Dosimetry in radionuclide therapy

International Nuclear Information System (INIS)

Riccabona, G.

2001-01-01

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

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

Determination of dose rates from natural radionuclides in dental materials

International Nuclear Information System (INIS)

Veronese, I.; Guzzi, G.; Giussani, A.; Cantone, M.C.; Ripamonti, D.

2006-01-01

Different types of materials used for dental prosthetics restoration, including feldspathic ceramics, glass ceramics, zirconia-based ceramics, alumina-based ceramics, and resin-based materials, were investigated with regard to content of natural radionuclides by means of thermoluminescence beta dosimetry and gamma spectrometry. The gross beta dose rate from feldspathic and glass ceramics was about ten times higher than the background measurement, whereas resin-based materials generated negligible beta dose rate, similarly to natural tooth samples. The specific activity of uranium and thorium was significantly below the levels found in the period when addition of uranium to dental porcelain materials was still permitted. The high-beta dose levels observed in feldspathic porcelains and glass ceramics are thus mainly ascribable to 4 K, naturally present in these specimens. Although the measured values are below the recommended limits, results indicate that patients with prostheses are subject to higher dose levels than other members of the population. Alumina- and zirconia-based ceramics might be a promising alternative, as they have generally lower beta dose rates than the conventional porcelain materials. However, the dosimetry results, which imply the presence of inhomogeneously distributed clusters of radionuclides in the sample matrix, and the still unsuitable structural properties call for further optimization of these materials

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)

Considerations of beta and electron transport in internal dose calculations. Final progress report, 1994 -1998

International Nuclear Information System (INIS)

Bolch, W.E.

1998-01-01

This research focused on the following major tasks: improved dosimetric models of the head and brain; development of improved skeletal dosimetry models; development of dosimetric techniques for nonuniform activity distributions; pediatric dosimetry phantoms and radionuclide S values; microdosimetry of beta emitters in radioimmunotherapy; and mechanisms of molecular radiation damage

Is the human nasal cavity at risk from inhaled radionuclides?

International Nuclear Information System (INIS)

Boecker, B.B.; Hahn, F.F.; Cuddihy, R.G.; Snipes, M.B.; McClellan, R.O.

1986-01-01

In a series of three life-span studies in which beagle dogs inhaled relatively soluble forms of beta-emitting radionuclides, a number of cancers of the nasal cavity have arisen at long times after the inhalation exposure. No such cancers were observed in the control dogs. Data obtained in other studies involving serial sacrifice of dogs that received these radionuclides in similar forms have shown that high local concentrations of the radionuclides can persist in nasal turbinates for long periods of time, depending on the physical half-life of the radionuclide inhaled. Several nasal carcinomas have also been observed in dogs injected with 137 CsCl in which the relative concentrations of beta activity in the turbinate region were not as pronounced as in the above studies. Similar risks of sinonasal cancer were calculated for dogs in each of these studies regardless of differences in radionuclide, dosimetry, and route of administration. Since sinonasal cancers have occurred in people exposed to alpha-emitting radionuclides, it is reasonable to assume this could occur with beta emitters as well. Radiation protection guidelines should account for the sinonasal region being at risk. 23 refs., 1 fig., 6 tabs

The relative effectiveness of inhaled alpha- and beta-emitting radionuclides in producing lung cancer

International Nuclear Information System (INIS)

Boecker, B.B.; Hahn, F.F.; Muggenburg, B.A.; Guilmetter, R.A.; Griffith, W.C.; McClellan, R.O.

1988-01-01

Proper assessment of a long-term human health risks associated with inhaled radionuclides requires knowledge of dose to critical cells and tissues and relationships between dose and effect for different biological end points. Results from epidemiological studies of exposed human populations provided important information for such assessments. However, because the types of exposures are limited, these results need to be supplemented with more detailed information on dosimetry and biological effects available through studies in laboratory animals and in vitro systems. To provide health risk information for inhaled fission product and actinide aerosols, life-span studies are being conducted using beagle dogs and other species at the Lovelace Inhalation Toxicology Research Institute (ITRI). Results of two life-span studies in dogs involving inhalation of the beta emitter 91 Y in fused aluminosilicate particles or the alpha emitter 239 PuO 2 are reported here

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

Toxicity studies of inhaled beta-emitting radionuclides - Status report

Energy Technology Data Exchange (ETDEWEB)

Hahn, F F; Boeker, B B; Gillett, N A; Griffith, W C; Lundgren, D L; McClellan, R O; Muggenburg, B A; Snipes, M B

1988-12-01

The effects of beta-emitting radionuclides inhaled in either a relatively soluble form ({sup 90}SrCl{sub 2}, {sup 144}CeCl{sub 3}, {sup 91}yl{sub 3}, or {sup 137}CsCl) or in a relatively insoluble form ({sup 90}Y, {sup 91}Y, {sup 144}Ce or {sup 90}Sr in fused aluminosilicate particles [FAP]) have been studied in laboratory animals. The results showed that the total beta dose and the dose-rate pattern can modify both the neoplastic and non-neoplastic effects of inhaled beta-emitting radionuclides. In addition, the solubility and chemical characteristics of the radionuclides influence which organs are affected. Effects are seen primarily in organs where the radionuclide is ultimately accumulated, e.g., lung, bone, liver, or tracheobronchial lymph nodes. In addition, effects may be seen in organs where there is little accumulation, but where the radiation dose may still be high, e.g., nasal epithelium and heart. Studies of inhaled {sup 144}Ce-FAP in four different species showed that, compared to mice and dogs, lung tumor risk factors are very low for Syrian hamsters and high for rats. Studies of mice, Syrian hamsters, rats, and dogs repeatedly exposed to aerosols of {sup 144}Ce-FAP showed that lung tumor incidence correlates better with cumulative dose to the lung than with dose rate. Most of the studies in this program are nearing completion and full analyses are in progress. (author)

Nuclear decay data files of the Dosimetry Research Group

International Nuclear Information System (INIS)

Eckerman, K.F.; Westfall, R.J.; Ryman, J.C.; Cristy, M.

1993-12-01

This report documents the nuclear decay data files used by the Dosimetry Research Group at Oak Ridge National Laboratory and the utility DEXRAX which provides access to the files. The files are accessed, by nuclide, to extract information on the intensities and energies of the radiations associated with spontaneous nuclear transformation of the radionuclides. In addition, beta spectral data are available for all beta-emitting nuclides. Two collections of nuclear decay data are discussed. The larger collection contains data for 838 radionuclides, which includes the 825 radionuclides assembled during the preparation of Publications 30 and 38 of the International Commission on Radiological Protection (ICRP) and 13 additional nuclides evaluated in preparing a monograph for the Medical Internal Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine. The second collection is composed of data from the MIRD monograph and contains information for 242 radionuclides. Abridged tabulations of these data have been published by the ICRP in Publication 38 and by the Society of Nuclear Medicine in a monograph entitled ''MIRD: Radionuclide Data and Decay Schemes.'' The beta spectral data reported here have not been published by either organization. Electronic copies of the files and the utility, along with this report, are available from the Radiation Shielding Information Center at Oak Ridge National Laboratory

Dosimetry of beta sources utilized in nuclear medicine and biomedicine

International Nuclear Information System (INIS)

Bergoc, R.M.; Rivera, E.; Cricco, G.; Martin, G.; Cocca, C.; Caro, R.A.

1998-01-01

Full text: The use of high energy pure beta sources (i.e., 32 P= 1.71 MeV/des) is common in medicine (intratumoral therapy or treatment of non-malignant illness as restenosis) and in biochemistry (molecular biology). The external dosimetry of these sources offers some important points that must be considered: 1) beta particles emitted by the source are not monoenergetic; 2) the range (R 0 ) vary with the source energy and the Z of the absorber; 3) below an energy of 1 MeV, the specific ionization in the absorbent medium (air, water, lucite) increases as the beta energy (E β ) decreases; 4) the range of beta particles, R β , is independent from Z of the material, provided Z is low and the material has no hydrogen; in this case, the expression: R β δ 1 = R β δ 2 is valid; 5) the calculation of the external beta dosimetry must consider that since the used sources are not punctual there is self-absorption which should be taken into account. However, in the range of the fractions of activities for the above mentioned practices a theoretical model for punctual sources can be used; in this case, it is valid to use the expression: Dose Rate: = A (S/δ)E β e -S/δ δx /4 π d 2 , where: (S/δ) is the absorbent Mass Stopping Power and represents the loss of energy by unit mass thickness; it depends from E β and it is independent from Z; (δx) is the mass thickness of the absorber. By this way, e -S/δ δx is the attenuation of the beta particles flow. From the application of this formula it can be deduced that, for sources of 1 mCi of 32 P activities, as those employed in biochemistry, a small thickness of lucite is enough shield. When the source has higher activities, as those used in radiotherapy, the operator should take into account the regulations for a strict dosimetric control. These formulae allow a simplified calculation of the 32 P dosimetry of sources used in nuclear medicine and biomedical practices. (author) [es

Graphite mixed magnesium borate TL dosemeters for beta ray dosimetry

DEFF Research Database (Denmark)

Prokic, M; Christensen, Poul

1984-01-01

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

Methodology development for dosimetry of 90Sr + 90Y beta therapy applicators

International Nuclear Information System (INIS)

Coelho, T.S.; Yoriyaz, H.; Fernandes, M.A.R.

2009-01-01

The 9 0Sr+ 9 0Y applicators, used in beta therapy for prevention of keloids and pterigio, are imported and its dosimetric features are only illustrated by the manufacturers. The exhaustive routine of the medical physicists in the clinic do not make possible the accomplishment of procedures for the confirmation of these parameters. This work presents a methodology development for dosimetry in two 9 0Sr+ 9 0Y beta therapy applicators of the Amersham brand. The Monte Carlo code MCNP 4 C was used for the simulation of the percentage depth dose curves. The experimental measurements of the radiation attenuation had been done with a mini-extrapolation chamber. The results of the experimental measures had been compared with the simulated values. Both percentage deep dose curves, the theoretical and the experimental ones, had presented similar behavior, which may validate the use of the MCNP 4 C for these simulations, strengthening the usage of this method at procedures of dosimetry of these beta radiation sources. (author)

Hot beta particles in the lung: Results from dogs exposed to fission product radionuclides

Energy Technology Data Exchange (ETDEWEB)

Hahn, F.F.; Griffith, W.C.; Hobbs, C.H. [and others

1995-12-01

The Chernobyl nuclear reactor accident resulted in the release of uranium dioxide fuel and fission product radionuclides into the environment with the fallout of respirable, highly radioactive particles that have been termed {open_quotes}hot beta particles.{close_quotes} There is concern that these hot beta particles (containing an average of 150-20,000 Bq/particle), when inhaled and deposited in the lung, may present an extraordinary hazard for the induction of lung cancer. We reviewed data from a group of studies in dogs exposed to different quantities of beta-emitting radionuclides with varied physical half-lives to determine if those that inhaled hot beta particles were at unusual risk for lung cancer. This analysis indicates that the average dose to the lung is adequate to predict biologic effects of lung cancer for inhaled beta-emitting radionuclides in the range of 5-50 Gy to the lung and with particle activities in the range of 0.10-50 Bq/particle.

Calculation of absorbed dose of anchorage-dependent cells from internal beta-rays irradiation

International Nuclear Information System (INIS)

Chen Jianwei; Huang Gang; Li Shijun

2001-01-01

Objective: To elicit the formula of internal dosimetry in anchorage-dependent cells by beta-emitting radionuclides from uniformly distributed volume sources. Methods: By means of the definition of absorbed dose and the MIRD (Medical International Radiation Dose) scheme the formula of internal dosimetry was reasonably deduced. Firstly, studying the systems of suspension culture cells. Then, taking account of the speciality of the systems of the anchorage-dependent cells and the directions of irradiation, the absorbed dose of anchorage -dependent cells was calculated by the accumulated radioactivity, beta-ray energy, and the volume of the cultured systems. Results: The formula of internal dosimetry of suspension culture cells and anchorage-dependent cells were achieved. At the same time, the formula of internal dosimetry of suspension culture cells was compared with that of MIRD and was confirmed accurate. Conclusion: The formula of internal dosimetry is concise, reliable and accurate

Dosimetry and quantitative radionuclide imaging in radioimmunotherapy: Final report, July 15, 1992-July 14, 1996

International Nuclear Information System (INIS)

Leichner, P.K.

1996-09-01

Brief summaries of the principal accomplishments of this project on the development of quantitative SPECT for high energy photons (87Y, 19F) and stability testing of 87Y-labeled antibodies in the nude mouse model, development of an unified approach to photon and beta particle dosimetry, quantitative SPECT for nonuniform attenuation, and development of patient-specific dosimetry in radioimmunotherapy

Dosimetry in radionuclide therapies with 90Y-conjugates. The IEO experience

International Nuclear Information System (INIS)

Cremonesi, M.; Ferrari, M.; Chinol, M.; Bartolomei, M.; Sacco, E.; Fiorenza, M.; Tosi, G.; Paganelli, G.; Stabin, M. G.

2000-01-01

The basis for successful radionuclide therapy is a high and stable uptake of the radiopharmaceutical in the target tissue along with low activity concentration in other normal organs. The contribution of dosimetry in radionuclide therapy is to predict before the treatment the absorbed doses in tumor and normal organs, to identify the critical organs, to minimize any possible toxicity and to evaluate the maximum tolerated dose. In this article is reported the experience concerning pharmacokinetics and dosimetry of two 90 Y-therapeutic protocols: 3-step pretargeting radioimmunotherapy (RIT) according to the biotin-avidin system and receptor mediated radionuclide therapy with the somatostatin analogue (DOTA-D-Phe 1 -Tyr 3 ) octreotide named DOTATOC. For the dosimetric analysis, analogous approaches for the two radiolabeled compounds due to the similar pharmacokinetic characteristics were adopted; the MIRD formalism was applied, taking into account both the physical and the biological characteristics of the radio conjugate and patients' metabolism. In order to determine biological clearance, serial blood samples and complete urine collection were obtained up to 48 hours after injection; to evaluate biodistribution, several whole body scans were acquired. Both therapies showed the advantageous characteristics of a fast blood clearance and a predominantly renal excretion of the radiopharmaceuticals thus lowering the irradiation of the total body. Although pharmacokinetic characteristics were similar, different critical organs were found for the two therapies: in particular, some considerations regarding red marrow, spleen and kidneys were required. The results of the studies indicate that high activities of 90 Y-biotin (3-step RIT) and 90 Y-DOTATOC can be administered with acceptable radiation doses to normal organs

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)

Evaluation of Brazilian intercomparison program data from 1991 to 1995 of radionuclide assays in environmental samples

International Nuclear Information System (INIS)

Vianna, Maria Elizabeth Couto M.; Tauhata, Luiz; Oliveira, Antonio Eduardo de; Oliveira, Josue Peter de; Clain, Almir Faria; Ferreira, Ana Cristina M.

1998-01-01

Historical radioanalytical data from the Institute of Radiation Protection and Dosimetry (IRD) national intercomparison program from 1991 to 1995 were analyzed to evaluate the performance of sixteen Brazilian laboratories in radionuclide analyses in environmental samples. Data are comprised of measurements of radionuclides in 435 spiked environmental samples distributed in fifteen intercomparison runs comprised of 955 analyses. The general and specific radionuclide performances of the participating laboratories were evaluated relative to the reference value. Data analysis encourages improvements in beta emitter measurements

Uptake and dosimetry of Auger emitting diagnostic radionuclides (in particular indium-111) in human male germ cells

International Nuclear Information System (INIS)

Nettleton, J.S.; Lawson, R.S.; Prescott, M.C.; Hoyes, K.P.; Morris, I.D.

2000-01-01

This paper concerns the uptake and dosimetry of Auger electron emitting radionuclides which are used during routine diagnostic nuclear medicine procedures, in human testes and spermatozoa (sperm). A computer model was developed to calculate the doses to sperm heads from cellular localisation of the Auger electron emitting radionuclides 99m Tc, 111 In, 123 I and 201 Tl. An assumption of ellipsoidal geometry was made to approximate the sperm head. S Factors were determined for differing sub-cellular localisations of radionuclide. The S-Factors determined were then combined with in-vitro data for quantification of radionuclide uptake for 99m Tc pertechnetate, 111 In chloride and 201 Tl chloride, to estimate in-vivo doses to sperm heads following intravenous administration of radionuclide in typical diagnostic quantities. The uptake and resulting cellular radiation dose of 111 In (from the chloride) was significantly larger than the other radionuclides in the chemical forms investigated. Further investigations were carried out to determine localisation of 111 In on sperm. The results of these experiments indicate that the radiation dose to mature sperm following administration of 111 In pharmaceuticals for diagnostic purposes might be large enough to result in DNA damage which is not expressed until after fertilisation of an oocyte. Consideration should therefore be given to providing some contraceptive advice following diagnostic administrations of this radionuclide. In order to consider the possible effects of these radionuclides on other spermatogenic cells, further studies were undertaken to obtain in-vivo data for quantification of 111 In chloride and 201 Tl chloride uptake into the human testis following intravenous administration. Conventional dosimetry was then used to estimate testicular radiation dose using our values of percentage uptake. The results obtained indicate that the values of testicular radiation doses quoted by ICRP for 111 In might be too low by

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

International Nuclear Information System (INIS)

Sherbini, S.; Porter, S.W.

1983-06-01

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

Dosimetric model for antibody targeted radionuclide therapy of tumor cells in cerebrospinal fluid

International Nuclear Information System (INIS)

Millar, W.T.; Barrett, A.

1990-01-01

Although encouraging results have been obtained using systemic radioimmunotherapy in the treatment of cancer, it is likely that regional applications may prove more effective. One such strategy is the treatment of central nervous system leukemia in children by intrathecal instillation of targeting or nontargeting beta particle emitting radionuclide carriers. The beta particle dosimetry of the spine is assessed, assuming that the spinal cord and the cerebrospinal fluid compartment can be adequately represented by a cylindrical annulus. The radionuclides investigated were 90 Y, 131 I, 67 Cu, and 199 Au. It is shown that the radiation dose to the cord can be significantly reduced using short range beta particle emitters and that there is little advantage in using targeting carriers with these radionuclides. 199 Au and 67 Cu also have the advantage of having a suitable gamma emission for imaging, permitting pretherapy imaging and dosimetric calculations to be undertaken prior to therapy. If these methods prove successful, it may be possible to replace the external beam component used in the treatment of central nervous system leukemia in children by intrathecal radionuclide therapy, thus reducing or avoiding side effects such as growth and intellectual impairment

State-of-the-Art Beta Detection and Dosimetry

International Nuclear Information System (INIS)

David M. Hamby

2008-01-01

The research funded by this NEER grant establishes the framework for a detailed understanding of the challenges in beta dosimetry, especially in the presence of a mixed radiation field. The work also stimulated the thinking of the research group which will lead to new concepts in digital signal processing to allow collection of detection signals and real-time analysis such that simultaneous beta and gamma spectroscopy can take place. The work described herein (with detail in the many publications that came out of this research) was conducted in a manner that provided dissertation and thesis topics for three students, one of whom was completely funded by this grant. The overall benefit of the work came in the form of a dramatic shift in signal processing that is normally conducted in analog pulse shape analysis. Analog signal processing was shown not to be feasible for this type of work; digital signal processing was a must. This, in turn, led the research team to a new understanding of pulse analysis, one in which expands the state-of-the-art in simultaneous beta and gamma spectroscopy with a single detector

State-of-the-Art Beta Detection and Dosimetry

Energy Technology Data Exchange (ETDEWEB)

David M. Hamby

2008-08-15

The research funded by this NEER grant establishes the framework for a detailed understanding of the challenges in beta dosimetry, especially in the presence of a mixed radiation field. The work also stimulated the thinking of the research group which will lead to new concepts in digital signal processing to allow collection of detection signals and real-time analysis such that simultaneous beta and gamma spectroscopy can take place. The work described herein (with detail in the many publications that came out of this research) was conducted in a manner that provided dissertation and thesis topics for three students, one of whom was completely funded by this grant. The overall benefit of the work came in the form of a dramatic shift in signal processing that is normally conducted in analog pulse shape analysis. Analog signal processing was shown not to be feasible for this type of work; digital signal processing was a must. This, in turn, led the research team to a new understanding of pulse analysis, one in which expands the state-of-the-art in simultaneous beta and gamma spectroscopy with a single detector.

Atmospheric deposition of long-lived Beta radionuclides over the territory of Bulgaria during the last decades

Energy Technology Data Exchange (ETDEWEB)

Veleva, B. [National Institute of Meteorology and Hydrology, Bulgarian Academy of Sciences, Sofia (Bulgaria)

2013-07-01

The sources of atmospheric radioactivity are discussed and compared. Radon isotopes and their daughters' dominate the natural background of beta activity in the surface air. The man-made radionuclides, much of them beta emitters, started to contaminate regionally and globally the environment after 1940's due to the atmospheric nuclear bomb tests. Additional significant sources of technogenic radionuclides in the atmosphere were nuclear accidents with pronounced examples of Chernobyl and Fukushima. The Bulgarian network for atmospheric radioactivity monitoring has been developing since 1959 in the frame of the state Hydro-meteorological service, now National Institute of Meteorology and Hydrology. It includes daily measurements of aerosol beta activity and deposition immediately and 120h after the sampling. The time and space variations of deposited beta activity, based on long term data records are presented and impact assessment of the different sources is given. The role of precipitation in deposition of radionuclides is evaluated. (author)

Calibration of radionuclides with decay trough beta emission or electron capture by liquid scintillation technique

International Nuclear Information System (INIS)

Loureiro, Jamir dos Santos

2000-02-01

In this work is reported a methodology a methodology for pure beta and electron capture radionuclides standardization, suing liquid scintillation technique. In this sense the CIEMAT/NIST method, recently utilized by international laboratories, was implemented and the lack in the Laboratorio Nacional das Radiacoes Ionizantes - LNMRI, of the Comissao Nacional de Energia Nuclear - CNEN, for adequate methodology to standardize this kind if radionuclides was filled, fact that was not present with alpha and gamma radionuclides. The implementation procedure evaluation was provided by concentration activity determination of the following radionuclides: 14 C and 90 Sr, pure beta emitters; 55 Fe, electron capture decay; 204 Tl, electron capture and beta decay and 60 Co, beta-gamma emitter. In this way, a careful analysis of the implementation procedure with these radionuclides types, ranging on a broad energy spectral, was possible. To check the calibration results, intercomparisons among our measurements of these radionuclides and the reference values of the CIEMAT/Spain laboratory were provided. To check the calibration results, intercomparisons among our measurements of these radionuclides and the reference values of the CIEMAT/Spain laboratory were provided. Besides this intercomparisons, one was provided with a 204 Tl solution, utilized in the international comparison recently promoted by BIPM, and another one with a 60 C solution calibrated in LNMRI/CNEN previously by a relative calibration system, with a well type pressurized ionization chamber, and an absolute beta-gamma coincidence system, with a pill-box type proportional counter 4 π geometry, coupled with a scintillator system with a sodium iodide cristal of 4x4 inches. The comparisons among LNMRI/CNEN results and the reference values, showed a small deviation of 1,32% for 14 C, 0,40% for 60 Co, 1,12% for 55 Fe, 0,10% for 90 Sr and 0,73% for 204 Tl. For the BIPM solution the deviation was 0,46% and for 60 Co

Internal dosimetry, past and future

International Nuclear Information System (INIS)

Johnson, J.R.

1989-03-01

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

SU-E-T-345: Validation of a Patient-Specific Monte Carlo Targeted Radionuclide Therapy Dosimetry Platform

International Nuclear Information System (INIS)

Besemer, A; Bednarz, B

2014-01-01

Purpose: There is a compelling need for personalized dosimetry in targeted radionuclide therapy given that conventional dose calculation methods fail to accurately predict dose response relationships. To address this need, we have developed a Geant4-based Monte Carlo patient-specific 3D dosimetry platform for TRT. This platform calculates patient-specific dose distributions based on serial CT/PET or CT/SPECT images acquired after injection of the TRT agent. In this work, S-values and specific absorbed fractions (SAFs) were calculated using this platform and benchmarked against reference values. Methods: S-values for 1, 10, 100, and 1000g spherical tumors with uniform activity distributions of I-124, I-125, I-131, F-18, and Ra-223 were calculated and compared to OLINDA/EXM reference values. SAFs for monoenergetic photons of 0.01, 0.1, and 1 MeV and S factors for monoenergetic electrons of 0.935 MeV were calculated for the liver, kidneys, lungs, pancreas, spleen, and adrenals in the Zubal Phantom and compared with previously published values. Sufficient particles were simulated to keep the voxel statistical uncertainty below 5%. Results: The calculated spherical S-values agreed within a few percent of reference data from OLINDA/EXM for each radionuclide and sphere size. The comparison of photon SAFs and electron S-values with previously published values showed good agreement with the previously published values. The S-values and SAFs of the source organs agreed within 1%. Conclusion: Our platform has been benchmarked against reference values for a variety of radionuclides and over a wide range of energies and tumor sizes. Therefore, this platform could be used to provide accurate patientspecific dosimetry for use in radiopharmaceutical clinical trials

Study of Optically Stimulated Luminescence of LiF:Mg,Ti for beta and gamma dosimetry

International Nuclear Information System (INIS)

Matsushima, Luciana C.; Veneziani, Glauco R.; Campos, Letícia L.

2013-01-01

Modern advances in radiation medicine – radiodiagnosis, radiotherapy and interventional radiography – each present dosimetry challenges for the medical physicist that did not exist previously. In all of these areas a constant balance has to be made between the treatment necessary to destroy the tumor and the unnecessary exposure of healthy tissue. Innovative applications of OSL dosimetry are now appearing in each of these areas to help the medical physicist and oncologist design the most effective, and least deleterious, treatment for their patients. High sensitivity, precise delivery of light, fast readout times, simpler readers and easier automation are the main advantages of OSL in comparison with TLD. This work aimed to study the application of OSL technique using lithium fluoride dosimeters doped with magnesium and titanium (LiF:Mg,Ti) for application in beta and gamma dosimetry. -- Highlights: •Study of Optically Stimulated Luminescence of LiF:Mg,Ti and microLiF:Mg,Ti. •OSL response of TLD-100 dosimeters to beta and gamma radiation. •Analysis of repeatability and lowest levels of detection of detectors LiF:Mg,Ti

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)

Extension of the biological effective dose to the MIRD schema and possible implications in radionuclide therapy dosimetry

International Nuclear Information System (INIS)

Baechler, Sebastien; Hobbs, Robert F.; Prideaux, Andrew R.; Wahl, Richard L.; Sgouros, George

2008-01-01

In dosimetry-based treatment planning protocols, patients with rapid clearance of the radiopharmaceutical require a larger amount of initial activity than those with slow clearance to match the absorbed dose to the critical organ. As a result, the dose-rate to the critical organ is higher in patients with rapid clearance and may cause unexpected toxicity compared to patients with slow clearance. In order to account for the biological impact of different dose-rates, radiobiological modeling is beginning to be applied to the analysis of radionuclide therapy patient data. To date, the formalism used for these analyses is based on kinetics derived from activity in a single organ, the target. This does not include the influence of other source organs to the dose and dose-rate to the target organ. As a result, only self-dose irradiation in the target organ contributes to the dose-rate. In this work, the biological effective dose (BED) formalism has been extended to include the effect of multiple source organ contributions to the net dose-rate in a target organ. The generalized BED derivation has been based on the Medical Internal Radionuclide Dose Committee (MIRD) schema assuming multiple source organs following exponential effective clearance of the radionuclide. A BED-based approach to determine the largest safe dose to critical organs has also been developed. The extended BED formalism is applied to red marrow dosimetry, as well as kidney dosimetry considering the cortex and the medulla separately, since both those organs are commonly dose limiting in radionuclide therapy. The analysis shows that because the red marrow is an early responding tissue (high α/β), it is less susceptible to unexpected toxicity arising from rapid clearance of high levels of administered activity in the marrow or in the remainder of the body. In kidney dosimetry, the study demonstrates a complex interplay between clearance of activity in the cortex and the medulla, as well as the initial

Assessment and management of risks associated with exposures to Auger- and beta-emitting radionuclides. Recommendations and proposals for lines of research

International Nuclear Information System (INIS)

2010-01-01

The assessment and management of risks associated with exposures to ionising radiation are defined by the general radiological protection system, proposed by the International Commission on Radiological Protection (ICRP). This system is regarded by a large majority of users as a robust system with well-established relevance for the management and prevention of exposures. Despite this, there are a number of dissenting voices, claiming that this system is not suitable for estimating the risks resulting from internal exposures, particularly when incorporated radionuclides decay, emitting electrons. Criticisms of the system particularly pertain to Auger- and beta-emitting radionuclides, the intake of which can occur during environmental and industrial exposures or, simply, during a medical use of ionising radiation for diagnostic or therapeutic purposes. These debates result from a lack of data in the fields of dosimetry and toxicology of these radionuclides. Auger and beta emitters can be distributed preferentially in certain tissue structures and even in certain cellular organelles, according to the vector with which they are associated. Given the limited range of electrons in matter, this heterogeneous distribution can generate highly localised energy depositions, not taken into account in conventional dosimetry methods, which make the assumption of uniform energy depositions. These specific physical and biochemical features of some of these radionuclides seem to influence their cellular toxicity directly. It is thus established that intranuclear distribution of iodine-125 is more effective for the induction of mutations or even cell death than a cytosolic distribution. This point is explained by the very short range of Auger electrons in matter (around a few dozen nm), which, in the case of an intranuclear distribution, would deliver all of their energy in the vicinity of the DNA, which, if affected, would be detrimental to the survival of the cell. The observation

The assessment and management of risks associated with exposures to short-range Auger- and beta-emitting radionuclides. State of the art and proposals for lines of research

International Nuclear Information System (INIS)

Paquet, F; Biau, A; Barbey, P; Bardiès, M; Blanchardon, E; Chetioui, A; Lebaron-Jacobs, L; Pasquier, J L

2013-01-01

The assessment and management of risks associated with exposures to ionising radiation are defined by the general radiological protection system, proposed by the International Commission on Radiological Protection (ICRP). This system is regarded by a large majority of users as a robust system although there are a number of dissenting voices, claiming that it is not suitable for estimating the risks resulting from internal exposures. One of the specific issues of internal exposure involves short-range radiations such as Auger and beta particles. Auger- and beta-emitting radionuclides can be distributed preferentially in certain tissue structures and even in certain cellular organelles, according to their chemical nature and the vector with which they are associated. Given the limited range of the low-energy electrons in biological matter, this heterogeneous distribution can generate highly localised energy depositions and exacerbate radiotoxic responses at cellular level. These particularities in energy distribution and cellular responses are not taken into account by the conventional methods for the assessment of risk. Alternative systems have been proposed, based on dosimetry conducted at the cellular or even molecular level, whose purpose is to determine the energy deposition occurring within the DNA molecule. However, calculation of absorbed doses at the molecular level is not sufficient to ensure a better assessment of the risks incurred. Favouring such a microdosimetric approach for the risk assessments would require a comprehensive knowledge of the biological targets of radiation, the dose–response relationships at the various levels of organisation, and the mechanisms leading from cellular energy deposition to the appearance of a health detriment. The required knowledge is not fully available today and it is not yet possible to link an intracellular energy deposition to a probability of occurrence of health effects or to use methods based on cellular

Patient-specific dosimetry in peptide receptor radionuclide therapy: a clinical review

International Nuclear Information System (INIS)

Chalkia, M.T.; Stefanoyiannis, A.P.; Chatziioannou, S.N.; Efstathopoulos, E.P.; Round, W.H.; Nikiforidis, G.C.

2015-01-01

Neuroendocrine tumours (NETs) belong to a relatively rare class of neoplasms. Nonetheless, their prevalence has increased significantly during the last decades. Peptide receptor radionuclide therapy (PRRT) is a relatively new treatment approach for inoperable or metastasised NETs. The therapeutic effect is based on the binding of radiolabelled somatostatin analogue peptides with NETs’ somatostatin receptors, resulting in internal irradiation of tumours. Pre-therapeutic patient-specific dosimetry is essential to ensure that a treatment course has high levels of safety and efficacy. This paper reviews the methods applied for PRRT dosimetry, as well as the dosimetric results presented in the literature. Focus is given on data concerning the therapeutic somatostatin analogue radiopeptides 111 In-[DTPA o , D -Phe 1 ]-octreotide ( 111 In-DTPA-octreotide), 90 Y-[DOTA o ,Tyr 3 ]-octreotide ( 90 Y-DOTATOC) and 177 Lu-[DOTA o ,Tyr 3 ,Thr 8 ]-octreotide ( 177 Lu-DOTATATE). Following the Medical Internal Radiation Dose (MIRD) Committee formalism, dosimetric analysis demonstrates large interpatient variability in tumour and organ uptake, with kidneys and bone marrow being the critical organs. The results are dependent on the image acquisition and processing protocol, as well as the dosimetric imaging radiopharmaceutical.

Thermoluminescent dosimetry of new phosphors of Zn O exposed to beta radiation; Dosimetria termoluminiscente de nuevos fosforos de ZnO expuestos a radiacion beta

Energy Technology Data Exchange (ETDEWEB)

Cruz V, C.; Burruel I, S.E.; Grijalva M, H. [UNISON, A.P. 130, Hermosillo, Sonora (Mexico); Barboza F, M.; Bernal, R. [CIF, UNISON, A.P. 5-088, Hermosillo, Sonora (Mexico)

2004-07-01

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)

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

Biological Dosimetry of In Vitro Irradiation with Radionuclides : Comparison of Whole Blood, Lymphocyte and Buffy Coat Culture

International Nuclear Information System (INIS)

Kim, Jong Ho; Lee, Dong Soo; Choi, Chang Woon; Chung, June Key; Lee, Myung Chul; Koh, Chang Soon; Kim, Chong Soon; Kim, Hee Geun; Kang, Duck Won; Song, Myung Jae

1995-01-01

The purpose of this study was to establish mononuclear cell cultures such as lymphocytes or buffy coat for the biological dosimetry of in vitro irradiation of the radionuclide Tc-99m in order to exclude the effect of residual doses seen in the cultures of whole blood. Biological dosimetry of Tc-99m on cultured mononuclear cells at doses ranging from 0.05 to 6.00 Gy, by scoring unstable chromosomal aberrations(Ydr) observed in cultured lymphocytes, were performed using peripheral venous blood of healthy normal person. The results showed that; (1) In vitro irradiation of radioisotope in separated lymphocyte or buffy coat showed trace amount af residual doses of isotope after washing. Residual doses of isotopes are increased in proportion tn exposed time and irradiated dose without difference between I-131 anct Tc-99m. (2) We obtained these linear-quadratic dose response equations in lymphocyte and buffy coat culture after in vitro irradiation of Tc-99m, respectively (Ydr = 0,001949 D 2 +0,006279D+ 0.000185; Ydr= 0.002531 D 2 -0.003274 D+0.003488). In conclusion, the linear quadrstic dose response equation from in vitro irradiation of Tc-99m with lymphocyte and buffy coat culture was thought to be useful for assessing Tc-99m indueed biological effects. And mononuclear cell cultures seem to be the most appropriate experimental model for the assessment of biological dosimetry of internal irradiation of radionuclides.

Primary and scattering contributions to beta scaled dose point kernels by means of Monte Carlo simulations; Contribuicoes primaria e espalhada para dosimetria beta calculadas pelo dose point kernels empregando simulacoes pelo Metodo Monte Carlo

Energy Technology Data Exchange (ETDEWEB)

Valente, Mauro [CONICET - Consejo Nacional de Investigaciones Cientificas y Tecnicas de La Republica Argentina (Conicet), Buenos Aires, AR (Brazil); Botta, Francesca; Pedroli, Guido [European Institute of Oncology, Milan (Italy). Medical Physics Department; Perez, Pedro, E-mail: valente@famaf.unc.edu.ar [Universidad Nacional de Cordoba, Cordoba (Argentina). Fac. de Matematica, Astronomia y Fisica (FaMAF)

2012-07-01

Beta-emitters have proved to be appropriate for radioimmunotherapy. The dosimetric characterization of each radionuclide has to be carefully investigated. One usual and practical dosimetric approach is the calculation of dose distribution from a unit point source emitting particles according to any radionuclide of interest, which is known as dose point kernel. Absorbed dose distributions are due to primary and radiation scattering contributions. This work presented a method capable of performing dose distributions for nuclear medicine dosimetry by means of Monte Carlo methods. Dedicated subroutines have been developed in order to separately compute primary and scattering contributions to the total absorbed dose, performing particle transport up to 1 keV or least. Preliminarily, the suitability of the calculation method has been satisfactory, being tested for monoenergetic sources, and it was further applied to the characterization of different beta-minus radionuclides of nuclear medicine interests for radioimmunotherapy. (author)

Gamma environmental dosimetry and radon concentration in Venezuela

International Nuclear Information System (INIS)

Sajo B, L.; Greaves E, D.

1996-01-01

The environmental radiation levels have been determined in Venezuela by means of different techniques including the passive dosimeters and the alpha and gamma dosimetry besides the gross alpha/beta counting. The most important conclusion is that the presence of artificial radionuclides (Cesium-137, Beryllium-7 and Cadmium-109) was observed in different environmental samples and in food considered contaminant. The values of gamma levels are between 28 and 40 mGy/day and the mean value of radon concentration in closed environment is 36 Bq/m 3 ; the higher values of a factor 10 have been measured in the Andes region. The 20% of analysed drinking water has a concentration of alpha radionuclides emitters less than 0.005 Bq/l and only the 8% is greater than 0.450 Bq/l. (authors). 6 refs., 1 fig

Internal sources dosimetry

International Nuclear Information System (INIS)

Savio, Eduardo

1994-01-01

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

Radiation fields, dosimetry, biokinetics and biophysical models for cancer induction by ionising radiation 1996-1999. Biokinetics and dosimetry of incorporated radionuclides. Final report

International Nuclear Information System (INIS)

Roth, P.; Aubineau-Laniece, I.; Bailly-Despiney, I.

2000-01-01

The final report 'Biokinetics and Dosimetry of Incorporated Radionuclides' presented here is one part of the 5 individual reports. The work to be carried out within this project is structured into four Work Packages: Workpackage 1 concentrates on ingested radionuclides, considering doses to the GI tract and radionuclide absorption. A major objective is the development of a new dosimetric model of the GI tract, taking account of most recent data on gut transit and dose to sensitive cells. Workpackage 2 seeks to improve and extend biokinetic and dosimetric models for systemic radionuclides. Existing models for adults and children will be extended to other elements and new models will be developed for the embryo and fetus. Workpackage 3 is to improve assessment of localised distribution of dose within tissues at the cellular level for specific examples of Auger emitters and alpha emitting isotopes, in relation to observed effects. The work will include experimental studies of dose/effect relationship and the development of localisation methods. Workpackage 4 concerns the development of computer codes for the new dosimetric models, quality assurance of the models and the calculation of dose coefficients. Formal sensitivity analysis will be used to identify critical areas of model development and to investigate the effects of variability and incertainty in biokinetic parameters. (orig.)

TH-AB-206-01: Advances in Radionuclide Therapy - From Radioiodine to Nanoparticles

International Nuclear Information System (INIS)

Humm, J.

2016-01-01

In the past few decades, the field of nuclear medicine has made long strides with the continued advancement of related sciences and engineering and the availability of diagnostic and therapeutic radionuclides. Leveraging these advancements while combining the advantages of therapeutic and diagnostic radionuclides into one radiopharmaceutical has also created a new subfield “theranostics” in nuclear medicine that has the potential to further propel the field into the future. This session is composed of two talks; one focused on the physics principles of theranostics from properties of beta and alpha emitting radionuclides to dosimetric models and quantification; while the second describes preclinical and clinical applications of theranostics and discusses the challenges and opportunities of bringing them to the clinic. At the end of the session the listener should be able to identify: The different properties of beta and alpha emitting radionuclides Which radionuclides are selected for which nuclear medicine therapies and why How PET can be used to accurately quantify the uptake of tumor targeting molecules How individualized dosimetry can be performed from the management of thyroid cancer to novel radiolabeled antibody therapies Promising pre-clinical radiopharmaceutical pairs in prostate cancer and melanoma. Promising clinical Theranostics in neuroendocrine cancers. Challenges of bringing Theranostics to the clinic. E. Delpassand, RITA Foundation -Houston; SBIR Grant; CEO and share holder of RadioMedix.

TH-AB-206-01: Advances in Radionuclide Therapy - From Radioiodine to Nanoparticles

Energy Technology Data Exchange (ETDEWEB)

Humm, J. [Memorial Sloan-Kettering Cancer Center (United States)

2016-06-15

In the past few decades, the field of nuclear medicine has made long strides with the continued advancement of related sciences and engineering and the availability of diagnostic and therapeutic radionuclides. Leveraging these advancements while combining the advantages of therapeutic and diagnostic radionuclides into one radiopharmaceutical has also created a new subfield “theranostics” in nuclear medicine that has the potential to further propel the field into the future. This session is composed of two talks; one focused on the physics principles of theranostics from properties of beta and alpha emitting radionuclides to dosimetric models and quantification; while the second describes preclinical and clinical applications of theranostics and discusses the challenges and opportunities of bringing them to the clinic. At the end of the session the listener should be able to identify: The different properties of beta and alpha emitting radionuclides Which radionuclides are selected for which nuclear medicine therapies and why How PET can be used to accurately quantify the uptake of tumor targeting molecules How individualized dosimetry can be performed from the management of thyroid cancer to novel radiolabeled antibody therapies Promising pre-clinical radiopharmaceutical pairs in prostate cancer and melanoma. Promising clinical Theranostics in neuroendocrine cancers. Challenges of bringing Theranostics to the clinic. E. Delpassand, RITA Foundation -Houston; SBIR Grant; CEO and share holder of RadioMedix.

Direct internal dosimetry. A new way for routine incorporation monitoring of γ-emitting radionuclides

International Nuclear Information System (INIS)

Doerfel, H.

1996-01-01

The INDOS detector system offers the following advantages with respect to routine incorporation monitoring: The measurement is performed automatically and there is no need for trained staff. The measuring time is short and thus a relative large number of persons may be monitored with a relative high measuring frequency. First estimates of the individual effective dose equivalent rate are available immediately after the measurement. 1) The direct determination of the dose equivalent in principle is more precise than the conventional procedures for internal dosimetry, because (i) the retention of radionuclides in the body may be measured explicitly and (ii) the dependence of the dose equivalent on the body proportions is corrected implicitly. 2) The measuring procedure is comparable to the external dosimetry with respect to accuracy and lower limit of detection. Thus, the results of internal and external dosimetry can be summed up in an easy and reasonable manner. 3) The detector system can be installed in any building; it also can be installed as a mobile unit in a car or a container for long distance transportation by aircraft or train. 4) Last but not least, the cost for monitoring with INDOS is much lower than for the conventional monitoring procedures using whole body counters. (author)

Statistical construction of a Japanese male liver phantom for internal radionuclide dosimetry

International Nuclear Information System (INIS)

Mofrad, F. B.; Zoroofi, R. A.; Tehrani-Fard, A. A.; Akhlaghpoor, S.; Hori, M.; Chen, Y. W.; Sato, Y.

2010-01-01

A computational framework is presented, based on statistical shape modelling, for construction of race-specific organ models for internal radionuclide dosimetry and other nuclear-medicine applications. This approach was applied to the construction of a Japanese liver phantom, using the liver of the digital Zubal phantom as the template and 35 liver computed tomography (CT) scans of male Japanese individuals as a training set. The first step was the automated object-space registration (to align all the liver surfaces in one orientation), using a coherent-point-drift maximum-likelihood alignment algorithm, of each CT scan-derived manually contoured liver surface and the template Zubal liver phantom. Six landmark points, corresponding to the intersection of the contours of the maximum-area sagittal, transaxial and coronal liver sections were employed to perform the above task. To find correspondence points in livers (i.e. 2000 points for each liver), each liver surface was transformed into a mesh, was mapped for the parameter space of a sphere (parameterization), yielding spherical harmonics (SPHARMs) shape descriptors. The resulting spherical transforms were then registered by minimising the root-mean-square distance among the SPHARMs coefficients. A mean shape (i.e. liver) and its dispersion (i.e. covariance matrix) were next calculated and analysed by principal components. Leave-one-out-tests using 5-35 principal components (or modes) demonstrated the fidelity of the foregoing statistical analysis. Finally, a voxelisation algorithm and a point-based registration is utilised to convert the SPHARM surfaces into its corresponding voxelised and adjusted the Zubal phantom data, respectively. The proposed technique used to create the race-specific statistical phantom maintains anatomic realism and provides the statistical parameters for application to radionuclide dosimetry. (authors)

Primary and scattering contributions to beta scaled dose point kernels by means of Monte Carlo simulations

International Nuclear Information System (INIS)

Valente, Mauro; Botta, Francesca; Pedroli, Guido

2012-01-01

Beta-emitters have proved to be appropriate for radioimmunotherapy. The dosimetric characterization of each radionuclide has to be carefully investigated. One usual and practical dosimetric approach is the calculation of dose distribution from a unit point source emitting particles according to any radionuclide of interest, which is known as dose point kernel. Absorbed dose distributions are due to primary and radiation scattering contributions. This work presented a method capable of performing dose distributions for nuclear medicine dosimetry by means of Monte Carlo methods. Dedicated subroutines have been developed in order to separately compute primary and scattering contributions to the total absorbed dose, performing particle transport up to 1 keV or least. Preliminarily, the suitability of the calculation method has been satisfactory, being tested for monoenergetic sources, and it was further applied to the characterization of different beta-minus radionuclides of nuclear medicine interests for radioimmunotherapy. (author)

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

Method of measuring the disintegration rate of a beta-emitting radionuclide in a liquid sample

International Nuclear Information System (INIS)

Horrocks, D.L.

1980-01-01

A novel liquid scintillation counting method of measuring the disintegration rate of a beta-emitting radionuclide is described which involves counting the sample at at least two different quench levels. (UK)

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.

Measurement of beta emitting radionuclides in dose calibrators routinely used in nuclear medicine departments

International Nuclear Information System (INIS)

Tastan, S.; Soylu, A.; Kucuk, O.; Ibis, E.

2004-01-01

Full text: Radionuclides for diagnostics purposes like Tc-99m, Tl-201, Ga-67 and In-111 are measured by using ionization type of dose calibrators. Therapeutic radionuclides, which emit both beta and gamma rays are detected by the same type of dose calibrators. Other therapeutic products like Y-90, P-32 and Sr-89 are pure beta emitters and they are gaining wider utility because various new therapy radiopharmaceuticals are being developed. The type of container material, like glass or plastic, may seriously affect radioactivity measurement due to attenuation, Since it is crucial to give the exact amount of radioactivity to the patient for therapy purposes, dedicated dose calibrators are specially manufactured for the measurement of these radionuclides. But these measuring systems are not widely available in nuclear medicine centers where therapy is applied to the patient. It is a known fact that dose calibrators routinely used in nuclear medicine departments can be calibrated for vials and syringes using standard sources of the same radioisotope. The method of calibration of Y-90 measurement for two ionization chamber dose calibrators available in the institute will be summarized in this presentation

Measurement of beta emitting radionuclides in dose calibrators routinely used in nuclear medicine departments

International Nuclear Information System (INIS)

Tastan, S.; Soylu, A.; Kucuk, O.; Ibis, E.

2004-01-01

Radionuclides for diagnostics purposes like Tc-99m, Tl-201, Ga-67 and In-111 are measured by using ionization type of dose calibrators. Therapeutic radionuclides, which emit both beta and gamma rays are detected by the same type of dose calibrators. Other therapeutic products like Y-90, P-32 and Sr-89 are pure beta emitters and they are gaining wider utility because various new therapy radiopharmaceuticals are being developed. The type of container material, like glass or plastic, may seriously affect radioactivity measurement due to attenuation, Since it is crucial to give the exact amount of radioactivity to the patient for therapy purposes, dedicated dose calibrators are specially manufactured for the measurement of these radionuclides. But these measuring systems are not widely available in nuclear medicine centers where therapy is applied to the patient. It is a known fact that dose calibrators routinely used in nuclear medicine departments can be calibrated for vials and syringes using standard sources of the same radioisotope. The method of calibration of Y-90 measurement for two ionization chamber dose calibrators available in the institute will be summarized in this presentation. (author)

Dosimetry of internal emitters - quo vadis?

International Nuclear Information System (INIS)

Reddy, A.R.; Nagaratnam, A.; Jain, S.C.; Gupta, M.M.; Mehta, S.C.

1999-01-01

The dosimetry of internally administered radiopharmaceuticals in nuclear medicine procedures using MIRD formalisms and dosimetry in the case of intakes of radionuclides and ICRP methodology for the purpose of radiological protection are well established working practices. It should, however, be remembered that dose or dose coefficients calculated refer to a reference individual, defined in terms of a mathematical phantom established on the basis of certain biokinetic reference parameters. The reference individual represents a typical caucasian adult of West Europe or North American origin. Recently, some attempts have been made to define a Reference Asian and a Reference Indian individual and to assess the effects of anatomical differences and changes in the biokinetics of radiopharmaceuticals and other radionuclides in these different reference individuals on the estimation of dose and dose coefficients in relation to the intake of internal radionuclides. The assessment of doses to the embryo/fetus due to intake of radionuclides by pregnant women, local dose estimates, microdosimetry, radiobiology and radiation protection aspects relating to Auger electron emitters represent other areas of active research in the area of dosimetry of internal emitters. The present review summarises these different aspects of work. (orig.) [de

Monte Carlo verification of polymer gel dosimetry applied to radionuclide therapy: a phantom study

International Nuclear Information System (INIS)

Gear, J I; Partridge, M; Flux, G D; Charles-Edwards, E

2011-01-01

This study evaluates the dosimetric performance of the polymer gel dosimeter 'Methacrylic and Ascorbic acid in Gelatin, initiated by Copper' and its suitability for quality assurance and analysis of I-131-targeted radionuclide therapy dosimetry. Four batches of gel were manufactured in-house and sets of calibration vials and phantoms were created containing different concentrations of I-131-doped gel. Multiple dose measurements were made up to 700 h post preparation and compared to equivalent Monte Carlo simulations. In addition to uniformly filled phantoms the cross-dose distribution from a hot insert to a surrounding phantom was measured. In this example comparisons were made with both Monte Carlo and a clinical scintigraphic dosimetry method. Dose-response curves generated from the calibration data followed a sigmoid function. The gels appeared to be stable over many weeks of internal irradiation with a delay in gel response observed at 29 h post preparation. This was attributed to chemical inhibitors and slow reaction rates of long-chain radical species. For this reason, phantom measurements were only made after 190 h of irradiation. For uniformly filled phantoms of I-131 the accuracy of dose measurements agreed to within 10% when compared to Monte Carlo simulations. A radial cross-dose distribution measured using the gel dosimeter compared well to that calculated with Monte Carlo. Small inhomogeneities were observed in the dosimeter attributed to non-uniform mixing of monomer during preparation. However, they were not detrimental to this study where the quantitative accuracy and spatial resolution of polymer gel dosimetry were far superior to that calculated using scintigraphy. The difference between Monte Carlo and gel measurements was of the order of a few cGy, whilst with the scintigraphic method differences of up to 8 Gy were observed. A manipulation technique is also presented which allows 3D scintigraphic dosimetry measurements to be compared to polymer

Skin dose assessment in routine personnel beta/gamma dosimetry

International Nuclear Information System (INIS)

Christensen, P.

1980-01-01

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

Technical basis for internal dosimetry at Hanford

Energy Technology Data Exchange (ETDEWEB)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ({sup 58}Co, {sup 60}Co, {sup 54}Mn, and {sup 59}Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs.

Technical basis for internal dosimetry at Hanford

Energy Technology Data Exchange (ETDEWEB)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products (/sup 58/Co, /sup 60/Co, /sup 54/Mn, and /sup 59/Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs.

Technical basis for internal dosimetry at Hanford

International Nuclear Information System (INIS)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs

Technical basis for internal dosimetry at Hanford

International Nuclear Information System (INIS)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs

Evaluation of selected predictive models and parameters for the environmental transport and dosimetry of radionuclides

International Nuclear Information System (INIS)

Miller, C.W.; Dunning, D.E. Jr.; Etnier, E.L.; Hoffman, F.O.; Little, C.A.; Meyer, H.R.; Shaeffer, D.L.; Till, J.E.

1979-07-01

Evaluations of selected predictive models and parameters used in the assessment of the environmental transport and dosimetry of radionuclides are summarized. Mator sections of this report include a validation of the Gaussian plume disperson model, comparison of the output of a model for the transport of 131 I from vegetation to milk with field data, validation of a model for the fraction of aerosols intercepted by vegetation, an evaluation of dose conversion factors for 232 Th, an evaluation of considering the effect of age dependency on population dose estimates, and a summary of validation results for hydrologic transport models

Quantitative imaging for clinical dosimetry

Energy Technology Data Exchange (ETDEWEB)

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

2006-12-20

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

Methodology for quantification of radionuclides used in therapy by bioanalysis 'in vitro'

International Nuclear Information System (INIS)

Juliao, Ligia M.Q.C.; Sousa, Wanderson O.; Mesquita, Sueli A.; Santos, Maristela S.; Oliveira, S.M. Velasques de

2008-01-01

In Brazil, the radionuclides used for therapy are 131 ; 153 Sm, 90 Y and 177 Lu, under routine or experimentally. The quantification of the radiopharmaceutical activity excreted by the patient through the bioassay method, can be an important tool for individualized dosimetry, aiming the planning of subsequent therapies. The Bioanalysis In Vitro Laboratory (LBIOVT) of the Service of Individual monitoring (SEMIN) of the Institute for Radiation Protection and Dosimetry (IRD/CNEN-RJ), Brazil, has equipment and procedures for gamma and beta spectrometry. These detection systems are calibrated in energy and efficiency, and used standard reference sources provided by the National Laboratory of Metrology of Ionizing Radiation (LMNRI/IRD/CNEN-RJ). The LBIOVT Quality System follows the guidelines of the ISO-ABNT-17025 standard and annually, the laboratory participates in national (PNI) and international (PROCORAD). With respect to the excreta samples from patients, these are collected immediately after administration of the radiopharmaceutical. During the first 24 hours, they are collected with the patient hospitalized, and depending upon the physical half-life of the radionuclide can also be collected in the patient's home. Both in hospital and at home, the excreta is handled, stored and transported in accordance with standards for clinical research, radiation protection and transport of radioactive and biological materials. The specific activity radionuclide is referenced to the date and time of collection, allowing further evaluation of biological individual half-life. The care with the registration of excreted volumes as well as possible loss of excreta during collection, may interfere with the interpretation of the measures, since the results are provided in specific activity (Bq / L). Regarding the bioassay laboratory, these results are reliable when the laboratory is certified and participates in intercomparison programs of measures and methods. The laboratory

Radionuclides and the normal bone scan

International Nuclear Information System (INIS)

Mettler, F.A. Jr.; Monsein, L.; Rosenberg, R.D.

1988-01-01

Recently, Eisenhut and co-workers have described development of iodine-131 labeled diphosphonates for palliative treatment of bone metastases. The compound labeled was alpha-amino (4-hydroxybenzylidene) diphosphonate (BDP3). Other beta-emitting radionuclides have been used for treatment of intractable pain secondary to bone metastases. These include strontium-89, which has some difficulties, particularly in terms of disposal of the excretions due to the long physical half-life of the life of the radionuclide. Yttrium-90 has also been used but has a relatively high hepatic uptake. Phosphorus-32 labeled compounds have also been used. Although palliation has been described, bone marrow depression has also occurred. Rhenium-186 also has been suggested, however, high renal uptake is a problem. At present, the iodine-131 labeled BDP3 appears to be the best of the available therapeutic radiopharmaceuticals. One of the major disadvantages in use of this compound is the production of gamma photons. While undesirable from a dosimetry viewpoint, gamma photons do, however, permit imaging if desired

Calibration of radionuclides with decay trough beta emission or electron capture by liquid scintillation technique; Calibracao de radionuclideos que decaem por emissao beta ou por captura eletronica pela tecnica de cintilacao liquida

Energy Technology Data Exchange (ETDEWEB)

Loureiro, Jamir dos Santos

2000-02-01

In this work is reported a methodology a methodology for pure beta and electron capture radionuclides standardization, suing liquid scintillation technique. In this sense the CIEMAT/NIST method, recently utilized by international laboratories, was implemented and the lack in the Laboratorio Nacional das Radiacoes Ionizantes - LNMRI, of the Comissao Nacional de Energia Nuclear - CNEN, for adequate methodology to standardize this kind if radionuclides was filled, fact that was not present with alpha and gamma radionuclides. The implementation procedure evaluation was provided by concentration activity determination of the following radionuclides: {sup 14} C and {sup 90} Sr, pure beta emitters; {sup 55} Fe, electron capture decay; {sup 204} Tl, electron capture and beta decay and {sup 60} Co, beta-gamma emitter. In this way, a careful analysis of the implementation procedure with these radionuclides types, ranging on a broad energy spectral, was possible. To check the calibration results, intercomparisons among our measurements of these radionuclides and the reference values of the CIEMAT/Spain laboratory were provided. To check the calibration results, intercomparisons among our measurements of these radionuclides and the reference values of the CIEMAT/Spain laboratory were provided. Besides this intercomparisons, one was provided with a {sup 204} Tl solution, utilized in the international comparison recently promoted by BIPM, and another one with a {sup 60} C solution calibrated in LNMRI/CNEN previously by a relative calibration system, with a well type pressurized ionization chamber, and an absolute beta-gamma coincidence system, with a pill-box type proportional counter 4 {pi} geometry, coupled with a scintillator system with a sodium iodide cristal of 4x4 inches. The comparisons among LNMRI/CNEN results and the reference values, showed a small deviation of 1,32% for {sup 14} C, 0,40% for {sup 60} Co, 1,12% for {sup 55} Fe, 0,10% for {sup 90} Sr and 0,73% for {sup

Comparison of bone tumors induced by beta-emitting or alpha-emitting radionuclides: Schemes of pathogenesis

International Nuclear Information System (INIS)

Gillett, N.A.; Muggenburg, B.A.; Pool, R.R.; Hahn, F.F.

1988-01-01

Life-span studies in Beagle dogs have documented the occurrence of bone tumors following exposure to bone-seeking alpha- or beta-emitting radionuclides administered by different routes of exposure. Bone tumors from dogs in four different life-span studies were analyzed according to tumor phenotype, tumor location, radiographic appearance, incidence of metastasis, and association with radiation osteodystrophy. Marked differences in these parameters were observed that did not correlate with differences in radionuclide type, route of exposure, or duration of radionuclide uptake. Radiation osteodystrophy, which is postulated to be a preneoplastic lesion, was not a significant component in one of the studies. Analysis of the data from these four studies suggests that at least two different mechanisms of bone tumor pathogenesis occur for radiation-induced bone tumors. (author)

Modeling the effects of repeated systemic administrations of small activity amounts In radionuclide therapy with beta emitters

International Nuclear Information System (INIS)

Calderon, Carlos; Gonzalez, Joaquin; Cepero, Janet; Colom, Camila; Rodriguez, Juan C.

2008-01-01

Full text: Good results for radionuclide therapy treatments where repeated short time spaced systemic injection of small activity amounts are given have been reported. Bone marrow and kidneys are usually considered as dose-limiting organs in radionuclide therapy. The treatments in radionuclide therapy with repeated administration could be optimized if irradiation effects in those one might be estimated. Xeno-grafted mice is the often biological model used during the evaluation of candidates for radionuclide therapy. A mathematical model of tumor cell kinetics was combined with another one reported for marrow cell kinetics which allows the calculation of marrow cell survival and proliferation in response to different irradiation schemes. Radionuclide therapy treatment with repeated administrations with radiopharmaceuticals labeled with beta emitters were simulated. The effects on fast-growing and slow-growing tumors were evaluated, as well as radiosensitive and radioresistant tumors. For more realistic estimation of absorbed dose in mice organs the cross-irradiation due to high energy beta particles was included into the MIRD's formula. Tumor and kidneys responses to the irradiation were estimated on the linear-quadratic model framework which was adapted for a multi-exponential dose rate function describing radionuclide therapy treatments with repeated administrations. Published values for murine tumors kinetics, marrows cellular turnover rates and radiosensitivities were used during the calculations. Iso-effective schemes were also determined varying the interval between fractions and the number of administration. For a given tolerated level of thrombocytopenia and absorbed dose in kidneys an optimal regime of radionuclide therapy with repeated administration could be found. The mathematical model presented here allows the prediction of the nadir and duration of thrombocytopenia, the effects on kidneys and the tumor cell response to various treatment schemes

Special workshop on lung dosimetry

International Nuclear Information System (INIS)

Fisher, D.R.

1983-01-01

A Special Workshop on Lung Dosimetry was convened in Salt Lake City, Utah, on April 21-22, 1982, to stimulate the use of improved radiation dosimetry and to formulate a stronger basis for dose-response relationships for inhaled radionuclides. The two-day workshop was held in conjunction with the 30th Annual Meeting of the Radiation Research Society. Publication is planned

Beta-ray depth dose in tissue equivalent material due to gaseous radioactive effluents from nuclear power plants

International Nuclear Information System (INIS)

Schadt, W.W.

1978-01-01

The magnitude of the absorbed dose to skin from beta particles emitted by the radionuclides in gaseous effluents from boiling water nuclear power reactors is investigated in this dissertation. Using the radionuclide release patterns of F. Brutschy and the beta dosimetry methods of M. Berger, an equation is derived which gives the dose rate in rads per day when the total radionuclide concentration is one microcurie per gram of air. The coefficients in the equation are presented for a wide range of reactor gas hold-up times (48 minutes to 6 days) and plume environmental transit time (0.5 to 60 minutes). The beta dose rates at the skin surface are found to range from 3.9 to 26.7 rads per day. An upper limit of the relative standard deviation in the dose rate is estimated to be 30 percent. The techniques used to develop the equation are applied to data from the Millstone Nuclear Power Station obtained during the summer of 1972. The beta dose at a site 1.7 miles from the reactor is determined to have been 675 millirads per year at the skin surface and 476 millirads per year at a depth of 200 micrometers. At a site 5.1 miles from the reactor these dose rates were 138 and 100 millirads per year respectively

Internal Dosimetry Monitoring- Detection Limits for a Selected Set of Radionuclides and Their Translation Into Committed Effective Dose

International Nuclear Information System (INIS)

Brandl, A.; Hrnecek, E.; Steger, F.

2004-01-01

To harmonize the practice of internal dosimetry monitoring across the country, the Austrian Standards Institute is currently drafting a new set of standards which are concerned with occupational incorporation monitoring of individuals handling non-sealed radioactive material. This set of standards is expected to consist of three parts discussing the general necessity and frequency, the requirements for monitoring institutions, and the determination and rigorous calculation of committed effective dose after incorporation of radioactive material, respectively. Considerations of the requirements for routine monitoring laboratories have led to an evaluation of the detection limits for routine monitoring equipment. For a selected set of radionuclides, these detection limits are investigated in detail. The main emphasis is placed on the decay chains of naturally occurring radionuclides showing some significant potential for being out of equilibrium due to chemical processes in certain mining industries. The radionuclides considered in this paper are 226Ra, 228Ra, 228Th, 232Th, 234U, 235U, and 238U. Given the routine monitoring intervals of the Austrian Standard, these detection limits are translated into information on committed effective dose. This paper investigates whether routine monitoring equipment is sufficient to ensure compliance with EC directive 96/29/Euratom for this selected set of radionuclides. (Author) 9 refs

Cellular dosimetry in nuclear medicine imaging: training

International Nuclear Information System (INIS)

Gardin, I.; Faraggi, M.; Stievenart, J.L.; Le Guludec, D.; Bok, B.

1998-01-01

The radionuclides used in nuclear medicine imaging emit not only diagnostically useful photons, but also energy electron emissions, responsible for dose heterogeneity at the cellular level. The mean dose delivered to the cell nucleus by electron emissions of 99m Tc, 123 I, 111 In, 67 Ga, and 201 Tl, has been calculated, for the cell nucleus, a cytoplasmic and a cell membrane distribution of radioactivity. This model takes into account both the self-dose which results from the radionuclide located in the target cell, and the cross-dose, which comes from the surrounding cells. The results obtained by cellular dosimetry (D cel ) have been compared with those obtained with conventional dosimetry (D conv ), by assuming the same amount of radioactivity per cell. Cellular dosimetry shows, for a cytoplasmic and a cell membrane distributions of radioactivity, that the main contribution to the dose to the cell nucleus, comes from the surrounding cells. On the other hand, for a cell nucleus distribution of radioactivity, the self-dose is not negligible and may be the main contribution. The comparison between cellular and conventional dosimetry shows that D cel /D conv ratio ranges from 0.61 and O.89, in case of a cytoplasmic and a cell membrane distributions of radioactivity, depending on the radionuclide and cell dimensions. Thus, conventional dosimetry slightly overestimates the mean dose to the cell nucleus. On the other hand, D cel /D conv ranges from 1.1 to 75, in case of a cell nucleus distribution of radioactivity. Conventional dosimetry may strongly underestimates the absorbed dose to the nucleus, when radioactivity is located in the nucleus. The study indicates that in nuclear medicine imaging, cellular dosimetry may lead to a better understanding of biological effects of radiopharmaceuticals. (authors)

Assessment and management of risks associated with exposures to Auger- and beta-emitting radionuclides. Recommendations and proposals for lines of research; L'evaluation et la gestion des risques associes aux expositions aux radionucleides emetteurs Auger et beta. Avis et propositions de pistes de recherche

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

The assessment and management of risks associated with exposures to ionising radiation are defined by the general radiological protection system, proposed by the International Commission on Radiological Protection (ICRP). This system is regarded by a large majority of users as a robust system with well-established relevance for the management and prevention of exposures. Despite this, there are a number of dissenting voices, claiming that this system is not suitable for estimating the risks resulting from internal exposures, particularly when incorporated radionuclides decay, emitting electrons. Criticisms of the system particularly pertain to Auger- and beta-emitting radionuclides, the intake of which can occur during environmental and industrial exposures or, simply, during a medical use of ionising radiation for diagnostic or therapeutic purposes. These debates result from a lack of data in the fields of dosimetry and toxicology of these radionuclides. Auger and beta emitters can be distributed preferentially in certain tissue structures and even in certain cellular organelles, according to the vector with which they are associated. Given the limited range of electrons in matter, this heterogeneous distribution can generate highly localised energy depositions, not taken into account in conventional dosimetry methods, which make the assumption of uniform energy depositions. These specific physical and biochemical features of some of these radionuclides seem to influence their cellular toxicity directly. It is thus established that intranuclear distribution of iodine-125 is more effective for the induction of mutations or even cell death than a cytosolic distribution. This point is explained by the very short range of Auger electrons in matter (around a few dozen nm), which, in the case of an intranuclear distribution, would deliver all of their energy in the vicinity of the DNA, which, if affected, would be detrimental to the survival of the cell. The observation

Hanford internal dosimetry program manual

International Nuclear Information System (INIS)

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

1989-10-01

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

Polymer gel dosimetry

Energy Technology Data Exchange (ETDEWEB)

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

2010-03-07

Polymer gel dosimeters are fabricated from radiation sensitive chemicals which, upon irradiation, polymerize as a function of the absorbed radiation dose. These gel dosimeters, with the capacity to uniquely record the radiation dose distribution in three-dimensions (3D), have specific advantages when compared to one-dimensional dosimeters, such as ion chambers, and two-dimensional dosimeters, such as film. These advantages are particularly significant in dosimetry situations where steep dose gradients exist such as in intensity-modulated radiation therapy (IMRT) and stereotactic radiosurgery. Polymer gel dosimeters also have specific advantages for brachytherapy dosimetry. Potential dosimetry applications include those for low-energy x-rays, high-linear energy transfer (LET) and proton therapy, radionuclide and boron capture neutron therapy dosimetries. These 3D dosimeters are radiologically soft-tissue equivalent with properties that may be modified depending on the application. The 3D radiation dose distribution in polymer gel dosimeters may be imaged using magnetic resonance imaging (MRI), optical-computerized tomography (optical-CT), x-ray CT or ultrasound. The fundamental science underpinning polymer gel dosimetry is reviewed along with the various evaluation techniques. Clinical dosimetry applications of polymer gel dosimetry are also presented. (topical review)

Beta Radiation Exposure of Personnel in Radiosynovectomy and at the Production of Eye Application

International Nuclear Information System (INIS)

Mielcarek, J.; Barth, I.

2001-01-01

Full text: Beta radionuclides are increasingly used in nuclear medicine therapy. In a study of exposure at working places with supposed enhanced radiation risk the followings are monitored: 1. Production of eye applicators ( 106 Ru/ 106 Rh) for therapy of intraocular tumours. During the processes radionuclides are used in sealed and unsealed form. 2. Radiosynovectomy (RSO). This therapy is often used in treatment of inflammatory joint disease. The radionuclides 169 Er, 186 Re and 90 Y are applied in form of radioactive solutions. A complex of problems has to be solved here: Handling of high activities (several GBq per day), very small distances between source and skin, high risk of skin contamination, unsatisfactory dose measurement techniques. In our investigations high sensitive thin thermoluminescence dosimeters (LiF:Mg,Cu,P) were used to determine the skin dose of the hands especially fingertips during preparation and application of the radioactive substances at several institutions. During production of eye applicators we found hand doses essentially below the annual limit. But direct radiation at RSO caused more than 100 mSv at the fingertips per working day in some cases. Even higher doses (more than 50% of the annual limit for skin during a working day) were caused by contamination of the hands. By use of manipulators, wearing of appropriate protection gloves and by improvement of directions for work, the radiation exposure could be reduced dramatically. Consequences for individual beta dosimetry and with respect to license of use of beta radionuclides are discussed. (author)

Radionuclide, scintillation cocktail and chemical/color quench influence on discriminator setting in gross alpha/beta measurements by LSC

International Nuclear Information System (INIS)

Stojković, Ivana; Tenjović, Branislava; Nikolov, Jovana; Todorović, Nataša

2015-01-01

Gross alpha/beta measurements in drinking waters enable radiochemical composition analysis in environmental studies providing efficient screening method that can indicate whether water contains elevated levels of any radionuclide. Routine gross alpha/beta activity monitoring in drinking waters has been carried out for a few years in laboratory for low-level radioactivity measurements in Novi Sad according to ASTM method, performing measurements on liquid scintillation counter Quantulus 1220 which can simultaneously generate alpha/beta spectra of samples by Pulse Shape Analysis (PSA circuit). In this paper, PSA discriminator impact was investigated to ensure obtaining of accurate and reliable alpha/beta activities. One novelty of presented work is PSA parameter setup with two combinations of radionuclides ( 241 Am, 226 Ra and 90 Sr/ 90 Y) with varying activity concentrations. Performed experiments also make contribution to investigations on the manner in which chemical and color quench affect optimal PSA parameter setting and further on, their altogether influence on gross alpha/beta activity measurements. Nitromethane, 15.8 M nitric acid and water, as well as yellow and yellow-orange dye, were used as quenching agents in order to test PSA/interference factor behavior in the presence of quenchers with different quenching strengths. Variation of PSA setting in quenched samples with two different commercially available cocktails (Ultima Gold LLT and OptiPhase HiSafe 3) was also tested. Lastly, application i.e. assessment of obtained PSA-SQP(E) correlation on the obtained results of activity concentrations of few artesian well water samples and colored spiked samples, based on the measured SQP(E) value of samples, has been demonstrated. - Highlights: • Thorough study on influence of relevant factors on optimal PSA level in gross alpha/beta measurements in waters is presented. • Experiments were performed on liquid scintillation counter Quantulus 1220™ according

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

International Nuclear Information System (INIS)

Wernli, C.; Kahilainen, J.

2001-01-01

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

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

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

Radiotherapy Based On α Emitting Radionuclides: Geant4 For Dosimetry And Micro-/Nano-Dosimetry

International Nuclear Information System (INIS)

Guatelli, Susanna

2013-01-01

Possible physics approaches to evaluate the efficacy of TAT are dosimetry, microdosimetry and nanodosimetry. Dosimetry is adequate when mean absorbed dose to a macroscopic target volume is important to understand the biological effect of radiation. General purpose Monte Carlo (MC) codes, based on condensed history approach, are a very useful, cost effective tool to solve dosimetric problems. The condensed history approach is based on the use of multiple scattering theories to calculate the energy losses and angular changes in the direction of the particle. The short α particle range and high LET make the microdosimetric approach more suitable than dosimetry to study TAT from first physics principles, as this approach takes into account the stochastic nature of energy deposition at cellular level

Influence of radiation-dose pattern from inhaled beta--gamma-emitting radionuclides on canine peripheral lymphocytes

International Nuclear Information System (INIS)

Jones, R.K.; Boecker, B.B.; Pickrell, J.A.; Hobbs, C.H.; McClellan, R.O.

1976-01-01

As part of studies assess the biological hazards associated with inhaled radionuclides, periodic hematologic evaluations were performed on beagle dogs given a single nose-only exposure to aerosols of beta--gamma-emitting isotopes. The physical form and specific radionuclides selected produced radiation-dose patterns representative of those which might be encountered in the event of human accidental exposures. Dogs received graded lung burdens of either 90 Y, 91 Y, 144 Ce, or 90 Sr, each in fused clay. Differences in the effective half-lives of these radionuclides resulted in a spectrum of cumulative radiation doses to lung delivered at a variety of dose rates. Since the form in which the radionuclides were inhaled was relatively insoluble, the lung and intrathoracic tissues represented the primary recipient of the dose. Regardless of the effective half-life of radionuclide retention, a dose-related depression of peripheral lymphocytes was observed at various times after inhalation exposure. The time at which maximum depression and subsequent recovery occurred, however, was most directly related to the effective half-life of the radionuclide. Of special interest was the persistence of lymphopenia through 2 1 / 2 years after exposure to 144 Ce and 90 Sr in fused clay where, other than tracheobronchial lymph nodes, the lymphoid tissue received very little radiation dose. The possible mechanisms responsible for lymphocyte depression from these various radiation-dose patterns are discussed

Preclinical animal research on therapy dosimetry with dual isotopes

NARCIS (Netherlands)

M.W. Konijnenberg (Mark); M. de Jong (Marion)

2011-01-01

textabstractPreclinical research into radionuclide therapies based on radiation dosimetry will enable the use of any LET-equivalent radionuclide. Radiation dose and dose rate have significant influence on dose effects in the tumour depending on its radiation sensitivity, possibilities for repair of

Dosimetric studies of anti-CD20 labeled with therapeutic radionuclides at IPEN/CNEN-SP

Energy Technology Data Exchange (ETDEWEB)

Barrio, G.; Dias, C.R.B.R.; Osso Junior, J.A., E-mail: gracielabarrio@gmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2012-07-01

Radioimmunotherapy (RIT) makes use of monoclonal antibodies (MAb) labeled with alpha/beta radionuclides for therapeutical purposes, leading to tumor irradiation and destruction, preserving the normal organs on the radiation excess. The therapeutic activity to be injected in a specific patient is based on information obtained in dosimetric studies. Beta emitting radionuclides such as {sup 131}I, {sup 188}Re, {sup 90}Y, {sup 177}Lu and {sup 166}Ho are useful for the development of therapeutic radiopharmaceuticals. Anti-CD20 (Rituximab) is a chimeric MAb directed against antigen surface CD20 on B-lymphocytes, used in non-Hodgkin lymphoma treatment (NHL). The association with beta radionuclides have shown greater therapeutic efficacy. Currently, two radiopharmaceuticals with Anti-CD20 for radioimmunotherapy have FDA approval for NHL treatment: {sup 131}I-AntiCD20 (Bexar) and {sup 90}Y-AntiCD20 (Zevalin). Techniques for the radiolabeling of {sup 188}Re-antiCD20 have been recently developed by IPEN-CNEN/SP in order to evaluate the clinical use of this radionuclide in particular. The use of {sup 188}Re (T{sub 1/2} 17h) produced by the decay of {sup 188}W (T{sub 1/2} 69d), from an {sup 188}W/{sup 188}Re generator system, has represented an alternative to RIT. Beyond high energy beta emission for therapy, {sup 188}Re also emits gamma rays (155keV) suitable for image. The aim of this new project is to compare the labeling of anti-CD20 with {sup 188}Re with the same MAb labeled with {sup 131}I, {sup 177}Lu, {sup 90}Y and even {sup 99m}Tc. The first step in this project is the review of the published data available concerning the labeling of this MAb with different radionuclides, along with data obtained at IPEN, taking into account labeling procedures, labeling yields, reaction time, level and kind of impurities and biodistribution studies. The pharmacokinetic code will be developed in Visual Studio.NET platform through VB.NET and C{sup ++} for biodistribution and dosimetric

Rapid method of identification of {beta}-ray emitters and of {beta}-radioactive impurity dosage (1961); Methode rapide d'identification des emetteurs-{beta} et de dosage d'impuretes radioactives-{beta} (1961)

Energy Technology Data Exchange (ETDEWEB)

Le Gallic, Y; Legrand, J; Grinberg, B [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1961-07-01

We describe a simple method of radioactive analysis, which allows an accurate determination of maximal energies of {beta}-emitters, and detection and titration of radioactive impurities in radionuclides as well. The method described, which uses a plastic scintillator, is based on the fact that the curve obtained by plotting the number of pulses measured against the threshold is a straight line, in the case of pure {beta}-emitters. We then derive a simple relation between the data of this straight line and the maximal energy of the {beta}-spectrum of the radionuclide under consideration. (authors) [French] Description d'une methode simple d'analyse radioactive, permettant de determiner avec precision l'energie maximum des emetteurs-{beta}, ainsi que de deceler et de doser les impuretes radioactives dans un radionuclide. La technique decrite utilise un scintillateur plastique. On exploite le fait que la courbe du nombre d'impulsions mesurees, en fonction du seuil de discrimination, est une droite, pour un emetteur-{beta} pur. Une relation simple entre les caracteristiques de cette droite et l'energie maximum du spectre-{beta} du radionuclide, correspondant, a ete etablie. (auteurs)

Current internal-dosimetry practices at US Department of Energy facilities

International Nuclear Information System (INIS)

Traub, R.J.; Murphy, B.L.; Selby, J.M.; Vallario, E.J.

1985-04-01

The internal dosimetry practice at DOE facilities were characterized. The purpose was to determine the size of the facilities' internal dosimetry programs, the uniformity of the programs among the facilities, and the areas of greatest concern to health physicists in providing and reporting accurate estimates of internal radiation dose and in meeting proposed changes in internal dosimetry. The differences among the internal-dosimetry programs are related to the radioelements in use at each facility and, to some extent, the number of workers at each facility. The differences include different frequencies in the use of quality control samples, different minimum detection levels, different methods of recording radionuclides, different amounts of data recorded in the permanent record, and apparent differences in modeling the metabolism of radionuclides within the body. Recommendations for improving internal-dosimetry practices include studying the relationship between air-monitoring/survey readings and bioassay data, establishing uniform methods for recording bioassay results, developing more sensitive direct-bioassay procedures, establishing a mechanism for sharing information on internal-dosimetry procedures among DOE facilities, and developing mathematical models and interactive computer codes that can help quantify the uptake of radioactive materials and predict their distribution in the body. 19 refs., 8 tabs

Internal dosimetry - its evolution and new trends

International Nuclear Information System (INIS)

Bertelli, Luiz

1997-01-01

This paper presents some discussions on the developments and trends of metabolic models and dosimetry and their associated parameters, which have been adopted by ICRP to evaluate intakes of radionuclides

Manual of bioassay procedures for radionuclides

International Nuclear Information System (INIS)

Pleskach, S.; Petkau, A.

1986-06-01

A monitoring program is described by which atomic radiation workers ar monitored for internal contamination with radionuclides in the workplace. The program involves analytical procedures for measuring alpha, beta and gamma activity in biological specimens, usually urine. Radionuclides are identified by their characteristic radiation using liquid scintillation counting, and alpha, beta and gamma spectrometry. Examples of calculating the minimum detectable activity for specific radionuclides are given and used to derive call-in-criteria in accordance with which the different groups of workers are monitored each month

Preclinical animal research on therapy dosimetry with dual isotopes

International Nuclear Information System (INIS)

Konijnenberg, Mark W.; Jong, Marion de

2011-01-01

Preclinical research into radionuclide therapies based on radiation dosimetry will enable the use of any LET-equivalent radionuclide. Radiation dose and dose rate have significant influence on dose effects in the tumour depending on its radiation sensitivity, possibilities for repair of sublethal damage, and repopulation during or after the therapy. Models for radiation response of preclinical tumour models after peptide receptor radionuclide therapy based on the linear quadratic model are presented. The accuracy of the radiation dose is very important for observation of dose-effects. Uncertainties in the radiation dose estimation arise from incomplete assay of the kinetics, low accuracy in volume measurements and absorbed dose S-values for stylized models instead of the actual animal geometry. Normal dose uncertainties in the order of 20% might easily make the difference between seeing a dose-effect or missing it altogether. This is true for the theoretical case of a homogeneous tumour type behaving in vivo in the same way as its cells do in vitro. Heterogeneity of tumours induces variations in clonogenic cell density, radiation sensitivity, repopulation capacity and repair kinetics. The influence of these aspects are analysed within the linear quadratic model for tumour response to radionuclide therapy. Preclinical tumour models tend to be less heterogenic than the clinical conditions they should represent. The results of various preclinical radionuclide therapy experiments for peptide receptor radionuclide therapy are compared to the outcome of theoretical models and the influence of increased heterogeneity is analysed when the results of preclinical research is transferred to the clinic. When the radiation dose and radiobiology of the tumour response is known well enough it may be possible to leave the current phenomenological approach in preclinical radionuclide therapy and start basing these experiments on radiation dose. Then the use of a gamma ray

Preclinical animal research on therapy dosimetry with dual isotopes

Energy Technology Data Exchange (ETDEWEB)

Konijnenberg, Mark W.; Jong, Marion de [Nuclear Medicine Department, Erasmus MC, Rotterdam (Netherlands)

2011-06-15

Preclinical research into radionuclide therapies based on radiation dosimetry will enable the use of any LET-equivalent radionuclide. Radiation dose and dose rate have significant influence on dose effects in the tumour depending on its radiation sensitivity, possibilities for repair of sublethal damage, and repopulation during or after the therapy. Models for radiation response of preclinical tumour models after peptide receptor radionuclide therapy based on the linear quadratic model are presented. The accuracy of the radiation dose is very important for observation of dose-effects. Uncertainties in the radiation dose estimation arise from incomplete assay of the kinetics, low accuracy in volume measurements and absorbed dose S-values for stylized models instead of the actual animal geometry. Normal dose uncertainties in the order of 20% might easily make the difference between seeing a dose-effect or missing it altogether. This is true for the theoretical case of a homogeneous tumour type behaving in vivo in the same way as its cells do in vitro. Heterogeneity of tumours induces variations in clonogenic cell density, radiation sensitivity, repopulation capacity and repair kinetics. The influence of these aspects are analysed within the linear quadratic model for tumour response to radionuclide therapy. Preclinical tumour models tend to be less heterogenic than the clinical conditions they should represent. The results of various preclinical radionuclide therapy experiments for peptide receptor radionuclide therapy are compared to the outcome of theoretical models and the influence of increased heterogeneity is analysed when the results of preclinical research is transferred to the clinic. When the radiation dose and radiobiology of the tumour response is known well enough it may be possible to leave the current phenomenological approach in preclinical radionuclide therapy and start basing these experiments on radiation dose. Then the use of a gamma ray

Applied Beta Dosimetry

International Nuclear Information System (INIS)

Rich, B.L.

1986-01-01

Measurements of beta and/or nonpenetrating exposure results is complicated and past techniques and capabilities have resulted in significant inaccuracies in recorded results. Current developments have resulted in increased capabilities which make the results more accurate and should result in less total exposure to the work force. Continued development of works in progress should provide equivalent future improvements

An analytical model to calculate absorbed fractions for internal dosimetry with alpha, beta and gamma emitters

OpenAIRE

Amato, Ernesto; Italiano, Antonio; Baldari, Sergio

2014-01-01

We developed a general model for the calculation of absorbed fractions in ellipsoidal volumes of soft tissue uniformly filled with alpha, beta and gamma emitting radionuclides. The approach exploited Monte Carlo simulations with the Geant4 code to determine absorbed fractions in ellipsoids characterized by a wide range of dimensions and ellipticities, for monoenergetic emissions of each radiation type. The so-obtained absorbed fractions were put in an analytical relationship with the 'general...

Results from 2010 Caliban Criticality Dosimetry Intercomparison

Energy Technology Data Exchange (ETDEWEB)

Veinot, K. G.

2011-10-12

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

Radionuclide Sensors for Water Monitoring

International Nuclear Information System (INIS)

Grate, Jay W.; Egorov, Oleg B.; DeVol, Timothy A.

2004-01-01

Radionuclide contamination in the soil and groundwater at U.S. Department of Energy (DOE) sites is a severe problem that requires monitoring and remediation. Radionuclide measurement techniques are needed to monitor surface waters, groundwater, and process waters. Typically, water samples are collected and transported to an analytical laboratory, where costly radiochemical analyses are performed. To date, there has been very little development of selective radionuclide sensors for alpha- and beta-emitting radionuclides such as 90Sr, 99Tc, and various actinides of interest. The objective of this project is to investigate novel sensor concepts and materials for sensitive and selective determination of beta- and alpha-emitting radionuclide contaminants in water. To meet the requirements for loW--level, isotope-specific detection, the proposed sensors are based on radiometric detection. As a means to address the fundamental challenge of the short ranges of beta and alpha particle s in water, our overall approach is based on localization of preconcentration/separation chemistries directly on or within the active area of a radioactivity detector. Automated microfluidics is used for sample manipulation and sensor regeneration or renewal. The outcome of these investigations will be the knowledge necessary to choose appropriate chemistries for selective preconcentration of radionuclides from environmental samples, new materials that combine chemical selectivity with scintillating properties, new materials that add chemical selectivity to solid-state diode detectors, new preconcentrating column sensors, and improved instrumentation and signal processing for selective radionuclide sensors. New knowledge will provide the basis for designing effective probes and instrumentation for field and in situ measurements

Primary 4{pi}{beta}-{gamma} coincidence system for standardization of radionuclides by means of plastic scintillators; Sistema primario por coincidencias 4{pi}{beta}-{gamma} para a padronizacao de radionuclideos empregando cintiladores plasticos

Energy Technology Data Exchange (ETDEWEB)

Baccarelli, Aida Maria

2003-07-01

The present work describes a 4{pi}({alpha},{beta})-{gamma} coincidence system for absolute measurement of radionuclide activity using a plastic scintillator in 4{pi} geometry for charged particles detection and a Nal (Tl) crystal for gamma-ray detection. Several shapes and dimensions of the plastic scintillator have been tried in order to obtain the best system configuration. Radionuclides which decay by alpha emission, {beta}{sup -}, {beta}{sup +} and electron capture have been standardized. The results showed excellent agreement with other conventional primary system which makes use of a 4{pi} proportional counter for X-ray and charged particle detection. The system developed in the present work have some advantages when compared with the conventional systems, namely; it does not need metal coating on the films used as radioactive source holders. When compared to liquid scintillators, is showed the advantage of not needing to be kept in dark for more than 24 h to allow phosphorescence decay of ambient light. Therefore it can be set to count immediately after the sources are placed inside of it. (author)

Significant impact of transient deterioration of renal function on dosimetry in PRRT

International Nuclear Information System (INIS)

Van Binnebeek, S.; Baete, K.; Terwinghe, C.

2013-01-01

Peptide receptor radionuclide therapy (PRRT), with 90 Y-DOTATOC and 177 Lu-DOTATATE as most clinically used radiopeptides, is widely used in the management of metastatic neuroendocrine tumors. With respect to radiation dosimetry, the kidneys are the critical organ for 90 Y-DOTATOC. Renal irradiation is significant because of reabsorption of the radiopeptide from the proximal tubuli and the resulting retention in the interstitium, mainly in the inner cortical zone. The high energy and consequently wide range in tissue of the yttrium-90 beta particle result in high absorbed doses to the kidney cortex and medulla. Accurate renal dosimetry can help minimizing radiation nephropathy. We report a case of a 69-year-old candidate for PRRT with an acceptable kidney function at the time of screening. When performing 111 In-octreotide pretreatment dosimetry 3 weeks later, we observed a drastic deterioration in kidney function, caused by undisclosed non-steroidal anti-inflammatory drug intake. The calculated kidney biological effective dose (BED) was 153 Gy after four projected cycles. PRRT was canceled as our full-course BED limit is 37 Gy and the patient was switched to morphine analgesics. Renal function normalized after 3 months and repeated dosimetry yielded an acceptable kidney BED of 28 Gy after four projected cycles (7 Gy/cycle). This case emphasizes that acute kidney insufficiency can yield toxic kidney doses in a single therapy cycle, with an inherent risk of persistent renal insufficiency. All clinical factors which might influence kidney function should be verified at screening and before PRRT administration. (author)

Tooth enamel as a naturtal beta dosemeter for bone seeking radionuclides

International Nuclear Information System (INIS)

Wieser, A.; Petzoldt, G.

1996-01-01

EPR dosimetry was done on teeth from residents of villages along the Techa river, Southern Urals, Russia. The residents have a 90 Sr body burden due to massive releases of liquid nuclear waste into the Techa river in the early fifties. A long time after ingestion, strontium is only incorporated into the skeleton and dentine of the adults but not in tooth enamel. Tooth enamel therefore, is measuring the beta dose from the contaminated dentine. Based on experimental data of this study a first approximation of the ingestion dose coefficient of tooth enamel was found to be more than 5 times lower than the value given in ICRP 69 for the bone surface of the skeleton. A similar difference was found earlier for the dose absorbed in tooth enamel and dentine. The result of this study allows the supposition that that the metabolism of strontium is very very similar for tooth dentine and the skeleton. (author)

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

Trends of personal dosimetry at atomic power plants

International Nuclear Information System (INIS)

Yamamura, Seini

1998-01-01

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

Dosimetry of incorporated transuranic radionuclides

International Nuclear Information System (INIS)

Loessner, V.

1983-01-01

Modern in vivo and in vitro techniques for detecting transuranic radionuclides within the human body are described with special emphasis on multiparameter measuring methods developed at the National Board of Nuclear Safety and Radiation Protection. Furthermore, problems related to calibration and interpretation of measuring data are discussed and new methods presented for the calculation of committed dose equivalents on the basis of data from ICRP Publication 30. Also included is an introductory chapter on radiobiological fundamentals of intake, translocation and metabolism of these nuclides. (author)

BETA digital beta radiometer

International Nuclear Information System (INIS)

Borovikov, N.V.; Kosinov, G.A.; Fedorov, Yu.N.

1989-01-01

Portable transportable digital beta radiometer providing for measuring beta-decay radionuclide specific activity in the range from 5x10 -9 up to 10 -6 Cu/kg (Cu/l) with error of ±25% is designed and introduced into commercial production for determination of volume and specific water and food radioactivity. The device specifications are given. Experience in the BETA radiometer application under conditions of the Chernobyl' NPP 30-km zone has shown that it is convenient for measuring specific activity of the order of 10 -8 Cu/kg, and application of a set of different beta detectors gives an opportunity to use it for surface contamination measurement in wide range of the measured value

Aspects of the dosimetry of radionuclides within the skeleton with particular emphasis on the active marrow

International Nuclear Information System (INIS)

Eckerman, K.F.

1985-01-01

Epidemiological surveys on man and results from animal experiments have shown that two tissues associated with the skeleton are of primary concern with respect to cancer induction by ionizing radiation. These are the cells on or near endosteal surfaces of bone, from which osteosarcomas are thought to arise, and hematopoietic bone marrow, which is associated with leukemia. The complex geometry of the soft tissue-bone intermixture makes calculations of absorbed dose to these target regions a difficult problem. In the case of photon or neutron radiations, charged particle equilibrium may not exist in the vicinity of soft tissue-bone mineral interface. In this paper a general study of the dosimetry of radionuclides within the skeleton is presented. Dosimetric data consistent with the MIRD schema and reflecting the physical and anatomical parameters defining the energy deposition are tabulated for the relevant target regions. 27 refs., 5 figs., 5 tabs

Internal Dosimetry for Nuclear Power Program

International Nuclear Information System (INIS)

Wo, Y.M.

2011-01-01

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

SU-E-T-256: Optimizing the Combination of Targeted Radionuclide Therapy Agents Using a Multi-Scale Patient-Specific Monte Carlo Dosimetry Platform

International Nuclear Information System (INIS)

Besemer, A; Bednarz, B; Titz, B; Grudzinski, J; Weichert, J; Hall, L

2014-01-01

Purpose: Combination targeted radionuclide therapy (TRT) is appealing because it can potentially exploit different mechanisms of action from multiple radionuclides as well as the variable dose rates due to the different radionuclide half-lives. The work describes the development of a multiobjective optimization algorithm to calculate the optimal ratio of radionuclide injection activities for delivery of combination TRT. Methods: The ‘diapeutic’ (diagnostic and therapeutic) agent, CLR1404, was used as a proof-of-principle compound in this work. Isosteric iodine substitution in CLR1404 creates a molecular imaging agent when labeled with I-124 or a targeted radiotherapeutic agent when labeled with I-125 or I-131. PET/CT images of high grade glioma patients were acquired at 4.5, 24, and 48 hours post injection of 124I-CLR1404. The therapeutic 131I-CLR1404 and 125ICLR1404 absorbed dose (AD) and biological effective dose (BED) were calculated for each patient using a patient-specific Monte Carlo dosimetry platform. The optimal ratio of injection activities for each radionuclide was calculated with a multi-objective optimization algorithm using the weighted sum method. Objective functions such as the tumor dose heterogeneity and the ratio of the normal tissue to tumor doses were minimized and the relative importance weights of each optimization function were varied. Results: For each optimization function, the program outputs a Pareto surface map representing all possible combinations of radionuclide injection activities so that values that minimize the objective function can be visualized. A Pareto surface map of the weighted sum given a set of user-specified importance weights is also displayed. Additionally, the ratio of optimal injection activities as a function of the all possible importance weights is generated so that the user can select the optimal ratio based on the desired weights. Conclusion: Multi-objective optimization of radionuclide injection activities

Biokinetics of radionuclides and treatment of accidental intakes

International Nuclear Information System (INIS)

Taylor, D.M.; Stradling, G.N.; Menetrier, F.

2003-01-01

This paper describes the objectives and reviews the progress of EULEP Working Party 5, convened under the auspices of the European Union's Fifth Framework Programme, to 'cluster' two EU-supported contracts, Biokinetics and Dosimetry of Internal Contamination (BIODOS (EU Contract FIS5-1999-00214)) and Radionuclide Biokinetics Database (EULEP) ( RBDATA-EULEP (Concerted Action Contract FIS5-1999-00218), and two non-EU funded projects, Biokinetics of Radionuclides in Human Volunteers (RNHV (non-EU Funded Project) and Treatment of Accidental Intakes of Radionuclides (TAIR (part-funded by EULEP)). (author)

The importance of BMI in dosimetry of 153Sm-EDTMP bone pain palliation therapy: A Monte Carlo study

International Nuclear Information System (INIS)

Fallahpoor, Maryam; Abbasi, Mehrshad; Asghar Parach, Ali; Kalantari, Faraz

2017-01-01

Using digital phantoms as an atlas compared to acquiring CT data for internal radionuclide dosimetry decreases patient overall radiation dose and reduces the required analysis effort and time for organ segmentation. The drawback is that the phantom may not match exactly with the patient. We assessed the effect of varying BMIs on dosimetry results for a bone pain palliation agent, 153 Sm-EDTMP. The simulation was done using the GATE Monte Carlo code. Female XCAT phantoms with the following different BMIs were employed: 18.6, 20.8, 22.1, 26.8, 30.3 and 34.7 kg/m 2 . S-factors (mGy/MBq.s) and SAFs (kg −1 ) were calculated for the dosimetry of the radiation from major source organs including spine, ribs, kidney and bladder into different target organs as well as whole body dosimetry from spine. The differences in dose estimates from different phantoms compared to those from the phantom with BMI of 26.8 kg/m 2 as the reference, were calculated for both gamma and beta radiations. The relative differences (RD) of the S-factors or SAFs from the values of reference phantom were calculated. RDs greater than 10% and 100% were frequent in radiations to organs for photon and beta particles, respectively. The relative differences in whole body SAFs from the reference phantom were 15.4%, 7%, 4.2%, −9.8% and −1.4% for BMIs of 18.6, 20.8, 22.1, 30.3 and 34.7 kg/m 2 , respectively. The differences in whole body S-factors for the phantoms with BMIs of 18.6, 20.8, 22.1, 30.3 and 34.7 kg/m 2 were 39.5%, 19.4%, 8.8%, −7.9% and −4.3%, respectively. The dosimetry of the gamma photons and beta particles changes substantially with the use of phantoms with different BMIs. The change in S-factors is important for dose calculation and can change the prescribed therapeutic dose of 153 Sm-EDTMP. Thus a phantom with BMI better matched to the patient is suggested for therapeutic purposes where dose estimates closer to those in the actual patient are required. - Highlights: • Internal

Current status of personnel monitoring for beta particles

International Nuclear Information System (INIS)

Plato, P.; Miklos, J.

1983-01-01

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

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

Biological effect of radionuclides on plants

International Nuclear Information System (INIS)

Prister, B.S.; Khal'chenko, V.A.; Polyakova, V.Y.; Shevchenko, V.A.; Shejn, G.P.; Aleksakhin, R.M.

1979-01-01

Stated are dosimetry principles and given is an analysis of biological radionuclide effect on plants in aerial and root intakes. A comparative barley radiosensitivity characteristic depending on plant development phases during irradiation is given using LD 50 criteria. Considered is a possibility for using generalized bioinformation parameters as sensitive indications for estimating biological effects due to the influence of low radiation doses. On the grounds of data obtained generalization are forecasted probable losses of crops when getting radionuclides into plants during various vegetation periods

Characteristics of beta detection and dose measurement at Department of Energy facilities

International Nuclear Information System (INIS)

Mulvehill, J.M.; Brackenbush, L.W.

1987-02-01

This report considers the current state of the art of beta dosimetry practices and beta detection methods used by health physicists at US Department of Energy facilities. This information is based on a survey of DOE facilities. Beta measurements are technically difficult and innovative efforts must be expended to improve their accuracy. Perhaps the most pronounced problem is that beta dosimetry and instrumentation in use are highly energy and angular dependent. Many believe that beta exposures are adequately controlled because beta to photon ratios are assumed to be low. This assumption is not always valid as demonstrated by the accident at Three Mile Island (TMI). Significant beta doses exist where personnel are exposed to mixed fission products; for example, chemical reprocessing plants, reactor accidents, or where uranium metals are processed. This report is part of an effort to increase the DOE response to this technically difficult area of health protection. Problem areas are addressed and methods recommended to improve beta dosimetry through a cooperative effort among the various DOE contractors. 34 refs., 2 figs., 16 tabs

Dosimetry characterization of the commercial CaF{sub 2} for beta radiation of {sup 90}Sr + {sup 90}Y; Caracterizacao dosimetrica de CaF{sub 2} comercial para radiacao beta de {sup 90}Sr + {sup 90}Y

Energy Technology Data Exchange (ETDEWEB)

Oliveira, Mercia L.; Caldas, Linda V.E. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)], e-mail: mlolivei@ipen.br, e-mail: lcaldas@ipen.br

2003-07-01

This work studies the dosimetric characteristics of the CaF{sub 2} commercial dosimetry for detection of {sup 90}Sr + {sup 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.

The US Department of Energy Personnel Dosimetry Evaluation and Upgrade Program

International Nuclear Information System (INIS)

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

1987-11-01

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

Beta dosimetry in teeth from SR-90 exposed subjects

International Nuclear Information System (INIS)

Fattibene, P.; De Coste, V.; Onori, S.; Veronese, I.; Giussani, A.; Cantone, M.C.; Shishkina, E.

2006-01-01

Tooth enamel is a well recognized dosimeter for retrospective dose reconstruction of individuals accidentally exposed to ionizing radiation. The measurements of the absorbed dose in tooth enamel is conventionally carried out with the Electron Paramagnetic Resonance technique. Tooth enamel is sensitive to all kind of ionizing radiation. Its response to photons has been widely investigated. For application to contaminated teeth with 90 Sr, one of the most common osteo tropic radionuclides, the effectiveness of tooth enamel response to the β spectrum needs be evaluated. The response function to 90 Sr of the EPR/tooth enamel systems, its linearity and reproducibility have been investigated under a controlled geometry, and the results will be presented and compared to those obtained with photons. When the subject has been exposed to both external and internal radiation, a combined EPR/T.L. method can be used to distinguish the internal from the external contribution to the cumulative dose in tooth (Gosku et al., 2002;=Veronese et al. 2004, Shishkina et al. 2005). The T.L. measurement, performed putting thin ± Al 2 O 3 :C dosimeters at contact with the tooth surfaces, enables to estimate the beta dose rate due to the radionuclides present in tooth. The combination of this information with that coming from EPR allows, under specific assumptions, to evaluate separately the internal and external contribution to the tooth dose. In a previous work (Veronese et al., 2004) the dose in enamel measured by EPR in a tooth contaminated with 90 Sr of a Techa River resident was compared to the dose rate measured by TLDs. The test has been extended to a larger number of 90 Sr contaminated teeth. EPR measurements have been also performed in other portions of the teeth, i.e. tooth dentin and root. The correlation between the results, obtained from EPR and TLD measurements, and the evaluation of the relative proportion of internal and external dose are presented and discussed. (authors)

Dosimetry techniques applied to thermoluminescent age estimation

International Nuclear Information System (INIS)

Erramli, H.

1986-12-01

The reliability and the ease of the field application of the measuring techniques of natural radioactivity dosimetry are studied. The natural radioactivity in minerals in composed of the internal dose deposited by alpha and beta radiations issued from the sample itself and the external dose deposited by gamma and cosmic radiations issued from the surroundings of the sample. Two technics for external dosimetry are examined in details. TL Dosimetry and field gamma dosimetry. Calibration and experimental conditions are presented. A new integrated dosimetric method for internal and external dose measure is proposed: the TL dosimeter is placed in the soil in exactly the same conditions as the sample ones, during a time long enough for the total dose evaluation [fr

Calibration of photon and beta ray sources used in brachytherapy. Guidelines on standardized procedures at Secondary Standards Dosimetry Laboratories

International Nuclear Information System (INIS)

2004-03-01

It has generally been recognized that international harmonization in radiotherapy dosimetry is essential. Consequently, the IAEA has given much effort to this, for example by publishing a number of reports in the Technical Reports Series (TRS) for external beam dosimetry, most notably TRS-277 and more recently TRS-398. Both of these reports describe in detail the steps to be taken for absorbed dose determination in water and they are often referred to as 'dosimetry protocols'. Similar to TRS-277, it is expected that TRS-398 will be adopted or used as a model by a large number of countries as their national protocol. In 1996, the IAEA established a calibration service for low dose rate (LDR) 137 Cs brachytherapy sources, which is the most widely used source for treatment of gynecological cancer. To further enhance harmonization in brachytherapy dosimetry, the IAEA published in 1999 IAEA-TECDOC-1079 entitled 'Calibration of Brachytherapy Sources. Guidelines on Standardized Procedures for the Calibration of Brachytherapy Sources at Secondary Standard Dosimetry Laboratories (SSDLs) and Hospitals'. The report was well received and was distributed in a large number of copies to the members of the IAEA/WHO network of SSDLs and to medical physicists working with brachytherapy. The present report is an update of the aforementioned TECDOC. Whereas TECDOC-1079 described methods for calibrating brachytherapy sources with photon energies at or above those of 192 Ir, the current report has a wider scope in that it deals with standardization of calibration of all the most commonly used brachytherapy sources, including both photon and beta emitting sources. The latter sources have been in use for a few decades already, but their calibration methods have been unclear. Methods are also described for calibrating sources used in the rapidly growing field of cardiovascular angioplasty. In this application, irradiation of the vessel wall is done in an attempt to prevent restenosis after

The problem of adequacy in skin dosimetry for the case of a nuclear reactor emergency and for occupational exposure

International Nuclear Information System (INIS)

Osanov, D.

1991-01-01

The requirement for satisfactory skin dosimetry is, briefly, that the measured dosimetric values should be applicable for further unambiguous prediction of the radiation-induced effects. To fit these requirements the dose limits and actual dose burdens should be concerned with those target skin structures that are primarily responsible for biological effects. The problem of adequate skin dosimetry is here considered for the two most important situations: (1) for normal operation of nuclear power plants, and (2) for a nuclear reactor emergency. A method for determination of the absorbed dose of beta radiation in the surface tissues of the human body from a flat source produced by radionuclides accumulated on the ground surface is presented. Skin dose estimation techniques and actual values of personnel skin doses are also presented, as well as the application of such dose data in predicting the consequences of the irradiation. The principles of emergency and conventional skin dosemeter construction fulfilling the requirements for adequacy and for the measurement of the dose limits for occupational irradiation of the skin are discussed. (author)

Application of gel dosimetry - A preliminary study on verification of uniformity of activity and length of source used in Beta-Cath system

International Nuclear Information System (INIS)

Subramaniam, S.; Rabi Raja Singh, I.; Visalatchi, S.; Paul Ravindran, B.

2002-01-01

Recently the intraluminal irradiation of coronary arteries following balloon angioplasty is found to reduce proliferation of smooth muscle cells and restenosis. Among the isotopes used for the intracoronary irradiation, 90 Sr/Y appears to be ideal (H I Almos et al, 1996). In 1984 Gore et al proposed that radiation induced changes in the well-established Fricke solution could be probed with Nuclear Magnetic Resonance (NMR) relaxation measurements rather than using conventional spectrophotometry measurements. This was a major step in the development of gel dosimetry and since then gel dosimetry has been one of the major advances in the dosimetry of complex radiation fields has been in the area of gel dosimetry. In this preliminary work on gel dosimetry we present the verification of uniformity of activity along the length of the source train and verification of the length of the source used in the Beta-Cath system used for intracoronary brachytherapy with ferrous gel dosimeter. The Beta-Cath system obtained from Novoste, Norcross, GA was used in this study. It consists of a source train of 16 90 Sr/Y sources each of length 2.5mm. The total length of the source train is 40mm. For preparation of the Ferrous-Gelatin Gel, the recipe provided by the London Regional Cancer Center, London Ontario, Canada was used. Stock solutions of 50mM H 2 SO 4 , 0.3 mM ferrous ammonium sulphate, 0.05mM Xylenol orange was first prepared. The gel was prepared by mixing 4% gelatin with distilled water while stirring in a water bath at 40-42 deg. C. Acid solution, Ferrous ammonium sulphate solution and Xylenol orange were added and stirred in the water bath for about an hour to allow aeration. The mixture was poured in to three 20ml syringes to form the gel and stored in the refrigerator at 5 deg. C. For irradiation with Beta-Cath, the gel was prepared in three cylindrical 20ml syringes. A nylon tube having the same dimension as that of the delivery catheter used in intra-coronary was placed

Dosimetry for the treatment of cystic craniopharyngioma through radiocolloids with 186 Re

International Nuclear Information System (INIS)

Rojas, E.L.; Al-dweri, F.M.O.; Lallena, A.M.; Bodineau, C.; Galan, P.

2003-01-01

The cystic craniopharyngioma (CQ) are histologically benign tumors that can affect important organs, as the hypothalamus or the optic nerve. They are treated introducing, inside the cyst, a radioactive colloid. The wall constitutes the white volume and the dosimetry is usually carried out starting from analytic formulas that only are valid in the case of an homogeneous media, uniform and infinite. In this work it is studied the dosimetry of the CQ by means of Monte Carlo simulation (MC), taking in account the different materials and interfaces that conform them. We present the obtained results for the radionuclide 186 Re. We have used the Monte Carlo code Penelope and we follow 5x10 6 histories in each simulation. We supposed a size of CQ of 1.75 cm of radio and a wall thickness of 1 mm and we have varied the constituent materials of the interior of the cyst and of the wall. The analytic calculations that we carry out show an excellent agreement with the MC results for an unique media (water), as much for the beta radiation as for those originated of the Rhenium disintegration. However, when it takes in account the gel that is introduced in the tumor for the treatment and we vary the constituent material of the wall, we find important differences. Of the analysis of our results we can conclude that the dosimetry for the treatment of CQ based in the usual analytic formulas overestimates the doses really deposited in the wall of the CQ. (Author)

SU-G-TeP3-08: Pre-Clinical Radionuclide Therapy Dosimetry in Several Pediatric Cancer Xenografts

Energy Technology Data Exchange (ETDEWEB)

Marsh, I; Otto, M; Weichert, J; Baiu, D; Bednarz, B [University of Wisconsin, Madison, WI (United States)

2016-06-15

Purpose: The focus of this work is to perform Monte Carlo-based dosimetry for several pediatric cancer xenografts in mice treated with a novel radiopharmaceutical {sup 131}I-CLR1404. Methods: Four mice for each tumor cell line were injected with 8–13 µCi/g of the {sup 124}124I-CLR1404. PET/CT images of each individual mouse were acquired at 5–6 time points over the span of 96–170 hours post-injection. Following acquisition, the images were co-registered, resampled, rescaled, corrected for partial volume effects (PVE), and masked. For this work the pre-treatment PET images of {sup 124}I-CLR1404 were used to predict therapeutic doses from {sup 131}I-CLR1404 at each time point by assuming the same injection activity and accounting for the difference in physical decay rates. Tumors and normal tissues were manually contoured using anatomical and functional images. The CT and the PET images were used in the Geant4 (v9.6) Monte Carlo simulation to define the geometry and source distribution, respectively. The total cumulated absorbed dose was calculated by numerically integrating the dose-rate at each time point over all time on a voxel-by-voxel basis. Results: Spatial distributions of the absorbed dose rates and dose volume histograms as well as mean, minimum, maximum, and total dose values for each ROI were generated for each time point. Conclusion: This work demonstrates how mouse-specific MC-based dosimetry could potentially provide more accurate characterization of efficacy of novel radiopharmaceuticals in radionuclide therapy. This work is partially funded by NIH grant CA198392.

40 CFR 141.66 - Maximum contaminant levels for radionuclides.

Science.gov (United States)

2010-07-01

... beta particle and photon radioactivity from man-made radionuclides in drinking water must not produce.../year). (2) Except for the radionuclides listed in table A, the concentration of man-made radionuclides... may make this technology too complex for small surface water systems. e Removal efficiencies can vary...

EANM/ESC guidelines for radionuclide imaging of cardiac function

DEFF Research Database (Denmark)

Hesse, B.; Lindhardt, T.B.; Acampa, W.

2008-01-01

radionuclide ventriculography, gated myocardial perfusion scintigraphy, gated PET, and studies with non-imaging devices for the evaluation of cardiac function. The items covered are presented in 11 sections: clinical indications, radiopharmaceuticals and dosimetry, study acquisition, RV EF, LV EF, LV volumes...

Internal emitter dosimetry: are patient-specific calculations necessary?

International Nuclear Information System (INIS)

Sgouros, G.

1996-01-01

Full text: The question of whether patient-specific calculations are needed in internal emitter dosimetry arises when radionuclides are used for therapy. In diagnostic procedures the absorbed dose delivered to normal tissue is far below hazardous levels. In internal emitter therapy, the need for patient-specific dosimetry may arise if a large variability in biodistribution, normal tissue toxicity or efficacy is anticipated. Patient-specificity may be accomplished at the level of pharmacokinetics, anatomy/tumor-geometry or both. At the first level, information regarding the biodistribution of a particular radiolabeled agent is obtained and used to determine the maximum activity that may be administered for treatment. The classical example of this is radioiodine therapy for thyroid cancer. In radioiodine therapy, the therapy dose is preceded by a tracer dose of I-131-iodide which is used to measure patient kinetics by imaging and whole-body counting. Absorbed dose estimates obtained from these data are used to constrain the therapy dose to meet safety criteria established in a previously performed dose-response study. The most ambitious approach to patient-specific dosimetry, requires a three-dimensional set of images representing radionuclide distribution (SPECT or PET) and a corresponding set of registered images representing anatomy (CT or MRI). The spatial distribution of absorbed dose or dose-rate may then be obtained by convolution of a point-kernel with the radioactivity distribution or by Monte Carlo calculation. The spatial absorbed dose or dose-rate distribution may be represented as a set of images, as isodose contours, or as dose-volume histograms. The 3-D Monte Carlo approach is, in principle, the most patient-specific; it accounts for patient anatomy and tumor geometry as well as for the spatial distribution of radioactivity. It is also, however, the most logistically and technically demanding. Patients are required to undergo CT or MRI and at least one

Addendum report of the JHPS expert committee on radiation protection of the lens of the eye (2). When and how should the dosimetry of beta H_p(3) be made?

International Nuclear Information System (INIS)

Akahane, Keiichi; Tatsuzaki, Hideo; Iimoto, Takeshi; Ichiji, Takeshi; Hamada, Nobuyuki; Iwai, Satoshi; Ohguchi, Hiroyuki; Ohno, Kazuko; Kawaura, Chiyo; Kurosawa, Tadahiro; Tsujimura, Norio; Hayashida, Toshiyuki; Hotta, Yutaka; Yamasaki, Tadashi; Yokoyama, Sumi

2015-01-01

In a mixed field of photon and beta radiations, the same dose assigned to skin is normally assigned to the dose to the lens of the eye as a conservative estimate of H_p(3). In exceptional cases where a very high beta dose might be imparted of the same order with the dose limit, however, the conservatively biased dose must be too limiting, and thereby an accurate estimate of beta H_p(3) is desirable. This addendum report of the Japan Health Physics Society Expert Committee on Radiation Protection of the Lens of the Eye presents a practical proposal of when and how the dosimetry of beta H_p(3) should be made. (author)

Radionuclide injury to the lung

International Nuclear Information System (INIS)

Dagle, G.E.; Sanders, C.L.

1984-01-01

Radionuclide injury to the lung has been studied in rats, hamsters, dogs, mice and baboons. Exposure of the lung to high dose levels of radionuclides produces a spectrum of progressively more severe functional and morphological changes, ranging from radiation pneumonitis and fibrosis to lung tumors. These changes are somewhat similar for different species. Their severity can be related to the absorbed radiation dose (measured in rads) produced by alpha, beta or gamma radiation emanating from various deposited radionuclides. The chemicophysical forms of radionuclides and spatial-temporal factors are also important variables. As with other forms of injury to the lung, repair attempts are highlighted by fibrosis and proliferation of pulmonary epithelium. Lung tumors are the principal late effect observed in experimental animals following pulmonary deposition of radionuclides at dose levels that do not result in early deaths from radiation pneumonitis or fibrosis. The predominant lung tumors described have been of epithelial origin and have been classified, in decreasing frequency of occurrence, as adenocarcinoma, bronchioloalveolar carcinoma, epidermoid carcinomas and combined epidermoid and adenocarcinoma. Mesothelioma and fibrosarcoma have been observed in rats, but less commonly in other species. Hemangiosarcomas were frequently observed in dogs exposed to beta-gamma emitters, and occasionally in rats exposed to alpha emitters. These morphologic changes in the lungs of experimental animals were reviewed and issues relevant to the prediction of human hazards discussed. 88 references

External dosimetry sources and shielding

International Nuclear Information System (INIS)

Calisto, Washington

1994-01-01

A definition of external dosimetry r external sources dosimetry,physical and mathematical treatment of the interaction of gamma radiation with a minimal area in that direction. Concept of attenuation coefficient, cumulated effect by polyenergetic sources, exposition rate, units, cumulated dose,shielding, foton shielding, depth calculation, materials used for shielding.Beta shielding, consideration of range and maximum β energy , low stopping radiation by use of low Z shielding. Tables for β energy of β emitters, I (tau) factor, energy-range curves for β emitters in aqueous media, gamma attenuation factors for U, W and Pb. Y factor for bone tissue,muscle and air, build-up factors

An interspecies comparison of the biological effects of an inhaled, relatively insoluble beta emitter

International Nuclear Information System (INIS)

Griffith, W.C.; Lundgren, D.L.; Hahn, F.F.; Boecker, B.B.; McClellan, R.O.

1986-01-01

Mice, rats, Syrian hamsters, and beagle dogs were exposed by inhalation to graded levels of 144 Ce in relatively insoluble forms to demonstrate species similarities and differences regarding patterns of deposition, fate, dosimetry, and dose-response relationships. All animals were serially evaluated to determine lung burdens, held for life-span observation, necropsied at death, and examined histopathologically to characterize the lesions present and to determine the cause of death. The primary malignant lung tumors observed in rodents were predominantly squamous-cell carcinomas and adenocarcinomas, whereas those in dogs at earlier times were primarily hemangiosarcomas and those in dogs that died at later times were pulmonary carcinomas. The relationship between the incidence of lung cancer and absorbed beta dose to the lung differed among species. The results of modeling these data provide a better understanding of how the choice of species can influence the outcome of a life-span study. The data are used to estimate the risk of lung cancer in man from an inhaled beta-emitting radionuclide. 26 refs., 5 figs., 6 tabs

Glass badge dosimetry system for large scale personal monitoring

International Nuclear Information System (INIS)

Norimichi Juto

2002-01-01

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

GENMOD - A program for internal dosimetry calculations

International Nuclear Information System (INIS)

Dunford, D.W.; Johnson, J.R.

1987-12-01

The computer code GENMOD was created to calculate the retention and excretion, and the integrated retention for selected radionuclides under a variety of exposure conditions. Since the creation of GENMOD new models have been developed and interfaced to GENMOD. This report describes the models now included in GENMOD, the dosimetry factors database, and gives a brief description of the GENMOD program

Concentration and speciation of radionuclides in environmental samples

International Nuclear Information System (INIS)

Testa, C.; Desideri, D.; Meli, M.A.; Roselli, C.

2000-01-01

The paper will describe three examples dealing with the measure of some natural (U, Th, 2 10Pb, 4 0K) and artificial ( 1 37Cs, 9 0Sr, 2 39 +2 40Pu, 2 41Am) radionuclides in environmental samples such as mosses, sediments, soils. Extraction chromatography, liquid extraction, selective precipitation and electroplating were used to isolate the radionuclides, except for gamma emitters which were detected by gamma spectrometry. Alpha spectrometry were used to measure the alpha emitters and low background beta detector to measure the beta emitters

Monte Carlo and experimental internal radionuclide dosimetry in RANDO head phantom

International Nuclear Information System (INIS)

Ghahraman Asl, Ruhollah; Nasseri, Shahrokh; Parach, Ali Asghar; Zakavi, Seyed Rasoul; Momennezhad Mehdi; Davenport, David

2015-01-01

Monte Carlo techniques are widely employed in internal dosimetry to obtain better estimates of absorbed dose distributions from irradiation sources in medicine. Accurate 3D absorbed dosimetry would be useful for risk assessment of inducing deterministic and stochastic biological effects for both therapeutic and diagnostic radiopharmaceuticals in nuclear medicine. The goal of this study was to experimentally evaluate the use of Geant4 application for tomographic emission (GATE) Monte Carlo package for 3D internal dosimetry using the head portion of the RANDO phantom. GATE package (version 6.1) was used to create a voxel model of a human head phantom from computed tomography (CT) images. Matrix dimensions consisted of 319 × 216 × 30 voxels (0.7871 × 0.7871 × 5 mm 3 ). Measurements were made using thermoluminescent dosimeters (TLD-100). One rod-shaped source with 94 MBq activity of 99m Tc was positioned in the brain tissue of the posterior part of the human head phantom in slice number 2. The results of the simulation were compared with measured mean absorbed dose per cumulative activity (S value). Absorbed dose was also calculated for each slice of the digital model of the head phantom and dose volume histograms (DVHs) were computed to analyze the absolute and relative doses in each slice from the simulation data. The S-values calculated by GATE and TLD methods showed a significant correlation (correlation coefficient, r 2 ≥ 0.99, p < 0.05) with each other. The maximum relative percentage differences were ≤14 % for most cases. DVHs demonstrated dose decrease along the direction of movement toward the lower slices of the head phantom. Based on the results obtained from GATE Monte Carlopackage it can be deduced that a complete dosimetry simulation study, from imaging to absorbed dose map calculation, is possible to execute in a single framework.

Medical concerns in the application of ultrashort-lived radionuclides

International Nuclear Information System (INIS)

Strauss, H.W.; Gill, J.; Miller, D.D.; Callahan, R.; Elmaleh, D.

1986-01-01

The dosimetry of ultrashort-lived radionuclides is dependent on the biodistribution and residence time of the materials eluted from the generator. Since the half-life of the daughter usually precludes any serious chemical manipulations, the eluates are usually infused in the chemical form available directly from the generator, typically simple ions. As a result, the factors that will define dosimetry are: (1) decay scheme of the daughter; (2) progeny of the daughter; (3) decay scheme of the parent; (4) radiocontaminants of the parent; (5) breakthrough of the parent; (6) biodistribution of the radionuclides. The half-life of the daughter is usually sufficiently short that it does not contribute significantly to the radiation burden. The half-life of the parent, associated radiocontaminants or the progeny, on the other hand, may contribute substantially to the radiation burden of the patient. Many of these agents, including osmium, germanium, and mercury have long biological half-lives and specific organ localization which contribute the radiation burden. 9 references

Extremity dosimetry at US Department of Energy facilities

International Nuclear Information System (INIS)

Harty, R.; Reece, W.D.; MacLellan, J.A.

1986-05-01

A questionnaire on extremity dosimetry was distributed to DOE facilities along with a questionnaire on beta dosimetry. An informal telephone survey was conducted as a follow-up survey to answer a few additional questions concerning extremity monitoring practices. The responses to the questionnaire and the telephone survey are summarized in this report. Background information, developed from operational experience and a review of the current literature, is presented as a basis for understanding the information obtained by the survey and questionnaire

Method of measuring the disinteration rate of beta-emitting radionuclide in a liquid sample

International Nuclear Information System (INIS)

Horrocks, D.L.

1977-01-01

A method of measuring the disintegration rate of a beta-emitting radionuclide in a liquid sample by counting at least two differently quenched versions of the sample is described. In each counting operation the sample is counted in the presence of and in the absence of a standard radioactive source. A pulse height (PH) corresponding to a unique point on the pulse height spectrum generated in the presence of the standard is determined. A zero threshold sample count rate (CPM) is derived by counting the sample once in a counting window having a zero threshold lower limit. Normalized values of the measured pulse heights (PH) are developed and correlated with the corresponding pulse counts (CPM) to determine the pulse count for a normalized pulse height value of zero and hence the sample disintegration rate

Personnel radiation dosimetry symposium: program and abstracts

Energy Technology Data Exchange (ETDEWEB)

1984-10-01

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

Personnel radiation dosimetry symposium: program and abstracts

International Nuclear Information System (INIS)

1984-10-01

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

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

International Nuclear Information System (INIS)

Souleyrette, M.L.

1992-01-01

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

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

Workshop on intakes of radionuclides: occupational and public exposure, Avignon, 15-18 September 1997

International Nuclear Information System (INIS)

Etherington, G.; Phipps, A.W.; Harrison, J.D.; Jones, D.G.; Stradling, G.N.

1998-01-01

This meeting was the fourth in this series of Workshops, previous meetings having been held in Versailles, France in 1988, in Elmau, Germany in 1991, and in Bath, UK in 1993. The Avignon meeting comes at a time of intense activity in internal dosimetry. The International Commission on Radiological Protection (ICRP) has recently completed development and publication of a series of physiologically based age-dependent biokinetic models for a range of important radionuclides. This followed the publication in 1994 of the new Human Respiratory Tract Model (HRTM). These models have now been used to determine the dose coefficients that are given in the EURATOM Directive and in the International Basic Safety Standards. A forthcoming ICRP publication will present predictions of the new models for bioassay quantities of interest, and will give revised guidance on the design and interpretation of internal dosimetry monitoring programmes. Another will give technical guidance on the use of the HRTM in practical situations. Looking further into the future, work on the development of a new age-dependent dosimetric model for the gastro-intestinal tract is now under way. With so many recent and forthcoming developments in modelling, it is not surprising that one of the unifying themes of the meeting was the impending need for internal dosimetry practitioners to be able to use the new models for assessments of doses in the workplace. The meeting's main sessions were organised under five headings: occupational exposure to radionuclides, public exposure to radionuclides, developments in modelling, physical dosimetry and treatment of accidental intakes

National intercomparison programme for radionuclide analysis in environmental samples: Aramar radioecological laboratory performance

Energy Technology Data Exchange (ETDEWEB)

Arine, Bruno Burini Robles, E-mail: bruno.arine@ctmsp.mar.mil.b [Centro Tecnologico da Marinha em Sao Paulo (CTMSP/ARAMAR), Ipero, SP (Brazil). Lab. Radioecologico; Moraes, Marco Antonio P.V., E-mail: marco.proenca@ctmsp.mar.mil.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

The radioecological laboratory is concerned with the measurements of background radiation (mainly uranium and thorium natural series) and present effluents in the Aramar Experimental Centre, as well as in its surroundings. The laboratory is directly subordinated to the Navy Technological Centre in Sao Paulo (CTMSP - Sao Paulo - Brazil), a military research organization whose goal is to develop nuclear and energy systems for the Brazilian naval ship propulsion. The measurements were performed in addition to the Environmental Monitoring Programme carried out in the same region. For this endeavour, the laboratory has attended to the National Intercomparison Programme conducted by the Institute for Radioprotection and Dosimetry (IRD) by analyzing several kinds of solid and liquid samples containing specific radionuclides through gamma spectrometry, liquid scintillation, alpha-beta total counting and fluorimetry techniques, since December 1995. In the last 15 years, our results were compared to another 19 laboratories and rated as 'very good' and 'acceptable' in at least 90% of the results. (author)

Analytical methods for radionuclides in liquid and solid media

International Nuclear Information System (INIS)

Sedlet, J.

1983-01-01

This lecture describes in vitro techniques for the radiochemical determination and dosimetry of radionuclides in the body that have been metabolized and are in the circulatory system. Measurements are made in the excretions and other body specimens such as blood, perspiration, hair, exhaled air, and tissue. 13 references, 4 tables

The principles of radioiodine dosimetry following a nuclear accident

International Nuclear Information System (INIS)

Zvonova, I.A.

1996-01-01

Based upon the experience of radioiodine dosimetry after the Chernobyl accident main principals of radioiodine measurements and dosimetry in thyroid glands of population in case of a radiation accident are discussed in the report. For the correct dose estimation following the radioiodine measurement in the thyroid one should know the ''history'' of radionuclide intake into the body of a contaminated person. So a measurement of radioiodine thyroid content should be accompanied by asking questions of investigated persons about, their life style and feeding after a nuclear incident. These data coincidently with data of radionuclides dynamic in the air and food (especially in milk products) are used for the development of radioiodine intake model and then for thyroid dose estimation. The influence of stable iodine prophylaxis and other countermeasures on values are discussed in dependence on the time of its using. Some methods of thyroid dose reconstruction used after the Chernobyl accident in Russia for a situation of thyroid radioiodine measurements lacking in a contaminated settlement are presented in the report. (author). 16 refs, 5 figs, 3 tabs

The principles of radioiodine dosimetry following a nuclear accident

Energy Technology Data Exchange (ETDEWEB)

Zvonova, I A [Institute of Radiation Hygiene, St. Petersburg (Russian Federation)

1996-08-01

Based upon the experience of radioiodine dosimetry after the Chernobyl accident main principals of radioiodine measurements and dosimetry in thyroid glands of population in case of a radiation accident are discussed in the report. For the correct dose estimation following the radioiodine measurement in the thyroid one should know the ``history`` of radionuclide intake into the body of a contaminated person. So a measurement of radioiodine thyroid content should be accompanied by asking questions of investigated persons about, their life style and feeding after a nuclear incident. These data coincidently with data of radionuclides dynamic in the air and food (especially in milk products) are used for the development of radioiodine intake model and then for thyroid dose estimation. The influence of stable iodine prophylaxis and other countermeasures on values are discussed in dependence on the time of its using. Some methods of thyroid dose reconstruction used after the Chernobyl accident in Russia for a situation of thyroid radioiodine measurements lacking in a contaminated settlement are presented in the report. (author). 16 refs, 5 figs, 3 tabs.

Beta Autoradiography. An analytical technique to investigate radionuclides contamination on surface

International Nuclear Information System (INIS)

Ficher, P.; Goutelard, F.; Siitari-Kauppi, M.

2012-01-01

In decommissioning of old buildings and after disposal of nuclear facilities (materials, glove boxes,...), the inventory of the radioactive contamination of various building materials needs to be obtained in order to fix the working condition for dismantling. The challenge of this study was to classify different building materials of a whole research laboratory that was dedicated to research on organic molecules labeled with H-3 and C-14. The problem of waste classification is essential for safety treatment of waste and also for its cost. The analytical technique of beta autoradiography particularly well known for biological researches has been tested to investigate radionuclides contamination on surface. This technique is mainly interesting for beta and alpha emitters but also sensitive to gamma radiation. The first step of this technique is the deposit of a film on the surface of material to be analyzed. Films can be deposited on the ground or also fixed on the walls or even on the ceiling. The film is a plastic sheet covered with an emulsion containing photostimulable crystals and Eu that is activated when the film is exposed on radioactive source. The exposed films are then scanned with the Cyclone Plus equipment to get a digitized image. This image represents the radioactivity of the surface studied. The possibility to re-use the films is very important to investigate a large area. This autoradiography technique has retained our attention for its sensitivity and moreover the possibility of 2-dimensional investigation has been found as a real advantage. However it remains now as a qualitative technique and new studies must be launched to prove its quantitative potentialities. The high spatial resolution was not as important as in biological observation, and the mm resolution is totally sufficient

Application of Monte Carlo method in study of the padronization for radionuclides with complex disintegration scheme in 4{pi}{beta}-{gamma} coincidence System; Aplicacao do metodo de Monte Carlo no estudo da padronizacao de radionuclideos com esquema de desintegracao complexos em sistema de coincidencias 4{pi}{beta}-{gamma}

Energy Technology Data Exchange (ETDEWEB)

Takeda, Mauro Noriaki

2006-07-01

The present work described a new methodology for modelling the behaviour of the activity in a 4{pi}{beta}-{gamma} coincidence system. The detection efficiency for electrons in the proportional counter and gamma radiation in the NaI(Tl) detector was calculated using the Monte Carlo program MCNP4C. Another Monte Carlo code was developed which follows the path in the disintegration scheme from the initial state of the precursor radionuclide, until the ground state of the daughter nucleus. Every step of the disintegration scheme is sorted by random numbers taking into account the probabilities of all {beta}{sup -} branches, electronic capture branches, transitions probabilities and internal conversion coefficients. Once the final state was reached beta, electronic capture events and gamma transitions are accounted for the three spectra: beta, gamma and coincidence variation in the beta efficiency was performed simulating energy cut off or use of absorbers (Collodion). The selected radionuclides for simulation were: {sup 134}Cs, {sup 72}Ga which disintegrate by {beta}{sup -} transition, {sup 133}Ba which disintegrates by electronic capture and {sup 35}S which is a beta pure emitter. For the latter, the Efficiency Tracing technique was simulated. The extrapolation curves obtained by Monte Carlo were filled by the Least Square Method with the experimental points and the results were compared to the Linear Extrapolation method. (author)

Calibration of photon and beta ray sources used in brachytherapy. Guidelines on standardized procedures at Secondary Standards Dosimetry Laboratories (SSDLs) and hospitals

International Nuclear Information System (INIS)

2002-03-01

It has generally been recognized that international harmonization in radiotherapy dosimetry is essential. Consequently, the IAEA has given much effort to this, for example by publishing a number of reports in the Technical Reports Series (TRS) for external beam dosimetry, most notably TRS-277 and more recently TRS-398. Both of these reports describe in detail the steps to be taken for absorbed dose determination in water and they are often referred to as 'dosimetry protocols'. Similar to TRS-277, it is expected that TRS-398 will be adopted or used as a model by a large number of countries as their national protocol. In 1996, the IAEA established a calibration service for low dose rate (LDR) 137 Cs brachytherapy sources, which is the most widely used source for treatment of gynecological cancer. To further enhance harmonization in brachytherapy dosimetry, the IAEA published in 1999 IAEA-TECDOC-1079 entitled 'Calibration of Brachytherapy Sources. Guidelines on Standardized Procedures for the Calibration of Brachytherapy Sources at Secondary Standard Dosimetry Laboratories (SSDLs) and Hospitals'. The report was well received and was distributed in a large number of copies to the members of the IAEA/WHO network of SSDLs and to medical physicists working with brachytherapy. The present report is an update of the aforementioned TECDOC. Whereas TECDOC-1079 described methods for calibrating brachytherapy sources with photon energies at or above those of 192 Ir, the current report has a wider scope in that it deals with standardization of calibration of all the most commonly used brachytherapy sources, including both photon and beta emitting sources. The latter sources have been in use for a few decades already, but their calibration methods have been unclear. Methods are also described for calibrating sources used in the rapidly growing field of cardiovascular angioplasty. In this application, irradiation of the vessel wall is done in an attempt to prevent restenosis after

The contribution of chemical speciation to internal dosimetry

International Nuclear Information System (INIS)

Paquet, F.; Frelon, S.; Cote, G.; Madic, C.

2003-01-01

Speciation studies refer to the distribution of species in a particular sample or matrix. These studies are necessary to improve the description, understanding and prediction of trace element kinetics and toxicity. In the case of internal contamination with radionuclides, speciation studies could help to improve both the biokinetic and dosimetric models for radionuclides. There are different methods to approach the speciation of radionuclides in a biological system, depending on the degree of accuracy needed and the level of uncertainties accepted. Among them, computer modelling and experimental determination are complementary approaches. This paper describes what is known about speciation of actinides in blood, GI tract, liver and skeleton and of their consequences in terms of internal dosimetry. The conclusion is that such studies provide very valuable data and should be targeted in the future on some specific tissues and biomolecules. (author)

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

International Nuclear Information System (INIS)

Ferro F, G.

1999-01-01

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

Radionuclide data

International Nuclear Information System (INIS)

Anon.

1992-01-01

Chapter 8 presents tables on selected alpha, beta, gamma and x-ray emitters by increasing energy; information on specific activity for selected radionuclides; naturally occurring radionuclides; the natural decay series; and the artificially produced neptunium series. A table of alpha emitters is listed by increasing atomic number and by energy. The table of β emitters presented is useful in identifying β emitters whose energies and possibly half-lives have been determined by standard laboratory techniques. It is also a handy guide to β-emitting isotopes for applications requiring specific half-lives and/or energies. Gamma rays for radionuclides of importance to radiological assessments and radiation protection are listed by increasing energy. The energies and branching ratios are important for radionuclide determinations with gamma spectrometry detectors. This section also presents a table of x-ray energies which are useful for radiochemical analyses. A number of nuclides emit x-rays as part of their decay scheme. These x-rays may be counted with Ar proportional counters, Ge planar or n-type Ge co-axial detectors, or thin crystal NaI(T1) scintillation counters. In both cases, spectral measurements can be made and both qualitative and quantitative information obtained on the sample. Nuclear decay data (energy and probability by radiation type) for more than one hundred radionuclides that are important to health physicists are presented in a schematic manner

Dosimetry and effects of fetal irradiation from incorporated radionuclides

International Nuclear Information System (INIS)

Harrison, J.D.; Coffigny, H.; Henshaw, D.L.

1993-01-01

An important aspect of the assessment of risks from incorporated radionuclides is the possibility of intakes by pregnant women and in utero exposure of the developing fetus. The overall objective of the project is to provide experimental data for the development of dosimetric models and assessment of risk. Studies include measurements of 210 Po and 239/240 Pu in human fetal tissues and placentae, animal studies of the biokinetics of radionuclide transfer and effects. Animal biokinetic studies concentrate on comparing the uptake and distribution of Po-210, Pu-238 and Am-241 in rats and guinea pigs for different exposure conditions. The data are used, together with the human data, to develop dosimetric models. Objectives and results of the three contributions to the project for the reporting period are presented. (R.P.) 4 figs., 1 tab

Method for measuring the disintegration rate of a beta-emitting radionuclide in a liquid sample

International Nuclear Information System (INIS)

1977-01-01

A method of measuring the distintegration rate of a beta-emitting radionuclide in a liquid sample by counting at least two differently quenched versions of the sample. In each counting operation the sample is counted in the presence of and in the absence of a standard radioactive source. A pulse height (PH) corresponding to a unique point on the pulse height spectrum generated in the presence of the standard is determined. A zero threshold sample count rate (CPM) is derived by counting the sample once in a counting window having a zero threshold lower limit. Normalized values of the measured pulse heights (PH) are developed and correlated with the corresponding counts (CPM) to determine the pulse count for a normalized pulse height value of zero and hence the sample disintegration rate

Blood flow measurements in the irradiated pig skin using {beta} emitters radionuclides; Mesure de la circulation sanguine cutanee chez le porc irradie a l`aide de radioisotopes emetteurs {beta}

Energy Technology Data Exchange (ETDEWEB)

Daburon, F; Lefaix, J L; Leplat, J J; Fayart, G; Delacroix, D; Le Thanh, P

1997-01-01

Non invasive methods of study of the skin blood flow are numerous, but generally do not give any indication on the cutaneous micro-circulatory flow, except for cutaneous laser Doppler. The isotopic exploration of the skin with injected {gamma} radionuclides, even of weak energy, doe snot allow to characterize the skin blood flow, because of the important contribution of the subcutaneous tissues. The use of {beta} emitters energy spectrum, analyzed by different quantitative methods, are proportional to the thickness of the screen localized between the radioactive source and detector. Using simple and complex phantoms composed of tissue equivalent screens, with {sup 32}P sources placed at different depths, it was possible to study the degradation of {beta} spectra, simulating respectively the sub-epidermis and sub-dermis vascular levels. A modelization and an experimental study in-vivo are proposed in this work, with {sup 32}P phosphate administered intravenously in pigs. (author).

Radiation-Induced Second Cancer Risk Estimates From Radionuclide Therapy

Science.gov (United States)

Bednarz, Bryan; Besemer, Abigail

2017-09-01

The use of radionuclide therapy in the clinical setting is expected to increase significantly over the next decade. There is an important need to understand the radiation-induced second cancer risk associated with these procedures. In this study the radiation-induced cancer risk in five radionuclide therapy patients was investigated. These patients underwent serial SPECT imaging scans following injection as part of a clinical trial testing the efficacy of a 131Iodine-labeled radiopharmaceutical. Using these datasets the committed absorbed doses to multiple sensitive structures were calculated using RAPID, which is a novel Monte Carlo-based 3D dosimetry platform developed for personalized dosimetry. The excess relative risk (ERR) for radiation-induced cancer in these structures was then derived from these dose estimates following the recommendations set forth in the BEIR VII report. The radiation-induced leukemia ERR was highest among all sites considered reaching a maximum value of approximately 4.5. The radiation-induced cancer risk in the kidneys, liver and spleen ranged between 0.3 and 1.3. The lifetime attributable risks (LARs) were also calculated, which ranged from 30 to 1700 cancers per 100,000 persons and were highest for leukemia and the liver for both males and females followed by radiation-induced spleen and kidney cancer. The risks associated with radionuclide therapy are similar to the risk associated with external beam radiation therapy.

Status of beta measurement evaluation and upgrade program

International Nuclear Information System (INIS)

Swinth, K.L.

1986-01-01

In 1983, the US Department of Energy (DOE) initiated a program to evaluate and upgrade beta dosimetry capabilities at DOE and DOE-contractor facilities. The program has several elements which structure the development of improvements in beta measurement practices. In addition to Pacific Northwest Laboratory (PNL), universities, private corporations, and other DOE facilities are involved in the research efforts

100 Years of radionuclide metrology

International Nuclear Information System (INIS)

Judge, S.M.; Arnold, D.; Chauvenet, B.; Collé, R.; De Felice, P.; García-Toraño, E.; Wätjen, U.

2014-01-01

The discipline of radionuclide metrology at national standards institutes started in 1913 with the certification by Curie, Rutherford and Meyer of the first primary standards of radium. In early years, radium was a valuable commodity and the aim of the standards was largely to facilitate trade. The focus later changed to providing standards for the new wide range of radionuclides, so that radioactivity could be used for healthcare and industrial applications while minimising the risk to patients, workers and the environment. National measurement institutes responded to the changing demands by developing new techniques for realising primary standards of radioactivity. Looking ahead, there are likely to be demands for standards for new radionuclides used in nuclear medicine, an expansion of the scope of the field into quantitative imaging to facilitate accurate patient dosimetry for nuclear medicine, and an increasing need for accurate standards for radioactive waste management and nuclear forensics. - Highlights: • The driving forces for the development of radionuclide metrology. • Radium standards to facilitate trade of this valuable commodity in the early years. • After 1950, focus changes to healthcare and industrial applications. • National Measurement Institutes develop new techniques, standards, and disseminate the best practice in measurement. • Challenges in nuclear medicine, radioactive waste management and nuclear forensics

Hanford Internal Dosimetry Project manual. Revision 1

International Nuclear Information System (INIS)

Carbaugh, E.H.; Bihl, D.E.; MacLellan, J.A.; Long, M.P.

1994-07-01

This document describes the Hanford Internal Dosimetry Project, as it is administered by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy and its Hanford contractors. Project services include administrating the bioassay monitoring program, evaluating and documenting assessment of potential intakes and internal dose, ensuring that analytical laboratories conform to requirements, selecting and applying appropriate models and procedures for evaluating radionuclide deposition and the resulting dose, and technically guiding and supporting Hanford contractors in matters regarding internal dosimetry. Specific chapters deal with the following subjects: practices of the project, including interpretation of applicable DOE Orders, regulations, and guidance into criteria for assessment, documentation, and reporting of doses; assessment of internal dose, including summary explanations of when and how assessments are performed; recording and reporting practices for internal dose; selection of workers for bioassay monitoring and establishment of type and frequency of bioassay measurements; capability and scheduling of bioassay monitoring services; recommended dosimetry response to potential internal exposure incidents; quality control and quality assurance provisions of the program

Hanford Internal Dosimetry Project manual. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Carbaugh, E.H.; Bihl, D.E.; MacLellan, J.A.; Long, M.P.

1994-07-01

This document describes the Hanford Internal Dosimetry Project, as it is administered by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy and its Hanford contractors. Project services include administrating the bioassay monitoring program, evaluating and documenting assessment of potential intakes and internal dose, ensuring that analytical laboratories conform to requirements, selecting and applying appropriate models and procedures for evaluating radionuclide deposition and the resulting dose, and technically guiding and supporting Hanford contractors in matters regarding internal dosimetry. Specific chapters deal with the following subjects: practices of the project, including interpretation of applicable DOE Orders, regulations, and guidance into criteria for assessment, documentation, and reporting of doses; assessment of internal dose, including summary explanations of when and how assessments are performed; recording and reporting practices for internal dose; selection of workers for bioassay monitoring and establishment of type and frequency of bioassay measurements; capability and scheduling of bioassay monitoring services; recommended dosimetry response to potential internal exposure incidents; quality control and quality assurance provisions of the program.

The work of committee 2 of ICRP on internal dosimetry

International Nuclear Information System (INIS)

Stather, J.W.

2005-01-01

Full text: Over the last few years the Task Group of Committee 2 of ICRP on Internal Dosimetry (INDOS), in conjunction with the Task Group on Dose Calculations (DOCAL), has prepared a series of publications that have given dose coefficients for intakes of radionuclides by infants, children and adults. The most recent publications have been Publication 88 that gives doses to the embryo, fetus and newborn child from intakes of radionuclides by the mother and Publication 94 that will give doses to the newborn child from intakes of radionuclides in mothers' milk. These documents have completed the programme of work of Committee 2 on dose coefficients for members of the public. The emphasis of work on internal dosimetry by Committee 2 is now concerned with occupational exposure. This is will take into account recent advice from ICRP, including the new 2005 Recommendations of ICRP which are expected to provide revised tissue weighting factors for the calculation of effective dose. In addition ICRP has issued Publication 89 on Basic Anatomical and Physiological Data for use in Radiological Protection and in addition will have published a new Human Alimentary Tract Model (HATM). It will have implemented a human phantom for dose calculations based upon medical imaging data and updated radionuclide decay data; superseding Publication 38. In addition, the systemic models for a number of elements are being revised to take account of more recent data, and the lung clearance characteristics of a wide range of compounds relevant to occupational exposure are being reviewed. It is intended to replace Publications 30 and 68 that give biokinetic data and dose coefficients for intakes of radionuclides and Publications 54 and 78 that give information for bioassay interpretation, with a single series of publications. This series will cover both dosimetry and data for bioassay interpretation. The first report will cover radionuclides of the 31 elements covered in the series of

Skeletal dosimetry models for alpha-particles for use in molecular radiotherapy

Science.gov (United States)

Watchman, Christopher J.

Molecular radiotherapy is a cancer treatment methodology whereby a radionuclide is combined with a biologically active molecule to preferentially target cancer cells. Alpha-particle emitting radionuclides show significant potential for use in molecular radiotherapy due to the short range of the alpha-particles in tissue and their high rates of energy deposition. Current radiation dosimetry models used to assess alpha emitter dose in the skeleton were developed originally for occupational applications. In medical dosimetry, individual variability in uptake, translocation and other biological factors can result in poor correlation of clinical outcome with marrow dose estimates determined using existing skeletal models. Methods presented in this work were developed in response to the need for dosimetry models which account for these biological and patient-specific factors. Dosimetry models are presented for trabecular bone alpha particle dosimetry as well as a model for cortical bone dosimetry. These radiation transport models are the 3D chord-based infinite spongiosa transport model (3D-CBIST) and the chord-based infinite cortical transport model (CBICT), respectively. Absorbed fraction data for several skeletal tissues for several subjects are presented. Each modeling strategy accounts for biological parameters, such as bone marrow cellularity, not previously incorporated into alpha-particle skeletal dosimetry models used in radiation protection. Using these data a study investigating the variability in alpha-particle absorbed fractions in the human skeleton is also presented. Data is also offered relating skeletal tissue masses in individual bone sites for a range of ages. These data are necessary for dose calculations and have previously only been available as whole body tissue masses. A revised 3D-CBIST model is also presented which allows for changes in endosteum thickness to account for revised target cell location of tissues involved in the radiological

Fourth international radiopharmaceutical dosimetry symposium

International Nuclear Information System (INIS)

Schlafke-Stelson, A.T.; Watson, E.E.

1986-04-01

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

Dosimetry of Radiopharmaceuticals for Diagnostic and Therapeutic Nuclear Medicine

International Nuclear Information System (INIS)

Smart, Richard

2011-01-01

A standard formalism for radionuclide internal radiation dosimetry was developed in the 1960s and continues to be refined today. Early work was based on a mathematical phantom but this is being replaced by phantoms developed from whole-body CT scans to give more realistic dose estimates. The largest contributors to the uncertainties in these dose estimates are the errors associated with in vivo activity quantitation, the variability of the biokinetics between patients and the limited information that can be obtained on these kinetics in individual patients. Despite these limitations, pre-treatment patient-specific dosimetry is being increasing used, particularly to limit the toxicity to non-target organs such as the bone marrow.

Fast neutron dosimetry

International Nuclear Information System (INIS)

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

1992-01-01

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

Internal Dosimetry. Chapter 18

Energy Technology Data Exchange (ETDEWEB)

Hindorf, C. [Department of Radiation Physics, Skåne University Hospital, Lund (Sweden)

2014-12-15

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

Beta measurement evaluation and upgrade

International Nuclear Information System (INIS)

Swinth, K.L.; Rathbun, L.A.; Roberson, P.L.; Endres, G.W.R.

1986-01-01

This program focuses on the resolution of problems associated with the field measurement of the beta dose component at Department of Energy (DOE) facilities. The change in DOE programs, including increased efforts in improved waste management and decontamination and decommissioning (D and D) of facilities, coupled with beta measurement problems identified at Three Mile Island has increased the need to improve beta measurements. In FY 1982, work was initiated to provide a continuing effort to identify problems associated with beta dose assessment at DOE facilities. The problems identified resulted in the development of this program. The investigation includes (1) an assessment of measurement systems now in use, (2) development of improved calibration systems and procedures, (3) application of innovative beta dosimetry concepts, (4) investigation of new instruments or concepts for monitoring and spectroscopy, and (5) development of recommendations to assure an adequate beta measurement program within DOE facilities

Counting efficiency for radionuclides decaying by beta and gamma-ray emission; Calculo de la eficiencia de recuento de nucleidos que experimentan desintegracion beta y desexcitacion gamma simple

Energy Technology Data Exchange (ETDEWEB)

Grau, A.; Garcia-Torano, E.

1988-07-01

In this paper, counting efficiency vs figure of merit for beta and gamma-ray emitters has been computed. It is assumed that the decay scheme has only a gamma level and the beta-ray emission may be coincident with the gamma-rays or the internal-conversion electrons. The radionuclides tabulated are: 20 {sub 0}, 20{sub p}, 28{sub A}l, 35{sub p}, 41{sub A}r, 42{sub K}, 47{sub S}e, 62{sub F}e, 66{sub C}u, 81{sub G}e, 86{sub B}b, 108{sub R}u, 112{sub p}d, 121{sub S}n(Ni), 122{sub I}n, 129{sub I}, 141{sub C}e 171{sub T}m, 194{sub O}s, 2O3{sub H}g, 205{sub H}g, 210{sub p}b, 225{sub R}a, 142{sub p}r, 151{sub S}m, 244{sub A}m(m). It has been assumed that the liquid is a toluene based scintillator solution in standard glass vials containing 10 cm''3. (Author) 8 refs.

Dosimetry in intravascular brachytherapy

International Nuclear Information System (INIS)

Campos, Laelia Pumilla Botelho

2000-03-01

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

Dosimetry of β extensive sources

International Nuclear Information System (INIS)

Rojas C, E.L.; Lallena R, A.M.

2002-01-01

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

The photodiodes response in beta dosimetry

International Nuclear Information System (INIS)

Khoury, Helen; Amaral, Ademir; Hazin, Clovis; Melo, Francisco

1996-01-01

The response of the photodiodes BPY-12, BPW-34 and SFH-206 is tested for use as beta dosimeters. The results obtained show a dose-response relationships as well as less than 1% of coefficient of variation for the reproducibility of their responses. The photodiode BPY-12 has presented a better response in comparison with the others

Internal dosimetry and control

International Nuclear Information System (INIS)

Rich, B.L.

1990-05-01

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

Radiosynoviorthesis. Clinical and preclinical dosimetry

International Nuclear Information System (INIS)

Torres Berdeguez, Mirta B; Ayra Pardo, Fernando E

2006-01-01

Accurate calculation of internal dose estimates in the Radiosynoviorthesis treatment requires several steps of analysis. The use of animal models (rabbits) to predict human kinetics and dosimetry is an essential first step in the evaluation of new radiocolloids, but involves many uncertainties. There is no gold standard method for extrapolating animal data to humans. Nonetheless, human dose estimates based on animal data are considered to be reasonable approximations to be used for proceeding with dose estimates based on human data, which are ultimately used to assess the safety and efficacy evaluations of radiopharmaceuticals, and continues to be an important element in the radiopharmaceutical approval process. The obtained absorbed dose profiles versus synovial tissue, bone and articular cartilage depth will permit the specialist to prescribe the adequate dose of radionuclide to treat rheumatoid arthritis in medium and large joints without expose the healthy structures of the synovial joint to an excessive and unnecessary irradiation risk, eliminating the fixed dose and fixed radionuclides for each joints (Author)

Radionuclides: Accumulation and Transport in Plants.

Science.gov (United States)

Gupta, D K; Chatterjee, S; Datta, S; Voronina, A V; Walther, C

Application of radioactive elements or radionuclides for anthropogenic use is a widespread phenomenon nowadays. Radionuclides undergo radioactive decays releasing ionizing radiation like gamma ray(s) and/or alpha or beta particles that can displace electrons in the living matter (like in DNA) and disturb its function. Radionuclides are highly hazardous pollutants of considerable impact on the environment, food chain and human health. Cleaning up of the contaminated environment through plants is a promising technology where the rhizosphere may play an important role. Plants belonging to the families of Brassicaceae, Papilionaceae, Caryophyllaceae, Poaceae, and Asteraceae are most important in this respect and offer the largest potential for heavy metal phytoremediation. Plants like Lactuca sativa L., Silybum marianum Gaertn., Centaurea cyanus L., Carthamus tinctorius L., Helianthus annuus and H. tuberosus are also important plants for heavy metal phytoremediation. However, transfer factors (TF) of radionuclide from soil/water to plant ([Radionuclide]plant/[Radionuclide]soil) vary widely in different plants. Rhizosphere, rhizobacteria and varied metal transporters like NRAMP, ZIP families CDF, ATPases (HMAs) family like P1B-ATPases, are involved in the radio-phytoremediation processes. This review will discuss recent advancements and potential application of plants for radionuclide removal from the environment.

Performance analysis of numeric solutions applied to biokinetics of radionuclides

International Nuclear Information System (INIS)

Mingatos, Danielle dos Santos; Bevilacqua, Joyce da Silva

2013-01-01

Biokinetics models for radionuclides applied to dosimetry problems are constantly reviewed by ICRP. The radionuclide trajectory could be represented by compartmental models, assuming constant transfer rates between compartments. A better understanding of physiological or biochemical phenomena, improve the comprehension of radionuclide behavior in the human body and, in general, more complex compartmental models are proposed, increasing the difficulty of obtaining the analytical solution for the system of first order differential equations. Even with constant transfer rates numerical solutions must be carefully implemented because of almost singular characteristic of the matrix of coefficients. In this work we compare numerical methods with different strategies for ICRP-78 models for Thorium-228 and Uranium-234. The impact of uncertainty in the parameters of the equations is also estimated for local and global truncation errors. (author)

Natural radionuclides monitoring in Lombardia drinking water by liquid scintillation technique

International Nuclear Information System (INIS)

Forte, M.; Rusconi, R.; Bellinsona, S.; Sgorbati, G.

2002-01-01

Concern about total radionuclides content in water intended for human consumption has been brought to public attention by the recent Council Directive 98/83/EC, subsequently enforced through an Italian law (DL 31, February 2., 2001). Parameter values have been fixed for Tritium content and total indicative dose: the Directive points out that the total indicative dose must be evaluated excluding Tritium, 4 0K , 1 4C , Radon and its decay products, but including all other natural series radionuclides. Maximum concentration values for Radon are separately proposed in Commission Recommendation 2001/928/Euratom. Tritium determination follows a well established procedure, standardised by International Standard Organisation (ISO 9698, 1989). On the contrary, total indicative dose evaluation requires more specific and cumbersome procedures for the measurement of radioactivity content, with special regard to natural series radionuclides. The large number of possibly involved radionuclides and the good sensitivities required make the application of traditional analytical techniques unsuitable in view of a large scale monitoring program. World Health Organisation (WHO 1993 and 1996) guidelines for drinking water suggest performing an indirect evaluation of committed dose by measuring alpha and beta gross radioactivity and checking compliance to derived limit values; the proposed limit values are 0,1 Bq/l for gross alpha and 1 Bq/l for gross beta radioactivity. Nevertheless, it is desirable to identify single radionuclides contribution to alpha and beta activity in order to perform more accurate measurements of committed dose

The internal dosimetry code PLEIADES.

Science.gov (United States)

Fell, T P; Phipps, A W; Smith, T J

2007-01-01

The International Commission on Radiological Protection (ICRP) has published dose coefficients for the ingestion or inhalation of radionuclides in a series of reports covering intakes by workers and members of the public, including children and pregnant or lactating women. The calculation of these coefficients divides naturally into two distinct parts-the biokinetic and dosimetric. This paper describes in detail the methods used to solve the biokinetic problem in the generation of dose coefficients on behalf of the ICRP, as implemented in the Health Protection Agency's internal dosimetry code PLEIADES. A summary of the dosimetric treatment is included.

The internal dosimetry code PLEIADES

International Nuclear Information System (INIS)

Fell, T. P.; Phipps, A. W.; Smith, T. J.

2007-01-01

The International Commission on Radiological Protection (ICRP) has published dose coefficients for the ingestion or inhalation of radionuclides in a series of reports covering intakes by workers and members of the public, including children and pregnant or lactating women. The calculation of these coefficients divides naturally into two distinct parts - the biokinetic and dosimetric. This paper describes in detail the methods used to solve the biokinetic problem in the generation of dose coefficients on behalf of the ICRP, as implemented in the Health Protection Agency's internal dosimetry code PLEIADES. A summary of the dosimetric treatment is included. (authors)

Application of the linear-quadratic model with incomplete repair to radionuclide directed therapy

International Nuclear Information System (INIS)

Millar, W.T.; Glasgow Univ.

1991-01-01

The LQ model has now been extended to include a general time varying dose rate profile, and the equations can be readily evaluated if an exponential radiation damage repair process is assumed. These equations are applicable to radionuclide directed therapy, including brachytherapy. Kinetic uptake data obtained during radionuclide directed therapy may therefore be used to determine the radiobiological dosimetry of the target and non-target tissues. Also, preliminary tracer studies may be used to pre-plan the radionuclide directed therapy, provided that tracer and therapeutic amounts of the radionuclide carrier are identically processed by the tissues. It is also shown that continuous radionuclide therapy will induce less damage in late-responding tissues than 2 Gy/fraction external beam therapy if the ratio of the maximum dose rate and the sublethal damage repair half-life in the tissue is less than 1.0 Gy. Similar inequalities may be derived for β-particle radionuclide directed therapy. (author)

Speciation and internal dosimetry: from chemical species to dosimetric models

International Nuclear Information System (INIS)

Paquet, F.; Frelon, S.; Cote, G.; Madic, C.

2004-01-01

Speciation studies refer to the distribution of species in a particular sample or matrix. These studies are necessary to improve the description, understanding and prediction of trace element kinetics and toxicity. In case of internal contamination with radionuclides, speciation studies could help to improve both the biokinetic and dosimetric models for radionuclides. There are different methods to approach the speciation of radionuclide in a biological system, depending on the degree of accuracy needed and the level of uncertainties accepted. Among them, computer modelling and experimental determination are complementary approaches. This paper describes what is known about speciation of actinides in blood, GI-tract, liver and skeleton and of their consequences in terms of internal dosimetry. The conclusion is that such studies provide very valuable data and should be targeted in the future on some specific tissues and biomolecules. (authors)

Li-Ion Batteries for Forensic Neutron Dosimetry

Science.gov (United States)

2016-03-01

Li-Ion Batteries for Forensic Neutron Dosimetry Distribution Statement A. Approved for public release, distribution is unlimited. March...ion batteries are the common technology for powering portable electronics. The nuclear reactions within the batteries are sensitive to neutrons. By...and chemical changes within the battery . These changes can be determined by mass spectrometry or gamma and beta spectroscopy of long-lived

Study of a 4{pi}{beta}-{gamma} coincidence system for absolute radionuclide activity measurement using plastic scintillators; Estudo de um sistema de coincidencias 4{pi}{beta}-{gamma} para a medida absoluta de atividade de radionuclideos empregando cintiladores plasticos

Energy Technology Data Exchange (ETDEWEB)

Piuvezam Filho, Helio

2007-07-01

The present work was intended to study a coincidence system 4{pi}(PS){beta}-{gamma} for absolute activity measurement using plastic scintillators in 4{pi} geometry. Along with experiments on the coincidence system, simulations were also performed applying the Monte Carlo Method, by means of codes PENELOPE and ESQUEMA. These simulations were performed in order to calculate the extrapolation curve of the coincidence system 4{pi}(PS){beta}-{gamma} and compare it to experimental data. A new geometry was proposed to the coincidence system adding up a second photomultiplier tube to the previous system for improving light collection from the plastic scintillator, as this system presented limitations in the minimum detected energy due to the presence of electronic noise and low gain. The results show that an improvement in the signal-to-noise ratio was obtained, as well as in the minimum detected energy. Moreover, there was an increase in the detection efficiency. With these modifications, it is now possible to calibrate radionuclides which emit low energy electrons or X-rays, increasing the number of radionuclides that can be standardized with this type of system.(author)

Radionuclides in radiation-induced bystander effect; may it share in radionuclide therapy?

Science.gov (United States)

Widel, M

2017-01-01

For many years in radiobiology and radiotherapy predominated the conviction that cellular DNA is the main target for ionizing radiation, however, the view has changed in the past 20 years. Nowadays, it is assumed that not only directed (targeted) radiation effect, but also an indirect (non-targeted) effect may contribute to the result of radiation treatment. Non-targeted effect is relatively well recognized after external beam irradiation in vitro and in vivo, and comprises such phenomena like radiation-induced bystander effect (RIBE), genomic instability, adaptive response and abscopal (out of field) effect. These stress-induced and molecular signaling mediated phenomena appear in non-targeted cells as variety responses resembling that observed in directly hit cells. Bystander effects can be both detrimental and beneficial in dependence on dose, dose-rate, cell type, genetic status and experimental condition. Less is known about radionuclide-induced non-targeted effects in radionuclide therapy, although, based on characteristics of the radionuclide radiation, on experiments in vitro utilizing classical and 3-D cell cultures, and preclinical study on animals it seems obvious that exposure to radionuclide is accompanied by various bystander effects, mostly damaging, less often protective. This review summarizes existing data on radionuclide induced bystander effects comprising radionuclides emitting beta- and alpha-particles and Auger electrons used in tumor radiotherapy and diagnostics. So far, separation of the direct effect of radionuclide decay from crossfire and bystander effects in clinical targeted radionuclide therapy is impossible because of the lack of methods to assess whether, and to what extent bystander effect is involved in human organism. Considerations on this topic are also included.

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.)

Technical basis document for internal dosimetry

International Nuclear Information System (INIS)

Hickman, D.P.

1991-01-01

This document provides the technical basis for the Chem-Nuclear Geotech (Geotech) internal dosimetry program. Geotech policy describes the intentions of the company in complying with radiation protection standards and the as low as reasonably achievable (ALARA) program. It uses this policy and applicable protection standards to derive acceptable methods and levels of bioassay to assure compliance. The models and computational methods used are described in detail within this document. FR-om these models, dose- conversion factors and derived limits are computed. These computations are then verified using existing documentation and verification information or by demonstration of the calculations used to obtain the dose-conversion factors and derived limits. Recommendations for methods of optimizing the internal dosimetry program to provide effective monitoring and dose assessment for workers are provided in the last section of this document. This document is intended to be used in establishing an accredited dosimetry program in accordance with expected Department of Energy Laboratory Accreditation Program (DOELAP) requirements for the selected radionuclides provided in this document, including uranium mill tailing mixtures. Additions and modifications to this document and procedures derived FR-om this document are expected in the future according to changes in standards and changes in programmatic mission

Tumour therapy with radionuclides: assessment of progress and problems

International Nuclear Information System (INIS)

Carlsson, Joergen; Forssell Aronsson, Eva; Hietala, Sven-Ola; Stigbrand, Torgny; Tennvall, Jan

2003-01-01

Radionuclide therapy is a promising modality for treatment of tumours of haematopoietic origin while the success for treatment of solid tumours so far has been limited. The authors consider radionuclide therapy mainly as a method to eradicate disseminated tumour cells and small metastases while bulky tumours and large metastases have to be treated surgically or by external radiation therapy. The promising therapeutic results for haematological tumours give hope that radionuclide therapy will have a breakthrough also for treatment of disseminated cells from solid tumours. New knowledge related to this is continuously emerging since new molecular target structures are being characterised and the knowledge on pharmacokinetics and cellular processing of different types of targeting agents increases. There is also improved understanding of the factors of importance for the choice of appropriate radionuclides with respect to their decay properties and the therapeutic applications. Furthermore, new methods to modify the uptake of radionuclides in tumour cells and normal tissues are emerging. However, we still need improvements regarding dosimetry and treatment planning as well as an increased knowledge about the tolerance doses for normal tissues and the radiobiological effects on tumour cells. This is especially important in targeted radionuclide therapy where the dose rates often are lower than 1 Gy/h

Monte Carlo dosimetry of a tandem positioned beta-emitting intravascular brachytherapy source train

International Nuclear Information System (INIS)

Wallace, Steven A.; Schumer, Wendy; Horrigan, Mark

2002-01-01

Prevention of restenosis following interventional coronary procedures with catheter based beta-emitting sources is currently under clinical trial investigations. Systems utilizing fixed length source trains limit the clinician's ability to increase the radiation source length as required. A technique known as 'pull back' is used when the segment of artery requiring radiation is longer than the available fixed length source train. In this instance, tandem positioning of the fixed length source is used to treat the longer length of artery. The aim of this study was to examine the dosimetry of the junction region associated with pull back treatments using a commercially available 90 Sr/Y catheter based intravascular brachytherapy source train. Dose profiles were calculated, using the Monte Carlo code MCNP4B, at radial distances of 1.5, 2.0, and 2.5 mm for pull back techniques using 2.5 mm overlapping, abutting, and 2.5 mm spaced source trains. Results at the protocol prescription radius of 2 mm showed a junction dose elevated 61% above prescription for 2.5 mm overlapping source trains. For 2.5 mm spaced trains, this figure falls to 64% below prescription dose. In contrast, abutted source trains exhibited only a 1% depression below prescription dose in the junction region. The reference point dose rate per unit activity of this source was found to be consistent with previous studies

Introduction to radiobiology of targeted radionuclide therapy

Directory of Open Access Journals (Sweden)

Jean-Pierre ePOUGET

2015-03-01

Full Text Available During the last decades, new radionuclide-based targeted therapies have emerged as efficient tools for cancer treatment. Targeted radionuclide therapies (TRT are based on a multidisciplinary approach that involves the cooperation of specialists in several research fields. Among them, radiobiologists investigate the biological effects of ionizing radiation, specifically the molecular and cellular mechanisms involved in the radiation response. Most of the knowledge about radiation effects concerns external beam radiation therapy (EBRT and radiobiology has then strongly contributed to the development of this therapeutic approach. Similarly, radiobiology and dosimetry are also assumed to be ways for improving TRT, in particular in the therapy of solid tumors which are radioresistant. However, extrapolation of EBRT radiobiology to TRT is not straightforward. Indeed, the specific physical characteristics of TRT (heterogeneous and mixed irradiation, protracted exposure and low absorbed dose rate differ from those of conventional EBRT (homogeneous irradiation, short exposure and high absorbed dose rate, and consequently the response of irradiated tissues might be different. Therefore, specific TRT radiobiology needs to be explored. Determining dose-effect correlation is also a prerequisite for rigorous preclinical radiobiology studies because dosimetry provides the necessary referential to all TRT situations. It is required too for developing patient-tailored TRT in the clinic in order to estimate the best dose for tumor control, while protecting the healthy tissues, thereby improving therapeutic efficacy. Finally, it will allow to determine the relative contribution of targeted effects (assumed to be dose-related and non-targeted effects (assumed to be non-dose-related of ionizing radiation. However, conversely to EBRT where it is routinely used, dosimetry is still challenging in TRT. Therefore, it constitutes with radiobiology, one of the main

Electronic personal dosimeter heralds a revolution in legal dosimetry

International Nuclear Information System (INIS)

Fletcher, R.

1991-01-01

The Electronic Personal Dosimeter (EPD) developed by Siemens Plessey Controls and the UK's national Radiological Protection Board is approaching the pre-production stage. It provides ''legal'' dosimetry and all the features of a personal alarming dosimeter. The EPD uses solid state semiconductor detectors for gamma and beta radiation and has a dose threshold of about 1μ Sv, with a low energy gamma range down to 20 KeV. It has a multi function liquid crystal display for instant readout and audible and visual alarms. Two separates dose stores are maintained. Short term dose for tactical management and long term dose for approved dosimetry service record keeping. The latter can be reset only by an approved dosimetry service and is maintained on a search memory disk which can be read even if the EPD is destroyed. (UK)

Development of medical application methods using radiation. Radionuclide therapy

International Nuclear Information System (INIS)

Choi, Chang Woon; Lim, S. M.; Kim, E.H.; Woo, K. S.; Chung, W. S.; Lim, S. J.; Choi, T. H.; Hong, S. W.; Chung, H. Y.; No, W. C.; Oh, B. H.; Hong, H. J.

1999-04-01

In this project, we studied following subjects: 1. development of monoclonal antibodies and radiopharmaceuticals 2. clinical applications of radionuclide therapy 3. radioimmunoguided surgery 4. prevention of restenosis with intracoronary radiation. The results can be applied for the following objectives: 1) radionuclide therapy will be applied in clinical practice to treat the cancer patients or other diseases in multi-center trial. 2) The newly developed monoclonal antibodies and biomolecules can be used in biology, chemistry or other basic life science research. 3) The new methods for the analysis of therapeutic effects, such as dosimetry, and quantitative analysis methods of radioactivity, can be applied in basic research, such as radiation oncology and radiation biology

Development of medical application methods using radiation. Radionuclide therapy

Energy Technology Data Exchange (ETDEWEB)

Choi, Chang Woon; Lim, S. M.; Kim, E.H.; Woo, K. S.; Chung, W. S.; Lim, S. J.; Choi, T. H.; Hong, S. W.; Chung, H. Y.; No, W. C. [Korea Atomic Energy Research Institute. Korea Cancer Center Hospital, Seoul, (Korea, Republic of); Oh, B. H. [Seoul National University. Hospital, Seoul (Korea, Republic of); Hong, H. J. [Antibody Engineering Research Unit, Taejon (Korea, Republic of)

1999-04-01

In this project, we studied following subjects: 1. development of monoclonal antibodies and radiopharmaceuticals 2. clinical applications of radionuclide therapy 3. radioimmunoguided surgery 4. prevention of restenosis with intracoronary radiation. The results can be applied for the following objectives: (1) radionuclide therapy will be applied in clinical practice to treat the cancer patients or other diseases in multi-center trial. (2) The newly developed monoclonal antibodies and biomolecules can be used in biology, chemistry or other basic life science research. (3) The new methods for the analysis of therapeutic effects, such as dosimetry, and quantitative analysis methods of radioactivity, can be applied in basic research, such as radiation oncology and radiation biology.

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.)

Reference beta radiations for calibrating dosemeters and dose ratemeters and for determining their response as a function of beta radiation energy. 1. ed.

International Nuclear Information System (INIS)

1984-01-01

This International Standard specifies the requirements for reference beta radiations produced by radionuclide sources to be used for the calibration of protection level dosemeters and dose ratemeters, and for the determination of their response as a function of beta energy. It gives the characteristics of radionuclides which have been used to produce reference beta radiations, gives examples of suitable source constructions and describes methods for the measurement of the residual maximum beta energy and the absorbed dose rate at a depth of 7 mg·cm -2 in a semi-infinite tissue-equivalent medium. The energy range involved lies between 66 keV and 3.6 MeV and the absorbed dose rates are in the range from about 10 μGy·h -1 (1 mrad·h -1 ) to at least 10 Gy·h -1 (10 3 rad·h -1 ). This International Standard proposes two series of beta reference radiations from which the radiation necessary for determining the characteristics (calibration and energy response) of an instrument shall be selected. Series 1 reference radiations are produced by radionuclide sources used with beam flattening filters designed to give uniform dose rates over a large area at a specific distance. The proposed sources of 90 Sr+ 90 Y, 204 TI and 147 Pm produce maximum dose rates of approximately 5mGy·h -1 (0.5 rad·h -1 ). Series 2 reference radiations are produced without the use of beam flattening filters which allows a range of source-to-calibration plane distances to be used. Close to the sources only relatively small areas of uniform dose rate are produced but this Series has the advantage of extending the energy and dose rate ranges beyond those of Series 1. The radionuclides used are those of Series 1 with the addition of the radionuclides 14 C and 106 Ru+ 106 Rh; these sources produce dose rates of up to 10 Gy·h -1 (10 3 rad·h -1 )

Radionuclide Therapy. Chapter 19

Energy Technology Data Exchange (ETDEWEB)

Flux, G.; Du, Yong [Royal Marsden Hospital and Institute of Cancer Research, Surrey (United Kingdom)

2014-12-15

Cancer has been treated with radiopharmaceuticals since the 1940s. The radionuclides originally used, including 131I and 32P, are still in use. The role of the physicist in radionuclide therapy encompasses radiation protection, imaging and dosimetry. Radiation protection is of particular importance given the high activities of the unsealed sources that are often administered, and must take into account medical staff, comforters and carers, and, as patients are discharged while still retaining activity, members of the public. Regulations concerning acceptable levels of exposure vary from country to country. If the administered radiopharmaceutical is a γ emitter, then imaging can be performed which may be either qualitative or quantitative. While a regular system of quality control must be in place to prevent misinterpretation of image data, qualitative imaging does not usually rely on the image corrections necessary to determine the absolute levels of activity that are localized in the patient. Accurate quantitative imaging is dependent on these corrections and can permit the distribution of absorbed doses delivered to the patient to be determined with sufficient accuracy to be clinically beneficial.

Role of tomography in providing radionuclide distribution and kinetic data

International Nuclear Information System (INIS)

Budinger, T.F.; Derenzo, S.E.; Huesman, R.H.

1981-01-01

A major limitation in radionuclide dosimetry has been the lack of human organ-specific radionuclide distribution and kinetic data because methods of acquiring sequential quantitative information from volumes of interest were not available. Developments in emission computed tomography instrumentation and associated algorithms have overcome this basic limitation, thus allowing in vivo noninvasive tissue distribution studies to be performed. Five aspects of kinetic data acquisition using tomography are: (1) the resolution volume for quantitative work is about two times larger than the system resolution element size as defined by a spread function criterion of full width at half (peak) maximum; (2) scattered radiation might account for 30% of the activity in a given resolution volume and must be taken into account for accurate calculations; (3) proper attenuation compensation must be made to yield quantitative data, particularly with single photon tomography; (4) for dosimetry studies with short half-life labels, multisection systems with dynamic imaging capabilities commensurate with the half-life are needed; (5) the biological conditions such as patient disease and dietary history and the specific activity of the radiopharmaceutical are factors of prime importance in the distribution kinetics

The work of Committee 2 of ICRP on internal dosimetry

International Nuclear Information System (INIS)

Stather, J.W.

2007-01-01

Following publication of new recommendations by ICRP, a series of publications on Occupational Intakes of Radionuclides (OIR) will give both dose coefficients for intakes of radionuclides and data for the interpretation of bioassay information. Account will be taken of revised tissue weighting factors given in the new recommendations and a number of additional developments. These include new human phantoms based upon medical imaging data for calculating doses to body tissues and the new Human Alimentary Tract Model. In addition, parameter values for the Human Respiratory Tract Model are being reviewed, radionuclide decay data are being updated and systemic models for a number of elements revised to take account of more recent data and to provide models that are appropriate for both dosimetry and for bioassay interpretation. The OIR series of publications will be accompanied by a supporting Guidance Document that will give advice on the interpretation of bioassay data. (author)

ARRONAX, a high-energy and high-intensity cyclotron for nuclear medicine

International Nuclear Information System (INIS)

Haddad, Ferid; Guertin, Arnaud; Michel, Nathalie; Ferrer, Ludovic; Carlier, Thomas; Barbet, Jacques; Chatal, Jean-Francois

2008-01-01

This study was aimed at establishing a list of radionuclides of interest for nuclear medicine that can be produced in a high-intensity and high-energy cyclotron. We have considered both therapeutic and positron emission tomography radionuclides that can be produced using a high-energy and a high-intensity cyclotron such as ARRONAX, which will be operating in Nantes (France) by the end of 2008. Novel radionuclides or radionuclides of current limited availability have been selected according to the following criteria: emission of positrons, low-energy beta or alpha particles, stable or short half-life daughters, half-life between 3 h and 10 days or generator-produced, favourable dosimetry, production from stable isotopes with reasonable cross sections. Three radionuclides appear well suited to targeted radionuclide therapy using beta ( 67 Cu, 47 Sc) or alpha ( 211 At) particles. Positron emitters allowing dosimetry studies prior to radionuclide therapy ( 64 Cu, 124 I, 44 Sc), or that can be generator-produced ( 82 Rb, 68 Ga) or providing the opportunity of a new imaging modality ( 44 Sc) are considered to have a great interest at short term whereas 86 Y, 52 Fe, 55 Co, 76 Br or 89 Zr are considered to have a potential interest at middle term. Several radionuclides not currently used in routine nuclear medicine or not available in sufficient amount for clinical research have been selected for future production. High-energy, high-intensity cyclotrons are necessary to produce some of the selected radionuclides and make possible future clinical developments in nuclear medicine. Associated with appropriate carriers, these radionuclides will respond to a maximum of unmet clinical needs. (orig.) 5

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

International Nuclear Information System (INIS)

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

1985-01-01

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

Radionuclide releases to the Columbia River from Hanford Operations, 1944--1971

International Nuclear Information System (INIS)

Heeb, C.M.; Bates, D.J.

1994-05-01

The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of radionuclide emissions since 1944 from the Hanford Site. One source of radionuclide releases to the Columbia River was from production reactor operations. This report provides a quantitative estimate of the amount of radioactivity released each month (1944--1971) to the Columbia River from eleven radionuclides as well as from gross beta activity

Assessments for high dose radionuclide therapy treatment planning

International Nuclear Information System (INIS)

Fisher, D.R.

2003-01-01

Advances in the biotechnology of cell specific targeting of cancer and the increased number of clinical trials involving treatment of cancer patients with radiolabelled antibodies, peptides, and similar delivery vehicles have led to an increase in the number of high dose radionuclide therapy procedures. Optimised radionuclide therapy for cancer treatment is based on the concept of absorbed dose to the dose limiting normal organ or tissue. The limiting normal tissue is often the red marrow, but it may sometimes be the lungs, liver, intestinal tract, or kidneys. Appropriate treatment planning requires assessment of radiation dose to several internal organs and tissues, and usually involves biodistribution studies in the patient using a tracer amount of radionuclide bound to the targeting agent and imaged at sequential timepoints using a planar gamma camera. Time-activity curves are developed from the imaging data for the major organ tissues of concern, for the whole body and sometimes for selected tumours. Patient specific factors often require that dose estimates be customised for each patient. In the United States, the Food and Drug Administration regulates the experimental use of investigational new drugs and requires 'reasonable calculation of radiation absorbed dose to the whole body and to critical organs' using the methods prescribed by the Medical Internal Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine. Review of high dose studies shows that some are conducted with minimal dosimetry, that the marrow dose is difficult to establish and is subject to large uncertainties. Despite the general availability of software, internal dosimetry methods often seem to be inconsistent from one clinical centre to another. (author)

OEDIPE, a software for personalized Monte Carlo dosimetry and treatment planning optimization in nuclear medicine: absorbed dose and biologically effective dose considerations

International Nuclear Information System (INIS)

Petitguillaume, A.; Broggio, D.; Franck, D.; Desbree, A.; Bernardini, M.; Labriolle Vaylet, C. de

2014-01-01

For targeted radionuclide therapies, treatment planning usually consists of the administration of standard activities without accounting for the patient-specific activity distribution, pharmacokinetics and dosimetry to organs at risk. The OEDIPE software is a user-friendly interface which has an automation level suitable for performing personalized Monte Carlo 3D dosimetry for diagnostic and therapeutic radionuclide administrations. Mean absorbed doses to regions of interest (ROIs), isodose curves superimposed on a personalized anatomical model of the patient and dose-volume histograms can be extracted from the absorbed dose 3D distribution. Moreover, to account for the differences in radiosensitivity between tumoral and healthy tissues, additional functionalities have been implemented to calculate the 3D distribution of the biologically effective dose (BED), mean BEDs to ROIs, isoBED curves and BED-volume histograms along with the Equivalent Uniform Biologically Effective Dose (EUD) to ROIs. Finally, optimization tools are available for treatment planning optimization using either the absorbed dose or BED distributions. These tools enable one to calculate the maximal injectable activity which meets tolerance criteria to organs at risk for a chosen fractionation protocol. This paper describes the functionalities available in the latest version of the OEDIPE software to perform personalized Monte Carlo dosimetry and treatment planning optimization in targeted radionuclide therapies. (authors)

The personal dosimetry in Mexico

International Nuclear Information System (INIS)

Salazar, M.A.

2006-01-01

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

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

The continuous monitoring of the artificial beta aerosol activity by measuring the alpha and beta activity in aerosol simultaneously

International Nuclear Information System (INIS)

Hayakawa, Hironobu; Oonishi, Masaki; Matsuura, Hiroyuki

1990-01-01

We have constructed the system to monitor the artificial beta aerosol activity around the nuclear power plants continuously in real time. The smaller releases of artificial radionuclides from the nuclear power plants can be lost in the fluctuations of the natural background of the beta aerosol activity, when only the beta activity of the aerosol is measured. This method to discriminate the artificial and the natural beta activity of the aerosol is based on the fact that the ratio of the natural alpha and beta activities of the aerosol is almost constant. The detection limit of this system is below 3 Bq/m 3 . (author)

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.)

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.)

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.)

Intercalibration of radiological measurements for surveillance purposes of the internal dosimetry laboratory coordinated by the IAEA

International Nuclear Information System (INIS)

Alfaro L, M.M.

2002-07-01

The ININ of Mexico participated in this intercomparison organized by the IAEA in 2000. The objective of this activity is that the dosimetry laboratories that participate can validate the programs of internal dosimetry, with the purpose of improving its capacity in the evaluation of the internal dose and have access to a mechanism to evaluate its dosimetry system under real conditions. The specific objectives of this intercomparison were: 1. To evaluate the participant's capacity to manage the measurements of individual monitoring in terms of the activity in the phantom. 2. To provide the access to the unique calibration resources that otherwise would not be available. 3. To compare the operation of several detection systems, the geometry, phantoms, calibration methods and methods for the evaluation of activity of the radionuclide used by each institution. 4. To provide the independent verification of the direct measurement methods of the dosimetry service. (Author)

Design of an internal dosimetry program

International Nuclear Information System (INIS)

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

2004-01-01

Measurement of radiation dose is an essential element of radiation protection programs at nuclear facilities. To protect workers and demonstrate compliance with regulatory requirements, dosimetry programs must be established based on sound technical basis. Historically, external exposure was controlled by occupational dose limits. Internal exposure to radionuclides was limited by maximum permissible body burden and maximum permissible concentration. With the issuance of ICRP 26, ICRP 30, DOE Order 5480.11, DOE/EH-0256T, and the new 10 CFR 20, it has become a requirement that internal dose be assessed and the sum of internal and external doses be maintained below regulatory limits. Nuclear facilities are required to have internal dose evaluation programs adequate to demonstrate compliance with radiation protection standards (RPSs). The Waste Isolation Pilot Plant is a DOE facility designed to demonstrate safe disposal of transuranic (TRU) wastes in an ancient salt bed 2,150 feet underground. Internal dose measurement is required to support waste handling activities. This paper describes the technical basis for the WIPP Internal Dosimetry Program. (author)

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

The ENSDF based radionuclide source for MCNP

International Nuclear Information System (INIS)

Berlizov, A.N.; Tryshyn, V.V.

2003-01-01

A utility for generating source code of the Source subroutine of MCNP (a general Monte Carlo NxParticle transport code) on the basis of ENSDF (Evaluated Nuclear Structure Data File) is described. The generated code performs statistical simulation of processes, accompanying radioactive decay of a chosen radionuclide through a specified decay branch, providing characteristics of emitted correlated particles on its output. At modeling the following processes are taken into account: emission of continuum energy electrons at beta - -decay to different exited levels of a daughter nucleus; annihilation photon emission accompanying beta + -decay; gamma-ray emission; emission of discrete energy electrons resulted from internal conversion process on atomic K- and L I,II,III -shells; K and LX-ray emission at single and double fluorescence, accompanying electron capture and internal conversion processes. Number of emitted particles, their types, energies and emission times are sampled according to characteristics of a decay scheme of a particular radionuclide as well as characteristics of atomic shells of mother and daughter nuclei. Angular correlations, calculated for a particular combination of nuclear level spins, mixing ratios and gamma-ray multipolarities, are taken into account at sampling of directional cosines of emitted gamma-rays. The paper contains examples of spectrometry system response simulation at measurements with real radionuclide sources. (authors)

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

International Nuclear Information System (INIS)

Gold, Raymond

1999-01-01

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

Performance of the Brazilian laboratories on radionuclide analysis in environmental samples

International Nuclear Information System (INIS)

Vianna, Maria Elizabeth; Tauhata, Luiz; Oliveira, Josue P.; Oliveira, Antonio E.; Clain, Almir F.; Garcia, Luiz Carlos; Conceicao, Cirilo C. da

1995-01-01

The performance of fifteen Brazilian environmental radioanalytical laboratories was evaluated after their participation in nine intercomparison runs of the National Intercomparison Program, PNI, offered by the Instituto de Radioprotecao e Dosimetria, CNEN. A total of 549 radionuclide determinations in environmental samples were evaluated. The results classified as Good ranged from 56.4% for Alpha and Beta Gross determinations up to 84.9% for Gamma spectrometry determinations. These results shows that the best performance in radionuclide determination is reached in gamma spectrometry analyses and the worst in Alpha and Beta Gross determinations. This general behavior is similar to the one reached by other laboratories in international intercomparison programs. (author). 1 ref., 1 fig., 1 tab

Gross alpha and beta activities in Tunisian mineral water

International Nuclear Information System (INIS)

Hamrouni Benbelgacem, Samar

2011-01-01

The quality of natural mineral water is a universal health problem seeing its vital importance. This problem is related to the presence of the radionuclides since this water is coming from underground, during their circulation it dissolves and conveys the radionuclides which are present in the earth's crust. This problem which leads to the contamination of the mineral water urged the World Health Organization to set standards and to recommend the respect of the median values of the activities alpha and beta within the framework of the man protection against this internal exhibition. Concerning the radiological quality of Tunisian mineral water studied in this project, we showed, by using the gross alpha and beta activities counting, that this water is specific to human consumption since their gross alpha and beta activities do not forward any risk on health.

ZZ NUCDECAY, Nuclear Decay Data for Radiation Dosimetry Calculation for ICRP and MIRD

International Nuclear Information System (INIS)

Eckerman, K.F.; Westfall, R.J.; Ryman, J.C.; Cristy, M.

1995-01-01

1 - Description of program or function: - ICRP38: Format: Special format. Number of groups: Energies and intensities of radiations emitted; designed to address the needs in medical, environmental, and occupational radiation protection. Nuclides: 825 + 13 radionuclides. Origin: ENSDF (data used in preparing ICRP Publication 38). - MIRD: Format: Special format. Number of groups: Energies and intensities of radiations emitted; designed to address the needs in medical, environmental, and occupational radiation protection. Nuclides: 242 radionuclides. Origin: ENSDF (monograph of the MIRD Committee). The unabridged data used in preparing ICRP Publication 38 and a monograph of the MIRD Committee are distributed in electronic form in this package. The data are assembled in two collections. The collection referred to as ICRP38 consists of data on the energies and intensities of radiations emitted by the 825 radionuclides reported, although abridged, in ICRP Publication 38 plus an additional 13 radionuclides evaluated during preparation of a monograph for the MIRD Committee. The second collection, denoted as MIRD, contains data for the 242 radionuclides in the MIRD monograph noted above. Each collection consists of three ASCII files: (1) the index file (ICRP38.IDX or MIRD.IDX) is a sorted list of the radionuclides with pointers into the data files; (2) the radiation file (ICRP38.RAD or MIRD.RAD) contains data on the energies and intensities of the emitted radiations; (3) the beta spectra file (ICRP38.BET or MIRD.BET) contains the spectra for all beta emitters in the collection. 161 radionuclides of the MIRD collection have later ENSDF dates than those in the ICRP38 collection. In most instances, the differences are of no dosimetric significance, but considerable differences may exist for some nuclides. 2 - Method of solution: This data base has been designed to address the needs in medical, environmental, and occupational radiation protection. Calculations of the spatial

Radiation protection in radionuclide investigations

International Nuclear Information System (INIS)

Taylor, D.M.

1985-01-01

The subject is covered in sections: introduction; radiation and radioactivity; alpha particles; beta particles; neutrons; electromagnetic radiation; units of radioactivity and radiation; biological effects of radiation; the philosophy of radiation protection (ALARA principle); practical aspects of radiation protection; work with unsealed radiation sources; radionuclide studies in experimental animals; radiation safety during clinical investigations; legislative control of radiation work; radioactive waste disposal; emergency procedures; conclusion. (U.K.)

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

Energy Technology Data Exchange (ETDEWEB)

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

2007-07-01

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

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

International Nuclear Information System (INIS)

Gupta, V.P.

1982-08-01

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

Calculation of dose point kernels for five radionuclides used in radio-immunotherapy

International Nuclear Information System (INIS)

Okigaki, S.; Ito, A.; Uchida, I.; Tomaru, T.

1994-01-01

With the recent interest in radioimmunotherapy, attention has been given to calculation of dose distribution from beta rays and monoenergetic electrons in tissue. Dose distribution around a point source of a beta ray emitting radioisotope is referred to as a beta dose point kernel. Beta dose point kernels for five radionuclides such as 131 I, 186 Re, 32 P, 188 Re, and 90 Y appropriate for radioimmunotherapy are calculated by Monte Carlo method using the EGS4 code system. Present results were compared with the published data of experiments and other calculations. Accuracy and precisions of beta dose point kernels are discussed. (author)

Uranium Dispersion and Dosimetry (UDAD) Code

International Nuclear Information System (INIS)

Momeni, M.H.; Yuan, Y.; Zielen, A.J.

1979-05-01

The Uranium Dispersion and Dosimetry (UDAD) Code provides estimates of potential radiation exposure to individuals and to the general population in the vicinity of a uranium processing facility. The UDAD Code incorporates the radiation dose from the airborne release of radioactive materials, and includes dosimetry of inhalation, ingestion, and external exposures. The removal of raioactive particles from a contaminated area by wind action is estimated, atmospheric concentrations of radioactivity from specific sources are calculated, and source depletion as a result of deposition, fallout, and ingrowth of radon daughters are included in a sector-averaged Gaussian plume dispersion model. The average air concentration at any given receptor location is assumed to be constant during each annual release period, but to increase from year to year because of resuspension. Surface contamination and deposition velocity are estimated. Calculation of the inhalation dose and dose rate to an individual is based on the ICRP Task Group Lung Model. Estimates of the dose to the bronchial epithelium of the lung from inhalation of radon and its short-lived daughters are calculated based on a dose conversion factor from the BEIR report. External radiation exposure includes radiation from airborne radionuclides and exposure to radiation from contaminated ground. Terrestrial food pathways include vegetation, meat, milk, poultry, and eggs. Internal dosimetry is based on ICRP recommendations. In addition, individual dose commitments, population dose commitments, and environmental dose commitments are computed. This code also may be applied to dispersion of any other pollutant

In vivo dosimetry in external beam radiotherapy

International Nuclear Information System (INIS)

Mijnheer, Ben; Beddar, Sam; Izewska, Joanna; Reft, Chester

2013-01-01

In vivo dosimetry (IVD) is in use in external beam radiotherapy (EBRT) to detect major errors, to assess clinically relevant differences between planned and delivered dose, to record dose received by individual patients, and to fulfill legal requirements. After discussing briefly the main characteristics of the most commonly applied IVD systems, the clinical experience of IVD during EBRT will be summarized. Advancement of the traditional aspects of in vivo dosimetry as well as the development of currently available and newly emerging noninterventional technologies are required for large-scale implementation of IVD in EBRT. These new technologies include the development of electronic portal imaging devices for 2D and 3D patient dosimetry during advanced treatment techniques, such as IMRT and VMAT, and the use of IVD in proton and ion radiotherapy by measuring the decay of radiation-induced radionuclides. In the final analysis, we will show in this Vision 20/20 paper that in addition to regulatory compliance and reimbursement issues, the rationale for in vivo measurements is to provide an accurate and independent verification of the overall treatment procedure. It will enable the identification of potential errors in dose calculation, data transfer, dose delivery, patient setup, and changes in patient anatomy. It is the authors’ opinion that all treatments with curative intent should be verified through in vivo dose measurements in combination with pretreatment checks

In vivo dosimetry in external beam radiotherapy

Energy Technology Data Exchange (ETDEWEB)

Mijnheer, Ben [Department of Radiation Oncology, Netherlands Cancer Institute-Antoni van Leeuwenhoek Hospital, Amsterdam 1066 CX (Netherlands); Beddar, Sam [Department of Radiation Physics, University of Texas MD Anderson Cancer Center, Houston, Texas 77030 (United States); Izewska, Joanna [Division of Human Health, International Atomic Energy Agency, Vienna 1400 (Austria); Reft, Chester [Department of Radiation and Cellular Oncology, University of Chicago Medical Center, Chicago, Illinois 60637 (United States)

2013-07-15

In vivo dosimetry (IVD) is in use in external beam radiotherapy (EBRT) to detect major errors, to assess clinically relevant differences between planned and delivered dose, to record dose received by individual patients, and to fulfill legal requirements. After discussing briefly the main characteristics of the most commonly applied IVD systems, the clinical experience of IVD during EBRT will be summarized. Advancement of the traditional aspects of in vivo dosimetry as well as the development of currently available and newly emerging noninterventional technologies are required for large-scale implementation of IVD in EBRT. These new technologies include the development of electronic portal imaging devices for 2D and 3D patient dosimetry during advanced treatment techniques, such as IMRT and VMAT, and the use of IVD in proton and ion radiotherapy by measuring the decay of radiation-induced radionuclides. In the final analysis, we will show in this Vision 20/20 paper that in addition to regulatory compliance and reimbursement issues, the rationale for in vivo measurements is to provide an accurate and independent verification of the overall treatment procedure. It will enable the identification of potential errors in dose calculation, data transfer, dose delivery, patient setup, and changes in patient anatomy. It is the authors' opinion that all treatments with curative intent should be verified through in vivo dose measurements in combination with pretreatment checks.

The work of the task group of committee 2 of ICRP on age-dependent dosimetry

International Nuclear Information System (INIS)

Stather, J.W.; Kaul, A.; Metivier, H.

1996-01-01

With the accident at Chernobyl and developing concern in regard to the consequences of discharging radionuclides into the environment has come increasing awareness of the need to assess radiation doses to all age groups in the population. In 1987, ICRP set up a Task Group of Committee 2 on Age-dependent Dosimetry with the responsibility for calculating internationally agreed dose coefficients for members of the public. This covered the calculation and ingestion, as well as doses to the embryo and fetus from intakes of radionuclides by the mother. This paper reviews the programme of work.(authors). 17 refs., 6 tabs

Limitation of radioactive discharges from NPP based on radionuclide specific monitoring

International Nuclear Information System (INIS)

Bucina, I.; Malatova, I.; Vidlakova, J.

1998-01-01

Monitoring of gaseous and liquid discharges from nuclear power plants based on particulate-iodine-gas measurements and gross beta or gamma plus tritium measurements is being improved by performing radionuclide specific measurements using semiconductor gamma and beta spectrometers and radiochemical methods. A new concept of regulatory effluent limits is being developed. The activities of all the relevant radionuclides discharged during a years, multiplied by the appropriate Sv/Bq conversion coefficient based on a standard multi-pathway model, are summed up, and the effective dose is compared with the new limit. Such limits should be laid down as the per capita collective commitment effective dose in the plant surroundings for atmospheric discharges, and as the committed effective dose to a critical group member for the hydrospheric releases

Methodology assessment of the total beta activity in tobacco and tobacco products and certain results

International Nuclear Information System (INIS)

Georgieva, A.; Srentz, A.

2016-01-01

The presence of alpha and beta radionuclides in tobacco and tobacco products is a frequently discussed issue. However, any information in publications about them and their presence in tobacco products is too scarce. World Health care Organization monitors the influence of tobacco smoking on human health. In 2003, a Framework Convention on Tobacco Control was accepted with the aim to protect human health, which was signed by 179 countries, including Bulgaria. The first debates on the presence of radionuclides in tobacco products are raised in Moscow in 2014. These were instigated by data on the findings of polonium-210, reported by USA and Russia. The aim of the report is to outline a methodology to detect the presence of beta-active radionuclides in tobacco and its products. Keywords: beta activity, geiger counter, samples with infinite thickness, tobacco samples

Development of a definitive internal dosimetry code

International Nuclear Information System (INIS)

Miller, G.; Inkret, W.C.; Schillaci, M.E.

1996-01-01

Internal dosimetry may be divided into tow main problems: (1) the forward (scientific) problem of determining biokinetics models that describe how radionuclides are taken into the body, distributed in body tissues, and excreted, and (2) the inverse (mathematical) problem: given the measured amounts in excreta and assuming a biokinetic model, to determine the times and amounts of intakes into the body. The inverse problem of internal dosimetry is, in fact, a generic problem studied in other fields (e.g., image reconstruction, spectral deconvulution, and model parameter fitting). We have developed a code for plutonium internal dosimetry using the maximum entropy method, a method for solving underdetermined inverse problems with a positivity constraint. Within the framework of Bayesian statistics, we believe the definitive approach is to examine the Bayesian posterior probability describing the probability of an intake scenario (X i ) read ( ... ) as open-quotes the set of,close quotes where X i denotes the intake amount that occurs on the with day. For plutonium, for a worker with a long employment history, this is a very high dimensional probability space, since there may be on the order of 10,000 days when intakes may have occurred. Within this high dimensional space, we calculate the mean intake scenario as i > where denotes the expectation value over the posterior probability distribution. Similarly, we calculate uncertainties and other relevant quantities, such as X 2 , as expectation values over the posterior distribution. Thanks to a recent breakthrough in describing the mathematical structure of the intake process (a Poisson sum representation of intakes), we have developed the initial version of a Bayesian expectation-value algorithm for internal dosimetry reconstructions

Dosimetry for the treatment of cystic craniopharyngioma through radiocolloids with {sup 186} Re; Dosimetria para el tratamiento de craneofaringiomas quisticos mediante radiocoloide con {sup 186} Re

Energy Technology Data Exchange (ETDEWEB)

Rojas, E.L.; Al-dweri, F.M.O.; Lallena, A.M. [Depto. de Fisica Moderna, Universidad de Granada (Spain); Bodineau, C.; Galan, P. [Servicio de Radiofisica Hospitalaria, Hospital Regional Universitario ' Carlos Haya' , 29010 Malaga (Spain)

2003-07-01

The cystic craniopharyngioma (CQ) are histologically benign tumors that can affect important organs, as the hypothalamus or the optic nerve. They are treated introducing, inside the cyst, a radioactive colloid. The wall constitutes the white volume and the dosimetry is usually carried out starting from analytic formulas that only are valid in the case of an homogeneous media, uniform and infinite. In this work it is studied the dosimetry of the CQ by means of Monte Carlo simulation (MC), taking in account the different materials and interfaces that conform them. We present the obtained results for the radionuclide {sup 186} Re. We have used the Monte Carlo code Penelope and we follow 5x10{sup 6} histories in each simulation. We supposed a size of CQ of 1.75 cm of radio and a wall thickness of 1 mm and we have varied the constituent materials of the interior of the cyst and of the wall. The analytic calculations that we carry out show an excellent agreement with the MC results for an unique media (water), as much for the beta radiation as for those originated of the Rhenium disintegration. However, when it takes in account the gel that is introduced in the tumor for the treatment and we vary the constituent material of the wall, we find important differences. Of the analysis of our results we can conclude that the dosimetry for the treatment of CQ based in the usual analytic formulas overestimates the doses really deposited in the wall of the CQ. (Author)

Present status and perspective of radiochemical analysis of radionuclides in Nordic countries

DEFF Research Database (Denmark)

Hou, Xiaolin; Olsson, Mattias; Togneri, Laura

2016-01-01

Radiochemical analysis plays a critical role in the determination of pure beta and alpha emitting radionuclides for environmental monitoring, radioecology, decommissioning, nuclear forensics and geological dating. A remarkable development on radiochemical analysis has been achieved in the past...... of radionuclides, especially in Nordic countries; some requirements from nuclear industries and research organizations, as well as perspectives on the development of radiochemical analysis are discussed....

What is the role of the bystander response in radionuclide therapies?

Directory of Open Access Journals (Sweden)

Darren eBrady

2013-08-01

Full Text Available Radionuclide therapy for cancer is undergoing a renaissance, with a wide range of radionuclide and clinical delivery systems currently under investigation. Dosimetry at the cellular and subcellular level is complex with inhomogeneity and incomplete targeting of all cells such that some tumour cells will receive little or no direct radiation energy. There is now sufficient preclinical evidence of a bystander response which can modulate the biology of these unirradiated cells with current research demonstrating both protective and inhibitory responses. Dependence upon fraction of irradiated cells has also been found has and the presence of functional gap junctions appears to be import for several bystander responses. The selection of either high or low LET radionuclides may be critical. While low LET radionuclides appear to have a bystander response proportional to dose, the dose-response from high LET radionuclides are more complex. In media transfer experiments a U shaped response curve has been demonstrated for high LET treatments. However this U shaped response has not been seen with co-culture experiments and its relevance remains uncertain. For high LET treatments there is a suggestion that dose rate effects may also be important with inhibitory effects noted with 125I labelling study and a stimulatory seen with 123I labelling in one study.

Beta particle dose rates to micro-organisms in soil

International Nuclear Information System (INIS)

Kabir, M.; Spiers, F.W.; Iinuma, Takeshi.

1977-01-01

Studies were made to estimate the beta-particle dose rates to micro-organisms of various sizes in soil. The small insects and organisms living in soil are constantly exposed to beta-radiation arising from naturally occuring radionuclides in soil as in this case no overlying tissue shields them. The technique of measuring beta-particle dose rate consisted of using of a thin plastic scintillator to measure the pulse height distribution as the beta particle traverses the scintillator. The integrated response was determined by the number and size of the photomultiplier pulses. From the data of soil analyses it was estimated that typically about 29% of the beta particles emitted per gm. of soil were contributed by the U/Ra series, 21% by the Th series and about 50% by potassium. By combining the individual spectra of these three radionuclides in the proportion found in a typical soil, a resultant spectrum was computed representing the energy distribution of the beta particles. The dose rate received by micro-organisms of different shape and size in soil was derived from the equilibrium dose rates combined with a 'Geometrical Factor' of the organisms. For small organisms, the dose rates did not vary between the spherical and cylindrical types, but in the case of larger organisms, the dose rates were found to be greater for the spherical types of the same diameter. (auth.)

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

International Nuclear Information System (INIS)

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

1983-10-01

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

Revue of some dosimetry and dose assessment European projects

International Nuclear Information System (INIS)

Bolognese-Milsztajn, T.; Frank, D.; Lacoste, V.; Pihet, P.

2006-01-01

Full text of publication follows: Within the 5. Framework Programme of the European Commission several project dealing with dosimetry and dose assessment for internal and external exposure have been supported. A revue of the results of some of them is presented in this paper. The EURADOS network which involved 50 dosimetry institutes in EUROPE has coordinated the project DOSIMETRY NETWORK: the main results achieved within this action are the following: - The release on the World Wide Web of the EURADOS Database of Dosimetry Research Facilities; - The realisation of the report 'Harmonization of Individual Monitoring (IM) in Europe'; - The continuation of the intercomparisons programme of environmental radiation monitoring systems; - The realisation of the report Cosmic radiation exposure of aircraft crew. The EVIDOS project aimed at evaluating state of the art dosimetry techniques in representative workplaces of the nuclear industry with complex mixed neutron-photon radiation fields. This paper summarises the main findings from a practical point of view. Conclusions and recommendations will be given concerning characterisation of radiation fields, methods to derive radiation protection quantities and dosimeters results. The IDEA project aimed to improve the assessment of incorporated radionuclides through developments of advanced in-vivo and bioassay monitoring techniques and making use of such enhancements for improvements in routine monitoring. The primary goal was to categorize those new developments regarding their potential and eligibility for the routine monitoring community. The costs of monitoring for internal exposures in the workplace are usually significantly greater than the equivalent costs for external exposures. There is therefore a need to ensure that resources are employed with maximum effectiveness. The EC-funded OMINEX (Optimisation of Monitoring for Internal Exposure) project has developed methods for optimising the design and implementation of

Standardization of low energy beta and beta-gamma complex emitters by the tracer and the efficiency extrapolation methods

International Nuclear Information System (INIS)

Sahagia, M.

1978-01-01

The absolute standardization of radioactive solutions of low energy beta emitters and beta-gamma emitters with a high probability of disintegration to the ground state is described; the tracer and the efficiency extrapolation methods were used. Both types of radionuclides were mathematically and physically treated in an unified manner. The theoretical relations between different beta spectra were calculated according to Williams' model and experimentally verified for: 35 S + 60 Co, 35 S + 95 Nb, 147 Pm + 60 Co, 14 C + 95 Nb and two beta branches of 99 Mo. The optimum range of beta efficiency variation was indicated. The basic supposition that all beta efficieny tend to unity in the same time was experimentally verified, using two 192 Ir beta branches. Four computer programs, written in the FORTRAN IV language, were elaborated, for the adequate processing of the experimental data. Good precision coefficients according to international standards were obtained in the absolute standardization of 35 S, 147 Pm, 99 Mo solutions. (author)

Personnel dosimetry methods introduced in the Czechoslovak national laboratories

International Nuclear Information System (INIS)

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

1979-01-01

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

Relationship between internal dosimetry and DNA double strand breaks in lymphocytes after radionuclide therapy; Zusammenhang zwischen physikalischer Dosimetrie und DNA Doppelstrangbruechen in Lymphozyten nach Radionuklidtherapie

Energy Technology Data Exchange (ETDEWEB)

Eberlein, Uta

2015-09-30

In radionuclide therapy radiopharmaceuticals are administered mostly systemically. Primarily, beta-emitters are used because of their short range in tissue. As a result the radiopharmaceutical distributes within the human body and accumulates in organs and target structures. Thus, the body is irradiated internally, in contrast to external irradiation in radiotherapy. The pattern of the activity distribution within the human body is determined by the physical and chemical properties of the radiopharmaceutical. Furthermore, the amount of activity and its accumulation in organs or tissues is essential for the calculation of the absorbed dose which defines the energy deposited in the body by ionizing radiation. During internal or external irradiation, patients are exposed to ionizing radiation which does not only destroy the malignant cells but also damages healthy tissue and cells. This is mainly caused by direct and indirect interaction of the radiation with the DNA which damages the DNA structure. Most frequently, there are single strand breaks and base damages. DNA double strand breaks (DSBs) are rare; nevertheless, they are the most critical lesions for cells as repairing the damage is difficult. Unrepaired or misrepaired DNA could cause mutations, chromosomal aberrations or lead to cell death. The formation of a DNA DSB in nuclear chromatin results in the rapid phosphorylation of the histone H2 variant H2AX, then called gamma-H2AX. Furthermore, DSBs also recruit the damage sensor 53BP1 to the chromatin surrounding the DSBs, which leads to 53BP1 and gamma-H2AX co-localization in the chromatin surrounding a DSB. By immunofluorescence staining with gamma-H2AX and 53BP1 antibodies those biomarkers can be addressed by microscopically visible DNA damage protein foci, this is also known as the DNA damage focus assay. With progression of DSB repair, gamma-H2AX and 53BP1 foci disappear. It is assumed that one focus corresponds to one DSB. Therefore, the number of foci per

Long-lived radionuclides in the marine environment of Thailand

Energy Technology Data Exchange (ETDEWEB)

Mahapanyawong, S; Sonsuk, M; Polphong, P; Milintawisamai, M; Panyatipsakul, Y

1993-12-31

Natural and artificial radionuclides in the environment of the Gulf of Thailand were studied during 1989-1991. In the study, surface water, sediment at 5 locations between latitudes 9 degree 28 minute N and 13 degree 15 minute N longitudes 100 degree 35 minute E. and 5 species of marine biota were collected in 1989. In 1990 and 1991, 9 and 7 species of marine biota were collected from the Gulf of Thailand and the Andaman Sea respectively. These samples were prepared and analyzed for gamma-emitting radionuclides as well as some beta and alpha-emitting radionuclides such as C-14, Sr-90, Pu-239,240, Po-210 etc. The results indicate the present status of radioactivity level of the environment of the gulf and the sea

Long-lived radionuclides in the marine environment of Thailand

International Nuclear Information System (INIS)

Mahapanyawong, S.; Sonsuk, M.; Polphong, P.; Milintawisamai, M.; Panyatipsakul, Y.

1992-01-01

Natural and artificial radionuclides in the environment of the Gulf of Thailand were studied during 1989-1991. In the study, surface water, sediment at 5 locations between latitudes 9 degree 28 minute N and 13 degree 15 minute N longitudes 100 degree 35 minute E. and 5 species of marine biota were collected in 1989. In 1990 and 1991, 9 and 7 species of marine biota were collected from the Gulf of Thailand and the Andaman Sea respectively. These samples were prepared and analyzed for gamma-emitting radionuclides as well as some beta and alpha-emitting radionuclides such as C-14, Sr-90, Pu-239,240, Po-210 etc. The results indicate the present status of radioactivity level of the environment of the gulf and the sea

Long-lived radionuclides in the marine environment of Thailand

International Nuclear Information System (INIS)

Mahapanyawong, S.; Sonsuk, M.; Polphong, P.; Milintawisamai, M.; Panyatipsakul, Y.

1992-01-01

Natural and artificial radionuclides in the environment of the Gulf of Thailand were studied during 1989-1991. In the study, surface water, sediment at 5 locations between latitudes 9 0 28' N and 13 0 15' N longitudes 100 0 35' E. and 5 species of marine biota were collected in 1989. In 1990 and 1991, 9 and 7 species of marine biota were collected from the Gulf of Thailand and the Andaman Sea respectively. These samples were prepared and analyzed for gamma-emitting radionuclides as well as some beta and alpha-emitting radionuclides such as C 14 , Sr 90 , Pu 239,240 , Po 210 etc. The results indicate the present status of radioactivity level of the environment of the gulf and the sea

Organization of the internal dosimetry in the Spanish nuclear facilities

International Nuclear Information System (INIS)

Manchena, P.; Soliet, E.

1998-01-01

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

Health effects of internally deposited radionuclides

International Nuclear Information System (INIS)

Raabe, Otto G.

2008-01-01

A comparative evaluation has been conducted of the ionizing radiation dose-response relationships in both human and laboratory animal studies involving internal deposition of radionuclides including alpha-emitters 226 Ra, 238 Pu, 239 Pu, and 241 Am and beta-emitters 90 Sr, 90 Y and 144 Ce. Intake routes included inhalation, injection, and ingestion. The preeminent importance of dose rate was revealed in this analysis. The lifetime effects of the ionizing radiation from internal emitters are described by three-dimensional dose rate/ time/response surfaces that compete with other causes of death during an individual's lifetime. Using maximum likelihood survival regression methods, the characteristic logarithmic slope for cancer induction was found to be about negative one-third for alpha-emitters or about negative two-thirds for beta-emitters. The relative biological effectiveness (RBE) of alpha versus beta radiations for cancer induction is a strong function of dose rate, near one at high dose rates and greater than 20 at low dose rates. The cumulative dose required to yield any level of induced-cancer risk is less at lower dose rates than at higher dose rates showing an apparent inverse-dose effect (up to a factor of 10 for high LET alpha radiation and a factor of 2 for low LET beta radiation). The competing risks of death associated with radiation injury, radiation-induced cancer, and natural aging are graphically shown using three-dimensional illustrations. At the higher average dose rates the principal deleterious effects are those associated with radiation-induced injury while at intermediate average dose rates radiation-induced cancer predominates. At the lower average dose rates the long latency time required for radiation-induced cancer may exceed natural life span, yielding an apparent lifespan effective threshold for death associated with radiation-induced cancer for cumulative doses to the target tissue below from 1.1 to 1.4 Gy for alpha-emitters or below

Health effects of internally deposited radionuclides

Energy Technology Data Exchange (ETDEWEB)

Raabe, Otto G., E-mail: ograabe@ucdavis.edu [California Univ., Davis, CA (United States). Center for Health and the Environment

2008-07-01

A comparative evaluation has been conducted of the ionizing radiation dose-response relationships in both human and laboratory animal studies involving internal deposition of radionuclides including alpha-emitters {sup 226}Ra, {sup 238}Pu, {sup 239}Pu, and {sup 241}Am and beta-emitters {sup 90}Sr, {sup 90}Y and {sup 144}Ce. Intake routes included inhalation, injection, and ingestion. The preeminent importance of dose rate was revealed in this analysis. The lifetime effects of the ionizing radiation from internal emitters are described by three-dimensional dose rate/ time/response surfaces that compete with other causes of death during an individual's lifetime. Using maximum likelihood survival regression methods, the characteristic logarithmic slope for cancer induction was found to be about negative one-third for alpha-emitters or about negative two-thirds for beta-emitters. The relative biological effectiveness (RBE) of alpha versus beta radiations for cancer induction is a strong function of dose rate, near one at high dose rates and greater than 20 at low dose rates. The cumulative dose required to yield any level of induced-cancer risk is less at lower dose rates than at higher dose rates showing an apparent inverse-dose effect (up to a factor of 10 for high LET alpha radiation and a factor of 2 for low LET beta radiation). The competing risks of death associated with radiation injury, radiation-induced cancer, and natural aging are graphically shown using three-dimensional illustrations. At the higher average dose rates the principal deleterious effects are those associated with radiation-induced injury while at intermediate average dose rates radiation-induced cancer predominates. At the lower average dose rates the long latency time required for radiation-induced cancer may exceed natural life span, yielding an apparent lifespan effective threshold for death associated with radiation-induced cancer for cumulative doses to the target tissue below from 1.1 to

Calibration of photon and beta ray sources used in brachytherapy. Guidelines on standardized procedures at Secondary Standards Dosimetry Laboratories; Calibracion de fuentes de fotones y rayos beta usadas en braquiterapia. Guia de procedimiento estandarizados en Laboratorios Secundarios de Calibracion Dosimetrica (LSCD) y en hospitales

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-03-01

It has generally been recognized that international harmonization in radiotherapy dosimetry is essential. Consequently, the IAEA has given much effort to this, for example by publishing a number of reports in the Technical Reports Series (TRS) for external beam dosimetry, most notably TRS-277 and more recently TRS-398. Both of these reports describe in detail the steps to be taken for absorbed dose determination in water and they are often referred to as 'dosimetry protocols'. Similar to TRS-277, it is expected that TRS-398 will be adopted or used as a model by a large number of countries as their national protocol. In 1996, the IAEA established a calibration service for low dose rate (LDR) 137 Cs brachytherapy sources, which is the most widely used source for treatment of gynecological cancer. To further enhance harmonization in brachytherapy dosimetry, the IAEA published in 1999 IAEA-TECDOC-1079 entitled 'Calibration of Brachytherapy Sources. Guidelines on Standardized Procedures for the Calibration of Brachytherapy Sources at Secondary Standard Dosimetry Laboratories (SSDLs) and Hospitals'. The report was well received and was distributed in a large number of copies to the members of the IAEA/WHO network of SSDLs and to medical physicists working with brachytherapy. The present report is an update of the aforementioned TECDOC. Whereas TECDOC-1079 described methods for calibrating brachytherapy sources with photon energies at or above those of {sup 192}Ir, the current report has a wider scope in that it deals with standardization of calibration of all the most commonly used brachytherapy sources, including both photon and beta emitting sources. The latter sources have been in use for a few decades already, but their calibration methods have been unclear. Methods are also described for calibrating sources used in the rapidly growing field of cardiovascular angioplasty. In this application, irradiation of the vessel wall is done in an attempt to prevent restenosis

Natural radionuclides in waste water discharged from coal-fired power plants in Serbia.

Science.gov (United States)

Janković, Marija M; Todorović, Dragana J; Sarap, Nataša B; Krneta Nikolić, Jelena D; Rajačić, Milica M; Pantelić, Gordana K

2016-12-01

Investigation of the natural radioactivity levels in water around power plants, as well as in plants, coal, ash, slag and soil, and to assess the associated radiation hazard is becoming an emerging and interesting topic. This paper is focused on the results of the radioactivity analysis in waste water samples from five coal-fired power plants in Serbia (Nikola Tesla A, Nikola Tesla B, Kolubara, Morava and Kostolac), which were analyzed in the period 2003-2015. River water samples taken upstream and downstream from the power plants, drain water and overflow water were analyzed. In the water samples gamma spectrometry analysis was performed as well as determination of gross alpha and beta activity. Natural radionuclide 40 K was detected by gamma spectrometry, while the concentrations of other radionuclides, 226 Ra, 235 U and 238 U, usually were below the minimum detection activity (MDA). 232 Th and artificial radionuclide 137 Cs were not detected in these samples. Gross alpha and beta activities were determined by the α/β low level proportional counter Thermo Eberline FHT 770 T. In the analyzed samples, gross alpha activity ranged from MDA to 0.47 Bq L - 1 , while the gross beta activity ranged from MDA to 1.55 Bq L - 1 .

Chemical dosimetry principles in high dose dosimetry

International Nuclear Information System (INIS)

Mhatre, Sachin G.V.

2016-01-01

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

Internal dosimetry for occupationally exposed personnel in nuclear medicine

International Nuclear Information System (INIS)

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

2013-01-01

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

Paving the way to personalized medicine. Production of some theragnostic radionuclides at Brookhaven National Laboratory

International Nuclear Information System (INIS)

Srivastava, S.C.

2011-01-01

This paper introduces a relatively novel paradigm that involves specific individual radionuclides or radionuclide pairs that have emissions that allow pre-therapy low-dose imaging plus higher-dose therapy in the same patient. We have made an attempt to sort out and organize a number of such theragnostic radionuclides and radionuclide pairs that may potentially bring us closer to the age-long dream of personalized medicine for performing tailored low-dose molecular imaging (SPECT/CT or PET/CT) to provide the necessary pre-therapy information on biodistribution, dosimetry, the limiting or critical organ or tissue, and the maximum tolerated dose (MTD), etc. If the imaging results then warrant it, it would be possible to perform higher-dose targeted molecular therapy in the same patient with the same radiopharmaceutical. A major problem that remains yet to be fully resolved is the lack of availability, in sufficient quantities, of a majority of the best candidate theragnostic radionuclides in a no-carrier-added (NCA) form. A brief description of the recently developed new or modified methods at BNL for the production of four theragnostic radionuclides, whose nuclear, physical, and chemical characteristics seem to show great promise for personalized cancer therapy are described.

Preliminary investigation of PAGAT polymer gel radionuclide dosimetry of Tc-99m

Science.gov (United States)

Braun, Kelly; Bailey, Dale; Hill, Brendan; Baldock, Clive

2009-05-01

PAGAT polymer gel was investigated as a suitable dosimeter materials for measuring absorbed dose from the unsealed source radionuclide Tc-99m. Differing amounts of Tc-99m over the range of 25-5000 MBq were introduced into a normoxic polymer gel mixture (PAGAT) in sealed nitrogen-filled P6 glass vials. After irradiation the gels were evaluated using MRI more than 48 hours after preparation to allow for radioactive decay. The dose delivered to the vial was also calculated empirically. R2 versus total activity curves were obtained over a number of experiments and these were used to evaluate the relationship between the amount of gel polymerization and the dose deposited by the radionuclide. A linear response up to 1000 MBq (corresponding to 20Gy) was displayed and was still behaving monotonically at 5000 MBq. Polymer gels offer the potential to measure radiation dose three-dimensionally using MRI.

High beta radiation exposure of medical staff measures for optimisation of radiation protection

International Nuclear Information System (INIS)

Barth, I.; Rimpler, A.

2006-01-01

Full text of publication follows: New therapies applying beta radionuclides have been introduced in medicine in recent years, especially in nuclear medicine, e. g. radio-synoviorthesis, radioimmunotherapy and palliative pain therapy. The preparation of radiopharmaceuticals, their dispensary as well as injection require the handling of vials and syringes with high activities of beta emitters at small distances to the skin. Thus the medical staff may be exposed to a high level of beta radiation. Hence the local skin dose, Hp(0,07), was measured at these workplaces with thin-layer thermoluminescent dosemeters TLD (LiF:Mg,P,Cu) fixed to the tip of the fingers at both hands of the personnel. In addition, official beta/photon ring dosemeters were worn at the first knuckle of the index finger. Very high local skin doses were measured at the tip of index finger and thumb. The findings indicate that the exposure of the staff can exceed the annual dose limit for skin of 500 mSv when working at a low protection standard. By the use of appropriate shieldings and tools (e.g. tweezers or forceps) the exposure was reduced of more than one order of magnitude. The German dosimetry services provide official beta/photon ring dosemeters for routine monitoring of the extremity exposure of occupationally exposed persons. But even monitoring with these official dosemeters does not provide suitable results to control compliance with the dose limit in the majority of cases because they can mostly not be worn at the spot of highest beta exposure (finger tip). Therefore, a study was performed to identify the difference of readings of official ring dosemeters and the maximum local skin dose at the finger tips. At workplaces of radio-synoviorthesis a correction factor of 3 was determined provided that the staff worked at high radiation protection standard and the ring dosemeters were worn at the first knuckle of the index finger. The correction factor increases significantly when the radiation

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

Dosimetry in radioisotope placentography

International Nuclear Information System (INIS)

Sastry, K.G.K.; Reddy, A.R.; Nagaratnam, A.

1976-01-01

Radionuclide investigation of the placenta is being widely used in recent years for the diagnosis and management of vaginal bleeding in the third trimester of pregnancy. One is, therefore, concerned about the radiation exposure to the foetus during such procedures. In the present communication a precise method of estimation of radiation doses is presented. A concept termed 'effective absorbed dose constant' is utilized to enable the absorbed fractions and equilibrium absorbed dose constants to be more easily employed in radiation dose estimations. Tables of the effective absorbed dose constants for radionuclides like 131 I, 123 I, sup(113m)Tc, sup(99m)Tc, 67 Ga, and 51 Cr, are given for different masses and shapes. Masses of different organs of both mother and foetus at different periods of pregnancy and the biological turnover data for different radiopharmaceuticals are reviewed and typical values are presented. Radiation doses to different organs of both mother and foetus at the 30th week of pregnancy are finally estimated for 131 I-HSA, 123 I-SHA, sup(99m)Tc-HSA and sup(113m)In-chloride. The advantage of the effective absorbed dose constants in radiation dosimetry in general is discussed. The relative merits of different radiopharmaceuticals for placental investigations are brought out in comparison with antenatal pelvimetric and abdominal X-ray investigations, from the point of view of radiation doses. (author)

Age-specific models for evaluating dose and risk from internal exposures to radionuclides: Report of current work of the Metabolism and Dosimetry Research Group, July 1, 1985-June 30, 1987

International Nuclear Information System (INIS)

Leggett, R.W.; Warren, B.P.

1987-09-01

A projection of the health risk to a population internally exposed to a radionuclide requires explicit or implicit use of demographic, biokinetic, dosimetric, and dose-response models. Exposure guidelines have been based on models for a reference adult with a fixed life span. In this report, we describe recent efforts to develop a comprehensive methodology for estimation of radiogenic risk to individuals and to heterogeneous populations. Emphasis is on age-dependent biokinetics and dosimetry for internal emitters, but consideration also is given to conversion of age-specific doses to estimates of risk using realistic, site-specific demographic models and best available age-specific dose-response functions. We discuss how the methods described here may also improve estimates for the reference adult usually considered in radiation protection. 159 refs

Age-specific models for evaluating dose and risk from internal exposures to radionuclides: Report of current work of the Metabolism and Dosimetry Research Group, July 1, 1985-June 30, 1987

Energy Technology Data Exchange (ETDEWEB)

Leggett, R.W.; Warren, B.P. (eds.)

1987-09-01

A projection of the health risk to a population internally exposed to a radionuclide requires explicit or implicit use of demographic, biokinetic, dosimetric, and dose-response models. Exposure guidelines have been based on models for a reference adult with a fixed life span. In this report, we describe recent efforts to develop a comprehensive methodology for estimation of radiogenic risk to individuals and to heterogeneous populations. Emphasis is on age-dependent biokinetics and dosimetry for internal emitters, but consideration also is given to conversion of age-specific doses to estimates of risk using realistic, site-specific demographic models and best available age-specific dose-response functions. We discuss how the methods described here may also improve estimates for the reference adult usually considered in radiation protection. 159 refs.

Workshop Report on Atomic Bomb Dosimetry--Review of Dose Related Factors for the Evaluation of Exposures to Residual Radiation at Hiroshima and Nagasaki.

Science.gov (United States)

Kerr, George D; Egbert, Stephen D; Al-Nabulsi, Isaf; Bailiff, Ian K; Beck, Harold L; Belukha, Irina G; Cockayne, John E; Cullings, Harry M; Eckerman, Keith F; Granovskaya, Evgeniya; Grant, Eric J; Hoshi, Masaharu; Kaul, Dean C; Kryuchkov, Victor; Mannis, Daniel; Ohtaki, Megu; Otani, Keiko; Shinkarev, Sergey; Simon, Steven L; Spriggs, Gregory D; Stepanenko, Valeriy F; Stricklin, Daniela; Weiss, Joseph F; Weitz, Ronald L; Woda, Clemens; Worthington, Patricia R; Yamamoto, Keiko; Young, Robert W

2015-12-01

Groups of Japanese and American scientists, supported by international collaborators, have worked for many years to ensure the accuracy of the radiation dosimetry used in studies of health effects in the Japanese atomic bomb survivors. Reliable dosimetric models and systems are especially critical to epidemiologic studies of this population because of their importance in the development of worldwide radiation protection standards. While dosimetry systems, such as Dosimetry System 1986 (DS86) and Dosimetry System 2002 (DS02), have improved, the research groups that developed them were unable to propose or confirm an additional contribution by residual radiation to the survivor's total body dose. In recognition of the need for an up-to-date review of residual radiation exposures in Hiroshima and Nagasaki, a half-day technical session was held for reports on newer studies at the 59 th Annual HPS Meeting in 2014 in Baltimore, MD. A day-and-a-half workshop was also held to provide time for detailed discussion of the newer studies and to evaluate their potential use in clarifying the residual radiation exposure to atomic bomb survivors at Hiroshima and Nagasaki. The process also involved a re-examination of very early surveys of radioisotope emissions from ground surfaces at Hiroshima and Nagasaki and early reports of health effects. New insights were reported on the potential contribution to residual radiation from neutron-activated radionuclides in the airburst's dust stem and pedestal and in unlofted soil, as well as from fission products and weapon debris from the nuclear cloud. However, disparate views remain concerning the actual residual radiation doses received by the atomic bomb survivors at different distances from the hypocenter. The workshop discussion indicated that measurements made using thermal luminescence and optically stimulated luminescence, like earlier measurements, especially in very thin layers of the samples, could be expanded to detect possible

EPR and TL-based beta dosimetry measurements in various tooth components contaminated by 90Sr

International Nuclear Information System (INIS)

Veronese, I.; Fattibene, P.; Cantone, M.C.; De Coste, V.; Giussani, A.; Onori, S.; Shishkina, E.A.

2008-01-01

Thermoluminescence-based beta dosimetry, previously proposed for the estimate of the internal contamination in teeth, and EPR has been used in this paper to investigate the homogeneity of 90 Sr contamination and of dose within nine teeth of one person born in the year of the onset of waterborne radioactive releases of the Mayak plutonium facility. A large deviation of dose and activity distributions in both enamel and radical dentine of the various teeth was observed. Average dose was 27±7Gy in enamel and 0.90±0.31Gy in radical dentine. Average 90 Sr concentration was 52±8Bq/g in enamel and 5±2Bq/g in radical dentine. The observed deviation around the mean value of dose and 90 Sr concentration can be explained due to the specific mineral evolution of each tooth at the time of Sr intake. In the same donor, a negative correlation was also observed between radical dentine and enamel for the 90 Sr specific activity as well for the dose. Similar analyses performed on one massive molar belonging to a second donor revealed absence of correlation between dose and 90 Sr concentration in the same tissue, indicating a dose contribution from 90 Sr present in neighbouring tissue compartments. Systematic differences in cumulated dose and activity levels between the lingual and the buccal parts of crown dentine and of enamel were also observed

Acute ingestion dosimetry using the ICRP 30 gastrointestinal tract model

International Nuclear Information System (INIS)

Cassels, B.M.

1987-01-01

This paper examines the gastrointestinal (GI) tract model used for dosimetry as outlined in ICRP30, to allow quick calculations of effective dose equivalents for acute radionuclide ingestion. A computer program has been developed to emulate the GI tract model. The program and associated data files are structured so that the GI tract model parameters can be varied, while the file structure and algorithm for the GI tract model should require minimal modification to allow the same theories that apply in this model to be used for other dosimetric models

Eurados trial performance test for photon dosimetry

DEFF Research Database (Denmark)

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

2001-01-01

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

Referent 3D tumor model at cellular level in radionuclide therapy

International Nuclear Information System (INIS)

Spaic, R.; Ilic, R.D.; Petrovic, B.J.

2002-01-01

Aim Conventional internal dosimetry has a lot of limitations because of tumor dose nonuniformity. The best approach for absorbed dose at cellular level for different tumors in radionuclide therapy calculation is Monte Carlo method. The purpose of this study is to introduce referent tumor 3D model at cellular level for Monte Carlo simulation study in radionuclide therapy. Material and Methods The moment when tumor is detectable and when same therapy can start is time period in which referent 3D tumor model at cellular level was defined. In accordance with tumor growth rate at that moment he was a sphere with same radius (10 000 μm). In that tumor there are cells or cluster of cells, which are randomly distributed spheres. Distribution of cells/cluster of cells can be calculated from histology data but it was assumed that this distribution is normal with the same mean value and standard deviation (100±50 mm). Second parameter, which was selected to define referent tumor, is volume density of cells (30%). In this referent tumor there are no necroses. Stroma is defined as space between spheres with same concentration of materials as in spheres. Results: Referent tumor defined on this way have about 2,2 10 5 cells or cluster of cells random distributed. Using this referent 3D tumor model and for same concentration of radionuclides (1:100) and energy of beta emitters (1000 keV) which are homogeneously distributed in labeled cells absorbed dose for all cells was calculated. Simulations are done using FOTELP Monte Carlo code, which is modified for this purposes. Results of absorbed dose in cells are given in numerical values (1D distribution) and as the images (2D or 3D distributions). Conclusion Geometrical module for Monte Carlo simulation study can be standardized by introducing referent 3D tumor model at cellular level. This referent 3D tumor model gives most realistic presentation of different tumors at the moment of their detectability. Referent 3D tumor model at

Calculated effects of backscattering on skin dosimetry for nuclear fuel fragments

International Nuclear Information System (INIS)

Aydarous, A. Sh

2008-01-01

The size of hot particles contained in nuclear fallout ranges from 10 nm to 20 μm for the worldwide weapons fallout. Hot particles from nuclear power reactors can be significantly bigger (100 μm to several millimetres). Electron backscattering from such particles is a prominent secondary effect in beta dosimetry for radiological protection purposes, such as skin dosimetry. In this study, the effect of electron backscattering due to hot particles contamination on skin dose is investigated. These include parameters such as detector area, source radius, source energy, scattering material and source density. The Monte-Carlo Neutron Particle code (MCNP4C) was used to calculate the depth dose distribution for 10 different beta sources and various materials. The backscattering dose factors (BSDF) were then calculated. A significant dependence is shown for the BSDF magnitude upon detector area, source radius and scatterers. It is clearly shown that the BSDF increases with increasing detector area. For high Z scatterers, the BSDF can reach as high as 40 and 100% for sources with radii 0.1 and 0.0001 cm, respectively. The variation of BSDF with source radius, source energy and source density is discussed. (authors)

Table of radionuclides (Vol. 5 - A = 22 to 244)

International Nuclear Information System (INIS)

Be, M.M.; Chiste, V.; Dulieu, C.; Mougeot, X.; Browne, E.; Chechev, V.; Kuzmenko, N.; Kondev, F.; Luca, A.; Galan, M.; Arinc, A.; Huang, X.

2010-01-01

This monograph is one of several published in a series by the Bureau International des Poids et Mesures (BIPM) on behalf of the Comite Consultatif des Rayonnements Ionisants (CCRI), previously known as the Comite Consultatif pour les Etalons de Mesure des Rayonnements Ionisants (CCEMRI). The aim of this series of publications is to review topics that are of importance for the measurement of ionizing radiation and especially of radioactivity, in particular those techniques normally used by participants in international comparisons. It is hoped that these publications will prove to be useful reference volumes both for those who are already engaged in this field and for those who are approaching such measurements for the first time. The purpose of this monograph is to present the recommended values of nuclear and decay data for a wide range of radionuclides. Activity measurements for more than forty of these radionuclides have already been the subject of comparisons under the auspices of Section II of the CCRI. The material for this monograph is now covered in four volumes. The first two volumes contain the primary recommended data relating to half-lives, decay modes, x-rays, gamma-rays, electron emissions; alpha- and beta-particle transitions and emissions, and their uncertainties for a set of sixty-eight radionuclides: Volume 1 for those radionuclides with mass number up to and including 150, and Volume 2 for those radionuclides with mass number over 150. Volume 3 contains the equivalent data for twenty-six additional radionuclides and re-evaluations for 125 Sb and 153 Sm; Volume 4 contains the data for a further thirty-one radionuclides with re-evaluation for 226 Ra while the present Volume 5 includes 17 new radionuclide evaluations and 8 re-evaluations of previous data as identified in the contents page. The data have been collated and evaluated by an international working group (Decay Data Evaluation Project) led by the LNE-LNHB. The evaluators have agreed on the

Long-lived radionuclides in the marine environment of Thailand

Energy Technology Data Exchange (ETDEWEB)

Mahapanyawong, S; Sonsuk, M; Polphong, P; Milintawisamai, M; Panyatipsakul, Y

1993-12-31

Natural and artificial radionuclides in the environment of the Gulf of Thailand were studied during 1989-1991. In the study, surface water, sediment at 5 locations between latitudes 9{sup 0} 28` N and 13{sup 0} 15` N longitudes 100{sup 0} 35` E. and 5 species of marine biota were collected in 1989. In 1990 and 1991, 9 and 7 species of marine biota were collected from the Gulf of Thailand and the Andaman Sea respectively. These samples were prepared and analyzed for gamma-emitting radionuclides as well as some beta and alpha-emitting radionuclides such as C{sup 14}, Sr{sup 90}, Pu{sup 239,240}, Po{sup 210} etc. The results indicate the present status of radioactivity level of the environment of the gulf and the sea.

The work of committee 2 of ICRP on internal dosimetry

International Nuclear Information System (INIS)

Stather, J. W.

2007-01-01

Over the last few years Committee 2 of ICRP has been responsible for preparing a series of publications giving dose coefficients for intakes of radionuclides by members of the public. The last report in this series covers doses to the offspring in mothers' milk and should be issued in 2005. The emphasis of work on internal dosimetry is now concerned with occupational exposure. It is intended to replace Publications 30 and 68 that give biokinetic data and dose coefficients for intakes of radionuclides and Publications 54 and 78 that give information for bioassay interpretation, with a single series of publications. The first report of the series is expected to cover radionuclides of the elements addressed in the publications on dose coefficients for members of the public. It will also take into account new recommendations from the Commission. Subsequent publications will cover additional elements. A supporting Guidance Document is also being developed that will give more comprehensive advice on the interpretation of bioassay data. The need for this document was identified following recent interlaboratory comparisons that have shown wide variations in the way monitoring data can be interpreted in different laboratories. (authors)

Bone marrow dosimetry in peptide receptor radionuclide therapy with [177Lu-DOTA0,Tyr3]octreotate

International Nuclear Information System (INIS)

Forrer, Flavio; Krenning, Eric P.; Kooij, Peter P.; Bernard, Bert F.; Bakker, Willem H.; Teunissen, Jaap J.M.; Jong, Marion de; Kwekkeboom, Dik J.; Konijnenberg, Mark; Lom, Kirsten van; Herder, Wouter W. de

2009-01-01

Adequate dosimetry is mandatory for effective and safe peptide receptor radionuclide therapy (PRRT). Besides the kidneys, the bone marrow is a potentially dose-limiting organ. The radiation dose to the bone marrow is usually calculated according to the MIRD scheme, where the accumulated activity in the bone marrow is calculated from the accumulated radioactivity of the radiopharmaceutical in the blood. This may underestimate the absorbed dose since stem cells express somatostatin receptors. We verified the blood-based method by comparing the activity in the blood with the radioactivity in bone marrow aspirates. Also, we evaluated the absorbed cross-dose from the source organs (liver, spleen, kidneys and blood), tumours and the so-called ''remainder of the body'' to the bone marrow. Bone marrow aspirates were drawn in 15 patients after treatment with [ 177 Lu-DOTA 0 ,Tyr 3 ]octreotate. Radioactivity in the bone marrow was compared with radioactivity in the blood drawn simultaneously. The nucleated cell fraction was isolated from the bone marrow aspirate and radioactivity was measured. The absorbed dose to the bone marrow was calculated. The results were correlated to the change in platelet counts 6 weeks after treatment. A strong linear correlation and high agreement between the measured radioactivities in the bone marrow aspirates and in the blood was found (r=0.914, p 177 Lu-DOTA 0 ,Tyr 3 ]octreotate, the radioactivity concentration in the bone marrow is identical to that in the blood; (2) There is no significant binding of the radiopharmaceutical to bone marrow precursor stem cells; (3) The contribution of the cross dose from source organs and tumours to the bone marrow dose is significant; and (4) There is considerable variation in bone marrow absorbed dose between patients. These findings imply that for individual dose optimization, individual calculation of the bone marrow absorbed dose is necessary. (orig.)

Availability of nuclear decay data in electronic form, including beta spectra not previously published

International Nuclear Information System (INIS)

Eckerman, K.F.; Westfall, R.J.; Ryman, J.C.; Cristy, M.

1994-01-01

The unabridged data used in preparing ICRP Publication 38 (1983) and a monograph of the Medical Internal Radiation Dose (MIRD) Committee are now available in electronic form. The open-quotes ICRP38 collectionclose quotes contains data on the energies and intensities of radiations emitted by 825 radionuclides (those in ICRP Publication 38 plus 13 from the MIRD monograph), and the open-quotes MIRD collectionclose quotes contains data on 242 radionuclides. Each collection consists of a radiations data file and a beta spectra data file. The radiations data file contains the complete listing of the emitted radiations, their types, mean or unique energies, and absolute intensities for each radionuclide, the probability that a beta particle will be emitted with kinetic energies defined by a standard energy grid. Although summary information from the radiation data files has been published, neither the unabridged data nor the beta spectra have been published. These data files and a data extraction utility, which runs on a personal computer, are available from the Radiation Shielding Information Center at Oak Ridge National Laboratory. 13 refs., 1 fig., 6 tabs

Determination of long-lived radionuclides in environment

International Nuclear Information System (INIS)

Seki, Riki

2001-01-01

This review summarized the recent papers published after 1985, because Higuchi had written 'Radiometry in Environment' for Advanced Review in this journal, 1985. Separation, purification and measurement method of long-lived radionuclide without light elements are reported. To determine radionuclide in the environment, a pretreatment of sample such as enrichment and separation is need. An extraction chromatography and adsorbents, for example, active carbon and AMP, were developed for the above objects. For analysis of low level radionuclide, background was decreased. ICP-MS, RIMS (Resonance Ionization Mass Spectroscopy) and AMS were used to determine mass of long-lived ones. ICP-MS can measure 93 Zr, 99 Tc, 107 Pd, 129 I and 135 Cs in the radioactive waste without a chemical analysis. RIMS determined 41 Ca, 236-244 Pu, 90 Sr and 237 Np. AMS showed good results for pure beta emitter nuclides ad trace long-lived radionuclide, for example, 14 C, 10 Be, 26 Al, 36 Cl, 129 I and 236 U. Measurement method and results of 14 C, 10 Be, 26 Al, 36 Cl, 41 Ca, 63 Ni, 79 Se, 85 Kr, 99 Tc, 129 I, 237 Np and Pu were explained. (S.Y.)

Biological dosimetry, diagnosis, and treatment of bone-marrow syndrome in victims of the Chernobyl accident

International Nuclear Information System (INIS)

Nugis, V.Yu.; Konchalovskii, M.V.

1993-01-01

During our medical investigation and treatment of victims of the Chernobyl accident, we obtained extensive clinical and laboratory data. The injuries to these victims were caused primarily by high external gamma and beta radiation doses. In some cases, these doses were accompanied by skin contamination by beta- and gamma-emitting radionuclides and by an intake of radionuclides, although the latter exposure mode was, for the most part, insignificant. Cytogenetic analysis of lymphocyte cultures of peripheral blood and bone marrow provided early estimations of radiation doses based on frequency of dicentrics. These dose estimates were well correlated with dose estimates derived from analysis of neutrophil numbers in peripheral blood. Early isolation of patients with acute radiation sickness (ARS), selective decontamination of the intestine, and application of a wide range of antibiotics and antifungal and antiviral medications helped avoid the development of fatal infections in many patients. Autological cryopreserved thrombocyte mass treatment was successfully used for victims in the second and third degree of ARS. Transplantation of allogenic bone marrow (13 cases) was ineffective and frequently caused fatal secondary sickness. As a whole, complications from widespread skin contamination by beta-emitting radionuclides, interstitial radiation pneumonia complicated by infection, and gastrointestinal syndrome were the leading factors in thanatogenesis. 21 refs., 10 figs., 5 tabs

Monitoring and assessment of individual doses of occupationally exposed workers due to intake of radionuclides

International Nuclear Information System (INIS)

Alexander, O. A.

2014-04-01

Monitoring and estimation of individual intakes of radionuclides can be complex. Doses of intakes cannot be measured directly, however must be assessed from the monitoring data of the individual. The individual monitoring data includes whole body counting, excretion analysis (urine or faecal). In the estimation of these data requires that the assessor makes assumptions about the exposure scenario, including the pattern and mode of radionuclide intake. Also physicochemical characteristics of the material involved and the period of time between exposure and measurement. This project report seeks to provide some underlying guidance on monitoring programmes and data interpretation using case study. In this present study the committed effective dose (CED) 1.20mSv exceeded the recording level (i.e. 1mSv) however it was below the investigation level (i.e. 2mSv). The present study recommends that as an essential part in internal dosimetry, specialists be capable of recognizing conditions warranting follow-up bioassay and dose evaluation. Personnel should be familiar with the relevant internal dosimetry literature and the recommendations of national and international scientific organizations with regard to internal dose. (au)

Rapid determination of long-lived artificial alpha radionuclides using time interval analysis

International Nuclear Information System (INIS)

Uezu, Yasuhiro; Koarashi, Jun; Sanada, Yukihisa; Hashimoto, Tetsuo

2003-01-01

It is important to monitor long lived alpha radionuclides as plutonium ( 238 Pu, 239+240 Pu) in the field of working area and environment of nuclear fuel cycle facilities, because it is well known that potential risks of cancer-causing from alpha radiation is higher than gamma radiations. Thus, these monitoring are required high sensitivity, high resolution and rapid determination in order to measure a very low-level concentration of plutonium isotopes. In such high sensitive monitoring, natural radionuclides, including radon ( 222 Rn or 220 Rn) and their progenies, should be eliminated as low as possible. In this situation, a sophisticated discrimination method between Pu and progenies of 222 Rn or 220 Rn using time interval analysis (TIA), which was able to subtract short-lived radionuclides using the time interval distributions calculation of successive alpha and beta decay events within millisecond or microsecond orders, was designed and developed. In this system, alpha rays from 214 Po, 216 Po and 212 Po are extractable. TIA measuring system composes of Silicon Surface Barrier Detector (SSD), an amplifier, an Analog to Digital Converter (ADC), a Multi-Channel Analyzer (MCA), a high-resolution timer (TIMER), a multi-parameter collector and a personal computer. In ADC, incidental alpha and beta pulses are sent to the MCA and the TIMER simultaneously. Pulses from them are synthesized by the multi-parameter collector. After measurement, natural radionuclides are subtracted. Airborne particles were collected on membrane filter for 60 minutes at 100 L/min. Small Pu particles were added on the surface of it. Alpha and beta rays were measured and natural radionuclides were subtracted within 5 times of 145 msec. by TIA. As a result of it, the hidden Pu in natural background could be recognized clearly. The lower limit of determination of 239 Pu is calculated as 6x10 -9 Bq/cm 3 . This level is satisfied with the derived air concentration (DAC) of 239 Pu (8x10 -9 Bq/cm 3

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)

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)

Screening procedures for alpha, beta and gamma emitting radionuclides in urine

International Nuclear Information System (INIS)

Kramer, G.H.; Gardner, S.E.; Johnson, J.R.

1983-08-01

The gross actinide and beta screening methods currently used by the Bioassay Laboratory at Chalk River Nuclear Laboratories have been documented and tested. The gross gamma method has also been documented. The gross actinide method was tested with Th-nat, Pu-239, Np-237, Am-241 and Cm-244 and the average percent recoveries were 90, 99, 45, 72 and 78, respectively. The gross beta method was tested with Sr-90/Y-90, Ce-144/Pr-144, Pm-147 and Ba-133 and the average percent recoveries were 78, 100, 46 and 46, respectively. Detection limits for the gross actinide (alpha) method are found to be about 0.4 mBq and about 39 mBq for the gross beta method

Three new projects for the CERN Dosimetry Service

CERN Multimedia

CERN Bulletin

2011-01-01

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

Dosimetry Service

CERN Multimedia

2006-01-01

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

Natural radioactivity in zirconia-based dental ceramics

International Nuclear Information System (INIS)

Giussani, Augusto; Gerstmann, Udo; La Porta, Caterina; Cantone, Marie C.; Veronese, Ivan

2008-01-01

Zirconia-based ceramics are being increasingly used in dental prosthetics in substitution of metal cores, which are known to induce local toxic reactions and delayed allergic responses in the oral tissues. Some concerns have been however raised about the use of zirconia, since it is known that unpurified zirconia materials may contain non negligible levels of natural radionuclides of the U/Th series. Combined measurements of alpha and gamma spectrometry as well as beta dosimetry were conducted on zirconia samples used for dental applications. Samples were available in form of powder and/or solid blocks. The results showed that the beta dose rate in zirconia ceramics was on average only slightly higher than the levels measured in natural teeth, and generally lower than the values measured in feldspatic and glass ceramics. These materials are indeed known to deliver a beta dose significantly higher than that measured from natural teeth, due to the relatively high levels of 40 K (between 2 and 3 kBq·kg -1 ). The content of radionuclides of the U/Th series in the zirconia sample was estimated to be lower than 15 Bq·kg -1 , i.e. doubtlessly below the exclusion level of 1 kBq·kg -1 recommended by IAEA in the Safety Standard Series. Beta dosimetry measurements, however, gave indications of possible inhomogeneous clusters of radioactivity, which might give rise to local doses above the background. (author)

Public Health Goal for Naturally Occurring Radionuclides in Groundwater

International Nuclear Information System (INIS)

Kamel, N.H.M.; Omar, H.A.; El-Baset, L.A.

2008-01-01

Naturally occurring and man-made radionuclide in groundwater may have a health hazardous to some residents. The objective of this work is to provide criteria for safety of drinking-water with respect to the chemical parameters and the radionuclide content. The annual effective dose for the consumption of drinking water was considered. Ground water samples were selected from different sites in Egypt, that have the most population, it were taken from aquifer regions along Giza sites in Egypt. Chemical analyses for the major anions, cations, and the radiological analyses were tested . Activity concentrations (Bq/l) of the gross alpha and the gross beta activities of our investigated samples were compared with the maximum contaminant level (MCL) of the world health organization (WHO). Some of the water samples were found to have a higher of gross beta and alpha particles than the MCL. Alpha activity were found depending on to the total dissolved solids (TDS) content of the water samples. Gamma activity concentrations were analyzed using low background germanium detector, the higher of activity values was found in some investigated samples is due to increasing of 226 Ra and 228 Ra activities. Tritium activity concentrations also were measured using soft beta liquid scintillation counter, it was found lower than the MCL. Our investigated samples were found to have a higher concentrations of the phosphate, nitrites, iron, and manganese contents than the maximum permissible limit, all the ground water samples were found to have a higher of silica and alumina content. Commercial carbon powder and natural clay materials were tested as ion exchangers for the removal of inorganic contaminants in the ground water samples. Clay materials was found to have a higher selectivity than activated carbon for the removal of radionuclides, phosphates, nitrites, and manganese content at the ground water samples

Nuclear energy - Reference beta-particle radiation - Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field

International Nuclear Information System (INIS)

2004-01-01

ISO 6980 consists of the following parts, under the general title Nuclear energy - Reference beta-particle radiation: Part 1: Method of production; Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field; Part 3: Calibration of area and personal dosimeters and determination of their response as a function of energy and angle of incidence. This part 2 of ISO 6980 specifies methods for the measurement of the directional absorbed-dose rate in a tissue-equivalent slab phantom in the ISO 6980 reference beta-particle radiation fields. The energy range of the beta-particle-emitting isotopes covered by these reference radiations is 0.066 to 3.54 MeV (maximum energy). Radiation energies outside this range are beyond the scope of this standard. While measurements in a reference geometry (depth of 0.07 mm at perpendicular incidence in a tissue-equivalent slab phantom) with a reference class extrapolation chamber are dealt with in detail, the use of other measurement systems and measurements in other geometries are also described, although in less detail. The ambient dose equivalent, H*(10) as used for area monitoring of strongly penetrating radiation, is not an appropriate quantity for any beta radiation, even for that penetrating a 10 mm thick layer of ICRU tissue (i.e. E max > 2 MeV). If adequate protection is provided at 0.07 mm, only rarely will one be concerned with other depths, for example 3 mm. This document is geared towards organizations wishing to establish reference-class dosimetry capabilities for beta particles, and serves as a guide to the performance of dosimetry with the reference class extrapolation chamber for beta-particle dosimetry in other fields. Guidance is also provided on the statement of measurement uncertainties

Microscopic beta and gamma data for decay-heat needs

International Nuclear Information System (INIS)

Dickens, J.K.

1983-01-01

Microscopic beta and gamma data for decay-heat needs are defined as absolute-intensity spectral distributions of beta and gamma rays following radioactive decay of radionuclides created by, or following, the fission process. Four well-known evaluated data files, namely the US ENDF/B-V, the UK UKFPDD-2, the French BDN (for fission products), and the Japanese JNDC Nuclear Data Library, are reviewed. Comments regarding the analyses of experimental data (particularly gamma-ray data) are given; the need for complete beta-ray spectral measurements is emphasized. Suggestions on goals for near-term future experimental measurements are presented. 34 references

Infant doses from the transfer of radionuclides in mothers' milk

International Nuclear Information System (INIS)

Harrison, J.D.; Smith, T.J.; Phipps, A.W.

2003-01-01

Assessments of potential internal exposures of the child following radionuclide intakes by the mother require consideration of transfers during lactation as well as during pregnancy. Current ICRP work on internal dosimetry includes the estimation of radiation doses to newborn infants from radionuclides ingested in mothers' milk. Infant doses will be calculated for maternal intakes by ingestion or inhalation of the radionuclides, radioisotopes of 31 elements, for which fetal dose coefficients have been published. In this paper, modelling approaches are examined, concentrating on models developed for iodine, caesium, polonium, alkaline earth elements and the actinides. Comparisons of model predictions show maximum overall transfer to milk following maternal ingestion during lactation of about 30% of ingested activity for 131 I, 20% for 45 Ca and 137 Cs, 10% for 90 Sr, 1% for 210 Po and low values of less than 0.01% for 239 Pu and 241 Am. The corresponding infant doses from milk consumption are estimated in preliminary calculations to be about two to three times the adult dose for 45 Ca and 131 I, 70-80% of the adult dose for 90 Sr, about 40% for 137 Cs, 20% for 210 Po, and 239 Pu and 241 Am. Infant doses from radionuclides in breast milk are compared with doses to the offspring resulting from in utero exposures during pregnancy. (author)

Dosimetry system 1986

International Nuclear Information System (INIS)

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

1987-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1999-07-01

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

Current trends on internal dosimetry for patient protection in nuclear medicine

International Nuclear Information System (INIS)

Rojo, A.M.; Gisone, P.A.; Kunst, J.J.

2001-01-01

The associated risk-benefit analyses in nuclear medicine implicitly performed by the clinician have been straightforward. Relatively low administered activity activities yield important diagnostic information, the benefit of which far outweigh any potential risk associated with the attendant normal tissue radiation doses. Such small risk to benefit ratios have been very forgiving of possible inaccuracies in dose estimates. With the ongoing development of new radiopharmaceutical and the increasing therapeutic application of internal radionuclides, radiation dosimetry in nuclear medicine continues to evolve from population- and organ-average to patient-specific dose estimation. Patient-specific dosimetry refers to the estimation of radiation dose to tissues of a specific-patients based on their individual body and measured biokinetics rather than an average anthropomorphic model and hypothetic kinetic. The importance of dosimetry specific-patient considers to avoid the risk of an unsuitable treatment and/or with probability of damage to the patient. This is illustrated by the dosimetric approaches to radioiodine treatment of hyperthyroidism. The most common prescription algorithm to fix the activity administered to a hyperthyroid patient does not consider individual parameters that are highly variable (thyroid uptake, biological half-life, thyroid mass). Its arbitrary approach doesn't permit individually optimized therapy and it may be inappropriate and even hazardous. (author)

Radionuclide therapy: regional and systemic routes of administration

International Nuclear Information System (INIS)

Shapiro, B.

1991-01-01

The optimal sequencing and integration of radiopharmaceutical therapy with respect to the multiple and competing therapeutic modalities is examined. It is estimated that the central goal of therapeutic nuclear medicine is to increase radiopharmaceutical delivery to tumour targets while sparing sensitive normal tissues. Among the factors to be considered in the choice of therapeutic radionuclides are: the decay mode, gamma-ray yield, half-lives and chemical reactivity. Several routes of administration are discussed and a number of manipulations which may be used to further improve radioparmaceutical delivery are outlined. The difficulty to perform accurate radiation dosimetry is also briefly examined. 14 refs., 1 tab

Design and dosimetry of a novel 90y beta source to prevent restenosis after angioplasty

International Nuclear Information System (INIS)

Mueck, Konrad; Schmidt, Werner; Wexberg, Paul; Goerz, Walter; Maurer, Gerald; Gottsauner-Wolf, Michael

2000-01-01

Purpose: Post-dilatation irradiation of the vessel wall is currently under investigation for prevention of restenosis after balloon dilatation. For the irradiation, special sources were designed for animal experiments which would give equivalent irradiation conditions and doses to the vessel wall that would later be employed for human application. Methods and Materials: For the planned irradiations, a specially designed yttrium-wire of 0.45-mm diameter coated with a thin shrink tube to prevent contamination was deployed. Several leakage tests applied before and after application proved that the irradiation source was leakproof. Dosimetry was performed by using 0.1-mm-thick thermoluminescent dosimeters (TLD-100) calibrated against a primary standard. A shielding transport and application container was designed to facilitate the handling of the source during use, while reducing exposure of the medical personnel. Results: The designed source proves to be flexible for the insertion into proximal coronary vessels, and positioning at the site of stenosis. It provides an optimum protection of the animal and requires little radiation protection efforts on behalf of the medical staff. Dosimetric calculations and measurements showed that a centering of the source inside the vessel could be achieved with a maximum deviation of 50% between maximum and average dose levels. Conclusion: A yttrium-90 beta brachytherapy source was designed which provides high flexibility within proximal coronary arteries, ensures an adequate centering inside the artery, and provides irradiation conditions to the vessel wall of the experimental animal comparable to the application inside a human artery

Dosimetry in intravascular brachytherapy; Calculos dosimetricos em braquiterapia intravascular

Energy Technology Data Exchange (ETDEWEB)

Campos, Laelia Pumilla Botelho

2000-03-01

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

Dosimetry in intravascular brachytherapy; Calculos dosimetricos em braquiterapia intravascular

Energy Technology Data Exchange (ETDEWEB)

Campos, Laelia Pumilla Botelho

2000-03-01

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

The role of laboratory animals in studying bone cancer resulting from skeletally deposited radionuclides

International Nuclear Information System (INIS)

Boecker, B.B.; Miller, S.C.; Lloyd, R.D.; Taylor, G.N.; Griffith, W.C.; Guilmette, R.A.; Hahn, F.F.; Muggenburg, B.A.

1994-01-01

There is a continuing need to determine and understand the long-term health risks of internally deposited radionuclides in persons exposed medically or occupationally, or from radionuclides in the environment. A full understanding of these health risks, particularly for exposures involving low doses and dose rates, requires in-depth knowledge of both the dosimetry of a given exposure and the resulting long-term biological effects. Human data on 224 Ra and 226,228 Ra and their decay products are our primary sources of knowledge on the health risks of chronic alpha irradiation of the skeleton and serve as essential segments of our radiation protection practices for internally deposited radionuclides. However, we cannot obtain all of the needed information from these studies. This paper examines the role of laboratory animal studies in complementing and extending the knowledge of radiation-induced bone cancer obtained from studies of humans exposed to 224 Ra or 226,228 Ra

Methodology for implementation of a national metrology net of radionuclides used in nuclear medicine

International Nuclear Information System (INIS)

Santos, Joyra Amaral dos

2004-01-01

The National Laboratory for Ionizing Radiation Metrology, of the Institute of Radiation Protection and Dosimetry, of the National Commission on Nuclear Energy (IRD/CNEN), comes leading a comparison program for activity measurements of radiopharmaceuticals administered to patients in the Nuclear Medicine Services (NMS) with the purpose to promote the quality control. This work presents a quality assurance program for the performance of such measurements, evaluated in the comparison runs between hospitals and LNMRI, under the statistic point of view and the compliment of regulatory authority norms. The performance of the radionuclides 67 Ga, 123 I, 131 I, 99m Tc and 210 Tl were evaluated and 201 TI have been standardized by absolute methods. Besides, it was established the traceability of the radioactivity standards used in nuclear medicine and a methodology for implementation of a national metrology net of radionuclides. The comparison results prove that the implementation of a radionuclide metrology net is viable, important and feasible. (author)

Measurements of radionuclide activity by the (e-α, β, γ, Lx) coincidence method using electrons with energies of a few eV emitted from radionuclides

International Nuclear Information System (INIS)

Frolov, E.A.

1994-01-01

A study was made of the possibility of measuring radionuclide activities by the method of coincidence of electrons with energies of a few eV emitted from the valence shells of radioactive atoms with nuclear radiations. The low energy electrons were detected with a detector equipped with microchannel plates with trochoidal focusing of an original design. Photons were detected with NaI(TI) detectors. A 100 μm thick plastic scintillator was used to detect beta- and alpha-particles. The investigation shows that it is possible to use this method for accurate measurements of radionuclide activity. (orig.)

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

International Nuclear Information System (INIS)

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

2017-01-01

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

True dose from incorporated activities. Models for internal dosimetry

International Nuclear Information System (INIS)

Breustedt, B.; Eschner, W.; Nosske, D.

2012-01-01

The assessment of doses after incorporation of radionuclides cannot use direct measurements of the doses, as for example dosimetry in external radiation fields. The only observables are activities in the body or in excretions. Models are used to calculate the doses based on the measured activities. The incorporated activities and the resulting doses can vary by more than seven orders of magnitude between occupational and medical exposures. Nevertheless the models and calculations applied in both cases are similar. Since the models for the different applications have been developed independently by ICRP and MIRD different terminologies have been used. A unified terminology is being developed. (orig.)

In-house quality audit and benefits of some quality control procedures in the quality assurance of TL dosimetry system at NRPB

International Nuclear Information System (INIS)

Dutt, J.C.

1993-01-01

A number of Quality Control (QC) procedures have been introduced into the running and operation of the NRPB personal monitoring services. Those described here apply to the whole-body TL dosimetry system. These QC procedures comprise Quality Assurance (QA) of incoming raw materials and equipment, reader stabilisation, daily, routine and periodic QA checks on all phases of the service. In-house quality audit, periodic internal and external 'blind QA checks' on the dosimetry system as a whole have assured the continuing high quality and reliability of the NRPB TL dosimetry service for assessing body and skin doses of radiation workers from external photon and beta radiations. (author)

Requirement of radiochemical recovery determination for gross alpha and gross beta estimation in drinking water

International Nuclear Information System (INIS)

Raveendran, Nanda; Rao, D.D.; Hegde, A.G.

2010-01-01

Presence of radionuclides in drinking water which emits Alpha and Beta particles are the potential sources of internal exposure in drinking water. Gross alpha and gross beta determination in drinking water and packaged drinking water (PDW) as per BIS (Bureau of Indian standards) standards is discussed here. The methods have been tested to account for losses in the radiochemical procedures using radionuclides such as 137 Cs, 90 Sr, 226 Ra, 239 Pu, 243 Am, 232 U. The methods have also been validated in an IAEA proficiency test conducted during 2009. Monitoring of gross alpha and gross beta activity observed in drinking water/packaged drinking water from various states of India were within the limits set by BIS. Average radiochemical recoveries of 84% and 63% were obtained for gross α and gross β respectively. (author)

Some special considerations in evaluating the impacts of long-lived radionuclides in LLW

International Nuclear Information System (INIS)

Cohen, J.J.; Smith, C.F.; Cook, J.R.; King, C.M.

1988-01-01

A comprehensive program has been conducted at the Savannah River Plant (SRP) to assess environmental impacts of both radioactive and nonradioactive (hazardous) waste at its disposal sites to assure compliance with provisions of the National Environmental Protection Act. The objective of the current study is to characterize issues related to long-lived radionuclides in SRP waste. This work includes defining a reasonably attainable data base on parameters affecting leachability, mobility, dosimetry, and other factors that might affect radiological dose consequences. The long-lived radionuclides to be assessed include: certain transuranics, uranium, technetium-99, iodine-129, and carbon-14. The study is scheduled for completion by the end of this year. Preliminary insights and conclusions focusing primarily on neptunium-237, iodine-129, and uranium are discussed in this paper

US Army Radiological Bioassay and Dosimetry: The RBD software package

International Nuclear Information System (INIS)

Eckerman, K.F.; Ward, R.C.; Maddox, L.B.

1993-01-01

The RBD (Radiological Bioassay and Dosimetry) software package was developed for the U. S. Army Material Command, Arlington, Virginia, to demonstrate compliance with the radiation protection guidance 10 CFR Part 20 (ref. 1). Designed to be run interactively on an IBM-compatible personal computer, RBD consists of a data base module to manage bioassay data and a computational module that incorporates algorithms for estimating radionuclide intake from either acute or chronic exposures based on measurement of the worker's rate of excretion of the radionuclide or the retained activity in the body. In estimating the intake,RBD uses a separate file for each radionuclide containing parametric representations of the retention and excretion functions. These files also contain dose-per-unit-intake coefficients used to compute the committed dose equivalent. For a given nuclide, if measurements exist for more than one type of assay, an auxiliary module, REPORT, estimates the intake by applying weights assigned in the nuclide file for each assay. Bioassay data and computed results (estimates of intake and committed dose equivalent) are stored in separate data bases, and the bioassay measurements used to compute a given result can be identified. The REPORT module creates a file containing committed effective dose equivalent for each individual that can be combined with the individual's external exposure

Which radionuclide, carrier molecule and clinical indication for alpha-immunotherapy?

International Nuclear Information System (INIS)

Guerard, F.; Barbet, J.; Cherel, M.; Chatal, J.-F.; Haddad, F.; Kraeber-Bodere, F.

2015-01-01

Beta-emitting radionuclides are not able to kill isolated tumor cells disseminated in the body, even if a high density of radiolabeled molecules can be targeted at the surface of these cells because the vast majority of emitted electrons deliver their energy outside the targeted cells. Alpha-particle emitting radionuclides may overcome this limitation. It is thus of primary importance to test and validate the radionuclide of choice, the most appropriate carrier molecule and the most promising clinical indication. Four α-particle emitting radionuclides have been or are clinically tested in phase I studies namely 213 Bi, 225 Ac, 212 Pb and 211 At. Clinical safety has been documented and encouraging efficacy has been shown for some of them ( 213 Bi and 211 At). 211 At has been the most studied and could be the most promising radionuclide but 225 Ac and 212 Pb are also of potential great interest. Any carrier molecule that has been labeled with β-emitting radionuclides could be labeled with alpha particle-emitting radionuclide using, for some of them, the same chelating agents. However, the physical half-life of the radionuclide should match the biological half-life of the radioconjugate or its catabolites. Finally everybody agrees, based on the quite short range of alpha particles, on the fact that the clinical indications for alpha-immunotherapy should be limited to the situation of disseminated minimal residual diseases made of small clusters of malignant cells or isolated tumor cells.

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

International Nuclear Information System (INIS)

1987-02-01

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

Cellular dosimetry for radon progeny alpha particles in bronchial tissue

International Nuclear Information System (INIS)

Mohamed, A.; Hofmann, W.; Balashazy, I.

1996-01-01

Inhaled radon progeny are deposited in different regions of the human bronchial tree as functions of particle size and flow rate. Following deposition and mucociliary clearance, the sensitive bronchial basal and secretory cells are irradiated by two different alpha particle sources: (i) radon progeny in the sol and/or gel phase of the mucous layer, and (ii) radon progeny within the bronchial epithelium. In the case of internally deposited radionuclides, direct measurement of the energy absorbed from the ionizing radiation emitted by the decaying radionuclides is rarely, if ever, possible. Therefore, one must rely on dosimetric models to obtain estimates of the spatial and temporal patterns of energy deposition in tissues and organs of the body. When the radionuclide is uniformly distributed throughout the volume of a tissue of homogeneous composition and when the size of the tissue is large compared to the range of the particulate emissions of the radionuclide, then the dose rate within the tissue is also uniform and the calculation of absorbed dose can proceed without complication. However, if non-uniformities in the spatial and temporal distributions of the radionuclide are coupled with heterogeneous tissue composition, then the calculation of absorbed dose becomes complex and uncertain. Such is the case with the dosimetry of inhaled radon and radon progeny in the respiratory tract. There are increasing demands to obtain a definitive explanation of the role of alpha particles emitted from radon daughters in the induction of lung cancer. Various authors have attempted to evaluate the dose to the bronchial region of the respiratory tract due to the inhalation of radon daughters

Total lymphoid irradiation in the Wistar rat: technique and dosimetry

International Nuclear Information System (INIS)

Hoogenhout, J.; Kazem, I.; de Jong, J.

1983-01-01

The technical and dosimetric aspects of total lymphoid irradiation (TLI) in the Wistar rat were evaluated as part of a set-up to develop a new model for tumor xenotransplantation. Information obtained from anatomical dissections, radionuclide imaging of the spleen, lymphography and chromolymphography was used to standardize the localization portals cut out in a lead plate. The two portals encompassed the lymphoid tissue above and below the diaphragm. A specially designed masonite phantom was used to measure the dose distribution in the simulated target volumes. Ionization chamber dosimetery, thermoluminescence dosimetry and film densitometry were used for measuring exposure and absorbed dose. Irradiation was performed with 250 kV X rays (HVL 3.1 mm Cu). The dose rate was regulated by adjusting the treatment distance. The dose inhomogeneity measured in the target volumes varied between 80-100%. The side scatter dose to non target tissues under the shielded area between the two portals ranged between 20-30%. The technique and dosimetry of total lymphoid irradiation in Wistar rats are now standardized and validated and pave the way for tumor xenotransplantation experiments

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

Energy Technology Data Exchange (ETDEWEB)

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

2000-05-01

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

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

International Nuclear Information System (INIS)

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

2000-01-01

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

The 10th international congress of IRPA. The development of models for internal dosimetry

International Nuclear Information System (INIS)

Stather, J.W.

2000-01-01

that will be age-dependent and give a better definition of the anatomical regions needed for dosimetry. It will additionally evaluate information on the transport and absorption of materials in the various regions of the gastrointestinal tract and review information on the location of cells at risk. In the longer term there remains a need to develop a full revision of data used for monitoring the internal exposure for workers. With the progressive move to physiologically-based biokinetic models, the aim now is to develop models that are appropriate for both bioassay interpretation and for dosimetry calculations. Considerable thought is being given as to how the data will need to be presented, given the rapid changes in technology and the need for operational health physicists to be able to apply the more complex models that are now being developed. Other issues are presently being considered that are an important input to further model development. These include: the identification of target cells in the skeleton in relation to the calculation of doses from bone seeking radionuclides; the dosimetry of Auger emitters; the calculation of doses from inhaled radon; and the development of more realistic phantoms based on medical imaging data. (author)

Standardization of radionuclides 45Ca, 137Cs, 204Tl by tracing method using 4πβ-γ coincidence system

International Nuclear Information System (INIS)

Ponge-Ferreira, Claudia Regina Ponte

2005-01-01

The procedure followed for the standardization of 45 Ca, 137 Cs and 204 Tl is described. The activity measurements was carried out in a 4πβ-γ coincidence system by the tracing method. The radionuclides chosen as the P-y emitting tracer nuclide were 60 Co for the 45 Ca and 134 Cs for 137 Cs and 204 TL because their end-point beta-ray energy are close to the respective beta emitters. The radioactive sources were prepared using two different techniques: one was the drops technique and the other was the solution technique. In the drop technique the sources were prepared by dropping directly on the subtract both solutions (tracer and beta pure). In the other technique a solution of tracer plus beta pure was mixed previously before making the radioactive sources. The activities of the radionuclides obtained with these technique were compared and the values are in agreement within the experimental uncertainties. (author)

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

Energy Technology Data Exchange (ETDEWEB)

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

2009-09-30

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

Neutron personnel dosimetry

International Nuclear Information System (INIS)

Griffith, R.V.

1981-01-01

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

Dose point kernels for beta-emitting radioisotopes

International Nuclear Information System (INIS)

Prestwich, W.V.; Chan, L.B.; Kwok, C.S.; Wilson, B.

1986-01-01

Knowledge of the dose point kernel corresponding to a specific radionuclide is required to calculate the spatial dose distribution produced in a homogeneous medium by a distributed source. Dose point kernels for commonly used radionuclides have been calculated previously using as a basis monoenergetic dose point kernels derived by numerical integration of a model transport equation. The treatment neglects fluctuations in energy deposition, an effect which has been later incorporated in dose point kernels calculated using Monte Carlo methods. This work describes new calculations of dose point kernels using the Monte Carlo results as a basis. An analytic representation of the monoenergetic dose point kernels has been developed. This provides a convenient method both for calculating the dose point kernel associated with a given beta spectrum and for incorporating the effect of internal conversion. An algebraic expression for allowed beta spectra has been accomplished through an extension of the Bethe-Bacher approximation, and tested against the exact expression. Simplified expression for first-forbidden shape factors have also been developed. A comparison of the calculated dose point kernel for 32 P with experimental data indicates good agreement with a significant improvement over the earlier results in this respect. An analytic representation of the dose point kernel associated with the spectrum of a single beta group has been formulated. 9 references, 16 figures, 3 tables

Confirmation of selected milk and meat radionuclide-transfer coefficients

International Nuclear Information System (INIS)

Ward, G.M.; Johnson, J.E.

1983-01-01

The elements selected for study of their transfer coefficients to eggs, poultry meat, milk and beef were Mo, Tc, Te, and Ba. The radionuclides used in the study were the gamma-emitting radionuclides 99 Mo, /sup 123m/Te and 133 Ba. 133 Ba was selected because 140 Ba- 140 La is produced infrequently and availability was uncertain. 133 Ba has a great advantage for our type of experiment because of its longer physical half-life. 99 Tc is a pure beta-emitter and was used in the first three animal experiments because we could not obtain the gamma-emitting /sup 95m/Tc. A supply of this nuclide was recently obtained, however, for the second cow experiment

Biodistribution and dosimetry of iodine-123-labelled Z-MIVE: an oestrogen receptor radioligand for breast cancer imaging

NARCIS (Netherlands)

Rijks, L. J.; Busemann Sokole, E.; Stabin, M. G.; de Bruin, K.; Janssen, A. G.; van Royen, E. A.

1998-01-01

This study reports on the distribution and radiation dosimetry of iodine-123-labelled cis-11beta-methoxy-17alpha-iodovinyloestradiol (Z-[123I]MIVE), a promising radioligand for imaging of oestrogen receptors (ERs) in human breast cancer. Whole-body scans were performed up to 24 h after intravenous

Performance of a coumarin-based liquid dosimeter for phantom evaluations of internal dosimetry

Energy Technology Data Exchange (ETDEWEB)

Park, Mi-Ae [Department of Radiology, Brigham and Women' s Hospital, Boston, MA 02115 (United States): Harvard Medical School, Boston, MA 02115 (United States)]. E-mail: miaepark@bwh.Harvard.edu; Moore, Stephen C. [Department of Radiology, Brigham and Women' s Hospital, Boston, MA 02115 (United States): Harvard Medical School, Boston, MA 02115 (United States); Limpa-Amara, Naengnoi [Department of Radiology, Brigham and Women' s Hospital, Boston, MA 02115 (United States): Harvard Medical School, Boston, MA 02115 (United States); Kang Zhuang [Department of Physics, University of Massachusettes at Lowell, Lowell, MA 01854 (United States); Makrigiorgos, G. Mike [Dana Faber-Brigham and Women' s Cancer Center, Boston, MA 01225 (United States): Harvard Medical School, Boston, MA 02115 (United States)

2006-12-20

Targeted radionuclide therapy (TRT) requires accurate absorbed dose estimation in individual patients. It has been shown that a coumarin-based liquid dosimeter is useful for various phantom geometries of relevance to patient-specific internal dosimetry. The purpose of this study was to refine the performance limits of the coumarin-3-carboxylic acid (CCA) dosimeter using the high-energy {beta}-emitter, Y-90, by measuring the dosimeter's dependence on dose rate, by finding the maximum dose limit, and by comparing measured dose values to those from Monte Carlo (MC) simulation. Non-fluorescent CCA is converted to highly fluorescent 7-hydroxyl-coumarin-3-carboxylic acid (7-OH-CCA) upon irradiation. We measured the Y-90-induced fluorescence from 7-OH-CCA under different conditions. Fluorescence was measured using activity concentrations from 1.1 to 181 MBq/cc, providing initial dose rates from 0.7 to 117 cGy/min. To determine the maximum dose limit, fluorescence was measured for different elapsed times from 4 to 150 h, using a fixed activity concentration, 3.7 MBq/cc. A Cs-137 irradiator was used for calibration, to convert fluorescence measurements to absorbed dose. We calculated absorbed dose using the DOSXYZnrc MC program. We modeled the geometry of cuvettes realistically, including plastic walls, surrounding air, and Y-90 in liquid. S-values of Y-90 in water were calculated using 1-mm cubic voxels. A linear dependence of fluorescence on dose rate was observed up to 80 cGy/min, and the dependence on total dose was linear up to {approx}20 Gy The average difference between calculated and measured dose values over 9 samples was 3.6{+-}2%. For our geometry, the dose based on voxel S-values was within 1% of that calculated using MC simulation of the phantom. We refined the performance limits of a CCA-based dosimeter for phantom studies of TRT using Y-90, and confirmed a close agreement between measured and calculated dose values. CCA dosimetry is a promising technique

A preliminary investigation of radiation level and some radionuclides in imported food and food products

International Nuclear Information System (INIS)

Sinakhom, F.; Mongkolphantha, S.

1980-04-01

A preliminary study of gross beta activity and content of some long-lived radionuclides associated with fission products in various types of imported food and food-products was carried out. Food samples were purchased monthly during 1976-1977 from general well-known supermarkets and local grocery stores up to a total of 89 samples. The gamma spectrum of long-lived radionuclides was searched using a 128 channel analyzer coupled with 3'' x 3'' NaI (T1) crystal detector. Two radionuclides were frequently found to be present in these food samples, viz. potassium-40 and cesium-137 and their concentrations were subsequently determined. The limits of detection under the conditions used for potassium-40 and cesium-137 were 0.04 and 0.03 pCi/g-wet weight, respectively. Samples were dry-ashed and counted for gross beta activity utilizing a low background anti-coincidence G.M. counter. The content of strontium-90 was also investigated concurrently by solvent extraction technique employing tri-n-butyl phosphate as an extractant. Results of the study are tabulated. (author)

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

MIRD Pamphlet No. 21: A Generalized Schema for Radiopharmaceutical Dosimetry-Standardization of Nomenclature

International Nuclear Information System (INIS)

Bolch, W.E.; Eckerman, Keith F.; Sgouros, George; Thomas, Steven R.

2009-01-01

The internal dosimetry schema of the Medical Internal Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine has provided a broad framework for assessment of the absorbed dose to whole organs, tissue subregions, voxelized tissue structures, and individual cellular compartments for use in both diagnostic and therapeutic nuclear medicine. The schema was originally published in 1968, revised in 1976, and republished in didactic form with comprehensive examples as the MIRD primer in 1988 and 1991. The International Commission on Radiological Protection (ICRP) is an organization that also supplies dosimetric models and technical data, for use in providing recommendations for limits on ionizing radiation exposure to workers and members of the general public. The ICRP has developed a dosimetry schema similar to that of the MIRD Committee but has used different terminology and symbols for fundamental quantities such as the absorbed fraction, specific absorbed fraction, and various dose coefficients. The MIRD Committee objectives for this pamphlet are 3-fold: to restate its schema for assessment of absorbed dose in a manner consistent with the needs of both the nuclear medicine and the radiation protection communities, with the goal of standardizing nomenclature; to formally adopt the dosimetry quantities equivalent dose and effective dose for use in comparative evaluations of potential risks of radiation-induced stochastic effects to patients after nuclear medicine procedures; and to discuss the need to identify dosimetry quantities based on absorbed dose that address deterministic effects relevant to targeted radionuclide therapy.

Lower limits of detection in using carbon nanotubes as thermoluminescent dosimeters of beta radiation

Science.gov (United States)

Alanazi, Abdulaziz; Jurewicz, Izabela; Alalawi, Amani I.; Alyahyawi, Amjad; Alsubaie, Abdullah; Hinder, Steven; Bañuls-Ciscar, Jorge; Alkhorayef, Mohammed; Bradley, D. A.

2017-11-01

World-wide, on-going intensive research is being seen in adaptation of carbon nanotubes (CNTs) for a wide variety of applications, particular interest herein being in the thermoluminescent (TL) properties of CNTs and their sensitivity towards energetic radiations. Using beta radiation delivering dose levels of a few Gy it has been observed in previous study that strain and impurity defects in CNTs give rise to significant TL yields, providing an initial measure of the extent to which electron trapping centres exist in various qualities of CNT, from super-pure to raw. This in turn points to the possibility that there may be considerable advantage in using such media for radiation dosimetry applications, including for in vivo dosimetry. CNTs also have an effective atomic number similar to that of adipose tissue, making them suitable for soft tissue dosimetry. In present investigations various single-wall carbon nanotubes (SWCNT) samples in the form of buckypaper have been irradiated to doses in the range 35-1.3 Gy, use being made of a 90Sr beta source, the response of the CNTs buckypaper with dose showing a trend towards linearity. It is shown for present production methodology for buckypaper samples that the raw SWCNT buckypaper offer the greatest sensitivity, detecting doses down to some few tens of mGy.

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

International Nuclear Information System (INIS)

Poirier, G.S.

1989-04-01

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

Dosimetric characterization of radionuclides for systemic tumor therapy: Influence of particle range, photon emission, and subcellular distribution

International Nuclear Information System (INIS)

Uusijaervi, Helena; Bernhardt, Peter; Ericsson, Thomas; Forssell-Aronsson, Eva

2006-01-01

Various radionuclides have been proposed for systemic tumor therapy. However, in most dosimetric analysis of proposed radionuclides the charged particles are taken into consideration while the potential photons are ignored. The photons will cause undesirable irradiation of normal tissue, and increase the probability of toxicity in, e.g., the bone marrow. The aim of this study was to investigate the dosimetric properties according to particle range, photon emission, and subcellular radionuclide distribution, of a selection of radionuclides used or proposed for radionuclide therapy, and to investigate the possibility of dividing radionuclides into groups according to their dosimetric properties. The absorbed dose rate to the tumors divided by the absorbed dose rate to the normal tissue (TND) was estimated for different tumor sizes in a mathematical model of the human body. The body was simulated as a 70-kg ellipsoid and the tumors as spheres of different sizes (1 ng-100 g). The radionuclides were either assumed to be uniformly distributed throughout the entire tumor and normal tissue, or located in the nucleus or the cytoplasm of the tumor cells and on the cell membrane of the normal cells. Fifty-nine radionuclides were studied together with monoenergetic electrons, positrons, and alpha particles. The tumor and normal tissue were assumed to be of water density. The activity concentration ratio between the tumor and normal tissue was assumed to be 25. The radionuclides emitting low-energy electrons combined with a low photon contribution, and the alpha emitters showed high TND values for most tumor sizes. Electrons with higher energy gave reduced TND values for small tumors, while a higher photon contribution reduced the TND values for large tumors. Radionuclides with high photon contributions showed low TND value for all tumor sizes studied. The radionuclides studied could be divided into four main groups according to their TND values: beta emitters, Auger electron

Development of methodology for detection of long lived alpha emitters in air based on simultaneous alpha and beta activity measurement

International Nuclear Information System (INIS)

Kaushik, Vivek; Rath, D.P.; Vinayagami, Bhakti; Ashokkumar, P.; Umashankar, C.; Gopalakrishnan, R.K.; Kulkarni, M.S.

2018-01-01

Interference of the radon and thoron progeny co-deposited on the filtration media is the long-standing problem related to prompt analyses in continuous air sampling or monitoring of any potential suspect radionuclides. The solutions to this problem have been quite diverse, and included, for example, simple gross-alpha counting, the use of beta-to-alpha ratios, and the use of alpha spectrum analyses. The techniques based on beta to alpha disintegration ratios make use of the naturally occurring alpha to beta disintegration ratios and departures therefrom. This ratio is found empirically to be relatively constant. With the help of the solution of differential equation, which govern the deposition of radionuclide on filter paper, one can easily estimate theoretically the behavior of the radon progeny alpha to beta disintegration (or count) rate ratio

Contribution of maternal radionuclide burdens to prenatal radiation doses

International Nuclear Information System (INIS)

Sikov, M.R.; Hui, T.E.; Meznarich, H.K.; Thrall, K.D.

1992-03-01

This report discusses approaches to calculating and expressing radiation doses to the embryo/fetus from internal radionuclides. Information was obtained for selected, occupationally significant radionuclides in chemical forms that provided a spectrum of metabolic and dosimetric characteristics. Fractional placental transfer and/or ratios of concentration in the embryo/fetus to that in the woman were estimated for these materials, and were combined with data from biokinetic transfer models to predict radioactivity levels in the embryo/fetus as a function of stage of pregnancy and time after entry into the transfer compartment or blood of the pregnant woman. Medical Internal Radiation Dosimetry (MIRD) methodologies were extended to formalize and describe details for calculating radiation absorbed doses to the embryo/fetus. Calculations were performed for representative situations; introduction of 1 μCi into a woman's blood at successive months of pregnancy was assumed to accommodate the stage dependence of geometric relationships and biological behaviors. Summary tables of results, correlations, and dosimetric relations, and of tentative generalized categorizations, are provided in the report

Evaluation of environmental dosimetry models for applicability to possible radioactive waste repository discharges

International Nuclear Information System (INIS)

Mauro, J.J.; Michlewicz, D.; Letizia, A.

1977-09-01

This report presents the results of a review of the available codes, for application to the National Waste Terminal Storage (NWTS) Program. Consideration was given to the types of radionuclides which may be of concern, the possible modes of release of these radionuclides and the various pathways by which members of the general public in the vicinity of a terminal storage facility may be exposed to the releases. Results reveal that the types and quantities of radioactive material requiring disposal will depend on the type of back and fuel cycle adopted. It can be assumed that under normal operating conditions there will be virtually no liquid effluent and inconsequentially small quantities of radioactive gaseous effluent. Under accident conditions during operation, both liquid and gaseous releases could occur resulting in exposures to the general public. Failure of the facility subsequent to decommissioning could also result in exposures but primarily via the aquatic pathways. A review of three atmospheric dispersion models and 32 environmental dosimetry codes presently used by the nuclear industry was performed. A discussion is presented on standard NRC methodologies for determining the dispersion coefficients used as input to the various models and the inherent limitations of many of the techniques routinely used to evaluate site specific atmospheric dispersion. The review of the dosimetry codes reveals that no one code is generally applicable to the NWTS Program, but some codes permit radiological assessment of the most important exposure pathways

Standardization of the calibration of brachytherapy sources at the IAEA dosimetry laboratory

International Nuclear Information System (INIS)

Shanta, A.; Andreo, P.

1996-01-01

A new service to SSDLs has been initiated at the IAEA Dosimetry Laboratory for providing calibrations of well-type ionisation chambers, used in brachytherapy applications, which are traceable to the International Measurement System. Considering that the most common radionuclide used in the developing countries is 137 Cs, two such sources of the type used for gynaecological intracavitary applications have been purchased by the Agency and calibrated at the National Institute of Standards and Technology (NIST), USA. These 137 Cs reference sources together with a well-type ionization chamber constitute the IAEA brachytherapy dosimetry standard. Based on the recommendations by a group of experts, a method has been developed for transferring calibrations to SSDLs which is described in this paper. The method is based on the acquisition by the SSDLs of sources and equipment similar to those at the IAEA. The well-type chamber is to be calibrated at the IAEA Dosimetry Laboratory, and this will be used at the SSDL to calibrate its own reference sources. These sources can in turn by used to calibrate well-type chambers from hospital users and to calibrate other type of sources by performing measurements in air. In order to standardize the procedures for the two methods and to provide guidance to the SSDLs, measurements have been carried out at the IAEA Dosimetry Laboratory. The reproducibility of the two type of measurements has been found to be better than 0.5%, and the uncertainty of calibrations estimated to be less than 1.5% (one standard deviation). (author). 8 refs, 8 figs, 2 tabs

Decay profiles of {beta} and {gamma} for a radionuclide inventory in equilibrium cycle of a BWR type reactor; Perfiles de decaimiento de radiacion {beta} y {gamma} para un inventario de radionuclidos en ciclo de equilibrio de un reactor tipo BWR

Energy Technology Data Exchange (ETDEWEB)

Salaices, M.; Sandoval, S.; Ovando, R. [Instituto de Investigaciones Electricas. Gerencia de Energia Nuclear, Av. Reforma 113 Col. Palmira. 62490 Cuernavaca, Morelos (Mexico)]. e-mail: sal@iie.org.mx

2007-07-01

Presently work the {beta} and {gamma} radiation decay profiles for a radionuclides inventory in equilibrium cycle of a BWR type reactor is presented. The profiles are presented in terms of decay in the activity of the total inventory as well as of the chemical groups that conform the inventory. In the obtaining of the radionuclides inventory in equilibrium cycle the ORIGEN2 code, version 1 was used, which simulates fuel burnup cycles and it calculates the evolution of the isotopic composition as a result of the burnt one, irradiation and decay of the nuclear fuel. It can be observed starting from the results that the decrease in the activity for the initial inventory and the different chemical groups that conform it is approximately proportional to the base 10 logarithm of the time for the first 24 hours of having concluded the burnt one. It can also be observed that the chemical groups that contribute in more proportion to the total activity of the inventory are the lanthanides-actinides and the transition metals, with 39% and 28%, respectively. The groups of alkaline earth metals, halogens, metalloids, noble gases and alkaline metals, contribute with percentages that go from the 8 to 5%. The groups that less they contribute to the total activity of the inventory they are the non metals and semi-metals with smaller proportions that 1%. The chemical groups that more contribute to the energy of {beta} and {gamma} radiation its are the transition metals and the lanthanides-actinides with a change in the order of importance at the end of the 24 hours period. The case of the halogens is of relevance for the case of the {gamma} radiation energy due that occupying the very near third site to the dimensions of the two previous groups. Additionally, the decay in the activity for the total inventory and the groups that conform it can be simulated by means of order 6 polynomials or smaller than describe its behavior appropriately. The results presented in this work, coupled

Development of a portable triple silicon detector telescope for beta spectroscopy and skin dosimetry

Energy Technology Data Exchange (ETDEWEB)

Helt-Hansen, J

2000-11-01

It is now recognized that beta radiation can be a significant radiation problem for exposure of the skin. There is thus a need for a portable and rugged active beta dosemeter-spectrometer to carry out immediate measurements of doses and energies of beta particles even in the presence of photon radiation. The main objective of this report is to describe the development of such an instrument. A beta-spectrometer has been developed consisting of three silicon surface barrier detectors with the thickness: 50{mu}m/150{mu}m/7000{mu}m covered by a 2 {mu}m thick titanium window. The spectrometer is capable of measuring electron energies from 50 keV to 3.5 MeV. The spectrometer is characterized by a compact low weight design, achieved by digital signal processing beginning at an early stage in the signal chain. 255 channels are available for each of the three detectors. The spectrometer is controlled by a laptop computer, which also handles all subsequent data analysis. By use of coincidence/anti-coincidence considerations of the absorbed energy in the three detector elements, counts caused by electrons are separated from those originating from photons. The electron energy distribution is multiplied by a set of conversion coefficients to obtain the dose at 0.07 mm tissue. Monte Carlo calculations has been used to derive the conversion coefficients and to investigate the influence of noise and the design of detector assembly on the performance of the spectrometer. This report describes the development of the spectrometer and its mode of operation, followed by a description of the Monte Carlo calculations carried out to obtain the conversion coefficients. Finally is the capability of the telescope spectrometer to measure beta and photon spectra as well as beta dose rates in pure beta and mixed beta/photon radiation fields described. (au)

Development of a portable triple silicon detector telescope for beta spectroscopy and skin dosimetry

International Nuclear Information System (INIS)

Helt-Hansen, J.

2000-11-01

It is now recognized that beta radiation can be a significant radiation problem for exposure of the skin. There is thus a need for a portable and rugged active beta dosemeter-spectrometer to carry out immediate measurements of doses and energies of beta particles even in the presence of photon radiation. The main objective of this report is to describe the development of such an instrument. A beta-spectrometer has been developed consisting of three silicon surface barrier detectors with the thickness: 50μm/150μm/7000μm covered by a 2 μm thick titanium window. The spectrometer is capable of measuring electron energies from 50 keV to 3.5 MeV. The spectrometer is characterized by a compact low weight design, achieved by digital signal processing beginning at an early stage in the signal chain. 255 channels are available for each of the three detectors. The spectrometer is controlled by a laptop computer, which also handles all subsequent data analysis. By use of coincidence/anti-coincidence considerations of the absorbed energy in the three detector elements, counts caused by electrons are separated from those originating from photons. The electron energy distribution is multiplied by a set of conversion coefficients to obtain the dose at 0.07 mm tissue. Monte Carlo calculations has been used to derive the conversion coefficients and to investigate the influence of noise and the design of detector assembly on the performance of the spectrometer. This report describes the development of the spectrometer and its mode of operation, followed by a description of the Monte Carlo calculations carried out to obtain the conversion coefficients. Finally is the capability of the telescope spectrometer to measure beta and photon spectra as well as beta dose rates in pure beta and mixed beta/photon radiation fields described. (au)

Adaptation and impairment of DNA repair function in pollen of Betula verrucosa and seeds of Oenothera biennis from differently radionuclide-contaminated sites of Chernobyl.

Science.gov (United States)

Boubriak, I I; Grodzinsky, D M; Polischuk, V P; Naumenko, V D; Gushcha, N P; Micheev, A N; McCready, S J; Osborne, D J

2008-01-01

The plants that have remained in the contaminated areas around Chernobyl since 1986 encapsulate the effects of radiation. Such plants are chronically exposed to radionuclides that they have accumulated internally as well as to alpha-, beta- and gamma-emitting radionuclides from external sources and from the soil. This radiation leads to genetic damage that can be countered by DNA repair systems. The objective of this study is to follow DNA repair and adaptation in haploid cells (birch pollen) and diploid cells (seed embryos of the evening primrose) from plants that have been growing in situ in different radionuclide fall-out sites in monitored regions surrounding the Chernobyl explosion of 1986. Radionuclide levels in soil were detected using gamma-spectroscopy and radiochemistry. DNA repair assays included measurement of unscheduled DNA synthesis, electrophoretic determination of single-strand DNA breaks and image analysis of rDNA repeats after repair intervals. Nucleosome levels were established using an ELISA kit. Birch pollen collected in 1987 failed to perform unscheduled DNA synthesis, but pollen at gamma/beta-emitter sites has now recovered this ability. At a site with high levels of combined alpha- and gamma/beta-emitters, pollen still exhibits hidden damage, as shown by reduced unscheduled DNA synthesis and failure to repair lesions in rDNA repeats properly. Evening primrose seed embryos generated on plants at the same gamma/beta-emitter sites now show an improved DNA repair capacity and ability to germinate under abiotic stresses (salinity and accelerated ageing). Again those from combined alpha- and gamma/beta-contaminated site do not show this improvement. Chronic irradiation at gamma/beta-emitter sites has provided opportunities for plant cells (both pollen and embryo cells) to adapt to ionizing irradiation and other environmental stresses. This may be explained by facilitation of DNA repair function.

Radiosensitivity of Prostate Cancer Cell Lines for Irradiation from Beta Particle-emitting Radionuclide ¹⁷⁷Lu Compared to Alpha Particles and Gamma Rays.

Science.gov (United States)

Elgqvist, Jörgen; Timmermand, Oskar Vilhelmsson; Larsson, Erik; Strand, Sven-Erik

2016-01-01

The purpose of the present study was to investigate the radiosensitivity of the prostate cancer cell lines LNCaP, DU145, and PC3 when irradiated with beta particles emitted from (177)Lu, and to compare the effect with irradiation using alpha particles or gamma rays. Cells were irradiated with beta particles emitted from (177)Lu, alpha particles from (241)Am, or gamma rays from (137)Cs. A non-specific polyclonal antibody was labeled with (177)Lu and used to irradiate cells in suspension with beta particles. A previously described in-house developed alpha-particle irradiator based on a (241)Am source was used to irradiate cells with alpha particles. External gamma-ray irradiation was achieved using a standard (137)Cs irradiator. Cells were irradiated to absorbed doses equal to 0, 0.5, 1, 2, 4, 6, 8, or 10 Gy. The absorbed doses were calculated as mean absorbed doses. For evaluation of cell survival, the tetrazolium-based WST-1 assay was used. After irradiation, WST-1 was added to the cell solutions, incubated, and then measured for level of absorbance at 450 nm, indicating the live and viable cells. LNCaP, DU145, and PC3 cell lines all had similar patterns of survival for the different radiation types. No significant difference in surviving fractions were observed between cells treated with beta-particle and gamma-ray irradiation, represented for example by the surviving fraction values (mean±SD) at 2, 6, and 10 Gy (SF2, SF6, and SF10) for DU145 after beta-particle irradiation: 0.700±0.090, 0.186±0.050 and 0.056±0.010, respectively. A strong radiosensitivity to alpha particles was observed, with SF2 values of 0.048±0.008, 0.018±0.006 and 0.015±0.005 for LNCaP, DU145, and PC3, respectively. The surviving fractions after irradiation using beta particles or gamma rays did not differ significantly at the absorbed dose levels and dose rates used. Irradiation using alpha particles led to a high level of cell killing. The results show that the beta-particle emitter

Personnel β-dosimetry method for reducing energy dependence

International Nuclear Information System (INIS)

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

1979-03-01

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

The personal dosimetry in Mexico; La dosimetria personal en Mexico

Energy Technology Data Exchange (ETDEWEB)

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

2006-07-01

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

Radioactive decay data tables: A handbook of decay data for application to radiation dosimetry and radiological assessments

Science.gov (United States)

Kocher, D. C.; Smith, J. S.

Decay data are presented for approximately 500 radionuclides including those occurring naturally in the environment, those of potential importance in routine or accidental releases from the nuclear fuel cycle, those of current interest in nuclear medicine and fusion reactor technology, and some of those of interest to Committee 2 of the International Commission on Radiological Protection for the estimation of annual limits on intake via inhalation and ingestion for occupationally exposed individuals. Physical processes involved in radioactive decay which produce the different types of radiation observed, methods used to prepare the decay data sets for each radionuclide in the format of the computerized evaluated nuclear structure data file, the tables of radioactive decay data, and the computer code MEDLIST used to produce the tables are described. Applications of the data to problems of interest in radiation dosimetry and radiological assessments are considered as well as the calculations of the activity of a daughter radionuclide relative to the activity of its parent in a radioactive decay chain.

Life-span health effects of relatively soluble forms of internally deposited beta-emitting radionuclides

International Nuclear Information System (INIS)

Boecker, B.B.; Muggenburg, B.A.; Hahn, F.F.; Nikula, K.J.; Griffith, W.C.

1991-01-01

As part of a large research effort to study the lifetime health risks of inhaled radionuclides, Beagle dogs inhaled 90 SrCl 2 or 144 CeCl 3 or were injected intravenously with 137 CsCl. Because these three compounds were soluble in body fluids, the resulting widely differing patterns of radionuclide distribution and dose reflected tissue affinities of the elements involved. Long-term health effects, predominantly cancers, were seen in the organs receiving the highest doses. Investigations are continuing on the extent to which other less irradiated organs may have also been affected

Specific processes in solvent extractiotn of radionuclide complexes

International Nuclear Information System (INIS)

Macasek, F.

1982-01-01

The doctoral thesis discusses the consequences of the radioactive beta transformation in systems liquid-liquid and liquid-ion exchanger, and the effect of the chemical composition of liquid-liquid systems on the distribution of radionuclide traces. A model is derived of radiolysis in two-phase liquid-liquid systems used in nuclear chemical technology. The obtained results are used to suggest the processing of radioactive wastes using the Purex process. For solvent extraction the following radionuclides were used: 59 Fe, 95 Zr- 95 Nb, 99 Mo, sup(99m)Tc, 99 Tc, 103 Pd, 137 Cs, 141 Ce, 144 Ce- 144 Pr, 234 Th, and 233 Pa. Extraction was carried out at laboratory temperature. 60 Co was used as the radiation source. Mainly scintillation spectrometry equipment was used for radiometric analysis. (E.S.)

A comparative study of preliminary dosimetry for human based on distribution data in rats with 111In, 90Y, 153Sm, and 177Lu labeled rituximab

Directory of Open Access Journals (Sweden)

Radfar Edalat

2012-01-01

Full Text Available Radio immunotherapy is one of the most important and effective therapies for B-cell non Hoddgkin’s lymphoma treatment. Today, anti CD-20 antibodies labeled with beta emitter radionuclides are used in radio immunotherapy. Various radionuclides for labeling anti CD-20 antibodies have been studied and developed for the treatment and diagnosis of malignancies. This paper describes the preparation, bio-distribution and absorbed dose rate of 111In, 90Y, 177Lu, and 153Sm labeled anti CD-20 antibodies (rituximab in human organs, after injection to rats. The macro cyclic bifunctional chelating agent, N-succinimidyl-1, 4, 7, 10-tetraazacyclododecane-1, 4, 7, 10-tetraacetic acid (DOTA-NHS for conjugation to antibody, was used to prepare DOTA-rituximab. The conjugates were purified by molecular filtration, the average number of DOTA conjugated per mAb was calculated and total concentration was determined by spectrophotometric method. Radio-labeling was performed at 40 °C for 24 hours. After the quality control studies, the final radioactive solution was injected intravenously into rats through their tail vein. The tissue uptakes of each injection were measured. Then we calculated S values for 177Lu and 153Sm by using specific absorbed fractions and data used in the manner of radio-labeled analysis and dosimetry for humans. The absorbed dose rate of each organ was calculated in the specific time by medical internal radiation dose method with linear approximation in the activity measurements.

'Hot particle' intercomparison dosimetry

International Nuclear Information System (INIS)

Kaurin, D.G.L.; Baum, J.W.; Charles, M.W.; Darley, D.P.J.; Durham, J.S.; Scannell, M.J.; Soares, C.G.

1996-01-01

Dosimetry measurements of four 'hot particles' were made at different density thickness values using five different methods. The hot particles had maximum dimensions of 650 μm and maximum beta energies of 0.97, 046, 0.36, and 0.32 MeV. Absorbers were used to obtain the dose at different depths for each dosimeter. Measurements were made using exoelectron dosimeters, an extrapolation chamber, NE Extremity Tape Dosimeters (tm), Eberline RO-2 and RO-2A survey meters, and two sets of GafChromic (tm) dye film with each set read out at a different institution. From these results the dose was calculated averaged over 1 cm 2 of tissue at 18, 70, 125, and 400 μm depth. Comparisons of tissue-dose averaged over 1 cm 2 for 18, 70, and 125 μm depth based on interpolated measured values, were within 30% for the GafChromic (tm) dye film, extrapolation chamber, NE Extremity Tape Dosimeters (tm), and Eberline RO-2 and 2A (tm) survey meters except for the hot particle with 0.46 MeV maximum beta energy. The results for this source showed differences of up to 60%. The extrapolation chamber and NE Extremity Tape dosimeters under-responded for measurements at 400 μm by about a factor of 2 compared with the GafChromic dye films for two hot particles with maximum beta energy of 0.32 and 0.36 MeV which each emitted two 100% 1 MeV photons per disintegration. Tissue doses determined using exoelectron dosimeters were a factor of 2 to 5 less than those determined using other dosimeters, possibly due to failures of the equipment. (author)

Investigation of beta ray attenuation in CaSO4:Dy(Tm)-teflon rods

International Nuclear Information System (INIS)

Szabo, P.P.

1990-12-01

Ultrathin discs were prepared from CaSO 4 :Dy(Tm)-teflon rods by cutting them with a microtom. The effect of cutting was studied experimentally. It was found that the cutting does not affect the TL signal of the discs, so one will be able to irradiate the rod and cut it afterwards which means that this method can be applied in the dosimetry of boundaries or to establish the energy of beta radiation. Depth dose distribution measurements were carried out by irradiating the rods with beta sources. (K.A.) 5 refs.; 6 figs

Measurement of gross alpha, gross beta, radon and radium activity concentrations in aqueous samples using liquid scintillation technique

International Nuclear Information System (INIS)

Zaini Hamzah; Ahmad Saat; Masitah Alias; Siti Afiqah Abdul Rahman; Mohamed Kasim; Abdul Kadir Ishak

2011-01-01

Recently, Malaysia has taken a positive step toward providing a better water quality by introducing more water quality parameters into its Water Quality Standard. With regard to the natural radionuclides that may present in the water, 3 parameters were introduced that is gross alpha, gross beta and radium which need to be measured and cannot exceed 0.1, 1.0 and 1.0 Bq/ L respectively. This study was conducted to develop a more practical method in measuring these parameters in aqueous environmental samples. Besides having a lot of former tin mining areas, some part of Malaysia is located on the granitic rock which also contributes to a certain extent the amount of natural radionuclides such as uranium and thorium. For all we know these two radionuclides are the origin of other radionuclides being produced from their decay series. The State of Kelantan was chosen as the study area, where the water samples were collected from various part of the Kelantan River. 25 liters of samples were collected, acidify to pH 2 and filtered before the analysis. Measurement of these parameters was done using liquid scintillation counter (LSC). The LSC was set up to the optimum discriminator level and counting was done using alpha-beta mode. The results show that gross alpha and beta can be measured using scintillation cocktail and radium and radon using extraction method. The results for gross alpha, gross beta, 222 Ra and 226 Ra are 0.39-6.42, 0.66-16.18, 0.40-4.65 and 0.05-0.56 Bq/ L. MDA for gross alpha, gross beta and radium is 0.03, 0.08 and 0.00035 Bq/ L respectively. (Author)

Study on natural radionuclide activities in meat samples consumed in Sao Paulo City, Brazil

International Nuclear Information System (INIS)

Rosa, Mychelle M.L.; Taddei, Maria HelenaT.

2015-01-01

Consumption of food is usually the most important route by which natural and artificial radionuclides can enter the human body. An assessment of radionuclide levels in different foods and diets is therefore important to estimate the intake of these radionuclides by man. The contamination by radionuclides can occur via the food chain (soil, root, plant and animal), with emphasis to the long half-life radionuclides, which can also have their transfer through the animal meat. The inclusion of meat in human nutrition is important because it is an excellent source of high quality protein, nutrient related to construction and cell regeneration. This work aims the determination of natural radionuclides ( 234 U, 235 U, 238 U, 228 Th, 230 Th, 232 Th, 226 Ra, 228 Ra, and 210 Pb) in meat samples. Five groups of samples were analyzed, such as cattle meat (beef), fish, pork, poultry, and processed meat, after radiochemical separation followed by alpha or alpha beta spectrophotometry, and total count quantification. The determination of these radionuclides is very important because they are products of the natural decay series of 238 U and 232 Th, being easily found in meat samples. (author)

A mathematical model for predicting the probability of acute mortality in a human population exposed to accidentally released airborne radionuclides. Final report for Phase I of the project: early effects of inhaled radionuclides

International Nuclear Information System (INIS)

Filipy, R.E.; Borst, F.J.; Cross, F.T.; Park, J.F.; Moss, O.R.

1980-06-01

The report presents a mathematical model for the purpose of predicting the fraction of human population which would die within 1 year of an accidental exposure to airborne radionuclides. The model is based on data from laboratory experiments with rats, dogs and baboons, and from human epidemiological data. Doses from external, whole-body irradiation and from inhaled, alpha- and beta-emitting radionuclides are calculated for several organs. The probabilities of death from radiation pneumonitis and from bone marrow irradiation are predicted from doses accumulated within 30 days of exposure to the radioactive aerosol. The model is compared with existing similar models under hypothetical exposure conditions. Suggestions for further experiments with inhaled radionuclides are included

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

International Nuclear Information System (INIS)

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

1988-01-01

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

Performance analysis of numeric solutions applied to biokinetics of radionuclides; Analise de desempenho de solucoes numericas aplicadas a biocinetica de radionuclideos

Energy Technology Data Exchange (ETDEWEB)

Mingatos, Danielle dos Santos; Bevilacqua, Joyce da Silva, E-mail: dani@ime.usp.br, E-mail: joyce@ime.usp.br [Universidade de Sao Paulo (IME/USP), SP (Brazil). Instituto de Matematica e Estatistica; Todo, Alberto Saburo; Rodrigues Junior, Orlando, E-mail: astodo@ipen.br, E-mail: rodrijr@ipen.br [Instituto de Pesquisas Energeticas Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2013-07-01

Biokinetics models for radionuclides applied to dosimetry problems are constantly reviewed by ICRP. The radionuclide trajectory could be represented by compartmental models, assuming constant transfer rates between compartments. A better understanding of physiological or biochemical phenomena, improve the comprehension of radionuclide behavior in the human body and, in general, more complex compartmental models are proposed, increasing the difficulty of obtaining the analytical solution for the system of first order differential equations. Even with constant transfer rates numerical solutions must be carefully implemented because of almost singular characteristic of the matrix of coefficients. In this work we compare numerical methods with different strategies for ICRP-78 models for Thorium-228 and Uranium-234. The impact of uncertainty in the parameters of the equations is also estimated for local and global truncation errors. (author)

Kaolinite as an in situ dosimeter for past radionuclide migration at the Earth's surface

International Nuclear Information System (INIS)

Allard, T.; Muller, J.-P.

1998-01-01

The origin of 3 types of point defects (A-, Aminutes or feet- and B-centers) in kaolinite, due to natural irradiation and detected by electron paramagnetic resonance spectroscopy (EPR), has been demonstrated by artificial irradiation. The potential use of tracing the dynamics of the transfer of radionuclides through A-centers (i.e. the most stable centers) was qualitatively tested on different low-temperature alteration systems, some associated with U-concentrations. This paper proposes a quantitative approach to the reconstruction of the past migration of radionuclides by dosimetry of A-centers. With this aim in mind, the efficiency of α- and γ-radiations to produce A-centers was determined by experimental irradiation. Parameters extracted from A-center growth curves, together with their relationship with a parameter describing the degree of order of kaolinite, permitted (i) a definition to be made of the dose range in which a given kaolinite could be used as a dosimeter and (ii) the quantitative derivation of U-concentration from the cumulative dose (paleodose) of kaolinites. This was achieved by a formalism that accounted for the contribution of natural radiosources to the production of A-centers. The formalism was applied to the Nopal I U-deposit (Chihuhua, Mexico), considered as a natural analogue of a high level nuclear waste repository. Irrespective of the scenario considered, in terms of kaolinite age and of degree of isotopic disequilibrium in the system, A-center dosimetry permitted the determination of past occurrences of U which were several orders of magnitude higher than the present-day measured U-concentrations. Furthermore, this approach also provided evidence for several previous episodes of U-migration. EPR spectroscopy is thus a unique tool for the quantitative, indirect assessment of past radionuclide migration in the geosphere and kaolinite is a reliable in-situ dosimeter. (Copyright (c) 1998 Elsevier Science B.V., Amsterdam. All rights

Spermatogonial cell killing by radiolabeled methionine: a comparative study of the effects of Se-17, S-35, and H-3

International Nuclear Information System (INIS)

Rao, D.V.; Govelitz, G.F.; Sastry, K.S.R.; Howell, R.W.

1986-01-01

Spermatogenesis in the testes of mice offers an effective experimental model to investigate the biological effects and the dosimetry of Auger electron emitters in vivo, aspects that are not yet well understood. Killing of the radiosensitive spermatogonia by intratesticularly localized radionuclides is the biological effect of interest, manifesting as reduced sperm-head population four to six weeks after the initial administration of the radionuclides. The authors present here results of a comparative study of the effects of the Auger-emitter, 75 Se, and the beta-emitters, 35 S and 3 H, when these radionuclides are attached to methionine, and hence distributed similarly in the testis and in the cytoplasmic protein fractions of the spermatogonial cells. The sperm-head survival is assayed on the 36th day post-injection, when the sperm-head population reaches its minimum after the initial intratesticular administration of the radionuclides. In all the three cases, the survival fractions display similar dependence on the conventionally calculated average dose to the organ. These results show the adequacy of conventional dosimetry when 75 Se is localized in the cytoplasm of the cells, and emphasize the relative inefficiency of Auger electrons emitted from cytoplasmic decay sites in irradiating the radiosensitive DNA in the cells. 21 references, 4 figures, 4 tables

Biodistribution and dosimetry of {sup 123}I-mZIENT: a novel ligand for imaging serotonin transporters

Energy Technology Data Exchange (ETDEWEB)

Nicol, Alice [NHS Greater Glasgow and Clyde, Department of Nuclear Medicine, Southern General Hospital, Glasgow (United Kingdom); Krishnadas, Rajeev [University of Glasgow, Sackler Institute of Psychobiological Research, Glasgow (United Kingdom); Champion, Sue [University of Glasgow, Institute of Neuroscience and Psychology, College of Medical, Veterinary and Life Sciences, Glasgow (United Kingdom); Tamagnan, Gilles [Institute for Neurodegenerative Disorders, New Haven, CT (United States); Stehouwer, Jeffrey S.; Goodman, Mark M. [Emory University, Department of Radiology and Imaging Sciences, Atlanta, GA (United States); Hadley, Donald M. [NHS Greater Glasgow and Clyde, Department of Neuro-Radiology, Institute of Neurological Sciences, Glasgow (United Kingdom); Pimlott, Sally L. [NHS Greater Glasgow and Clyde, West of Scotland Radionuclide Dispensary, Glasgow (United Kingdom)

2012-05-15

{sup 123}I-labelled mZIENT (2{beta}-carbomethoxy-3{beta}-(3'-((Z)-2-iodoethenyl)phenyl)nortropane) has been developed as a radioligand for the serotonin transporter. The aim of this preliminary study was to assess its whole-body biodistribution in humans and estimate dosimetry. Three healthy controls and three patients receiving selective serotonin reuptake inhibitor (SSRI) therapy for depression were included (two men, four women, age range 41-56 years). Whole-body imaging, brain SPECT imaging and blood and urine sampling were performed. Whole-body images were analysed using regions of interest (ROIs), time-activity curves were derived using compartmental analysis and dosimetry estimated using OLINDA software. Brain ROI analysis was performed to obtain specific-to-nonspecific binding ratios in the midbrain, thalamus and striatum. Initial high uptake in the lungs decreased in later images. Lower uptake was seen in the brain, liver and intestines. Excretion was primarily through the urinary system. The effective dose was estimated to be of the order of 0.03 mSv/MBq. The organ receiving the highest absorbed dose was the lower large intestine wall. Uptake in the brain was consistent with the known SERT distribution with higher specific-to-nonspecific binding in the midbrain, thalamus and striatum in healthy controls compared with patients receiving SSRI therapy. {sup 123}I-mZIENT may be a promising radioligand for imaging the serotonin transporters in humans with acceptable dosimetry. (orig.)

Automated personal dosimetry monitoring system for NPP

International Nuclear Information System (INIS)

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

2006-01-01

personal dosimeters (albedo dosimeters). Operational and emergency monitoring of external radiation exposure: - Gamma radiation dose and dose rate measurement using direct reading personal dosimeters. - Gamma radiation dose measurement using radio-photoluminescent personal dosimeters. Monitoring of internal radiation exposure: - Measurement of activity of incorporated radionuclides using whole body counters. Hardware of A.P.D.M.S. represents a complex of automated workplaces based on industrial computers and measuring equipment; all workplaces are connected to one local computational network. Client software installed on automated workplaces processes the results of dosimetry monitoring (spectrum processing, computation of personal dose, report generation, etc.) and provides data exchange with data base of A.P.D.M.S. in the remote server. Communication with A.P.D.M.S. server is organized via the local computational network Ethernet. (authors)

Table of radionuclides (Vol.3 - Α = 3 to 244)

International Nuclear Information System (INIS)

Be, M.M.; Chiste, V.; Dulieu, Ch.; Browne, E.; Baglin, C.; Chechev, V.; Kuzmenko; Helmer, R.; Kondev, F.; MacMahon, T.D.; Lee, K.B.

2006-01-01

This monograph is one of several published in a series by the Bureau International des Poids et Mesures (BIPM) on behalf of the Comite Consultatif des Rayonnements Ionisants (CCRI), previously known as the Comite Consultatif pour les Etalons de Mesure des Rayonnements Ionisants (CCEMRI). The aim of this series of publications is to review topics that are of importance for the measurement of ionizing radiation and especially of radioactivity, in particular those techniques normally used by participants in international comparisons. It is hoped that these publications will prove to be useful reference volumes both for those who are already engaged in this field and for those who are approaching such measurements for the first time. The purpose of this monograph, number 5 in the series, is to present the recommended values of nuclear and decay data for a wide range of radionuclides. Activity measurements for more than forty of these radionuclides have already been the subject of comparisons under the auspices of Section II of the CCRI. The material for this monograph is now covered in three volumes. The first two volumes contain the primary recommended data relating to half-lives, decay modes, x-rays, gamma-rays, electron emissions; alpha- and beta-particle transitions and emissions, and their uncertainties for a set of sixty-eight radionuclides, Volume 1 for those radionuclides with mass number up to and including 150 and Volume 2 for those radionuclides with mass number over 150. Volume 3 contains the equivalent data for twenty-six additional radionuclides as listed and re-evaluation for 125 Sb and 153 Sm. The data have been collated and evaluated by an international working group (Decay Data Evaluation Project) led by the LNE-LNHB. The evaluators have agreed on the methodologies to be used and the CD-ROM included with this monograph contains the evaluators' comments for each radionuclide in addition to the data tables included in the monograph. The work involved in

Proceedings of the International Symposium Advances in alpha, Beta- and Gamma-Ray spectrometry

International Nuclear Information System (INIS)

1997-01-01

The International Committee for Radionuclide Metrology (ICRM) is an association of radionuclide metrology laboratories whose membership is composed of delegates of these laboratories together with other scientists actively engaged in the study and applications of radioactivity. The scientific activities are carried out in the frame of six Working Groups. Two of them, the Alpha-Particle Spectrometry and the Gamma-and Beta-ray Spectrometry Working Groups held a common workshop in Pushkin, St. Petersburg, 18 to 20 September 1996, under the title Advances in Alpha-Beta-and Gamma-Ray Sepectrometry, at the kind invitation of the D.I. Mendeleyev Institute for Metrology. More than 30 people from 14 laboratories attended the meeting, and nineteen oral communications were presented, from which twelve were retained for publication an are included in these proceedings. (Author)

Selected radionuclides. Tritium, carbon-14, krypton-85, strontium-90, iodine, caesium 137, radon, plutonium

International Nuclear Information System (INIS)

1983-01-01

The release of radioactive materials to the environment potentially exposes populations to ionizing radiation and increases the risk of incurring deleterious health effects. The associations of released amounts to effects establish the health criteria for radionuclides. This report provides background information in establishing such health criteria for 14 C, 85 Kr, 90 Sr, 137 Cs, Radon, Plutonium, Iodine and Tritium, including environmental behaviour, sources, transport to man and dosimetry. A brief summary of the general aspects of radiation effects and of radiation protection considerations is presented

The computation of ICRP dose coefficients for intakes of radionuclides with PLEIADES: biokinetic aspects.

Science.gov (United States)

Fell, T P

2007-01-01

The ICRP has published dose coefficients for the ingestion or inhalation of radionuclides in a series of reports covering intakes by workers and members of the public including children and pregnant or lactating women. The calculation of these coefficients conveniently divides into two distinct parts--the biokinetic and dosimetric. This paper gives a brief summary of the methods used to solve the biokinetic problem in the generation of dose coefficients on behalf of the ICRP, as implemented in the Health Protection Agency's internal dosimetry code PLEIADES.

The computation of ICRP dose coefficients for intakes of radionuclides with PLEIADES: biokinetic aspects

International Nuclear Information System (INIS)

Fell, T.P.

2007-01-01

The ICRP has published dose coefficients for the ingestion or inhalation of radionuclides in a series of reports covering intakes by workers and members of the public including children and pregnant or lactating women. The calculation of these coefficients conveniently divides into two distinct parts - the biokinetic and dosimetric. This paper gives a brief summary of the methods used to solve the biokinetic problem in the generation of dose coefficients on behalf of the ICRP, as implemented in the Health Protection Agency's internal dosimetry code PLEIADES. (author)

Beta dosimetry using pulsed laser heating of TLD materials

International Nuclear Information System (INIS)

Quam, W.

1983-01-01

Use of a pulsed CO 2 laser to heat the surface of hot-pressed LiF chips has been investigated. The thermoluminescent traps in the first 10 to 20 μm of depth may be read out with good efficiency, which will allow entrance dose and exit dose to be determined using a standard chip. These dose data can be used to calculate beta dose and gamma dose separately. Readout speed is estimated to be a few milliseconds per chip

Calculation of age-dependent dose conversion coefficients for radionuclides uniformly distributed in air

International Nuclear Information System (INIS)

Hung, Tran Van; Satoh, Daiki; Takahashi, Fumiaki; Tsuda, Shuichi; Endo, Akira; Saito, Kimiaki; Yamaguchi, Yasuhiro

2005-02-01

Age-dependent dose conversion coefficients for external exposure to photons emitted by radionuclides uniformly distributed in air were calculated. The size of the source region in the calculation was assumed to be effectively semi-infinite in extent. Firstly, organ doses were calculated with a series of age-specific MIRD-5 type phantoms using MCNP code, a Monte Carlo transport code. The calculations were performed for mono-energetic photon sources of twelve energies from 10 keV to 5 MeV and for phantoms of newborn, 1, 5, 10 and 15 years, and adult. Then, the effective doses to the different age-phantoms from the mono-energetic photon sources were estimated based on the obtained organ doses. The calculated effective doses were used to interpolate the conversion coefficients of the effective doses for 160 radionuclides, which are important for dose assessment of nuclear facilities. In the calculation, energies and intensities of emitted photons from radionuclides were taken from DECDC, a recent compilation of decay data for radiation dosimetry developed at JAERI. The results are tabulated in the form of effective dose per unit concentration and time (Sv per Bq s m -3 ). (author)

DB-1900 low-background measuring device of alpha and beta

International Nuclear Information System (INIS)

Liu Hongquan; Gan Jinbang; Chen Qi; Zhao Yunqing

1997-08-01

The device is a box-type detector used to measure the emissivity of Alpha and Beta from dry samples under 2π geometry in radionuclide metrology. It is composed of a high efficiency αβ detector with electrostatic screen of zero potential [patent ZL92111938.0 (in China)] and anticoincidence detector in lead chamber, and has been reasonably combined with double anticoincidence technique to form integral equipment. The characteristics of the device are as follows: It can stably measure the emissivity of Alpha and Beta from dry samples with less surface conductivity (the surface resistance of the samples: 13 Ω) in detector. It can measure Beta emissivity from samples in which Alpha coexist with Beta, and discrimination between Alpha and Beta emissivities can be made simultaneously by two paths. It is a good quantitative means for measuring Alpha and Beta radiation in radiometry, radiation protection and environmental protection. It could be used to measure weak radiativity of Alpha and Beta samples from scientific research, minerals, building materials, plastics, medicinal materials, seas and oceans biology, et al. (7 refs., 8 tabs., 17 figs.)

Application of nuclear analysis technique to determine radionuclide contents in critical food stuff

International Nuclear Information System (INIS)

Sri Murniasih; Sukirno; Agus Taftazani

2010-01-01

Rice, cassava, grist, corn and salt are Indonesian critical food stuff. The analysis of nature radionuclide in rice, cassava, grist, corn and salt measurements were carried out by gamma spectrometry with Germanium Lithium (GeLi) detector equipped by MESTROTM software and Multi Channel Analyzer (MCA) to analysis radionuclide and gamma gross. Analysis beta gross have been done using Low Background Counter (LBC) with Geiger Muller (GM) detector and Analog Digital Converter (ADC). Activity of K-40 on all samples range from 28.40 ± 2.06 to 4.22 ± 1.67 mBq/g; Th-232 range from 0.92 ± 0.57 to 6.63 ± 0.98 mBq/g; Pb-212 range from 0.38 ± 0.18 to 0.81 ± 0.10 mBq/g; Pb-214 range from 1.92 ± 1.28 - 5.17 ± 0.14 mBq/g. While beta gross and gamma gross activities range from 0.12 ± 0.09 to 0.31 ± 0.13 mBq/g and 101.73 ± 13.35 to 199.81 ± 9.21 mBq/g. Comparing with reference data from various countries, it can be concluded that radionuclide activity content in all of rice, cassava, grist, corn and salt samples doesn't difference significantly so that they are safe to be consumed. Using statistic test of ANOVA (α = 0.05) method, it found that the difference of sample has influence significant on the activity of TI-208, Pb-212, Pb-214 , gross beta and gamma gross radioactivity while on K-40 there is no significant influence on sample difference. (author)

Radioactivity, radionuclides, radiation

CERN Document Server

Magill, Joseph

2005-01-01

RADIOACTIVITY – RADIONUCLIDES – RADIATION is suitable for a general audience interested in topical environmental and human health radiological issues such as radiation exposure in aircraft, food sterilisation, nuclear medicine, radon gas, radiation dispersion devices ("dirty bombs")… It leads the interested reader through the three Rs of nuclear science, to the forefront of research and developments in the field. The book is also suitable for students and professionals in the related disciplines of nuclear and radiochemistry, health physics, environmental sciences, nuclear and astrophysics. Recent developments in the areas of exotic decay modes (bound beta decay of ‘bare’ or fully ionized nuclei), laser transmutation, nuclear forensics, radiation hormesis and the LNT hypothesis are covered. Atomic mass data for over 3000 nuclides from the most recent (2003) evaluation are included.

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)

Thermoluminescence albedo-neutron dosimetry

International Nuclear Information System (INIS)

Strand, T.; Storruste, A.

1986-10-01

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

Applications of gel dosimetry

International Nuclear Information System (INIS)

Ibbott, Geoffrey S

2004-01-01

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

Criteria for the selection of radionuclides for tumor radioimmunotherapy

Energy Technology Data Exchange (ETDEWEB)

Srivastava, S.C.; Mausner, L.F.; Mease, R.C.

1991-01-01

The potential of utilizing monoclonal antibodies as carriers of radionuclides for the selective destruction of tumors (radioimmunotherapy, RIT) has stimulated much research activity. From dosimetric and other considerations, the choice of radiolabel is an important factor that needs to be optimized for maximum effectiveness of RIT. This paper reviews and assesses a number of present and future radionuclides that are particularly suitable for RIT based on the various physical, chemical, and biological considerations. Intermediate to high-energy beta emitters' (with and without gamma photons in their emission) are emphasized since they possess a number of advantages over alpha and Auger emitters. Factors relating to the production and availability of candidate radiometals as well as their stable chemical attachment to monoclonal antibodies are discussed. 34 refs., 4 tabs.

Activity measurement of phosphorus-32 in the presence of pure beta-emitting impurities

CSIR Research Space (South Africa)

Simpson, B

2006-02-27

Full Text Available Activity measurements undertaken at the CSIR's National Metrology Laboratory (NML) on a solution of the pure beta-emitting radionuclide phosphorus-32, which formed part of an international key comparison, are described. Since exploratory source...

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

International Nuclear Information System (INIS)

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

1998-09-01

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

ZZ NUCDECAYCALC, Nuclear Decay Data for Radiation Dosimetry Calculation for ICRP

International Nuclear Information System (INIS)

2002-01-01

1 - Description or function: The Dosimetry Research Group (DRG) of the Health Sciences Research Division at ORNL has for several years maintained data bases of nuclear decay data for use in dosimetric calculations. The data on mean and unique energy plus intensity have been previously published, in abridged form, in Publication 38 of the International Commission on Radiological Protection (ICRP 1983). This data base was designed to address the needs in medical, environmental, and occupational radiation protection. DLC-172/NUCDECAY is required by the CCC-620/SEECAL program to calculate age-dependent specific effective energies. 2 - Methods: The unabridged data used in preparing ICRP Publication 38 are distributed in electronic form in this package. The collection consists of data on the energies and intensities of radiations emitted by the 825 radionuclides reported, although abridged, in ICRP Publication 38 plus an additional 13 radionuclides evaluated during preparation of a monograph for the Medical Internal Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine. Each collection is contained in an ASCII file (INDEXR.DAT) which is a sorted list of the radionuclides containing the decay chain information. The utility code DecayCalc extracts the decay data from the library for radionuclide(s) specified by the user. It computes the activities of radionuclides present after decay and ingrowth over a user-specified time period from 1 minute to 50 years. Decay data for any decay chain may be displayed and printed either in tabular form or graphically. DecayCalc, in a slightly modified version, will be a part of CCC-553/Rascal v3. DecayCalc is a Windows application that runs under Microsoft Windows 95 or 98, or Microsoft Windows NT 4.0 or later. The Compac Fortran 77 compiler was used to compile the code. The full source for DecayCalc is not provided but will be distributed when Rascal V3 is released

Measurement of radionuclides in the environment via Cherenkov radiation

International Nuclear Information System (INIS)

Ross, H.H.

1987-01-01

The author has developed an alternate approach to the measurement of some beta-emitting nuclides that utilizes the luminescence generated by the Cherenkov process. The luminescence, now known as Cherenkov radiation, was shown to be generated when a charged particle passes through a transparent medium at a speed that exceeds the phase velocity of light in the same medium. Cherenkov emission is different from most other luminescence processes in that it is a purely physical phenomenon. One consequence of this is that Cherenkov systems are free of chemical quenching effects. Conventional methods of analysis for environmental levels of beta-emitting radionuclides are often tedious, time-consuming, and expensive. The Cherenkov method is fast, requires very little operator attention, and is much less expensive to perform

Distribution of natural and artificial radionuclides in chernozem soil/crop system from stationary experiments.

Science.gov (United States)

Sarap, Nataša B; Rajačić, Milica M; Đalović, Ivica G; Šeremešić, Srđan I; Đorđević, Aleksandar R; Janković, Marija M; Daković, Marko Z

2016-09-01

The present paper focuses on the determination of radiological characteristics of cultivated chernozem soil and crops from long-term field experiments, taking into account the importance of distribution and transfer of radionuclides in the soil-plant system, especially in agricultural cropland. The investigation was performed on the experimental fields where maize, winter wheat, and rapeseed were cultivated. Analysis of radioactivity included determination of the gross alpha and beta activity as a screening method, as well as the activities of the following radionuclides: natural ((210)Pb, (235)U, (238)U, (226)Ra, (232)Th, (40)K, (7)Be) and artificial ((90)Sr and (137)Cs). The activities of natural and artificial ((137)Cs) radionuclides were determined by gamma spectrometry, while the artificial radionuclide (90)Sr was determined by a radiochemical analytical method. Based on the obtained results for the specific activity of (40)K, (137)Cs, and (90)Sr, accumulation factors for these radionuclides were calculated in order to estimate transfer of radionuclides from soil to crops. The results of performed analyses showed that there is no increase of radioactivity that could endanger the food production through the grown crops.

Study on natural radionuclide activities in meat samples consumed in Sao Paulo City, Brazil

Energy Technology Data Exchange (ETDEWEB)

Rosa, Mychelle M.L.; Taddei, Maria HelenaT. [Comissao Nacional de Energia Nuclear (LAPOC/CNEN), Pocos de Caldas, MG (Brazil). Laboratorio de Pocos de Caldas; Avegliano, Roseane P.; Maihara, Vera A., E-mail: mychelle@cnen.gov.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

Consumption of food is usually the most important route by which natural and artificial radionuclides can enter the human body. An assessment of radionuclide levels in different foods and diets is therefore important to estimate the intake of these radionuclides by man. The contamination by radionuclides can occur via the food chain (soil, root, plant and animal), with emphasis to the long half-life radionuclides, which can also have their transfer through the animal meat. The inclusion of meat in human nutrition is important because it is an excellent source of high quality protein, nutrient related to construction and cell regeneration. This work aims the determination of natural radionuclides ({sup 234}U, {sup 235}U, {sup 238}U, {sup 228}Th, {sup 230}Th, {sup 232}Th, {sup 226}Ra, {sup 228}Ra, and {sup 210}Pb) in meat samples. Five groups of samples were analyzed, such as cattle meat (beef), fish, pork, poultry, and processed meat, after radiochemical separation followed by alpha or alpha beta spectrophotometry, and total count quantification. The determination of these radionuclides is very important because they are products of the natural decay series of {sup 238}U and {sup 232}Th, being easily found in meat samples. (author)

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-06-15

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

On systematic and statistic errors in radionuclide mass activity estimation procedure

International Nuclear Information System (INIS)

Smelcerovic, M.; Djuric, G.; Popovic, D.

1989-01-01

One of the most important requirements during nuclear accidents is the fast estimation of the mass activity of the radionuclides that suddenly and without control reach the environment. The paper points to systematic errors in the procedures of sampling, sample preparation and measurement itself, that in high degree contribute to total mass activity evaluation error. Statistic errors in gamma spectrometry as well as in total mass alpha and beta activity evaluation are also discussed. Beside, some of the possible sources of errors in the partial mass activity evaluation for some of the radionuclides are presented. The contribution of the errors in the total mass activity evaluation error is estimated and procedures that could possibly reduce it are discussed (author)

Practice for use of a dichromate dosimetry system

International Nuclear Information System (INIS)

2003-01-01

This practice covers the preparation, testing, and procedure for using the acidic aqueous silver dichromate dosimetry system to measure absorbed dose in water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the dichromate system. It is classified as a reference standard dosimetry system (see ISO/ASTM Guide 51261). This practice describes the spectrophotometric analysis procedures for the dichromate system. This practice applies only to γ-rays, x-rays/ bremsstrahlung, and high energy electrons. This practice applies provided the following conditions are satisfied: the absorbed dose range is from 2x10 3 to 5x10 4 Gy; the absorbed dose rate does not exceed 600 Gy/pulse (12.5 pulses per second), or does not exceed an equivalent dose rate of 7.5 kGy/s from continuous sources; for radionuclide gamma-ray sources, the initial photon energy shall be greater than 0.6 MeV. For bremsstrahlung photons, the initial energy of the electrons used to produce the bremsstrahlung photons shall be equal to or greater than 2 MeV. For electron beams, the initial electron energy shall be greater than 8 MeV; the irradiation temperature of the dosimeter shall be above 0 deg C and should be below 80 deg C

Development of Calculation Module for Intake Retention Functions based on Occupational Intakes of Radionuclides

Energy Technology Data Exchange (ETDEWEB)

Noh, Siwan; Kwon, Tae-Eun; Lee, Jai-Ki [Hanyang Univ., Seoul (Korea, Republic of); Lee, Jong-Il; Kim, Jang-Lyul [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-10-15

In internal dosimetry, intake retention and excretion functions are essential to estimate intake activity using bioassay sample such as whole body counter, lung counter, and urine sample. Even though ICRP (International Commission on Radiological Protection)provides the functions in some ICRP publications, it is needed to calculate the functions because the functions from the publications are provided for very limited time. Thus, some computer program are generally used to calculate intake retention and excretion functions and estimate intake activity. OIR (Occupational Intakes of Radionuclides) will be published soon by ICRP, which totally replaces existing internal dosimetry models and relevant data including intake retention and excretion functions. Thus, the calculation tool for the functions is needed based on OIR. In this study, we developed calculation module for intake retention and excretion functions based on OIR using C++ programming language with Intel Math Kernel Library. In this study, we developed the intake retention and excretion function calculation module based on OIR using C++ programing language.

Development of Calculation Module for Intake Retention Functions based on Occupational Intakes of Radionuclides

International Nuclear Information System (INIS)

Noh, Siwan; Kwon, Tae-Eun; Lee, Jai-Ki; Lee, Jong-Il; Kim, Jang-Lyul

2014-01-01

In internal dosimetry, intake retention and excretion functions are essential to estimate intake activity using bioassay sample such as whole body counter, lung counter, and urine sample. Even though ICRP (International Commission on Radiological Protection)provides the functions in some ICRP publications, it is needed to calculate the functions because the functions from the publications are provided for very limited time. Thus, some computer program are generally used to calculate intake retention and excretion functions and estimate intake activity. OIR (Occupational Intakes of Radionuclides) will be published soon by ICRP, which totally replaces existing internal dosimetry models and relevant data including intake retention and excretion functions. Thus, the calculation tool for the functions is needed based on OIR. In this study, we developed calculation module for intake retention and excretion functions based on OIR using C++ programming language with Intel Math Kernel Library. In this study, we developed the intake retention and excretion function calculation module based on OIR using C++ programing language

Comparative studies on the transfer of radionuclides to the fetus in the rat - implications for human dosimetry

International Nuclear Information System (INIS)

Stather, J.W.; Adams, N.; Gray, S.A.; Rees, M.

1987-01-01

This paper describes a series of studies in which the transfer of isotopes of Cs, Sr, Ru, Ce and Am to newborn rats has been measured following their administration to the mother either before or during gestation. The results have shown that transfer to the fetus depends not only on the radionuclide administered but also on the time of administration relative to the onset of pregnancy. They have also demonstrated that average concentrations of radionuclides in the newborn infant and mother can vary by more than two orders of magnitude. Of the radionuclides studied 85 Sr and 137 Cs were the most effectively translocated to the fetus when administered towards the end of gestation, and 141 Ce and 241 Am the least. Thus following administration on the 14th day of pregnancy the relative concentrations of 85 Sr and 241 Am in the newborn rat and mother at birth were respectively 0.21 and 0.004, and on the 19th day 5.3 and 0.02. The development of a dosimetric model for 241 Am is also described. 23 refs.; 3 tabs

Development of a calibration protocol for quantitative imaging for molecular radiotherapy dosimetry

International Nuclear Information System (INIS)

Wevrett, J.; Fenwick, A.; Scuffham, J.; Nisbet, A.

2017-01-01

Within the field of molecular radiotherapy, there is a significant need for standardisation in dosimetry, in both quantitative imaging and dosimetry calculations. Currently, there are a wide range of techniques used by different clinical centres and as a result there is no means to compare patient doses between centres. To help address this need, a 3 year project was funded by the European Metrology Research Programme, and a number of clinical centres were involved in the project. One of the required outcomes of the project was to develop a calibration protocol for three dimensional quantitative imaging of volumes of interest. Two radionuclides were selected as being of particular interest: iodine-131 ( 131 I, used to treat thyroid disorders) and lutetium-177 ( 177 Lu, used to treat neuroendocrine tumours). A small volume of activity within a scatter medium (water), representing a lesion within a patient body, was chosen as the calibration method. To ensure ease of use in clinical centres, an “off-the-shelf” solution was proposed – to avoid the need for in-house manufacturing. The BIODEX elliptical Jaszczak phantom and 16 ml fillable sphere were selected. The protocol was developed for use on SPECT/CT gamma cameras only, where the CT dataset would be used to correct the imaging data for attenuation of the emitted photons within the phantom. The protocol corrects for scatter of emitted photons using the triple energy window correction technique utilised by most clinical systems. A number of clinical systems were tested in the development of this protocol, covering the major manufacturers of gamma camera generally used in Europe. Initial imaging was performed with 131 I and 177 Lu at a number of clinical centres, but due to time constraints in the project, some acquisitions were performed with 177 Lu only. The protocol is relatively simplistic, and does not account for the effects of dead-time in high activity patients, the presence of background activity

WE-H-207A-07: Image-Based Versus Atlas-Based Internal Dosimetry

Energy Technology Data Exchange (ETDEWEB)

Fallahpoor, M; Abbasi, M [Vali-Asr Hospital, School of Medicine, Tehran University of Medical Science, Tehran, Tehran (Iran, Islamic Republic of); Parach, A [Shahid Sadoughi University of Medical Sciences, Yazd, Yazd (Iran, Islamic Republic of); Kalantari, F [UT Southwestern Medical Center, Dallas, TX (United States)

2016-06-15

Purpose: Monte Carlo (MC) simulation is known as the gold standard method for internal dosimetry. It requires radionuclide distribution from PET or SPECT and body structure from CT for accurate dose calculation. The manual or semi-automatic segmentation of organs from CT images is a major obstacle. The aim of this study is to compare the dosimetry results based on patient’s own CT and a digital humanoid phantom as an atlas with pre-specified organs. Methods: SPECT-CT images of a 50 year old woman who underwent bone pain palliation with Samarium-153 EDTMP for osseous metastases from breast cancer were used. The anatomical date and attenuation map were extracted from SPECT/CT and three XCAT digital phantoms with different BMIs (i.e. matched (38.8) and unmatched (35.5 and 36.7) with patient’s BMI that was 38.3). Segmentation of patient’s organs in CT image was performed using itk-SNAP software. GATE MC Simulator was used for dose calculation. Specific absorbed fractions (SAFs) and S-values were calculated for the segmented organs. Results: The differences between SAFs and S-values are high using different anatomical data and range from −13% to 39% for SAF values and −109% to 79% for S-values in different organs. In the spine, the clinically important target organ for Samarium Therapy, the differences in the S-values and SAF values are higher between XCAT phantom and CT when the phantom with identical BMI is employed (53.8% relative difference in S-value and 26.8% difference in SAF). However, the whole body dose values were the same between the calculations based on the CT and XCAT with different BMIs. Conclusion: The results indicated that atlas-based dosimetry using XCAT phantom even with matched BMI for patient leads to considerable errors as compared to image-based dosimetry that uses the patient’s own CT Patient-specific dosimetry using CT image is essential for accurate results.

Internal exposure to neutron-activated {sup 56}Mn dioxide powder in Wistar rats. Pt. 1. Dosimetry

Energy Technology Data Exchange (ETDEWEB)

Stepanenko, Valeriy; Kaprin, Andrey; Galkin, Vsevolod; Ivanov, Sergey; Kolyzhenkov, Timofey; Petukhov, Aleksey; Yaskova, Elena; Belukha, Irina; Khailov, Artem; Skvortsov, Valeriy; Ivannikov, Alexander; Akhmedova, Umukusum; Bogacheva, Viktoria [Medical Radiological Research Center (MRRC) named after A.F. Tsyb - National Medical Research Radiological Center of the Health Ministry of the Russian Federation, Obninsk, Kaluga Region (Russian Federation); Rakhypbekov, Tolebay; Dyussupov, Altay; Chaizhunusova, Nailya; Sayakenov, Nurlan; Uzbekov, Darkhan; Saimova, Aisulu; Shabdarbaeva, Dariya; Kairkhanova, Yankar [Semey State Medical University, Semey (Kazakhstan); Otani, Keiko; Endo, Satoru; Satoh, Kenichi; Kawano, Noriyuki; Fujimoto, Nariaki; Hoshi, Masaharu [Hiroshima University, Hiroshima (Japan); Shichijo, Kazuko; Nakashima, Masahiro; Takatsuji, Toshihiro [Nagasaki University, Nagasaki (Japan); Sakaguchi, Aya; Kato, Hiroaki; Onda, Yuichi [University of Tsukuba, Ibaraki (Japan); Toyoda, Shin [Okayama University of Science, Okayama (Japan); Sato, Hitoshi [Ibaraki Prefectural University of Health Science, Ibaraki (Japan); Skakov, Mazhin; Vurim, Alexandr; Gnyrya, Vyacheslav; Azimkhanov, Almas; Kolbayenkov, Alexander [National Nuclear Center of the Republic of Kazakhstan, Kurchatov (Kazakhstan); Zhumadilov, Kasym [Eurasian National University named after L.N. Gumilyov, Astana (Kazakhstan)

2017-03-15

There were two sources of ionizing irradiation after the atomic bombings of Hiroshima and Nagasaki: (1) initial gamma-neutron irradiation at the moment of detonation and (2) residual radioactivity. Residual radioactivity consisted of two components: radioactive fallout containing fission products, including radioactive fissile materials from nuclear device, and neutron-activated radioisotopes from materials on the ground. The dosimetry systems DS86 and DS02 were mainly devoted to the assessment of initial radiation exposure to neutrons and gamma rays, while only brief considerations were given for the estimation of doses caused by residual radiation exposure. Currently, estimation of internal exposure of atomic bomb survivors due to dispersed radioactivity and neutron-activated radioisotopes from materials on the ground is a matter of some interest, in Japan. The main neutron-activated radionuclides in soil dust were {sup 24}Na, {sup 28}Al, {sup 31}Si, {sup 32}P, {sup 38}Cl, {sup 42}K, {sup 45}Ca, {sup 46}Sc, {sup 56}Mn, {sup 59}Fe, {sup 60}Co, and {sup 134}Cs. The radionuclide {sup 56}Mn (T{sub 1/2} = 2.58 h) is known as one of the dominant beta- and gamma emitters during the first few hours after neutron irradiation of soil and other materials on ground, dispersed in the form of dust after a nuclear explosion in the atmosphere. To investigate the peculiarities of biological effects of internal exposure to {sup 56}Mn in comparison with external gamma irradiation, a dedicated experiment with Wistar rats exposed to neutron-activated {sup 56}Mn dioxide powder was performed recently by Shichijo and coworkers. The dosimetry required for this experiment is described here. Assessment of internal radiation doses was performed on the basis of measured {sup 56}Mn activity in the organs and tissues of the rats and of absorbed fractions of internal exposure to photons and electrons calculated with the MCNP-4C Monte Carlo using a mathematical rat phantom. The first results of

Proceedings of 5. French speaking scientific days on calculation codes for radioprotection, radio-physics and dosimetry

International Nuclear Information System (INIS)

Simon-Cornu, Marie; Mourlon, Christophe; Bordy, J.M.; Daures, J.; Dusiac, D.; Moignau, F.; Gouriou, J.; Million, M.; Moreno, B.; Chabert, I.; Lazaro, D.; Barat, E.; Dautremer, T.; Montagu, T.; Agelou, M.; De Carlan, L.; Patin, D.; Le Loirec, C.; Dupuis, P.; Gassa, F.; Guerin, L.; Batalla, A.; Leni, Pierre-Emmanuel; Laurent, Remy; Gschwind, Regine; Makovicka, Libor; Henriet, Julien; Salomon, Michel; Vivier, Alain; Lopez, Gerald; Dossat, C.; Pourrouquet, P.; Thomas, J.C.; Sarie, I.; Peyrard, P.F.; Chatry, N.; Lavielle, D.; Loze, R.; Brun, E.; Damian, F.; Diop, C.; Dumonteil, E.; Hugot, F.X.; Jouanne, C.; Lee, Y.K.; Malvagi, F.; Mazzolo, A.; Petit, O.; Trama, J.C.; Visonneau, T.; Zoia, A.; Courageot, Estelle; Gaillard-Lecanu, Emmanuelle; Kutschera, Reinald; Le Meur, Gaelle; Uzio, Fabien; De Conto, Celine; Gschwind, Regine; Makovicka, Libor; Farah, Jad; Martinetti, Florent; Sayah, Rima; Donadille, Laurent; Herault, Joel; Delacroix, Sabine; Nauraye, Catherine; Lee, Choonsik; Bolch, Wesley; Clairand, Isabelle; Horodynski, Jean-Michel; Pauwels, Nicolas; Robert, Pierre; VOLLAIRE, Joachim; Nicoletti, C.; Kitsos, S.; Tardy, M.; Marchaud, G.; Stankovskiy, Alexey; Van Den Eynde, Gert; Fiorito, Luca; Malambu, Edouard; Dreuil, Serge; Mougeot, X.; Be, M.M.; Bisch, C.; Villagrasa, C.; Dos Santos, M.; Clairand, I.; Karamitros, M.; Incerti, S.; Petitguillaume, Alice; Franck, Didier; Desbree, Aurelie; Bernardini, Michela; Labriolle-Vaylet, Claire de; Gnesin, Silvano; Leadermann, Jean-Pascal; Paterne, Loic; Bochud, Francois O.; Verdun, Francis R.; Baechler, Sebastien; Prior, John O.; Thomassin, Alain; Arial, Emmanuelle; Laget, Michael; Masse, Veronique; Saldarriaga Vargas, Clarita; Struelens, Lara; Vanhavere, Filip; Perier, Aurelien; Courageot, Estelle; Gaillard-Lecanu, Emmanuelle; Le-Meur, Gaelle; Monier, Catherine; Thers, Dominique; Le-Guen, Bernard; Blond, Serge; Cordier, Gerard; Le Roy, Maiwenn; De Carlan, Loic; Bordy, Jean-Marc; Caccia, Barbara; Andenna, Claudio; Charimadurai, Arun; Selvam, T Palani; Czarnecki, Damian; Zink, Klemens; Gschwind, Regine; Martin, Eric; Huot, Nicolas; Zoubair, Mariam; El Bardouni, Tarek; Lazaro, Delphine; Barat, Eric; Dautremer, Thomas; Montagu, Thierry; Chabert, Isabelle; Guerin, Lucie; Batalla, Alain; Moignier, C.; Huet, C.; Bassinet, C.; Baumann, M.; Barraux, V.; Sebe-Mercier, K.; Loiseau, C.; Batalla, A.; Makovicka, L.; Desnoyers, Yvon; Juhel, Gabriel; Mattera, Christophe; Tempier, Maryline

2014-03-01

These scientific days were organised by the 'technical protection' Section of the French Society of Radiation Protection (SFRP) in cooperation with the French society of medical physicists (SFPM), the Swiss Romandie association of radioprotection (ARRAD) and the associated laboratories of radio-physics and dosimetry (LARD). The objective of these days was to review the existing calculation codes used in radiation transport, source estimation and dose management, and to identify some future prospects. This document brings together the available presentations (slides) together with their corresponding abstracts (in French) and dealing with: 1 - Presentation of the conference days (L. De Carlan); 2 - Simulating radionuclide transfers in the environment: what calculation codes and for what? (C. Mourlon); 3 - Contribution of Monte-Carlo calculation to the theoretical foundation analysis of calibration procedures and dosemeters design for radioprotection photon dosimetry (J.M. Bordy); 4 - Use of calculation codes in R and D for the development of a new passive dosemeter for photons and beta radiations (B. Moreno); 5 - Development of a new virtual sources model for the Monte-Carlo prediction of EPID (Electronic Portal Imaging Device) images and implementation in PENELOPE (I. Chabert); 6 - Prediction of high-resolution EPID images for in-vivo dosimetry (D. Patin); 7 - 4D thorax modeling by artificial neural networks (P.E. Leni); 8 - Presentation of the calculation utilities of the book 'Calculation of ionizing radiations generated doses' (Vivier, Lopez, EDP Sciences 2012) (A. Vivier); 9 - RayXpert C : a 3D modeling and Monte-Carlo dose rate calculation software (C. Dossat); 10 - TRIPOLI-4 R Version 9 S Monte-Carlo code for radioprotection (F. Damian); 11 - Realistic radioprotection training with the digital school workshop (E. Courageot); 12 - Use of BEAMNRC code for dental prostheses influence evaluation in ENT cancers treatment by external radiotherapy (C. De Conto); 13

Dosimetry Service

CERN Multimedia

2005-01-01

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

Gamma dosimetry of the uranium deposit in Sao Jose de Espinharas, Paraiba, Brazil

International Nuclear Information System (INIS)

Silva, Alberto Antonio da; Santos Junior, Jose Araujo dos; Cunha, Andre Felippe Vieira da; Amaral, Romilton dos Santos; Oliveira, Iane Andrade de; Bezerra, Jairo Dias; Silva, Flavio Ferreira da

2013-01-01

Radioecology studies contribute to the monitoring of both anthropic and natural radionuclides, as well as their correlation with the ecosystem and the population. Terrestrial sources, which mainly include the primary radionuclides of the 238 U, 232 Th, and 40 K series, contribute to a higher effective dose received by humanity, with 84% from terrestrial radionuclides and another 16% derived from cosmogenic nuclides. Areas with high levels of natural radiation, above the acceptable limits, are of great relevance for the development of dosimetry studies, whose core aims include the preservation of the environment and the control of the population's exposure to radiation. The town of Sao Jose de Espinharas, Paraiba, Brazil, has a uranium oxide mine with an average grade of 1,200 mg/kg. In the present study, non-destructive, in situ assays were performed along the entire radiometrically anomalous area. The results obtained in terms of effective doses varied from 3.79 to 93.80 mSv.y -1 , with an average of 19.47 mSv.y -1 thus leading to the conclusion that all of the monitored points presented environmental doses of above the reference value of 2.4 mSv.y -1 , suggesting that both qualitative and quantitative analyses concerning the environmental matrixes in question need to be performed. (author)

Medical necessity for shorter lived radionuclides, specifically pure Iodine-123

International Nuclear Information System (INIS)

DeNardo, G.L.; DeNardo, S.J.; Hines, H.H.; Lagunas-Solar, M.C.; Jungerman, J.A.

1985-01-01

Iodine-123 has physical and radiochemical characteristics ideal for most tracer procedures performed in patients. Its use is generally preferable to the use of 131 I for diagnosis. The potential for 123 I can be realized only if a radiopharmaceutical of lesser radionuclide contamination is generally and economically available. Iodine-123 produced by direct methods has significant disadvantages relative to quality of procedure and radiation dosimetry. Our experience with 123 I(p,5n) during the past 12 years causes us to vigorously encourage general availability of an 123 I radiopharmaceutical of this quality. Using this product, the authors have prepared radiopharmaceuticals for use in the study of cancer, coagulation, and renal and thyroid diseases

Thermoluminescence in medical dosimetry

International Nuclear Information System (INIS)

Rivera, T.

2011-10-01

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

A review of measurement and characterisation of airborne long-lived alpha-emitting radionuclides

International Nuclear Information System (INIS)

Bigu, J.

1993-01-01

Sampling principles, monitoring instrumentation and characterisation of Long-Lived Radioactive Dust (LLRD) generated in U-Th mine and mill operations are discussed. Methods and techniques for the quantification, radionuclide identification and the study of other important characteristics of LLRD (e.g., electrical charge) are reviewed. Furthermore, field and laboratory measurements and methods of radiation dose assessment are revised. Some emphasis is placed in this work on occupational worker exposure assessment and the principles, methods and techniques of 'external' radiation exposure, internal dosimetry, and dosimetric models. It is clear that in spite of constant advances in the several areas which are the subject of this paper, there is still considerable room for improvement. For example, there is no universally accepted sampling protocol and sampler for routine LLRD monitoring for occupational hygiene exposure calculation purposes. Other areas for improvement could include calibration of instrumentation and improved sensitivity in radionuclide quantification and identification. 105 refs., 6 tabs., 3 figs

Present and future activities of the IAEA on internal dosimetry: Lessons learned from international intercomparisons

International Nuclear Information System (INIS)

Cruz Suarez, R.; Gustafsson, M.; Mrabit, K.

2003-01-01

The International Atomic Energy Agency (IAEA) conducts safety activities to support the assessment of occupational exposure due to intakes of radionuclides; a comprehensive set of safety documents will soon be completed. In recent years, extensive improvements in measurement techniques, phantoms and computational tools have been made. Thus, it is important for laboratories involved in internal dosimetry to undergo performance testing procedures to demonstrate the correctness of the methods applied and also to determine the consistency of their results with those obtained by other laboratories. Several intercomparisons were organised, and they revealed significant differences among laboratories in their approaches, methods and assumptions, and consequently in their results. This paper presents the current and future IAEA activities in support of assessment of occupational exposure due to intakes of radionuclides in the IAEA Member States, as well as the lessons learned from several intercomparison exercises in the last 5 years. (author)

Review of personal monitoring techniques for the measurement of absorbed dose from external beta and low energy photon radiation

DEFF Research Database (Denmark)

Christensen, Poul

1986-01-01

The techniques available at present for personal monitoring of doses from external beta and low energy photon radiation are reviewed. The performance of currently used dosimetry systems is compared with that recommended internationally, and developments for improving the actual performance...

An application of in vivo whole body counting technique for studying strontium metabolism and internal dose reconstruction for the Techa River population

Science.gov (United States)

Shagina, N. B.; Bougrov, N. G.; Degteva, M. O.; Kozheurov, V. P.; Tolstykh, E. I.

2006-05-01

Nuclear techniques for direct assessment of internally deposited radionuclides are essential for monitoring and dosimetry of members of the public exposed due to radiation accidents. Selection of the methods for detection of internal contamination is determined by nuclear-physical characteristics of the deposits. For the population living in settlements located along the Techa River contaminated in 1950s by liquid radioactive wastes from the plutonium production complex Mayak (Southern Urals, Russia) the main dose-forming radionuclide was 90Sr. It is a bone-seeking radionuclide that incorporates in the skeleton and remains there for many years so it can be detected for long periods after the intake occurred. Measurements of pure beta-emitting 90Sr are possible through detection of bremsstrahlung from the 90Sr/90Y beta rays in the low energy range (30-160 keV) using phoswich detectors. This suggested the development of a unique whole body counter in 1974 for monitoring of the 90Sr- and 137Cs-body burden in the Techa River population with the use of phoswich detectors. Long-term observations with the WBC covering more than 38,000 measurements on over 20,000 people have been made. This has created a unique database for studying strontium and calcium metabolism and for assessment of the internal dose for residents of the Techa River settlements due to ingestion of 90Sr. This paper describes the main results obtained for the Techa River population essential for bone metabolism and dosimetry, epidemiological studies, and radiation protection.

Neutron dosimetry - A review

Energy Technology Data Exchange (ETDEWEB)

Baum, J W

1955-03-29

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

JENDL Dosimetry File

International Nuclear Information System (INIS)

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

1992-03-01

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

JENDL Dosimetry File

Energy Technology Data Exchange (ETDEWEB)

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

1992-03-15

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

Dosimetry Service

CERN Multimedia

2005-01-01

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

Dosimetry Service

CERN Multimedia

Dosimetry Service

2005-01-01

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

Use of dual-head gamma camera in radionuclide internal contamination monitoring on radiation workers from a nuclear medicine department

International Nuclear Information System (INIS)

Rodriguez-Laguna, A.; Brandan, M.E.

2008-01-01

As a part of an internal dosimetry program that is performed at the Mexican National Institute of Cancerology - Nuclear Medicine Department, in the present work we suggest a procedure for the routinely monitoring of internal contamination on radiation workers and nuclear medicine staff. The procedure is based on the identification and quantification of contaminating radionuclides in human body by using a dual-head whole-body gamma camera. The results have shown that the procedures described in this study can be used to implement a method to quantify minimal accumulated activity in the main human organs to evaluate internal contamination with radionuclides. The high sensitivity of the uncollimated gamma camera is advantageous for the routinely detection and identification of small activities of internal contamination. But, the null spatial resolution makes impossible the definition of contaminated region of interest. Then, the use of collimators is necessary to the quantification of incorporated radionuclides activities in the main human organs and for the internal doses assessment. (author)

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...

Dosimetric characterization of BeO samples in alpha, beta and X radiation beams using luminescent techniques

International Nuclear Information System (INIS)

Groppo, Daniela Piai

2013-01-01

In the medical field, the ionizing radiation is used both for therapeutic and diagnostic purposes, in a wide range of radiation doses. In order to ensure that the objective is achieved in practice, detailed studies of detectors and devices in different types of radiations beams are necessary. In this work a dosimetric characterization of BeO samples was performed using the techniques of thermoluminescence (TL) and optically stimulated luminescence (OSL) by a comparison of their response for alpha, beta and X radiations and the establishment of an appropriated system for use in monitoring of these radiations beams. The main results are: the high sensitivity to beta radiation for both techniques, good reproducibility of TL and OSL response (coefficients of variation lower than 5%), maximum energy dependence of the X radiation of 28% for the TL technique, and only 7% for the OSL technique, within the studied energy range. The dosimetric characteristics obtained in this work show the possibility of applying BeO samples to dosimetry of alpha, beta and X radiations, considering the studied dose ranges, using the TL and OSL techniques. From the results obtained, the samples of BeO showed their potential use for beam dosimetry in diagnostic radiology and radiotherapy. (author)

Assessment of gamma, beta and alpha-particle-emitting nuclides in marine samples

International Nuclear Information System (INIS)

Holm, E.

1997-01-01

Depending on the physical properties of radionuclides different systems must be used for their measurement. Most convenient is if gamma spectrometry can be used by germanium, Silicon or Scintillation detectors (eg. NaI). If, however, the main emission consists of beta or alpha particles or low-energy photons as is the case for radionuclides decaying by electron capture, radiochemical separation and specific source preparations must be undertaken. In such cases also the radiochemical yield must be determined. The radiochemical part mainly follows the lines presented by prof. T. Jaakkola, Department of Radiochemistry, Helsinki, Finland, at a course in radioecology in Lurid, 1991. For very long-lived radionuclides other methods such as mass spectrometry are superior although often associated with sophisticated expensive instrumentation. (author)

[{sup 18}F]{beta}-CIT-FP is superior to [{sup 11}C]{beta}-CIT-FP for quantitation of the dopamine transporter

Energy Technology Data Exchange (ETDEWEB)

Lundkvist, Camilla; Halldin, Christer; Ginovart, Nathalie; Swahn, Carl-Gunnar; Farde, Lars

1997-10-01

{beta}-CIT-FP [N-(3-fluoropropyl)-2{beta}-carbomethoxy-3{beta}-(4-iodophenyl)nortropane] is a cocaine analogue with high affinity for the dopamine transporter. Positron emission tomography (PET) studies with [O-methyl-{sup 11}C]{beta}-CIT-FP ([{sup 11}C]{beta}-CIT-FP) has shown that equilibrium conditions were approached but, however, not reached at the end of measurement. Moreover, metabolite studies of [{sup 11}C]{beta}-CIT-FP in monkey plasma demonstrated a lipophilic-labelled metabolite that may enter the brain. We therefore labelled {beta}-CIT-FP with fluorine-18 in a position that may avoid the formation of labelled lipophilic metabolites. The more long-lived radionuclide ({sup 18}F) was used to allow for measurements over longer time. [N-fluoropropyl-{sup 18}F]{beta}-CIT-FP ([{sup 18}F]{beta}-CIT-FP) was prepared by N-alkylation of nor-{beta}-CIT with [{sup 18}F]fluoropropyl bromide. PET studies were performed in cynomolgus monkeys. [{sup 18}F]{beta}-CIT-FP entered the brain rapidly. There was a high concentration of radioactivity in the striatum and much lower in the thalamus, neocortex, and cerebellum. The striatum-to-cerebellum ratio was about 5 at time of transient equilibrium, which occurred after 60 to 100 min. After pretreatment with GBR 12909, radioactivity in the striatum was markedly reduced, thus indicating specific [{sup 18}F]{beta}-CIT-FP binding to the dopamine transporter. The fraction of unchanged [{sup 18}F]{beta}-CIT-FP determined by HPLC was 10-15% after 140 min. No lipophilic labelled metabolites were detected. The absence of measurable lipophilic labelled metabolites and the occurrence of transient equilibrium within the time of the PET measurement indicate that [{sup 18}F]{beta}-CIT-FP is superior to [{sup 11}C]{beta}-CIT-FP as a PET radioligand for quantification of the dopamine transporter in the human brain.

Alanine dosimetry for clinical applications. Proceedings

International Nuclear Information System (INIS)

Anton, M.

2006-05-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-07-01

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

Textbook of dosimetry. 4. ed.

International Nuclear Information System (INIS)

Ivanov, V.I.

1999-01-01

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

Practice for use of a ceric-cerous sulfate dosimetry system

International Nuclear Information System (INIS)

2002-01-01

This practice covers the preparation, testing, and procedure for using the ceric-cerous sulfate dosimetry system to measure absorbed dose in water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the ceric-cerous system. It is classified as a reference standard dosimetry system (see ISO/ASTM Guide 51261). Ceric-cerous dosimeters are also used as transfer-standard dosimeters or routine dosimeters. This practice describes both the spectrophotometric and the potentiometric readout procedures for the ceric-cerous systems. This practice applies only to g rays, X rays, and high energy electrons. This practice applies provided the following are satisfied: The absorbed-dose range shall be between 5x10 2 and 5x10 4 Gy. The absorbed-dose rate shall be less than 10 6 Gy/s. For radionuclide gamma-ray sources, the initial photon energy shall be greater than 0.6 MeV. For bremsstrahlung photons, the initial energy of the electrons used to produce the bremsstrahlung photons shall be equal to or greater than 2 MeV. For electron beams, the initial electron energy shall be greater than 8 MeV. The irradiation temperature of the dosimeter shall be between 0 and 62 deg C

Personnel neutron dosimetry

International Nuclear Information System (INIS)

Hankins, D.

1982-04-01

This edited transcript of a presentation on personnel neutron discusses the accuracy of present dosimetry practices, requirements, calibration, dosemeter types, quality factors, operational problems, and dosimetry for a criticality accident. 32 figs

Metrological characteristics of the new BSS2 beta secondary standard system

International Nuclear Information System (INIS)

Reynaldo, Sibele R.

2005-01-01

Due to the increased interest and the importance of beta radiation dosimetry for radiation protection purposes, the Centro de Desenvolvimento da Tecnologia Nuclear. MG, Brazil, acquired the newest Beta Secondary Standard system (BSS2) in order to replace the old BSS1 model, with the goal of implement a beta radiation metrology laboratory and provide the corresponding reference radiation. The new system BSS2, unique in Latin America, requires operational testing and metrological characterization for reliability purposes. For this, some comparative investigations of the two systems were made. The influence of opening and closing the shutter in the final dose of radiation was identified as the highest in the BSS2 in relation to the one founded in BSS1, justified by the structural difference of the shutters of the systems and the reproducibility of source-detector geometry was better in BSS2, because of the robustness of the same

The challenge of Ciemat internal dosimetry service for accreditation according to ISO/IEC 17025 standard, for in vivo and in vitro monitoring and dose assessment of internal exposures

International Nuclear Information System (INIS)

Lopez, M.A.; Martin, R.; Hernandez, C.; Navarro, J.F.; Navarro, T.; Perez, B.; Sierra, I.

2016-01-01

The accreditation of an Internal Dosimetry Service (IDS) according to ISO/IEC 17025 Standard is a challenge. The aim of this process is to guarantee the technical competence for the monitoring of radionuclides incorporated in the body and for the evaluation of the associated committed effective dose E(50). This publication describes the main accreditation issues addressed by CIEMAT IDS regarding all the procedures involving good practice in internal dosimetry, focussing in the difficulties to ensure the traceability in the whole process, the appropriate calculation of detection limit of measurement techniques, the validation of methods (monitoring and dose assessments), the description of all the uncertainty sources and the interpretation of monitoring data to evaluate the intake and the committed effective dose. CIEMAT Internal Dosimetry Service (IDS) has developed and implemented a quality system based on ISO/IEC 17025 to ensure compliance with the general requirements of this reference standard. The development of documentary support according to this quality system permitted to standardise the systematic activities performed within the whole body counter and in vitro bioassay laboratories as well as the procedures carried out by qualified staff in charge of internal dose assessment. There was no previous experience in the accreditation of other internal dosimetry services in Spain. Then, requirements from the national regulatory body (Nuclear Safety Council, CSN) and national accreditation entity (ENAC) have been considered. The main concerns were to guarantee the traceability in the whole process and to avoid possible charge of interpretation or subjectivity in the methodology of dose assessment due to intakes of radionuclides when calculating from monitoring data. All the related international standards dealing with internal dosimetry were taken into account: ISO 28218 'Performance criteria for radiobioassay', ISO 27048 'Dose Assessment for the

Beta-particle dosimetry of the trabecular skeleton using Monte Carlo transport within 3D digital images

International Nuclear Information System (INIS)

Jokisch, D.W.; Bouchet, L.G.; Patton, P.W.; Rajon, D.A.; Bolch, W.E.

2001-01-01

Presently, skeletal dosimetry models utilized in clinical medicine simulate electron path lengths through skeletal regions based upon distributions of linear chords measured across bone trabeculae and marrow cavities. In this work, a human thoracic vertebra has been imaged via nuclear magnetic resonance (NMR) spectroscopy yielding a three-dimensional voxelized representation of this skeletal site. The image was then coupled to the radiation transport code EGS4 allowing for 3D tracing of electron paths within its true 3D structure. The macroscopic boundaries of the trabecular regions, as well as the cortex of cortical bone surrounding the bone site, were explicitly considered in the voxelized transport model. For the case of a thoracic vertebra, energy escape to the cortical bone became significant at source energies exceeding ∼2 MeV. Chord-length distributions were acquired from the same NMR image, and subsequently used as input for a chord-based dosimetry model. Differences were observed in the absorbed fractions given by the chord-based model and the voxel transport model, suggesting that some of the input chord distributions for the chord-based models may not be accurate. Finally, this work shows that skeletal mass estimates can be made from the same NMR image in which particle transport is performed. This feature allows one to determine a skeletal S-value using absorbed fraction and mass data taken from the same anatomical tissue sample. The techniques developed in this work may be applied to a variety of skeletal sites, thus allowing for the development of skeletal dosimetry models at all skeletal sites for both males and females and as a function of subject age

Organ dose from inhaled radionuclides taking lull period into account

International Nuclear Information System (INIS)

Datta, S.

1982-01-01

The dosimetry of inhaled radionuclides is generally carried out in accordance with the lung model recommended by the ICRP Task Group on Lung Dynamics. The relevant expressions are integrated over a given period, assuming continuous inhalation in an atmosphere of constant aerosol concentration. Though for the same amount of intake the dose commitment is found to be independent of variations in the rate of intake, the dose determined over specific intervals of time, is influenced by it or by lull intervals therein. Formulae are developed to arrive at doses to different organs when the subject's intake is constant and continuous for 8 hours, followed by a lull period of 16 hours each day. Results are given for a number of radionuclides and are compared with values characteristic of continuous inhalation. It is observed that when exposure is assumed to be continuous the dose for the same intake of activity is underestimated as compared to the dose when lull period is taken into account. For working periods of 6 days and 30 days the underestimate ranges from 5%-20% and 0.6% to 4.5% respectively. (author)

Skin dosimetry - radiological protection aspects of skin dosimetry

International Nuclear Information System (INIS)

Dennis, J.A.

1991-01-01

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

Release criteria for patients having undergone radionuclide therapy and criteria for their crossing the state border of the Russian Federation

International Nuclear Information System (INIS)

Zvonova, I.; Balonov, M.; Golikov, V.

2011-01-01

By means of a conservative dosimetry model, the values of operational radiological criteria for patients released from hospital-residual activity in a body and dose rate near the patient's body-are substantiated based on the effective dose limit of 5 mSv for persons helping the patient or living with him and 1 mSv for other adults and children. Two sets of operative criteria for radionuclides 125 I, 131 I, 153 Sm and 188 Re used in Russia for radionuclide therapy were derived. Release criteria for 125 I well differ from such values in other countries because in this work absorption of 125 I low-energy photon radiation in the patient was taken into account. When a patient having undergone radionuclide therapy crosses the frontier of Russia, high-sensitivity devices for radiation control at the custom can detect the patient. A simplified radiological assessment of the patient was suggested aimed at provision of radiation safety for patient companions in transport. (authors)

Bremsstrahlung parameters of praseodymium-142 in different human tissues. A dosimetric perspective for 142Pr radionuclide therapy

International Nuclear Information System (INIS)

Bakht, M.K.; Jabal-Ameli, H.; Ahmadi, S.J.; Sadeghi, M.; Sadjadi, S.; Tenreiro, Claudio

2012-01-01

Praseodymium-142 [T 1/2 =19.12 h, E β -=2.162 MeV (96.3%), E γ =1575 keV (3.7%)] is one of the 141 Pr radioisotopes. Many studies have been attempted to assess the significance of usage 142 Pr in radionuclide therapy. In many studies, the dosimetric parameters of 142 Pr sources were calculated by modeling 142 Pr sources in the water phantom and scoring the energy deposited around it. However, the medical dosimetry calculations in water phantom consider Bremsstrahlung production, raising the question: ''How important is to simulate human tissues instead of using water phantom?'' This study answers these questions by estimation of 142 Pr Bremsstrahlung parameters. The Bremsstrahlung parameters of 142 Pr as therapeutic beta nuclides in different human tissues (adipose, blood, brain, breast, cell nucleus, eye lens, gastrointestinal tract, heart, kidney, liver, lung deflated, lymph, muscle, ovary, pancreas, cartilage, red marrow, spongiosa, yellow marrow, skin, spleen, testis, thyroid and different skeleton bones) were calculated by extending the national council for radiation protection model. The specific Bremsstrahlung constant (Γ Br ), probability of energy loss by beta during Bremsstrahlung emission (P Br ) and Bremsstrahlung activity (A release ) Br were estimated. It should be mentioned that Monte Carlo simulation was used for estimation of 142 Pr Bremsstrahlung activity based on the element compositions of different human tissues and the calculated exposures from the anthropomorphic phantoms. Γ Br for yellow marrow was smallest amount (1.1962 x 10 -3 C/kg-cm 2 /MBq-h) compared to the other tissues and highest for cortical bone (2.4764 x 10 -3 C/kg-cm 2 /MBq-h), and, overall, Γ Br for skeletal tissues were greater than other tissues. In addition, Γ Br breast was 1.8261 x 10 -3 C/kg-cm 2 /MBq-h which was greater than sacrum and spongiosa bones. Moreover, according to (A release ) Br of 142 Pr, the patients receiving 142 Pr do not have to be hospitalized for

ESR Dosimetry

International Nuclear Information System (INIS)

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

2004-01-01

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

TH-AB-206-02: Nuclear Medicine Theronostics: Wave of the Future; Pre-Clinical and Clinical Opportunities

International Nuclear Information System (INIS)

Delpassand, E.

2016-01-01

In the past few decades, the field of nuclear medicine has made long strides with the continued advancement of related sciences and engineering and the availability of diagnostic and therapeutic radionuclides. Leveraging these advancements while combining the advantages of therapeutic and diagnostic radionuclides into one radiopharmaceutical has also created a new subfield “theranostics” in nuclear medicine that has the potential to further propel the field into the future. This session is composed of two talks; one focused on the physics principles of theranostics from properties of beta and alpha emitting radionuclides to dosimetric models and quantification; while the second describes preclinical and clinical applications of theranostics and discusses the challenges and opportunities of bringing them to the clinic. At the end of the session the listener should be able to identify: The different properties of beta and alpha emitting radionuclides Which radionuclides are selected for which nuclear medicine therapies and why How PET can be used to accurately quantify the uptake of tumor targeting molecules How individualized dosimetry can be performed from the management of thyroid cancer to novel radiolabeled antibody therapies Promising pre-clinical radiopharmaceutical pairs in prostate cancer and melanoma. Promising clinical Theranostics in neuroendocrine cancers. Challenges of bringing Theranostics to the clinic. E. Delpassand, RITA Foundation -Houston; SBIR Grant; CEO and share holder of RadioMedix.

TH-AB-206-00: Challenges and Opportunities for Nuclear Medicine Theranostics

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-06-15

In the past few decades, the field of nuclear medicine has made long strides with the continued advancement of related sciences and engineering and the availability of diagnostic and therapeutic radionuclides. Leveraging these advancements while combining the advantages of therapeutic and diagnostic radionuclides into one radiopharmaceutical has also created a new subfield “theranostics” in nuclear medicine that has the potential to further propel the field into the future. This session is composed of two talks; one focused on the physics principles of theranostics from properties of beta and alpha emitting radionuclides to dosimetric models and quantification; while the second describes preclinical and clinical applications of theranostics and discusses the challenges and opportunities of bringing them to the clinic. At the end of the session the listener should be able to identify: The different properties of beta and alpha emitting radionuclides Which radionuclides are selected for which nuclear medicine therapies and why How PET can be used to accurately quantify the uptake of tumor targeting molecules How individualized dosimetry can be performed from the management of thyroid cancer to novel radiolabeled antibody therapies Promising pre-clinical radiopharmaceutical pairs in prostate cancer and melanoma. Promising clinical Theranostics in neuroendocrine cancers. Challenges of bringing Theranostics to the clinic. E. Delpassand, RITA Foundation -Houston; SBIR Grant; CEO and share holder of RadioMedix.

TH-AB-206-02: Nuclear Medicine Theronostics: Wave of the Future; Pre-Clinical and Clinical Opportunities

Energy Technology Data Exchange (ETDEWEB)

Delpassand, E. [Excel Diagnostic & Nuclear Oncology Center, Houston, TX (United States)

2016-06-15

In the past few decades, the field of nuclear medicine has made long strides with the continued advancement of related sciences and engineering and the availability of diagnostic and therapeutic radionuclides. Leveraging these advancements while combining the advantages of therapeutic and diagnostic radionuclides into one radiopharmaceutical has also created a new subfield “theranostics” in nuclear medicine that has the potential to further propel the field into the future. This session is composed of two talks; one focused on the physics principles of theranostics from properties of beta and alpha emitting radionuclides to dosimetric models and quantification; while the second describes preclinical and clinical applications of theranostics and discusses the challenges and opportunities of bringing them to the clinic. At the end of the session the listener should be able to identify: The different properties of beta and alpha emitting radionuclides Which radionuclides are selected for which nuclear medicine therapies and why How PET can be used to accurately quantify the uptake of tumor targeting molecules How individualized dosimetry can be performed from the management of thyroid cancer to novel radiolabeled antibody therapies Promising pre-clinical radiopharmaceutical pairs in prostate cancer and melanoma. Promising clinical Theranostics in neuroendocrine cancers. Challenges of bringing Theranostics to the clinic. E. Delpassand, RITA Foundation -Houston; SBIR Grant; CEO and share holder of RadioMedix.

TH-AB-206-00: Challenges and Opportunities for Nuclear Medicine Theranostics

International Nuclear Information System (INIS)

2016-01-01

In the past few decades, the field of nuclear medicine has made long strides with the continued advancement of related sciences and engineering and the availability of diagnostic and therapeutic radionuclides. Leveraging these advancements while combining the advantages of therapeutic and diagnostic radionuclides into one radiopharmaceutical has also created a new subfield “theranostics” in nuclear medicine that has the potential to further propel the field into the future. This session is composed of two talks; one focused on the physics principles of theranostics from properties of beta and alpha emitting radionuclides to dosimetric models and quantification; while the second describes preclinical and clinical applications of theranostics and discusses the challenges and opportunities of bringing them to the clinic. At the end of the session the listener should be able to identify: The different properties of beta and alpha emitting radionuclides Which radionuclides are selected for which nuclear medicine therapies and why How PET can be used to accurately quantify the uptake of tumor targeting molecules How individualized dosimetry can be performed from the management of thyroid cancer to novel radiolabeled antibody therapies Promising pre-clinical radiopharmaceutical pairs in prostate cancer and melanoma. Promising clinical Theranostics in neuroendocrine cancers. Challenges of bringing Theranostics to the clinic. E. Delpassand, RITA Foundation -Houston; SBIR Grant; CEO and share holder of RadioMedix.

Intercalibration of radiological measurements for surveillance purposes of the internal dosimetry laboratory coordinated by the IAEA; Intercalibracion de mediciones radiologicas para fines de vigilancia del laboratorio de dosimetria interna coordinada por el OIEA

Energy Technology Data Exchange (ETDEWEB)

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

2002-07-15

The ININ of Mexico participated in this intercomparison organized by the IAEA in 2000. The objective of this activity is that the dosimetry laboratories that participate can validate the programs of internal dosimetry, with the purpose of improving its capacity in the evaluation of the internal dose and have access to a mechanism to evaluate its dosimetry system under real conditions. The specific objectives of this intercomparison were: 1. To evaluate the participant's capacity to manage the measurements of individual monitoring in terms of the activity in the phantom. 2. To provide the access to the unique calibration resources that otherwise would not be available. 3. To compare the operation of several detection systems, the geometry, phantoms, calibration methods and methods for the evaluation of activity of the radionuclide used by each institution. 4. To provide the independent verification of the direct measurement methods of the dosimetry service. (Author)

Possible applications of radionuclide techniques in criminology

International Nuclear Information System (INIS)

Stverak, B.; Kopejtko, J.; Chodora, F.; Chyska, J.

1976-01-01

The use of radioindicator methods in dactyloscopy is described, in which is used the bond of suitable radioindicators to certain components of the sweat secretion with subsequent detection of the local distribution of these radionuclides using the autoradiographic method. The use of autoradiography and gamma spectrometry is given in ballistics, neutron activation analysis and X-ray fluorescence analysis in the investigation of motor car accidents and in the verification of historical objects, in forensic medicine, the use of autoradiography in the expertise of photographs, beta radiography in graphology and the use of radioactive labelling for trapping criminals. (J.P.)

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

A Microdosimetric-Kinetic Model of Cell Killing by Irradiation from Permanently Incorporated Radionuclides.

Science.gov (United States)

Hawkins, Roland B

2018-01-01

An expression for the surviving fraction of a replicating population of cells exposed to permanently incorporated radionuclide is derived from the microdosimetric-kinetic model. It includes dependency on total implant dose, linear energy transfer (LET), decay rate of the radionuclide, the repair rate of potentially lethal lesions in DNA and the volume doubling time of the target population. This is used to obtain an expression for the biologically effective dose ( BED α / β ) based on the minimum survival achieved by the implant that is equivalent to, and can be compared and combined with, the BED α / β calculated for a fractionated course of radiation treatment. Approximate relationships are presented that are useful in the calculation of BED α / β for alpha- or beta-emitting radionuclides with half-life significantly greater than, or nearly equal to, the approximately 1-h repair half-life of radiation-induced potentially lethal lesions.

MEASUREMENT OF RADIONUCLIDES USING ION CHROMATOGRAPHY AND FLOW-CELL SCINTILLATION COUNTING WITH PULSE SHAPE DISCRIMINATION

International Nuclear Information System (INIS)

Fjeld, R. A.; DeVol, T.A.; Leyba, J.D.

2000-01-01

Radiological characterization and monitoring is an important component of environmental management activities throughout the Department of Energy complex. Gamma-ray spectroscopy is the technology most often used for the detection of radionuclides. However, radionuclides which cannot easily be detected by gamma-ray spectroscopy, such as pure beta emitters and transuranics, pose special problems because their quantification generally requires labor intensive radiochemical separations procedures that are time consuming and impractical for field applications. This project focused on a technology for measuring transuranics and pure beta emitters relatively quickly and has the potential of being field deployable. The technology combines ion exchange liquid chromatography and on-line alpha/beta pulse shape discriminating scintillation counting to produce simultaneous alpha and beta chromatograms. The basic instrumentation upon which the project was based was purchased in the early 1990's. In its original commercial form, the instrumentation was capable of separating select activation/fission products in ionic forms from relatively pure aqueous samples. We subsequently developed the capability of separating and detecting actinides (thorium, uranium, neptunium, plutonium, americium, and curium) in less than 30 minutes (Reboul, 1993) and realized that the potential time savings over traditional radiochemical methods for isolating some of these radionuclides was significant. However, at that time, the technique had only been used for radionuclide concentrations that were considerably above environmental levels and for aqueous samples of relatively high chemical purity. For the technique to be useful in environmental applications, development work was needed in lowering detection limits; to be useful in applications involving non-aqueous matrices such as soils and sludges or complex aqueous matrices such as those encountered in waste samples, development work was needed in

Determination of radionuclides present in the relation of waste plant storage of El Cabril

International Nuclear Information System (INIS)

Suarez, J.A.; Rodriguez Alcala, M.; Estartero, A.G.; Pina, G.; Gascon, J.L.

1997-03-01

Different waste streams of low and medium level radioactive are generated from the operation of Nuclear Power Plants with light water reactors. The most important waste streams are: spent ion exchange resin, used to purify the water of the reactor coolant and the evaporator concentrates produced in the evaporation of some liquid radioactive waste. In this paper are show the improvement and development of the analytical methods of all these radionuclides, performed in the CIEMAT project about Characterization of Radioactive Wastes and Materials. The alpha, beta and low energy gamma-emitting radionuclides are analyzed after the separation procedure by alpha-spectrometry, liquid scintillation counting and low-energy gamma spectrometry. The high energy gamma-emitting radionuclides (>50 keV) are analyzed by gamma spectrometry without separation. This work has been developed within the framework of the CIEMAT-ENRESA Association Agreement. (Author) 12 refs

Applied internal dosimetry staff exposed to Uranium

International Nuclear Information System (INIS)

Trotta, Marisa V.; Arguelles, Maria G.

2009-01-01

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

Clinical dosimetry

International Nuclear Information System (INIS)

Rassow, J.

1973-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1958-07-01

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

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

International Nuclear Information System (INIS)

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

1997-10-01

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

Radiochemical schemes of obtaining 89Sr and 90Y radionuclides

International Nuclear Information System (INIS)

Usarov, Z. O.

2010-03-01

Key words: strontium-89, yttrium-90, extraction and extraction-chromatographic purification of radionuclides, radiopharmaceuticals. Subjects of research: strontium-89 and yttrium-90 radionuclides and their chloride forms. Purpose of work is developing of radiochemical technologies on obtaining of 89 Sr and 90 Y on the WWR-SM reactor with high radionuclide purity. Methods of research: extraction and extraction-chromatographic methods of radionuclides separation, beta- and gamma-spectrometric methods of activity measuring. The results obtained and their novelty: Were determined the conformity to laws of Y and Sr distribution in two-phase systems TBP-HNO 3 , TBP-NH 4 NO 3 , TBP-HCI, HDEHP-NO 3 , HDEHP-NH 4 NO 3 and HDEHP-HCI. Were determined the conformity to laws of Y and Sr distribution in systems with craun ethers DB-18K-6 and DTBDB-18K-6 from water solutions of HNO 3 . Radiochemical technologies on obtaining of 89 Sr and 90 Y radionuclides including radiochemical process of yttrium target with using the systems TBP-HNO 3 and HDEHP/Teflone were developed. Practical value: the radiochemical technology of obtaining 89 Sr with high radionuclide purity was developed. The method of preparation a chloride compound of 89 SrCl 2 which is used as a drug form for preparation of 89 Sr- 'Metastron' was developed. The relatively simple method of on the way obtaining 90 Y in the reactor with high radionuclidic purity that is useful for follow using in medical practice was offered. Degree of embed and economic effectivity: the developed technologies have approbation in manufacturing conditions in Radiopreparat Enterprise of INP AS RU and were offered for receiving of domestic preparations against of import foreign analogues. The statement about using the invention by obtained patent is attached to dissertation. Field of application: the received results will be introduced in manufacture at Radiopreparat Enterprise of INP AS RU for receiving of domestic preparations

The environmental and radionuclide laboratory at VKTA Rossendorf; Das Labor fuer Umwelt- und Radionuklidanalytik im VKTA Rossendorf

Energy Technology Data Exchange (ETDEWEB)

Koehler, M.; Knappik, R.; Gleisberg, B.; Schaefer, I.; Boden, W.; Bothe, M. [Verein fuer Kernverfahrenstechnik und Analytik Rossendorf e.V. (VKTA), Dresden (Germany)

2001-07-01

The VKTA provides environmental and radionuclide analyses for remediation and waste management tasks at the Rossendorf research site and for commercial clients as well. The analyses, the correlated valuations and calculations were used for the decommissioning of nuclear facilities, for the remediation of contaminated mining sites and for environmental investigations. The Laboratory for Environmental and Radionuclide Analytics is able to handle and analyse artificial and natural radionuclides in the range from 10{sup -3} Bq until 10{sup 9} Bq. Besides the used activity measurement techniques ({alpha}-particle and {gamma}-ray spectrometry, {beta}-counting), which were also applied after radiochemical separations, mass-spectrometry with inductively coupled plasma provides analytical results for long-lived radionuclides and isotopic ratios very effective. The capability of the laboratory is demonstrated by selected applications. (orig.) [German] Der VKTA fuehrt im Rahmen seiner Rueckbau- und Entsorgungsaufgaben am Forschungsstandort Rossendorf und fuer externe Auftraggeber Umwelt- und Radionuklidanalysen als komplexe Dienstleistung durch. Die Analysen und die damit in Zusammenhang stehenden Bewertungen und Modellrechnungen finden beim Rueckbau kerntechnischer Anlagen, bei der Sanierung von Uranbergbau-Altlasten und im Umweltbereich Verwendung. Im Labor fuer Umwelt- und Radionuklidanalytik werden Proben mit kuenstlichen und natuerlichen Radionukliden im typischen Aktivitaetsbereich von 10{sup -3} Bq bis 10{sup 9} Bq bearbeitet und analysiert. Neben den Aktivitaetsmessverfahren ({alpha}-, {beta}-, {gamma}-Spektrometrie), die auch nach radiochemischen Trennungen eingesetzt werden, kommen massenspektrometrische Verfahren bei der Analyse langlebiger Radionuklide bzw. Isotopenverhaeltnisse zum Einsatz. Das Leistungsspektrum des Labors wird durch ausgewaehlte Applikationen belegt. (orig.)

Latest developments in silica fibre luminescence dosimetry

Energy Technology Data Exchange (ETDEWEB)

Bradley, D. A.; Abdul S, S. F.; Jafari, S. M.; Alanazi, A. [University of Surrey, Department of Physics, GU2 7XH Guildford, Surrey (United Kingdom); Amouzad M, G. [University of Malaya, Faculty of Engineering, Department of Electrical Engineering, Integrated Lightwave Research Group, 50603 Kuala Lumpur (Malaysia); Addul R, H. A.; Mizanur R, A. K. M.; Zubair, H. T.; Begum, M.; Yusoff, Z.; Omar, N. Y. M. [Multimedia University, Faculty of Engineering, 2010 Cyberjaya, Selangor (Malaysia); Maah, M. J. [University of Malaya, Department of Chemistry, 50603 Kuala Lumpur (Malaysia); Collin, S. [National Physical Laboratory, Hampton Road, Teddington, TW11 OLW Middlesex (United Kingdom); Mat-Sharif, K. A.; Muhd-Yassin, S. Z.; Zulkifli, M. I., E-mail: d.a.bradley@surrey.ac.uk [Telekom Malaysia Research and Development Sdn Bhd., 63000 Cyberjaya, Selangor (Malaysia)

2015-10-15

Full text: Using tailor made sub-mm diameter doped-silica fibres, we are carrying out luminescence dosimetry studies for a range of situations, including thermoluminescence (Tl)investigations on a liquid alpha source formed of {sup 223}RaCl (the basis of the Bayer Health care product Xofigo), the Tl response to a 62 MeV proton source and Tl response to irradiation from an {sup 241}Am-Be neutron source. In regard to the former, in accord with the intrinsic high linear energy transfer (Let) and short path length (<100 um) of the α-particles in calcified tissue, the product is in part intended as a bone-seeking radionuclide for treatment of metastatic cancer, offering high specificity and efficacy. The Tl yield of Ge-doped SiO{sub 2} fibres has been investigated including for photonic crystal fibre un collapsed, flat fibres and single mode fibres, these systems offering many advantages over conventional passive dosimetry types. In particular, one can mention comparable and even superior sensitivity, an effective atomic number Z{sub eff} of the silica dosimetric material close to that of bone, and the glassy nature of the fibres offering the additional advantage of being able to place such dosimeters directly into liquid environments. Finally we review the use of our tailor made fibres for on-line radioluminescence measurements of radiotherapy beams. The outcome from these various lines of research is expected to inform development of doped fiber radiation dosimeters of versatile utility, ranging from clinical applications through to industrial studies and environmental evaluations. (Author)

Non-conventional personal dosimetry techniques

International Nuclear Information System (INIS)

Regulla, D.F.

1984-01-01

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

Radionuclides in peat bogs and energy peat

International Nuclear Information System (INIS)

Helariutta, K.; Rantavaara, A.; Lehtovaara, J.

2000-06-01

The study was aimed at improving the general view on radionuclides contents in energy peat produced in Finland. The annual harvest of fuel peat in 1994 was studied extensively. Also thirteen peat bogs used for peat production and one bog in natural condition were analysed for vertical distributions of several radionuclides. These distributions demonstrate the future change in radioactivity of energy peat. Both natural nuclides emitting gamma radiation ( 238 U, 235 U, 232 Th, 226 Ra, 40 K) and radiocaesium ( 137 Cs, 134 Cs) origin in fallout from a nuclear power plant accident (1986) and in atmospheric nuclear weapon tests were analysed. The beta and alpha active natural nuclides of lead and polonium ( 210 Pb, 210 Po) were determined on a set of peat samples. These nuclides potentially contribute to radiation exposure through inhalation when partially released to atmosphere during combustion of peat. The activity concentrations of natural radionuclides often increased towards the deepest peat bog layers whereas the radioactive caesium deposited from atmosphere was missing in the deep layers. In undisturbed surface layers of a natural bog and peat production bogs the contents of 210 Pb and 210 Po exceeded those of the deeper peat layers. The nuclides of the uranium series in the samples were generally not in radioactive equilibrium, as different environmental processes change their activity ratios in peat. Radiation exposure from handling and utilisation of peat ash was estimated with activity indices derived from the data for energy peat harvested in 1994. Intervention doses were exceeded in a minor selection of samples due to 137 Cs, whereas natural radionuclides contributed very little to the doses. (orig.)

Dosimetry and Calibration Section

International Nuclear Information System (INIS)

Otto, T.

1999-01-01

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

EDISTR: a computer program to obtain a nuclear decay data base for radiation dosimetry

International Nuclear Information System (INIS)

Dillman, L.T.

1980-01-01

This report provides documentation for the computer program EDISTR. EDISTR uses basic radioactive decay data from the Evaluated Nuclear Structure Data File developed and maintained by the Nuclear Data Project at the Oak Ridge National Laboratory as input, and calculates the mean energies and absolute intensities of all principal radiations associated with the radioactive decay of a nuclide. The program is intended to provide a physical data base for internal dosimetry calculations. The principal calculations performed by EDISTR are the determination of (1) the average energy of beta particles in a beta transition, (2) the beta spectrum as function of energy, (3) the energies and intensities of x-rays and Auger electrons generated by radioactive decay processes, (4) the bremsstrahlung spectra accompanying beta decay and monoenergetic Auger and internal conversion electrons, and (5) the radiations accompanying spontaneous fission. This report discusses the theoretical and empirical methods used in EDISTR and also practical aspects of the computer implementation of the theory. Detailed instructions for preparing input data for the computer program are included, along with examples and discussion of the output data generated by EDISTR

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)

Lifetime tumor risk coefficients for beagle dogs that inhaled cerium-144 chloride

Energy Technology Data Exchange (ETDEWEB)

Boecker, B.B.; Hahn, F.F.; Griffith, W.C. [and others

1995-12-01

Reported here is one of the life-span radionuclide toxicology studies being conducted at ITRI in Beagle dogs. These studies are examining the life-span health risks of inhaled {Beta}-, {gamma}- and {alpha}-emitting radionuclides to expand available knowledge on these risks especially for the many cases for which human data are not available. The outcomes of these studies are providing important information on dosimetry and dose-response relationships for these inhaled radionuclides and the relative importance of a broad range of dose- and effect-modifying factors. A number of these studies are currently coming to completion. Much of the ITRI effort is being directed to final reviews of the dosimetric, clinical, and pathologic results and writing summary manuscripts. Radiation doses and effects in tissues adjacent to bone, specifically those of epithelial or marrow origin, should be considered when determining risks from internally deposited, bone-seeking radionuclides such as {sup 144}Ce.

Thin film tritium dosimetry

Science.gov (United States)

Moran, Paul R.

1976-01-01

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

Nuclear Decay Data for the International Reactor Dosimetry Library for Fission and Fusion (IRDFF: Updated Evaluations of the Half-Lives and Gamma Ray Intensities

Directory of Open Access Journals (Sweden)

Chechev Valery P.

2016-01-01

Full Text Available Updated evaluations of the half-lives and prominent gamma ray intensities have been presented for 20 radionuclides – dosimetry reaction residuals. The new values of these decay characteristics recommended for the IRDFF library were obtained using the approaches and methodology adopted by the working group of the Decay Data Evaluation Project (DDEP cooperation. The experimental data published up to 2014 were taken into account in updated evaluations. The list of radionuclides includes 3H, 18F, 22Na, 24Na, 46Sc, 51Cr, 54Mn, 59Fe, 57Co, 60Co, 57Ni, 64Cu, 88Y, 132Te, 131I, 140Ba, 140La, 141Ce, 182Ta, 198Au.

Application of Monte Carlo simulation to the standardization of positron emitting radionuclides; Aplicacao do metodo de Monte Carlo na padronizacao de radionuclideos emissores de positrons

Energy Technology Data Exchange (ETDEWEB)

Tongu, Margareth Lika Onishi

2009-07-01

Since 1967, the Nuclear Metrology Laboratory (LNM) at the Nuclear and Energy Research (IPEN) in Sao Paulo, Brazil, has developed radionuclide standardization methods and measurements of the Gamma-ray emission probabilities per decay by means of 4{pi}{beta}-{gamma} coincidence system, a high accuracy primary method for determining disintegration rate of radionuclides of interest. In 2001 the LNM started a research field on modeling, based on Monte Carlo method, of all the system components, including radiation detectors and radionuclide decay processes. This methodology allows the simulation of the detection process in a 4{pi}{beta}-{gamma} system, determining theoretically the observed activity as a function of the 4{pi}{beta} detector efficiency, enabling the prediction of the behavior of the extrapolation curve and optimizing a detailed planning of the experiment before starting the measurements. One of the objectives of the present work is the improvement of the 4{pi} proportional counter modeling, presenting a detailed description of the source holder and radioactive source material, as well as absorbers placed around the source. The simulation of radiation transport through the detectors has been carried out using code MCNPX. The main focus of the present work is on Monte Carlo modeling of the standardization of positron emitting radionuclides associated (or not) with electron capture and accompanied (or not) by the emission of Gamma radiation. One difficulty in this modeling is to simulate the detection of the annihilation Gamma ray, which arise in the process of positron absorption within the 4{pi} detector. The methodology was applied to radionuclides {sup 18}F and {sup 22}Na. (author)

Synthesis of plastic scintillation microspheres: Alpha/beta discrimination

International Nuclear Information System (INIS)

Santiago, L.M.; Bagán, H.; Tarancón, A.; Garcia, J.F.

2014-01-01

Plastic scintillation microspheres (PSm) have been developed as an alternative for liquid scintillation cocktails due to their ability to avoid the mixed waste, besides other strengths in which the possibility for alpha/beta discrimination is included. The aim of this work was to evaluate the capability of PSm containing two combinations of fluorescence solutes (PPO/POPOP and pT/Bis-MSB) and variable amounts of a second organic solvent (naphthalene) to enhance the alpha/beta discrimination. Two commercial detectors with different Pulse Shape Discrimination performances (Quantulus and Triathler) were used to evaluate the alpha/beta discrimination. An optimal discrimination of alpha/beta particles was reached, with very low misclassification values (2% for beta particles and 0.5% for alpha particles), when PSm containing PPO/POPOP and between 0.6 and 2.0 g of naphthalene were evaluated using Triathler and the appropriate programme for data processing. - Highlights: • Plastic scintillation microspheres for α/β discrimination have been synthesised. • The energy transfer process in PSm with different compositions has been investigated. • The α/β discrimination capabilities of two commercial detectors have been evaluated. • 2% and 0.5% of misclassifications for β and α radionuclides have been achieved respectively

Reactor Dosimetry State of the Art 2008

Science.gov (United States)

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

2009-08-01

. Williams, A. P. Ribaric and T. Schnauber. Agile high-fidelity MCNP model development techniques for rapid mechanical design iteration / J. A. Kulesza.Extension of Raptor-M3G to r-8-z geometry for use in reactor dosimetry applications / M. A. Hunter, G. Longoni and S. L. Anderson. In vessel exposure distributions evaluated with MCNP5 for Atucha II / J. M. Longhino, H. Blaumann and G. Zamonsky. Atucha I nuclear power plant azimutal ex-vessel flux profile evaluation / J. M. Longhino ... [et al.]. UFTR thermal column characterization and redesign for maximized thermal flux / C. Polit and A. Haghighat. Activation counter using liquid light-guide for dosimetry of neutron burst / M. Hayashi ... [et al.]. Control rod reactivity curves for the annular core research reactor / K. R. DePriest ... [et al.]. Specification of irradiation conditions in VVER-440 surveillance positions / V. Kochkin ... [et al.]. Simulations of Mg-Ar ionisation and TE-TE ionisation chambers with MCNPX in a straightforward gamma and beta irradiation field / S. Nievaart ... [et al.]. The change of austenitic stainless steel elements content in the inner parts of VVER-440 reactor during operation / V. Smutný, J. Hep and P. Novosad. Fast neutron environmental spectrometry using disk activation / G. Lövestam ... [et al.]. Optimization of the neutron activation detector location scheme for VVER-lOOO ex-vessel dosimetry / V. N. Bukanov ... [et al.]. Irradiation conditions for surveillance specimens located into plane containers installed in the WWER-lOOO reactor of unit 2 of the South-Ukrainian NPP / O. V. Grytsenko. V. N. Bukanov and S. M. Pugach. Conformity between LRO mock-ups and VVERS NPP RPV neutron flux attenuation / S. Belousov. Kr. Ilieva and D. Kirilova. FLUOLE: a new relevant experiment for PWR pressure vessel surveillance / D. Beretz ... [et al.]. Transport of neutrons and photons through the iron and water layers / M. J. Kost'ál ... [et al.]. Condition evaluation of spent nuclear fuel assemblies

Collections of numerical data and definition. Volume 2: protection - dosimetry; Recueil de donnees numeriques et de definitions. Tome 2: protection - dosimetrie

Energy Technology Data Exchange (ETDEWEB)

Combrisson, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1955-07-01

Collections of numerical data and definition about radiation protection and dosimetry are given. It firstly gives the definitions of the different units in radiation measurement. The radiation beam deep distribution in human tissue is graphically presented. It stated the rules to apply for human protection when exposed to accidental or long period irradiations. The recommended values for the relative biological effectiveness are also discussed.The recommendations of the Chalk River conference for the dose of tolerance are given. The report of the Subcommittee on Permissible Dose for Internal Radiation of the International Commission on Radiological Protection of June 1953 is presented. It gives the real half-life, the effective energy RBE, the maximum permissible dose for known radioisotopes as well as the maximum permissible concentration in air and water. The method of calculation for a known radioisotopes mixture is given. After the presentation of the chemical composition and characteristics of the body of an adult, the radioactive doses due to {beta} and {gamma} radioisotopes are discussed and requisite numerical data for the calculation of doses due to {beta} and {gamma} radiations are given. The influence of the thickness of a water or animal tissue layer on a {beta} irradiation is studied as well as the transport of electrons and {beta} particles in animal tissue. A graphic determining the lead thickness needed to obtain the dose of tolerance according the energy and the activity of a {gamma} source is given as well as the lead thickness needed to protect ourself from a radium source according the radium quantity and the distance from the source. (M.P.)

Comparative cytogenetic analysis of chromosomal aberrations and premature centromere division in persons exposed to radionuclides

International Nuclear Information System (INIS)

Jovicic, D.; Rakic, B.; Vukov, T.; Pajic, J.; Milacic, S.; Kovacevic, R.; Stevanovic, M.; Drakulic, D.; Bukvic, N.

2009-01-01

The aim of the research was to determine the presence of correlation between the frequency of premature centromere division (PCD) and chromosomal aberrations (CA) in metaphases in persons professionally exposed to radionuclides. Biological dosimetry was performed by conventional cytogenetic technique. The presence of PCD was confirmed by Fluorescent in situ hybridization (FISH). The L1.84 probe (specific for centromeric region of chromosome 18) was used. The analysis included 50 subjects employed in the Clinical Center of Serbia (C) (the average age of 45.24 ± 1.18 and the average exposition time 17.96 ± 1.15) and 40 subjects in control group (K) (the average age of 44.40 ± 0.98 and the average years of employment 19.67 ± 0.98 years) which were not exposed to genotoxic agents in their workplaces. The results showed that frequencies of CA and PCD were statistically significantly higher in subjects exposed to radionuclides than in the control group (Mann-Whitney U test, P [sr

Radionuclide concentrations in white sturgeons from the Hanford Reach of the Columbia River

International Nuclear Information System (INIS)

Dauble, D.D.; Poston, T.M.

1994-01-01

We summarized radionuclide concentrations in white sturgeons Acipenser transmontanus from the Columbia River during a period when several plutonium-production reactors were operating at the Hanford Site in Washington State and compared these values to those measured several years after reactor shutdown. Studies conducted in the Hanford Reach of the Columbia River during 1953-1955 indicated that high concentrations of radionuclides (as total beta) were present in some internal organs on the external surface of white sturgeons. Average concentrations were about 1,480 Bq/kg for liver and kidney and exceeded 2,200 Bq/kg for fins and scutes. The principal radionuclides in the tissues of white sturgeons from the Hanford Reach during 1963-1967, the peak reactor operation interval, were 32 P, 65 Zn, and 51 Cr. Average concentrations of 32 P in muscle ranged from 925 to 2,109 Bq/kg and were typically two to seven times greater than 65 Zn. Average concentrations of radionuclides were usually in the order of gut contents much-gt carcass > muscle. Studies from 1989 to 1990 showed that radionuclide concentrations had decreased dramatically in white sturgeon tissue since the time of reactor operation. Maximum concentrations for artificial radionuclides ( 90 Sr, 60 Co, 137 Cs) in muscle and cartilage of white sturgeons in the Columbia River had declined to less than 4 Bq/kg. Formerly abundant radionuclides, including 32 P, 65 Zn, and 51 Cr, could not be detected in recent tissue samples. Further, radionuclide tissue burden in populations of sturgeons from the Hanford Reach and the upstream or downstream reference locations did not differ significantly. 34 refs., 3 figs., 4 tabs

An approved personal dosimetry service based on an electronic dosimeter

International Nuclear Information System (INIS)

Marshall, T.O.; Bartlett, D.T.; Burgess, P.H.; Campbell, J.I.; Hill, C.E.; Pook, E.A.; Sandford, D.J.

1991-01-01

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

Fundamentals of x-ray dosimetry

International Nuclear Information System (INIS)

Roesch, W.C.

1976-01-01

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

Thermoluminescent dosimetry in veterinary diagnostic radiology

International Nuclear Information System (INIS)

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

2012-01-01

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

Radionuclide toxicity

International Nuclear Information System (INIS)

Galle, P.

1982-01-01

The aim of this symposium was to review the radionuclide toxicity problems. Five topics were discussed: (1) natural and artificial radionuclides (origin, presence or emission in the environment, human irradiation); (2) environmental behaviour of radionuclides and transfer to man; (3) metabolism and toxicity of radionuclides (radioiodine, strontium, rare gas released from nuclear power plants, ruthenium-activation metals, rare earths, tritium, carbon 14, plutonium, americium, curium and einsteinium, neptunium, californium, uranium) cancerogenous effects of radon 222 and of its danghter products; (4) comparison of the hazards of various types of energy; (5) human epidemiology of radionuclide toxicity (bone cancer induction by radium, lung cancer induction by radon daughter products, liver cancer and leukaemia following the use of Thorotrast, thyroid cancer; other site of cancer induction by radionuclides) [fr

Sixth symposium on neutron dosimetry

International Nuclear Information System (INIS)

1987-01-01

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

Environmental dosimetry

International Nuclear Information System (INIS)

Gold, R.

1977-01-01

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

Nuclear accident dosimetry

International Nuclear Information System (INIS)

1982-01-01

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

Nuclear accident dosimetry

Energy Technology Data Exchange (ETDEWEB)

NONE

1983-12-31

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

Measurement of radionuclides using ion chromatography and flow-cell scintillation counting with pulse shape discrimination

International Nuclear Information System (INIS)

DeVol, T.A.; Fjeld, R.A.

1995-01-01

A project has been initiated at Clemson Univ. to develop a HPLC/flow- cell system for analysis of non-gamma emitting radionuclides in environmental samples; an important component is development of a low background flow-cell detector that counts alpha and beta particles separately through pulse shape discrimination. Objective of the work presented here is to provide preliminary results of an evaluation of the following scintillators: CaF 2 :Eu, scintillating glass, and BaF 2 . Slightly acidic aqueous solutions of the alpha emitter 233 U and the beta emitter 45 Ca were used. Detection efficiencies and minimum detectable activities were determined

Monte Carlo simulation of {beta}-{gamma} coincidence system using plastic scintillators in 4{pi} geometry

Energy Technology Data Exchange (ETDEWEB)

Dias, M.S. [Instituto de Pesquisas Energeticas e Nucleares: IPEN-CNEN/SP, Av. Prof. Lineu Prestes 2242, 05508-000 Sao Paulo, SP (Brazil)], E-mail: msdias@ipen.br; Piuvezam-Filho, H. [Instituto de Pesquisas Energeticas e Nucleares: IPEN-CNEN/SP, Av. Prof. Lineu Prestes 2242, 05508-000 Sao Paulo, SP (Brazil); Baccarelli, A.M. [Departamento de Fisica-PUC/SP-Rua Marques de Paranagua 111, 01303-050 Sao Paulo, SP (Brazil); Takeda, M.N. [Universidade Santo Amaro, UNISA-Rua Prof. Eneas da Siqueira Neto 340, 04829-300 Sao Paulo, SP (Brazil); Koskinas, M.F. [Instituto de Pesquisas Energeticas e Nucleares: IPEN-CNEN/SP, Av. Prof. Lineu Prestes 2242, 05508-000 Sao Paulo, SP (Brazil)

2007-09-21

A modified version of a Monte Carlo code called Esquema, developed at the Nuclear Metrology Laboratory in IPEN, Sao Paulo, Brazil, has been applied for simulating a 4{pi}{beta}(PS)-{gamma} coincidence system designed for primary radionuclide standardisation. This system consists of a plastic scintillator in 4{pi} geometry, for alpha or electron detection, coupled to a NaI(Tl) counter for gamma-ray detection. The response curves for monoenergetic electrons and photons have been calculated previously by Penelope code and applied as input data to code Esquema. The latter code simulates all the disintegration processes, from the precursor nucleus to the ground state of the daughter radionuclide. As a result, the curve between the observed disintegration rate as a function of the beta efficiency parameter can be simulated. A least-squares fit between the experimental activity values and the Monte Carlo calculation provided the actual radioactive source activity, without need of conventional extrapolation procedures. Application of this methodology to {sup 60}Co and {sup 133}Ba radioactive sources is presented and showed results in good agreement with a conventional proportional counter 4{pi}{beta}(PC)-{gamma} coincidence system.

Investigations of Differential Scanning Techniques using Two Radionuclides

Energy Technology Data Exchange (ETDEWEB)

Cottrall, M. F.; French, Rosemary J.; Trott, N. G. [Institute of Cancer Research and Royal Marsden Hospital, Sutton, Surrey (United Kingdom)

1969-01-15

In the development of scanning procedures difficulties sometimes arise because a particular radiopharmaceutical, which is selectively concentrated in an organ of interest, is also widely distributed in neighbouring sites in the body. Investigations have been made of a method which involves the use of a second radioactive substance to label such sites. By means of suitable electrical circuits fitted to a conventional mechanical scanner (Picker Magnascanner III), a direct colour scan of the organ under study can be obtained. Signals from the two radionuclides are distinguished by pulse-height analysis and used to operate the colour shift mechanism. Experimental studies with phantoms and clinical trials are reported. An analysis of the statistical limitations of the technique is given, including a discussion of the most suitable operating conditions for particular pairs of radionuclides. Illustrations include the use of {sup 75}Se selenomethionine and {sup 99m}Tc sulphur colloid or {sup 198}Au colloid in the delineation of the pancreas, and reference is also made to work with {sup 18}F, {sup 99m}Tc, {sup 133m}In and {sup 197}Hg, which are used in various chemical forms to visualize specific types of tumours in vascular surroundings labelled with other suitable tracers. Some discussion of the dosimetry of these procedures is made, since the extent to which the technique can be applied may be limited by the activities which can be administered. However, successful results are being obtained using activities within the range generally accepted for single radionuclide scanning procedures. For example, the pancreas can be successfully visualised using 250 {mu}Ci {sup 75}Se selenomethionine in combination with 1 mCi {sup 99m}TC sulphur colloid. (author)

Monte Carlo dosimetry in simple geometries with interfaces: applications in radiotherapy; Dosimetria Monte Carlo en geometrias simples con interfases: aplicaciones en radioterapia

Energy Technology Data Exchange (ETDEWEB)

Rojas C, E.L

2004-07-01

In the last decade, dosimetry has evolved in an accelerated way due in part, to the development of new techniques and advances in instruments manufactured for several applications in Medical Physics. In order to improve achievements gotten with the use of radiation sources for therapeutic use, a guessed right dosimetry must be done and clinical data must be explained with the aid of investigation and supported with scientific bases. In this context, Monte Carlo (MC) method used to simulate radiation transport in materials, contribute with extensive knowledge and extremely useful information to that objective. MC dosimetry has some advantages over experimental and analytical dosimetry but it also has limitations. Maybe the most important is the computer time required to reach to an acceptable uncertainty level in a complex problem. Though this restrictive factor, a right application of MC simulation of radiation transport is a useful, reliable and versatile instrument for dosimetric calculations. From our point of view, the problem of heterogeneities in the sources or in the treatment targets in radiotherapy is of great importance, and this is the principal question to study aboard in this work. We use the MC simulation code Penelope to calculate some dosimetric quantities.The cases we study involve dosimetric aspects of different geometric distributions of radionuclides where interfaces are evident and must be taken into account. This work is divided in five chapters. In the first chapter we give a succinctly description of MC codes for simulation of the transport of particles in a medium and we describe the code Penelope. In chapter two, we study spherical distributions of radionuclides and the effect that interfaces in the target have in the dose received by the tumor. Specifically we study the application of radiocolloids with {sup 186} Re and {sup 32} P to treat homogeneous and nonhomogeneous cystic craniopharyngioma. Chapter three is dedicated to study plane

Rapid determination of gross alpha and beta activity in seafood utilizing microwave digestion and liquid scintillation counting

International Nuclear Information System (INIS)

Daniel Sas; Jiri Janda; Alena Tokarova

2015-01-01

This paper describes a method for rapid determination of gross alpha and beta activity in seafood using liquid scintillation counting and microwave digestion for fast sample decomposition. The general group of seafood was divided into two groups based on its structure, whether it has shell or not. The selected group of radionuclides was chosen with respect to military significance, radiotoxicity, and possibility of potential misuse. 90 Sr and 239 Pu were selected as model radionuclides. (author)

Design and device construction for plane tables preparation for counter alpha/beta total; Diseno y construccion de dispositivo para preparacion de planchetas para contador alfa/beta total

Energy Technology Data Exchange (ETDEWEB)

Galicia C, F. J.; Monroy G, F., E-mail: fgalicia82@yahoo.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2014-10-15

This work presents the design and assembly of a device for plane tables preparation for quantification alpha/beta total of radioactive waste samples. The determination of the activity index alpha/beta total is used to detect a wide variety of matrices quickly and the concentration of alpha and/or beta emitters of the contained radionuclides in different samples. In particular, the determination of the activity index alpha and beta total of radioactive wastes involves the digestion of samples in aggressive means that will be evaporated to dryness for its quantification. With the purpose of controlling the emission of corrosive gases during the preparation of the plane tables for the quantification of the index alpha and beta total, was designed and built the device in the Radioactive Waste Laboratory that allows to prepare plane tables for proportional counters in a sure and efficient way. The device is constituted by heating equipment, evaporation cylinder and a gases cleaning system. The self-absorption curve got ready starting from the device. (Author)

The GSF secondary standard dosimetry laboratory for photon and beta radiation

International Nuclear Information System (INIS)

Eckerl, H.; Nahrstedt, U.

1986-03-01

A brief outline of the laboratory's tasks and a detailed description of its layout and equipment is given. The laboratory contains a Co-60 irradiation unit, a Cs-137 irradiation unit, a panoramic irradiation unit for different nuclide sources, a 160- and 420 kV X-ray unit, a beta-irradiation unit and a measuring and control room. The calibration laboratory is equipped with reference and field dosemeters. (DG)

EURADOS intercomparisons in external radiation dosimetry: similarities and differences among exercises for whole-body photon, whole-body neutron, extremity, eye-lens and passive area dosemeters

International Nuclear Information System (INIS)

Romero, Ana M.; Grimbergen, Tom; McWhan, Andrew; Stadtmann, Hannes; Fantuzzi, Elena; Clairand, Isabelle; Neumaier, Stefan; Dombrowski, Harald; Figel, Markus

2016-01-01

The European Radiation Dosimetry Group (EURADOS) has been organising dosimetry intercomparisons for many years in response to an identified requirement from individual monitoring services (IMS) for independent performance tests for dosimetry systems. The participation in intercomparisons gives IMS the opportunity to show compliance with their own quality management system, compare results with other participants and develop plans for improving their dosimetry systems. In response to growing demand, EURADOS has increased the number of intercomparisons for external radiation dosimetry. Most of these fit into the programme of self-financing intercomparisons for dosemeters routinely used by IMS. This programme is being coordinated by EURADOS working group 2 (WG2). Up to now, this programme has included four intercomparisons for whole-body dosemeters in photon fields, one for extremity dosemeters in photon and beta fields, and one for whole-body dosemeters in neutron fields. Other EURADOS working groups have organised additional intercomparisons including events in 2014 for eye-lens dosemeters and passive area dosemeters for environmental monitoring. In this paper, the organisation and achievements of these intercomparisons are compared in detail focusing on the similarities and differences in their execution. (authors)

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

International Nuclear Information System (INIS)

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

1995-09-01

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

Methods of separating short half-life radionuclides from a mixture of radionuclides

International Nuclear Information System (INIS)

Bray, L.A.; Ryan, J.L.

1998-01-01

The present invention is a method of obtaining a radionuclide product selected from the group consisting of 223 Ra and 225 Ac, from a radionuclide ''cow'' of 227 Ac or 229 Th respectively. The method comprises the steps of (a) permitting ingrowth of at least one radionuclide daughter from said radionuclide ''cow'' forming an ingrown mixture; (b) insuring that the ingrown mixture is a nitric acid ingrown mixture; (c) passing the nitric acid ingrown mixture through a first nitrate form ion exchange column which permits separating the ''cow'' from at least one radionuclide daughter; (d) insuring that the at least one radionuclide daughter contains the radionuclide product; (e) passing the at least one radionuclide daughter through a second ion exchange column and separating the at least one radionuclide daughter from the radionuclide product and (f) recycling the at least one radionuclide daughter by adding it to the ''cow''. In one embodiment the radionuclide ''cow'' is the 227 Ac, the at least one daughter radionuclide is a 227 Th and the product radionuclide is the 223 Ra and the first nitrate form ion exchange column passes the 227 Ac and retains the 227 Th. In another embodiment the radionuclide ''cow'' is the 229 Th, the at least one daughter radionuclide is a 225 Ra and said product radionuclide is the 225 Ac and the 225 Ac and nitrate form ion exchange column retains the 229 Th and passes the 225 Ra/Ac. 8 figs

Implantation of a new Beta Secondary Standard system at Centro de Desenvolvimento da Tecnologia Nuclear

International Nuclear Information System (INIS)

Reynaldo, Sibele Reis