canada, and the United Kingdom. In the U.S., the Department of Energy (DOE) has established the Comprehensive Epidemiologic Data Resource (CEDR) to provide investigators an opportunity to analyze data from several DOE laboratories. IARC investigators, in collaboration with those conducting the individual studies, have developed a dosimetry protocol for the international combined analyses. (author)

  5. Consistency of external dosimetry in epidemiologic studies of nuclear workers

    International Nuclear Information System (INIS)

    Fix, J.J.; Gilbert, E.S.

    1992-05-01

    Efforts are underway to pool data from epidemiologic studies of nuclear workers to obtain more precise estimates of radiation risk than would be possible from any single study. The International Agency for Research on Cancer (IARC) is coordinating combined analyses of data from studies in the United States, Canada, and the United Kingdom. In the US, the Department of Energy (DOE) has established the Comprehensive Epidemiologic Data Resource (CEDR) to provide investigators an opportunity to analyze data from several DOE laboratories. IARC investigators, in collaboration with those conducting the individual studies, have developed a dosimetry protocol for the international combined analyses

  6. 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.)

  7. EVIDOS: Individual dosimetry in mixed neutron and photon radiation fields

    International Nuclear Information System (INIS)

    Vanhavere, F.

    2006-01-01

    The EVIDOS project (partly funded by the European Commission RTD Programme: Nuclear Energy, Euratom Framework Programme V, 1998-2002, Contract No FIKR-CT-2001-00175) aimed at improving individual monitoring in mixed neutron-photon radiation fields by evaluating the performance of routine and novel personal dosimeters for mixed radiation, and by giving guidelines for deriving sufficiently accurate values of personal dose equivalent from the readings of area survey instruments and dosimeters. The main objective of EVIDOS was to evaluate different methods for individual dosimetry in mixed neutron-photon work-places in nuclear industry. This implied a determination of the capabilities and limitations of personal dosimeters and the establishment of methods to enable sufficiently accurate values of personal dose equivalent from spectrometers, area survey instruments and routine personal dosimeters. Also novel electronic personal dosimeters were investigated. To this end spectrometric and dosimetric investigations in selected representative workplaces in nuclear industry where workers can receive significant neutron doses were performed. As part of this project, a number of tasks were executed, in particular: (1) the determination of the energy and direction distribution of the neutron fluence; (2) the derivation of the (conventionally true) values of radiation protection quantities; (3) the determination of the readings of routine and innovative personal dosimeters and of area monitors; and (4) the comparison between dosimeter readings and values of the radiation protection quantities

  8. A contribution to the study and development of radiothermoluminescent dosimetry

    International Nuclear Information System (INIS)

    Portal, Guy.

    1975-10-01

    The applications of radiothermoluminescence to radiation dosimetry were investigated. The fundamental processes are first reviewed and the main properties of radiothermoluminescence dosemeters are stated. The investigations carried out in order to have materials presenting particular dosimetric characteristics are then described: a lithium fluoride stabilized by sodium that can be reused without regeneration an alumina suitable for dosimetry in case of accident. Finally, the measurement of electromagnetic radiation in presence of neutrons of various energies are considered [fr

  9. Gel Dosimetry Analysis of Gold Nanoparticle Application in Kilovoltage Radiation Therapy

    International Nuclear Information System (INIS)

    Marques, T; Schwarcke, M; Garrido, C; Zucolot, V; Baffa, O; Nicolucci, P

    2010-01-01

    In this work gold nanoparticles (AuNP) were embedded in MAGIC-f gel and irradiated in a 250 kV x-ray clinical beam. The signal of non-irradiated gel samples containing AuNPs showed maximum difference of 0.5% related to gel without nanoparticles. Different AuNPs concentrations were studied: 0.10 mM, 0.05 mM and 0.02 mM, presenting dose enhancements of 106%, 90% and 77% respectively. Monte Carlo spectrometry was performed to quantify theoretical changes in photon energy spectrums due to AuNPs presence. Concordance between simulated dose enhancements and gel dosimetry measurements was better than 97% to all concentrations studied. This study evidences that polymer gel dosimetry as a suitable tool to perform dosimetric investigations of nanoparticle applications in Radiation Therapy.

  10. The status of radiation processing dosimetry in China

    International Nuclear Information System (INIS)

    Chen Wenxiu; Li Chenghua; Pang Ruicao; Zhang Yanli.

    1995-01-01

    Radiation processing is a rapidly expanding technology in China since 1970s. About 50 facilities of Co-60 source with the designed capacity more than 3.7PBq have been set up in Beijing, Shanghai, and 36 cities. The total charged activity of sources is more than 862PBq some facilities are shown in Table 1. More than 26 electron beam (EB) irradiation facilities have been established as listed in Table 2. The total power of electron beams had reached about 926 kW. The effectiveness of the process depends on the proper application of dose and its measurement. The importance of dosimetry events on the processing control of irradiation technology and the quality assurance of irradiated products has been acknowledged in China, which was introduced in this paper. (author)

  11. 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)

  12. Radiation Dosimetry Using Three-Dimensional Optical Random Access Memories

    International Nuclear Information System (INIS)

    Moscovitch, M.

    2001-01-01

    The ability to determine particle type and energy plays an important role in the dosimetry of heavy charged particles (HCP) and neutrons. A new approach to radiation dosimetry is presented, which is shown to be capable of particle type and energy discrimination. This method is based on utilizing radiation induced changes in the digital information stored on three-dimensional optical random access memories (3D ORAM). 3D ORAM is a small cube (a few mm 3 ) composed of poly(methyl methacrylate) doped with a photochromic dye, and it was originally proposed as a memory device in high speed parallel computers. A Nd:YAG laser system is used to write and read binary information (bits) on the ORAM, which functions as a charged particle detector. Both the read and the write processes use two laser beams that simultaneously strike the material to cause a color change at their intersection (similar to the darkening of light-sensitive sunglasses when exposed to sunlight.) The laser produces color changes in the ORAM, which then reverts to the original color (''bit-flips'') at sites where energy is deposited from interaction with incident HCP or neutron-recoil protons. The feasibility of this approach was demonstrated both theoretically and experimentally. Calculations based on track structure theory (TST) predict that when HCP interact with the ORAM material, the local energy deposition is capable of inducing measurable ''bit-flips''. These predictions were recently confirmed experimentally using two types of ORAM systems, one based on spirobenzopyran and the other on anthracene, as the photochromic dyes

  13. Radiation dosimetry using three-dimensional optical random access memories

    International Nuclear Information System (INIS)

    Moscovitch, M.; Phillips, G.W.; Cullum, B.M.; Mobley, J.; Bogard, J.S.; Emfietzoglou, D.; Vo-Dinh, T.

    2002-01-01

    The ability to determine particle type and energy plays an important role in the dosimetry of heavy charged particles (HCP) and neutrons. A new approach to radiation dosimetry is presented, which is shown to be capable of particle type and energy discrimination. This method is based on utilising radiation induced changes in the digital information stored on three-dimensional optical random access memories (3D ORAM). 3D ORAM is a small cube (a few mm 3 ) composed of poly(methyl methacrylate) doped with a photochromic dye, and it was originally proposed as a memory device in high speed parallel computers. A Nd:YAG laser system is used to write and read binary information (bits) on the ORAM, which functions as a charged particle detector. Both the read and the write processes use two laser beams that simultaneously strike the material to cause a colour change at their intersection (similar to the darkening of light-sensitive sunglasses when exposed to sunlight). The laser produces colour changes in the ORAM, which then reverts to the original colour ('bit-flips') at sites where energy is deposited from interaction with incident HCP or neutron-recoil protons. The feasibility of this approach was demonstrated both theoretically and experimentally. Calculations based on track structure theory predict that when HCP interact with the ORAM material, the local energy deposition is capable of inducing measurable 'bit-flips'. These predictions were recently confirmed experimentally using two types of ORAM systems, one based on spirobenzopyran and the other on anthracene, as the photochromic dyes. (author)

  14. How feasible is remote 3D dosimetry for MR guided Radiation Therapy (MRgRT)?

    International Nuclear Information System (INIS)

    Mein, S; Miles, D; Juang, T; Fenoli, J; Oldham, M; Rankine, L; Cai, B; Curcuru, A; Mutic, S; Li, H; Adamovics, J

    2017-01-01

    To develop and apply a remote dosimetry protocol with PRESAGE® radiochromic plastic and optical-CT readout in the validation of MRI guided radiation therapy (MRgRT) treatments (MRIdian® by ViewRay®). Through multi-institutional collaboration we performed PRESAGE® dosimetry studies in 4ml cuvettes to investigate dose-response linearity, MR-compatibility, and energy-independence. An open calibration field and symmetrical 3-field plans were delivered to 10cm diameter PRESAGE® to examine percent depth dose and response uniformity under a magnetic field. Evidence of non-linear dose response led to a large volume PRESAGE® study where small corrections were developed for temporally- and spatially-dependent behaviors observed between irradiation and delayed readout. TG-119 plans were created in the MRIdian® TPS and then delivered to 14.5cm 2kg PRESAGE® dosimeters. Through the domestic investigation of an off-site MRgRT system, a refined 3D remote dosimetry protocol is presented capable of validation of advanced MRgRT radiation treatments. (paper)

  15. How feasible is remote 3D dosimetry for MR guided Radiation Therapy (MRgRT)?

    Science.gov (United States)

    Mein, S.; Rankine, L.; Miles, D.; Juang, T.; Cai, B.; Curcuru, A.; Mutic, S.; Fenoli, J.; Adamovics, J.; Li, H.; Oldham, M.

    2017-05-01

    To develop and apply a remote dosimetry protocol with PRESAGE® radiochromic plastic and optical-CT readout in the validation of MRI guided radiation therapy (MRgRT) treatments (MRIdian® by ViewRay®). Through multi-institutional collaboration we performed PRESAGE® dosimetry studies in 4ml cuvettes to investigate dose-response linearity, MR-compatibility, and energy-independence. An open calibration field and symmetrical 3-field plans were delivered to 10cm diameter PRESAGE® to examine percent depth dose and response uniformity under a magnetic field. Evidence of non-linear dose response led to a large volume PRESAGE® study where small corrections were developed for temporally- and spatially-dependent behaviors observed between irradiation and delayed readout. TG-119 plans were created in the MRIdian® TPS and then delivered to 14.5cm 2kg PRESAGE® dosimeters. Through the domestic investigation of an off-site MRgRT system, a refined 3D remote dosimetry protocol is presented capable of validation of advanced MRgRT radiation treatments.

  16. Requirements for the approval of dosimetry services under the Ionising Radiations Regulations 1985: Pt. 2: Internal radiations

    International Nuclear Information System (INIS)

    1991-01-01

    Guidance for dosimetry services on the requirements for approval by the Health and Safety Executive (HSE) is provided in three parts. This part sets out the procedures and criteria that will be used by HSE in the assessment of dosimetry services seeking approval in relation to internal radiations (including radon decay products). (author)

  17. Requirements for the approval of dosimetry services under the Ionising Radiations Regulations 1985: Pt. 1: External radiations

    International Nuclear Information System (INIS)

    1991-01-01

    Guidance for dosimetry services on the requirements for approval by the Health and Safety Executive (HSE) is provided in three parts. This part sets out the procedures and criteria that will be used by HSE in the assessment of dosimetry services seeking approval in relation to external radiations (including accidents). (author)

  18. Biokinetics and radiation dosimetry of 14C-labelled triolein, urea, glycocholic acid and xylose in man. Studies related to nuclear medicine 'breath tests' using accelerator mass spectrometry

    International Nuclear Information System (INIS)

    Gunnarsson, Mikael

    2002-08-01

    14 C-labelled substances have been used in biomedical research and clinical medicine for over 50 years. Physicians and scientists however, often hesitate to use these substances in patients and volunteers because the radiation dosimetry is unclear. In this work detailed long-term biokinetic and dosimetric estimation have been carried out for four clinically used 14 C-breath tests: 14 C-triolein (examination of fat malabsorption), urea (detection of Helicobacter pylori infection in the stomach), glycocholic acid and xylose (examination of bacterial overgrowth in the small intestine) by using the highly sensitive accelerator mass-spectrometry (AMS) technique. The AMS technique has been used to measure low 14 C concentrations in small samples of exhaled air, urine, faeces and tissue samples and has improved the base for the estimation of the absorbed dose to various organs and tissues and the effective dose to man. The high sensitivity of the AMS system has also made it possible to perform 14 C breath tests on patient groups which were earlier subject for restriction (e.g. small children). In summary, our results show that for adult patients - and in the case of 14 C-urea breath test also for children down to 3 years of age - the dose contributions are comparatively low, both described as organ doses and as effective doses. For adults, the latter is: 14 C-glycocholic acid - 0.4 mSv/MBq, 14 C-triolein - 0.3 mSv/MBq, 14 C-xylose - 0.1 mSv/MBq and 14 C-urea - 0.04 mSv/MBq. Thus, from a radiation protection point of view there is no reason for restrictions in using any of the 14 C-labelled radiopharmaceutical included in this work in the activities normally used (0.07-0.2 MBq for a 70 kg patient)

  19. Computer-assisted planning and dosimetry for radiation treatment of head and neck cancer in Cameroon

    International Nuclear Information System (INIS)

    Yomi, J.; Ngniah, A.; Kingue, S.; Muna, W.F.T.; Durosinmi-Etti, F.A.

    1995-01-01

    This evaluation was part of a multicenter, multinational study sponsored by the International Agency for Atomic Energy (Vienna) to investigate a simple, reliable computer-assisted planning and dosimetry system for radiation treatment of head and neck cancers in developing countries. Over a 13-month period (April 1992-April 1993), 120 patients with histologically-proven head or neck cancer were included in the evaluation. In each patient, planning and dosimetry were done both manually and using the computer-assisted system. The manual and computerized systems were compared on the basis of accuracy of determination of the outer contour, target volume, and critical organs; volume inequality resolution; structure heterogeneity correction; selection of the number, angle, and size of beams; treatment time calculation; availability of dosimetry predictions; and duration and cost of the procedure. Results demonstrated that the computer-assisted procedure was superior over the manual procedure, despite less than optimal software. The accuracy provided by the completely computerized procedure is indispensable for Level II radiation therapy, which is particularly useful in tumors of the sensitive, complex structures in the head and neck. (authors). 7 refs., 3 tabs

  20. A preliminary study on thermoluminescence of AMOLED glass from mobile phones for retrospective dosimetry

    International Nuclear Information System (INIS)

    Kim, Hyoungtaek; Lee, Jungil; Chang, Insu; Lee, Seung Kyu; Kim, Min Chae; Park, Sang Won; Kim, Jang-Lyul; Kim, Bong-Hwan; Yu, Hyungjoon; Kim, Ah-reum

    2017-01-01

    Since mobile phones are always carried by individuals, the retrospective dosimetry using thermoluminescence (TL) and optically stimulated luminescence (OSL) characteristics of elements in mobile phone is intensively developing nowadays due to its advantages over conventional biological dosimetry techniques. Using a TL and OSL method on resistors and inductors in a mobile phone, a low background dose (zero dose) about tens of mGy is acquired in previous study. Radiation workers have to wear a dosimeter to assess individual exposure during their works. This monitoring system facilitate a fast medical treatment for highly exposed workers in case of a radiation accident. In the event of large-scale radiation accidents, where most of the subjects are ordinary people, it is difficult to evaluate the individual dose due to the absence of dosimeters. A technique for dose evaluation using a radiation dependency of various materials in the absence of a dosimeter is called retrospective dosimetry.

  1. Patient dosimetry study of a paediatric CT examination

    International Nuclear Information System (INIS)

    Hranitzky, C.; Stadtmann, H.

    2011-01-01

    Dosimetry studies are of increasing interest in diagnostic high-dose applications such as computed tomography especially for examinations of children. A routine CT scan protocol for paediatric head and neck imaging was investigated at a new multi-detector CT scanner using LiF:Mg,Cu,P thermoluminescence dosemeters (TLDs) and a 0.125 cm 3 thimble ionization chamber. Calibrations of the detectors in terms of absorbed dose to water were carried out at the Dosimetry Laboratory Seibersdorf in standard radiation fields. The dosimetry method was validated in the spiral CT X-ray field by comparing TLD and ionization chamber measurement results in cylindrical PMMA phantoms. Absorbed dose results were within stated uncertainties. An anthropomorphic phantom representing a child of about 5 years was loaded with TLD chips at various organ and tissue positions in the head and neck region as well as at some critical organ locations. Organ dose values were calculated from TLD based average absorbed dose with about 5% total uncertainty, e.g. 22 mGy (eyes), 21 mGy (thyroid), 19 mGy (brain), 3.4 mGy (thymus), and 0.03 mGy (testes). For comparison purposes an effective dose of 1.9 mSv was estimated for the investigated paediatric CT examination based on ICRP-103 age-independent tissue-weighting factors.

  2. International Symposium on Standards, Applications and Quality Assurance in Medical Radiation Dosimetry (IDOS). Book of Extended Synopses

    International Nuclear Information System (INIS)

    2010-01-01

    The major goal of the symposium is to provide a forum where advances in radiation dosimetry during the last decade, in radiation medicine and radiation protection can be disseminated and scientific knowledge exchanged. It will include all specialties in radiation medicine and radiation protection dosimetry with a specific focus on those areas where the standardization of dosimetry has improved in the recent years (brachytherapy, diagnostic radiology and nuclear medicine). It will also summarize the present status and outline future trends in medical radiation dosimetry and identify possible areas for improvement. Its conclusions and summaries should lead to the formulation of recommendations for the scientific community

  3. International Symposium on Standards, Applications and Quality Assurance in Medical Radiation Dosimetry (IDOS). Book of Extended Synopses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    The major goal of the symposium is to provide a forum where advances in radiation dosimetry during the last decade, in radiation medicine and radiation protection can be disseminated and scientific knowledge exchanged. It will include all specialties in radiation medicine and radiation protection dosimetry with a specific focus on those areas where the standardization of dosimetry has improved in the recent years (brachytherapy, diagnostic radiology and nuclear medicine). It will also summarize the present status and outline future trends in medical radiation dosimetry and identify possible areas for improvement. Its conclusions and summaries should lead to the formulation of recommendations for the scientific community

  4. Development of radiation biological dosimetry and treatment of radiation-induced damaged tissue

    International Nuclear Information System (INIS)

    Cho, Chul Koo; Kim, Tae Hwan; Lee, Yun Sil

    2000-04-01

    Util now, only a few methods have been developed for radiation biological dosimetry such as conventional chromosome aberration and micronucleus in peripheral blood cell. However, because these methods not only can be estimated by the expert, but also have a little limitation due to need high technique and many times in the case of radiation accident, it is very difficult to evaluate the absorbed dose of victims. Therefore, we should develop effective, easy, simple and rapid biodosimetry and its guideline(triage) to be able to be treated the victims as fast as possible. We established the apoptotic fragment assay, PCC, comet assay, and micronucleus assay which was the significant relationship between dose and cell damages to evaluate the irradiated dose as correct and rapid as possible using lymphocytes and crypt cells, and compared with chromosome dosimetry and micronucleus assay

  5. Development of radiation biological dosimetry and treatment of radiation-induced damaged tissue

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Chul Koo; Kim, Tae Hwan; Lee, Yun Sil [and others

    2000-04-01

    Util now, only a few methods have been developed for radiation biological dosimetry such as conventional chromosome aberration and micronucleus in peripheral blood cell. However, because these methods not only can be estimated by the expert, but also have a little limitation due to need high technique and many times in the case of radiation accident, it is very difficult to evaluate the absorbed dose of victims. Therefore, we should develop effective, easy, simple and rapid biodosimetry and its guideline(triage) to be able to be treated the victims as fast as possible. We established the apoptotic fragment assay, PCC, comet assay, and micronucleus assay which was the significant relationship between dose and cell damages to evaluate the irradiated dose as correct and rapid as possible using lymphocytes and crypt cells, and compared with chromosome dosimetry and micronucleus assay.

  6. 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

  7. 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.

  8. The application of radiation-induced free radicals signals in retrospective dosimetry

    International Nuclear Information System (INIS)

    Liu Zhongchao; Zhang Wenyi; Jiao Ling

    2013-01-01

    For some materials and biological samples, free radicals can be induced after ionizing radiation. Electron spin resonance (ESR) spectroscopy can detect free radical signal and its intensity can reflect the dose of the ionizing radiation. It is a typical way to estimate the radiation dosimetry by using the ESR spectroscopy of teeth. In recent years, many researchers studied on ESR of easy-getting materials such as finger (toe) nail, hair, cell phone screen, in order to investigate the relationship between signal intensity and radiation dose. The aim of this paper is to survey the current literature about methodologies and the materials on background signal, linearity of dose-response relationship, minimum detection limit and post-irradiation signal stability, so that more data will be provided for nuclear accident dose estimation. (authors)

  9. Radiation dosimetry for residents of the Chernobyl region: a comparison of cytogenetic and electron spin resonance methods

    Energy Technology Data Exchange (ETDEWEB)

    Serezhenkov, V A; Mordvintcev, P I; Vanin, A F; Voevodskaya, N V [AN SSSR, Moscow (Russian Federation). Inst. Fizicheskoj Khimii; Domracheva, E V; Kulikov, S M; Kuznetsov, S A; Schklovsky-Kordi, N E; Vorobiev, A I [National Center for Haematology, Moscow (Russian Federation); Klevezal, G A; Sukhovskaya, L I [Russian Academy of Science, Moscow (Russian Federation). Inst. of Developmental Biology

    1992-01-01

    Persons from the Gomel region of Byelorussia who were irradiated by the Chernobyl reactor accident have been studied. Estimations of their radiation doses using electron spin resonance spectrometry of dental enamel showed good agreement with dosimetry by chromosomal analysis of blood lymphocytes. (author).

  10. Dosimetry characterization of the commercial CaF2 for beta radiation of 90Sr + 90Y

    International Nuclear Information System (INIS)

    Oliveira, Mercia L.; Caldas, Linda V.E.

    2003-01-01

    This work studies the dosimetric characteristics of the CaF 2 commercial dosimetry for detection of 90 Sr + 90 Y beta radiation for using in the calibration of flat and concave appliers. Were determined the repetitiousness and linearity of answers of the samples, and their calibration curves

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

    International Nuclear Information System (INIS)

    Andisco, D.; Blanco, S.; Bourel, V.; Schmidt, L.; Di Risio, C.

    2014-08-01

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

  12. Standards for radiation protection and diagnostic radiology at the IAEA Dosimetry Laboratory

    International Nuclear Information System (INIS)

    Pernicka, F.; Andreo, P.; Meghzifene, A.; Czap, L.; Girzikowsky, R.

    1999-01-01

    International standardization in dosimetry is essential for the successful exploitation of radiation technology. The IAEA dosimetry programme is focused into services provided to Member States through the IAEA/WHO Network of Secondary Standard Dosimetry Laboratories (SSDLs), to radiotherapy centres and radiation processing facilities. Radiation protection quantities defined by ICRU and ICRP are used to relate the risk due to exposure to ionizing radiation to a single quantity, irrespective of the type of radiation, which takes into account the human body as a receptor. Two types of quantities, limiting and operational, can be related to basic physical quantities which are defined without need for considering specific aspects of radiation protection, e.g. air kerma for photons and fluence for neutrons. The use of a dosimeter for measurements in radiation protection requires a calibration in terms of a physical quantity together with a conversion from physical into protection quantities by means of a factor or a coefficient

  13. MOSFET dosimetry of the radiation therapy microbeams at the European synchrotron radiation facility

    International Nuclear Information System (INIS)

    Rozenfeld, A.; Lerch, M.

    2002-01-01

    Full text: We have developed an innovative on-line MOSFET readout system for use in the quality assurance of radiation treatment beams. Recently the system has found application in areas where excellent spatial resolution is also a requirement in the quality assurance process, for example IMRT, and microbeam radiation therapy. The excellent spatial resolution is achieved by using a quadruple RADFET TM chip in 'edge on' mode. In developing this approach we have found that the system can be utilised to determine any error in the beam profile measurements due to misalignment of RADFET with respect to the radiation beam or microbeam. Using this approach will ensure that the excellent spatial resolution of the RADFET used in 'edge-on' mode is fully utilised. In this work we report on dosimetry measurements performed at the microbeam radiation therapy beamline located at the European Synchrotron Radiation Facility. The synchrotron planar array microbeam with size 10-30 μm and pitch ∼200 μm has found an important application in microbeam radiation therapy (MRT) of brain tumours in infants for whom other kinds of radiotherapy are inadequate and/or unsafe. The radiation damage from an array of parallel microbeams correlates strongly with the range of peak-valley dose ratios (PVDR), ie, the range of the ratio of the absorbed dose to tissue directly in line with the mid-plane of the microbeam to that in the mid-plane between adjacent microbeams. Novel physical dosimetry of the microbeams using the online MOSFET reader system will be presented. Comparison of the experimental results with both GaF film measurements and Monte Carlo computer-simulated dosimetry are described here for selected points in the peak and valley regions of a microbeam-irradiated tissue phantom

  14. A method of dosimetry for synchrotron microbeam radiation therapy using radiochromic films and microdensitometry

    International Nuclear Information System (INIS)

    Crosbie, J. C.; Svalbe, I. D.; Lewis, R. A.

    2007-01-01

    Full text: Normal tissue displays an exceptional tolerance to high doses of radiation (hundreds of Gy) when delivered as a microplanar array of synchrotron-generated x-rays. Furthermore, MRT has been shown to cause significant tumour growth delay and in some case complete ablation. The biological effects of MRT on tissue are not fully understood. This is further complicated by difficulties in performing accurate dosimetry. The majority of dosimetry performed for MRT has been Monte Carlo simulations. The aim of this work was to utilise film dosimetry and microdensitometry to measure the peak-to-valley dose ratios (PVDRs) for synchrotron microbeam radiation therapy.

  15. Analysis of population dosimetry data in the high level natural radiation areas, Kerala, India

    International Nuclear Information System (INIS)

    Chougaonkar, M.P.; Mayya, Y.S.; Koya, P.K.M.; Cheriyan, V.D.; Seshadri, M.; Eappen, K.P.; Ramachandran, T.V.; Jojo, P.J.; Predeep, P.

    2010-01-01

    In the Indian scenario, Kerala has huge monazite bearing sand deposits on the west coast thereby having high natural background radiation levels. Extensive studies on the radiation dosimetry as well as effects on the human health are therefore being carried out in the region. We have recently completed a dosimetric survey aimed for epidemiological studies using case control methodology. This study, in collaboration with two local colleges in Kollam, Kerala, was taken up to study the relationship of congenital malformations and radiation exposures, if any. The two conditions that were selected were mental retardation and cleft lip-palate. Stringent selection criteria were set in selecting the cases and suitable controls. A ratio of 1:3 for case:control was selected for getting the optimum statistical significance from the data generated. The paper describes the methodology of dosimetric survey and the analysis of dose data based on case and controls

  16. Study and characterization of dosimeter LiF:Mg,Cu,P for using in aeronautical dosimetry

    International Nuclear Information System (INIS)

    Flavia, Hanna; Federico, Claudio; Lelis, Odair; Pereira, Heloisa; Pereira, Marlon

    2014-01-01

    The effects of cosmic ionizing radiation incidents in aircraft components and crews has been a source of concern and motivated increasingly studies and improvements in the area. The low dose rates involved in this radiation field in aircraft flight altitudes imply Dosimetric necessity of using materials with high efficiency of detection, to enable studies lower cumulative doses resulting in shorter routes or lower altitude. The choice of thermoluminescent dosimeters LiF: Mg, Cu, P was done by having a detection efficiency of about fifteen times higher than its predecessor (LiF: Mg, Ti), and therefore, applied in very low doses dosimetry, and environmental dosimetry . The implementation of the use of pair dosimetric TLD-600H and 700H-TLD will serve as support for testing and studies on the effects of low doses of cosmic radiation in environmental dosimetry applied in the aviation environment in the usual flight altitudes. In this paper are presented the results of development of a methodology for dosimetry low doses of gamma radiation and neutrons using the pair dosimetric TLD-600H and 700H-TLD. The results demonstrate a sensitivity of dosimeters well above the dosimeters LiF: Mg, Ti confirming its suitability for dosimetry of low doses

  17. Cytogenetic dosimetry in suspected cases of ionizing radiation occupational exposure

    International Nuclear Information System (INIS)

    Ramalho, Adriana T.; Costa, Maria Lucia P.; Oliveira, Monica S.; Silva, Francisco Cesar A. da

    2001-01-01

    Cytogenetic dosimetry is very useful in routine as well as in serious accident situations in which exposed individuals do not wear physical dosimeters. Since 1984, the technique of cytogenetic dosimetry has been used as a routine in our laboratory at IRD/CNEN to complement the data of physical dosimetry. In the period from 1984 to 2000, 138 cases of occupational overexposure of individual dosimeters were investigated by us. In total, only in 36 of the 138 cases investigated the overexposure was confirmed by cytogenetic dosimetry. The data indicates a total confirmation index of just 26% of the suspected cases.(author)

  18. In vivo thermoluminescent dosimetry in studies of helicoid computed tomography and excretory urogram

    International Nuclear Information System (INIS)

    Cruz C, D.; Azorin N, J.; Saucedo A, V.M.; Barajas O, J.L.

    2005-01-01

    The dosimetry is the field of measurement of the ionizing radiations. It final objective is to determine the 'absorbed dose' for people. The dosimetry is vital in the radiotherapy, the radiological protection and the treatment technologies by irradiation. Presently work, we develop 'In vivo' dosimetry, in exposed patients to studies of helical computed tomography and excretory urogram. The dosimetry 'in vivo' was carried out in 20 patients selected aleatorily, for each medical study. The absorbed dose was measured in points of interest located in crystalline, thyroid, chest and abdomen of each patient, by means of thermoluminescent dosemeters (TLD) LiF: Mg,Cu,P + Ptfe of national fabrication. Also it was quantified the dose in the working area. (Author)

  19. Radiation dosimetry predicts IQ after conformal radiation therapy in pediatric patients with localized ependymoma

    International Nuclear Information System (INIS)

    Merchant, Thomas E.; Kiehna, Erin N.; Li Chenghong; Xiong Xiaoping; Mulhern, Raymond K.

    2005-01-01

    Purpose: To assess the effects of radiation dose-volume distribution on the trajectory of IQ development after conformal radiation therapy (CRT) in pediatric patients with ependymoma. Methods and Materials: The study included 88 patients (median age, 2.8 years ± 4.5 years) with localized ependymoma who received CRT (54-59.4 Gy) that used a 1-cm margin on the postoperative tumor bed. Patients were evaluated with tests that included IQ measures at baseline (before CRT) and at 6, 12, 24, 36, 48, and 60 months. Differential dose-volume histograms (DVH) were derived for total-brain, supratentorial-brain, and right and left temporal-lobe volumes. The data were partitioned into three dose intervals and integrated to create variables that represent the fractional volume that received dose over the specified intervals (e.g., V 0-20Gy , V 20-40Gy , V 40-65Gy ) and modeled with clinical variables to develop a regression equation to estimate IQ after CRT. Results: A total of 327 IQ tests were performed in 66 patients with infratentorial tumors and 20 with supratentorial tumors. The median follow-up was 29.4 months. For all patients, IQ was best estimated by age (years) at CRT; percent volume of the supratentorial brain that received doses between 0 and 20 Gy, 20 and 40 Gy, and 40 and 65 Gy; and time (months) after CRT. Age contributed significantly to the intercept (p > 0.0001), and the dose-volume coefficients were statistically significant (V 0-20Gy , p = 0.01; V 20-40Gy , p 40-65Gy , p = 0.04). A similar model was developed exclusively for patients with infratentorial tumors but not supratentorial tumors. Conclusion: Radiation dosimetry can be used to predict IQ after CRT in patients with localized ependymoma. The specificity of models may be enhanced by grouping according to tumor location

  20. SU-E-T-89: Characterization of Dental Restoration Material for Cs-137 Radiation Dosimetry.

    Science.gov (United States)

    Ratliff, S; Gustafson, B; Barry, K

    2012-06-01

    The purpose of this work is to characterize the radiation-induced thermoluminescence properties of a dental restoration material and to see if the material might be feasible for use in retrospective radiation dosimetry. Retrospective, or accidental, dosimetry is the study of using nearby materials to measure radiation received by individuals. In this project we obtained samples of Ivoclar Vivadent e.max CAD material, a glass-ceramic used for making dental restorations such as full or partial crowns. The samples were machined into square chips .32 cm × .32 cm × .089 cm and annealed in the same furnace used by the dentist. The samples were exposed to a Cs-137 source using a PMMA source holder and then read in a Harshaw 3500 TLD reader. The samples were read without nitrogen gas flux using heating rates of 5 degrees C/s or 10 degrees C/s up to a maximum temperature of 400 degrees Celsius. The glow curves were analyzed using Systat PeakFIT peak-fitting software and Microsoft Excel spreadsheets. The authors gratefully thank Dr. Aaron Imdieke and the staff of River City Dental, St. Cloud, MN for the dental restoration materials and the use of their dental furnace. A sample subjected to a radiation exposure of .04 C/kg exhibits a glow curve with a prominent peak at approximately 140 degrees Celsius, which is well-modeled by the first order glow curve deconvolution formula developed by Kitis, Gomez-Ros, and Tuyn. The activation energy corresponding to this peak is approximately 1 eV. The thermoluminescent signal fades with time after exposure. Ivoclar Vivadent e.max CAD dental restoration material has the potential to be used as a material for retrospective Cs-137 radiation dosimetry. Future work could look at its thermoluminescent dosimetry properties in more detail and also at other dental restoration materials. The authors would like to thank Dr. Aaron Imdieke and the staff of River City Dental, St. Cloud, MN, for the donation of scrap dental restoration materials and

  1. GENII (Generation II): The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

    Energy Technology Data Exchange (ETDEWEB)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-09-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs.

  2. GENII [Generation II]: The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

    International Nuclear Information System (INIS)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-09-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs

  3. GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 2, Users' manual: Hanford Environmental Dosimetry Upgrade Project

    International Nuclear Information System (INIS)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-11-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. This second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The first volume describes the theoretical considerations of the system. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 27 refs., 17 figs., 23 tabs

  4. Multi-dimensional fiber-optic radiation sensor for ocular proton therapy dosimetry

    International Nuclear Information System (INIS)

    Jang, K.W.; Yoo, W.J.; Moon, J.; Han, K.T.; Park, B.G.; Shin, D.; Park, S-Y.; Lee, B.

    2012-01-01

    In this study, we fabricated a multi-dimensional fiber-optic radiation sensor, which consists of organic scintillators, plastic optical fibers and a water phantom with a polymethyl methacrylate structure for the ocular proton therapy dosimetry. For the purpose of sensor characterization, we measured the spread out Bragg-peak of 120 MeV proton beam using a one-dimensional sensor array, which has 30 fiber-optic radiation sensors with a 1.5 mm interval. A uniform region of spread out Bragg-peak using the one-dimensional fiber-optic radiation sensor was obtained from 20 to 25 mm depth of a phantom. In addition, the Bragg-peak of 109 MeV proton beam was measured at the depth of 11.5 mm of a phantom using a two-dimensional sensor array, which has 10×3 sensor array with a 0.5 mm interval.

  5. Theory, development and principal application trends of lyoluminescence in integral radiation dosimetry

    International Nuclear Information System (INIS)

    Kubicek, I.

    1984-01-01

    The mechanism of lyoluminescence (LL) of inorganic and organic compounds is described in detail and discussed are the basic characteristics of the LL process, the physico-chemical properties of the system, the principle of measurement and the possibility of increasing the LL yield. Attention is also devoted to the design of evaluation kits developed and used by different laboratories. A substantial part of the study is devoted to the response of LL dosemeters to different types of ionizing radiation (gamma radiation, fast and slow neutrons and heavy charged particles). The high level of tissue equivalence of some organic materials, their sensitivity to gamma radiation and fast neutrons and finally the possible use of human biological tissue as a dosemeter predestinates the LL method for uses mainly in clinical and accident dosimetry. (author)

  6. EURADOS strategic research agenda. Visions for dosimetry of ionising radiation; Die strategische Forschungsagenda von EURADOS. Visionen fuer die Dosimetrie ionisierender Strahlung

    Energy Technology Data Exchange (ETDEWEB)

    Ruehm, W. [Helmholtz Zentrum Muenchen (Germany). Inst. fuer Strahlenschutz

    2016-07-01

    Since its foundation in 1981, EURADOS (the European Radiation Dosimetry Group e.V.) has been pursuing the goal to harmonise dosimetric practice of ionizing radiation in Europe, and to promote dosimetric research. As of August 2016, EURADOS had 67 institutional members, and up to 500 individual scientists, organized in eight Working Groups, work on improvements in dosimetry. In 2013, the EURADOS Council installed an ad-hoc editorial group, to identify open questions in radiation dosimetry research and to develop strategies that would allow answering these questions. In a joint effort of all EURADOS Working Groups, proposals were developed and summarized in a EURADOS Report. A short version of this report was published early this year in the peer reviewed international literature, in Radiation Protection Dosimetry. The present paper summarizes the proposals made. It is noted that this first version of the EURADOS Strategic Research Agenda already served as an input for a recent call published in Europe for Radiation Protection Research.

  7. γ radiation dosimetry in Mega rad range using sugar solution

    International Nuclear Information System (INIS)

    Venkataramani, R.; Mehta, S.K.; Soman, S.D.

    1976-01-01

    The formation of malonaldehyde under γ irradiation of solid sucrose and aqueous sucrose, fructose and arabinose solutions has been studied in the Mega rad range. Malonaldehyde (MA) concentration was estimated spectrophotometrically after complexing with 2-thio-barbituric acid. The effect of free radical scavengers (KI and N 2 O) on the yield of MA was investigated. Of the systems studied a 5% aqueous sucrose solution gave a proportional response of MA formation with dose in 0.2 to 5 Mega rad range. A 5% aqueous solution of sucrose prepared from sucrose irradiated in solid state also gave a smooth response of MA yield with dose from 8 to 30 Mega rad. The aqueous and solid sucrose systems together can be conveniently used for dosimetry in the range of 0.2 30 Mega rad. (author)

  8. gamma. radiation dosimetry in Mega rad range using sugar solution

    Energy Technology Data Exchange (ETDEWEB)

    Venkataramani, R; Mehta, S K; Soman, S D [Bhabha Atomic Research Centre, Bombay (India). Health Physics Div.

    1976-09-01

    The formation of malonaldehyde under ..gamma.. irradiation of solid sucrose and aqueous sucrose, fructose and arabinose solutions has been studied in the Mega rad range. Malonaldehyde (MA) concentration was estimated spectrophotometrically after complexing with 2-thio-barbituric acid. The effect of free radical scavengers (KI and N/sub 2/O) on the yield of MA was investigated. Of the systems studied a 5% aqueous sucrose solution gave a proportional response of MA formation with dose in 0.2 to 5 Mega rad range. A 5% aqueous solution of sucrose prepared from sucrose irradiated in solid state also gave a smooth response of MA yield with dose from 8 to 30 Mega rad. The aqueous and solid sucrose systems together can be conveniently used for dosimetry in the range of 0.2 30 Mega rad.

  9. A practical proposal for neutron dosimetry in radiation protection

    International Nuclear Information System (INIS)

    Busuoli, G.; Pelliccioni, M.

    1985-01-01

    The innovations recommended in ICRP Publication 26 give rise to questionable consequences for current radiation protection practice. One of the most efficient is a proliferation of quantities for external exposure, the so called ''operational quantities'', devoid of any physical basis and scientifically undesirable. This risks undermining the unitary order given to the formulation of the limits. Moreover, as soon as an agreement is reached, then most of the instrumentation used at present should be replaced or modified. In the case of neutron dosimetry, at the moment, changes would be inappropriate. This is because one must take into account the results from the reassessment of the doses received by Japanese who were exposed at Hiroshima and Nagasaki, and the recent rumours about an increase of the quality factor at low doses. While awaiting further reflection on the matter, the way to continue to use the most popular neutron environmental instrument, the rem-counter is explained. The proposed solution, which is as open to question as any other, should at least allow considerable economical advantages and secure the continuity of current practice. (author)

  10. Thermoluminescent properties of CVD diamond: applications to ionising radiation dosimetry

    International Nuclear Information System (INIS)

    Petitfils, A.

    2007-09-01

    Remarkable properties of synthetic diamond (human soft tissue equivalence, chemical stability, non-toxicity) make this material suitable for medical application as thermoluminescent dosimeter (TLD). This work highlights the interest of this material as radiotherapy TLD. In the first stage of this work, we looked after thermoluminescent (TL) and dosimetric properties of polycrystalline diamond made by Chemically Vapor Deposited (CVD) synthesis. Dosimetric characteristics are satisfactory as TLD for medical application. Luminescence thermal quenching on diamond has been investigated. This phenomenon leads to a decrease of dosimetric TL peak sensitivity when the heating rate increases. The second part of this work analyses the use of synthetic diamond as TLD in radiotherapy. Dose profiles, depth dose distributions and the cartography of an electron beam obtained with our samples are in very good agreement with results from an ionisation chamber. It is clearly shown that CVD) diamond is of interest to check beams of treatment accelerators. The use of these samples in a control of treatment with Intensity Modulated Radiation Therapy underlines good response of synthetic diamond in high dose gradient areas. These results indicate that CVD diamond is a promising material for radiotherapy dosimetry. (author)

  11. WE-AB-BRB-12: Nanoscintillator Fiber-Optic Detector System for Microbeam Radiation Therapy Dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Rivera, J [University of North Carolina and North Carolina State University, Chapel Hill, NC (United States); Dooley, J; Chang, S [University of North Carolina School of Medicine, Chapel Hill, NC (United States); Belley, M; Yoshizumi, T [Duke University Medical Center, Durham, NC (United States); Stanton, I; Langloss, B; Therien, M [Duke University, Durham, NC (United States)

    2015-06-15

    Purpose: Microbeam Radiation Therapy (MRT) is an experimental radiation therapy that has demonstrated a higher therapeutic ratio than conventional radiation therapy in animal studies. There are several roadblocks in translating the promising treatment technology to clinical application, one of which is the lack of a real-time, high-resolution dosimeter. Current clinical radiation detectors have poor spatial resolution and, as such, are unsuitable for measuring microbeams with submillimeter-scale widths. Although GafChromic film has high spatial resolution, it lacks the real-time dosimetry capability necessary for MRT preclinical research and potential clinical use. In this work we have demonstrated the feasibility of using a nanoscintillator fiber-optic detector (nanoFOD) system for real-time MRT dosimetry. Methods: A microplanar beam array is generated using a x-ray research irradiator and a custom-made, microbeam-forming collimator. The newest generation nanoFOD has an effective size of 70 µm in the measurement direction and was calibrated against a kV ion chamber (RadCal Accu-Pro) in open field geometry. We have written a computer script that performs automatic data collection with immediate background subtraction. A computer-controlled detector positioning stage is used to precisely measure the microbeam peak dose and beam profile by translating the stage during data collection. We test the new generation nanoFOD system, with increased active scintillation volume, against the previous generation system. Both raw and processed data are time-stamped and recorded to enable future post-processing. Results: The real-time microbeam dosimetry system worked as expected. The new generation dosimeter has approximately double the active volume compared to the previous generation resulting in over 900% increase in signal. The active volume of the dosimeter still provided the spatial resolution that meets the Nyquist criterion for our microbeam widths. Conclusion: We have

  12. Computer codes in nuclear safety, radiation transport and dosimetry; Les codes de calcul en radioprotection, radiophysique et dosimetrie

    Energy Technology Data Exchange (ETDEWEB)

    Bordy, J M; Kodeli, I; Menard, St; Bouchet, J L; Renard, F; Martin, E; Blazy, L; Voros, S; Bochud, F; Laedermann, J P; Beaugelin, K; Makovicka, L; Quiot, A; Vermeersch, F; Roche, H; Perrin, M C; Laye, F; Bardies, M; Struelens, L; Vanhavere, F; Gschwind, R; Fernandez, F; Quesne, B; Fritsch, P; Lamart, St; Crovisier, Ph; Leservot, A; Antoni, R; Huet, Ch; Thiam, Ch; Donadille, L; Monfort, M; Diop, Ch; Ricard, M

    2006-07-01

    The purpose of this conference was to describe the present state of computer codes dedicated to radiation transport or radiation source assessment or dosimetry. The presentations have been parted into 2 sessions: 1) methodology and 2) uses in industrial or medical or research domains. It appears that 2 different calculation strategies are prevailing, both are based on preliminary Monte-Carlo calculations with data storage. First, quick simulations made from a database of particle histories built though a previous Monte-Carlo simulation and secondly, a neuronal approach involving a learning platform generated through a previous Monte-Carlo simulation. This document gathers the slides of the presentations.

  13. International symposium on standards and codes of practice in medical radiation dosimetry. Book of extended synopses

    International Nuclear Information System (INIS)

    2002-01-01

    The development of radiation measurement standards by National Metrology Institutes (NMIs) and their dissemination to Secondary Standard Dosimetry Laboratories (SSDLs), cancer therapy centres and hospitals represent essential aspects of the radiation dosimetry measurement chain. Although the demands for accuracy in radiotherapy initiated the establishment of such measurement chains, similar traceable dosimetry procedures have been implemented, or are being developed, in other areas of radiation medicine (e.g. diagnostic radiology and nuclear medicine), in radiation protection and in industrial applications of radiation. In the past few years the development of primary standards of absorbed dose to water in 60 Co for radiotherapy dosimetry has made direct calibrations in terms of absorbed dose to water available in many countries for the first time. Some laboratories have extended the development of these standards to high energy photon and electron beams and to low and medium energy x-ray beams. Other countries, however, still base their dosimetry for radiotherapy on air kerma standards. Dosimetry for conventional external beam radiotherapy was probably the field where standardized procedures adopted by medical physicists at hospitals were developed first. Those were related to exposure and air kerma standards. The recent development of Codes of Practice (or protocols) based on the concept of absorbed dose to water has led to changes in calibration procedures at hospitals. The International Code of Practice for Dosimetry Based on Standards of Absorbed Dose to Water (TRS 398) was sponsored by the International Atomic Energy Agency (IAEA), World Health Organization (WHO), Pan-American Health Organization (PAHO) and the European Society for Therapeutic Radiology and Oncology (ESTRO) and is expected to be adopted in many countries worldwide. It provides recommendations for the dosimetry of all types of beams (except neutrons) used in external radiotherapy and satisfies

  14. International symposium on standards and codes of practice in medical radiation dosimetry. Book of extended synopses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    The development of radiation measurement standards by National Metrology Institutes (NMIs) and their dissemination to Secondary Standard Dosimetry Laboratories (SSDLs), cancer therapy centres and hospitals represent essential aspects of the radiation dosimetry measurement chain. Although the demands for accuracy in radiotherapy initiated the establishment of such measurement chains, similar traceable dosimetry procedures have been implemented, or are being developed, in other areas of radiation medicine (e.g. diagnostic radiology and nuclear medicine), in radiation protection and in industrial applications of radiation. In the past few years the development of primary standards of absorbed dose to water in {sup 60}Co for radiotherapy dosimetry has made direct calibrations in terms of absorbed dose to water available in many countries for the first time. Some laboratories have extended the development of these standards to high energy photon and electron beams and to low and medium energy x-ray beams. Other countries, however, still base their dosimetry for radiotherapy on air kerma standards. Dosimetry for conventional external beam radiotherapy was probably the field where standardized procedures adopted by medical physicists at hospitals were developed first. Those were related to exposure and air kerma standards. The recent development of Codes of Practice (or protocols) based on the concept of absorbed dose to water has led to changes in calibration procedures at hospitals. The International Code of Practice for Dosimetry Based on Standards of Absorbed Dose to Water (TRS 398) was sponsored by the International Atomic Energy Agency (IAEA), World Health Organization (WHO), Pan-American Health Organization (PAHO) and the European Society for Therapeutic Radiology and Oncology (ESTRO) and is expected to be adopted in many countries worldwide. It provides recommendations for the dosimetry of all types of beams (except neutrons) used in external radiotherapy and

  15. Development a high-resolution radiation dosimetry system based on Fricke solutions

    Energy Technology Data Exchange (ETDEWEB)

    Vedelago, J. [Laboratorio de Investigaciones e Instrumentacion en Fisica Aplicada a la Medicina e Imagenes por Rayos X, Laboratorio 448 FaMAF - UNC, Ciudad Universitaria, 5000 Cordoba (Argentina); Mattea, F. [Universidad Nacional de Cordoba, Facultad de Ciencias Quimicas, Departamento de Quimica Organica, Ciudad Universitaria, 5000 Cordoba (Argentina); Valente, M., E-mail: josevedelago@gmail.com [Instituto de Fisica E. Gaviola, Oficina 102 FaMAF - UNC, Ciudad Universitaria, 5000 Cordoba (Argentina)

    2014-08-15

    Due to the growing complexity of modern medical procedures involving the use of ionizing radiation, dosimetry by non-conventional techniques is one of the research areas in the field of greatest interest nowadays. Tissue-equivalent high-resolution dosimetry systems capable of attaining continuous dose mapping are required. In this scenario, Fricke gel dosimetry is a very promising option for in-phantom dose measurements in complex radiation techniques. Implementation of this technique requires dedicated instruments capable of measuring and performing the immediate in situ analysis of the acquired data at the radiation facility. The versatility of Fricke gel dosimetry in different applications depending on the chemical and isotopic composition of the dosimeter extends its application to different high performance conventional and non-conventional radiation procedures involving diverse types of radiation treatments and also radiation diagnosis procedures. This work presents an integral dosimetry system, based on Fricke gel solutions and their analysis by optical techniques, aiming for an increase in the precision on dose determinations. The chemical synthesis and dosimeter preparation were accomplished at LIIFAMIRx facilities, following the procedures and protocols described in previous works. Additionally, specific instrumentation for optical sample analysis was completely designed and constructed at LIIFAMIRx facilities. The main outcome of this work was the development of a methodology that improves the integral dose determination performance by the pre-irradiation of Fricke gel dosimeters. (author)

  16. Development a high-resolution radiation dosimetry system based on Fricke solutions

    International Nuclear Information System (INIS)

    Vedelago, J.; Mattea, F.; Valente, M.

    2014-08-01

    Due to the growing complexity of modern medical procedures involving the use of ionizing radiation, dosimetry by non-conventional techniques is one of the research areas in the field of greatest interest nowadays. Tissue-equivalent high-resolution dosimetry systems capable of attaining continuous dose mapping are required. In this scenario, Fricke gel dosimetry is a very promising option for in-phantom dose measurements in complex radiation techniques. Implementation of this technique requires dedicated instruments capable of measuring and performing the immediate in situ analysis of the acquired data at the radiation facility. The versatility of Fricke gel dosimetry in different applications depending on the chemical and isotopic composition of the dosimeter extends its application to different high performance conventional and non-conventional radiation procedures involving diverse types of radiation treatments and also radiation diagnosis procedures. This work presents an integral dosimetry system, based on Fricke gel solutions and their analysis by optical techniques, aiming for an increase in the precision on dose determinations. The chemical synthesis and dosimeter preparation were accomplished at LIIFAMIRx facilities, following the procedures and protocols described in previous works. Additionally, specific instrumentation for optical sample analysis was completely designed and constructed at LIIFAMIRx facilities. The main outcome of this work was the development of a methodology that improves the integral dose determination performance by the pre-irradiation of Fricke gel dosimeters. (author)

  17. Preliminary studies with 188Rhenium-tin colloid for radiation synovectomy: preparation, size determination, in vivo distribution, effects and dosimetry studies

    International Nuclear Information System (INIS)

    Mathe, D.; Balogh, L.; Polyak, A.; Kiraly, R.; Andocs, G.; Janoki, G. A.; Chaudhari, P.R.; Perge, E.; Glavits, R.

    2002-01-01

    Generator-produced beta-emitting radionuclides such 188R e are gaining in importance for radiosynoviorthesis because of their availability on a regular basis. We prepared a 188 Re-tin colloid in reaction carried out either at 100 o C or at room temperature (RT). The size of the colloid particles was measured with a laser light-scattering method, and their biodistribution, dosimetric aspects and therapeutic effects were studied in an antigen-induced arthritis (AIA) model in rabbits. 188R e-tin colloid solution was injected intraarticularly into the knee joints of rabbits with AIA and imaging studies were performed. Blood samples were collected post injection for estimation of the blood residence time. We also injected 2 intact rabbits in the same manner with 188R e perrhenate solution in order to observe its effects and distribution in the body. All the treated rabbit knees were subjected to histopathology.The colloid particle size distribution was different after preparation at the different reaction temperatures, with a more suitable mean of 4.53 μm in the RT preparation. The dose delivered to the synovial surface was between 3.51 and 4.21 Gy and that to the bone surface was between 0.70 and 0.84 Gy. Histopathologic examination revealed the development of fibrous connective tissue in the AIA knees 4 weeks after treatment, but not in the control group. The 188R e-tin colloid preparation used in study was suitable for radiation synovectomy application. It requires modifications in the preparation protocol so as to increase the labelling efficiency in correlation with an appropriate particle size. (author)

  18. Practice for characterization and performance of a high-dose radiation dosimetry calibration laboratory

    International Nuclear Information System (INIS)

    2003-01-01

    This practice addresses the specific requirements for laboratories engaged in dosimetry calibrations involving ionizing radiation, namely, gamma-radiation, electron beams or X-radiation (bremsstrahlung) beams. It specifically describes the requirements for the characterization and performance criteria to be met by a high-dose radiation dosimetry calibration laboratory. The absorbed-dose range is typically between 10 and 10 5 Gy. This practice addresses criteria for laboratories seeking accreditation for performing high-dose dosimetry calibrations, and is a supplement to the general requirements described in ISO/IEC 17025. By meeting these criteria and those in ISO/IEC 17025, the laboratory may be accredited by a recognized accreditation organization. Adherence to these criteria will help to ensure high standards of performance and instill confidence regarding the competency of the accredited laboratory with respect to the services it offers

  19. Neutron generator (HIRRAC) and dosimetry study.

    Science.gov (United States)

    Endo, S; Hoshi, M; Takada, J; Tauchi, H; Matsuura, S; Takeoka, S; Kitagawa, K; Suga, S; Komatsu, K

    1999-12-01

    Dosimetry studies have been made for neutrons from a neutron generator at Hiroshima University (HIRRAC) which is designed for radiobiological research. Neutrons in an energy range from 0.07 to 2.7 MeV are available for biological irradiations. The produced neutron energies were measured and evaluated by a 3He-gas proportional counter. Energy spread was made certain to be small enough for radiobiological studies. Dose evaluations were performed by two different methods, namely use of tissue equivalent paired ionization chambers and activation of method with indium foils. Moreover, energy deposition spectra in small targets of tissue equivalent materials, so-called lineal energy spectrum, were also measured and are discussed. Specifications for biological irradiation are presented in terms of monoenergetic beam conditions, dose rates and deposited energy spectra.

  20. Dosimetry for radiation processing. Final report of the co-ordinated research project on characterization and evaluation of high dose dosimetry techniques for quality assurance in radiation processing

    International Nuclear Information System (INIS)

    2000-06-01

    In many Member States the use of large cobalt-60 gamma ray facilities and electron beam accelerators with beam energies from about 0.1 to 10 MeV for industrial processing continues to increase. For these processes, quality assurance relies on the application of well established dosimetry systems and procedures. This is especially the case for health regulated processes, such as the radiation sterilization of health care products, and the irradiation of food to eliminate pathogenic organisms or to control insect pests. A co-ordinated research project (CRP) was initiated by the IAEA in June 1995. Research contracts and research agreements in areas of high dose dosimetry were initiated to meet these challenges. The major goals of this CRP were to investigate the parameters that influence the response of dosimeters and to develop reference and transfer dosimetry techniques, especially for electron beams of energy less than 4 MeV and for high energy X ray sources (up to 5 MV). These will help to unify the radiation measurements performed by different radiation processing facilities and other high dose dosimetry users in Member States and encourage efforts to obtain traceability to primary and secondary standards laboratories. It will also aim to strengthen and expand the present International Dose Assurance Service (IDAS) provided by the IAEA

  1. Personnel radiation dosimetry laboratory accreditation programme for thermoluminescent dosimeters : a proposal

    International Nuclear Information System (INIS)

    Bhatt, B.C.; Srivastava, J.K.; Iyer, P.S.; Venkatraman, G.

    1993-01-01

    Accreditation for thermoluminescent dosimeters is the process of evaluating a programme intending to use TL personnel dosimeters to measure, report and record dose equivalents received by radiation workers. In order to test the technical competence for conducting personnel dosimetry service as well as to decentralize personnel monitoring service, it has been proposed by Radiological Physics Division (RPhD) to accredit some of the laboratories, in the country. The objectives of this accreditation programme are: (i) to give recognition to competent dosimetry processors, and (ii) to provide periodic evaluation of dosimetry processors, including review of internal quality assurance programme to improve the quality of personnel dosimetry processing. The scientific support for the accreditation programme will be provided by the scientific staff from Radiological Physics Division (RPhD) and Radiation Protection Services Division (RPSD). This paper describes operational and technical requirements for the Personnel Radiation Dosimetry Laboratory Accreditation Programme for Thermoluminescent Dosimeters for Personnel Dosimetry Processors. Besides, many technical documents dealing with the TL Personnel Dosimeter System have been prepared. (author). 5 refs., 2 figs

  2. International Standardization of the Clinical Dosimetry of Beta Radiation Brachytherapy Sources: Progress of an ISO Standard

    Science.gov (United States)

    Soares, Christopher

    2006-03-01

    In 2004 a new work item proposal (NWIP) was accepted by the International Organization for Standardization (ISO) Technical Committee 85 (TC85 -- Nuclear Energy), Subcommittee 2 (Radiation Protection) for the development of a standard for the clinical dosimetry of beta radiation sources used for brachytherapy. To develop this standard, a new Working Group (WG 22 - Ionizing Radiation Dosimetry and Protocols in Medical Applications) was formed. The standard is based on the work of an ad-hoc working group initiated by the Dosimetry task group of the Deutsches Insitiut für Normung (DIN). Initially the work was geared mainly towards the needs of intravascular brachytherapy, but with the decline of this application, more focus has been placed on the challenges of accurate dosimetry for the concave eye plaques used to treat ocular melanoma. Guidance is given for dosimetry formalisms, reference data to be used, calibrations, measurement methods, modeling, uncertainty determinations, treatment planning and reporting, and clinical quality control. The document is currently undergoing review by the ISO member bodies for acceptance as a Committee Draft (CD) with publication of the final standard expected by 2007. There are opportunities for other ISO standards for medical dosimetry within the framework of WG22.

  3. Substance for thermoluminescent dosimetry of photon radiation in adipose tissue

    International Nuclear Information System (INIS)

    Kalmykov, L.Z.; Kandel', T.G.

    1983-01-01

    Substance composition for thermoluminescent photon dosimetry in adipose tissue is proposed which makes it possible to simplify dosimetric measurements and to improve their accuracy. The substance consists of powder-like thermoluminophor Li 2 B 4 O 7 (0.03%Mn) 48-52 mass % and bistriethylammonium dodecahydrododecaborane - 48-52 mass %. The above substance is equivalent in respect to dosimetry to adipose tissue within the 10 keV - 10 MeV energy range

  4. Academic Training - The use of Monte Carlo radiation transport codes in radiation physics and dosimetry

    CERN Multimedia

    Françoise Benz

    2006-01-01

    2005-2006 ACADEMIC TRAINING PROGRAMME LECTURE SERIES 27, 28, 29 June 11:00-12:00 - TH Conference Room, bldg. 4 The use of Monte Carlo radiation transport codes in radiation physics and dosimetry F. Salvat Gavalda,Univ. de Barcelona, A. FERRARI, CERN-AB, M. SILARI, CERN-SC Lecture 1. Transport and interaction of electromagnetic radiation F. Salvat Gavalda,Univ. de Barcelona Interaction models and simulation schemes implemented in modern Monte Carlo codes for the simulation of coupled electron-photon transport will be briefly reviewed. Different schemes for simulating electron transport will be discussed. Condensed algorithms, which rely on multiple-scattering theories, are comparatively fast, but less accurate than mixed algorithms, in which hard interactions (with energy loss or angular deflection larger than certain cut-off values) are simulated individually. The reliability, and limitations, of electron-interaction models and multiple-scattering theories will be analyzed. Benchmark comparisons of simu...

  5. Application of spectroscopic techniques in the radiation dosimetry of glasses: An update

    International Nuclear Information System (INIS)

    Natarajan, V

    2009-01-01

    The colorimetry and thermoluminescence properties of gamma irradiated glass were reported in as early as 1920. The utility of radio-photoluminescence (RPL) of silver activated metaphosphate glass for monitoring high doses of accidental and routine gamma radiation was reported in the 1960s. Since then considerable amount of research work has been carried out to study the thermoluminescence (TL), optical absorption (OA), electron paramagnetic resonance (EPR) and optically stimulated luminescence (OSL) of different commercially available glasses for high as well as low dose applications. A brief review of the progress made in the spectroscopic studies of glasses during the past few decades and the application of glasses for radiation dosimetry has been given in this paper.

  6. Application of spectroscopic techniques in the radiation dosimetry of glasses: An update

    Energy Technology Data Exchange (ETDEWEB)

    Natarajan, V, E-mail: vnatra@yahoo.co.in [Radiochemistry Division, Bhabha Atomic Research Centre, Mumbai 40085 (India)

    2009-07-15

    The colorimetry and thermoluminescence properties of gamma irradiated glass were reported in as early as 1920. The utility of radio-photoluminescence (RPL) of silver activated metaphosphate glass for monitoring high doses of accidental and routine gamma radiation was reported in the 1960s. Since then considerable amount of research work has been carried out to study the thermoluminescence (TL), optical absorption (OA), electron paramagnetic resonance (EPR) and optically stimulated luminescence (OSL) of different commercially available glasses for high as well as low dose applications. A brief review of the progress made in the spectroscopic studies of glasses during the past few decades and the application of glasses for radiation dosimetry has been given in this paper.

  7. Overview of environmental radiological monitoring program of Institute of Radiation Protection And Dosimetry - IRD

    Energy Technology Data Exchange (ETDEWEB)

    Gomes, Sarah Barreto Oliveira de Christo; Peres, Sueli da Silva, E-mail: suelip@ird.gov.br, E-mail: sarah.barreto1@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Div. de Radioproteção

    2017-07-01

    As a branch of the Brazilian Nuclear Energy Commission (CNEN), the Institute of Radiation Protection and Dosimetry (IRD) performs extensive activities in the fields of radiation protection, metrology, and dosimetry, as well as specific education, onto a wide operational scope that includes the technical support to national regulatory authorities in the licensing process for nationwide nuclear and radioactive facilities. IRD has several laboratories where are performed radiometric and radiochemical analyses and others radioactivity evaluation procedures in different types of samples obtained in the inspection activities, production of radioactivity metrological standards and reference material by National Laboratory of Metrology of Ionizing Radiation (LMNRI), besides others research activities. In this laboratories can be used sealed or unsealed radioactive sources and radiation-producing devices and are classified with radioactive installations in accordance to national regulations. This way, radioactive liquid effluents can be eventually produced and released into the environment in the course of such activities and an effluent monitoring program to control and reduce the releases to environment is carried out. Additionally, IRD maintains the Radioactive Waste Management Program and Environmental Radiological Monitoring Program (ERMP) in accordance to national regulations requirements. The primary focus of ERMP comprises the validation of the dose prognostics for the public members due to effluents discharge and the provision of consistent projections of the radiation levels at the monitoring sites. In this study, a long term ERMP data survey is discussed, spanning the last thirteen years of activities. On the basis of such discussions and prognostics, it could be observed that the radiological environmental radiological impact due to operation of IRD installations is negligible. (author)

  8. Overview of environmental radiological monitoring program of Institute of Radiation Protection And Dosimetry - IRD

    International Nuclear Information System (INIS)

    Gomes, Sarah Barreto Oliveira de Christo; Peres, Sueli da Silva

    2017-01-01

    As a branch of the Brazilian Nuclear Energy Commission (CNEN), the Institute of Radiation Protection and Dosimetry (IRD) performs extensive activities in the fields of radiation protection, metrology, and dosimetry, as well as specific education, onto a wide operational scope that includes the technical support to national regulatory authorities in the licensing process for nationwide nuclear and radioactive facilities. IRD has several laboratories where are performed radiometric and radiochemical analyses and others radioactivity evaluation procedures in different types of samples obtained in the inspection activities, production of radioactivity metrological standards and reference material by National Laboratory of Metrology of Ionizing Radiation (LMNRI), besides others research activities. In this laboratories can be used sealed or unsealed radioactive sources and radiation-producing devices and are classified with radioactive installations in accordance to national regulations. This way, radioactive liquid effluents can be eventually produced and released into the environment in the course of such activities and an effluent monitoring program to control and reduce the releases to environment is carried out. Additionally, IRD maintains the Radioactive Waste Management Program and Environmental Radiological Monitoring Program (ERMP) in accordance to national regulations requirements. The primary focus of ERMP comprises the validation of the dose prognostics for the public members due to effluents discharge and the provision of consistent projections of the radiation levels at the monitoring sites. In this study, a long term ERMP data survey is discussed, spanning the last thirteen years of activities. On the basis of such discussions and prognostics, it could be observed that the radiological environmental radiological impact due to operation of IRD installations is negligible. (author)

  9. Computational hybrid anthropometric paediatric phantom library for internal radiation dosimetry

    Science.gov (United States)

    Xie, Tianwu; Kuster, Niels; Zaidi, Habib

    2017-04-01

    Hybrid computational phantoms combine voxel-based and simplified equation-based modelling approaches to provide unique advantages and more realism for the construction of anthropomorphic models. In this work, a methodology and C++ code are developed to generate hybrid computational phantoms covering statistical distributions of body morphometry in the paediatric population. The paediatric phantoms of the Virtual Population Series (IT’IS Foundation, Switzerland) were modified to match target anthropometric parameters, including body mass, body length, standing height and sitting height/stature ratio, determined from reference databases of the National Centre for Health Statistics and the National Health and Nutrition Examination Survey. The phantoms were selected as representative anchor phantoms for the newborn, 1, 2, 5, 10 and 15 years-old children, and were subsequently remodelled to create 1100 female and male phantoms with 10th, 25th, 50th, 75th and 90th body morphometries. Evaluation was performed qualitatively using 3D visualization and quantitatively by analysing internal organ masses. Overall, the newly generated phantoms appear very reasonable and representative of the main characteristics of the paediatric population at various ages and for different genders, body sizes and sitting stature ratios. The mass of internal organs increases with height and body mass. The comparison of organ masses of the heart, kidney, liver, lung and spleen with published autopsy and ICRP reference data for children demonstrated that they follow the same trend when correlated with age. The constructed hybrid computational phantom library opens up the prospect of comprehensive radiation dosimetry calculations and risk assessment for the paediatric population of different age groups and diverse anthropometric parameters.

  10. Recent developments of optically stimulated luminescence materials and techniques for radiation dosimetry and clinical applications

    Directory of Open Access Journals (Sweden)

    Pradhan A

    2008-01-01

    Full Text Available During the last 10 years, optically stimulated luminescence (OSL has emerged as a formidable competitor not only to thermoluminescence dosimetry (TLD but also to several other dosimetry systems. Though a large number of materials have been synthesized and studied for OSL, Al 2 O 3 :C continues to dominate the dosimetric applications. Re-investigations of OSL in BeOindicate that this material might provide an alternative to Al 2 O 3 :C. Study of OSL of electronic components of mobile phones and ID cards appears to have opened up a feasibility of dosimetry and dose reconstruction using the electronic components of gadgets of everyday use in the events of unforeseen situations of radiological accidents, including the event of a dirty bomb by terrorist groups. Among the newly reported materials, a very recent development of NaMgF 3 :Eu 2+ appears fascinating because of its high OSL sensitivity and tolerable tissue equivalence. In clinical dosimetry, an OSL as a passive dosimeter could do all that TLD can do, much faster with a better or at least the same efficiency; and in addition, it provides a possibility of repeated readout unlike TLD, in which all the dose information is lost in a single readout. Of late, OSL has also emerged as a practical real-time dosimeter for in vivo measurements in radiation therapy (for both external beams and brachytherapy and in various diagnostic radiological examinations including mammography and CT dosimetry. For in vivo measurements, a probe of Al 2 O 3 :C of size of a fraction of a millimeter provides the information on both the dose rate and the total dose from the readout of radioluminescence and OSL signals respectively, from the same probe. The availability of OSL dosimeters in various sizes and shapes and their performance characteristics as compared to established dosimeters such as plastic scintillation dosimeters, diode detectors, MOSFET detectors, radiochromic films, etc., shows that OSL may soon become

  11. Perofrmance testing of personnel dosimetry services. Final report of a two-year pilot study, October 1977-September 1979

    International Nuclear Information System (INIS)

    Plato, P.; Hudson, G.

    1980-01-01

    A two-year pilot study was conducted of the Health Physics Society Standards Committee (HPSSC) Standard titled, Criteria for Testing Personnel Dosimetry Performance. The objectives of the pilot study were: to give processors an opportunity to correct any problems that are uncovered; to develop operational and administrative prodedures to be used later by a permanent testing laboratory; and to determine whether the proposed HPSSC Standard provides an adequate and practical test of dosimetry performance. Fifty-nine dosimetry processors volunteered to submit dosimeters for test irradiations according to the requirements of the HPSSC Standard. The feasibility of using the HPSSC Standard for a future mandatory testing program for personnel dosimetry processors is discussed. This report shows the results of the pilot study and contains recommendations for revisions in the Standard that will make a mandatory testing program useful to regulatory agencies, dosimetry processors, and radiation workers that use personnel dosimeters

  12. Thermoluminescence characteristics of different dimensions of Ge-doped optical fibers in radiation dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Begum, M.; Mizanur R, A. K. M.; Abdul R, H. A.; Yusoff, Z. [Multimedia University, Faculty of Engineering, 63100 Cyberjaya, Selangor Darul Ehsan (Malaysia); Begum, M. [Bangladesh Atomic Energy Commission, E-12/A, Agargaon, Sher-e-Blanga Nagar Dhaka-1207 (Bangladesh); Mat-Sharif, K. A. [Lingkaran Teknokrat Timur, Telekom Research and Development, 63000 Cyberjaya, Selangor Darul Ehsan (Malaysia); Amin, Y. M. [University of Malaya, Faculty of Science, Depatment of Physics, 50603 Kuala Lumpur (Malaysia); Bradley, D. A., E-mail: go2munmun@yahoo.com [University of Surrey, Department of Physics, Guildford GU2 7XH (United Kingdom)

    2014-08-15

    Important thermoluminescence (Tl) properties of five (5) different core sizes Ge doped optical fibers have been studied to develop new Tl material with better response. These are drawn from same preform applying different speed and tension during drawing phase. The results of the investigations are also compared with most commonly used standard TLD-100 chips (LiF:Mg,Ti) and commercial multimode Ge doped optical fiber (Yangtze Optical Fiber, China). Scanning Electron Microscope (Sem) and EDX analysis of the fibers are also performed to map Ge distribution across the deposited region. Standard Gamma radiation source in SSDL (Secondary Standard Dosimetry Lab) was used for irradiation covering dose range from 1 Gy to 10 Gy. The essential dosimetric parameters that have been studied are Tl linearity, reproducibility and fading. Prior to irradiation all samples ∼0.5 cm length are annealed at temperature of 400 grades C for 1 hour period to standardize their sensitivities and background. Standard TLD-100 chips are also annealed for 1 hour at 400 grades C and subsequently 2 hours at 100 grades C to yield the highest sensitivity. Tl responses of these fibers show linearity over a wide gamma radiation dose that is an important property for radiation dosimetry. Among all fibers used in this study, 100 μm core diameter fiber provides highest response that is 2.6 times than that of smallest core (20 μm core) optical fiber. These fiber-samples demonstrate better response than commercial multi-mode optical fiber and also provide low degree of fading about 20% over a period of fifteen days for gamma radiation. Effective atomic number (Z{sub eff}) is found in the range (13.25 to 13.69) that is higher than soft tissue (7.5) however within the range of human-bone (11.6-13.8). All the fibers can also be re-used several times as a detector after annealing. Tl properties of the Ge-doped optical fibers indicate promising applications in ionizing radiation dosimetry. (author)

  13. Thermoluminescence characteristics of different dimensions of Ge-doped optical fibers in radiation dosimetry

    International Nuclear Information System (INIS)

    Begum, M.; Mizanur R, A. K. M.; Abdul R, H. A.; Yusoff, Z.; Begum, M.; Mat-Sharif, K. A.; Amin, Y. M.; Bradley, D. A.

    2014-08-01

    Important thermoluminescence (Tl) properties of five (5) different core sizes Ge doped optical fibers have been studied to develop new Tl material with better response. These are drawn from same preform applying different speed and tension during drawing phase. The results of the investigations are also compared with most commonly used standard TLD-100 chips (LiF:Mg,Ti) and commercial multimode Ge doped optical fiber (Yangtze Optical Fiber, China). Scanning Electron Microscope (Sem) and EDX analysis of the fibers are also performed to map Ge distribution across the deposited region. Standard Gamma radiation source in SSDL (Secondary Standard Dosimetry Lab) was used for irradiation covering dose range from 1 Gy to 10 Gy. The essential dosimetric parameters that have been studied are Tl linearity, reproducibility and fading. Prior to irradiation all samples ∼0.5 cm length are annealed at temperature of 400 grades C for 1 hour period to standardize their sensitivities and background. Standard TLD-100 chips are also annealed for 1 hour at 400 grades C and subsequently 2 hours at 100 grades C to yield the highest sensitivity. Tl responses of these fibers show linearity over a wide gamma radiation dose that is an important property for radiation dosimetry. Among all fibers used in this study, 100 μm core diameter fiber provides highest response that is 2.6 times than that of smallest core (20 μm core) optical fiber. These fiber-samples demonstrate better response than commercial multi-mode optical fiber and also provide low degree of fading about 20% over a period of fifteen days for gamma radiation. Effective atomic number (Z eff ) is found in the range (13.25 to 13.69) that is higher than soft tissue (7.5) however within the range of human-bone (11.6-13.8). All the fibers can also be re-used several times as a detector after annealing. Tl properties of the Ge-doped optical fibers indicate promising applications in ionizing radiation dosimetry. (author)

  14. Thermoluminescence characteristics of Ge-doped optical fibers with different dimensions for radiation dosimetry

    International Nuclear Information System (INIS)

    Begum, Mahfuza; Rahman, A.K.M. Mizanur; Abdul-Rashid, H.A.; Yusoff, Z.; Begum, Mahbuba; Mat-Sharif, K.A.; Amin, Y.M.; Bradley, D.A.

    2015-01-01

    Important thermoluminescence (TL) properties of five (5) different core sizes Ge-doped optical fibers have been studied to develop new TL material with better response. These are drawn from same preform applying different speed and tension during drawing phase to produce Ge-doped optical fibers with five (5) different core sizes. The results of the investigations are also compared with most commonly used standard TLD-100 chips (LiF:Mg,Ti) and commercial multimode Ge-doped optical fiber (Yangtze Optical Fiber, China). Scanning Electron Microscope (SEM) and EDX analysis of the fibers are also performed to map Ge distribution across the deposited region. Standard Gamma radiation source in Secondary Standard Dosimetry Lab (SSDL) was used for irradiation covering dose range from 1 Gy to 10 Gy. The essential dosimetric parameters that have been studied are TL linearity, reproducibility and fading. Prior to irradiation all samples ∼0.5 cm length are annealed at temperature of 400 °C for 1 h period to standardize their sensitivities and background. Standard TLD-100 chips are also annealed for 1 h at 400 °C and subsequently 2 h at 100 °C to yield the highest sensitivity. TL responses of these fibers show linearity over a wide gamma radiation dose that is an important property for radiation dosimetry. Among all fibers used in this study, 100 μm core diameter fiber provides highest response that is 2.6 times than that of smallest core (20 μm core) optical fiber. These fiber-samples demonstrate better response than commercial multi-mode optical fiber and also provide low degree of fading about 20% over a period of fifteen days for gamma radiation. Effective atomic number (Z eff ) is found in the range (13.25–13.69) which is higher than soft tissue (7.5) however within the range of human-bone (11.6–13.8). All the fibers can also be re-used several times as a detector after annealing. TL properties of the Ge-doped optical fibers indicate promising applications in

  15. Voxel anthropomorphic phantoms: review of models used for ionising radiation dosimetry

    International Nuclear Information System (INIS)

    Lemosquet, A.; Carlan, L. de; Clairand, I.

    2003-01-01

    Computational anthropomorphic phantoms have been used since the 1970's for dosimetric calculations. Realistic geometries are required for this operation, resulting in the development of ever more accurate phantoms. Voxel phantoms, consisting of a set of small-volume elements, appeared towards the end of the 1980's, and significantly improved on the original mathematical models. Voxel phantoms are models of the human body, obtained using computed tomography (CT) or magnetic resonance images (MRI). These phantoms are an extremely accurate representation of the human anatomy. This article provides a review of the literature available on the development of these phantoms and their applications in ionising radiation dosimetry. The bibliographical study has shown that there is a wide range of phantoms, covering various characteristics of the general population in terms of sex, age or morphology, and that they are used in applications relating to all aspects of ionising radiation. (author)

  16. Uses of polymer-alanine film/ESR dosimeters in dosimetry of ionizing radiation

    International Nuclear Information System (INIS)

    Xie Liqing; Zhang Yinfeng; Dai Jinxian; Lu Ting; Chen Ruyi; Yang Hua

    1993-01-01

    Alanine ESR dosimetry is a reliable method, used in a various fields of ionizing radiation. The polymer-alanine film/ESR dosimeters of 0.3 -0.4 mm thickness were prepared and their dosimetric properties were studied for 60 Co γ photons and 3 - 5 MeV electrons in the dose range from 20 Gy to 100 kGy. The results show that under normal conditions the alanine calibration curves are linear in the dose range from 100 Gy to 10kGy. The dose profiles at the electron radiation field were measured with the film alanine dosimeters. The polymer-alanine film dosimeters were used for ion implantation of 400 keV ion implantor. Their dose response and energy dependence were investigated initially. (Author)

  17. Estimation of background radiation doses for the Peninsular Malaysia's population by ESR dosimetry of tooth enamel.

    Science.gov (United States)

    Rodzi, Mohd; Zhumadilov, Kassym; Ohtaki, Megu; Ivannikov, Alexander; Bhattacharjee, Deborshi; Fukumura, Akifumi; Hoshi, Masaharu

    2011-08-01

    Background radiation dose is used in dosimetry for estimating occupational doses of radiation workers or determining radiation dose of an individual following accidental exposure. In the present study, the absorbed dose and the background radiation level are determined using the electron spin resonance (ESR) method on tooth samples. The effect of using different tooth surfaces and teeth exposed with single medical X-rays on the absorbed dose are also evaluated. A total of 48 molars of position 6-8 were collected from 13 district hospitals in Peninsular Malaysia. Thirty-six teeth had not been exposed to any excessive radiation, and 12 teeth had been directly exposed to a single X-ray dose during medical treatment prior to extraction. There was no significant effect of tooth surfaces and exposure with single X-rays on the measured absorbed dose of an individual. The mean measured absorbed dose of the population is 34 ± 6.2 mGy, with an average tooth enamel age of 39 years. From the slope of a regression line, the estimated annual background dose for Peninsular Malaysia is 0.6 ± 0.3 mGy y(-1). This value is slightly lower than the yearly background dose for Malaysia, and the radiation background dose is established by ESR tooth measurements on samples from India and Russia.

  18. Biodistribution and radiation dosimetry of [11C]DASB in baboons

    International Nuclear Information System (INIS)

    Belanger, Marie-Jose; Simpson, Norman R.; Wang, Theodore

    2004-01-01

    Objective: The serotonin transporter has been implicated in a variety of conditions including mood disorders and suicidal behavior. In vivo human brain studies with positron emission tomography and the serotonin transporter antagonist [ 11 C]DASB ([ 11 C]-3-amino-4-(2-dimethylaminomethyl-phenylsulfanyl)-benzonitrile) are ongoing in several laboratories with the maximum administered activity based on dosimetry collected in rodents. We report on the biodistribution and dosimetry of [ 11 C]DASB in the baboon as this species may be a more reliable surrogate for human dosimetry. Methods: Four baboon studies (two studies in each of two baboons) were acquired in an ECAT ACCEL camera after the bolus injection of 183±5 MBq/2.3±1.0 nmol of [ 11 C]DASB. For each study, six whole-body emission scans were collected in 3D mode over 6/7 bed positions for 2 h. Regions of interest were drawn on brain, lungs, liver, gallbladder, spleen, kidneys, small intestine and bladder. Since no fluid was removed from the animal, total body radioactivity was calculated using the injected dose calibrated to the ACCEL image units. Results: Uptake was greatest in lungs, followed by the urinary bladder, gallbladder, brain and other organs. The ligand was eliminated via the hepato-billiary and renal systems. The largest absorbed dose was found in the lungs (3.6x10 -2 mSv/MBq). The absorbed radiation doses in lungs and gallbladder were four and nine times larger than that previously estimated from rat studies. Conclusion: Based on our baboon biodistribution and dose estimates, the lungs are the critical organs for administration of [ 11 C]DASB. In the United States, the absorbed dose to the lungs would limit [ 11 C]DASB administered with the approval of a Radioactive Drug Research Committee to 1400 MBq (37 mCi) in the adult male and 1100 MBq (30 mCi) in the adult female

  19. European questionnaire on the use of computer programmes in radiation dosimetry

    International Nuclear Information System (INIS)

    Gualdrini, G.; Tanner, R.; Terrisol, M.

    1999-01-01

    Because of a potential reduction of necessary experimental efforts, the combination of measurements and supplementing calculations, also in the field of radiation dosimetry, may allow time and money to be saved if computational methods are used which are well suited to reproduce experimental data in a satisfactory quality. The dramatic increase in computing power in recent years now permits the use of computational tools for dosimetry also in routine applications. Many institutions dealing with radiation protection, however, have small groups which, in addition to their routine work, often cannot afford to specialise in the field of computational dosimetry. This means that not only experts but increasingly also casual users employ complicated computational tools such as general-purpose transport codes. This massive use of computer programmes in radiation protection and dosimetry applications motivated the Concerted Action Investigation and Quality Assurance of Numerical Methods in Radiation Protection Dosimetry of the 4th framework programme of the European Commission to prepare, distribute and evaluate a questionnaire on the use of such codes. A significant number of scientists from nearly all the countries of the European Community (and some countries outside Europe) contributed to the questionnaire, that allowed to obtain a satisfactory overview of the state of the art in this field. The results obtained from the questionnaire and summarised in the present Report are felt to be indicative of the situation of using sophisticated computer codes within the European Community although the group of participating scientist may not be a representative sample in a strict statistical sense [it

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

    International Nuclear Information System (INIS)

    2014-01-01

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

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

    International Nuclear Information System (INIS)

    2011-01-01

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

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

    International Nuclear Information System (INIS)

    2014-01-01

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

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

    International Nuclear Information System (INIS)

    2014-01-01

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

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

    International Nuclear Information System (INIS)

    2015-01-01

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

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

    International Nuclear Information System (INIS)

    2013-01-01

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

  6. A Finnish national code of practice for reference dosimetry of radiation therapy

    International Nuclear Information System (INIS)

    Kosunen, A.; Sipilae, P.; Jaervinen, H.; Parkkinen, R.; Jokelainen, I.

    2002-01-01

    Full text: A national Code of Practice (CoP) for reference dosimetry of radiation therapy in Finland will be established during 2002 and will be implemented from the beginning of 2003. The CoP will cover dosimetry of the conventional radiotherapy modalities used in Finland i.e. external radiotherapy with megavoltage photon and electron beams, external radiotherapy with low energy kilovoltage X-ray beams and brachytherapy. The formalisms for external radiation beam dosimetry are those of TRS 389. For brachytherapy the formalism will follow the general guidelines of TECDOC-1274. The CoP will be prepared by the SSDL of STUK in close co-operation with the Finnish radiotherapy physicists. For external beam radiotherapy, the main objective of the national Code of Practice for radiation therapy dosimetry is to maintain the achieved good level of consistency of the dosimetry procedures in external beam radiotherapy as the 'absorbed dose to water' based approach of TRS 389 is implemented in Finland. In the CoP the dosimetry the procedures are described for the whole dosimetry chain starting from the calibration of the ionisation chambers at the SSDL of STUK and ending to the calibration of the beam monitor ionisation chamber of a linear accelerator. For brachytherapy dosimetry the aim is to fix the national practice for reference air kerma rate calibrations both for radioactive sources and for well-type ionisation chambers. Although the dosimetry procedures are described independently of the SSDL service, CoP makes use of the special features of the calibration service offered by the SSDL of STUK. For ionisation chambers used for photon dosimetry the calibration factors for the user measurement chain are given not only for the actual reference beam quality ( 60 Co) but also for a set of user beam qualities. Furthermore, SSDL of STUK offers calibration services for plane parallel ionisation chambers in an electron beam of a user linac. For brachytherapy SSDL of STUK has

  7. Radiation effects analysis in a group of interventional radiologists using biological and physical dosimetry methods

    Energy Technology Data Exchange (ETDEWEB)

    Ramos, M., E-mail: WEMLmirapas@iqn.upv.e [Department of Chemical and Nuclear Engineering, Polytechnic University of Valencia, Camino de Vera s/n, 46022 Valencia (Spain); Montoro, A.; Almonacid, M. [Radiation Protection Service, Hospital Universitario La Fe Valencia (Spain); Ferrer, S. [Department of Chemical and Nuclear Engineering, Polytechnic University of Valencia, Camino de Vera s/n, 46022 Valencia (Spain); Barquinero, J.F. [Biological Dosimetry Service, Unit of Anthropology, Department of Animal and Vegetable Biology and Ecology, Universitat Autonoma de Barcelona (UAB) (Spain); Tortosa, R. [Radiation Protection Service, Hospital Universitario La Fe Valencia (Spain); Verdu, G. [Department of Chemical and Nuclear Engineering, Polytechnic University of Valencia, Camino de Vera s/n, 46022 Valencia (Spain); Rodriguez, P. [Biological Dosimetry Service, Unit of Anthropology, Department of Animal and Vegetable Biology and Ecology, Universitat Autonoma de Barcelona (UAB) (Spain); Barrios, L.L. [Department of Physiology and Cellular Biology, Unit of Cellular Biology (UAB) (Spain); Villaescusa, J.I. [Radiation Protection Service, Hospital Universitario La Fe Valencia (Spain)

    2010-08-15

    Interventional radiologists and staff members are frequently exposed to protracted and fractionated low doses of ionizing radiation, which extend during all their professional activities. These exposures can derive, due to the effects of direct and scattered radiation, in deterministic effects (radiodermitis, aged skin, cataracts, telangiectasia in nasal region, vasocellular epitelioms, hands depilation) and/or stochastic ones (cancer incidence). A methodology has been proposed for estimating the radiation risk or detriment from a group of six exposed interventional radiologists of the Hospital Universitario La Fe (Valencia, Spain), which had developed general exposition symptoms attributable to deterministic effects of ionizing radiation. Equivalent doses have been periodically registered using TLD's and wrist dosimeters, H{sub p}(10) and H{sub p}(0.07), respectively, and estimated through the observation of translocations in lymphocytes of peripheral blood (biological methods), by extrapolating the yield of translocations to their respective dose-effect curves. The software RADRISK has been applied for estimating radiation risks in these occupational radiation exposures. This software is based on transport models from epidemiological studies of population exposed to external sources of ionizing radiation, such as Hiroshima and Nagasaki atomic bomb survivors [UNSCEAR, Sources and effects of ionizing radiation: 2006 report to the general assembly, with scientific annexes. New York: United Nations; 2006]. The minimum and maximum average excess ratio for skin cancer has been, using wrist physical doses, of [1.03x10{sup -3}, 5.06x10{sup -2}], concluding that there is not an increased risk of skin cancer incidence. The minimum and maximum average excess ratio for leukemia has been, using TLD physical doses, of [7.84x10{sup -2}, 3.36x10{sup -1}], and using biological doses, of [1.40x10{sup -1}, 1.51], which is considerably higher than incidence rates, showing an

  8. Radiochromic film containing methyl viologen for radiation dosimetry

    DEFF Research Database (Denmark)

    Lavalle, M.; Corda, U.; Fuochi, P.G.

    2007-01-01

    Poly(vinyl alcohol) (PVA) films containing methyl viologen (MV2+) that colours blue upon exposure to ionizing radiation were investigated as possible dosimeters for use in radiation processing applications. In order to find the most suitable composition of the PVA-MV2+ film, different......, humidity and temperature on the response of the PVA-MV2+ dosimeter film have been studied under laboratory conditions. We conclude that the PVA film containing MV2+ is a promising tool for the absorbed dose measurements in several industrial applications of ionizing radiations. (C) 2007 Elsevier Ltd. All...

  9. TH-A-204-01: Part I - Key Data for Ionizing-Radiation Dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Seltzer, S. [National Institute of Standards & Technology (United States)

    2016-06-15

    The ICRU is currently finalizing a report on key data for radiation dosimetry. This multi-year review has resulted in a number of recommendations regarding “fundamental” data that are used in dosimetry related to radiation therapy. This educational session will explain the background for the ICRU committee’s work, the content and conclusions of the report and the impact on outputs, including NIST primary standards, ADCL calibration coefficients and clinical reference dosimetry. Parameters and beam modalities potentially affected by this report include: The mean excitation energy, I, for graphite, air, and water, The average energy required to create an ion pair in dry air (commonly referred to as W/e), The uncertainty in the determination of air kerma in kV x-rays The absolute value of Co-60 and Cs-137 primary standards and the dissemination of calibration coefficients, The determination of air kerma strength for Ir-192 HDR brachytherapy sources Ion chamber kQ factors for linac MV beams Ion chamber kQ factors for proton beams. The changes in reference dosimetry that would result from adoption of the ICRU recommendations are of the order of 0.5% to 1%, an effect that will not impact clinical dose delivery but will be detectable in the clinical setting. This session will also outline how worldwide metrology is coordinated through the Convention of the Meter and therefore how the international dosimetry community will proceed with adopting these recommendations so that uniformity from country to country in reference dosimetry is maintained. Timelines and communications methods will also be discussed to ensure that users, such as clinical medical physicists, are not surprised when their chamber’s calibration coefficient apparently changes. Learning Objectives: Understand the background for the ICRU committee’s work on key dosimetry data. Understand the proposed changes to key data and the impacts on reference dosimetry. Understand the methodology and timeline

  10. Biological dosimetry of X-rays by micronuclei study

    International Nuclear Information System (INIS)

    Gomez, E.; Silva, A.; Navlet, J.

    1991-01-01

    Biological dosimetry consists of estimating absorbed doses for people exposed to radiation by mean biological methods. Several indicators used are based in hematological, biochemical an cytogenetics data, although nowadays without doubt, the cytogenetic method is considered to be the most reliable, in this case, the study of micronuclei in peripheral blood lymphocytes cytokinetic blocked can be related to absorbed dose through an experimental calibration curve. An experimental dose-response curve, using micronuclei assay for X-rays at 250 kVp, 43,79 rads/min and temperature 37 degree celsius has been produced. Experimental data is fitted to model Y=c+ α D+β D 2 where. Y is the number micronuclei per cell and D the dose. the curve is compared with those produced elsewhere

  11. Biological Dosimetry of X-rays by micronuclei study

    International Nuclear Information System (INIS)

    Gomez, E.; Silva, A.; Navlet, J.

    1991-01-01

    Biological dosimetry consists of estimating absorbed doses for people exposed to radiation by mean biological methods. Several indicators used are based in haematological, biochemical an cytogenetics data, although nowadays without doubt, the cytogenetic method is considered to be the most reliable, in this case, the study of micronuclei in peripheral blood lymphocytes citokinetics blocked can be related to absorbed dose through an experimental calibration curve. An experimental dose-response curve, using micronuclei assay for X-rays at 250 kVp, 43,79 rads/min and temperature 37 degree centigree has been produced. Experimental data is fitted to model Y=C+ αD+BD''2 where Y is the number of micronuclei per cell and D the dose. The curve is compared with those produced elsewhere. (Author) 24 refs

  12. 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)

  13. 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)

  14. The role of the IAEA Dosimetry Laboratory in the dissemination of standards for radiation protection

    International Nuclear Information System (INIS)

    Czap, L.; Andreo, P.; Matscheko, G.

    1998-01-01

    Approximately 90% of the Secondary Standard Dosimetry Laboratories (SSDLs) provide users with calibrations of radiation protection instruments, and the IAEA is taking every necessary effort to insure that SSDLs measurements are traceable to Primary Standards. The Agency has proper radiation sources available to provide traceable calibrations to the SSDLs involved in measurements on diagnostic x-ray generators, including an x-ray unit specifically for mammography dedicated to standardization procedures. The different photon beam qualities and calibration procedures available in the Agency's Dosimetry Laboratory are described

  15. New ways for the coordination of research for the dosimetry of ionizing radiation

    International Nuclear Information System (INIS)

    Schuhmacher, Helmut

    2009-01-01

    The European Radiation Dosimetry Group (EURADOS) is a network of about 50 institutions from nearly oil European countries which coordinates research and development for the dosimetry of ionizing radiation. EURADOS was supported over many years by the European Communities. Since 2008 EURADOS is registered as a non-profit society (eingetragener Verein, e.V.) in Braunschweig with the office at the Physikalisch-Technische Bundesanstalt (PTB). This new formal status and the related independence from European research programmes allows new ways in the coordination of research. (orig.)

  16. 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)

  17. Biodistribution and radiation dosimetry of the α7 nicotinic acetylcholine receptor ligand [11C]CHIBA-1001 in humans

    International Nuclear Information System (INIS)

    Sakata, Muneyuki; Wu, Jin; Toyohara, Jun; Oda, Keiichi; Ishikawa, Masatomo; Ishii, Kenji; Hashimoto, Kenji; Ishiwata, Kiichi

    2011-01-01

    Introduction: 4-[ 11 C]Methylphenyl 2,4-diazabicyclo[3.2.2]nonane-2-carboxylate ([ 11 C]CHIBA-1001) is a newly developed positron emission tomography (PET) ligand for mapping α 7 nicotinic acetylcholine receptors. We investigated whole-body biodistribution and radiation dosimetry of [ 11 C]CHIBA-1001 in humans and compared the results with those obtained in mice. Methods: Dynamic whole-body PET was carried out for three human subjects after administering a bolus injection of [ 11 C]CHIBA-1001. Emission scans were collected in two-dimensional mode over five bed positions. Regions of interest were placed over 12 organs. Radiation dosimetry was estimated from the residence times of these source organs using the OLINDA program. Biodistribution data from mice were also used for the prediction of radiation dosimetry in humans, and results with and those without accommodation of different proportions of organ-to-total-body mass were compared with the results from the human PET study. Results: In humans, the highest accumulation was observed in the liver, whereas in mice, the highest accumulation was observed in the urinary bladder. The estimated effective dose from the human PET study was 6.9 μSv/MBq, and that from mice was much underestimated. Conclusion: Effective dose estimates for [ 11 C]CHIBA-1001 were compatible with those associated with other common nuclear medicine tests. Absorption doses among several organs were considerably different between the human and mouse studies. Human dosimetry studies for the investigation of radiation safety are desirable as one of the first clinical trials of new PET probes before their application in subsequent clinical investigations.

  18. Characterization and evaluation studies on some JAERI dosimetry systems

    International Nuclear Information System (INIS)

    Kojima, T.; Sunaga, H.; Tachibana, H.; Takizawa, H.; Tanaka, R.

    2000-01-01

    Characterization and evaluation studies were carried out on some JAERI dosimetry systems, mainly alanine-ESR, in terms of the influence on the dose response of parameters such as orientation at ESR analysis, and the temperature during irradiation and analysis. Feasibility study for application of these dosimetry systems to electrons with energies lower than 4 MeV and bremsstrahlung (X rays) was also performed parallel to their reliability check through international dose intercomparison. (author)

  19. Precision dosimetry system suited for low temperature radiation damage experiments

    DEFF Research Database (Denmark)

    Andersen, H.H.; Hanke, C.C.; Sørensen, H.

    1967-01-01

    A calorimetric system for dosimetry on a beam of charged particles is described. The calorimeter works at liquid helium temperature. The total dose may be measured with an accuracy of 0.3%, and the dose per area with 0.4%. No theoretical corrections are needed. © 1967 The American Institute...

  20. Characterization of chemical compounds for dosimetry of the radiation in industrial processes

    International Nuclear Information System (INIS)

    Galante, Ana Maria Sisti

    1999-01-01

    Different chemical compounds have been studied to optimize dosimetric systems in irradiation processes. In this study 2,3,5 Triphenyl -2H- Tetrazolium Chloride, Brilliant Cresyl Blue, Bromocresol Green and Potassium Nitrate were investigated for their merits or faults, for 60 Co gamma field, in order to verify if can be considered as dosimeters. Fricke solution was used as reference dosimeter to determine absorption dose rates at the gamma facilities.Only Bromocresol Green and Potassium Nitrate are recommended for dosimetry purposes since the main characteristics were achieved. The other two compounds could be used in dosimetry with changes in their formulation. Bromocresol Green and potassium Nitrate are reproducible and radiation sensitive for absorbed doses from 300 Gy to 150 kGy Bromocresol Green was used in liquid form and Potassium Nitrate was prepared in solid pellets form. Spectrophotometry in the visible region was used as the main detection technique, which allows relating optical absorption, before and after irradiation, with the absorbed dose. The maximum absorption wavelength for each compound was observed at 450-460nm for bromocresol Green and 546nm for Potassium Nitrate. Dose calibration curves are linear for both compounds in all dose intervals. When irradiated with accelerated electrons, with energies between o,9 MeV and 1,5MeV, optical absorption intensification, of about 2,6 times, was observed when comparing results for Potassium Nitrate, with those for gamma rays. All the evaluations are presented in this work. (author)

  1. 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)

  2. Fourth conference on radiation protection and dosimetry: Proceedings, program, and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    Casson, W.H.; Thein, C.M.; Bogard, J.S. [eds.

    1994-10-01

    This Conference is the fourth in a series of conferences organized by staff members of Oak Ridge National Laboratory in an effort to improve communication in the field of radiation protection and dosimetry. Scientists, regulators, managers, professionals, technologists, and vendors from the United States and countries around the world have taken advantage of this opportunity to meet with their contemporaries and peers in order to exchange information and ideas. The program includes over 100 papers in 9 sessions, plus an additional session for works in progress. Papers are presented in external dosimetry, internal dosimetry, radiation protection programs and assessments, developments in instrumentation and materials, environmental and medical applications, and on topics related to standards, accreditation, and calibration. Individual papers are indexed separately on EDB.

  3. 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

  4. Statistical issues in biological radiation dosimetry for risk assessment using stable chromosome aberrations

    International Nuclear Information System (INIS)

    Cologne, J.B.; Preston, D.L.

    1998-01-01

    Biological dosimeters are useful for epidemiologic risk assessment in populations exposed to catastrophic nuclear events and as a means of validating physical dosimetry in radiation workers. Application requires knowledge of the magnitude of uncertainty in the biological dose estimates and an understanding of potential statistical pitfalls arising from their use. This paper describes the statistical aspects of biological dosimetry in general and presents a detailed analysis in the specific case of dosimetry for risk assessment using stable chromosome aberration frequency. Biological dose estimates may be obtained from a dose-response curve, but negative estimates can result and adjustment must be made for regression bias due to imprecise estimation when the estimates are used in regression analyses. Posterior-mean estimates, derived as the mean of the distribution of true doses compatible with a given value of the biological endpoint, have several desirable properties: they are nonnegative, less sensitive to extreme skewness in the true dose distribution, and implicitly adjusted to avoid regression bias. The methods necessitate approximating the true-dose distribution in the population in which biological dosimetry is being applied, which calls for careful consideration of this distribution through other information. An important question addressed here is to what extent the methods are robust to misspecification of this distribution, because in many applications of biological dosimetry it cannot be characterized well. The findings suggest that dosimetry based solely on stable chromosome aberration frequency may be useful for population-based risk assessment

  5. Dosimetry in support of wholesomeness studies

    International Nuclear Information System (INIS)

    Jarrett, R.D.; Halliday, J.W.

    1979-01-01

    Interest in dosimetry procedures in the context of a large-scale processing situation exceeds the purely documentary aspects of this report. The numerous combinations afforded by the various types, strengths and configurations of irradiation sources and the possibilities for various conveyors and other facility design factors impacting on irradiation logistics render a completely general treatment of dosimetry procedures in such instances almost impossible. While the exact combination of these various factors represented by the irradiation facilities at NARADCOM may be duplicated nowhere else, the dosimetry procedures documented in this report offer both experience and solutions that might be more generally useful. Therefore, this report complements and supplements more general discussions found in the literature and cited in the text

  6. Whole body [{sup 11}C]-dihydrotetrabenazine imaging of baboons: biodistribution and human radiation dosimetry estimates

    Energy Technology Data Exchange (ETDEWEB)

    Murthy, Rajan [Columbia University College of Physicians and Surgeons, Department of Psychiatry, New York, NY (United States); New York State Psychiatric Institute, Department of Neuroscience, Division of Brain Imaging, New York, NY (United States); Harris, Paul; Leibel, Rudolph [Columbia University College of Physicians and Surgeons, Department of Medicine, New York, NY (United States); Simpson, Norman; Parsey, Ramin [Columbia University College of Physicians and Surgeons, Department of Psychiatry, New York, NY (United States); Van Heertum, Ronald [Columbia University College of Physicians and Surgeons, Department of Radiology, New York, NY (United States); New York State Psychiatric Institute, Department of Neuroscience, Division of Brain Imaging, New York, NY (United States); Mann, J.J. [Columbia University College of Physicians and Surgeons, Department of Psychiatry, New York, NY (United States); Columbia University College of Physicians and Surgeons, Department of Radiology, New York, NY (United States); New York State Psychiatric Institute, Department of Neuroscience, Division of Brain Imaging, New York, NY (United States)

    2008-04-15

    Vesicular monoamine transporter type 2 abundance quantified using the radiotracer [{sup 11}C]-dihydrotetrabenazine (DTBZ) has been used to study diagnosis and pathogenesis of dementia and psychiatric disorders in humans. In addition, it may be a surrogate marker for insulin-producing pancreatic beta cell mass, useful for longitudinal measurements using positron emission tomography to track progression of autoimmune diabetes. To support the feasibility of long-term repeated administrations, we estimate the biodistribution and dosimetry of [{sup 11}C]-DTBZ in humans. Five baboon studies were acquired using a Siemens ECAT camera. After transmission scanning, 165-210 MBq of [{sup 11}C]-DTBZ were injected, and dynamic whole body emission scans were conducted. Time-activity data were used to obtain residence times and estimate absorbed radiation dose according to the MIRD model. Most of the injected tracer localized to the liver and the lungs, followed by the intestines, brain, and kidneys. The highest estimated absorbed radiation dose was in the stomach wall. The largest radiation dose from [{sup 11}C]-DTBZ is to the stomach wall. This dose estimate, as well as the radiation dose to other radiosensitive organs, must be considered in evaluating the risks of multiple administrations. (orig.)

  7. 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

  8. 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

  9. Preclinical pharmacokinetics, biodistribution, radiation dosimetry and acute toxicity studies required for regulatory approval of a Clinical Trial Application for a Phase I/II clinical trial of 111In-BzDTPA-pertuzumab

    International Nuclear Information System (INIS)

    Lam, Karen; Chan, Conrad; Done, Susan J.; Levine, Mark N.; Reilly, Raymond M.

    2015-01-01

    Introduction: 111 In-BzDTPA-pertuzumab is a novel imaging probe for detecting changes in HER2 expression in breast cancer (BC) caused by treatment with trastuzumab (Herceptin). Our aim was to evaluate the pharmacokinetics, normal tissue biodistribution, radiation dosimetry and acute toxicity of 111 In-BzDTPA-pertuzumab in non-tumor bearing mice in order to obtain regulatory approval to advance this agent to a first-in-humans Phase I/II clinical trial. Methods: Biodistribution and pharmacokinetic studies were performed in non-tumor bearing Balb/c mice injected i.v. with 111 In-BzDTPA-pertuzumab (2.5 MBq; 2 μg). The cumulative number of disintegrations per source organ derived from the biodistribution data was used to predict the radiation absorbed doses in humans using OLINDA/EXM software. Acute toxicity was studied at two weeks post-injection of 111 In-BzDTPA-pertuzumab (1.0 MBq, 20 μg) with comparison to control mice injected with unlabeled BzDTPA-pertuzumab (20 μg) or Sodium Chloride Injection USP. The dose of 111 In-BzDTPA-pertuzumab corresponded to 23-times the human radioactivity dose and 10-times the protein dose on a MBq/kg and mg/kg basis, respectively. Toxicity was assessed by monitoring body mass, complete blood cell count (CBC), hematocrit (Hct), hemoglobin (Hb), serum creatinine (SCr) and alanine aminotransferease (ALT) and by histopathological examination of tissues at necropsy. Results: 111 In-BzDTPA-pertuzumab exhibited a biphasic elimination from the blood with a distribution half-life (t 1/2 α) of 3.8 h and an elimination half-life (t 1/2 β) of 228.2 h. The radiopharmaceutical was distributed mainly in the blood, heart, lungs, liver, kidneys and spleen. The projected whole-body radiation absorbed dose in humans was 0.05 mSv/MBq corresponding to a total of 16.8 mSv for three separate administrations of 111 In-BzDTPA-pertuzumab (111 MBq) planned for the Phase I/II trial. There were slight changes in Hb and SCr levels associated with

  10. Henri Jammet Memorial lecture: The role of dosimetry in radiation accident response

    International Nuclear Information System (INIS)

    Ricks, Robert C.; Joiner, Eugene; Toohey, Richard E.; Holloway, Elizabeth C.

    1997-01-01

    This document presents a lecture given on the role of dosimetry in radiation accident response, focusing accidents such as: Vinca, occurred on october 15, 1958, Goiania Cs-137, Hanford Am-241 and Juarez Co-60, Chernobyl nuclear power plant. Other accidents are reported as they are registered in the REAC/TS Registry

  11. Guidelines for the Calibration of Routine Dosimetry Systems for use in Radiation Processing

    DEFF Research Database (Denmark)

    Sharpe, Peter; Miller, Arne

    A set of guidelines has been developed to assist in the calibration of routine dosimetry systems for use in industrial radiation processing plants. Topics covered include the calibration of equipment, the performance of calibration irradiations and the derivation of mathematical functions...

  12. In-situ radiation dosimetry based on Radio-Fluorogenic Co-Polymerization

    NARCIS (Netherlands)

    Warman, J.M.; Luthjens, L.H.; De Haas, M.P.

    2009-01-01

    A fluorimetric method of radiation dosimetry is presented for which the intensity of the fluorescence of a (tissue equivalent) medium is linearly dependent on accumulated dose from a few Gray up to kiloGrays. The method is based on radio-fluorogenic co-polymerization (RFCP) in which a normally very

  13. Implementation of a post graduated course in radiation protection and dosimetry

    International Nuclear Information System (INIS)

    Papa, A.R.R.; Rodrigues, L.N.; Godoy, J.M.O.; Fonseca, E.S. da; Pereira, W.W.; Dantas, B.M.; Goncalves, M. G.

    2001-01-01

    The main motivations and followed lines in the implementation of a postgraduate course in Radiation Protection and Dosimetry are exposed. The principal research areas as well as the academic program are described. A prevision on the future and perspectives of the program is done. (author)

  14. Brazilian Institute for Radiation Protection and Dosimetry (IRD/CNEN-RJ): Report 2000-2010

    International Nuclear Information System (INIS)

    2010-01-01

    This report presents the activities of the Institute for Radiation Protection and Dosimetry of the Brazilian Nuclear Energy Commission from 2000 to 2010 and has eight chapters: 1) history; 2) main designations and attributions; 3) metrology and assays; 4) conformity evaluation; 5) assistance to radiological and nuclear emergencies; 6) capacity and training; 7) infrastructure of information technology and 8) operational indicators

  15. Alanine/ESR dosimetry system for routine use in radiation processing

    International Nuclear Information System (INIS)

    Kojima, T.; Haruyama, Y.; Tachibana, H.; Tanaka, R.; Okamoto, J.; Hara, H.; Kashiwazaki, S.

    1993-01-01

    A new alanine-polystyrene(PS) dosimeter prepared with simplified molding procedure and an automatic desk-top dose-reader of alanine dosimeter were developed for the purpose of routine use. Combination of these two allows us to apply a reliable alanine/ESR dosimetry system to routine dosimetric process control in industrial gamma radiation processing. (Author)

  16. Intercomparison on the usage of computational codes in radiation dosimetry

    International Nuclear Information System (INIS)

    Ilic, R.; Pesic, M.; Pavlovic, R.

    2003-01-01

    SRNA-2KG software package was modified for this work to include necessary input and output data and for predicted voxelized geometry and dosimetry. SRNA is a Monte Carlo code developed for applications in proton transport, radiotherapy and dosimetry. Protons within energy range from 100 keV to 250 MeV with predefined spectra are transported in 3D geometry through material zones confined by planes and second order surfaces or in 3D voxelized geometry. The code can treat proton transport in a few hundred different materials including elements from Z=1 to Z=98. Simulation of proton transport is based on the multiple scattering theory of charged particles and on the model for compound nucleus decay

  17. EPR dosimetry in a mixed neutron and gamma radiation field.

    Science.gov (United States)

    Trompier, F; Fattibene, P; Tikunov, D; Bartolotta, A; Carosi, A; Doca, M C

    2004-01-01

    Suitability of Electron Paramagnetic Resonance (EPR) spectroscopy for criticality dosimetry was evaluated for tooth enamel, mannose and alanine pellets during the 'international intercomparison of criticality dosimetry techniques' at the SILENE reactor held in Valduc in June 2002, France. These three materials were irradiated in neutron and gamma-ray fields of various relative intensities and spectral distributions in order to evaluate their neutron sensitivity. The neutron response was found to be around 10% for tooth enamel, 45% for mannose and between 40 and 90% for alanine pellets according their type. According to the IAEA recommendations on the early estimate of criticality accident absorbed dose, analyzed results show the EPR potentiality and complementarity with regular criticality techniques.

  18. Fabrication and optimization of a fiber-optic radiation sensor for proton beam dosimetry

    International Nuclear Information System (INIS)

    Jang, K.W.; Yoo, W.J.; Seo, J.K.; Heo, J.Y.; Moon, J.; Park, J.-Y.; Hwang, E.J.; Shin, D.; Park, S.-Y.; Cho, H.-S.; Lee, B.

    2011-01-01

    In this study, we fabricated a fiber-optic radiation sensor for proton therapy dosimetry and measured the output and the peak-to-plateau ratio of scintillation light with various kinds of organic scintillators in order to select an organic scintillator appropriate for measuring the dose of a proton beam. For the optimization of an organic scintillator, the linearity between the light output and the stopping power of a proton beam was evaluated for two different diameters of the scintillator, and the angular dependency and standard deviation of the light pulses were investigated for four different scintillator lengths. We also evaluated the linearity between the light output and the dose rate and monitor units of a proton generator, respectively. The relative depth-dose curve of the proton beam was obtained and corrected using Birk's theory.

  19. Thermoluminescence of metal oxides and its applications to the dosimetry of low energy ionizing radiation

    International Nuclear Information System (INIS)

    Azorin N, J.; Rivera M, T.; Falcony G, C.; Martinez S, E.; Garcia H, M.

    1999-01-01

    There are presented the results obtained since 1997 at present in the project Study of the thermoluminescence of metal oxides and its applications to the dosimetry of ionizing radiation. Its have been developed ZrO 2 films without doping and doped with Eu, Tb, and Mn as well as Al 2 O 3 films without doping and doped with Na. The results obtained to the irradiated films of ZrO 2 with ultraviolet and visible lights have been satisfactory. The Al 2 O 3 in film form showed to be a promising material for the measuring ultraviolet light and the pellets of ZrO 2 + Ptfe for X-rays and low energy gamma rays. (Author)

  20. Polycarbonate-based benzo-δ-sultam films for high-dose dosimetry in radiation processing

    International Nuclear Information System (INIS)

    Feizi, Shazad; Nuclear Science and Technology Research Institute, Tehran; Ziaie, Farhood; Ghandi, Mehdi

    2015-01-01

    In this work characteristics of the polycarbonate films with 20 μm in thickness containing different weight percentage of Benzo-δ-sultam were studied for use as a high dose dosimetry system in radiation processing facilities. The sensitivity of the dosimeters and the linearity of dose-response curves were investigated under 60 Co γ-rays in a dose range of 0-100 kGy, and obtained results were compared with the commercial CTA and FWT film dosimeters. The results show that the absorbance at 348 nm depends linearly on the dose in the investigated dose range. The effects of pre-irradiation (shelf-life) and post-irradiation storage in dark and in indirect sunlight are also discussed. The results show that the dosimeters characteristics are stable within 1% at 25 C, 3 months after the irradiation.

  1. Polycarbonate-based benzo-δ-sultam films for high-dose dosimetry in radiation processing

    Energy Technology Data Exchange (ETDEWEB)

    Feizi, Shazad [University of Tehran, Tehran (India). School of Chemistry; Nuclear Science and Technology Research Institute, Tehran (Iran, Islamic Republic of). Radiation Application Research School; Ziaie, Farhood [Nuclear Science and Technology Research Institute, Tehran (Iran, Islamic Republic of). Radiation Application Research School; Ghandi, Mehdi [University of Tehran, Tehran (India). School of Chemistry

    2015-05-01

    In this work characteristics of the polycarbonate films with 20 μm in thickness containing different weight percentage of Benzo-δ-sultam were studied for use as a high dose dosimetry system in radiation processing facilities. The sensitivity of the dosimeters and the linearity of dose-response curves were investigated under {sup 60}Co γ-rays in a dose range of 0-100 kGy, and obtained results were compared with the commercial CTA and FWT film dosimeters. The results show that the absorbance at 348 nm depends linearly on the dose in the investigated dose range. The effects of pre-irradiation (shelf-life) and post-irradiation storage in dark and in indirect sunlight are also discussed. The results show that the dosimeters characteristics are stable within 1% at 25 C, 3 months after the irradiation.

  2. Analysis of transient and thermostatic behavior of water calorimeter for radiation dosimetry

    International Nuclear Information System (INIS)

    Kang, M. Y.; Kim, J. H.; Kim, Jinhyeong; Choi, H. D.; Kim, I. J.

    2015-01-01

    In order to maintain the therapeutic accuracy recommended by the WHO, the American Medical Physics Association has published research results that uncertainty of absorbed dose measurement should be given to less than 3% and many countries are developing the absorbed dose evaluation technique using a calorimeter. Therefore development of water calorimeter and standard measurement method of absorbed dose through the evaluation and ongoing measurement is required in Korea. As an initial step in the development of the water calorimeter by domestic technology, we designed geometry of the phantom and carried out the simulation of the thermal behavior according to the radiation transport and energy deposition by 145TBq KRISS 60 Co beam. The results of this study will be used as the basic data for development of the standard water calorimeter in Korea Research Institute of Standards and Science. Through a parallel development and comparison with the graphite calorimeter, this result is expected to be utilized to improve the standard dosimetry

  3. Experimental study and Monte Carlo modeling of operational quantities in metrology of ionizing radiation: application to neutrons dosimetry by radio-photoluminescence

    International Nuclear Information System (INIS)

    Salem, Youbba-Ould

    2014-01-01

    We characterize a passive dosimeter capable of measuring both fast and thermal neutrons for ambient and personal dosimetry. These neutrons can be detected in a mixed neutron-gamma field with appropriate converters (polyethylene for fast neutrons, cadmium for thermal neutrons). Monte Carlo simulations with MCNPX helped with the geometrical conception of the dosimeter and the choice of materials. The responses of the RPL dosimeter to these neutrons are linear in H * (10) and H p (10) with detection limits of 2 mSv for fast neutrons and 0.19 mSv for thermal neutrons. The angular dependencies are satisfactory according to the ISO 21909 norm. A calibration factor of (9.5 ± 0.5)*10 -2 mSv.cm 2 /RPL signal is obtained to the fast neutrons of the IPHC's 241 Am-Be calibrator. This factor is (9.7 ± 0.3)*10 -3 mSv.cm 2 /RPL signal for the thermalized neutrons. (author)

  4. Development of a three-dimensional radiation dosimetry system

    International Nuclear Information System (INIS)

    Bero, M.A.

    2001-12-01

    The direct non-destructive measurement of the radiation absorbed dose in three dimensions is considered to be technically difficult. Accurate determination of the spatial distribution of absorbed dose plays an important role in many applications particularly in medicine. In radiotherapy computer calculations are frequently used to estimate three-dimensional dose distributions in complex geometry, hence a practical dosimetry system able to provide three-dimensional (3-D) integrated measurements is highly desirable for verifying such dose predictions. Magnetic Resonance Imaging (MRI) has been used to visualise 3-D dose distributions, inside two different detector materials, namely the ferrous sulphate gel (Fricke gel) and the polymer gel system. Each of these procedures has its own drawbacks and limitations, and this research project sought to find improvements and alternatives to overcome these problems. Work on the Fricke gel led to an improved preparation procedure employing gelatin gel whose lower melting point reduces the possibility of dissolved oxygen loss. The role of each component was clarified which led to the omission of all unnecessary chemicals such as the sodium chloride and benzoic acid. Initially MRI was the only 3-D readout technique available, however simple relaxometry was used to characterise the detector quantitatively with each modification before employing an MRI scanner to obtain images. Optimisation of the active constituents saves time and effort, and minimises the cost of equipment as well as materials. A serious drawback of the Fricke gel is ion diffusion, which causes blurring of the recorded spatial distribution and much effort was given to attempts to reduce this. However it was concluded that it is possible to slow down ion diffusion but at the cost of detector sensitivity. Therefore the best way of dealing with this problem is by introducing a fast readout technique so that the dose distribution can be recorded before serious

  5. Electron spin resonance (ESR) spectroscopy applied to radiation dosimetry and other fields

    International Nuclear Information System (INIS)

    Schneider, C.C.J.

    1994-12-01

    A short introduction to the theory and practice of ESR spectroscopy is given. ESR alanine dosimetry for low and high LET (linear energy transfer) ionising radiation is described, indicating its advantages over traditional methods. Problems arising in the therapy dose range (below 5 Gy), and possible future developments, are mentioned. The application of ESR to the radiation processing of materials and foodstuffs, to geological dating, biology, molecular chemistry and to medicine is discussed. Some examples of chemical analyses are also presented. (orig.)

  6. Dosimetric characterization of two radium sources for retrospective dosimetry studies

    Energy Technology Data Exchange (ETDEWEB)

    Candela-Juan, C., E-mail: ccanjuan@gmail.com [Radiation Oncology Department, La Fe University and Polytechnic Hospital, Valencia 46026, Spain and Department of Atomic, Molecular and Nuclear Physics, University of Valencia, Burjassot 46100 (Spain); Karlsson, M. [Division of Radiological Sciences, Department of Medical and Health Sciences, Linköping University, Linköping SE 581 85 (Sweden); Lundell, M. [Department of Medical Physics and Oncology, Karolinska University Hospital and Karolinska Institute, Stockholm SE 171 76 (Sweden); Ballester, F. [Department of Atomic, Molecular and Nuclear Physics, University of Valencia, Burjassot 46100 (Spain); Tedgren, Å. Carlsson [Division of Radiological Sciences, Department of Medical and Health Sciences, Linköping University, Linköping SE 581 85, Sweden and Swedish Radiation Safety Authority, Stockholm SE 171 16 (Sweden)

    2015-05-15

    Purpose: During the first part of the 20th century, {sup 226}Ra was the most used radionuclide for brachytherapy. Retrospective accurate dosimetry, coupled with patient follow up, is important for advancing knowledge on long-term radiation effects. The purpose of this work was to dosimetrically characterize two {sup 226}Ra sources, commonly used in Sweden during the first half of the 20th century, for retrospective dose–effect studies. Methods: An 8 mg {sup 226}Ra tube and a 10 mg {sup 226}Ra needle, used at Radiumhemmet (Karolinska University Hospital, Stockholm, Sweden), from 1925 to the 1960s, were modeled in two independent Monte Carlo (MC) radiation transport codes: GEANT4 and MCNP5. Absorbed dose and collision kerma around the two sources were obtained, from which the TG-43 parameters were derived for the secular equilibrium state. Furthermore, results from this dosimetric formalism were compared with results from a MC simulation with a superficial mould constituted by five needles inside a glass casing, placed over a water phantom, trying to mimic a typical clinical setup. Calculated absorbed doses using the TG-43 formalism were also compared with previously reported measurements and calculations based on the Sievert integral. Finally, the dose rate at large distances from a {sup 226}Ra point-like-source placed in the center of 1 m radius water sphere was calculated with GEANT4. Results: TG-43 parameters [including g{sub L}(r), F(r, θ), Λ, and s{sub K}] have been uploaded in spreadsheets as additional material, and the fitting parameters of a mathematical curve that provides the dose rate between 10 and 60 cm from the source have been provided. Results from TG-43 formalism are consistent within the treatment volume with those of a MC simulation of a typical clinical scenario. Comparisons with reported measurements made with thermoluminescent dosimeters show differences up to 13% along the transverse axis of the radium needle. It has been estimated that

  7. The UF family of hybrid phantoms of the developing human fetus for computational radiation dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Maynard, Matthew R; Geyer, John W; Bolch, Wesley [Department of Nuclear and Radiological Engineering, University of Florida, Gainesville, FL (United States); Aris, John P [Department of Anatomy and Cell Biology, University of Florida, Gainesville, FL (United States); Shifrin, Roger Y, E-mail: wbolch@ufl.edu [Department of Radiology, University of Florida, Gainesville, FL (United States)

    2011-08-07

    Historically, the development of computational phantoms for radiation dosimetry has primarily been directed at capturing and representing adult and pediatric anatomy, with less emphasis devoted to models of the human fetus. As concern grows over possible radiation-induced cancers from medical and non-medical exposures of the pregnant female, the need to better quantify fetal radiation doses, particularly at the organ-level, also increases. Studies such as the European Union's SOLO (Epidemiological Studies of Exposed Southern Urals Populations) hope to improve our understanding of cancer risks following chronic in utero radiation exposure. For projects such as SOLO, currently available fetal anatomic models do not provide sufficient anatomical detail for organ-level dose assessment. To address this need, two fetal hybrid computational phantoms were constructed using high-quality magnetic resonance imaging and computed tomography image sets obtained for two well-preserved fetal specimens aged 11.5 and 21 weeks post-conception. Individual soft tissue organs, bone sites and outer body contours were segmented from these images using 3D-DOCTOR(TM) and then imported to the 3D modeling software package Rhinoceros(TM) for further modeling and conversion of soft tissue organs, certain bone sites and outer body contours to deformable non-uniform rational B-spline surfaces. The two specimen-specific phantoms, along with a modified version of the 38 week UF hybrid newborn phantom, comprised a set of base phantoms from which a series of hybrid computational phantoms was derived for fetal ages 8, 10, 15, 20, 25, 30, 35 and 38 weeks post-conception. The methodology used to construct the series of phantoms accounted for the following age-dependent parameters: (1) variations in skeletal size and proportion, (2) bone-dependent variations in relative levels of bone growth, (3) variations in individual organ masses and total fetal masses and (4) statistical percentile variations

  8. The UF family of hybrid phantoms of the developing human fetus for computational radiation dosimetry

    International Nuclear Information System (INIS)

    Maynard, Matthew R; Geyer, John W; Bolch, Wesley; Aris, John P; Shifrin, Roger Y

    2011-01-01

    Historically, the development of computational phantoms for radiation dosimetry has primarily been directed at capturing and representing adult and pediatric anatomy, with less emphasis devoted to models of the human fetus. As concern grows over possible radiation-induced cancers from medical and non-medical exposures of the pregnant female, the need to better quantify fetal radiation doses, particularly at the organ-level, also increases. Studies such as the European Union's SOLO (Epidemiological Studies of Exposed Southern Urals Populations) hope to improve our understanding of cancer risks following chronic in utero radiation exposure. For projects such as SOLO, currently available fetal anatomic models do not provide sufficient anatomical detail for organ-level dose assessment. To address this need, two fetal hybrid computational phantoms were constructed using high-quality magnetic resonance imaging and computed tomography image sets obtained for two well-preserved fetal specimens aged 11.5 and 21 weeks post-conception. Individual soft tissue organs, bone sites and outer body contours were segmented from these images using 3D-DOCTOR(TM) and then imported to the 3D modeling software package Rhinoceros(TM) for further modeling and conversion of soft tissue organs, certain bone sites and outer body contours to deformable non-uniform rational B-spline surfaces. The two specimen-specific phantoms, along with a modified version of the 38 week UF hybrid newborn phantom, comprised a set of base phantoms from which a series of hybrid computational phantoms was derived for fetal ages 8, 10, 15, 20, 25, 30, 35 and 38 weeks post-conception. The methodology used to construct the series of phantoms accounted for the following age-dependent parameters: (1) variations in skeletal size and proportion, (2) bone-dependent variations in relative levels of bone growth, (3) variations in individual organ masses and total fetal masses and (4) statistical percentile variations in

  9. 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.)

  10. Regulatory requirements for radiopharmaceutical radiochemistry and radiation dosimetry

    International Nuclear Information System (INIS)

    Bonnyman, J.

    1985-01-01

    The Australian Department of Health is responsible for ensuring that radiopharmaceuticals are safe and effective and that their use does not result in unnecessary radiation exposure. Section B1 requirements of New Drug Form 4 (NDF4) fall into the following sections - manufacture, product specifications, quality assurance testing, stability studies and expiry dating. It covers ready to inject pharmaceuticals, radioactive formulations used to prepare a radiopharmaceutical, generators and cold kits

  11. PREFACE: 7th International Conference on 3D Radiation Dosimetry (IC3DDose)

    Science.gov (United States)

    Thwaites, David; Baldock, Clive

    2013-06-01

    IC3DDose 2013, the 7th International Conference on 3D Radiation Dosimetry held in Sydney, Australia from 4-8 November 2012, grew out of the DosGel series, which began as DosGel99, the 1st International Workshop on Radiation Therapy Gel Dosimetry in Lexington, Kentucky. Since 1999 subsequent DoSGel conferences were held in Brisbane, Australia (2001), Ghent, Belgium (2004), Sherbrooke, Canada (2006) and Crete, Greece (2008). In 2010 the conference was held on Hilton Head Island, South Carolina and underwent a name-change to IC3DDose. The aim of the first workshop was to bring together individuals, both researchers and users, with an interest in 3D radiation dosimetry techniques, with a mix of presentations from basic science to clinical applications, which has remained an objective for all of the meetings. One rationale of DosGel99 was stated as supporting the increasing clinical implementation of gel dosimetry, as the technique appeared, at that time, to be leaving the laboratories of gel dosimetry enthusiasts and entering clinical practice. Clearly by labelling the first workshop as the 1st, there was a vision of a continuing series, which has been fulfilled. On the other hand, the expectation of widespread clinical use of gel dosimetry has perhaps not been what was hoped for and anticipated. Nevertheless the rapidly increasing demand for advanced high-precision 3D radiotherapy technology and techniques has continued apace. The need for practical and accurate 3D dosimetry methods for development and quality assurance has only increased. By the 6th meeting, held in South Carolina in 2010, the Conference Scientific Committee recognised the wider developments in 3D systems and methods and decided to widen the scope, whilst keeping the same span from basic science to applications. This was signalled by a change of name from 'Dosgel' to 'IC3DDose', a name that has continued to this latest conference. The conference objectives were: to enhance the quality and accuracy of

  12. Measurement and analysis of high energy radiation through activation detectors. Application in dosimetry

    International Nuclear Information System (INIS)

    Sklavenitis, L.

    1967-10-01

    This work is concerned with the possibility of measurement and analysis of radiation fluences within objects of small volume submitted to a high energy proton beam. The first part, consecrated to the establishment of a method of analysis, comprises a detailed study of the radiation nature and energy spectra as well as of the various dosimetry methods. In order to select a group of detectors, high energy nuclear reactions were systematically studied and for some of them cross sections were measured or calculated: for example the cross section of the reaction 11 B (p,n) 11 C between 150 and 3000 MeV and of the reaction 34 S (p,2pn) 32 P between 50 and 3000 MeV. The second part is relative to the application of the fore-mentioned analysis to radiation within a tissue equivalent phantom irradiated by 3 GeV protons. This analysis is sufficiently detailed to allow the reconstitution of the absorbed doses, the dose equivalent and, contingent on a better knowledge of the dose due to heavy particles, the quality factors. It allowed also to follow the evolution of the various dosimetric data as a function of the depth inside the phantom and to verify calculations already done by other researchers. The comparison of the measured doses and the corresponding detector activities revealed the possibility that some detectors could give directly the absorbed dose, or even the dose equivalent, by a simple activity measurement. (author) [fr

  13. Dosimetry methods

    DEFF Research Database (Denmark)

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

    2003-01-01

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

  14. Thermoluminescent dosimetry of new phosphors of Zn O exposed to beta radiation

    International Nuclear Information System (INIS)

    Cruz V, C.; Burruel I, S.E.; Grijalva M, H.; Barboza F, M.; Bernal, R.

    2004-01-01

    In this work, we report the thermoluminescence dosimetry of a new Zn O phosphor obtained by annealing of Zn S powder precipitated when Zn S films were grown by employing a CBD method. The collected Zn S powder was pressed in a die to form pellets which were subjected to different thermal treatments under air atmosphere. X-ray diffraction (XRD) patterns and energy-dispersive X-ray Spectrometry (EDS) analyses confirmed the transformation of Zn S to Zn O. The phosphors thus obtained were exposed to high doses of beta radiation and their thermoluminescent dosimetry show that these new phosphors are materials suitable to be used in high dose thermoluminescence dosimetry. (Author)

  15. Guide for dosimetry in radiation research on food and agricultural products

    International Nuclear Information System (INIS)

    2002-01-01

    This guide covers the minimum requirements for dosimetry and absorbed-dose validation needed to conduct research on the irradiation of food and agricultural products. Such research includes establishment of the quantitative relationship between the absorbed dose and the relevant effects in these products. This guide also describes the overall need for dosimetry in such research, and in reporting of the results. This guide is intended for use by research scientists in the food and agricultural communities, and not just scientists conducting irradiation research. It, therefore, includes more tutorial information than most other ASTM and ISO/ASTM dosimetry standards for radiation processing. This guide is in no way intended to limit the flexibility of the experimenter in the experimental design. However, the radiation source and experimental set up should be chosen such that the results of the experiment will be beneficial and understandable to other scientists, regulatory agencies, and the food and agricultural communities. The effects produced by ionizing radiation in biological systems depend on a large number of factors which may be physical, physiological, or chemical. Although not treated in detail in this guide, quantitative data of environmental factors that may affect the absorbed-dose response of dosimeters, such as temperature and moisture content in the food or agricultural products should be reported. The overall uncertainty in the absorbed-dose measurement and the inherent absorbed-dose range within the specimen should be taken into account in the design of an experiment. The guide covers research conducted using the following types of ionizing radiation: gamma rays, bremsstrahlung X-rays, and electron beams. This guide does not include other aspects of radiation processing research, such as planning of the experimental design. Dosimetry must be considered as an integral part of the experimental design. The guide does not include dosimetry for irradiator

  16. Study for applying microwave power saturation technique on fingernail/EPR dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Park, Byeong Ryong; Choi, Hoon; Nam, Hyun Ill; Lee, Byung Ill [Radiation Health Research Institute, Seoul (Korea, Republic of)

    2012-10-15

    There is growing recognition worldwide of the need to develop effective uses of dosimetry methods to assess unexpected exposure to radiation in the event of a large scale event. One of physically based dosimetry methods electron paramagnetic resonance (EPR) spectroscopy has been applied to perform retrospective radiation dosimetry using extracted samples of tooth enamel and nail(fingernail and toenail), following radiation accidents and exposures resulting from weapon use, testing, and production. Human fingernails are composed largely of a keratin, which consists of {alpha} helical peptide chains that are twisted into a left handed coil and strengthened by disulphide cross links. Ionizing radiation generates free radicals in the keratin matrix, and these radicals are stable over a relatively long period (days to weeks). Most importantly, the number of radicals is proportional to the magnitude of the dose over a wide dose range (0{approx}30 Gy). Also, dose can be estimated at four different locations on the human body, providing information on the homogeneity of the radiation exposure. And The results from EPR nail dosimetry are immediately available However, relatively large background signal (BKS) converted from mechanically induced signal (MIS) after cutting process of fingernail, normally overlaps with the radiation induced signal (RIS), make it difficult to estimate accurate dose accidental exposure. Therefore, estimation method using dose response curve was difficult to ensure reliability below 5 Gy. In this study, In order to overcome these disadvantages, we measured the reactions of RIS and BKS (MIS) according to the change of Microwave power level, and researched about the applicability of the Power saturation technique at low dose.

  17. Review of present beta dosimetry problems in radiation protection; to day's answers and future trends

    International Nuclear Information System (INIS)

    Fracas, P.

    1986-01-01

    The large use of pure beta radionuclides needs to be develop beta dosimetry methods for radiation protection. The different types of present dosimetry assessments are reviewed. In all the cases the quantity to take into account is the absorbed dose rate in human tissus and more particularly in skin. In the case of point sources of known nature and activity this quantity can be worked out. This calculation is achieved either by incident beta spectrum analysis or theoretical considerations based on Kernel point. The absorbed dose rate can also be measured by extrapolation ionization chamber which characteristics and working are detailed here. All present survey meter were not initially planned for such a beta dosimetry, as this performed with the extrapolation ionization chamber which is taken here as a reference. So responses of usual dosimeters compared to this reference need to be estimated. Responses of personal film badges used in CEA, portable ionization chambers as babyline, pocket dosimeters SEQ7 and the thermoluminescent dosimeters TLD700 are exposed here. Results show that all these survey meters are not completely suitable for routine beta dosimetry. Consequently other operational dosimetry techniques have to be pursued. In particular some thermoluminescence dosimeters for instance boron diffused in surface layer and multi-elements, and furthermore Thermally Stimulated Exoelectron Emission (TSEE) and surface barrier detectors are described [fr

  18. Study on biological dosimetry of premature chromosome condensation technique

    International Nuclear Information System (INIS)

    Jiang Bo

    2005-01-01

    The premature chromosome condensation technique has been applied for biological dosimetry purpose. Premature chromo-some condensation was induced by incubating unstimulated human peripheral blood lymphocytes in the presence of okadaic acid or calyculin A (a phosphatase inhibitor) which eliminated the need for fusion with mitotic cells. It is now possible to examine the early damage induced by radiation. It is simple, exact when it combines with fluorecence in situ hybridization. (authors)

  19. Internal radiation dosimetry using nuclear medicine imaging in radionuclide therapy

    International Nuclear Information System (INIS)

    Kim, Kyeong Min; Byun, Byun Hyun; Cheon, Gi Jeong; Lim, Sang Moo

    2007-01-01

    Radionuclide therapy has been an important field in nuclear medicine. In radionuclide therapy, relevant evaluation of internally absorbed dose is essential for the achievement of efficient and sufficient treatment of incurable disease, and can be accomplished by means of accurate measurement of radioactivity in body and its changes with time. Recently, the advances of nuclear medicine imaging and multi modality imaging processing techniques can provide chance of more accurate and easier measurement of the measures commented above, in cooperation of conventional imaging based approaches. In this review, basic concept for internal dosimetry using nuclear medicine imaging is summarized with several check points which should be considered in real practice

  20. The radiation oncology workforce: A focus on medical dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, Gregg F., E-mail: grobinson@medicaldosimetry.org [American Association of Medical Dosimetrists, Herndon, VA (United States); Mobile, Katherine [American Association of Medical Dosimetrists, Herndon, VA (United States); Yu, Yan [Thomas Jefferson University, Philadelphia, PA (United States)

    2014-07-01

    The 2012 Radiation Oncology Workforce survey was conducted to assess the current state of the entire workforce, predict its future needs and concerns, and evaluate quality improvement and safety within the field. This article describes the dosimetrist segment results. The American Society for Radiation Oncology (ASTRO) Workforce Subcommittee, in conjunction with other specialty societies, conducted an online survey targeting all segments of the radiation oncology treatment team. The data from the dosimetrist respondents are presented in this article. Of the 2573 dosimetrists who were surveyed, 890 responded, which resulted in a 35% segment response rate. Most respondents were women (67%), whereas only a third were men (33%). More than half of the medical dosimetrists were older than 45 years (69.2%), whereas the 45 to 54 years age group represented the highest percentage of respondents (37%). Most medical dosimetrists stated that their workload was appropriate (52%), with respondents working a reported average of 41.7 ± 4 hours per week. Overall, 86% of medical dosimetrists indicated that they were satisfied with their career, and 69% were satisfied in their current position. Overall, 61% of respondents felt that there was an oversupply of medical dosimetrists in the field, 14% reported that supply and demand was balanced, and the remaining 25% felt that there was an undersupply. The medical dosimetrists' greatest concerns included documentation/paperwork (78%), uninsured patients (80%), and insufficient reimbursement rates (87%). This survey provided an insight into the dosimetrist perspective of the radiation oncology workforce. Though an overwhelming majority has conveyed satisfaction concerning their career, the study allowed a spotlight to be placed on the profession's current concerns, such as insufficient reimbursement rates and possible oversupply of dosimetrists within the field.

  1. The radiation oncology workforce: A focus on medical dosimetry

    International Nuclear Information System (INIS)

    Robinson, Gregg F.; Mobile, Katherine; Yu, Yan

    2014-01-01

    The 2012 Radiation Oncology Workforce survey was conducted to assess the current state of the entire workforce, predict its future needs and concerns, and evaluate quality improvement and safety within the field. This article describes the dosimetrist segment results. The American Society for Radiation Oncology (ASTRO) Workforce Subcommittee, in conjunction with other specialty societies, conducted an online survey targeting all segments of the radiation oncology treatment team. The data from the dosimetrist respondents are presented in this article. Of the 2573 dosimetrists who were surveyed, 890 responded, which resulted in a 35% segment response rate. Most respondents were women (67%), whereas only a third were men (33%). More than half of the medical dosimetrists were older than 45 years (69.2%), whereas the 45 to 54 years age group represented the highest percentage of respondents (37%). Most medical dosimetrists stated that their workload was appropriate (52%), with respondents working a reported average of 41.7 ± 4 hours per week. Overall, 86% of medical dosimetrists indicated that they were satisfied with their career, and 69% were satisfied in their current position. Overall, 61% of respondents felt that there was an oversupply of medical dosimetrists in the field, 14% reported that supply and demand was balanced, and the remaining 25% felt that there was an undersupply. The medical dosimetrists' greatest concerns included documentation/paperwork (78%), uninsured patients (80%), and insufficient reimbursement rates (87%). This survey provided an insight into the dosimetrist perspective of the radiation oncology workforce. Though an overwhelming majority has conveyed satisfaction concerning their career, the study allowed a spotlight to be placed on the profession's current concerns, such as insufficient reimbursement rates and possible oversupply of dosimetrists within the field

  2. Proceedings of the 5. Symposium on neutron dosimetry. Radiation protection aspects

    International Nuclear Information System (INIS)

    Schraube, H.; Burger, G.; Booz, J.

    1985-01-01

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

  3. Laboratory of research for environmental radiation and its dosimetry in the ININ

    International Nuclear Information System (INIS)

    Chavez S, B.M.

    2003-01-01

    The objectives of this work are to learn on the methodology that should be continued for the investigation of such a specialized topic as it is a radiation laboratory and to develop the executive project of a building that contains laboratories focused to the investigation of the radiation levels in the environment and their dosimetry. The National Institute of Nuclear Research (ININ), is the place where are carried out many of the investigations related to the field of the physics and chemistry in Mexico besides being the center of nuclear research more important of Latin America and it is for that reason that here is proposed the Laboratory of Low Radiation and its Dosimetry, since the Institute accounts with the whole infrastructure and necessary safety for this type of laboratories. (Author)

  4. Radiation fields, dosimetry, biokinetics and biophysical models for cancer induction by ionising radiation 1996 - 1999. Mid-term reports for the period 1996-1997

    Energy Technology Data Exchange (ETDEWEB)

    Jacob, P; Paretzke, H G; Roth, P [GSF - Forschungszentrum fuer Umwelt und Gesundheit Neuherberg GmbH, Oberschleissheim (Germany). Inst. fuer Strahlenschutz; Michael, B D [Mount Vernon Hospital, Northwood (United Kingdom). Gray Lab.; O` Sullivan, D [Dublin Inst. for Advanced Studies (Ireland)

    1999-12-31

    The main objectives of the first dosimetry project are the measurement of neutron and charged particle flux and energy spectra at altitudes in civil aviation, the determination of response characteristics for detectors, the investigation of calibration procedures, and the evaluation of exposures of aircrews. The overall objective of the second dosimetry project is to improve estimates of dose following the intake of radionuclides by adults and children. The work includes the development of biokinetic and dosimetric models, including models of the gastrointestinal tract, for the systemic behaviour of radionuclides, and for the developing embryo and foetus. Further subjects are target cell dosimetry for short-range particles and the development of computational tools for sensitivity and uncertainty analysis models. The third dosimetry project encompasses the study of different methods for retrospective dose assessments for individuals or groups of individuals accidentally exposed to increased levels of radiation. The methods investigated include electron paramagnetic resonance (EPR) of tooth enamel and chromosome painting (FISH) for lymphocytes in peripheral blood for individual retrospective dose assessments, luminescence techniques on materials in inhabited environment (ceramics, bricks) and model calculations using environmental data as input. (orig.)

  5. Radiation fields, dosimetry, biokinetics and biophysical models for cancer induction by ionising radiation 1996 - 1999. Mid-term reports for the period 1996-1997

    Energy Technology Data Exchange (ETDEWEB)

    Jacob, P.; Paretzke, H.G.; Roth, P. [GSF - Forschungszentrum fuer Umwelt und Gesundheit Neuherberg GmbH, Oberschleissheim (Germany). Inst. fuer Strahlenschutz; Michael, B.D. [Mount Vernon Hospital, Northwood (United Kingdom). Gray Lab.; O`Sullivan, D. [Dublin Inst. for Advanced Studies (Ireland)

    1998-12-31

    The main objectives of the first dosimetry project are the measurement of neutron and charged particle flux and energy spectra at altitudes in civil aviation, the determination of response characteristics for detectors, the investigation of calibration procedures, and the evaluation of exposures of aircrews. The overall objective of the second dosimetry project is to improve estimates of dose following the intake of radionuclides by adults and children. The work includes the development of biokinetic and dosimetric models, including models of the gastrointestinal tract, for the systemic behaviour of radionuclides, and for the developing embryo and foetus. Further subjects are target cell dosimetry for short-range particles and the development of computational tools for sensitivity and uncertainty analysis models. The third dosimetry project encompasses the study of different methods for retrospective dose assessments for individuals or groups of individuals accidentally exposed to increased levels of radiation. The methods investigated include electron paramagnetic resonance (EPR) of tooth enamel and chromosome painting (FISH) for lymphocytes in peripheral blood for individual retrospective dose assessments, luminescence techniques on materials in inhabited environment (ceramics, bricks) and model calculations using environmental data as input. (orig.)

  6. Radiation fields, dosimetry, biokinetics and biophysical models for cancer induction by ionising radiation 1996 - 1999. Mid-term reports for the period 1996-1997

    International Nuclear Information System (INIS)

    Jacob, P.; Paretzke, H.G.; Roth, P.

    1998-01-01

    The main objectives of the first dosimetry project are the measurement of neutron and charged particle flux and energy spectra at altitudes in civil aviation, the determination of response characteristics for detectors, the investigation of calibration procedures, and the evaluation of exposures of aircrews. The overall objective of the second dosimetry project is to improve estimates of dose following the intake of radionuclides by adults and children. The work includes the development of biokinetic and dosimetric models, including models of the gastrointestinal tract, for the systemic behaviour of radionuclides, and for the developing embryo and foetus. Further subjects are target cell dosimetry for short-range particles and the development of computational tools for sensitivity and uncertainty analysis models. The third dosimetry project encompasses the study of different methods for retrospective dose assessments for individuals or groups of individuals accidentally exposed to increased levels of radiation. The methods investigated include electron paramagnetic resonance (EPR) of tooth enamel and chromosome painting (FISH) for lymphocytes in peripheral blood for individual retrospective dose assessments, luminescence techniques on materials in inhabited environment (ceramics, bricks) and model calculations using environmental data as input. (orig.)

  7. Cytogenetic techniques for biological indications and dosimetry of of radiation damages in humans

    International Nuclear Information System (INIS)

    Hadjidekova, V.

    2003-01-01

    The cytogenetic methods present a proved way for bio-monitoring and bio-dosimetry for persons, submitted to ionising radiation in occupational and emergency conditions. Their application complement and assist the evaluation of the physical dosimetry and takes in account the individual radiosensitivity of the organism. A comparative assessment is made of the cytogenetic markers for radiation damage of humans applied in Bulgaria. It is discussed the sensitivity of the methods and their development in the last years, as well as the basic concept for their application - the causal relationship between the frequency of the observation of cytogenetic markers in peripheral blood lymphocytes and the risk of oncological disease. The conventional analysis of dicentrics is recognised as a 'golden standard' for the quantitative assessment of the radiation damage. The long term persisting translocations reflect properly the cumulative dose burden from chronic exposure. The micronucleus test allows a quick screening of large groups of persons, working in ionising radiation environment. The combined application with centromeric DNA probe improves the sensitivity and presents a modern alternative of the bio-monitoring and bio-dosimetry. It is discussed the advantages of the different cytogenetic techniques and their optimised application for the assessment of the radiation impact on humans

  8. Biodistribution and radiation dosimetry of [{sup 11}C]DASB in baboons

    Energy Technology Data Exchange (ETDEWEB)

    Belanger, Marie-Jose [Department of Psychiatry, Columbia University College of Physicians and Surgeons New York, NY 10032 (United States); Division of Brain Imaging, Department of Neuroscience, New York State Pyschiatric Institute, New York, NY 10032 (United States); Simpson, Norman R. [Department of Radiology, Columbia University College of Physicians and Surgeons and Division of Brain Imaging, Department of Neuroscience, New York State Psychiatric Institute, New York, NY 10032 (United States); Wang, Theodore [Department of Radiology, Columbia University College of Physicians and Surgeons and Division of Brain Imaging, Department of Neuroscience, New York State Psychiatric Institute, New York, NY 10032 (United States); Division of Brain Imaging, Department of Neuroscience, New York State Pyschiatric Institute, New York, NY 10032 (United States)] [and others

    2004-11-01

    Objective: The serotonin transporter has been implicated in a variety of conditions including mood disorders and suicidal behavior. In vivo human brain studies with positron emission tomography and the serotonin transporter antagonist [{sup 11}C]DASB ([{sup 11}C]-3-amino-4-(2-dimethylaminomethyl-phenylsulfanyl)-benzonitrile) are ongoing in several laboratories with the maximum administered activity based on dosimetry collected in rodents. We report on the biodistribution and dosimetry of [{sup 11}C]DASB in the baboon as this species may be a more reliable surrogate for human dosimetry. Methods: Four baboon studies (two studies in each of two baboons) were acquired in an ECAT ACCEL camera after the bolus injection of 183{+-}5 MBq/2.3{+-}1.0 nmol of [{sup 11}C]DASB. For each study, six whole-body emission scans were collected in 3D mode over 6/7 bed positions for 2 h. Regions of interest were drawn on brain, lungs, liver, gallbladder, spleen, kidneys, small intestine and bladder. Since no fluid was removed from the animal, total body radioactivity was calculated using the injected dose calibrated to the ACCEL image units. Results: Uptake was greatest in lungs, followed by the urinary bladder, gallbladder, brain and other organs. The ligand was eliminated via the hepato-billiary and renal systems. The largest absorbed dose was found in the lungs (3.6x10{sup -2} mSv/MBq). The absorbed radiation doses in lungs and gallbladder were four and nine times larger than that previously estimated from rat studies. Conclusion: Based on our baboon biodistribution and dose estimates, the lungs are the critical organs for administration of [{sup 11}C]DASB. In the United States, the absorbed dose to the lungs would limit [{sup 11}C]DASB administered with the approval of a Radioactive Drug Research Committee to 1400 MBq (37 mCi) in the adult male and 1100 MBq (30 mCi) in the adult female.

  9. A study of the dosimetry of small field photon beams used in intensity modulated radiation therapy in inhomogeneous media: Monte Carlo simulations, and algorithm comparisons and corrections

    International Nuclear Information System (INIS)

    Jones, Andrew Osler

    2004-01-01

    There is an increasing interest in the use of inhomogeneity corrections for lung, air, and bone in radiotherapy treatment planning. Traditionally, corrections based on physical density have been used. Modern algorithms use the electron density derived from CT images. Small fields are used in both conformal radiotherapy and IMRT, however, their beam characteristics in inhomogeneous media have not been extensively studied. This work compares traditional and modern treatment planning algorithms to Monte Carlo simulations in and near low-density inhomogeneities. Field sizes ranging from 0.5 cm to 5 cm in diameter are projected onto a phantom containing inhomogeneities and depth dose curves are compared. Comparisons of the Dose Perturbation Factors (DPF) are presented as functions of density and field size. Dose Correction Factors (DCF), which scale the algorithms to the Monte Carlo data, are compared for each algorithm. Physical scaling algorithms such as Batho and Equivalent Pathlength (EPL) predict an increase in dose for small fields passing through lung tissue, where Monte Carlo simulations show a sharp dose drop. The physical model-based collapsed cone convolution (CCC) algorithm correctly predicts the dose drop, but does not accurately predict the magnitude. Because the model-based algorithms do not correctly account for the change in backscatter, the dose drop predicted by CCC occurs farther downstream compared to that predicted by the Monte Carlo simulations. Beyond the tissue inhomogeneity all of the algorithms studied predict dose distributions in close agreement with Monte Carlo simulations. Dose-volume relationships are important in understanding the effects of radiation to the lung. The dose within the lung is affected by a complex function of beam energy, lung tissue density, and field size. Dose algorithms vary in their abilities to correctly predict the dose to the lung tissue. A thorough analysis of the effects of density, and field size on dose to the

  10. Dosimetry of internal emitters

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    The Dosimetry of Internal Emitter Program endeavors to refine the correlation between radiation dose and observed biological effects. The program is presently engaged in the development of studies that will demonstrate the applicability of microdosimetry models developed under the Microdosimetry of Internal Sources Program. The program also provides guidance and assistance to Pacific Northwest Laboratory's Biology Department in the dosimetric analysis of internally deposited radionuclides. This report deals with alpha particle dosimetry plutonium 239 inhalation, and in vitro studies of chromosomal observations

  11. 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

  12. Effect of respiratory motion on internal radiation dosimetry

    NARCIS (Netherlands)

    Xie, Tianwu; Zaidi, Habib

    2014-01-01

    Purpose: Estimation of the radiation dose to internal organs is essential for the assessment of radiation risks and benefits to patients undergoing diagnostic and therapeutic nuclear medicine procedures including PET. Respiratory motion induces notable internal organ displacement, which influences

  13. The radiation dosimetry of 99Tcm-exametazime

    International Nuclear Information System (INIS)

    Soundy, R.G.; Tyrrell, D.A.; Pickett, R.D.; Stabin, M.

    1990-01-01

    The biodistribution of the regional cerebral perfusion imaging agent, 99 Tc m -exametazime, has been studied with volunteer subjects at Aberdeen, Hamburg, Manchester and Milan. Data from these studies have been pooled and analysed to formulate a kinetic biodistribution model, allowing estimation of time integrals of activity in various body organs. Estimates of radiation dose to humans injected with this material have been made by applying the MIRD formalism to these data. The highest doses occur to the lachrymal glands, gallbladder and kidneys (33, 27 and 18 mSv, respectively, per 500 MBq administered). The lachrymal glands were visualized in only 6 of the 26 volunteer studies. The effective dose equivalent, for the worst case individual, is 8.3 mSv. In the majority of subjects where there was no uptake in the lachrymal gland, the effective dose equivalent reduces to 6.9 mSv. (author)

  14. Studies of the properties of some saccharides for lyoluminescence dosimetry

    International Nuclear Information System (INIS)

    Hazin, C.A.

    1983-03-01

    Alternative dosimetric methods for high doses are under investigation in a number of research centres. Dosemeters based on the phenomenon of lyoluminescence, i.e., emission of light following dissolution of irradiated organic and inorganic compounds were proposed in the 70's. In the present work, the response of several saccharides submitted to the radiation from a 60 Co source was studied. In order to carry out the study, a measuring system consisting of a light detection chamber and an electrometric unit was designed and built. Thereafter, studies concerning the change in light yield as a function of dose were carried out. Other investigated factors were the change in light yield with solvent pH and temperature and the stability of the response for long term storage. The results showed that maltose, lactose and glucose behaved properly as dosimetric materials for high dose measurements. Besides, no significant changes in the lyoluminescent response ocurred when the solvent pH and temperature varied around the usual values. These results show that the control of these parameters is not critica for the utilization of the saccharides under study for dosimetry. (Author) [pt

  15. Spectral and kinetic analysis of radiation induced optical attenuation in silica: towards intrinsic fibre optic dosimetry?

    International Nuclear Information System (INIS)

    Borgermans, P.

    2002-01-01

    The document is an abstract of a PhD thesis. The PhD work concerns the detailed investigation of the behaviour of optical fibres in radiation fields such as is the case for various nuclear and space application,s. The core of the work concerns the spectral and kinetic analysis of the radiation induced optical attenuation. Models describing underlying physical phenomena, both for the spectral and the time dimensions, have been developed. The potential of silica optical fibre waveguides for intrinsic dosimetry has been assessed by employing specific properties of radiation induced defects in the silica waveguide material

  16. Sci-Sat AM: Radiation Dosimetry and Practical Therapy Solutions - 10: Towards LET detection: A study on the effects of scintillator doping

    Energy Technology Data Exchange (ETDEWEB)

    Nusrat, Humza; Pang, Geordi; Ahmad, Syed; Keller, Brian; Sarfehnia, Arman [Ryerson University, Sunnybrook Health Sciences Centre (Canada)

    2016-08-15

    Purpose: In radiotherapy, the amount of radiation delivered is determined by optimizing the amount of absorbed dose to the tumor. Dose does not always correlate well with the actual biological effects of radiation. This work seeks to validate the LET-dependence of doped plastic scintillators for use in a radiation beam quality (LET) detector. Methods: The LET spectrum ([Φ]) can be resolved knowing the measured signals of uniquely LET-dependent detectors, [S], and the response of each LET-dependent detector to specific LETs ([R]), through the relation [Φ]=[S][R]{sup −1}. Plastic scintillator response is intrinsically LET dependent and can be varied via doping. Initial prototype consists of plastic scintillator and glass taper coupled to an optical fiber; components are housed in black acrylic, reducing effect of ambient light. In order to determine [R], the light response matrix, GEANT4.10.1 Monte Carlo (MC) was used. To validate MC, measurements were done using high energy electrons (9,12,15MeV) and orthovoltage x-rays (100,250kV); scintillator signal was normalized to dose measured simultaneously. Results: Stopping power was varied by changing particle type/energy; measurements indicated that as stopping power increased from 1.9 to 6.6MeV/cm, detector response increased by 263% (+/−29.2%) for 5%Pb-doped scintillator (155% in MC); 52% (+/−7.8%) increase observed when undoped scintillator was used (49% in MC). 5%Pb-doped discrepancy (100kV x-rays) is being investigated. Conclusions: This work validates that doping effects LET/energy response of scintillators; an effect that can be utilized for construction of an LET detector.

  17. Application of the INS facility as a high-flux benchmark for neutron dosimetry and for radiation damage studies in D--T fusion spectra

    International Nuclear Information System (INIS)

    Dierckx, R.; Emigh, C.R.

    1977-01-01

    An Intense Neutron Source facility (INS), is presently under construction at the Los Alamos Scientific Laboratory. This facility is being built by the Energy Research and Development Administration for the radiation damage program in magnetic fusion energy. The facility will contain two D-T neutron sources, both producing about 10 15 primary 14-MeV neutrons per second on a continuous basis. One source will be used to produce a ''pure'' 14-MeV spectrum while the other will be surrounded by a multiplying blanket converter to produce a fusion-like spectrum with a total of about 10 16 neutrons per second

  18. Radiation dosimetry properties of smart-phone CMOS sensors

    International Nuclear Information System (INIS)

    Van Hoey, Olivier; Salavrakos, Alexia; Marques, Antonio; Nagao, Alexandre; Vanhavere, Filip; Cauwels, Vanessa; Nascimento, Luana F.; Willems, Ruben

    2016-01-01

    During the past years, several smart-phone applications have been developed for radiation detection. These applications measure radiation using the smart-phone camera complementary metal-oxide-semiconductor sensor. They are potentially useful for data collection and personal dose assessment in case of a radiological incident. However, it is important to assess these applications. Six applications were tested by means of irradiations with calibrated X-ray and gamma sources. It was shown that the measurement stabilises only after at least 10-25 min. All applications exhibited a flat dose rate response in the studied ambient dose equivalent range from 2 to 1000 μSv h -1 . Most applications significantly over- or underestimate the dose rate or are not calibrated in terms of dose rate. A considerable energy dependence was observed below 100 keV but not for the higher energy range more relevant for incident scenarios. Photon impact angle variation gave a measured signal variation of only about 10 %. (authors)

  19. Thermoluminescent dosimetry of ionizing radiations using ZrO2 prepared at low temperatures

    International Nuclear Information System (INIS)

    Rivera M, T.; Diaz G, J.A.I.; Olvera T, L.; Azorin N, J.; Barrera S, M.; Soto E, A.M.

    2005-01-01

    The thermoluminescent dosimetry (TLD) it is a versatile tool for an evaluation of dose of ionizing radiation. A great variety of ceramic materials and their different physical forms allow a determination of the ionizing radiation in a wide dose interval. In this work the results of studying those thermoluminescent characteristics (TL) of the zirconium oxide obtained by means of the sol-gel technique to low temperatures are presented. To these temperatures the material was obtained in its amorphous state (ZrO 2 -a). The structural characteristics of ZrO 2 -a they were obtained by means of X-ray diffraction. The TL characteristics studied were: TL curve, reproducibility of the TL signal and the fading of the information. The powders of ZrO 2 -a, previously irradiated with beta particles of 90 Sr/ 90 Y, they presented a thermoluminescent curve with two peaks at 150 and 260 C. The fading of the information of the one ZrO 2 -a it was of 20% during the first two hours starting from this time there was one lost of information of 5% to the finish of the 30 days. The reproducibility of the information was of ± 2.5% in standard deviation. (Author)

  20. Investigation of thermal and temporal responses of ionization chambers in radiation dosimetry.

    Science.gov (United States)

    AlMasri, Hussein; Funyu, Akira; Kakinohana, Yasumasa; Murayama, Sadayuki

    2012-07-01

    The ionization chamber is a primary dosimeter that is used in radiation dosimetry. Generally, the ion chamber response requires temperature/pressure correction according to the ideal gas law. However, this correction does not consider the thermal volume effect of chambers. The temporal and thermal volume effects of various chambers (CC01, CC13, NACP parallel-plate, PTW) with different wall and electrode materials have been studied in a water phantom. Measurements were done after heating the water with a suitable heating system, and chambers were submerged for a sufficient time to allow for temperature equilibrium. Temporal results show that all chambers equilibrate quickly in water. The equilibration time was between 3 and 5 min for all chambers. Thermal results show that all chambers expanded in response to heating except for the PTW, which contracted. This might be explained by the differences in the volumes of all chambers and also by the difference in wall material composition of PTW from the other chambers. It was found that the smallest chamber, CC01, showed the greatest expansion. The magnitude of the expansion was ~1, 0.8, and 0.9% for CC01, CC13, and parallel-plate chambers, respectively, in the temperature range of 295-320 K. The magnitude of the detected contraction was <0.3% for PTW in the same temperature range. For absolute dosimetry, it is necessary to make corrections for the ion chamber response, especially for small ion chambers like the CC01. Otherwise, room and water phantom temperatures should remain within a close range.

  1. Epid cine acquisition mode for in vivo dosimetry in dynamic arc radiation therapy

    International Nuclear Information System (INIS)

    Fidanzio, Andrea; Mameli, Alessandra; Placidi, Elisa; Greco, Francesca; Stimato, Gerardina; Gaudino, Diego; Ramella, Sara; D'Angelillo, Rolando; Cellini, Francesco; Trodella, Lucio; Cilla, Savino; Grimaldi, Luca; D'Onofrio, Guido; Azario, Luigi; Piermattei, Angelo

    2008-01-01

    In this paper the cine acquisition mode of an electronic portal imaging device (EPID) has been calibrated and tested to determine the in vivo dose for dynamic conformal arc radiation therapy (DCAT). The EPID cine acquisition mode, that allows a frame acquisition rate of one image every 1.66 s, was studied with a monitor unit rate equal to 100 UM/min. In these conditions good signal stability, ±1% (2SD) evaluated during three months, signal reproducibility within ±0.8% (2SD) and linearity with dose and dose rate within ±1% (2SD) were obtained. The transit signal, S t , (due to the transmitted beam below the phantom) measured by the EPID cine acquisition mode was used to determine, (i) a set of correlation functions, F(w,L), defined as the ratio between S t and the dose at half thickness, D m , measured in solid water phantoms of different thicknesses, w and with square fields of side L, (ii) a set of factors, f(d,L), that take into account the different X-ray scatter contribution from the phantom to the S t signal as a function of the variation, d, of the air gap between the phantom and the EPID. The reconstruction of the isocenter dose, D iso , for DCAT was obtained convolving the transit signal values, obtained at different gantry angles, with the respective reconstruction factors determined by a house-made software. The method was tested with cylindrical and anthropomorphic phantoms and the results show that the reconstructed D iso values can be obtained with an accuracy within ±2.5% in cylindrical phantom and within ±3.4% for anthropomorphic phantom. In conclusion, the transit dosimetry by EPID was assessed to be adequate to perform DCAT in vivo dosimetry, that is not realizable with the other traditional techniques. Moreover, the method proposed here could be implemented to supply in vivo dose values in real time

  2. Calculation codes in radiation protection, radiation physics and dosimetry; Codes de calcul en radioprotection, radiophysique et dosimetrie

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    These scientific days had for objective to draw up the situation of calculation codes of radiation transport, of sources estimation, of radiation doses managements and to draw the future perspectives. (N.C.)

  3. Small Radiation Beam Dosimetry for Radiosurgery of Trigeminal Neuralgia: One Case Analysis

    International Nuclear Information System (INIS)

    Garcia-Garduno, O. A.; Larraga-Gutierrez, J. M.; Rodriguez-Villafuerte, M.; Martinez-Davalos, A.; Moreno-Jimenez, S.; Suarez-Campos, J. J.; Celis, M. A.

    2008-01-01

    The use of small radiation beams for trigeminal neuralgia (TN) treatment requires high precision and accuracy in dose distribution calculations and delivery. Special attention must be kept on the type of detector to be used. In this work, the use of GafChromic EBT registered radiochromic and X-OMAT V2 radiographic films for small radiation beam characterization is reported. The dosimetric information provided by the films (total output factors, tissue maximum ratios and off axis ratios) is compared against measurements with a shielded solid state (diode) reference detector. The film dosimetry was used for dose distribution calculations for the treatment of trigeminal neuralgia radiosurgery. Comparison of the isodose curves shows that the dosimetry produced with the X-OMAT radiographic film overestimates the dose distributions in the penumbra region

  4. Guidelines for Member States concerning radiation measurement standards and Secondary Standard Dosimetry Laboratories

    International Nuclear Information System (INIS)

    1986-01-01

    In the early nineteen-sixties an acute need developed for higher dosimetric accuracy in radiation therapy, particularly in developing countries. This need led to the establishment of a number of dosimetry laboratories around the world, specializing in the calibration of radiation therapy dosimeters. In order to co-ordinate the provision of guidance and assistance to such laboratories, the International Atomic Energy Agency (IAEA) and the World Health Organization (WHO) set up a Network of Secondary Standard Dosimetry Laboratories (SSDLs) under their joint aegis, as described in the IAEA booklet 'SSDLs: Development and Trends' (1985). This publication includes detailed criteria for the establishment of these laboratories. The present guidelines deal with the functions and status of SSDLs, in particular with the need for recognition and support by the competent national authorities. (author)

  5. Mathematical phantom of Indian adult for radiation dosimetry

    International Nuclear Information System (INIS)

    Jain, S.C.; Tyagi, K.

    2000-01-01

    Various countries have either developed or are in process of developing their own reference man for radiation protection purposes. Efforts are made to develop Indian Reference Man, especially by scientific groups at DRDO and BARC. The proposed mathematical phantom of Indian adult will be useful for estimation of radiation dose to various organs from radiation sources from external as well as internal, and compute the effective dose

  6. Automated radiofrequency radiation dosimetry. Final report, Jun 89-Sep 90

    Energy Technology Data Exchange (ETDEWEB)

    Gandhi, O.P.

    1990-12-01

    The interaction of radiofrequency (RF) and microwave (MW) electromagnetic radiation with biological tissues is of increasing importance from the standpoint of health and safety. From considerable literature devoted to the study of RF and MW bioeffects based primarily on animal experimentation it has been determined that bioeffects are correlated with mass-normalized rates of RF or MW energy absorption (specific absorption rates or SARs). An emphasis of our project was to improve the efficiency of the SAR algorithms and to extend their use to higher RF and MW frequencies. Another objective was to adapt these algorithms to computing workstations and distributed memory parallel processors that are becoming more affordable and hence readily available to potential users of these codes.

  7. X-ray diffraction analysis of KY3F10 nanoparticles doped with Nd and preliminary studies for its use in high-dose radiation dosimetry

    International Nuclear Information System (INIS)

    Ichikawa, Rodrigo U.; Linhares, Horacio M.S.M.D.; Silva, Andre S.B. da; Teixeira, Maria I.; Ranieri, Izilda M.; Turrillas, Xavier; Martinez, G.

    2017-01-01

    In this work, the structure and microstructure of Nd:KY 3 F 10 nanoparticles was probed using X-ray synchrotron diffraction analysis. Rietveld refinement was applied to obtain cell parameters, atomic positions and atomic displacement factors to be compared with the ones found in literature. X-ray line profile methods were applied to determine mean crystallite size and crystallite size distribution. Thermoluminescent (TL) emission curves were measured for different radiation doses, from 0.10kGy up to 10.0kGy. Dose-response curves were obtained by area integration beneath the peaks from TL. The reproducibility of the results in this work has shown that this material can be considered a good dosimetric material. (author)

  8. X-ray diffraction analysis of KY3F10 nanoparticles doped with Nd and preliminary studies for its use in high-dose radiation dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Ichikawa, Rodrigo U.; Linhares, Horacio M.S.M.D.; Silva, Andre S.B. da; Teixeira, Maria I.; Ranieri, Izilda M.; Turrillas, Xavier; Martinez, G., E-mail: ichikawa@usp.br, E-mail: andre.santos.silva@usp.br, E-mail: miteixeira@ipen.br, E-mail: iranieri@ipen.br, E-mail: lgallego@ipen.br, E-mail: horaciolinhares@id.uff.br, E-mail: xturrillas@icmab.es [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Universidade Federal Fluminense (INFES/ UFF), Niteroi, RJ (Brazil); Institut de Ciència de Materials de Barcelona (ICMAB / CSIC) (Spain)

    2017-07-01

    In this work, the structure and microstructure of Nd:KY{sub 3}F{sub 10} nanoparticles was probed using X-ray synchrotron diffraction analysis. Rietveld refinement was applied to obtain cell parameters, atomic positions and atomic displacement factors to be compared with the ones found in literature. X-ray line profile methods were applied to determine mean crystallite size and crystallite size distribution. Thermoluminescent (TL) emission curves were measured for different radiation doses, from 0.10kGy up to 10.0kGy. Dose-response curves were obtained by area integration beneath the peaks from TL. The reproducibility of the results in this work has shown that this material can be considered a good dosimetric material. (author)

  9. Radiation dosimetry and its influencing factors for the multi-detector/slice spiral CT

    International Nuclear Information System (INIS)

    Bai Mei; Zheng Junzheng

    2008-01-01

    The Multi-Detector/Slice Spiral Computed Tomography (MDCT/MSCT)reflects the new progress in equipment and technology for radiology. Its popularized application demonstrates its advantages for clinical diagnosis. With the continuous development and growing uses of the MD