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Sample records for radionuclide activity measurements

  1. Bilateral Comparison CIEMAT-CENTIS-DMR for radionuclide activity measurements

    International Nuclear Information System (INIS)

    Oropesa Verdecia, P.; Garcia-Torano, E.

    2004-01-01

    We present the results of a bilateral comparison of radionuclide activity measurements between the Radionuclide Metrology Department of the Center of Isotopes of Cuba (CENTIS-DMR), and the Ionising Radiation Metrology Laboratory (LMRI) of the Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas (CIEMAT) of Spain. The aim of the comparison was to establish the comparability of the measurement instruments and methods used to obtain radioactive reference materials of some gamma-emitting nuclides at CENTIS-DMR. The results revealed that there are no statistically significant differences between the data reported by both laboratories. (Author) 7 refs

  2. Activity measurement of 33P and 32P radionuclide mixture

    International Nuclear Information System (INIS)

    Hanker, I.; Kansky, Z.

    1984-01-01

    The possibilities are briefly summed up of measuring mixtures of 33 P and 32 P with special regard to the method of simultaneous determination of both radionuclides in a liquid scintillator. This method was experimentally tested for special detection sensitivity and intended special applications in plant physiology and biochemistry using a dioxane scintillator (SLD-31, Spolana Neratovice, CSSR) and a Packard Tri-Carb 300 C, USA. The method gave erroneous results. The main cause of the errors in measurements of the 33 P and 32 P mixture in the SLD-31 was the adsorption of radionuclides on the inner wall of glass tubes. This phenomenon is not accompanied by changes in the quenching index. However, the effectiveness of measurement dropped and the relative contribution of the spectra of the two radionuclides changed with the time following sample preparation. The said effects were removed by adding 0.4% silicon dioxide (Cab-O-Sil M5, Serva) to the liquid scintillator. (author)

  3. Activity measurement and effective dose modelling of natural radionuclides in building material

    International Nuclear Information System (INIS)

    Maringer, F.J.; Baumgartner, A.; Rechberger, F.; Seidel, C.; Stietka, M.

    2013-01-01

    In this paper the assessment of natural radionuclides' activity concentration in building materials, calibration requirements and related indoor exposure dose models is presented. Particular attention is turned to specific improvements in low-level gamma-ray spectrometry to determine the activity concentration of necessary natural radionuclides in building materials with adequate measurement uncertainties. Different approaches for the modelling of the effective dose indoor due to external radiation resulted from natural radionuclides in building material and results of actual building material assessments are shown. - Highlights: • Dose models for indoor radiation exposure due to natural radionuclides in building materials. • Strategies and methods in radionuclide metrology, activity measurement and dose modelling. • Selection of appropriate parameters in radiation protection standards for building materials. • Scientific-based limitations of indoor exposure due to natural radionuclides in building materials

  4. Activity measurement and effective dose modelling of natural radionuclides in building material.

    Science.gov (United States)

    Maringer, F J; Baumgartner, A; Rechberger, F; Seidel, C; Stietka, M

    2013-11-01

    In this paper the assessment of natural radionuclides' activity concentration in building materials, calibration requirements and related indoor exposure dose models is presented. Particular attention is turned to specific improvements in low-level gamma-ray spectrometry to determine the activity concentration of necessary natural radionuclides in building materials with adequate measurement uncertainties. Different approaches for the modelling of the effective dose indoor due to external radiation resulted from natural radionuclides in building material and results of actual building material assessments are shown. Copyright © 2013 Elsevier Ltd. All rights reserved.

  5. The performance test of NAA laboratory at radionuclide measure with low activity

    International Nuclear Information System (INIS)

    Sri Murniasih; Sukirno

    2016-01-01

    The performance test to measure the I-131 radionuclide activity has been carried out at CAST-NAA laboratory. The purpose of this activity is to know the performance of a laboratory in the testing of low radioactivity sample. The tested sample consists of the form I-131 radionuclide sources shaped thin plastic disk with a certain weight. Evaluation of laboratory performance test results carried out by the organizer of the program test appeal (PTKMR-BATAN). Evaluation results showed that testing of point source of the I-131 radionuclide with comparative method gives a good enough results with errors below 10%. The results of the performance test evaluation are useful as the external quality control to a testing method that is expected in NAA laboratory. (author)

  6. Measurement of highly active samples of ultrashort-lived radionuclides and its problems

    International Nuclear Information System (INIS)

    van der Baan, J.G.; Panek, K.J.

    1985-01-01

    The measurement of highly active eluates obtained from the generators for ultrashort-lived radionuclides poses several problems which are briefly discussed by using the example of the /sup 195m/Hg→/sup 195m/Au generator. For overcoming some of the problems, the construction of a multiple single-channel analyzer that allows high count rates, is described, as well as the counting technique applicable for highly active eluates

  7. Comparisons of activity measurements in nuclear medicine with radionuclide calibrators in the Czech Republic

    International Nuclear Information System (INIS)

    Olsovcova, V.; Dryak, P.

    2002-01-01

    Activity measurements in nuclear medicine using so called 'radionuclide calibrators' or 'activimeters' have been performed for several decades and their reliability has varied. This paper presents comparison of data obtained in annual accuracy checks during the last decade in the Czech Republic, which were carried out by Czech Metrological Institute, Inspectorate for Ionizing Radiation (CMI IIR). Since there is a legal requirement of annual accuracy checks, all of 48 Nuclear Medicine departments in the Czech Republic have participated in the survey. During the last decade the system of accuracy checks has undergone a gradual development. In the initial system one radionuclide sample out of the offer-list was prepared and its activity measured by 4πγ reference chamber. The sample was then sent to the participants, who measured for them an unknown activity and filled out the questionnaire. Later the answers were evaluated in CMI IIR. This system was found unsatisfactory, mostly because of the long time intervals between the measurement and evaluation of results. Therefore, a different system, under which each participant can choose for the accuracy check all the radionuclides from the offered set, was first tried in the year 2000. The offered set is being gradually enlarged, so in 2001 it consisted of four nuclides 99m Tc, 131 I, 67 Ga and 201 Tl. Solution samples (5 ml volume in 10 ml standard serum bottle - the most common in the CR) are prepared in advance from all the nuclides except for 99m Tc and measured with 4πγ chamber to obtain a conventionally true value of activity. In case of 99m Tc is as the true value considered the activity measured with CMI's activimeter whose calibration is periodically compared with 4πγ chamber measurements

  8. Accurate and simple measurement method of complex decay schemes radionuclide activity

    International Nuclear Information System (INIS)

    Legrand, J.; Clement, C.; Bac, C.

    1975-01-01

    A simple method for the measurement of the activity is described. It consists of using a well-type sodium iodide crystal whose efficiency mith monoenergetic photon rays has been computed or measured. For each radionuclide with a complex decay scheme a total efficiency is computed; it is shown that the efficiency is very high, near 100%. The associated incertainty is low, in spite of the important uncertainties on the different parameters used in the computation. The method has been applied to the measurement of the 152 Eu primary reference [fr

  9. 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.)

  10. Measurement of activity concentration of primordial radionuclides in the soil samples of Tiruchirappalli, Tamil Nadu, India

    International Nuclear Information System (INIS)

    Sadiq Bukhari, A.; Saiyad Musthafa, M.; Syed Mohamed, H.E.; Krishnamoorthy, R.; Shahul Hameed, M.M.; Shahul Hameed, P.

    2008-01-01

    Full text: Radioactive minerals such as uranium ( 238 U), thorium ( 232 Th) and potassium ( 40 K) are considered to be Primordial radionuclides which are widely distributed in the earth's crust. Gamma-radiation from these radionuclides represents the main external source of irradiation for the human body. Human beings are exposed outdoors to the natural terrestrial radiation that originates predominantly from the upper 30 cm of the soil. A pilot project was therefore initiated aiming at systematically measuring the terrestrial gamma radiation in Tiruchirappalli city, Tamil Nadu, South India and to establish baseline data on the terrestrial background radiation level determining its contribution to the annual effective dose equivalent to the human population. The natural radioactivity concentrations were studied in soil samples collected from 50 locations in Tiruchirappalli city. The concentration varies significantly over different soil types and the highest radioactivity was measured over soil types of granite origin followed by red soil and alluvial loam. The mean activity concentrations of 232 Th, 238 U and 40 K in soil samples are found to be 81.78 Bq.kg -1 , 32.62 Bq.kg -1 , and 551.35 Bq.kg -1 respectively. The calculated gamma dose from the soil is in the range between 38.86nGy.h -1 and 240.59 nGy.h -1 with a mean value of 89.76 nGy.h -1 . The mean annual effective dose to the population from outdoor terrestrial gamma radiation was estimated to be 0.11mSv.y -1 which is low as compared with the maximum permissible effective dose equivalent of 1mSv.y -1 (ICRP,1991). In the present study it is observed that the major sources of gamma radiation in soils are mainly derived from rocky area with granite basement. (author)

  11. Activity measurements of {sup 18}F and {sup 90}Y with commercial radionuclide calibrators for nuclear medicine in Switzerland

    Energy Technology Data Exchange (ETDEWEB)

    Caffari, Yvan, E-mail: Yvan.Caffari@chuv.c [Institut de Radiophysique Appliquee, Grand-Pre 1, 1007 Lausanne (Switzerland); Spring, Philippe; Bailat, Claude; Nedjadi, Youcef; Bochud, Francois [Institut de Radiophysique Appliquee, Grand-Pre 1, 1007 Lausanne (Switzerland)

    2010-07-15

    The activity of radiopharmaceuticals in nuclear medicine is measured before patient injection with radionuclide calibrators. In Switzerland, the general requirements for quality controls are defined in a federal ordinance and a directive of the Federal Office of Metrology (METAS) which require each instrument to be verified. A set of three gamma sources (Co-57, Cs-137 and Co-60) is used to verify the response of radionuclide calibrators in the gamma energy range of their use. A beta source, a mixture of {sup 90}Sr and {sup 90}Y in secular equilibrium, is used as well. Manufacturers are responsible for the calibration factors. The main goal of the study was to monitor the validity of the calibration factors by using two sources: a {sup 90}Sr/{sup 90}Y source and a {sup 18}F source. The three types of commercial radionuclide calibrators tested do not have a calibration factor for the mixture but only for {sup 90}Y. Activity measurements of a {sup 90}Sr/{sup 90}Y source with the {sup 90}Y calibration factor are performed in order to correct for the extra-contribution of {sup 90}Sr. The value of the correction factor was found to be 1.113 whereas Monte Carlo simulations of the radionuclide calibrators estimate the correction factor to be 1.117. Measurements with {sup 18}F sources in a specific geometry are also performed. Since this radionuclide is widely used in Swiss hospitals equipped with PET and PET-CT, the metrology of the {sup 18}F is very important. The {sup 18}F response normalized to the {sup 137}Cs response shows that the difference with a reference value does not exceed 3% for the three types of radionuclide calibrators.

  12. The measurement of activity in vials and syringes using a radionuclide assay calibrator

    International Nuclear Information System (INIS)

    Hooper, S.A.; Davies, I.H.

    1993-01-01

    To enable accurate measurements of the activity in both vials and syringes, a series of measurements was undertaken to ascertain the changes in response with geometry in nine isotope assay calibrators. From these measurements, two jigs were made for each calibrator to enable (a) optimal measurement of activity in vials and (b) optimal measurement of activity in a variety of syringe sizes. (Author)

  13. Implementation of a metrology programme to provide traceability for radionuclides activity measurements in the CNEN Radiopharmaceuticals Producers Centers

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, Erica A.L. de; Braghirolli, Ana M.S.; Tauhata, Luiz; Gomes, Regio S.; Silva, Carlos J., E-mail: erica@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Delgado, Jose U.; Oliveira, Antonio E.; Iwahara, Akira, E-mail: ealima@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The commercialization and use of radiopharmaceuticals in Brazil are regulated by Agencia Nacional de Vigilancia Sanitaria (ANVISA) which require Good Manufacturing Practices (GMP) certification for Radiopharmaceuticals Producer Centers. Quality Assurance Program should implement the GMP standards to ensure radiopharmaceuticals have requirements quality to proving its efficiency. Several aspects should be controlled within the Quality Assurance Programs, and one of them is the traceability of the Radionuclides Activity Measurement in radiopharmaceuticals doses. The quality assurance of activity measurements is fundamental to maintain both the efficiency of the nuclear medicine procedures and patient and exposed occupationally individuals safety. The radiation doses received by patients, during the nuclear medicine procedures, is estimated according to administered radiopharmaceuticals quantity. Therefore it is very important either the activity measurements performed in radiopharmaceuticals producer centers (RPC) as the measurements performed in nuclear medicine services are traceable to national standards. This paper aims to present an implementation program to provide traceability to radionuclides activity measurements performed in the dose calibrators(well type ionization chambers) used in Radiopharmaceuticals Producer Center placed in different states in Brazil. The proposed program is based on the principles of GM Pand ISO 17025 standards. According to dose calibrator performance, the RPC will be able to provide consistent, safe and effective radioactivity measurement to the nuclear medicine services. (author)

  14. Volume corrections factors in the measurement of 99mTc and 123I activities in radionuclide calibrators

    International Nuclear Information System (INIS)

    Correia, Amanda Ribeiro; Rezende, Eduarda Alexandre; Iwahara, Akira; Oliveira, Antonio Eduardo de; Oliveira, Estela Maria de; Tauhata, Luiz; Chaves, Taina Olivieri

    2012-01-01

    To determine correction factors for the variation in volume of radiopharmaceuticals in containers of different geometries, comparing the influence of such factors on the determination of 99m Tc and 123 I activity with two types of calibrators - one with ionization chamber and another with Geiger-Mueller (G-M) detector -; and to evaluate calibrators performance in the measurement of 99m Tc and 1 '2 3 I activities. Materials and Methods: Eight calibrators, 10R glass vials, 3 and 5 mL plastic syringes and 99m Tc and 123 I solutions were utilized. The correction factors were determined with basis on practical measurements of the variation in the calibrators' response according to the volume of radionuclide solution in the glass vials. The performance was evaluated according to the acceptance criterion of +- 10% accuracy required by the Brazilian standard. Results: The variation of the calibrators' response according to the variation in radionuclide volume was reasonably greater in the calibrator with G-M detector. It was also greater for 123 I than for 99m Tc. Conclusion: The results confirm that the calibrators' response depends on the radionuclide volume contained in the vials. Such dependence is more critical for the calibrators equipped with G-M detector and for 123 I as compared with 99m Tc. (author)

  15. Measurement of radionuclide activities of uranium-238 series in soil samples by gamma spectrometry: case of Vinaninkarena

    International Nuclear Information System (INIS)

    Randrianantenaina, F.R.

    2017-01-01

    The aim of this work is to determine the activity level of radionuclides of uranium-238 series. Eight soil samples are collected at Rural Commune of Vinaninkarena. After obtaining secular equilibrium, these samples have been measured using gamma spectrometry system in the Nuclear Analyses and Techniques Department of INSTN-Madagascar, with HPGe detector (30 % relative efficiency) and a Genie 2000 software. Activities obtained vary from (78±2)Bq.kg -1 to (49 231 ± 415)Bq.kg -1 . Among these eight samples, three activity levels are shown. Low activity is an activity which has value lower or equal to (89±3)Bq.kg -1 . Average activity is an activity which has value between (186± 1)Bq.kg -1 and (1049 ±7)Bq.kg -1 . And high activity is an activity which has value higher or equal to (14501±209)Bq.kg -1 . According to UNSCEAR 2000, these value are all higher than the world average value which is 35 Bq.kg -1 .It is due to the localities of sampling points. The variation of the activity level depends on radionuclide concentration of uranium-238 series in the soil. [fr

  16. Measurement of radionuclides in waste packages

    Science.gov (United States)

    Brodzinski, R.L.; Perkins, R.W.; Rieck, H.G.; Wogman, N.A.

    1984-09-12

    A method is described for non-destructively assaying the radionuclide content of solid waste in a sealed container by analysis of the waste's gamma-ray spectrum and neutron emissions. Some radionuclides are measured by characteristic photopeaks in the gamma-ray spectrum; transuranic nuclides are measured by neutron emission rate; other radionuclides are measured by correlation with those already measured.

  17. Calibration of a 4π-γ well-type ionization chamber system for measuring of the radionuclides activity

    International Nuclear Information System (INIS)

    Dias, M.S.

    1978-01-01

    The calibration of a 4π well-type ionization Chamber System installed at the Laboratorio de Metrologia Nuclear, of the Instituto de Energia Atomica of Sao Paulo used for of the activity determination of radioactive solutions is descrided. The determination can be performed by two methods: 1) Direct Method, comparing the ionization Chamber response for solutions of unknown activity against that obtained with a solution which is standardized by the Absolute 4πβγ Coincidence Method. By this method the following radionuclides are standardized: 241 Am, 139 Ce, 198 Au, 22 Na, 134 Cs, 54 Mn, 60 Co, 42 K, 24 Na. In this case, the accuracy achieved is about 0.2 to 0,4%. 2) Indirect Method, by means of curves of relative beta or gama efficiency, which were determined in this work. This method can be applied for those radionuclides not included in the direct method. In this case, the accuracy depends on the gama energy range of the curves and on the accuracy of the absolute gama intensities, taken from the literature. In general the uncertainty is greater than the direct method, but values of 0,2% can be achieved in favourable cases. The upper and lower limits of Activity that can be measured depend on the radionuclide. These limits are from a few micro-curies to many mili-curies, which are satisfactory for most purposes. The sample preparation is simple and the time spent in the measurement is, in general, restricted to a few minutes. These are some of the advantages of this ionization Chamber System in comparison with other systems [pt

  18. Assessment of Intercomparison of Radionuclide Activity Measurement between P3KRBiN-BATAN and NMIJ/AIST-JAPAN

    International Nuclear Information System (INIS)

    Nazaroh; Pujadi; Hermawan Candra; Ermi Juita; Holnisar

    2003-01-01

    On every radionuclide activity measurements or any measurements always contain uncertainties. The uncertainties come from standard source, equipment to be used, condition of measurements (background) and sample (measurement). Those elements should be taken into account in the measurement result evaluation. To know the result of activity measurement was in a good agreement or not, it can be done by intercomparison. A good result of a measurement if it was nearly with the result of international/primary laboratories measurements such as System Internationale de Reference (SIR)-Franch, National Metrology Institute of Japan- Advanced Industrial Science and Technology (NMIJ/AIST or Physikalisch Technische Bundes-anstalt (PTB) and the absolute value of E n should be less than 1. The result of intercomparison between Center for Research and Development of Radiation Safety and Nuclear Biomedicine (P3KRBiN) -BATAN and NMIJ/AIST were in a good agreement for activity measurement of 125 I (E n =0.193), 58 Co(E n =0.503), 88 Y(E n =0.035) and 59 Fe(E n =0.632), by using gamma spectrometry counting system (HPGe detector) and 166m Ho(E n =0.492), by using Merlin Gerin Ionization chamber. (author)

  19. Study of a 4πβ-γ coincidence system for absolute radionuclide activity measurement using plastic scintillators

    International Nuclear Information System (INIS)

    Piuvezam Filho, Helio

    2007-01-01

    The present work was intended to study a coincidence system 4π(PS)β-γ for absolute activity measurement using plastic scintillators in 4π 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 4π(PS)β-γ 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)

  20. The CdZnTe Detector with Slit Collimator for Measure Distribution of the Specific Activity Radionuclide in the Ground

    Science.gov (United States)

    Stepanov, V. E.; Volkovich, A. G.; Potapov, V. N.; Semin, I. A.; Stepanov, A. V.; Simirskii, Iu. N.

    2018-01-01

    From 2011 in the NRC "Kurchatov Institute" carry out the dismantling of the MR multiloop research reactor. Now the reactor and all technological equipment in the premises of the reactor were dismantled. Now the measurements of radioactive contamination in the reactor premises are made. The most contaminated parts of premises - floor and the ground beneath it. To measure the distribution of specific activity in the ground the CdZnTe detector (volume 500MM3) was used. Detector placed in a lead shielding with a slit collimation hole. The upper part of shielding is made movable to close and open the slit of the collimator. At each point two measurements carried out: with open and closed collimator. The software for determination specific activity of radionuclides in ground was developed. The mathematical model of spectrometric system based on the Monte-Carlo method. Measurements of specific activity of ground were made. Using the results of measurements the thickness of the removed layer of ground and the amount of radioactive waste were calculated.

  1. Bilateral Comparison CIEMAT-CENTIS-DMR for radionuclide activity measurements; Comparacion Bilateral CIEMAT-CENTIS-DMR de la Medida de Actividad de Radionucleidos

    Energy Technology Data Exchange (ETDEWEB)

    Oropesa Verdecia, P.; Garcia-Torano, E.

    2004-07-01

    We present the results of a bilateral comparison of radionuclide activity measurements between the Radionuclide Metrology Department of the Center of Isotopes of Cuba (CENTIS-DMR), and the Ionising Radiation Metrology Laboratory (LMRI) of the Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas (CIEMAT) of Spain. The aim of the comparison was to establish the comparability of the measurement instruments and methods used to obtain radioactive reference materials of some gamma-emitting nuclides at CENTIS-DMR. The results revealed that there are no statistically significant differences between the data reported by both laboratories. (Author) 7 refs.

  2. Automation of the ANSTO working standard of measurement for the activity of radionuclides

    International Nuclear Information System (INIS)

    Buckman, S.M.

    1990-08-01

    The ANSTO working standard ion chamber is used routinely for the standardisation of a range of gamma emitting radio-isotopes. The ion chamber has recently been automated by replacing the AAEC type 292 Recycling Discriminator, timer module and model 43 teletype printer with the HP86B computer, HP-59501B voltage programmer and HP-6181C current source. The program 'MEASION', running on the Deltacom IBM AT clone, calculates the radioactivity, with full error statements, from the ion chamber measurements. Each of these programs is listed and discussed. 13 refs., 5 figs., tabs

  3. Determination of the germanium detector efficiency for measurements of the radionuclide activity contained in a radioactive waste drum

    International Nuclear Information System (INIS)

    Rodenas, J.; Gallardo, S.; Ballester, S.; Hoyler, F.

    2006-01-01

    One of the features in the characterization of a drum containing radioactive wastes is to verify the activity of radionuclides contained in the drum. An H.P. Ge detector can be used for this measurement. However, it is necessary to perform an efficiency calibration for all geometries involved. In the framework of a joint project between the Departamento de Ingenieria Quimica y Nuclear (Universidad Politecnica de Valencia, Spain) and the Fachbereich Angewandte Naturwissenschaften und Technik (Fachhochschule Aachen, Abteilung Julich, Germany), different configurations for a drum containing radioactive sources have been implemented in the laboratory. A cylindrical drum of 850 mm height, a diameter equal to 560 mm and 3 mm of steel thickness has been used in the experimental measurements. The drum contains a clay ceramic matrix whose chemical composition is 55% SiO 2 , 40% of Al 2 O 3 and 5% of TiO 2 . Several vertical PVC tubes having a diameter of 30 mm are inserted in the drum at different distances from the central axis. In the experiment, a pack of point sources with 133 Ba, 60 Co and 137 Cs is introduced into each one of the tubes. A ring-shape distributed source is generated by rotating the drum around its axis during the measurement. The detector efficiency is determined experimentally for these configurations. On the other hand, a Monte Carlo model, using the M.C.N.P. code, has been developed to simulate the drum, the clay matrix and the PVC tubes. The effect of the drum spinning has been reproduced simulating a ring source with different diameters. The model also includes detailed detector geometry. Using this Monte Carlo model, the detector efficiency is calculated for each configuration implemented in the laboratory. Comparison of results from Monte Carlo simulation and experimental measurements should permit the validation of the M.C.N.P. model. Consequently it will be possible to obtain efficiency curves without experimental measurements. Therefore, these

  4. High resolution simultaneous measurements of airborne radionuclides

    International Nuclear Information System (INIS)

    Abe, T.; Yamaguchi, Y.; Tanaka, K.; Komura, K.

    2006-01-01

    High resolution (2-3 hrs) simultaneous measurements of airborne radionuclides, 212 Pb, 210 Pb and 7 Be, have been performed by using extremely low background Ge detectors at Ogoya Underground Laboratory. We have measured above radionuclides at three monitoring points viz, 1) Low Level Radioactivity Laboratory (LLRL) Kanazawa University, 2) Shishiku Plateau (640 m MSL) located about 8 km from LLRL to investigate vertical difference of activity levels, and 3) Hegura Island (10 m MSL) located about 50 km from Noto Peninsula in the Sea of Japan to evaluate the influences of Asian continent or mainland of Japan on the variation to the activity levels. Variations of short-lived 212 Pb concentration showed noticeable time lags between at LLRL and at Shishiku Plateau. These time lags might be caused by change of height of a planetary boundary layer. On the contrary, variations of long-lived 210 Pb and 7 Be showed simultaneity at three locations because of homogeneity of these concentrations all over the area. (author)

  5. Interpretation of biological-rate coefficients derived from radionuclide content, radionuclide concentration and specific activity experiments

    International Nuclear Information System (INIS)

    Vanderploeg, H.A.; Booth, R.S.

    1976-01-01

    Rigorous expressions are derived for the biological-rate coefficients (BRCs) determined from time-dependent measurements of three different dependent variables of radionuclide tracer experiments. These variables, which apply to a single organism, are radionuclide content, radionuclide concentration and specific activity. The BRCs derived from these variables have different mathematical expressions and, for high growth rates, their numerical values can be quite different. The precise mathematical expressions for the BRCs are presented here to aid modelers in selecting the correct parameters for their models and to aid experiments in interpreting their results. The usefulness of these three variables in quantifying elemental uptakes and losses by organisms is discussed. (U.K.)

  6. Estimation of the skeletal burden of bone-seeking radionuclides from in vivo scintillation measurements of their content in the skull: contribution from radionuclides in the thoracic skeleton to in vivo measurement of activity in the lung

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    After the initiation of NaI(Tl), spectrometric methods for detecting photon-emitting radionuclides in man, it became evident that the high background rates in the low energy regions precluded in vivo measurement of many bone-seeking nuclides. To meet these needs a dual crystal, low energy sensitive NaI(Tl)-CsI(Tl) detector system was developed. To date this system, in combination with more routine bioassays, remains the optimum methodology for the determination of internal exposure to low energy, photon-emitting radionuclides. Since most occupational exposures occur by inhalation, internal deposits must be quantitated with these detectors placed over the lung area. Since many of the alpha-emitting nuclides are bone-seekers, the contribution of material which has been transported from the lung and deposited in the skeleton must be accounted for

  7. Radionuclide Activity Concentrations in Spas of Argentina

    International Nuclear Information System (INIS)

    Gnoni, G.; Czerniczyniec, M.; Palacios, M.

    2011-01-01

    Geothermal waters have been used on a large scale for bathing, drinking and medical purposes. These waters often have a very high mineral content because solubility increases with temperature. Ground waters are in close contact with soil and rocks containing radium. Once formed by decay from radium, radon gas (Rn-222) may diffuse through rocks pores and geological discontinuities and may dissolve in these waters. Radon and other natural radionuclides are transported to the surface where radon can easily diffuse into the atmosphere. Then it may be possible to find out significant radon levels at places like geothermal spas. In this work the most important natural radionuclide activity concentrations in different thermal spas of Argentina were measured to characterize waters and to evaluate the exposure of workers and members of the public. Three passive methods were used to measure radon in air. One of them is an screening method based on the radon adsorption on activated charcoal. The other two methods are time integrated ones, CR-39 or Makrofol tracks detectors, which can be exposed between two and three months. To characterize waters other natural radionuclides have been also measured. Uranium concentration was measured by fluorimetry. Ra-226 and Pb-210 measurements were performed by radiochemical methods and liquid scintillation. The results obtained were compared with the guidelines values recommended by WHO and EPA for drinking waters and, in the case of radon in air, the results were compared with values established by BSS-115. In order to assess worker doses, the higher value measured for radon in air and real scenario data were taken into account. Moreover, in situ dose rate measurements were also performed and then compared with natural background values. In relation with water characterization, almost all values obtained for the geothermal waters analyzed were below the corresponding guidance levels. Taking into account the highest value measured of radon

  8. Comparison of activity measurements of 131I and 99mTc radionuclides administered in nuclear medicine services of Porto Alegre

    International Nuclear Information System (INIS)

    Alabarse, Frederico Gil.; Santos, Carlos Eduardo Lima dos

    2005-01-01

    A programme for the comparison of activity measurements of radionuclides administered to patients in Nuclear Medicine Services, for the purpose of diagnosis or therapy, is being conducted under the coordination of the Radioprotection and Dosimetry Institute of the Brazilian Nuclear Energy Commission, IRD/CNEN. In the present work, measurements of the activity of samples of 131 I and 99 mTc were conducted in the dose calibrators of the Nuclear Medicine Services of the city of Porto Alegre, in the period from June to September 2004. The results were analysed to evaluate the compliance with the Brazilian regulation and were also compared to data available in the literature for the cities of Rio de Janeiro and Brasilia. The performance of the activity meters in Porto Alegre is shown to be very good, which contributes to the radiological protection of patients submitted to diagnosis or therapy with radiopharmaceuticals. (author)

  9. Radionuclides incorporation in activated natural nanotubes

    International Nuclear Information System (INIS)

    Silva, Jose Parra

    2016-01-01

    Natural palygorskite nanotubes show suitable physical and chemical properties and characteristics to be use as potential nanosorbent and immobilization matrix for the concentration and solidification of radionuclides present in nuclear wastes. In the development process of materials with sorption properties for the incorporation and subsequent immobilization of radionuclides, the most important steps are related with the generation of active sites simultaneously to the increase of the specific surface area and suitable heat treatment to producing the structural folding. This study evaluated the determining parameters and conditions for the activation process of the natural palygorskite nanotubes aiming at the sorption of radionuclides in the nanotubes structure and subsequent evaluation of the parameters involve in the structural folding by heat treatments. The optimized results about the maximum sorption capacity of nickel in activated natural nanotubes show that these structures are apt and suitable for incorporation of radionuclides similar to nickel. By this study is verified that the optimization of the acid activation process is fundamental to improve the sorption capacities for specifics radionuclides by activated natural nanotubes. Acid activation condition optimized maintaining structural integrity was able to remove around 33.3 wt.% of magnesium cations, equivalent to 6.30·10 -4 g·mol -1 , increasing in 42.8% the specific surface area and incorporating the same molar concentration of nickel present in the liquid radioactive waste at 80 min. (author)

  10. Measurements for modeling radionuclide transfer in the aquatic environment

    International Nuclear Information System (INIS)

    Kahn, B.

    1976-01-01

    Analytical methods for measuring radionuclides in the aquatic environment are discussed for samples of fresh water and seawater, fish and shellfish, biota such as algae, plankton, seaweed, and aquatic plants, and sediment. Consideration is given to radionuclide collection and concentration, sample preservation, radiochemical and instrumental analysis, and quality assurance. Major problems are the very low environmental levels of the radionuclides of interest, simultaneous occurrence of radionuclides in several chemical and physical forms and the numerous factors that affect radionuclide levels in and transfers among media. Some radionuclides of importance in liquid effluents from nuclear power stations are listed, and sources of radiochemical analytical methods are recommended

  11. Coincidence method for determination of radionuclides activities

    International Nuclear Information System (INIS)

    Andrukhovich, S.K.; Berestov, A.V.; Rudak, E.A.

    2004-01-01

    The radon and radium activity measurements using six-crystal gamma-gamma coincidence, 4 -spectrometer PRIPJAT and radioactivity measurements in different samples of meat and vegetation by 32-crystal spectrometer ARGUS, are described. Radiation detector with 4 -geometry provides higher efficiency, and therefore shorter counting time than a detector without such geometry. However, its application is limited by the fact that obtained spectrum contains summing peaks of all γ-quanta registered in coincidence. Multiparameter information on coincident photon emission can be obtained only by a detection system where the 4 -geometry is made by many detectors, such are both the PRIPJAT and the ARGUS - γ-coincidence spectrometer of the Crystal Ball type in the Institute of Physics, Minsk [1,2]. There are other characteristics, as background conditions, energy and time resolution, makes it ve suitable for investigation of rare decays and interactions, cascade transitions, k intensity radiations etc. We are developing a method of 2 26R a and 2 26 Rn measurement by a multidetector 4 -spectrometer. The method is based on coincidence counting of γ-rays from two step cascade transitions that follow - decay of 2 14 Bi. Its application to the PRIPL spectrometer, which has 6 Nal(Tl) detectors, is presented here, as well as the method of the determination of radionuclide activities based on the registration of the cascades intensity of γ-rays of different multiplicity using ARGUS

  12. Critical evaluation of the Laboratory of Radionuclide Metrology results of the Institute of Radiation Protection and Dosimetry - IRD in the international key comparisons of activity measurement of radioactive solutions

    International Nuclear Information System (INIS)

    Iwahara, A.; Tauhata, L.; Silva, C.J. da

    2014-01-01

    The Radionuclide Metrology Laboratory (LMR) of LNMRI/IRD has been participating since 1984, in international key-comparisons of activity measurement of radioactive sources organized by BIPM and the Regional Metrology Organizations as EURAMET and APMP. The measured quantity is the activity of a radioactive solution, in becquerel (Bq), containing the radionuclide involved and the of measurement methods used are 4αβ-γ coincidence/anticoincidence, coincidence sum-peak and liquid scintillation. In this paper a summary of the methods used and a performance analysis of the results obtained are presented. (author)

  13. Direct measurement of γ-emitting radionuclides in waste drum

    International Nuclear Information System (INIS)

    Ma Ruwei; Mao Yong; Zhang Xiuzhen; Xia Xiaobin; Guo Caiping; Han Yueqin

    1993-01-01

    The low-level rad waste produced from nuclear power plant, nuclear facilities, and in the process of their decommissioning is stored in waste depository. For the safety of transport and storage of these wastes, some test must be done. One of them is to analyse the kinds and activities of radionuclides in each waste drum. Segmented scanning gamma spectrum analysis can be used for direct measurement of gamma-emitting radionuclides in drum. Gamma emitters such as Co-60, Cs-137, Ra-226 can be measured directly from outside of drum. A method and system for direct measuring gamma emitters in waste drum are described, and measuring apparatus and measurement results as well

  14. Radionuclide measurements using resonantly enhanced collisional ionization

    International Nuclear Information System (INIS)

    Whitaker, T.J.; Bushaw, B.A.; Gerke, G.K.

    1987-01-01

    This report describes development of a laser-enhanced collisional ionization method for direct radionuclide measurements that are independent of radioactive decay. The technique uses two nitrogen-laser-pumped dye lasers to selectively excite the target isotope to an electronic state near the ionization threshold. The excited actinide atoms then undergo collisions with a buffer gas and are efficiently ionized. The resulting ions can be detected by conventional methods. The attributes of this approach include highly sensitive isotope analysis with relatively inexpensive lasers and a simple vacuum system. 9 refs., 3 figs

  15. Activation analysis with neutron generators using short-lived radionuclides

    International Nuclear Information System (INIS)

    Salma, I.

    1993-01-01

    The short half-life involves a number of important differences in production, transportation and measurement of radionuclides, and in counting statistics as compared with those in traditional activation analysis. Experiments were performed to investigate the analytical possibilities and prospective utilization of short-lived radionuclides produced by 14-MeV neutron irradiation. A rapid pneumatic transfer system for use with neutron generators was installed and applied for detecting radionuclides with a half-life from 300 ms to 30 s. The transport time for samples with a total mass of 1-4 g is between 130 and 160 ms for pressurized air of 0.1-0.4 MPa. 11 elements were studied by the conventional activation method using both a typical pneumatic transport system (run time 3 s) and the fast pneumatic transport facility. The effect of the cyclic activation technique on the elemental sensitivities was also investigated. (orig.)

  16. Bayesian statistics in radionuclide metrology: measurement of a decaying source

    International Nuclear Information System (INIS)

    Bochud, F. O.; Bailat, C.J.; Laedermann, J.P.

    2007-01-01

    The most intuitive way of defining a probability is perhaps through the frequency at which it appears when a large number of trials are realized in identical conditions. The probability derived from the obtained histogram characterizes the so-called frequentist or conventional statistical approach. In this sense, probability is defined as a physical property of the observed system. By contrast, in Bayesian statistics, a probability is not a physical property or a directly observable quantity, but a degree of belief or an element of inference. The goal of this paper is to show how Bayesian statistics can be used in radionuclide metrology and what its advantages and disadvantages are compared with conventional statistics. This is performed through the example of an yttrium-90 source typically encountered in environmental surveillance measurement. Because of the very low activity of this kind of source and the small half-life of the radionuclide, this measurement takes several days, during which the source decays significantly. Several methods are proposed to compute simultaneously the number of unstable nuclei at a given reference time, the decay constant and the background. Asymptotically, all approaches give the same result. However, Bayesian statistics produces coherent estimates and confidence intervals in a much smaller number of measurements. Apart from the conceptual understanding of statistics, the main difficulty that could deter radionuclide metrologists from using Bayesian statistics is the complexity of the computation. (authors)

  17. In vivo measurements of bone-seeking radionuclides. Progress report, September 1, 1977--February 28, 1979

    International Nuclear Information System (INIS)

    Cohen, N.

    1978-01-01

    Progress is reported on the following research projects: estimation of the skeletal burden of bone-seeking radionuclides from in vivo scintillation measurements of their content in the skull; contribution from radionuclides in the thoracic skeleton to in vivo measurements of activity in the lung; design and optimization characterictics of in vivo detection system; development of a calibration phantom structure for determining activity deposited in the thoracic skeleton; computer assisted in vivo measurements of internally deposited radionuclides using dual-crystal scintillation detectors; low energy, photon-emitting nuclides; reference spectra library; and in vivo measurements of exposed individuals

  18. In vivo measurements of bone-seeking radionuclides. Progress report, September 1, 1977--February 28, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, N.

    1978-11-01

    Progress is reported on the following research projects: estimation of the skeletal burden of bone-seeking radionuclides from in vivo scintillation measurements of their content in the skull; contribution from radionuclides in the thoracic skeleton to in vivo measurements of activity in the lung; design and optimization characterictics of in vivo detection system; development of a calibration phantom structure for determining activity deposited in the thoracic skeleton; computer assisted in vivo measurements of internally deposited radionuclides using dual-crystal scintillation detectors; low energy, photon-emitting nuclides; reference spectra library; and in vivo measurements of exposed individuals. (HLW)

  19. Accreditation - Its relevance for laboratories measuring radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Palsson, S E [Icelandic Radiation Protection Inst. (Iceland)

    2001-11-01

    Accreditation is an internationally recognised way for laboratories to demonstrate their competence. Obtaining and maintaining accreditation is, however, a costly and time-consuming procedure. The benefits of accreditation also depend on the role of the laboratory. Accreditation may be of limited relevance for a research laboratory, but essential for a laboratory associated with a national authority and e.g. issuing certificates. This report describes work done within the NKSBOK-1.1 sub-project on introducing accreditation to Nordic laboratories measuring radionuclides. Initially the focus was on the new standard ISO/IEC 17025, which was just in a draft form at the time, but which provides now a new framework for accreditation of laboratories. Later the focus was widened to include a general introduction to accreditation and providing through seminars a forum for exchanging views on the experience laboratories have had in this field. Copies of overheads from the last such seminar are included in the appendix to this report. (au)

  20. Direct methods for measuring radionuclides in the human body

    International Nuclear Information System (INIS)

    1996-01-01

    Occupational exposure leading to intakes of internally incorporated radionuclides can occur as a result of various activities. This includes work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve exposure to enhanced levels of naturally occurring radionuclides. In 1987 the IAEA published a Safety Guide on basic principles for occupational radiation monitoring which set forth principles and objectives of a strategy for monitoring exposures of workers. Since drafting of the present Safety Practice commenced, the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS) have been issued. On the basis of the principles laid down in the BSS, the 1987 Safety Guide is also being revised, and recommendations on the assessment of the occupational intake of radioactive materials are to be added. The present Safety Practice, which deals with direct measurement of radionuclides in the human body, is the first to be published in this area. Refs, figs, tabs

  1. Activity measurements of the radionuclide {sup 111}In for the LNE-LNHB, France in the ongoing comparison BIPM.RI(II)-K1.In-111

    Energy Technology Data Exchange (ETDEWEB)

    Michotte, C.; Ratel, G.; Courte, S. [Bureau International des Poids et Mesures (BIPM), Pavillon de Breteuil, 92 - Sevres (France); Verdeau, E.; Amiot, M.N. [Laboratoire national de metrologie et d' essais-Laboratoire National Henri Becquerel (LNE-LNHB), 91 - Gif-sur-Yvette (France)

    2010-10-15

    In 2006, the Laboratoire national de metrologie et d'essais - Laboratoire national Henri Becquerel (LNE-LNHB) submitted a sample of known activity of {sup 111}In to the International Reference System (SIR). The value of the activity submitted was about 14 MBq. This provides a new result for France in the matrix of degrees of equivalence in the key comparison database that enables them to maintain their degrees of equivalence for this radionuclide. The key comparison reference value has been re-evaluated and the comparison, identifier BIPM.RI(II)-K1.In-111, now contains five valid results. (authors)

  2. Measurement of anthropogenic radionuclides in the atmosphere with a radionuclide monitoring network for nuclear tests

    International Nuclear Information System (INIS)

    Yonezawa, Chushiro; Yamamoto, Yoichi

    2011-01-01

    A worldwide radionuclide monitoring network for nuclear tests has detected the anthropogenic radioactive materials released in the atmosphere due to the accident of the Fukushima Daiichi Nuclear Power Plant impacted by the Great East Japan Earthquake on March 11, 2011. After four months have passed since the accident occurred, most overseas stations do not detect the radionuclides of Fukushima origin any more. The Takasaki station in Japan, however, is still detecting them every day. This paper describes radionuclide monitoring stations and the network of them as part of the International Monitoring System (IMS) in the Comprehensive Nuclear Test Ban Treaty (CTBT), as well as the measurement results of radionuclide particulates and radioactive isotopes of xenon released from the Fukushima Daiichi Nuclear Power Plant with the monitoring network. (J.P.N.)

  3. Analysis of 137Cs radionuclides activities in Cs-zeolite using gamma spectrometry

    International Nuclear Information System (INIS)

    Noviarty; Ginting, Aslina Br; Anggraini, Dian; Rosika K

    2013-01-01

    137 Cs Radionuclide activity analysis has been carried out. The objective is to determine the activity of the 137 Cs radionuclide in Cs-zeolite are packaged in the form of point source. Analysis of 137 Cs Radionuclide activities in Cs zeolite samples was determined by measuring intensity of the isotope 137 Cs gamma energy at 661.7 keV use-y spectrometer. Before measurement the sample, was first carried out measurements of 137 Cs radionuclide in certified point standards from Amersham, to determine the efficiency value. Result the standard sample measurement obtained the efficiency value of 43.98%. Efficiency values obtained are used in the calculation of sample activity. On the measurement of the intensity of the sample obtained results dose rate 196.4537 cps with a standard deviation of 0.5274. By using standard measurement efficiency values obtained by the calculation of the average activity of the radionuclide 137 Cs in Cs-zeolite 524.9082 Bq. Deviation measurements were below 5% (0.27% ) so that the analysis of the activity of radionuclide 137 Cs in Cs-zeolite samples using gamma spectrometer can be accepted with a 95% confidence level. (author)

  4. Resonantly enhanced collisional ionization measurements of radionuclides

    International Nuclear Information System (INIS)

    Whitaker, T.J.; Bushaw, B.A.; Gerke, G.K.

    1986-01-01

    The authors developed a new laser technique to analyze for radionuclides at extremely low levels. The technique, called resonantly enhanced collisional ionization (RECI), uses two nitrogen-laser pumped dye lasers to excite the target isotope to a high-energy Rydberg state. Atoms in these Rydberg states (within a few hundred wavenumbers in energy from the ionization threshold) efficiently ionize upon colliding with an inert gas and the ions can be detected by conventional means. The principal advantage of resonantly-enhanced collisional ionization is the extreme sensitivity coupled with its relative simplicity and low cost. Actinides typically have an ionization potential of about 6eV (uranium I.P. = 6.2 eV, plutonium I.P. = 5.7 eV). Two-step laser excitation to a state just below threshold requires wavelengths in the blue region of the visible spectrum. They showed that when both steps in the excitation process are resonant steps, relatively low-power lasers can populate the Rydberg state with almost unit efficiency. This is because the resonant excitations have much larger cross-sections than do photoionization processes. They also demonstrated that a few torr of a buffer gas will cause most of the excited-state atoms to be ionized

  5. Rapid methods for measuring radionuclides in food and environmental samples

    International Nuclear Information System (INIS)

    Perkins, Richard W.

    1995-01-01

    The application of ICP/mass spectrometry for the isotopic analysis of environmental samples, the use of drum assayers for measuring radionuclides in food and a rapid procedure for the measurement of the transuranic elements and thorium, performed at the Pacific Northwest Laboratory are discussed

  6. Direct methods for radionuclides measurement in water environment

    International Nuclear Information System (INIS)

    Chernyaev, A.; Gaponov, I.; Kazennov, A.

    2004-01-01

    The paper is devoted to the direct method of anthropogenic radionuclide measurement in the water environment. Opportunities of application of submersible gamma-spectrometers for in situ underwater measurements of gamma-radiating nuclides and also the direct method for 90 Sr detection are considered

  7. An overview of Fukushima radionuclides measured in the northern hemisphere

    International Nuclear Information System (INIS)

    Thakur, P.; Ballard, S.; Nelson, R.

    2013-01-01

    The Great East Japan Earthquake and tsunami on March 11, 2011 resulted in the tragic accident at the Fukushima Nuclear Power Plant (NPP) and subsequently uncontrolled release of radioactive contaminants into the atmosphere. This review article attempts to compile and interpret data collected by various national and international monitoring networks in response to the Fukushima releases across the northern hemisphere. The majority of the releases occurred during the period March 12–22 with a maximum release phase from March 14–17, 2011. The radioactivity released was dominated by volatile fission products including isotopes of the noble gases (xenon and krypton), iodine, cesium, and tellurium. The radioactive gases and particles released in the accident were dispersed over the middle latitudes of the entire northern hemisphere and for the first time also measured in the southern Hemisphere. Isotopes of iodine and cesium were detected in air, water, milk and food samples collected across the entire northern hemisphere. Elevated levels of fission products were detected from March to May 2011 at many locations over the northern hemisphere. This article focuses on the most prevalent cesium and iodine isotopes, but other secondary isotopes are also discussed. Spatial and temporal patterns and differences are contrasted. The activity ratios of 131 I/ 137 Cs and 134 Cs/ 137 Cs measured at several locations are evaluated to gain an insight into the fuel burn-up, the inventory of radionuclides in the reactor and the isotopic signature of the accident. It is important to note that all of the radiation levels detected outside of Japan have been very low and are well below any level of public and environmental hazard. - Graphical abstract: The trace levels of radioactivity in air, water, and milk samples collected across the northern hemisphere between March–May, 2011 from the damaged Fukushima Daiichi nuclear power plant, Japan are discussed. Highlights: • We report

  8. An overview of Fukushima radionuclides measured in the northern hemisphere

    Energy Technology Data Exchange (ETDEWEB)

    Thakur, P., E-mail: pthakur@cemrc.org [Carlsbad Environmental Monitoring and Research Center, 1400 University Drive, Carlsbad, NM 88220 (United States); Ballard, S. [Carlsbad Environmental Monitoring and Research Center, 1400 University Drive, Carlsbad, NM 88220 (United States); Nelson, R. [Department of Energy, Carlsbad Field Office, 4021, National Parks Hwy, Carlsbad, NM 88220 (United States)

    2013-08-01

    The Great East Japan Earthquake and tsunami on March 11, 2011 resulted in the tragic accident at the Fukushima Nuclear Power Plant (NPP) and subsequently uncontrolled release of radioactive contaminants into the atmosphere. This review article attempts to compile and interpret data collected by various national and international monitoring networks in response to the Fukushima releases across the northern hemisphere. The majority of the releases occurred during the period March 12–22 with a maximum release phase from March 14–17, 2011. The radioactivity released was dominated by volatile fission products including isotopes of the noble gases (xenon and krypton), iodine, cesium, and tellurium. The radioactive gases and particles released in the accident were dispersed over the middle latitudes of the entire northern hemisphere and for the first time also measured in the southern Hemisphere. Isotopes of iodine and cesium were detected in air, water, milk and food samples collected across the entire northern hemisphere. Elevated levels of fission products were detected from March to May 2011 at many locations over the northern hemisphere. This article focuses on the most prevalent cesium and iodine isotopes, but other secondary isotopes are also discussed. Spatial and temporal patterns and differences are contrasted. The activity ratios of {sup 131}I/{sup 137}Cs and {sup 134}Cs/{sup 137}Cs measured at several locations are evaluated to gain an insight into the fuel burn-up, the inventory of radionuclides in the reactor and the isotopic signature of the accident. It is important to note that all of the radiation levels detected outside of Japan have been very low and are well below any level of public and environmental hazard. - Graphical abstract: The trace levels of radioactivity in air, water, and milk samples collected across the northern hemisphere between March–May, 2011 from the damaged Fukushima Daiichi nuclear power plant, Japan are discussed. Highlights

  9. Sampling and measurement of long-lived radionuclides in environmental samples

    International Nuclear Information System (INIS)

    Brauer, F.P.; Goles, R.W.; Kaye, J.H.; Rieck, H.G. Jr.

    1977-01-01

    The volatile and semivolatile long-lived man-made radionuclides 3 H, 14 C, 79 Se, 85 Kr, 99 Tc, 129 I, 135 Cs, and 137 Cs are of concern in operation of nuclear facilities because they are difficult and expensive to contain and once emitted to the environment they become permanent ecological constituents with both local and global distributions. Species-selective sampling and analytical methods (radiochemical, neutron activation, and mass spectrometric) have been developed for many of these nuclides with sensitivities well below those required for radiation protection. These sampling and analytical methods have been applied to the measurement of current environmental levels of some of the more ecologically important radionuclides. The detection and tracing of long-lived radionuclides is being conducted in order to establish base-line values and to study environmental behavior. This paper describes detection and measurement techniques and summarizes current measurement results

  10. Correction factors of commercial radionuclide calibrators for several measurement geometries of radiopharmaceuticals

    International Nuclear Information System (INIS)

    Correia, Amanda Ribeiro

    2011-01-01

    In order to reach therapy and diagnosis objectives, the activity must be determined with high accuracy to administer a radiopharmaceutical to a patient. Initially, a glass vial with the radiopharmaceutical is placed into the radionuclide calibrator to determine its activity. Subsequently, an aliquot is transferred to a syringe and again its activity is measured on the calibrator before being administered to the patient. The glass vial and the syringe are different in many aspects as the calibration factors too, which may cause incorrect activities administered to the patient. This study aims to determine the correction factors, as well as the values of the uncertainties associated to two distinct models of calibrators: one that uses ionization chamber and another Geiger-Mueller as detectors. The radionuclides chosen were 99 Tc m and 123 1 and the containers were glass vials (type lOR and P6) and plastic syringes of 3 and 5 mL. The correction factors for each type of vials or syringe were determined as a function of volume and type of calibrator. Activity measurements comparison was also made involving several radionuclide calibrators of different models belonging to four nuclear medicine hospitals and to National Metrology Laboratory of lionizing Radiation (LNMRI). In the measurements of activity values larger than allowed by CNEN NN-3.05 norm, results have shown deviations for syringes in calibrator with Geiger-Mueller detectors and for both radionuclides. (author)

  11. Airborne anthropogenic radioactivity measurements from an international radionuclide monitoring system

    International Nuclear Information System (INIS)

    Mason, L.R.; Bohner, J.D.; Williams, D.L.

    1998-01-01

    Anthropogenic radioactivity is being measured in near-real time by an international monitoring system designed to verify the Comprehensive Nuclear Test Ban Treaty. Airborne radioactivity measurements are conducted in-situ by stations that are linked to a central data processing and analysis facility. Aerosols are separated by high-volume air sampling with high-efficiency particulate filters. Radio-xenon is separated from other gases through cryogenic methods. Gamma-spectrometry is performed by high purity germanium detectors and the raw spectral data is immediately transmitted to the central facility via Internet, satellite, or modem. These highly sensitive sensors, combined with the automated data processing at the central facility, result in a system capable of measuring environmental radioactivity on the microbecquerel scale where the data is available to scientists within minutes of the field measurement. During the past year, anthropogenic radioactivity has been measured at approximately half of the stations in the current network. Sources of these measured radionuclides include nuclear power plant emissions, Chernobyl resuspension, and isotope production facilities. The ability to thoroughly characterize site-specific radionuclides, which contribute to the radioactivity of the ambient environment, will be necessary to reduce the number of false positive events. This is especially true of anthropogenic radionuclides that could lead to ambiguous analysis. (author)

  12. Radionuclide transfer from soil to agricultural plants: measurements and modelling

    International Nuclear Information System (INIS)

    Sabbarese, C; Terrasi, F.; D'Onofrio, A.D.; Stellato, L.; Lubritto, C.; Ermice, A.; Cotrufo, M.F.

    2002-01-01

    To assess the internal doses to humans from ingestion of radionuclides present in agricultural products it is necessary to know the main processes which determine the transport of radionuclides in the environment (Russel, 1966; Peterson, 1983; IAEA, 1995). The available data, generally, do not reflect natural conditions, and the mechanisms of translocation and mobility of radionuclides within the soil-plant system are still not fully understood (Coughtrey and Thorne, 1983; Fresquez et a., 1998; Krouglov et al., 1997; Frissel, 1992; Roca and Vallejo, 1995; Desmet et al., 1990). The knowledge of the contributions of direct contamination of plant fruits and of the process of root to fruit transfer can improve the understanding of exposure through ingestion and of the mechanisms determining sorption and translocation. Several studies on the relations among specific activities of various radionuclides in different environmental compartments have been performed in the last decades (Coughtrey and Thorne, 1983; Fresquez et al., 1998; Krouglov et al., 1997; Howard et al., 1995; Strand et al., 1994; Konshin, 1992; Frissel, 1992; Alexakhin and Korneev, 1992; Desmet et al., 1990)

  13. Correlation Water Velocity and TSS with Natural Radionuclides Activity

    International Nuclear Information System (INIS)

    Tri Harningsih; Muzakky; Agus Taftazani

    2007-01-01

    Correlation water velocity and TSS with natural radionuclides activity has been studied. For that purpose, the study is to correlation water velocity and TSS with radionuclides on water and sediment samples in alongside river Code Yogyakarta. This research selected radionuclides, for examples Ra-226, Pb-212, Ac- 228, and K-40. Election of this radionuclides to spread over gamma gross composition alongside river of Code. Gamma gross influenced by water velocity and TSS, so that require to correct between water velocity and TSS to radionuclides. Sampling water and sediment conducted when dry season of August, 2006 at 11 locations, start from Boyong Bridge until Pacar Bridge. Result of analysis showed that water velocity range from 8-1070 L/dt and TSS range from 2.81 E-06 - 8.02 E-04 mg/L. The accumulation of radionuclides in water samples non correction water velocity for Ra-226: 0.302-2.861 Bq/L, Pb-212: 0.400-3.390 Bq/L, Ac- 228: 0.0029-0.0047 Bq/L and K-40: 0.780-9.178 Bq/L. The accumulation of radionuclide in water samples correction water velocity for Ra-226: 1.112-70.454 Bq/L, Pb-212: 0.850-77.113 Bq/L, Ac-228: 0.7187- 60.859 Bq/L and K-40: 2.420-208.8 Bq/L. While distribution of radionuclide in sediment for the Ra-226: 0.0012-0.0211 Bq/kg, Pb-212: 0.0017-0.0371 Bq/kg, Ac-228: 0.0021-0.0073 Bq/kg and K-40: 0.0006-0.0084 Bq/kg. (author)

  14. Activity measurements of the radionuclide {sup 124}Sb by the LNE-LNHB, France for the ongoing comparison BIPM.RI(II)-K1.Sb-124

    Energy Technology Data Exchange (ETDEWEB)

    Michotte, C.; Ratel, G. [Bureau International des Poids et Mesures (BIPM), Pavillon de Breteuil, F-92312 Sevres Cedex, (France); Moune, M.; Bobin, C. [Laboratoire national de metrologie et d' essais-Laboratoire national Henri Becquerel, 91191 Gif-sur-Yvette cedex, (France)

    2011-07-01

    In 2007, the Laboratoire national de metrologie et d'essais-Laboratoire national Henri Becquerel (LNE-LNHB), France submitted a sample of known activity of {sup 124}Sb to the International Reference System (SIR) for activity comparison at the Bureau International des Poids et Mesures (BIPM). The activity was about 5.3 MBq. The key comparison reference value (KCRV) has been recalculated to include this new value and the degrees of equivalence between each equivalent activity for the three participants measured in the SIR and the KCRV are presented in a table and graphically. (authors)

  15. Criteria for Radionuclide Activity Concentrations for Food and Drinking Water

    International Nuclear Information System (INIS)

    2016-04-01

    Requirements for the protection of people from the harmful consequences of exposure to ionizing radiation, for the safety of radiation sources and for the protection of the environment are established in IAEA Safety Standards Series No. GSR Part 3, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. GSR Part 3 requires that the regulatory body or other relevant authority establish specific reference levels for exposure due to radionuclides in commodities, including food and drinking water. The reference level is based on an annual effective dose to the representative person that generally does not exceed a value of about 1 mSv. International standards have been developed by the Food and Agriculture Organization of the United Nations/World Health Organization (FAO/WHO) Codex Alimentarius Commission for levels of radionuclides contained in food traded internationally that contains, or could potentially contain, radioactive substances as a consequence of a nuclear or radiological emergency. International standards have also been developed by the WHO for radionuclides contained in drinking water, other than in a nuclear or radiological emergency. These international standards provide guidance and criteria in terms of levels of individual radiation dose, levels of activity concentration of specific radionuclides, or both. The criteria derived in terms of levels of activity concentration in the various international standards differ owing to a number of factors and assumptions underlying the common objective of protecting public health in different circumstances. This publication considers the various international standards to be applied at the national level for the assessment of levels of radionuclides in food and in drinking water in different circumstances for the purposes of control, other than in a nuclear or radiological emergency. It collates and provides an overview of the different criteria used in assessing and

  16. 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)

  17. Measurement of natural radionuclides in bricks and brick-making clays from Cuddalore district, Tamilnadu, India

    International Nuclear Information System (INIS)

    Viruthagirl, G.; Rajamanan, B.; Ravisankar, R.; Thilaivelavan, K.; Chandrasekaran, A.; Meenkshisundram, V.

    2010-01-01

    In India, bricks as building materials are mainly prepared by clay using the deposited sediments of rivers, and the radionuclide contents in bricks and brick-making clays should vary with origin and geological condition. In this paper, the radionuclide contents of these materials from river bank areas of Cuddalore district, Tamilnadu India are measured by gamma ray spectrometer using NaI (Tl) detector, and compared with those of other countries. The radiation hazard indices, which are evaluated by radium-equivalent (Raeq) activity, are lower than that of NEA-OECD. (authors)

  18. Activity determination of radionuclides for diagnostic and therapy

    International Nuclear Information System (INIS)

    Kossert, Karsten

    2013-01-01

    The application of radionuclides plays in medicine an important role and requires reliable activity determination. The PTB provides for this activity normals and determines the activity of the presented sources. The article describes, how activity determinations in the PTB occur, and by which ways this can be used for nuclear medicine. Research and development works in the PTB are just so illuminated as the determination of nuclide data of some isotopes relevant for medicine.

  19. Measured radionuclide production from copper, gold and lead spallation targets

    Energy Technology Data Exchange (ETDEWEB)

    Parish, T.A.; Belian, A.P. [Texas A & M Univ., College Station, TX (United States)

    1995-10-01

    Spallation target materials are chosen so as to produce large numbers of neutrons while at the same time avoiding the creation of long-lived radioactive wastes. While there has been considerable research to determine the number of neutrons produced per incident particle for various target materials, there has been less effort to precisely quantify the types and amounts of radionuclides produced. Accurate knowledge of the radioactive species produced by spallation reactions is important for specifying waste disposal criteria for targets. In order to verify the production rates calculated by LAHET, a study has been conducted using the Texas A&M University (TAMU) Cyclotron to measure radionuclide yields from copper, gold, and lead targets.

  20. Development of standard methods for activity measurement of natural radionuclides in waterworks as basis for dose and risk assessment—First results of an Austrian study

    International Nuclear Information System (INIS)

    Stietka, M.; Baumgartner, A.; Seidel, C.; Maringer, F.J.

    2013-01-01

    A comprehensive study with the aim to evaluate the risks due to radiation exposure for workers in water supply is conducted in 21 Austrian waterworks. The development of standard methods for the assessment of occupational exposure of water work staff is a part of this study. Preliminary results of this study show a wide range of Rn-222 activity concentration in waterworks with values from (28±10) Bq/m 3 to (38,000±4000) Bq/m 3 . Also seasonal variations of the Rn-222 activity concentration could be observed. - Highlights: • In this study operational exposure of water work staff was evaluated. • The Rn-222 concentration in indoor air in waterworks was measured for 1 year. • Results show a wide range of Rn-222 activity concentration in waterworks. • Seasonal variations of the Rn-222 activity concentration could be observed

  1. Fast neutron activation analysis using short-lived radionuclides

    International Nuclear Information System (INIS)

    Salma, I.; Zemplen-Papp, E.

    1993-01-01

    Fast neutron activation analysis experiments were performed to investigate the analytical possibilities and prospective utilization of short-lived activation products. A rapid pneumatic transfer system for use with neutron generators has been installed and applied for detecting radionuclides with a half-life from ∼300 ms to 20 s. The transport time for samples of total mass of 1-4 g is between 130 and 160 ms for pressurized air of 0.1-0.4 MPa. The reproducibility of transport times is less than 2%. The employed method of correcting time-dependent counting losses is based on the virtual pulse generator principle. The measuring equipment consists of CAMAC modules and a special gating circuit. Typical time distributions of counting losses are presented. The same 14 elements were studied by the conventional activation method (single irradiation and single counting) by both a typical pneumatic transport system (run time 3 s) and the fast pneumatic transport facility. Furthermore, the influence of the cyclic activation technique on the elemental sensitivities was investigated. (author) 15 refs.; 5 figs.; 3 tabs

  2. The administered activity of radionuclides in nuclear medicine

    International Nuclear Information System (INIS)

    Nakamura, Mototoshi; Koga, Sukehiko; Kondo, Takeshi

    1993-01-01

    A survey of 104 hospitals was conducted to determine the administered activity of radionuclides. Eighty-five hospitals responded, and reported a total of 119,614 examinations in one year. The examinations included: bone scintigraphy, 26.4%; thallium-201 ( 201 Tl) myocardial scintigraphy, 15.5%; gallium-67 ( 67 Ga) scintigraphy, 13.3%; N-isopropyl-p-[ 123 I] iodoamphetamine (IMP) brain perfusion scintigraphy, 7.0%. The administered activity was corrected by body weight only for children at more than 80% of the responding hospitals. The number of hospitals that reported over-administration of radionuclide varied according to the type of scintigraphy performed: bone, 76%; inflammatory ( 67 Ga), 93%; myocardial ( 201 Tl), 89.2%; brain (IMP), 8.5%. The administered activity of IMP was closer to the upper limits specified in the Recommendations on Standardization of Radionuclide Imaging by the Japan Radioisotope Association (1987), because IMP is very expensive and is supplied as single vials. The highest average effective dose was for myocardial scintigraphy, the second-highest for inflammatory scintigraphy, and the third-highest for bone scintigraphy. In 201 Tl and 67 Ga scintigraphy, the entire contents of the vial may be administered two days before the expiration date, because the ratio of (true patient administered activity) to (declared patient administered activity) is similar to the ratio of (radioactivity on the day of supply) to (radioactivity on the day of expiration). The factors that influence administered activity are through put, price of the radionuclide, and whether the radionuclide is sold as a single vial. In order to decrease the effective dose, it is necessary to establish a close cooperation between medical personnel, the makers of radiopharmaceuticals, and manufactures of gamma cameras. (author)

  3. Absolute activity measurement of the electron-capture-based radionuclides Ce-139, I-125, Ir-192 and Zn-65 by liquid scintillation coincidence counting

    CSIR Research Space (South Africa)

    Van Wyngaardt, WM

    2006-10-01

    Full Text Available experimentally by measur- ing NC=Ng. Eq. (1) can then be expressed as N4pNg NC ? N?1 C0f ??1 C0P??N?f ??1 C0f ?PPSC138 Ng NC . (4) When ?Ng=NC?!1 so will PS and the source activity is given by the corresponding extrapolated value of N4pNg=NC.AsNg=NC is varied, PS...

  4. Activity measurements of the radionuclide 109Cd for the PTB, Germany and the NIST, USA in the ongoing comparison BIPM.RI(II)-K1.Cd-109

    International Nuclear Information System (INIS)

    Ratel, G.; Michotte, C.; Janssen, H.; Kossert, K.; Lucas, L.; Karam, L.

    2005-01-01

    In 2004, the Physikalisch-Technische Bundesanstalt (PTB, Germany) and the National Institute of Standards and Technology (NIST, USA) each submitted one sample of known activity of 109 Cd to the International Reference System (SIR). The PTB result replaces their previous measurement of 1994 and the NIST result updates their 1986 CCRI(II) comparison result. The values of the activity submitted were about 15 MBq and 42 MBq. The new key comparison results have replaced the earlier values in the matrix of degrees of equivalence that now contains six results, identifier BIPM.RI(II)-K1.Cd-109, to which the remaining eleven results from the CCRI(II)-K2.Cd-109 held in 1986 are still linked. (authors)

  5. Nondestructive measurement for radionuclide concentration distribution in soil column

    International Nuclear Information System (INIS)

    Ogawa, Hiromichi; Ohnuki, Toshihiko; Yamamoto, Tadatoshi; Wadachi, Yoshiki

    1985-01-01

    A nondestructive method has been studied for determining the concentration of radionuclide (Cs-137) distributed in a soil column. The concentration distribution was calculated from the counting rate distribution using the efficiency matrix of a detector. The concentration distribution obtained by this method, with measuring efficiencies of theoretical calculation, coincides well with that obtained by the destructive sampling method. This method is, therefore, found to be effective for the measurement of one dimensional concentration distribution. The measuring limit of this method is affected not only by the radionuclide concentration but also by the shape of concentration distribution in a soil column and also by the way it is divided into concentration blocks. It is found that, the radioactive concentration up to 2.6 x 10 -4 μCi/g (9.62 Bq/g), and also the distribution up to where the concentration reduces to half at every 1 cm of depth, can be measured by this system. The concentration blocks can be divided into 1 cm of thickness as a minimum value. (author)

  6. Activity concentrations and mean annual effective dose from gamma-emitting radionuclides in the Lebanese diet

    International Nuclear Information System (INIS)

    Nasreddine, L.; Hwalla, N.; El Samad, O.; Baydoun, R.; Hamze, M.; Parent-Massin, D.

    2008-01-01

    Since the primary factor contributing to the internal effective dose in the human organism is contaminated food, the control of radionuclides in food represents the most important means of protection. This study was conducted to determine the levels of the dietary exposure of the Lebanese population to gamma-emitting radioisotopes. The activity concentrations of gamma-emitting radioisotopes have been measured in food samples that represent the market basket of an adult urban population in Lebanon. The artificial radionuclide 137 Cs was measured above detection limits in only fish, meat and milk-based deserts. The most abundant natural radionuclide was 40 K (31-121 Bq kg -1 ), with the highest content in fish and meat samples. The annual mean effective dose contributed by 40 K in the reference typical diet was estimated equal to 186 μSv y -1 , a value reasonably consistent with findings reported by several other countries. (authors)

  7. ALPHA/AMPU, Radionuclide Radioactivity from Alpha Spectrometer Measurements

    International Nuclear Information System (INIS)

    Sill, D.S.

    1990-01-01

    1 - Description of program or function: The two computer programs, ALPHA and AMPU, take raw data obtained from alpha spectrometry and from these calculate activities and uncertainties of the radionuclides present in the sample. ALPHA determines activities of any alpha emitter in a sample that has been directly precipitated with NdF 3 . AMPU determines the Pu-239, Pu-238,and Am-241 activities using Pu-236 and Am-243 tracers. 2 - Method of solution: These programs propagate all random and systematic uncertainties, found anywhere in the experimental process, to the final result. The result is rounded and is in decimal agreement with the uncertainty. 3 - Restrictions on the complexity of the problem: In ALPHA, a chemical yield of 98% is assumed

  8. Pulmonary blood flow distribution measured by radionuclide computed tomography

    International Nuclear Information System (INIS)

    Maeda, H.; Itoh, H.; Ishii, Y.

    1982-01-01

    Distributions of pulmonary blood flow per unit lung volume were measured in sitting patients with a radionuclide computed tomography (RCT) by intravenously administered Tc-99m macroaggregates of human serum albumin (MAA). Four different types of distribution were distinguished, among which a group referred as type 2 had a three zonal blood flow distribution as previously reported (West and co-workers, 1964). The pulmonary arterial pressure (Pa) and the venous pressure (Pv) were determined in this group of distribution. These values showed satifactory agreements with the pulmonary artery pressure (Par) and the capillary wedged pressure (Pcw) measured by Swan-Ganz catheter in eighteen supine patients. Those good correlations enable to establish a noninvasive methodology for measurement of pulmonary vascular pressures

  9. Relationships between sea-bed radionuclide activities and some sedimentological variables

    International Nuclear Information System (INIS)

    Ligero, R.A.; Ramos-Lerate, I.; Barrera, M.; Casas-Ruiz, M.

    2001-01-01

    Natural radionuclides ( 232 Th, 226 Ra, 40 K) and 137 Cs, coming from atmospheric radioactive fallout, have been measured in sea-bed sediments of the Bay of Cadiz (South Western Spain). In this report, multivariate analysis methods have been employed to study the relationships between the activities of the radionuclides and some sedimentological variables like granulometric facies, organic content and apparent density. The correlation functions found show that it is possible to determine, with a satisfactory degree of approximation, the granulometric facies of the sediments using only radiometric information

  10. Measuring Radionuclides in the environment: radiological quantities and sampling designs

    International Nuclear Information System (INIS)

    Voigt, G.

    1998-10-01

    One aim of the workshop was to support and provide an ICRU report committee (International Union of Radiation Units) with actual information on techniques, data and knowledge of modern radioecology when radionuclides are to be measured in the environment. It has been increasingly recognised that some studies in radioecology, especially those involving both field sampling and laboratory measurements, have not paid adequate attention to the problem of obtaining representative, unbiased samples. This can greatly affect the quality of scientific interpretation, and the ability to manage the environment. Further, as the discipline of radioecology has developed, it has seen a growth in the numbers of quantities and units used, some of which are ill-defined and which are non-standardised. (orig.)

  11. Activity concentration of some anthropogenic radionuclides in the surface marine sediments near the Saudi coast of the Arabian (Persian) Gulf

    International Nuclear Information System (INIS)

    Al-Kheliewi, A.S.; Shabana, E.I.

    2007-01-01

    Activity concentrations of some anthropogenic radionuclides ( 90 Sr, 137 Cs, 238 Pu, 239+240 Pu and 241 Am) have been measured in the surface of marine sediments along the Saudi coast of the Arabian (Persian) Gulf. The samples were collected at different locations and water depths. The spatial distribution of the concentrations of the measured radionuclides showed a heterogeneous pattern and is independent of location or water depth. The obtained results are discussed and some conclusions are drawn. (author)

  12. Measurement of shunt amount using radionuclide angiocardiography: accuracy according to level of shunt and associated lesion

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yang Min [Sejong General Hospital, Bucheon (Korea, Republic of)

    2006-08-15

    Determination of pulmonary to systemic blood flow ratio (QP/QS) is important for the management of patients with left-to-right shunt. This study was performed to assess the agreement of Qp/Qs ratio using the radionuclide method and oxymetry, to investigate the factors influencing the agreement, and to know how interchangeable the results of each technique. We compared the Qp/Qs measured by single-pass radionuclide angiocardiography and oxymetry during catheterization in 207 patients who underwent both studies. In radionuclide method, Qp/Qs was calculated from the pulmonary time-activity curves using a gamma variate fit. The correlation and Bland-Altman analysis were performed according to the levels of shunt and associated lesions. The mean Qp/Qs was 1.83 {+-} 0.50 by radionuclide, and 1.74 {+-} 0.51 by oxymetry. The overall correlation coefficient was 0.86 ({rho} 0.001), and Bland-Altman range of agreement encompassing 4SD was 1.05. For atrial septal defect, ventricular septal defect, patent ductus arteriosus, tricuspid and mitral insufficiency, the correlation coefficient was 0.78, 0.90, 0.84, 0.63 and 0.44 and Bland-Altman range was 1.52, 0.74, 0.96, 1.57 and 1.50, respectively. There is good agreement but wide variance between the Qp/Qs ratios by radionuclide method and oxymetry. Associated atrioventricular valvar insufficiency decreases the correlation coefficient and widens the variance. Wide overall variance suggests that Qp/Qs measurements by two techniques should not be used interchangeably.

  13. Measurement of shunt amount using radionuclide angiocardiography: accuracy according to level of shunt and associated lesion

    International Nuclear Information System (INIS)

    Kim, Yang Min

    2006-01-01

    Determination of pulmonary to systemic blood flow ratio (QP/QS) is important for the management of patients with left-to-right shunt. This study was performed to assess the agreement of Qp/Qs ratio using the radionuclide method and oxymetry, to investigate the factors influencing the agreement, and to know how interchangeable the results of each technique. We compared the Qp/Qs measured by single-pass radionuclide angiocardiography and oxymetry during catheterization in 207 patients who underwent both studies. In radionuclide method, Qp/Qs was calculated from the pulmonary time-activity curves using a gamma variate fit. The correlation and Bland-Altman analysis were performed according to the levels of shunt and associated lesions. The mean Qp/Qs was 1.83 ± 0.50 by radionuclide, and 1.74 ± 0.51 by oxymetry. The overall correlation coefficient was 0.86 (ρ 0.001), and Bland-Altman range of agreement encompassing 4SD was 1.05. For atrial septal defect, ventricular septal defect, patent ductus arteriosus, tricuspid and mitral insufficiency, the correlation coefficient was 0.78, 0.90, 0.84, 0.63 and 0.44 and Bland-Altman range was 1.52, 0.74, 0.96, 1.57 and 1.50, respectively. There is good agreement but wide variance between the Qp/Qs ratios by radionuclide method and oxymetry. Associated atrioventricular valvar insufficiency decreases the correlation coefficient and widens the variance. Wide overall variance suggests that Qp/Qs measurements by two techniques should not be used interchangeably

  14. An overview of measurements of radionuclides in foods of the Comunidad Valenciana (Spain)

    Science.gov (United States)

    Ballesteros, L.; Ortiz, J.; Gallardo, S.; Martorell, S.

    2015-11-01

    Environmental radioactivity monitoring includes the determination of radionuclides in foods since they are an important way of intake of radionuclides to the human organism. Moreover, knowledge of the levels of radionuclides in foodstuffs will inform about the environmental radioactivity background permitting to control possible contamination due to human activity, such as agriculture activity, nuclear power plants or other radioactive facilities. The Environmental Radioactivity Laboratory (LRA) at the Universitat Politècnica de València (UPV) performs measurements on representative foods from all over the Comunidad Valenciana (CV). Those measurements are part of several monitoring programs promoted by the Generalitat Valenciana. A total of 2200 samples of fruits, cereals, vegetables, milk, meat, eggs and fish coming from markets, agricultural cooperatives or small producers have been analyzed. A gamma-ray spectrometry analysis has been performed in all samples. It has been detected 40K in all samples, 7Be in some of them. Radiochemical separation of 90Sr has been carried out in some of the samples collected, mainly orange and lettuce. Samples of lettuce and chard collected following Fukushima Nuclear Power Plant (NPP) accident present activity concentration of 131I (0.10-1.51 Bq kg-1). In this paper, a review of the data obtained at the 1991-2013 period in the framework of the development of the Environmental monitoring program is presented.

  15. 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

  16. New radionuclide method for determination of gastric content proteolytic activity. (Experiments)

    International Nuclear Information System (INIS)

    Sergienko, V.B.; Popova, L.V.; Khodarev, N.N.; Astashenkova, K.Yu.

    1988-01-01

    A possibility of the use of a radionuclide tubeless rapid method for measuring gastric content proteolytic activity (GCPA) with the help of a protein (gelatin) RP containing capsule was demonstrated in experiments in vitro. There was correlation between the time of dissolution of RP containing capsules and GCPA determined after Mett's method. Reference time intervals were established for normal, raised and lowered proteolytic activity. The method was shown to be physiological, simple and timesaving

  17. 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)

  18. Separation of radionuclides from gas by sorption on activated charcoal and inorganic sorbents

    International Nuclear Information System (INIS)

    Kepak, F.

    1988-01-01

    The review deals with the sorption and ion exchange of gaseous radionuclides on activated charcoal and on inorganic sorbents. It presents the physical and chemical characteristics of radionuclides, the sources of gaseous forms of radionuclides as well as the composition of radioactive gases from some nuclear facilities. 79 refs. (author)

  19. Update of the BIPM.RI(II)-K1.Rn-222 comparison of activity measurements for the radionuclide {sup 222}Rn to include the LNE-LNHB, France

    Energy Technology Data Exchange (ETDEWEB)

    Michotte, C.; Ratel, G. [Bureau International de Poids et Mesures, Pavillon de Breteuil, F-92312 Sevres cedex (France); Cassette, P. [Bureau International de Poids et Mesures, Pavillon de Breteuil, F-92312 Sevres cedex (France); Laboratoire national de metrologie et d' essais -Laboratoire national Henri Becquerel, 91191 Gif-sur-Yvette cedex (France)

    2012-02-15

    In 2007, the Laboratoire national de metrologie et d'essais - Laboratoire national Henri Becquerel (LNE-LNHB), France submitted a sample of known activity of {sup 222}Rn to the International Reference System (SIR) for comparison. The value of the activity submitted was about 90 kBq. This key comparison result joins that of Switzerland and Germany in the key comparison database that now contains three results, identifier BIPM.RI(II)-K1.Rn-222. Consequently, the KCRV has been updated and the degrees of equivalence with the KCRV have been evaluated. (authors)

  20. Dependency of soil activity concentration on soil -biota concentration ratio of radionuclides for earthworm

    Energy Technology Data Exchange (ETDEWEB)

    Keum, Dong Kwon; Kim, Byeong Ho; Jun, In; Lim, Kwang Muk; Choi, Yong Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    The transfer of radionuclides to wildlife (non-human biota) is normally quantified using an equilibrium concentration ratio (CR{sub eq}), defined as the radionuclide activity concentration in the whole organism (fresh weight) divided by that in the media (dry weight for soil). The present study describes the effect of soil radionuclide activity concentration on the transfer of {sup 137}Cs, {sup 85}Sr and {sup 65}Zn to a functionally important wildlife group, annelids, using a commonly studied experimental worm (E.andrei). Time-dependent whole body concentration ratios of {sup 137}Cs, {sup 85}Sr and {sup 65}Zn for the earthworm were experimentally measured for artificially contaminated soils with three different activity concentrations for each radionuclide which were considerably higher than normal background levels. Two parameters of a first order kinetic model, the equilibrium concentration ratio (CR{sub eq}) and the effective loss rate constant (k), were estimated by comparison of experimental CR results with the model prediction

  1. Research on sorption behavior of radionuclides under shallow land environment. Mechanism and standard methodologies for measurement of distribution coefficients of radionuclides

    International Nuclear Information System (INIS)

    Sakamoto, Yoshiaki; Tanaka, Tadao; Takebe, Shinichi; Nagao, Seiya; Ogawa, Hiromichi; Komiya, Tomokazu; Hagiwara, Shigeru

    2001-01-01

    This study consists of two categories' research works. One is research on sorption mechanism of radionuclides with long half-life, which are Technetium-99, TRU elements and U series radionuclides, on soil and rocks, including a development of database of distribution coefficients of radionuclides. The database on the distribution coefficients of radionuclides with information about measurement conditions, such as shaking method, soil characteristics and solution composition, has been already opened to the public (JAERI-DATABASE 20001003). Another study is investigation on a standard methodology of the distribution coefficient of radionuclide on soils, rocks and engineering materials in Japan. (author)

  2. Radionuclides difficult to measure in waste packages. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Thierfeldt, S; Deckert, A [Brenk Systemplanung, Aachen (Germany)

    1995-11-01

    In this study nuclide specific correlation analyses between key nuclides that can be easily measured and nuclides that are difficult to measure are presented. Data are taken from studies and data compilations from various countries. The results of this study can serve to perform assays of the nuclide specific radionuclide contents in waste packages by gamma measurements of {sup 60}Co and {sup 137}Cs and calculation of the contents of other nuclides via the correlation analyses, sometimes referred to as `scaling factor method`. It can thus be avoided to have to take samples from the waste for separate analysis. An attempt is made to also investigate the physical and chemical backgrounds behind the proposed correlations. For example, a formation pathway common to the two nuclides to be correlated can be regarded as an explanation, if a good correlation is found. On the other hand, if the observed correlation is of poor quality, reasons may possibly lie in different behaviour of the two nuclides in the water system of the nuclear plant. This implies not only chemical solubility, transfer constants etc. in the water system, which would not only affect the proportionality between the two nuclides, but a different behavior in different parts of the water system must be assumed (e.g. different filter efficiencies etc). 47 refs, 57 figs, 40 tabs.

  3. Methodology for determination of activity of radionuclides by gamma spectrometry

    International Nuclear Information System (INIS)

    Fragoso, Maria da Conceicao de Farias; Oliveira, Victor Rogerio S. de; Oliveira, Mercia L.; Lima, Fernando Roberto de Andrade

    2014-01-01

    Due to the growth in the number of procedures that make use of the positron emission tomography (PET), there is a need for standard solutions for the calibration of the systems used for the measurement of the PET radiopharmaceutical (activimeter) in radiopharmacies and in nuclear medicine services. Among the existing alternatives for the standardization of radioactive sources, the method known as gamma spectrometry is widely used for short-lived radionuclides. The purpose of this study was to implement the methodology for standardization of the 18 F solutions by gamma spectrometry at the Regional Center for Nuclear Sciences of the Northeast (CRCN-NE/CNEN-NE), Brazil. (author)

  4. Natural and anthropogenic radionuclide activity concentrations in the New Zealand diet.

    Science.gov (United States)

    Pearson, Andrew J; Gaw, Sally; Hermanspahn, Nikolaus; Glover, Chris N

    2016-01-01

    To support New Zealand's food safety monitoring regime, a survey was undertaken to establish radionuclide activity concentrations across the New Zealand diet. This survey was undertaken to better understand the radioactivity content of the modern diet and also to assess the suitability of the current use of milk as a sentinel for dietary radionuclide trends. Thirteen radionuclides were analysed in 40 common food commodities, including animal products, fruits, vegetables, cereal grains and seafood. Activity was detected for (137)Caesium, (90)Strontium and (131)Iodine. No other anthropogenic radionuclides were detected. Activity concentrations of the three natural radionuclides of Uranium and the daughter radionuclide (210)Polonium were detected in the majority of food sampled, with a large variation in magnitude. The maximum activity concentrations were detected in shellfish for all these radionuclides. Based on the established activity concentrations and ranges, the New Zealand diet contains activity concentrations of anthropogenic radionuclides far below the Codex Alimentarius guideline levels. Activity concentrations obtained for milk support its continued use as a sentinel for monitoring fallout radionuclides in terrestrial agriculture. The significant levels of natural and anthropogenic radionuclide activity concentrations detected in finfish and molluscs support undertaking further research to identify a suitable sentinel for New Zealand seafood monitoring. Copyright © 2015 The Authors. Published by Elsevier Ltd.. All rights reserved.

  5. ASSESSMENT OF RELEASE RATES FOR RADIONUCLIDES IN ACTIVATED CONCRETE.

    Energy Technology Data Exchange (ETDEWEB)

    SULLIVAN,T.M.

    2003-08-23

    The Maine Yankee (MY) nuclear power plant is undergoing the process of decontamination and decommissioning (D&D). Part of the process requires analyses that demonstrate that any radioactivity that remains after D&D will not cause exposure to radioactive contaminants to exceed acceptable limits. This requires knowledge of the distribution of radionuclides in the remaining material and their potential release mechanisms from the material to the contacting groundwater. In this study the concern involves radionuclide contamination in activated concrete in the ICI Sump below the containment building. Figures 1-3 are schematic representations of the ICI Sump. Figure 2 and 3 contain the relevant dimensions needed for the analysis. The key features of Figures 2 and 3 are the 3/8-inch carbon steel liner that isolates the activated concrete from the pit and the concrete wall, which is between 7 feet and 7 feet 2 inches thick. During operations, a small neutron flux from the reactor activated the carbon steel liner and the concrete outside the liner. Current MY plans call for filling the ICI sump with compacted sand.

  6. Natural and anthropogenic radionuclide activity concentrations in the New Zealand diet

    International Nuclear Information System (INIS)

    Pearson, Andrew J.; Gaw, Sally; Hermanspahn, Nikolaus; Glover, Chris N.

    2016-01-01

    To support New Zealand's food safety monitoring regime, a survey was undertaken to establish radionuclide activity concentrations across the New Zealand diet. This survey was undertaken to better understand the radioactivity content of the modern diet and also to assess the suitability of the current use of milk as a sentinel for dietary radionuclide trends. Thirteen radionuclides were analysed in 40 common food commodities, including animal products, fruits, vegetables, cereal grains and seafood. Activity was detected for 137 Caesium, 90 Strontium and 131 Iodine. No other anthropogenic radionuclides were detected. Activity concentrations of the three natural radionuclides of Uranium and the daughter radionuclide 210 Polonium were detected in the majority of food sampled, with a large variation in magnitude. The maximum activity concentrations were detected in shellfish for all these radionuclides. Based on the established activity concentrations and ranges, the New Zealand diet contains activity concentrations of anthropogenic radionuclides far below the Codex Alimentarius guideline levels. Activity concentrations obtained for milk support its continued use as a sentinel for monitoring fallout radionuclides in terrestrial agriculture. The significant levels of natural and anthropogenic radionuclide activity concentrations detected in finfish and molluscs support undertaking further research to identify a suitable sentinel for New Zealand seafood monitoring. - Highlights: • A radionuclide monitoring program was undertaken across the New Zealand food supply. • 40 food types were analysed for 13 radionuclides. • 137 Cs was present in 15% of foods (range: 0.05–0.44Bq/kg). • Anthropogenic radionuclides displayed compliance with international limits. • 210 Po, 234 U and 238 U were present in most foods with large ranges of activities.

  7. Scoping measurements of radionuclides in L Lake with an underwater HPGe detector

    International Nuclear Information System (INIS)

    Dunn, D.L.; Win, W.G.; Bresnahan, P.J.

    1996-01-01

    This study of L Lake was conducted to determine whether the distribution of man-made radiation levels had changed from the time preceding the filling of the newly created lake in 1985. Overflight gamma measurements by EG ampersand G in 1985 mapped the man-made radiation levels, indicating that significant levels were only detected from former stream beds that were to be covered by the lake. the present scoping gamma measurements were consistent with these earlier findings, indicating no major evidence of movement of the radioactivity. These results will be available to guide decisions concerning future plans for the lake. Gamma-emitting radionuclides of L Lake were examined in situ with an underwater HPGe detector and further studied by retrieving various sediment samples for analysis by HPGe gamma spectrometry in the Underground Counting Facility. The predominant man-made radionuclide detected was 137 Cs; it had about 100 times greater activity than 60 Co, which was the only other man-made radionuclide that was detected above trace levels

  8. Personnel dosimetry in internal radiation exposure by excretory radionuclide measurement

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  9. Apparatus for the measurement of radionuclide transport rates in rock cores

    International Nuclear Information System (INIS)

    Weed, H.C.; Koszykowski, R.F.; Dibley, L.L.; Murray, I.

    1981-09-01

    An apparatus and procedure for the study of radionuclide transport in intact rock cores are presented in this report. This equipment more closely simulates natural conditions of radionuclide transport than do crushed rock columns. The apparatus and the procedure from rock core preparation through data analysis are described. The retardation factors measured are the ratio of the transport rate of a non-retarded radionuclide, such as 3 H, to the transport rate of a retarded radionuclide. Sample results from a study of the transport of /sup 95m/Tc and 85 Sr in brine through a sandstone core are included

  10. Normalised radionuclide measures of left ventricular diastolic function

    International Nuclear Information System (INIS)

    Lee, K.J.; Southee, A.E.; Bautovich, G.J.; Freedman, B.; McLaughlin, A.F.; Rossleigh, M.A.; Hutton, B.F.; Morris, J.G.; Royal Prince Alfred Hospital, Sydney

    1989-01-01

    Abnormal left ventricular diastolic function is being increasingly recognised in patients with clinical heart failure and normal systolic function. A simple routine radionuclide measure of diastolic function would therefore be useful. To establish, the relationship of peak diastolic filling rate (normalized for either end diastolic volume, stroke volume, or peak systolic emptying rate), and heart rate, age, and left ventricular ejection fraction was studied in 64 subjects with normal cardiovascular systems using routine gated heart pool studies. The peak filling rate when normalized to end diastolic volume correlated significantly with heart rate, age and left ventricular ejection fraction, whereas normalization to stroke volume correlated significantly to heart rate and age but not to left ventricular ejection fraction. Peak filling rate normalized for peak systolic emptying rate correlated with age only. Multiple regression equations were determined for each of the normalized peak filling rates in order to establish normal ranges for each parameter. When using peak filling rate normalized for end diastolic volume or stroke volume, appropriate allowance must be made for heart rate, age and ejection fraction. Peak filling rate normalized to peak ejection rate is a heart rate independent parameter which allows the performance of the patient's ventricle in diastole to be compared with its systolic function. It may be used in patients with normal systolic function to serially follow diastolic function, or if age corrected to screen for diastolic dysfunction. (orig.)

  11. An overview of measurements of radionuclides in foods of the Comunidad Valenciana (Spain)

    International Nuclear Information System (INIS)

    Ballesteros, L.; Ortiz, J.; Gallardo, S.; Martorell, S.

    2015-01-01

    Environmental radioactivity monitoring includes the determination of radionuclides in foods since they are an important way of intake of radionuclides to the human organism. Moreover, knowledge of the levels of radionuclides in foodstuffs will inform about the environmental radioactivity background permitting to control possible contamination due to human activity, such as agriculture activity, nuclear power plants or other radioactive facilities. The Environmental Radioactivity Laboratory (LRA) at the Universitat Politècnica de València (UPV) performs measurements on representative foods from all over the Comunidad Valenciana (CV). Those measurements are part of several monitoring programs promoted by the Generalitat Valenciana. A total of 2200 samples of fruits, cereals, vegetables, milk, meat, eggs and fish coming from markets, agricultural cooperatives or small producers have been analyzed. A gamma-ray spectrometry analysis has been performed in all samples. It has been detected 40 K in all samples, 7 Be in some of them. Radiochemical separation of 90 Sr has been carried out in some of the samples collected, mainly orange and lettuce. Samples of lettuce and chard collected following Fukushima Nuclear Power Plant (NPP) accident present activity concentration of 131 I (0.10–1.51 Bq kg −1 ). In this paper, a review of the data obtained at the 1991–2013 period in the framework of the development of the Environmental monitoring program is presented. - Highlights: • Radioactivity levels have been monitored in foods of Comunidad Valenciana (Spain). • γ-Ray spectrometry analysis and radiochemical separation of Sr-90 have been performed. • K-40, Be-7, and Sr-90 has been detected in samples collected. • Samples collected after Fukushima accident show activity concentration of I-131.

  12. Radionuclide measurements, via different methodologies, as tool for geophysical studies on Mt. Etna

    Energy Technology Data Exchange (ETDEWEB)

    Morelli, D., E-mail: daniela.morelli@ct.infn.it [Dipartimento di Fisica e Astronomia, Universita di Catania, via S. Sofia, 64 I-95123 Catania (Italy); Istituto Nazionale di Fisica Nucleare- Sezione di Catania, via S. Sofia, 64 I-95123 Catania (Italy); Imme, G. [Dipartimento di Fisica e Astronomia, Universita di Catania, via S. Sofia, 64 I-95123 Catania (Italy); Istituto Nazionale di Fisica Nucleare- Sezione di Catania, via S. Sofia, 64 I-95123 Catania (Italy); Altamore, I.; Cammisa, S. [Dipartimento di Fisica e Astronomia, Universita di Catania, via S. Sofia, 64 I-95123 Catania (Italy); Giammanco, S. [Istituto Nazionale di Geofisica e Vulcanologia, Sezione di Catania, Piazza Roma, 2, I-95123 Catania (Italy); La Delfa, S. [Dipartimento di Scienze Geologiche, Universita di Catania, Corso Italia,57 I-95127 Catania (Italy); Mangano, G. [Dipartimento di Fisica e Astronomia, Universita di Catania, via S. Sofia, 64 I-95123 Catania (Italy); Neri, M. [Istituto Nazionale di Geofisica e Vulcanologia, Sezione di Catania, Piazza Roma, 2, I-95123 Catania (Italy); Patane, G. [Dipartimento di Scienze Geologiche, Universita di Catania, Corso Italia,57 I-95127 Catania (Italy)

    2011-10-01

    Natural radioactivity measurements represent an interesting tool to study geodynamical events or soil geophysical characteristics. In this direction we carried out, in the last years, several radionuclide monitoring both in the volcanic and tectonic areas of the oriental Sicily. In particular we report in-soil Radon investigations, in a tectonic area, including both laboratory and in-site measurements, applying three different methodologies, based on both active and passive detection systems. The active detection devices consisted of solid-state silicon detectors equipped in portable systems for short-time measurements and for long-time monitoring. The passive technique consisted of solid-state nuclear track detectors (SSNTD), CR-39 type, and allowed integrated measurements. The performances of the three methodologies were compared according to different kinds of monitoring. In general the results obtained with the three methodologies seem in agreement with each other and reflect the tectonic settings of the investigated area.

  13. Radionuclide measurements, via different methodologies, as tool for geophysical studies on Mt. Etna

    International Nuclear Information System (INIS)

    Morelli, D.; Imme, G.; Altamore, I.; Cammisa, S.; Giammanco, S.; La Delfa, S.; Mangano, G.; Neri, M.; Patane, G.

    2011-01-01

    Natural radioactivity measurements represent an interesting tool to study geodynamical events or soil geophysical characteristics. In this direction we carried out, in the last years, several radionuclide monitoring both in the volcanic and tectonic areas of the oriental Sicily. In particular we report in-soil Radon investigations, in a tectonic area, including both laboratory and in-site measurements, applying three different methodologies, based on both active and passive detection systems. The active detection devices consisted of solid-state silicon detectors equipped in portable systems for short-time measurements and for long-time monitoring. The passive technique consisted of solid-state nuclear track detectors (SSNTD), CR-39 type, and allowed integrated measurements. The performances of the three methodologies were compared according to different kinds of monitoring. In general the results obtained with the three methodologies seem in agreement with each other and reflect the tectonic settings of the investigated area.

  14. Hydrology/Radionuclide Migration Program and related research activities

    International Nuclear Information System (INIS)

    Jones, M.A.

    1992-02-01

    This report presents the results of technical studies conducted under the Hydrology/Radionuclide Migration Program (HRMP) at the Nevada Test Site (NTS) for the period of October 1, 1985 through September 30, 1986. The HRMP was initiated in 1973 as the Radionuclide Migration Program to study and better understand the hydrologic systems of the NTS and potential movement and rates of movement of radionuclides and other contaminants injected into these systems by underground nuclear testing

  15. Intercomparison of radionuclide measurements in marine sediment sample IAEA-367

    International Nuclear Information System (INIS)

    Ballestra, S.; Lopez, J.J.; Gastaud, J.; Vas, D.; Noshkin, V.

    1991-08-01

    The results of an intercomparison exercise on a Pacific Ocean sediment sample, IAEA-367, designed for the determination of artificial and natural radionuclides levels, are reported. The data from 81 laboratories representing 37 countries have been evaluated. The following are the recommended values, with confidence intervals, for 60 Co, 90 Sr, 137 Cs, 239+240 Pu (Reference date: 1 January 1990). Information values for 155 Eu, 238 Pu, 241 Am, and 241 Pu are reported. Information values for the following natural radionuclides 40 K, 226 Ra, 228 Th, 230 Th, 234 U, 235 U and 238 U are also reported. (author)

  16. SU-E-T-666: Radionuclides and Activity of the Patient Apertures Used in a Proton Beam of Wobbling System

    Energy Technology Data Exchange (ETDEWEB)

    Wang, B.Y.; Chen, H.H.; Tsai, H.Y.; Sheu, R.J.

    2015-06-15

    Purpose: To identify the radionuclides and quantify the activity of the patient apertures used in a 190-MeV proton beam of wobbling system. Methods: A proton beam of wobbling system in the first proton center in Taiwan, Chang Gung Memorial Hospital at Linkou, was used to bombard the patient apertures. The patient aperture was composed of 60.5 % copper, 39.4 % Zinc, 0.05 % iron, 0.05 % lead. A protable high-purity germanium (HPGe) coaxial detector was used to measure the spectra of the induced nuclides of patient apertures. The analysis of the spectra and the identification of the radionuclides were preliminarily operated by the Nuclide Navigator III Master Library. On the basis of the results by Nuclide Navigator III Master Library, we manually selected the reliable nuclides by the gamma-ray energies, branching ratio, and half life. In the spectra, we can quantify the activity of radionuclides by the Monte Carlo efficiency transfer method. Results: In this study, the radioisotopes activated in patient apertures by the 190-MeV proton beam were divided into two categories. The first category is long half-life radionuclides, such as Co-56 (half life, 77.3 days). Other radionuclides of Cu-60, Cu-61, Cu-62, Cu-66, and Zn-62 have shorter half life. The radionuclide of Cu-60 had the highest activity. From calculation with the efficiency transfer method, the deviations between the computed results and the measured efficiencies were mostly within 10%. Conclusion: To identify the radionuclides and quantify the activity helps us to estimate proper time intervals for cooling the patient apertures. This study was supported by the grants from the Chang Gung Memorial Hospital (CMRPD1C0682)

  17. SU-E-T-666: Radionuclides and Activity of the Patient Apertures Used in a Proton Beam of Wobbling System

    International Nuclear Information System (INIS)

    Wang, B.Y.; Chen, H.H.; Tsai, H.Y.; Sheu, R.J.

    2015-01-01

    Purpose: To identify the radionuclides and quantify the activity of the patient apertures used in a 190-MeV proton beam of wobbling system. Methods: A proton beam of wobbling system in the first proton center in Taiwan, Chang Gung Memorial Hospital at Linkou, was used to bombard the patient apertures. The patient aperture was composed of 60.5 % copper, 39.4 % Zinc, 0.05 % iron, 0.05 % lead. A protable high-purity germanium (HPGe) coaxial detector was used to measure the spectra of the induced nuclides of patient apertures. The analysis of the spectra and the identification of the radionuclides were preliminarily operated by the Nuclide Navigator III Master Library. On the basis of the results by Nuclide Navigator III Master Library, we manually selected the reliable nuclides by the gamma-ray energies, branching ratio, and half life. In the spectra, we can quantify the activity of radionuclides by the Monte Carlo efficiency transfer method. Results: In this study, the radioisotopes activated in patient apertures by the 190-MeV proton beam were divided into two categories. The first category is long half-life radionuclides, such as Co-56 (half life, 77.3 days). Other radionuclides of Cu-60, Cu-61, Cu-62, Cu-66, and Zn-62 have shorter half life. The radionuclide of Cu-60 had the highest activity. From calculation with the efficiency transfer method, the deviations between the computed results and the measured efficiencies were mostly within 10%. Conclusion: To identify the radionuclides and quantify the activity helps us to estimate proper time intervals for cooling the patient apertures. This study was supported by the grants from the Chang Gung Memorial Hospital (CMRPD1C0682)

  18. Measurement of the terrestrial and anthropogenic radionuclide concentrations in Bafra Kizilirmak delta (bird sanctuary) in Turkey

    International Nuclear Information System (INIS)

    Mutuk, H.; Guemues, H.; Turhan, S.

    2014-01-01

    In this study, the activity concentrations of terrestrial and anthropogenic radionuclides in the soil samples collected from Bafra Kizilirmak Delta were measured by using gamma spectrometry with an NaI(Tl) detector. The average values of activity concentrations of 238 U, 232 Th and 40 K were found to be 37.2±2.8, 33.7±3.1 and 413.0±59.8 Bq kg -1 , respectively. 137 Cs was also measured in some samples. It has a mean value of 13.8±1.0 Bq kg -1 . From the activity concentrations, the absorbed gamma dose rates in outdoor and the corresponding annual effective dose rates and external hazard index (Hex) were estimated. (authors)

  19. Measurement of the terrestrial and anthropogenic radionuclide concentrations in Bafra Kizilirmak delta (bird sanctuary) in Turkey.

    Science.gov (United States)

    Mutuk, Halil; Gümüs, Hasan; Turhan, Seref

    2014-01-01

    In this study, the activity concentrations of terrestrial and anthropogenic radionuclides in the soil samples collected from Bafra Kızılırmak Delta were measured by using gamma spectrometry with an NaI(Tl) detector. The average values of activity concentrations of (238)U, (232)Th and (40)K were found to be 37.2±2.8, 33.7±3.1 and 413.0±59.8 Bq kg(-1), respectively. (137)Cs was also measured in some samples. It has a mean value of 13.8±1.0 Bq kg(-1). From the activity concentrations, the absorbed gamma dose rates in outdoor and the corresponding annual effective dose rates and external hazard index (Hex) were estimated.

  20. 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

  1. Quarterly report on measurements of radionuclides in ground level air in Sweden. Third quarter 2004

    International Nuclear Information System (INIS)

    Soederstroem, C.; Arntsing, R.; Lindh, K.

    2005-04-01

    Filtering of ground level air is performed weekly at six different locations in Sweden: Kiruna, Umeaa, Gaevle, Ursvik, Visby and Ljungbyhed. The filters are pressed and the contents of different radionuclides are measured by gamma spectroscopy. Precipitation is also collected at four of the stations: Kiruna, Gaevle, Ursvik and Ljungbyhed, the samples are ashed and the contents of radionuclides measured. The levels of 7 Be and 137 Cs in air and deposition are presented for the different stations. Other anthropogenic radionuclides detected, if any, are also presented

  2. Quarterly report on measurements of radionuclides in ground level air in Sweden. Third quarter 2001

    International Nuclear Information System (INIS)

    Soederstroem, C.; Arntsing, R.; Vintersved, I.

    2002-01-01

    Filtering of ground level air is performed weekly at seven different locations in Sweden: Kiruna, Umeaa, Gaevle, Ursvik, Grindsjoen, Visby and Ljungbyhed. The filters are compressed and the contents of different radionuclides are measured by gamma spectroscopy. Precipitation is also collected at four of the stations: Kiruna, Gaevle, Ursvik and Ljungbyhed, the samples are ashed and the contents of radionuclides measured. The levels of 7 Be and 137 Cs in air and deposition are presented for the different stations. Other anthropogenic radionuclides detected, if any, are also presented

  3. Proposal of limits for the concentration of radionuclides activity in drinking water for Polish population

    International Nuclear Information System (INIS)

    Filipiak, B.; Haratym, Z.

    2008-01-01

    The paper discussed the influence of the radionuclides contents in drinking water on the exposure of the population. The way of transformation of the limits of effective dose into the relevant concentration of radionuclides in drinking water is presented together with the results of these calculations. We propose to approve these limits for particular radionuclides. The suggestion for the methodology and organization of measurements are also given. (author)

  4. 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)

  5. Spot measurements of radionuclides in air, water and solids with a single instrument

    International Nuclear Information System (INIS)

    Philipsborn, H. von

    1998-01-01

    A unique instrument for measuring environmental radionuclides and novel methods for their concentrative sampling are described here which meet high requirements of sensitivity, easy and reliable handling, and low cost for most applications in field screening, monitoring and training. (author)

  6. Prominent artificial radionuclide activity in the environment of coastal Karnataka on the southwest coast of India

    Energy Technology Data Exchange (ETDEWEB)

    Narayana, Y. [Department of Studies in Physics, Mangalore University, Mangalagangotri-574 199 (India)]. E-mail: narayanay@yahoo.com; Somashekarappa, H.M.; Karunakara, N.; Avadhani, D.N.; Mahesh, H.M.; Siddappa, K. [Department of Studies in Physics, Mangalore University, Mangalagangotri-574 199 (India)

    2000-09-01

    Studies on radiation level and radionuclide distribution in the environment of coastal Karnataka were undertaken to provide baseline data for the future assessment of the impact of the nuclear and thermal power stations that are being set up in the region and to understand the behaviour of radionuclides in the environment. As part of the programme the concentrations of two important artificial radionuclides, namely {sup 90}Sr and {sup 137}Cs, have been measured in a number of environmental samples. The concentration of {sup 90}Sr is very low in most of the samples. Among the samples analysed for the concentration of {sup 137}Cs, soil samples showed elevated levels of activity in some sampling stations. Among the vegetables, brinjal (Solanum melongena. L) showed considerable activity. The internal dose due to intake of {sup 90}Sr through diet was 0.42 {mu}Sv year{sup -1} for the vegetarian population and 0.32 {mu}Sv year{sup -1} for the non-vegetarian population. The internal dose due to dietary intake of {sup 137}Cs was found to be 0.34 {mu}Sv year{sup -1} and 0.26 {mu}Sv year{sup -1} respectively for the vegetarian and non-vegetarian population. The results are discussed in the light of the literature values reported for other environs of India and abroad and appropriate inferences are drawn. (author)

  7. Whole-body measurements of workers occupationally exposed to radionuclides at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Cardoso, Joaquim Carlos S.; Xavier, Marcos

    2015-01-01

    The intake of radioactive material by workers can occur in the radiopharmaceuticals production, during the handling of these in the medical fields (nuclear medicine) and in biological and research laboratories. The workers who work in areas where exposures are significant are routinely monitored to demonstrate that the workers are receiving adequate protection from internal contamination. Direct measurements of whole-body and thyroid contents provide an estimate of the activity of these radionuclides in the potentially exposed workers. The whole-body measurements of the workers, trainees and visitors are routinely performed by the In Vivo Monitoring Laboratory (LMIV) of the Energy and Nuclear Research Institute (IPEN/CNEN-SP). The frequency of measurements is defined by the Radioprotection Service (SRP) and the Dose Calculation Group of IPEN. For this purpose LMIV has two counters, whole body. NaITl (8 x 4”), and thyroid one, NaITl (3 x 3”). The system was calibrated in energy and efficiency, with calibration sources of Eu-152, Am-241 and Co-60 with gamma emissions between 59.54 and 1408.08 keV, positioned within Alderson Research Labs. anthropomorphic phantom. The background measures were obtained of worker's spectrum that was not exposed occupationally yet. The concepts adopted in the HPS N13.30 Standard and proposed in ISO documents for standardization were used for activity measurements. During the period January 2010 to December 2014, approximately 4500 measurements had been carried in workers who develop tasks related to the production and research. The activities of the radionuclides and the workers' tasks relationship had been evaluated. (author)

  8. Whole-body measurements of workers occupationally exposed to radionuclides at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Cardoso, Joaquim Carlos S.; Xavier, Marcos

    2013-01-01

    The intake of radioactive material by workers can occur in the radiopharmaceuticals production, during the handling of these in the medical fields (nuclear medicine) and in biological and research laboratories. The workers who work in areas where exposures are significant are routinely monitored to demonstrate that the workers are receiving adequate protection from internal contamination. Direct measurements of whole-body and thyroid contents provide an estimate of the activity of these radionuclides in the potentially exposed workers. The whole-body measurements of the workers, trainees and visitors are routinely performed by the In Vivo Monitoring Laboratory (LMIV) of the Energy and Nuclear Research Institute (IPEN/CNEN-SP). The frequency of measurements is defined by the Radioprotection Service (SRP) and the Dose Calculation Group of IPEN. For this purpose LMIV has two counters, whole body. NaIT1 (8x4″), and thyroid one, NaIT1 (3x3″). The system was calibrated in energy and efficiency, with calibration sources of Eu-152, Am-241 and Co-60 with gamma emissions between 59.54 and 1408.08 keV, positioned within Alderson Research Labs. anthropomorphic phantom. The background measures were obtained of worker's spectrum that wasn't exposed occupationally yet. The concepts adopted in the HPS N13.30 Standard and proposed in ISO documents for standardization were used for activity measurements. During the period January 2007 to December 2012, approximately 6700 measurements had been carried in workers who develop tasks related to the production and research. The activities of the radionuclides and the workers' tasks relationship had been evaluated. (author)

  9. Comparison of equilibrium radionuclide and contrast angiographic measurements of left ventricular peak ejection and filling rates and their time intervals

    Energy Technology Data Exchange (ETDEWEB)

    Sugrue, D.D.; Dickie, S.; Newman, H.; Myers, M.J.; Lavender, J.P.; McKenna, W.J. (Royal Postgraduate Medical School, London (UK))

    1984-10-01

    A comparison has been made of the equilibrium radionuclide and contrast angiographic estimates of normalized peak rates of ejection (PER) and filling (PFR) and their time intervals in twenty-one patients with cardiac disorders. Contrast angiographic and radionuclide measurements of left ventricular ejection fraction (LVEF), PER and PFR correlated well but time intervals correlated poorly. Mean values for radionuclide LVEF, PER and PFR were significantly lower and radionuclide time intervals were significantly longer compared to contrast angiography measurements.

  10. Intercomparison of radionuclide measurements in marine sediment sample IAEA-367

    Energy Technology Data Exchange (ETDEWEB)

    Ballestra, S; Lopez, J J; Gastaud, J; Vas, D; Noshkin, V

    1991-08-01

    The results of an intercomparison exercise on a Pacific Ocean sediment sample, IAEA-367, designed for the determination of artificial and natural radionuclides levels, are reported. The data from 81 laboratories representing 37 countries have been evaluated. The following are the recommended values, with confidence intervals, for {sup 60}Co, {sup 90}Sr, {sup 137}Cs, {sup 239+240}Pu (Reference date: 1 January 1990). Information values for {sup 155}Eu, {sup 238}Pu, {sup 241}Am, and {sup 241}Pu are reported. Information values for the following natural radionuclides {sup 40}K, {sup 226}Ra, {sup 228}Th, {sup 230}Th, {sup 234}U, {sup 235}U and {sup 238}U are also reported. (author)

  11. Thin-target excitation functions: a powerful tool for optimizing yield, radionuclidic purity and specific activity of cyclotron produced radionuclides

    International Nuclear Information System (INIS)

    Bonardi, M.L.

    2002-01-01

    In accelerator production of radionuclides, thin-target yield, y(E), is defined as a function of the projectile energy E, at the End Of an Instantaneous Bombardment (EOIB), as the slope at the origin of the growing curve of the activity per unit beam current (A/I) of a specific radionuclide vs. irradiation time, for a target in which the energy loss is negligible with respect to the projectile energy itself. In practice, y(E) is defined as the second derivative of A/I with respect to particle energy and irradiation time, calculated when the irradiation time tends to zero (EOIB). The thin-target yields of different radionuclides, produced by direct and side reactions, are numerically fitted, taking into account the overall statistical errors as weights. The 'effective' cross-section σ ± (E) as a function of projectile energy is proportional to thin-target yield, but the physical meaning of this parameter is poor, being only a raw summation of the several cross sections of the reaction channels concerned, weighted on target isotopic composition. Conversely, Thick-Target Yield, Y(E,ΔE), is defined as a two parameter function of the incident particle energy E(MeV) onto the target and the energy loss ΔE (MeV), in the target itself, obtained by integration of thin-target excitation function, y(E). This approach holds in the strict approximation of a monochromatic beam of energy E, not affected by either intrinsic energy spread or straggling. The energy straggling is computed by Monte Carlo computer codes, like TRIM 2001. In case of total particle energy absorption in the target, for a nuclear reaction of energy threshold E th , the function Y(E,ΔE) reaches a value Y(E,E- E th ), for ΔE=E- E th , that represents mathematically the envelope of the Y(E,ΔE) family of curves. This envelope is a monotonically increasing curve, never reaching either a maximum or a saturation value, even if its slope becomes negligible for high particle energies and energy losses. Some

  12. measurement of radionuclides in processed mine tailings in jos

    African Journals Online (AJOL)

    DR. AMINU

    The mine tailings are associated with radioactive minerals as impurities such as monazite, zircon among others. ... milling. A total of thirty-one (31) tailing samples were collected from a processing site in Jos at ... radioactive elements remain active for a very long period of time ..... Measurement of Radioactivity levels in soil.

  13. Automatic procedure go keep updated the activity levels for each radionuclide existing in a radioactivity laboratory

    International Nuclear Information System (INIS)

    Los Arcos, J.M.

    1988-01-01

    An automatic procedure to keep updated the activity levels each radionuclide existing in a radioactivity laboratory, and its classification according to the Spanish Regulations on Nuclear and Radioactive Establishments is described. This procedure takes into account the mixed composition of each source and whether it is sealed or the activity and mass variation due to extraction or evaporation in non-sealed sources. For a given date and time, the procedure prints out a complete listing of the activity of each radioactive source, the accumulated activity for each radionuclide, for each kind of radionuclide and the actual classification of the laboratory according to the legal regulations above mentioned. (Author)

  14. Monitoring intervals for measurement of the radionuclides 125 I and 129I in thyroid glands

    International Nuclear Information System (INIS)

    Simanca, Yoan Yera; Bejerano, Gladys M. Lopez

    2013-01-01

    This work shows the monitoring interval, which can be implemented in the Laboratorio de Contaminacion Interna del Centro de Proteccion e Higiene de las Radiaciones, for direct measurement in the thyroid gland of radionuclides 125 I and 129 I . Were used two measuring systems, one employing a scintillating detector and the other detector Phoswich. Both detectors were placed inside a depth camera, 2.5 x 2.5 x 2.5m of dimension covered with 15 cm of steel, 3 mm lead, 1.8 mm tin and 1.5 mm of copper. Was calculated for each system, the minimum detectable activity, and based on this, the monitoring interval is determined. Was obtained, for 125 , all tested intervals, 120, 90,60,30 , 14, and 7 days may be implemented with both systems. In the case of the radionuclide 129 I, with the installation of scintillating detector can only be implemented the intervals 120, 90, and 60 days , and for installation with Phoswich, all evaluated

  15. Measurement of Finger Blood Flow in Raynauds Phenomenon by Radionuclide Angiography

    International Nuclear Information System (INIS)

    Lim, Sang Moo; Chung, June Key; Lee, Myung Chul; Kim, Sang Joon; Choi, Sung Jae; Koh, Chang Soon

    1987-01-01

    In Raynauds phenomenon, the authors measured finger blood flow after ice water exposure by analyzing the time activity curve of radionuclide angiography on both hands. The results were as follows: 1) The digital blood flow did not decrease after ice water exposure in normal subjects. 2) In the patients with Raynauds phenomenon, there were two groups: the one had decreased digital blood flow after cold exposure, and the other had paradoxically increased digital blood flow after cold exposure. 3) There was no difference in the digital blood flow of hand in room temperature between the normal and the patients with reduced digital blood flow after cold exposure, but the digital blood flow of the hand in room temperature was markedly reduced in the patients with paradoxically increased flow after cold exposure. 4) In the static image the difference was not significant in comparison with the dynamic study, because it represents pooling of the blood in the vein rather than flow. 5) After the treatment with nifedipine, the digital blood flow increased. In conclusion, the radionuclide angiography was useful in measuring the digital blood flow in Raynauds phenomenon, and further studies with various drugs is expected.

  16. Radionuclides from the Fukushima accident in the air over Lithuania: measurement and modelling approaches.

    Science.gov (United States)

    Lujanienė, G; Byčenkienė, S; Povinec, P P; Gera, M

    2012-12-01

    Analyses of (131)I, (137)Cs and (134)Cs in airborne aerosols were carried out in daily samples in Vilnius, Lithuania after the Fukushima accident during the period of March-April, 2011. The activity concentrations of (131)I and (137)Cs ranged from 12 μBq/m(3) and 1.4 μBq/m(3) to 3700 μBq/m(3) and 1040 μBq/m(3), respectively. The activity concentration of (239,240)Pu in one aerosol sample collected from 23 March to 15 April, 2011 was found to be 44.5 nBq/m(3). The two maxima found in radionuclide concentrations were related to complicated long-range air mass transport from Japan across the Pacific, the North America and the Atlantic Ocean to Central Europe as indicated by modelling. HYSPLIT backward trajectories and meteorological data were applied for interpretation of activity variations of measured radionuclides observed at the site of investigation. (7)Be and (212)Pb activity concentrations and their ratios were used as tracers of vertical transport of air masses. Fukushima data were compared with the data obtained during the Chernobyl accident and in the post Chernobyl period. The activity concentrations of (131)I and (137)Cs were found to be by 4 orders of magnitude lower as compared to the Chernobyl accident. The activity ratio of (134)Cs/(137)Cs was around 1 with small variations only. The activity ratio of (238)Pu/(239,240)Pu in the aerosol sample was 1.2, indicating a presence of the spent fuel of different origin than that of the Chernobyl accident. Copyright © 2011 Elsevier Ltd. All rights reserved.

  17. Rapid determination of radionuclide activity concentrations in contaminated drinking water

    International Nuclear Information System (INIS)

    Medley, P.; Ryan, B.; Bollhofer, A.; Martin, P.; International Atomic Energy Agency, Vienna

    2007-01-01

    As a result of an incident at the Ranger Uranium mine in which drinking water was contaminated with process water, it was necessary to perform quick analysis for naturally occurring uranium and thorium series radionuclide activity concentrations, including 226Ra, 210Pb, 210Po, U and Th isotopes. The methods which were subsequently used are presented here. The techniques used were high-resolution gamma spectrometry, Inductively Coupled Plasma Mass Spectrometry (ICPMS) and high-resolution alpha spectrometry. Routine methods were modified to allow for rapid analyses on priority samples in 1-2 days, with some results for highest priority samples available in less than 1 day. Comparison of initial results obtained through standard procedures, is discussed. An emphasis is placed on high-resolution alpha spectrometry of major alpha-emitting nuclides, specifically 226Ra, 230Th and 238U. The range of uranium concentrations in the samples investigated was from background levels to 6.6ppm. Implications for radiological dose assessment in contamination incidents involving process water are presented. The worst-case scenario for the incident at Ranger Uranium Mine indicates that the maximum committed effective dose to workers was well below the ICRP limit for worker-related dose and below the dose limit for a member of the public, with 230Th being the highest contributor

  18. Intercomparison of radionuclide measurements in marine sediment sample IAEA-368

    International Nuclear Information System (INIS)

    Ballestra, S.; Lopez, J.J.; Gastaud, J.; Parsi, P.; Vas, D.; Noshkin, V.

    1991-08-01

    The results of an intercomparison exercise on a Pacific Ocean sediment sample, IAEA-368, designed for the determination of artificial and natural radionuclides levels, are reported. The data from 89 laboratories representing 37 countries have been evaluated. The following are the recommended values, with confidence intervals, for 60 Co, 155 Eu, 210 7Pb, 226 Ra, 238 U, 238 Pu and 239+240 Pu (Reference date: 1 January 1990). Information values for 40 K, 90 Sr, 137 Cs, 228 Th, 230 Th, 232 Th, 234 U, 235 U and 241 Am are also reported. (author)

  19. 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

  20. Measurement of radionuclides in food and the environment

    International Nuclear Information System (INIS)

    1989-01-01

    This guidebook is a production of the Fallout Radioactivity Monitoring in Environment and Food (MEF) Programme created by the IAEA in response to requests from Member States. The guidebook is divided into two parts. The first contains seven sections, including the introduction. Sections 2 and 3 provide general information on samples and radionuclides of interest. Laboratory equipment, space and personnel needed for radioanalyses are described in section 4. General instructions for sample collection and preparation are given in section 5. Sections 6 and 7 briefly discuss analytical methods and analytical quality control respectively. The second part of the guidebook is composed of ten annexes. The first four contain detailed methods for determination of gamma emitters collectively, strontium isotopes, tritium, and the isotopes of plutonium, americium and curium. Annex V provides a list of units and symbols; Annex VI gives information on radionuclide spectra in four types of nuclear accidents; nuclear data tables are listed in Annex VII; an example of a sample collection programme is presented in Annex VIII; some examples of NaI- and HP-Ge gamma spectrometric systems are given in Annex IX; and potential suppliers of calibration sources and reference materials are listed in Annex X. Refs, figs and tabs

  1. Measurement of natural radionuclides in U.K. diet.

    Science.gov (United States)

    Smith-Briggs, J L; Bradley, E J

    1984-05-01

    The levels of radium-226, lead-210 and polonium-210 in the U.K. diet have been determined. The important food groups contributing to the intake of these radionuclides have been identified. Seventy-five percent of the daily intake of radium-226 is derived from beverages, cereals, other vegetables, bread, sugars and preserves. Seventy-five percent of the intake of lead-210 and polonium-210 is derived from bread, milk, cereals, beverages, other vegetables, sugars and preserves, and meat products. The average daily intakes of these radionuclides are tentatively calculated to be 30 mBq for radium-226 and 82 mBq for both lead-210 and polonium-210. These levels are compared with data from other countries. The annual effective dose equivalents resulting from the intakes are approximately 3 muSv for radium-226 and 54 muSv from lead-210 and polonium-210 together. The differences between these doses and other current estimates are discussed.

  2. Measurements of β or α emitter long lived radionuclides using inductively coupled plasma mass spectrometry

    International Nuclear Information System (INIS)

    Provitina, O.

    1993-01-01

    The measurement of long-lived radionuclides is highly important for characterizing nuclear wastes for their later storage. The main techniques for characterizing these isotopes are α spectrometry, β counting and γ spectrometry. The large period of these isotopes leads to low specific activity needing time consuming measurements in order to obtain significant signals. Moreover, the radiometric techniques are often limited by problems of interferences involving several steps of pretreatments. Among these steps, the specific extraction with crown ethers is highly selective for the separation of 99 Tc, 129 I and 135 Cs particularly. The radiometric techniques are here replaced by inductively coupled plasma mass spectroscopy (ICP-MS) the advantages of which are: few interferences, sensitivity which does not depend on the radiologic period as compared to radiochemistry. ICP-MS can then measure 237 Np in enriched uranium matrix and thereby reduce by a factor of 4 the sample pretreatment and the duration of the analysis usually performed by α spectrometry. Another technique, electrothermal vaporization (ETV), is consequently used. Crown ether extraction-ETV-ICP-MS is employed for measuring the long lived radionuclides 99 Tc and 129 I. The conditions of the extraction and the parameters of the ETV and the ICP-MS are studied and optimized. The methods optimized (extraction, electrothermal vaporization) are validated in the case of 99 Tc, in real samples. The spike method is required to quantify technetium, the quantification with calibration leading to bad results. The results obtained are in good agreement with the expected values. Extraction of technetium on anionic resin and its measurement by the spike method with pneumatic nebulization-ICP-MS is also performed on other samples. Measured values are also in agreement with expected values, but the method of extraction is more time consuming (half a day) than the extraction with crown ether (one hour). (author). 54 figs

  3. Environmental Management Department Quality Assurance Project Plan for Radionuclide Emission Measurements Project for compliance with National Emission Standards for Hazardous Air Pollutants (NESHAP)

    Energy Technology Data Exchange (ETDEWEB)

    Poole, D A

    1992-06-01

    This Quality Assurance Project Plan (QAPP) satisfies the quality assurance (QA) requirements in 40 CFR Part 61, Method 114, for ensuring that the radionuclide air emission measurements from the Y-12 Plant are representative; of a known precision and accuracy; and include administrative controls to ensure prompt response when emission measurements indicate an increase over normal radionuclide emissions. The QAPP ensures the quality of the Y-12 Plant radionuclide emission measurements data from the continuous samplers, breakthrough monitors, and minor radionuclide release points. The plan specifies the procedures for the management of the activities affecting the quality of the data for the Y-12 Plant Environmental Management Department (EMD) within the Health, Safety, Environment, and Accountability Division (HSEA).

  4. Environmental Management Department Quality Assurance Project Plan for Radionuclide Emission Measurements Project for compliance with National Emission Standards for Hazardous Air Pollutants (NESHAP)

    International Nuclear Information System (INIS)

    Poole, D.A.

    1992-06-01

    This Quality Assurance Project Plan (QAPP) satisfies the quality assurance (QA) requirements in 40 CFR Part 61, Method 114, for ensuring that the radionuclide air emission measurements from the Y-12 Plant are representative; of a known precision and accuracy; and include administrative controls to ensure prompt response when emission measurements indicate an increase over normal radionuclide emissions. The QAPP ensures the quality of the Y-12 Plant radionuclide emission measurements data from the continuous samplers, breakthrough monitors, and minor radionuclide release points. The plan specifies the procedures for the management of the activities affecting the quality of the data for the Y-12 Plant Environmental Management Department (EMD) within the Health, Safety, Environment, and Accountability Division (HSEA)

  5. Intercomparison of radionuclide measurements in marine sediment sample IAEA-135

    International Nuclear Information System (INIS)

    Ballestra, S.; Gastaud, J.; Lopez, J.J.; Parsi, P.; Vas, D.

    1993-08-01

    The results of an intercomparison exercise on a marine sediment from Irish Sea, IAEA-135, designed for the determination of artificial and natural radionuclides levels, are reported. The data from 151 laboratories representing 51 countries have been evaluated. The following are the recommended values, with confidence intervals, for 40 K, 60 Co, 134 Cs, 137 Cs, 154 Eu, 155 Eu, 226 Ra, 228 Ra, 232 Th, 238 Pu, 239+240 Pu (Reference date: 1 January 1992). Information values for 57 Co, 90 Sr, 106 Ru, 125 Sb, 210 Pb, 210 Po, 228 Th, 230 Th, 234 U, 235 U, 238 U and 241 Am are also reported. All values are expressed in Bq kg -1 dry weight. (author)

  6. Intercomparison of radionuclide measurements in marine sediment sample IAEA-135

    Energy Technology Data Exchange (ETDEWEB)

    Ballestra, S; Gastaud, J; Lopez, J J; Parsi, P; Vas, D

    1993-08-01

    The results of an intercomparison exercise on a marine sediment from Irish Sea, IAEA-135, designed for the determination of artificial and natural radionuclides levels, are reported. The data from 151 laboratories representing 51 countries have been evaluated. The following are the recommended values, with confidence intervals, for {sup 40}K, {sup 60}Co, {sup 134}Cs, {sup 137}Cs, {sup 154}Eu, {sup 155}Eu, {sup 226}Ra, {sup 228}Ra, {sup 232}Th,{sup 238}Pu, {sup 239+240}Pu (Reference date: 1 January 1992). Information values for {sup 57}Co, {sup 90}Sr, {sup 106}Ru, {sup 125}Sb, {sup 210}Pb, {sup 210}Po, {sup 228}Th, {sup 230}Th, {sup 234}U, {sup 235}U, {sup 238}U and {sup 241}Am are also reported. All values are expressed in Bq kg{sup -1} dry weight. (author)

  7. Intercomparison of radionuclide measurements in marine sediment sample IAEA-368

    Energy Technology Data Exchange (ETDEWEB)

    Ballestra, S; Lopez, J J; Gastaud, J; Parsi, P; Vas, D; Noshkin, V

    1991-08-01

    The results of an intercomparison exercise on a Pacific Ocean sediment sample, IAEA-368, designed for the determination of artificial and natural radionuclides levels, are reported. The data from 89 laboratories representing 37 countries have been evaluated. The following are the recommended values, with confidence intervals, for {sup 60}Co, {sup 155}Eu, {sup 210}7Pb, {sup 226}Ra, {sup 238}U, {sup 238}Pu and{sup 239+240}Pu (Reference date: 1 January 1990). Information values for {sup 40}K, {sup 90}Sr, {sup 137}Cs, {sup 228}Th, {sup 230}Th, {sup 232}Th, {sup 234}U, {sup 235}U and {sup 241}Am are also reported. (author)

  8. Intercomparison of radionuclide measurements on marine sediment sample IAEA-300

    International Nuclear Information System (INIS)

    Ballestra, S.; Gastaud, J.; Lopez, J.J.; Parsi, P.; Vas, D.

    1994-09-01

    The results of an intercomparison exercise on a sediment from Baltic Sea, IAEA-300, designed for the determination of artificial and natural radionuclides' levels, are reported. The data from 159 laboratories representing 51 countries have been evaluated. The following are the recommended values, with confidence intervals, 40 K, 60 Co, 125 Sb, 134 Cs, 137 Cs, 155 Eu, 210 Pb, 210 Po, 228 Ra, 234 U, 238 U, 239+240 Pu and 241 Am. Information values for 54 Mn, 90 Sr, 226 Ra, 228 Th, 230 Th, 232 Th, 235 U and 238 Pu are also reported. All values are given on the reference date of 1 January 1993 and expressed in Bq kg -1 dry weight. (author)

  9. Intercomparison of radionuclide measurements on marine sediment sample IAEA-300

    Energy Technology Data Exchange (ETDEWEB)

    Ballestra, S; Gastaud, J; Lopez, J J; Parsi, P; Vas, D

    1994-09-01

    The results of an intercomparison exercise on a sediment from Baltic Sea, IAEA-300, designed for the determination of artificial and natural radionuclides' levels, are reported. The data from 159 laboratories representing 51 countries have been evaluated. The following are the recommended values, with confidence intervals, {sup 40}K, {sup 60}Co, {sup 125}Sb, {sup 134}Cs, {sup 137}Cs, {sup 155}Eu, {sup 210}Pb, {sup 210}Po, {sup 228}Ra, {sup 234}U, {sup 238}U, {sup 239+240}Pu and {sup 241}Am. Information values for {sup 54}Mn, {sup 90}Sr, {sup 226}Ra, {sup 228}Th, {sup 230}Th, {sup 232}Th, {sup 235}U and {sup 238}Pu are also reported. All values are given on the reference date of 1 January 1993 and expressed in Bq kg{sup -1} dry weight. (author)

  10. Activity concentration of radionuclides in plants in the environment of western Ghats

    International Nuclear Information System (INIS)

    Manigandan, P. K.

    2009-01-01

    A field study on the transfer of primordial radionuclides 238 U, 232 Th, 40 K and fallout radionuclides 210 Po in different plant species in tropical forest of western Ghats environment is presented. Material and Methods: The Top storey, Second storey, Shrubs and epiphytic plant species were chosen and concentration of these radionuclides in plant and soil were measured by employing gamma ray spectrometer and alpha counter. Results: The concentration ratio shows the variation in different species while a wild plant Elaeocarpus oblongus and epiphytic plants indicated preferential uptake of these radionuclides. Conclusion: The dust trapped in the root system of. epiphytic plants could be used as bio indicator to monitor fallout radionuclides in the Western Ghats. The concentration of 232 Th and 40 K in leaves depends on the age of the leaves.

  11. A Bayesian approach to assess data from radionuclide activity analyses in environmental samples

    International Nuclear Information System (INIS)

    Barrera, Manuel; Lourdes Romero, M.; Nunez-Lagos, Rafael; Bernardo, Jose M.

    2007-01-01

    A Bayesian statistical approach is introduced to assess experimental data from the analyses of radionuclide activity concentration in environmental samples (low activities). A theoretical model has been developed that allows the use of known prior information about the value of the measurand (activity), together with the experimental value determined through the measurement. The model has been applied to data of the Inter-laboratory Proficiency Test organised periodically among Spanish environmental radioactivity laboratories that are producing the radiochemical results for the Spanish radioactive monitoring network. A global improvement of laboratories performance is produced when this prior information is taken into account. The prior information used in this methodology is an interval within which the activity is known to be contained, but it could be extended to any other experimental quantity with a different type of prior information available

  12. Tumour control probability (TCP) for non-uniform activity distribution in radionuclide therapy

    International Nuclear Information System (INIS)

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

    2008-01-01

    Non-uniform radionuclide distribution in tumours will lead to a non-uniform absorbed dose. The aim of this study was to investigate how tumour control probability (TCP) depends on the radionuclide distribution in the tumour, both macroscopically and at the subcellular level. The absorbed dose in the cell nuclei of tumours was calculated for 90 Y, 177 Lu, 103m Rh and 211 At. The radionuclides were uniformly distributed within the subcellular compartment and they were uniformly, normally or log-normally distributed among the cells in the tumour. When all cells contain the same amount of activity, the cumulated activities required for TCP = 0.99 (A-tilde TCP=0.99 ) were 1.5-2 and 2-3 times higher when the activity was distributed on the cell membrane compared to in the cell nucleus for 103m Rh and 211 At, respectively. TCP for 90 Y was not affected by different radionuclide distributions, whereas for 177 Lu, it was slightly affected when the radionuclide was in the nucleus. TCP for 103m Rh and 211 At were affected by different radionuclide distributions to a great extent when the radionuclides were in the cell nucleus and to lesser extents when the radionuclides were distributed on the cell membrane or in the cytoplasm. When the activity was distributed in the nucleus, A-tilde TCP=0.99 increased when the activity distribution became more heterogeneous for 103m Rh and 211 At, and the increase was large when the activity was normally distributed compared to log-normally distributed. When the activity was distributed on the cell membrane, A-tilde TCP=0.99 was not affected for 103m Rh and 211 At when the activity distribution became more heterogeneous. A-tilde TCP=0.99 for 90 Y and 177 Lu were not affected by different activity distributions, neither macroscopic nor subcellular

  13. Activity Concentrations of radionuclides in sea water in some Coastal Egyptian Regions and Their Public Health Impacts

    International Nuclear Information System (INIS)

    Sefien, S.M.; Abdel Malik, W.E.Y.; Ibrahim, A.S.; Yousef, S.K.

    2008-01-01

    Extensive investigations have been carried out monthly for one year period in order to find out the average activity concentrations of the natural radionuclide in some Egyptian coastal aquatic environment and to assess the annual radiation doses likely to be received by population near by. The determinations were mainly for the measurement of gross α, β and γ activities in sea water samples and some of its constituents. It has been found that; the average gross α, β and γ activities in sea water samples for the different studied locations ranged from (0-52) x 10 -3 ,(3-68) x10 -3 and (13-283) x10 -3 Bq.l -1 respectively but still below the recommended permissible limits in most locations. It was found that Rashid area posses the highest concentrations of uranium and thorium. The present results have shown that the radio activities of most of the locations are mainly due to naturally occurring radionuclide. No regular tendency increase was observed in activity concentrations of any particular radionuclide in the studied period. Calculations have shown that, the average external dose from the γ- emitting radionuclide is ranged over (0.5-177)x10 -3 nGy/hr with annual exposure dose ranged from (1.04-29)x10 -3 nGy in most locations except Rashid. This exposure dose does not present radiological injuries to the population

  14. Measurement of natural activity in peat ashes

    International Nuclear Information System (INIS)

    Suomela, J.

    1985-01-01

    High proportions of radioactive materials in peat ashes may involve radiation hazards during handling and deposition of these waste materials. Measurements have been performed to determine the content of radioactive materials in ashes from peat burning. The activities in fly ash and ''solid'' ash in seven peat-fired power plants in Sweden are presented. The methods of analysing and measuring peat ashes for activity from different radionuclides are described. The activity levels in ash samples are given

  15. Cosmogenic radionuclide 7Be in atmospheric fallouts, weather factors and solar activity

    International Nuclear Information System (INIS)

    Kungurov, F.R.

    2011-11-01

    Key words: 7 Be activity, atmospheric fallouts, solar activity, gamma spectroscopy. Subjects of research: cosmogenic radionuclide 7 Be in atmospheric fallouts and surrounding objects of environment, its migrational distribution connected to solar activity and weather meteorologic parameters of the region studied. Purpose of work: Defining correlation between atmospheric humidity and solar activity with concentration and distribution of cosmogenic radionuclide 7 Be. Methods of research: gamma-spectrometry method of activity measurements. The results obtained and their novelty: Cycle of research works on definition of concentration and migrational distribution of CRN 7 Be in Samarkand region during 2002-2005 was carried out for the first time. Volumetric activity of 7 Be in squat air layer of Samarkand was determined. Average density of 7 Be fallouts for the four years of studies was determined. Qualitative correlation bet ween 7 Be fallouts density variations and solar activity, expressed through Wolf number has been found. Qualitative correlation between 7 Be fallouts density variations and amount of precipitations has been found. Regularity in 7 Be concentration decrease towards north latitudes has been detected. Practical value: Developed scintillation method of 7 Be activity detection in atmospheric fallouts was used in works performed in the framework of republican grants 2F-No 1.2.3, CNT RUz PFNI 2F-No 2.1.39 and ITD-7-024. Methodology was used for the estimation of the velocity of erosion processes in the soils of different regions of Uzbekistan. Methodology is used in the works on 7 Be radioactivity measurements. Degree of embed and economic effectivity: Gained results replenish database on 7 Be isotope distribution on Earth regions and its role in formation of some processes, connected with meteorology, agronomy and radioecology of Samarkand region. Field of application: meteorology, agronomy and radioecology. (author)

  16. The effects of the marine biosphere and hydrosphere upon the specific activity of contaminant radionuclides

    International Nuclear Information System (INIS)

    Lowman, F.G.

    1969-01-01

    Fusion and fission products as well as neutron induced radionuclides will be produced by the use of nuclear explosives for excavation. Stable elements from the geological matrix which are vaporized at the time of detonation will be vented in the same form as the radionuclides and will dilute the radionuclides to different specific activities depending upon the yield and design of the explosive, the neutron flux, neutron cross-sections for the stable elements and the homogeneity of the rock. Radionuclides in the cloud and fallout may be further diluted by pulverized rock on which they plate although the chemical forms may or may not be the same. This fallout material may be deposited into the sea and will react with sea water and its contained salts to precipitate or co-precipitate some radionuclides and release others as colloids or solutes where they will be subject to further dilution by the stable elements in sea water. The radionuclides will be subjected to varying amounts of physical and chemical dilution according to the physical environmental parameters. In some estuarine and upwelling areas of high biological productivity, the radionuclides and corresponding stable elements may become incorporated into cycles involving the biosphere, hydrosphere and bottom sediments in which the added material will remain in the area for longer periods of time than that expected from physical mixing and dilution. (author)

  17. The effects of the marine biosphere and hydrosphere upon the specific activity of contaminant radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Lowman, F G [Puerto Rico Nuclear Center, Mayaguez (Puerto Rico)

    1969-07-01

    Fusion and fission products as well as neutron induced radionuclides will be produced by the use of nuclear explosives for excavation. Stable elements from the geological matrix which are vaporized at the time of detonation will be vented in the same form as the radionuclides and will dilute the radionuclides to different specific activities depending upon the yield and design of the explosive, the neutron flux, neutron cross-sections for the stable elements and the homogeneity of the rock. Radionuclides in the cloud and fallout may be further diluted by pulverized rock on which they plate although the chemical forms may or may not be the same. This fallout material may be deposited into the sea and will react with sea water and its contained salts to precipitate or co-precipitate some radionuclides and release others as colloids or solutes where they will be subject to further dilution by the stable elements in sea water. The radionuclides will be subjected to varying amounts of physical and chemical dilution according to the physical environmental parameters. In some estuarine and upwelling areas of high biological productivity, the radionuclides and corresponding stable elements may become incorporated into cycles involving the biosphere, hydrosphere and bottom sediments in which the added material will remain in the area for longer periods of time than that expected from physical mixing and dilution. (author)

  18. The thickness measuring methods by means of radionuclides

    International Nuclear Information System (INIS)

    Henker, W.

    1974-01-01

    The thickness measuring devices RMM 24004 produced in German Democratic Republic are described. They consist of measuring probe and central unit. The measuring probe contains radiator and measuring head, which consists of radiation detector and electrometric amplifier. They utilize absorption or backscattering of 147 Pm, 85 Kr, 90 Sr/ 90 Y, 106 Ru/ 106 Rh or 137 Cs radiation in interaction with atoms of measured material. A survey of typical applications is given. (Z.M.)

  19. Measurement of natural and artificial radionuclide concentrations in meat consumed in Hong Kong

    International Nuclear Information System (INIS)

    Mao, S.Y.; Yu, K.N.

    1995-01-01

    Radionuclides in meat are determined using the EG and G ORTEC photon spectrometer system. Most of the naturally occurring radionuclides are found to have specific activities below the detectable limit. For our samples, 40 K is found to have values ranging from 295-407 Bq/kg, 172-423 Bq/kg and 172-282 Bq/kg for beef, pork and chicken meat samples, respectively, while 137 Cs has values from 0.19-2 Bq/kg, 0.34-0.71 Bq/kg and 0.12-0.53 Bq/kg, respectively. The estimated weighted committed dose equivalent due to the ingestion of natural radionuclides and 137 Cs in meat is 137 Cs in both sexes are less than the level recommended by the International Commission on Radiological Protection. (author)

  20. Measurement of 238U and 232Th radionuclides in ilmenite and synthetic rutile

    Science.gov (United States)

    Idris, M. I.; Siong, K. K.; Fadzil, S. M.

    2018-01-01

    The only factory that currently processes ilmenite to produce synthetic rutile is Tor Minerals in Ipoh, Perak, Malaysia. These two minerals contain radioactive elements such as uranium and thorium. Furthermore, this factory was built close to the residential areas. Thus, the primary issues are radiation exposure attributed to the decay of the radionuclides. Hence, the objectives of this study are to measure the dose and to evaluate activity levels of uranium and thorium. Dose rates from surrounding area of factory indicate the normal range for both on the surface and 1 meter above the ground (0.3-0.7 μSv/hr) lower than the global range of 0.5-1.3 μSv/hr set by UNSCEAR. The mean activity levels of uranium and thorium for ilmenite are 235 Bq/kg and 503 Bq/kg while for synthetic rutile are 980 Bq/kg and 401 Bq/kg, respectively. The result shows that uranium activity levels of synthetic rutile is 4 times higher than ilmenite but it is still lower than the regulatory exemption limit of 1000 Bq/kg set by IAEA Basic Safety Standards. Even though the dose rates at the factory and the activity levels are within safe limits, safety precautions must be followed by the factory management to prevent any unwanted accident to occur.

  1. 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

  2. International symposium on low level measurements of radionuclides in the environment, 2004

    International Nuclear Information System (INIS)

    2004-01-01

    The International Symposium of Low-Level Measurements of Radionuclides in the Environment was held on April 19-23, 2004 in Guilin, China, and sponsored by the Chinese Nuclear Society. The articles are published in the form of abstracts, and the contents include: 1. special lectures; 2.Environmental Radioanalysis; 3. Concentration and migration of radionuclides; 4. Analysis with instrumentation and applications; 5. preparation of samples and trace in living beings; 6. Environment impact assessment and calculation of dose; 7. Decommissioning, monitoring in emergency condition and others

  3. Measurement of some water quality parameters related to natural radionuclides in aqueous environmental samples from former tin mining lake

    International Nuclear Information System (INIS)

    Zaini Hamzah; Masitah Alias; Ahmad Saat; Abdul Kadir Ishak

    2011-01-01

    The issue of water quality is a never ended issue and becoming more critical when considering the presence of natural radionuclides. Physical parameters and the levels of radionuclides may have some correlation and need further attention. In this study, the former tin mine lake in Kampong Gajah was chosen as a study area for its past historical background which might contribute to attenuation of the levels of natural radionuclides in water. The water samples were collected from different lakes using water sampler and some in-situ measurement were conducted to measure physical parameters as well as surface dose level. The water samples were analyzed for its gross alpha and gross beta activity concentrations using liquid scintillation counting and in-house cocktail method. Gross alpha and beta analyzed using in-house cocktail are in the range of 3.17 to 8.20 Bq/ L and 9.89 to 22.20 Bq/ L; 1.64 to 8.78 Bq/ L and 0.22 to 28.22 Bq/ L, respectively for preserved and un-preserved sample. The surface dose rate measured using survey meter is in the range of 0.07 to 0.21 μSv/ h and 0.07 to 0.2 μSv/ h for surface and 1 meter above the surface of the water, respectively. (Author)

  4. The radionuclides of primary coolant in HANARO and the recent activities performed to reduce the radioactivity or reactor pool water

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Minjin [HANARO Research Reactor Centre, Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

    1998-10-01

    In HANARO reactor, there have been activities to identify the principal radionuclides and to quantify them under the normal operation. The purposes of such activities were to establish the measure by which we can reduce the radioactivity of the reactor pool water and detect, in early stage, the abnormal symptoms due to the leakage of radioactive materials from the irradiation sample or the damage of the nuclear fuel, etc. The typical radionuclides produced by the activation of reactor coolant are N{sup 16} and Ar{sup 41}. The radionuclides produced by the activation of the core structural material consist of Na{sup 24}, Mn{sup 56}, and W{sup 187}. Of the various radionuclides, governing the radiation level at the pool surface are Na{sup 24}, Ar{sup 41}, Mn{sup 58}, and W{sup 187}. By establishing the hot water layer system on the pool surface, we expected that the radionuclides such as Ar{sup 41} and Mn{sup 56} whose half-life are relatively short could be removed to a certain extent. Since the content of radioactivity of Na{sup 24} occupies about 60% of the total radioactivity, we assumed that the total radiation level would be greatly reduced if we could decrease the radiation level of Na{sup 24}. However the actual radiation level has not been reduced as much as we expected. Therefore, some experiments have been carried out to find the actual causes afterwards. What we learned through the experiments are that any disturbance in reactor pool water layer causes increase of the pool surface radiation level and even if we maintain the hot water layer well, reactor shutdown will be very much likely to happen once the hot water layer is disturbed. (author)

  5. Development of autoradiographic method for measuring sorption of radionuclides on natural fracture surfaces

    International Nuclear Information System (INIS)

    Muuronen, S.

    1983-11-01

    On the basis of positive results about sorption of radionuclides in rock thin sections an autoradiographic method applicable for measurement sorption of radionuclides on rough rock surfaces was developed. There is no method available because 1) a plane film cannot be used because due to the roughness of rock surfaces 2) rock samples used in this investigation cannot be studied with microscopes and 3) autoradiogram cannot be studied fixed on the surface of a rock sample because the colours of the minerals in the sample will interfere with the interpretation. This report discusses experimental work done to find an useful proedure. In the development of the method main emphasis was put on investigation of the following steps: 1) preparation of the sample for equilibration and spiking; 2) properties of the covering paint for the rock surface and 3) testing of autoradiographic methods using different nuclear emulsions. As the result of these experiments promising autoradiograms with gel emulsion for sawed rock surfaces and with stripping film for rough rock surfaces were obtained. The mineralogic disribution of sorbed activity is easily seen in autoradiograms. Much work must still be done to get reliable quantitative information from autoradiograms. For developing of the autoradiographic method sawed plane rock samples of quartz feldspar intergrowth, pegmatite and limestone were used. In addition core samples of tonalite and mica gneiss from Olkiluoto were utilized. The distribution coefficients (Ksub(a)) obtained for cesium were 560 x 10 -4 and 620 x 10 -4 m 3 /m 2 for tonalite and mica gneiss, respectively. The results are little higher but of the same order of magnitude as obtained by the autoradiographic method using rock thin sections and by the batch method using crused samples. The natural fracture surface sorption study is a logical step in determining the scaling factor from laboratory to field studies. Field data will be needed to determine whether laboratory

  6. Radionuclides measurements for the Phebus FP project - preliminary study

    International Nuclear Information System (INIS)

    Schuster, E.; Nopitsch, K.

    1989-09-01

    This report gives a review of proposed measurement techniques to measure quantitatively release and transport of fission products during and after fission product release tests. The measurement devices provided are for example gamma-spectrometers, scintillation counters and sampling vessels. The second part reviews the behaviour of fission product iodine under severe accident conditions and describes the iodine sampling system and the determination of iodine species in aqueous solutions

  7. Behaviour of natural radionuclides on activated carbon filter

    International Nuclear Information System (INIS)

    Haberer, K.; Akkermann-Kubillus, A.; Dahlheimer, A.

    1998-01-01

    To investigate the behaviour of radon in adsorption/desorption processes at filter systems based on different activated carbon types, measurements were focused on adsorption capacity, adsorption velocity, retain capability, interaction with ions (poisoning of active centers) and adsorption of radon daughters. Various activated carbon types derived from hard coal, brown coal, peat and wood, were used in adsorption tests runs with activated carbons which are applied in water treatment facilities. In laboratory tests, water facility filter conditions were simulated using pilot plant columns filled with different carbon types. A small scale laboratory column was installed at a natural water source with elevated activity. Tests runs were conducted under varying flow rates and with different amounts of carbon. A full-scale waterworks filter system operated for 6 months was investigated for radon decay products adsorbed on the carbon. The main results observed were: 1. The amount of radioactivity adsorbed depends upon the type of carbon, its granular size and the contact time between the activated carbon and water. The decontamination capacity was between 19% and 94%. 2. The DOC-levels of water influences the adsorbable radioactivity due to the poisoning of the active centers of the carbon. The adsorption velocity decreased down to 15%. 3. The maximum decontamination rate of the water under waterworks conditions was 60%. (orig.) [de

  8. Activation cross sections for the generation of long-lived radionuclides of importance in fusion reactor technology

    International Nuclear Information System (INIS)

    Wang Dahai

    1990-01-01

    The proceedings contain the progress reports of the Coordinated Research Programme to measure and evaluate the activation cross sections for the generation of long-lived radionuclides of importance in fusion reactor technology and the contributed papers (9) presented at the Consultants' Meeting held at Argonne National Laboratory between 11-12 September 1989. A separate abstract was prepared for each paper. Refs, figs and tabs

  9. Particle size distribution measurements of radionuclides from Chernobyl

    International Nuclear Information System (INIS)

    Georgi, B.; Tschiersch, J.

    1988-01-01

    Characteristics of the size distribution of the Chernobyl aerosol have been measured at four locations along the trajectory of the cloud. Changes in time and differences between 131 I and the other isotopes are explained by aerosol physical processes. The relevance of the measurements for dose calculations are discussed

  10. Airborne radionuclides of concern and their measurement in monitoring a Comprehensive Test Ban Treaty

    International Nuclear Information System (INIS)

    Perkins, R.W.; Miley, H.S.; Hensley, W.K.; Abel, K.H.

    1995-01-01

    The U.S. Department of Energy (DOE) is conducting radioanalytical developmental programs with the goal of providing near-real-time analysis technology for airborne signature radionuclides which are indicative of a nuclear weapons test in any of the earth's environments. If a test were conducted in the atmosphere or above the atmosphere, then the full spectrum of fission and activation products, together with residues from the device would be dispersed in the atmosphere. However, if a nuclear test were conducted underground or under water, the emission could range from a major to a very minor vent, and the material released would likely consist mainly of noble gas radionuclides and the radioiodines. Since many of the noble gases decay to form particulate radionuclides, these may serve as the more sensitive signatures. For example, Ba-140 is a daughter of Xe-140 (13.6 s), and Cs-137 is a daughter of Xe-137 (3.82 min). Both of these have been observed in large amounts relative to other fission products in dynamic venting of U.S. underground nuclear detonations. Large amounts of radionuclides are produced from even a comparatively small nuclear detonation. For example, a 10-KT fission device will produce approximately a megacurie of Ba-140 and of several other radionuclides with half-lives of days to weeks. If such a device were detonated in the atmosphere at midlatitude, it would easily be observable at downwind monitoring sites during its first and subsequent circumnavigations of the earth. Efficient and practical methods for the near-real-time analysis of both particulate and gaseous radionuclides are important to an effective monitoring and attribution program in support of a Comprehensive Test Ban Treaty (CTBT); methods for this purpose are being pursued

  11. Radionuclide Angiocardiographic Evaluation of Left-to-Right Cardiac Shunts: Analysis of Time-Active Curves

    International Nuclear Information System (INIS)

    Kim, Ok Hwa; Bahk, Yong Whee; Kim, Chi Kyung

    1987-01-01

    The noninvasive nature of the radionuclide angiocardiography provided a useful approach for the evaluation of left-to-right cardiac shunts (LRCS). While the qualitative information can be obtained by inspection of serial radionuclide angiocardiograms, the quantitative information of radionuclide angiocardiography can be obtained by the analysis of time-activity curves using advanced computer system. The count ratios method and pulmonary-to-systemic flow ratio (QP/QS) by gamma variate fit method were used to evaluate the accuracy of detection and localization of LRCS. One hundred and ten time-activity curves were analyzed. There were 46 LRCS (atrial septal defects 11, ventricular septal defects 22, patent ductus arteriosus 13) and 64 normal subjects. By computer analysis of time-activity curves of the right atriurn, ventricle and the lungs separately, the count ratios modified by adding the mean cardiac transit time were calculated in each anatomic site. In normal subjects the mean count ratios in the right atrium, ventricle and lungs were 0.24 on average. In atrial septal defects, the count ratios were high in the right atrium, ventricle and lungs, whereas in ventricular septal defects the count ratios were higher only in the right ventricle and lungs. Patent ductus arteriosus showed normal count ratios in the heart but high count ratios were obtained in the lungs. Thus, this count ratios method could be separated normal from those with intracardiac or extracardiac shunts, and moreover, with this method the localization of the shunt level was possible in LRCS. Another method that could differentiate the intracardiac shunts from extracardiac shunts was measuring QP/QS in the left and right lungs. In patent ductus arteriosus, the left lung QP/QS was higher than those of the right lung, whereas in atrial septal defects and ventricular septal defects QP/ QS ratios were equal in both lungs. From this study, it was found that by measuring QP/QS separately in the lungs

  12. Monitoring intervals for the measurement of the radionuclides 125I and 129I in the thyroid gland

    International Nuclear Information System (INIS)

    Yera Simanca, Yoan; Lopez Bejerano, Gladys M.; Ramos Machado, Dayana; Acosta Rodriguez; Nancy

    2014-01-01

    This paper shows the monitoring intervals that can be implemented in the Internal Contamination Laboratory of the Center for Radiation Protection and Hygiene for direct measurement of the radionuclides 125 I and 129 I in the Thyroid gland. Two measuring systems were used, one of them uses a scintillation detector and the other one uses a Phoswich detector. Both detectors were situated inside of one shielding chamber of 2.5 x 2.5 x 2.5 m of dimension, cover with 15 cm of steel, 3 mm of lead, 1.8 mm of tin, and 1.5 mm of copper. For each system was calculated the minimum detectable activity and in function of it were determined the monitoring intervals. The results obtained showed that for the radionuclide 125 I all the evaluated intervals (120, 90, 60, 30, 14 and 7 days).can be implemented with both systems. For the case of the radionuclide 129 I it can only be implemented the intervals (120, 90, and 60 days) using the scintillation detector and all of them with the Phoswich detector. (author)

  13. Production of high-specific activity radionuclides using SM high-flux reactor

    International Nuclear Information System (INIS)

    Karelin, Ye.A.; Toporov, Yu.G.; Filimonov, V.T.; Vakhetov, F.Z.; Tarasov, V.A.; Kuznetsov, R.A.; Lebedev, V.M.; Andreev, O.I.; Melnik, M.I.; Gavrilov, V.D.

    1997-01-01

    The development of High Specific Activity (HSA) radionuclides production technologies is one of the directions of RIAR activity, and the high flux research reactor SM, having neutron flux density up to 2.10 15 cm -2 s 1 in a wide range of neutron spectra hardness, plays the principal role in this development. The use of a high-flux reactor for radionuclide production provides the following advantages: production of radionuclides with extremely high specific activity, decreasing of impurities content in irradiated targets (both radioactive and non-radioactive), cost-effective use of expensive isotopically enriched target materials. The production technologies of P-33, Gd-153, W-188, Ni-63, Fe-55,59, Sn-113,117m,119m, Sr- 89, applied in industry, nuclear medicine, research, etc, were developed by RIAR during the last 5-10 years. The research work included the development of calculation procedures for radionuclide reactor accumulation forecast, experimental determination of neutron cross-sections, the development of irradiated materials reprocessing procedures, isolation and purification of radionuclides. The principal results are reviewed in the paper. (authors)

  14. Natural radionuclides in Austrian mineral water and their sequential measurement by fast methods

    International Nuclear Information System (INIS)

    Wallner, Gabriele; Wagner, Rosmarie; Katzlberger, Christian

    2008-01-01

    Ten samples of Austrian mineral water were investigated with regard to the natural radionuclides 228 Ra, 226 Ra, 210 Pb, 210 Po, 238 U and 234 U. The radium isotopes as well as 210 Pb were measured by liquid scintillation counting (LSC) after separation on a membrane loaded with element-selective particles (Empore TM Radium Disks) and 210 Po was determined by α-spectroscopy after spontaneous deposition onto a copper planchette. Uranium was determined by ICP-MS as well as by α-spectroscopy after ion separation and microprecipitation with NdF 3 . From the measured activity concentrations the committed effective doses for adults and babies were calculated and compared to the total indicative dose of 0.1 mSv/a given in the EC Drinking Water Directive as a maximum dose. The dominant portion of the committed effective dose was due to the radium isotopes; the dose from 228 Ra in most samples clearly exceeded the dose from 226 Ra

  15. Determination of the physiological root activity of fruit trees by means of the radionuclide 131I. 2

    International Nuclear Information System (INIS)

    Reckruehm, I.

    1976-01-01

    The rate of climb of the radionuclide per 1 m of stem vascular height was found to be dependent on the time of application; it came up to six to seven hours if applied in the morning, and 17 hours if applied in the evening. Limited information concerning the xylem transport activity was obtained through measuring the activity of a boring sample of stem fresh matter. Autoradiographic stem analysis provided the information most suitable for determining the transport routes in the stem. The analysis revealed that with increasing stem height the width of the radionuclide-labelled xylem is increasing 4.5 fold in proportion to the width when entering the stem. Beside the vertical climb there is some limited horizontal spread of the nuclide as well. (author)

  16. Radioactivity measurement of 18F in 16 ml vials for calibration of radionuclide calibrators

    International Nuclear Information System (INIS)

    Wurdiyanto, Gatot; Marsoem, Pujadi; Candra, Hermawan; Wijono, Paidi

    2012-01-01

    Fluorine-18 is obtained through the reaction 18 O(p, n) 18 F using a cyclotron that is situated in a hospital in Jakarta. Standardization of the 18 F solution is performed by gamma spectrometry using calibration sources of 152 Eu, 60 Co and 137 Cs that have traceability to the International System of units (SI). The activities in the 16 ml vials that were used for calibrating the radionuclide calibrators were between 1 and 2 GBq, with expanded uncertainties of 3.8%. The expanded uncertainty, at a coverage factor of k=2, on the derived calibration factor for the radionuclide calibrator was 6.6%. - Highlights: ► PTKMR–BATAN as a NMI of Indonesia is required to have procedures to calibrate the radionuclide calibrators. ► Standardizations were carried out on a solution of [ 18 F]FDG using gamma spectrometry. ► The volume of 18 F solutions used was 16 ml because this is the volume often used in hospitals. ► The Secondary Standard ionization chamber is a CRC-7BT Capintec radionuclide calibrator. ► A dial setting for 16 ml of [ 18 F]FDG solution in a vial is 443 for the Capintec dose calibrator.

  17. Gamma spectrometric validation of measurements test of radionuclides in food matrices

    International Nuclear Information System (INIS)

    Rosa, Mychelle M.L.; Custodio, Luis G.; Bonifacio, Rodrigo L.; Taddei, Maria Helena T.

    2013-01-01

    In a testing laboratory the quality system encompasses a set of activities planned and systematic, which ensure the traceability process of an analysis, which is based on the standards NBR ISO/TEC 17025. With the need for analysis of radionuclides in food products to meet the requirements of import and export, accreditation of testing on this standard becomes increasingly necessary. The Gamma Spectrometry is a technique used for direct determination of radionuclides in different matrices, among them the food, being possible the simultaneous determination of different radionuclides in the same sample without the need for a chemical separation. In the process of Accreditation the methodology validation is an important step that includes testing accuracy, traceability, linearity and recovery. This paper describes the procedures used to validate the assay for determining radionuclides using gamma spectrometry in food. These procedures were performed through analysis of a certificated reference material by the International Atomic Energy Agency (IAEA Soil 327), analysis of samples of milk powder prepared from the doping with certified liquid standards also by the results obtained in the participation of tests of proficiency in analysis of environmental samples. (author)

  18. 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

  19. 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)

  20. Quality assurance in the analysis of natural radionuclides - measures and results

    Energy Technology Data Exchange (ETDEWEB)

    Bothe, M [Nuclear Engineering and Analytics Rossendorf, Inc. (VKTA), Dresden (Germany)

    1997-03-01

    In the Laboratory for Environmental and Radionuclide Analytics we analyze several natural and also some artificial radionuclides in different materials. For the determination of radionuclides we use various analytical methods. (orig./DG)

  1. The measurement of released radionuclides during TIG-Welding and Grinding

    International Nuclear Information System (INIS)

    Reichelt, A.; Lehmann, K.-H.; Reineking, A.; Eder, E.

    2000-01-01

    The radiological relevance of the TIG welding using thoriated tungsten electrodes has recently been proved by means of different studies. As a result of this the TUEV Sueddeutschland and the University of Goettingen have carried out special investigations concerning the release of radionuclides during TIG welding. The main emphasis of these investigations were the representativity of various sampling techniques, the influence of various parameters during welding as well as the determination of activity size distributions related to the aerodynamic diameter of the inhaled aerosols. The properties of the tungsten rods are improved through the addition of radioactive thorium. We investigated the radiation exposure by handling with thoriated tungsten welding rods. We investigated the different exposure pathways and determined the specific activity in dependence to the different types of welding rods. By carrying out surveys with the users, we determined the exposure pathways for the individual exposed persons: TIG - hand-welders', TIG 'machine-welders', labourers, other persons. We measured the activity concentration of the breathing air while welding, at grinding the electrodes and by staying in the rooms where usually it's welded. The size distribution of the aerosol-attached activity was determined with several kinds of impactors. The main emphasis was the comparison of the different sampling systems at the measuring of the activity concentration of the breathing air. Selective sampling by impactors: · Berner-impactor, stationary · Sierra-impactor, stationary · Anderson-Imcaktor, stationary · Marple-impactor, personal sampler Aerosol sampling by air samplers · 5 personal air sampler · 2 stationary sampler, ring face · 2 stationary sampler, open face Rn-220-Measurements · Thoron-monitor Determination of activities on measuring filters · alpha spectrometry · low-level-gamma-spectrometry. For the various exposed persons, at the extern irradiation with gamma

  2. The measurement of released radionuclides during TIG-Welding and Grinding

    Energy Technology Data Exchange (ETDEWEB)

    Reichelt, A.; Lehmann, K.-H. [Technical Inspection Agency of Southern Germany (TUEV Sueddeutschland), Subdepartment Environmental Radioactivity, Munich (Germany); Reineking, A. [Isotope Laboratory for Biological and Medical Research, Georg-August-University of Goettingen, Goettingen (Germany); Eder, E. [Government of Bavaria, State Ministry for State Development and Environmental Affairs, Munich (Germany)

    2000-05-01

    The radiological relevance of the TIG welding using thoriated tungsten electrodes has recently been proved by means of different studies. As a result of this the TUEV Sueddeutschland and the University of Goettingen have carried out special investigations concerning the release of radionuclides during TIG welding. The main emphasis of these investigations were the representativity of various sampling techniques, the influence of various parameters during welding as well as the determination of activity size distributions related to the aerodynamic diameter of the inhaled aerosols. The properties of the tungsten rods are improved through the addition of radioactive thorium. We investigated the radiation exposure by handling with thoriated tungsten welding rods. We investigated the different exposure pathways and determined the specific activity in dependence to the different types of welding rods. By carrying out surveys with the users, we determined the exposure pathways for the individual exposed persons: TIG - hand-welders', TIG 'machine-welders', labourers, other persons. We measured the activity concentration of the breathing air while welding, at grinding the electrodes and by staying in the rooms where usually it's welded. The size distribution of the aerosol-attached activity was determined with several kinds of impactors. The main emphasis was the comparison of the different sampling systems at the measuring of the activity concentration of the breathing air. Selective sampling by impactors: {center_dot} Berner-impactor, stationary {center_dot} Sierra-impactor, stationary {center_dot} Anderson-Imcaktor, stationary {center_dot} Marple-impactor, personal sampler Aerosol sampling by air samplers {center_dot} 5 personal air sampler {center_dot} 2 stationary sampler, ring face {center_dot} 2 stationary sampler, open face Rn-220-Measurements {center_dot} Thoron-monitor Determination of activitys on measuring filters {center_dot} alpha

  3. Radionuclide measurement of urinary flow rates and residual urine in the evaluation of bladder outflow obstruction

    International Nuclear Information System (INIS)

    Groshar, D.; Embon, O.M.; Sazbon, A.; Koritny, E.; Frankel, A.

    1986-01-01

    A radionuclide method was developed to evaluate bladder outflow obstruction. Forty-seven patients with prostatic hypertrophy and 29 controls were studied. Urinary mean (MRF) and peak (PFR) flow rates were determined from the time-activity curves of bladder emptying. Residual urine (RU) was calculated by the volume voided and the bladder ejection fraction. A corrected PFR was calculated [CPFR = PFR/(vol. voided + RU)/sup 1/2/]. There was significant difference between patients and controls (MFR = 4 +- 2 vs. 9 +- 4 ml/sec, P <.001; PFR = 10 +- 6 vs. 20 +- 7, P <.001; CPFR = 0.57 +- 0.21 vs. 1.22 +- 0.32, P <.0001). RU was 13 +- 13 ml in controls and 155 +- 285 ml in patients (P <.01). CPFR was less than 0.89 in 94% of patients and 10% of controls, PFR was less than 14 ml/sec in 79% of patients and 17% of controls, and MFR was less than 7 ml/sec in 91% of patients and 21% of controls. The method enables good separation between patients and controls in a single examination that measures both flow and volume

  4. 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

  5. Activity concentrations of radionuclides in energy production from peat, wood chips and straw

    International Nuclear Information System (INIS)

    Hedvall, R.

    1997-04-01

    In this thesis quantitative analyses of radionuclide concentrations in bioenergy fuels such as peat, wood chips and straw are presented. For comparison a brief description is included of radionuclide concentrations and radiation doses from other sources of power and also from some industrial applications. Radioactive potassium is found in most materials and is the most easily detected radionuclide in fuels. It's activity concentration in Bq/kg normally dominates over the concentration of other natural radionuclides. The radiation dose from K in emission from combustion is nevertheless negligible. The most important radionuclides in the dose to man are the U- and Th-isotopes and 210 Pb and 210 Po. 137 Cs is the most common nuclide among the fission products in fallout from the Chernobyl accident. Compared to natural nuclides, the contribution from emission of 137 Cs is less than a few percent of the total dose to the population. A total dose of approx. only a few μSv from inhalation can be calculated from the emission of a district heating plant in Sweden. This dose can be compared with the annual dose limit to the public from nuclear industry, which is 0.1 mSv and the global collective effective dose of 5 manSv/year. 143 refs

  6. High resolution simultaneous measurements of airborne radionuclides in the pan-Japan sea area

    International Nuclear Information System (INIS)

    Yamaguchi, Y.; Abe, T.; Murata, Y.M.; Manikandan, N.; Tanaka, K.; Komura, K.

    2006-01-01

    By the use of ultra low background Ge detectors at Ogoya Underground Laboratory (OUL), it became possible to detect extremely low levels of environmental radionuclides. In this study, we tried to measure high resolution simultaneous measurements of airborne radionuclides at three monitoring points, i.e., 1) Low Level Radioactivity Laboratory (LLRL 40m asl) in Nomi City as the regular monitoring point, 2) Hegura Island Located 50 km from Noto Peninsula in the Sea of Japan to investigate the influence of Asian continent or mainland of Japan, and 3) Shishiku Plateau (640m asl) located about 8 km from LLRL to know vertical difference. Pb-210 and Be-7 were measured nondestructively by ultra low background gamma spectrometry at OUL, Po-210 by alpha spectrometry using Si detectors after the chemical treatment. Various interesting results on the concentrations and variation patterns of airborne radionuclides were obtained, particularly, during drastic meteorological changes such as the passage of typhoon, snow fall and so on. We have been analyzing the influence of the arrival of yellow sand occurred in this spring. (author)

  7. Update of the ongoing comparison BIPM.RI(II)-K1.Se-75 to include recent activity measurements of the radionuclide {sup 75}Se by the LNE-LNHB (France)

    Energy Technology Data Exchange (ETDEWEB)

    Michotte, C.; Courte, S.; Ratel, G. [Bureau International des Poids et Mesures (BIPM), Pavillon de Breteuil, F-92312 Sevres cedex (France); Moune, M.; Bobin, C. [Laboratoire national de metrologie et d' essais-Laboratoire National Henri Becquerel (LNE-LNHB), Gif-sur-Yvette Cedex (France)

    2011-06-15

    In 2006, to update their previous result of 1992, the LNE-LNHB submitted a new sample of {sup 75}Se with an activity of about 2.2 MBq to the International Reference System (SIR) for activity comparison at the Bureau International des Poids et Mesures (BIPM). This comparison has the identifier BIPM.RI(II)-K1.Se-75. The degree of equivalence between the equivalent activity measured in the SIR for the new LNE-LNHB sample and the updated key comparison reference value (KCRV) has been calculated, as have the degrees of equivalence with each of the other participants. The results are given in the form of a matrix and a graphical presentation is also given. (authors)

  8. Activity concentration of various radionuclides in tubificids living in the biobeds of a sewage treatment plant

    International Nuclear Information System (INIS)

    Erlandsson, A.; Erlandsson, B.; Mattsson, S.

    1988-04-01

    Oligochaeta belonging to the family Tubificidae are used in the biobeds of waste water treatment plants in the decomposition process of organic matter. Waste water treatment plants also receive radionuclides in the form of radiopharmaceuticals. The most commonly used radionuclides are 131 I and 99 Tc m . In this investigation the role of the Tubificids in the accumulation of these radionuclides has been studied. The activity concentration of 131 I in Tubificids was found to be 1-20 times higher than in the incoming waste water which is only 5-20% of the concentration factor between incoming water and outgoing sludge. Sludge is thus a more sensitive bioindicator, but Tubificids respond faster. (authors)

  9. Development of the k0-based cyclic neutron activation analysis for short-lived radionuclides

    NARCIS (Netherlands)

    Dung, H.M.; Blaauw, M.; Beasley, D.; Freitas, M.D.C.

    2011-01-01

    The k0-based cyclic neutron activation analysis (k0-CNAA) technique has been studied to explore the applicability at the Portuguese research reactor (RPI). In particular, for the determination of elements which form short-lived radionuclides, particularly fluorine (20F, 11.16 s half-life) and

  10. Measuring Physical Activity Intensity

    Medline Plus

    Full Text Available ... Physical Activity Basics Needs for Adults Needs for Children What Counts Needs for Older Adults Needs for ... Adding Physical Activity to Your Life Activities for Children Activities for Older Adults Overcoming Barriers Measuring Physical ...

  11. Measuring Physical Activity Intensity

    Medline Plus

    Full Text Available ... Adults Need More Physical Activity MMWR Data Highlights State Indicator Report on Physical Activity, 2014 Recommendations & Guidelines ... Activity Overweight & Obesity Healthy Weight Breastfeeding Micronutrient Malnutrition State and Local Programs Measuring Physical Activity Intensity Recommend ...

  12. Measuring Physical Activity Intensity

    Medline Plus

    Full Text Available ... Adults Needs for Children What Counts Needs for Older Adults Needs for Pregnant or Postpartum Women Physical Activity & ... to Your Life Activities for Children Activities for Older Adults Overcoming Barriers Measuring Physical Activity Intensity Target Heart ...

  13. Activity measurement algorithm in solid radioactive waste clearance procedure

    International Nuclear Information System (INIS)

    Hinca, R.; Skala, L.

    2014-01-01

    Most of European metrology experts prefer in radiation wastes characterization process to use scaling factor method in combination with high definition gamma spectrometry rather than radionuclide vector method in combination with gross gamma activity measurement. The second method is actually used in Slovakian nuclear facilities. The international (IAEA) and Slovak national authorities (UVZ) recognize both approach but there is a fact, that high definition gamma spectrometry radionuclides more properly. (authors)

  14. 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

  15. Measurement of sorption ratios for selected radionuclides on various geologic media

    International Nuclear Information System (INIS)

    MacLean, S.C.; Coles, D.G.; Weed, H.C.

    1978-09-01

    Experiments have been conducted to determine the sorptive characteristics of a variety of rocks and minerals with respect to several radionuclides of interest. This information will be used in the determination of the rates of radionuclide migration from nuclear waste repositories. The R/sub d/ values can be arranged according to the following inequalities: Pu greater than Cs, except for biotite; Cs greater than Sr, except for limestone; Sr greater than Tc. The exceptions are considered significant for Pu vs Cs on biotite, but not for Cs vs Sr on limestone. The low R/sub d/ values for Tc indicate that within the limits of measurement it is not sorbed under the experimental conditions studied

  16. Radionuclide adsorption distribution coefficients measured in Hanford sediments for the low level waste performance assessment project

    International Nuclear Information System (INIS)

    Kaplan, D.I.; Serne, R.J.; Owen, A.T.

    1996-08-01

    Preliminary modeling efforts for the Hanford Site's Low Level Waste-Performance Assessment (LLW PA) identified 129 I, 237 Np, 79 Se, 99 Tc, and 234 , 235 , 238 U as posing the greatest potential health hazard. It was also determined that the outcome of these simulations was very sensitive to the parameter describing the extent to which radionuclides sorb to the subsurface matrix, i.e., the distribution coefficient (K d ). The distribution coefficient is a ratio of the radionuclide concentration associated with the solid phase to that in the liquid phase. The objectives of this study were to (1) measure iodine, neptunium, technetium, and uranium K d values using laboratory conditions similar to those expected at the LLW PA disposal site, and (2) evaluate the effect of selected environmental parameters, such as pH, ionic strength, moisture concentration, and radio nuclide concentration, on K d values of selected radionuclides. It is the intent of these studies to develop technically defensible K d values for the PA. The approach taken throughout these studies was to measure the key radio nuclide K d values as a function of several environmental parameters likely to affect their values. Such an approach provides technical defensibility by identifying the mechanisms responsible for trends in K d values. Additionally, such studies provide valuable guidance regarding the range of K d values likely to be encountered in the proposed disposal site

  17. Update of the BIPM.RI(II)-K1.Tc-99m comparison of activity measurements for the radionuclide {sup 99m}Tc to include new results for the LNE-LNHB and the NPL

    Energy Technology Data Exchange (ETDEWEB)

    Michotte, C.; Courte, S.; Ratel, G. [Bureau International des Poids et Mesures (BIPM), 92 - Sevres (France); Moune, M. [LNE-LNHB, Laboratoire national de metrologie et d' essais-Laboratoire National Henri Becquerel, Gif sur Yvette (France); Johansson, L.; Keightley, J. [National Physical Laboratory (NPL), Middlesex (United Kingdom)

    2010-12-15

    In 2007 and 2008 respectively, the Laboratoire national de metrologie et d'essais -Laboratoire national Henri Becquerel (LNE-LNHB), France and the National Physical Laboratory (NPL), UK, submitted ampoules with between 10 MBq and 130 MBq activity of {sup 99m}Tc to the International Reference System (SIR), to update their results in the BIPM.RI(II)-K1.Tc-99m comparison. Together with the four other national metrology institutes (NMI) that are participants, thirteen samples have been submitted since 1983. The key comparison reference value (KCRV) has been recalculated to include the latest primary results of the PTB and the LNE-LNB as this makes the evaluation more robust. The degrees of equivalence between each equivalent activity measured in the SIR are given in the form of a matrix for all six NMIs. A graphical presentation is also given. (authors)

  18. Radiochemical Procedures Used at Iaea-Ilmr Monaco for Measuring Artificial Radionuclides Resulting from the Chernobyl Accident

    Science.gov (United States)

    Ballestra, S.; Gastaud, J.; Lopez, J. J.

    The Chernobyl accident which occurred on 26 April 1986 resulted in relatively high levels of radioactive fallout over the major part of Europe. Air filter and precipitation samples enabled us to follow the contamination from the accident. In addition contamination was also monitored in selected environmental samples such as seaweeds, sea water, sediment, soil, suspended matter and biological material from the Mediterranean. All samples were counted on Ge(Li) or Ge(HP) detectors to determine the type and quantity of gamma emitting radionuclides and plutonium, americium and curium isotopes were separated and measured using radiochemical techniques and alpha counting. Increased atmospheric radioactivity from the Chernobyl accident was first detected by observing increased activity levels on air filters taken on April 30, 1986, with maximum activities occurring during 1-3 May. Most of the radionuclides initially measured were short-lived fission products. Cs-137 was one of the predominant isotope in the fallout debris and its deposition at Monaco due to Chernobyl was estimated to be around 1400 Bq m-2, which represents 25-40% of the integrated fallout at this latitude. The deposition of Pu-239+240 was much smaller and was estimated to be around 10 mBq m-2 or only 0.1% of the total deposition from nuclear weapon testing.

  19. Measurements of radionuclide in Par Pond sediments with an underwater HPGe detector

    International Nuclear Information System (INIS)

    Winn, W.G.

    1993-01-01

    Savannah River Site (SRS) effluent gamma emitting radionuclides in Par Pond sediment were examined in situ with an underwater HPGe detector prior to and following a 19 ft drawdown of the pond in 1991 to address dam repairs. These measurements provide a map of the 137 Cs concentrations of the pond sediment, indicating that 9.4 ± 1.5 Ci is exposed by the drawdown and that 46.6 ± 7.2 Ci is the entire pond inventory. The highest individual 137 Cs concentration was 25 μCi/m 2 for the exposed sediment and 50 μCi/m 2 for the entire pond. The results are consistent with parallel studies conducted by SREL, as well as historical data. Aside from 137 Cs, the only other SRS-produced isotope observed was 60 Co, with activity of only about 1% of that for 137 Cs. This observation was also confirmed in grab samples of pond sediment and vegetation, which were returned to the laboratory for ultra-low-level gamma spectrometry analysis. A special effort was required to calibrate the underwater HPGe detector, where both measurements and calculational models were used. The effects of sediment depth profiles for density and 137 Cs concentration were addressed in the calibration. Calibration factors for sediment surface concentrations (μCi/m 2 /cpm) and sediment mass concentrations (pCi/kg/cpm) were obtained. In general, the μCi/m 2 /cpm factor is recommended, as the pCi/kg/cpm factor depends on the depth location of the sediment of interest. However, a pCi/kg/cpm factor, which is dependent on the depth within the sediment is presented to address dose calculations that require it

  20. Neutron activation of microspheres containing 165Ho: theoretical and experimental radionuclidic impurities study

    International Nuclear Information System (INIS)

    Squair, Peterson L.; Pozzo, Lorena; Ivanov, Evandro; Osso Junior, Joao A.

    2011-01-01

    The 166 Ho microspheres are potentially interesting for medical applications for treatment of many tumors. The internal radionuclide therapy can use polymer or glass device that provides structural support for the radionuclide. After activation, beta minus emission of 166 Ho (T 1/2 =26.8h, β - E max =1.84 MeV, γ E p =80.6 keV) can be used for therapeutic purposes. The aim of this work is study the influence of radionuclide impurities between End of Bombardment (EOB) and the medical application. The appropriate specific activities and purity along decay should be adequate for their safe and efficient medical applications. The good practices on neutron activation techniques are choice a high purity target to avoid production of undesirable radionuclides and when possible with enriched targets to obtain higher specific activity. In this work the target used was Ho 2 O 3 and polymeric microspheres containing holmium acetylacetonate (HoAcAc) manufactured at the Biotechnology Center-IPEN/CNEN-SP. Three conditions were evaluated: preliminary test with 1.0x10 13 n.cm -2 s -1 for 1.0 hour; nowadays maximum capability of IEA-R1 reactor with 5.0x10 13 n.cm -2 s -1 for 64.0 hours and the ideal IEA-R1 operation with 5.0x10 13 n.cm -2 s -1 for 120.0 hours. Considering the sample with 99.9% 165 Ho purity and 0.1% for each impurities elements with its natural abundance, the highest radionuclidic impurity is the Lutetium followed by Ytterbium, Lanthanum and Cerium. The intrinsic radionuclidic impurity of 166 mHo is less relevant. This review is important to identify the radionuclidic purity characteristics of the preliminary studies with different time and flux irradiation. The data produced in this paper will help to define strategies for the production of 166 Ho radioisotope at IEA-R1 IPEN/CNEN-SP reactor. (author)

  1. Measurement and Analysis of Specific Activities of Natural Radionuclides (40K, 226Ra and 232Th) in Beach Sand Samples from Talo Kapo Beach of Yaring District in Pattani Province using Gamma Ray Spectrometry

    Science.gov (United States)

    Daoh, M.; Masae, R. N.; Po-oh, S.; Boonkrongcheep; Kessaratikoon, P.

    2017-09-01

    The Specific Activities of 40K, 226Ra and 232Th were studied and determinate for 30 beach sand samples collected from Talo Kapo beach of Yaring district in Pattani province. Experimental results were obtained by using a high-purity germanium (HPGe) detector and gamma spectrometry analysis system. The IAEA-SOIL-6 reference materials obtained from the International Atomic Energy Agency were also used to analyze and compute the 40K, 226Ra and 232Th specific activity in all 30 beach sand samples. The measuring time of each sample is 10,000 seconds. It was found that specific activity range from 1805.37 - 3323.05, 40.96 - 2137.36 38.63 - 4329.28 Bq/kg for with mean values of 2242.79 ± 117.40, 250.18 ± 8.21 and 458.42 ± 7.68 Bq/kg for 40K, 226Ra and 232Th, respectively. Moreover, the results were also compared with research data in the south of Thailand, the Office of Atoms for Peace (OAP) annual report data and the recommended values which were proposed by United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR,)

  2. Radionuclides in man and his environment measured by accelerator mass spectrometry

    International Nuclear Information System (INIS)

    Hellborg, Ragnar; Erlandsson, Bengt; Kiisk, Madis; Persson, Per; Skog, Goeran; Stenstroem, Kristina; Mattsson, Soeren; Leide-Svegborn, Sigrid; Olofsson, Mikael

    1999-01-01

    Accelerator mass spectrometry (AMS) is a highly sensitive analytical method for measuring very low concentrations of both radionuclides and stable nuclides. For radioanalytical purposes, the main advantages of AMS compared to conventional radiometric methods are the use of smaller samples (mg size) and shorter measuring times (less than one hour). In this report some current applications of the AMS technique at the Lund Pelletron accelerator are presented, in particular studies of 14 C-labeled pharmaceuticals used in clinical nuclear medicine and biomedical research

  3. Distribution of natural radionuclides and radiation level measurements in Karnataka State, India. An overview

    International Nuclear Information System (INIS)

    Rangaswamy, D.R.; Sannappa, J.

    2016-01-01

    The exposure of human beings to ionizing radiation from natural sources is a continuing and inescapable feature of life on earth. A large number of natural radioactivity measurements were conducted throughout world, in order to know their distribution and to assess their radiological health hazards. In this regard, considerable studies have been conducted by different research groups in Karnataka state and more data are reported. In this article, all the studies of natural radioactivity measurements have been combined and reviewed. The majority of the reported articles are about monitoring, distribution and assessment of the radiological health hazards of naturally occurring radionuclides. (author)

  4. Methodology for monitoring radionuclide activity in waste waters

    International Nuclear Information System (INIS)

    Padilla, R.; Hernandez, R.; Fernandez, J.; Vizcaino, M.

    1996-01-01

    A procedure for the determination of the volumetric specific activity of the liquid effluents of the CEADEN was established. The waters of the retention tank are sampled weekly and analyzed by gamma and beta spectrometry, determining the activity of several isotopes used in the radiochemistry works

  5. New ways enhancing the vital activity of plants in order to increase crop yields and to suppress radionuclide accumulation

    International Nuclear Information System (INIS)

    Goncharova, N. V; Zebrakova, I. V.; Matsko, V. P.; Kislushko, P. M.

    1994-01-01

    After Chernobyl nuclear accident it has become very important to seek new ways of enhancing the vital activity of plants in order to increase crop yields and to suppress radionuclide accumulation. It is found that by optimizing the vital activity processes in plants, is possible to reduce radionuclide uptake. A great number of biologically active compounds have been tested, which increased the disease resistance of plants and simultaneously activated the physiological and biochemical processes that control the transport of micro- and macroelements (radionuclide included) and their 'soil-root-stem-leaf' redistribution. (author)

  6. Activation cross sections of longer-lived radionuclides produced in germanium by alpha particle irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Takács, S., E-mail: stakacs@atomki.hu [Institute for Nuclear Research, Hungarian Academy of Sciences, Atomki, 4026 Debrecen (Hungary); Takács, M.P.; Ditrói, F. [Institute for Nuclear Research, Hungarian Academy of Sciences, Atomki, 4026 Debrecen (Hungary); Aikawa, M. [Faculty of Science, Hokkaido University, Sapporo 060-0810 (Japan); Haba, H.; Komori, Y. [Nishina Center for Accelerator-Based Science, RIKEN, Wako, Saitama 351-0198 (Japan)

    2016-09-15

    The cross sections of alpha particles induced nuclear reactions on natural germanium were investigated by using the standard stacked foil target technique, the activation method and high resolution gamma spectrometry. Targets with thickness of about 1 μm were prepared from natural Ge by vacuum evaporation onto 25 μm thick polyimide (Kapton) backing foils. Stacks were composed of Kapton-Ge-Ge-Kapton sandwich target foils and additional titanium monitor foils with nominal thickness of 11 μm to monitor the beam parameters using the {sup nat}Ti(α,x){sup 51}Cr reaction. The irradiations were done with E{sub α} = 20.7 and E{sub α} = 51.25 MeV, I{sub α} = 50 nA alpha particle beams for about 1 h. Direct or cumulative activation cross sections were determined for production of the {sup 72,73,75}Se, {sup 71,72,74,76,78}As, and {sup 69}Ge radionuclides. The obtained experimental cross sections were compared to the results of theoretical calculations taken from the TENDL data library based on the TALYS computer code. A comparison was made with available experimental data measured earlier. Thick target yields were deduced from the experimental cross sections and compared with the data published before.

  7. Identification of Ambiguous Activities in Radionuclide Cisternography Using SPECT/CT: Aspirated and Ingested CSF Rhinorrhea

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong Yun; Kim, Jae Seung [Univ. of Ulsan College of Medicine, Ulsan (Korea, Republic of)

    2014-03-15

    A 2 year-old little girl underwent Tc-99m diethylenthriamine pentaacetic acid (DTPA) radionuclide cisternography to evaluate CSF rhinorrhea (Fig. 1). Cisternography clearly showed consecutive tracer activity in the nasal cavity and nasal tip, reflecting cerebrospinal fluid (CSF) leakage. However, several unexpected activities appeared on the bilateral mid- and unilateral lower thorax on delayed images, respectively. We performed additional SPECT/CT to delineate the CSF leakage tract and identify the unexpected activities. Through SPECT/CT, we could confirm that the mid-thoracic activity was in the lung parenchyma, while the lower thoracic activity was in the stomach. Thus, we speculated that these unexpected activities were the result of aspirated and ingested CSF rhinorrhea. CSF rhinorrhea occurs when there is a fistula between the dura mater and the skull base and discharge of CSF from the nose. A spinal fluid leak from the intracranial space to the nasal respiratory tract is potentially very serious because of the risk of an ascending infection that could produce fulminant meningitis. Therefore, identification of the fistulous tract is helpful for patient management. Radionuclide cisternography is an important imaging modality to detect the site of leakage in patients with CSF rhinorrhea. The combination of radionuclide cistenography and SPECT/CT has led to a major improvement in the diagnostic accuracy for localization of CSF leakage. This case also shows an important role for SPECT/CT fusion imaging in radionuclide cisternography not only for localizing the primary CSF fistula tract, but also for evaluating ambiguous radiotracer activities in planar imaging; these ultimately turned out to be aspirated and ingested CSF rhinorrhea.

  8. Identification of Ambiguous Activities in Radionuclide Cisternography Using SPECT/CT: Aspirated and Ingested CSF Rhinorrhea

    International Nuclear Information System (INIS)

    Lee, Dong Yun; Kim, Jae Seung

    2014-01-01

    A 2 year-old little girl underwent Tc-99m diethylenthriamine pentaacetic acid (DTPA) radionuclide cisternography to evaluate CSF rhinorrhea (Fig. 1). Cisternography clearly showed consecutive tracer activity in the nasal cavity and nasal tip, reflecting cerebrospinal fluid (CSF) leakage. However, several unexpected activities appeared on the bilateral mid- and unilateral lower thorax on delayed images, respectively. We performed additional SPECT/CT to delineate the CSF leakage tract and identify the unexpected activities. Through SPECT/CT, we could confirm that the mid-thoracic activity was in the lung parenchyma, while the lower thoracic activity was in the stomach. Thus, we speculated that these unexpected activities were the result of aspirated and ingested CSF rhinorrhea. CSF rhinorrhea occurs when there is a fistula between the dura mater and the skull base and discharge of CSF from the nose. A spinal fluid leak from the intracranial space to the nasal respiratory tract is potentially very serious because of the risk of an ascending infection that could produce fulminant meningitis. Therefore, identification of the fistulous tract is helpful for patient management. Radionuclide cisternography is an important imaging modality to detect the site of leakage in patients with CSF rhinorrhea. The combination of radionuclide cistenography and SPECT/CT has led to a major improvement in the diagnostic accuracy for localization of CSF leakage. This case also shows an important role for SPECT/CT fusion imaging in radionuclide cisternography not only for localizing the primary CSF fistula tract, but also for evaluating ambiguous radiotracer activities in planar imaging; these ultimately turned out to be aspirated and ingested CSF rhinorrhea

  9. Evaluation of an automated assay system to measure soil radionuclides by L x-ray and gamma-ray spectrometry

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Drennon, B.J.; Crowell, J.M.

    1982-08-01

    An automated radionuclide assay system for conducting soil radioassays using L x-ray and gamma-ray spectrometry was evaluated. Wet chemistry assay procedures were shown to be considerably more time consuming than similar analyses of soil on this radionuclide assay system. The detection limits of 241 Am and plutonium were determined, as well as the reproducibility of radionuclide assay results. The L x-ray spectrometric measurements were compared with radiochemical analyses on several tuff samples. The assay system's intrinsic germanium detector was found to respond linearly to varying low concentrations of 241 Am and plutonium, both of which were easily detected in the presence of elevated concentrations of 137 Cs

  10. BIPM comparison BIPM.RI(II)-K1.Zn-65 of activity measurements of the radionuclide 65Zn for the BARC (India) with linked results for the CCRI(II)-K2.Zn-65 comparison

    International Nuclear Information System (INIS)

    Michotte, C.; Ratel, G.; Courte, S.; Joseph, L.

    2015-01-01

    A new participation in the BIPM.RI(II)-K1.Zn-65 comparison has been added to the previous results. A link has been made to the CCRI(II)-K2.Zn-65 comparison held in 2003 through the measurement of all ampoules of the K2 comparison in the International Reference System (SIR) at the BIPM before despatch to the participants. This has produced a revised value for the key comparison reference value (KCRV), calculated using the power-moderated weighted mean. Six NMIs used the K2 comparison to update their degree of equivalence. The degrees of equivalence between each equivalent activity measured in the International Reference System (SIR) and the KCRV have been calculated and the results are given in the form of a table for the remaining two NMIs in the BIPM.RI(II)-K1.Zn-65 comparison and the 17 other participants in the CCRI(II)-K2.Zn-65 comparison. A graphical presentation is also given. (authors)

  11. Inspector measurement verification activities

    International Nuclear Information System (INIS)

    George, R.S.; Crouch, R.

    e most difficult and complex activity facing a safeguards inspector involves the verification of measurements and the performance of the measurement system. Remeasurement is the key to measurement verification activities. Remeasurerements using the facility's measurement system provide the bulk of the data needed for determining the performance of the measurement system. Remeasurements by reference laboratories are also important for evaluation of the measurement system and determination of systematic errors. The use of these measurement verification activities in conjunction with accepted inventory verification practices provides a better basis for accepting or rejecting an inventory. (U.S.)

  12. On iron radionuclide interactions and in situ measurement of iron corrosion products

    International Nuclear Information System (INIS)

    Puranen, A.; Jonsson, M.; Cui, D.; Scheidegger, A.M.; Wersin, P.; Spahiu, K.

    2005-01-01

    Full text of publication follows: In performance assessments of hard rock repositories, it is conservatively assumed that waste canisters are breached and that the spent fuel will get into contact with groundwater after 1000 years. When the canister eventually fails to protect HLW from groundwater, dissolved radionuclides from HLW will react with iron canister materials. The reactivity will depend on the conditions in solution and at the iron-water interface. To improve our understanding on the redox chemistry at near field conditions, batch experiments are conducted by contacting polished iron foils with a synthetic groundwater solution containing 10 mM NaCl, 2 mM NaHCO 3 and 5 ppm Se(IV), Se(VI), Tc(VII) and U(VI) in a glove box filled with Ar + 0.03% CO 2 gas mixture. The reaction rates are measured by analysing Se, Tc and U concentrations by ICP-MS. Iron corrosion products formed during the reaction(s) is monitored in-situ by a Layer Raman spectrometer through an optical window. The corrosion potential of the iron foil as well as the Eh and pH values of the bulk solution are recorded continuously during the experiment. The reacted iron foil is embedded with EPOXY resin, and the cross section will be analysed by SEM-EDS and XAS. The preliminary experimental results shows that with the formation of iron green rust FeII 4 FeIII 2 (OH) 12 CO 3 on iron foil, the rates of redox reactions between iron and the negatively charged radionuclides species are increased. The observation is explained by the fact that radionuclide anionic species can be first adsorbed then reduced on the positively charged outer surface of iron green rust. The positive charge is a result of the electrical balance of the negative charges of carbonate contained between the layered iron hydroxides in the green rust. Reduced forms of radionuclides are identified in the iron corrosion products. The results suggest that the formation of iron green rust as a corrosion product on the surface of iron

  13. 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

  14. Supernova-produced radionuclides in deep-sea sediments measured with AMS

    International Nuclear Information System (INIS)

    Feige, J.

    2014-01-01

    This thesis is dedicated to computational micromagnetics, where several new numerical methods are In this work a set of long-lived radionuclides is measured to detect supernova-traces presumably deposited on Earth 2-3 Myr ago. Approximately 100 samples of four deep-sea sediment cores (Indian Ocean) were analyzed for 26 Al, 53Mn, and 60 Fe with accelerator mass spectrometry (AMS). Additionally, 10 Be was measured to confirm the existing paleomagnetic chronology of the sediments. A signal of extraterrestrial 60 Fe, which is not produced in-situ on Earth, was detected in a time period of 1.7-3.2 Myr in the sediments used for this work. 60 Fe/ 26 Al ratios were used to calculate limits on theoretical nucleosynthesis models. A supernova-signature of 26 Al is hidden behind a terrestrial background. The measured 26 Al/ 10 Be ratios indicate, that the major source of 26 Al detected in the sediments is of atmospheric origin. Because of the extraordinarily good depth profile for the deep-sea sediments from the measured 26 Al data, this radionuclide was used for dating. (author) [de

  15. Validation of a method for radionuclide activity optimize in SPECT

    International Nuclear Information System (INIS)

    Perez Diaz, M.; Diaz Rizo, O.; Lopez Diaz, A.; Estevez Aparicio, E.; Roque Diaz, R.

    2007-01-01

    A discriminant method for optimizing the activity administered in NM studies is validated by comparison with ROC curves. the method is tested in 21 SPECT, performed with a Cardiac phantom. Three different cold lesions (L1, L2 and L3) were placed in the myocardium-wall for each SPECT. Three activities (84 MBq, 37 MBq or 18.5 MBq) of Tc-99m diluted in water were used as background. The linear discriminant analysis was used to select the parameters that characterize image quality (Background-to-Lesion (B/L) and Signal-to-Noise (S/N) ratios). Two clusters with different image quality (p=0.021) were obtained following the selected variables. the first one involved the studies performed with 37 MBq and 84 MBq, and the second one included the studies with 18.5 MBq. the ratios B/L, B/L2 and B/L3 are the parameters capable to construct the function, with 100% of cases correctly classified into the clusters. The value of 37 MBq is the lowest tested activity for which good results for the B/Li variables were obtained,without significant differences from the results with 84 MBq (p>0.05). The result is coincident with the applied ROC-analysis. A correlation between both method of r=890 was obtained. (Author) 26 refs

  16. Activity concentrations of radionuclides in energy production from peat, wood chips and straw

    Science.gov (United States)

    Hedvall, Robert Hans

    1997-11-01

    In this thesis quantitative analyses of radionuclide concentrations in bioenergy fuels such as peat, wood chips and straw are presented. For comparison a brief description is included of radionuclide concentrations and radiation doses from other sources of power and also from some industrial applications. Radiation is a natural phenomenon and radionuclides occur naturally. The first man-made spread of concentrated radioactivity occurred some 100,000 years ago when the first fireplace was lit, with fallout as a later consequence. Radioactive potassium is found in most materials and is the most easily detected nuclide in fuels. Its activity concentration in Bq kg-1 normally dominates over the concentration of other natural radionuclides. The radiation dose from potassium in the emission is nevertheless negligible. The most important radionuclides in the dose to humans are the U- and Th-isotopes and also 210Pb and 210Po. Of fission products in fallout from the atmospheric nuclear tests and after the Chernobyl accident, 137Cs was shown to be the most common nuclide. Compared to natural nuclides, the contribution from emission of 137Cs was shown to be the most common nuclide. Compared to natural nuclides, the contribution from emission of 137Cs is less than a few percent of the total dose to the population. A total dose of approximately a few μSv from inhalation only can be calculated from the emission of a district heating plant in Sweden. This dose can be compared with the annual dose limit to the public from nuclear industry, which is 0.1 mSv and the global collective effective dose of 5 person Sv a-1.

  17. Occupational exposure to natural radionuclides due to mining activities in Ibadan, Southwestern Nigeria

    International Nuclear Information System (INIS)

    Ademola, J.A.; Okpalaonwuka, N.E.

    2010-01-01

    The activity concentrations of potassium, uranium and thorium in minerals and soil samples from a mining site in Ibadan, Southwestern Nigeria were measured using gamma ray spectroscopy method. Effective dose per annum has been calculated from the activity concentrations of dominant gamma-emitting natural radionuclides, potassium, uranium and thorium. Samples collected include minerals (beryl, quartz and feldspar), soil samples from the mining pits, heaps and undisturbed land around the mining site. The activity concentrations of 40 K, 238 U and 232 Th, respectively in Bq kg-1 in the mineral samples were as follows: 1985 ± 16, 4.8 ± 0.9 and 11.8 ± 5.8 for beryl sample, 115.1 ± 27.9, 5.0 ± 1.3 and 6.3 ± 5.0 for feldspar samples and 1421 ± 122, 40 K, 238 U and 232 Th, respectively, were 314.2 ± 5.7, 27.7 ± 2.6 and 11.5 ± 5.9 Bq kg-1 for soil samples from the pits and 278.1 ± 5.4, 21.1 ± 2.0 and 15.3 ± 7.5 Bq kg-1 for soil samples from heaps. The mean activity concentrations of soil samples from the undisturbed land around the mining site were 194.3 ± 25.2, 14.5 ± 5.1 and 13.3 ± 5.9 Bq kg-1 for 40 K, 238 U and 232 Th, respectively. The effective dose to which the miners are exposed according to exposure scenarios were calculated as 89.9 μSv y-1 for digging and handling of soil and mineral samples in the pit and 63.6 μSv y-1 for handling of soil and mineral samples at the heaps. (authors)

  18. Measuring Physical Activity Intensity

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    Full Text Available ... Compartir For more help with what counts as aerobic activity, watch this video: Windows Media Player, 4: ... ways to understand and measure the intensity of aerobic activity: relative intensity and absolute intensity. Relative Intensity ...

  19. Intercomparison on the measurements of radionuclides in the ceramic brick of China

    International Nuclear Information System (INIS)

    Zhang Jing; Xu Cuihua; Zhang Qing

    2007-01-01

    Objective: To inspect the veracity and reiteration of γ-spectrometry in radioactive measurements. Methods: To be performed by multilateral intercomparison on measurements of radionuclides in two kinds of Chinese ceramic brick samples with γ-spectrometry between laboratories of Japan and of China. Results: The maximum difference of which the values measured by our laboratory related to the total average is 4.21%, and with an equipotent probability of positive and negative difference occurred. These showed that the veracity and reiteration of our measurement system are fine without obviously system errors. Conclusion: It has proved that the quality guarantee system and quality control technology of our γ-spectrum system is perfected and effective up to now. (authors)

  20. Measuring Physical Activity Intensity

    Medline Plus

    Full Text Available ... Older Adults Overcoming Barriers Measuring Physical Activity Intensity Target Heart Rate & Estimated Maximum Heart Rate Perceived Exertion ( ... a heavy backpack Other Methods of Measuring Intensity Target Heart Rate and Estimated Maximum Heart Rate Perceived ...

  1. Measuring Physical Activity Intensity

    Medline Plus

    Full Text Available ... Healthy Weight Breastfeeding Micronutrient Malnutrition State and Local Programs Measuring Physical Activity Intensity Recommend on Facebook Tweet Share Compartir For more help with what ...

  2. Design, fabrication and evaluation of a new calibration phantom for in vivo measurement of bone-seeking radionuclides (invited paper)

    International Nuclear Information System (INIS)

    Spitz, H.B.; Lodwick, J.

    2000-01-01

    A new anthropometric phantom has been developed for use in calibrating in vivo measurements of bone-seeking radionuclides. The phantom has the external shape and appearance of the human adult knee and contains a realistic femur, patella, tibia, and fibula. Unique formulations of polyurethanes, CaCo 3 , and other trace materials are used in construction of the phantom to produce substitutes for human tissue having the same density, attenuation coefficient, and effective Z as that of human muscle and trabecular bone. The formulation for trabecular bone includes provision for a precisely known quantity of radioactive material that is either uniformly distributed throughout the bone matrix or deposited on the exterior surface. The knee phantom is assembled in three interlocking sections that simplify inserting the skeletal structures and prevent streaming. One or more detectors can easily be positioned on the top or sides of the phantom. Intercomparison measurements of 241 Am in bone using separate arrays of phoswich and germanium detectors demonstrate that a single knee phantom exhibits the same detection efficiency as that using the skull. In vivo measurement of the knee is a desirable alternative to the head if facial contamination is present or when evaluating recent exposure to bone seeking radionuclides, since bones of the knee exhibit more rapid uptake than the skull. In practice, greater measurement efficiency can be obtained by placing detectors over both knees since a larger fraction of the total body activity is observed. Calibration measurements using the new anthropometric knee phantom demonstrate that it is durable, easy to use, and provides consistent results over repeated measurements. (author)

  3. Improving the control of systematic uncertainties in precision measurements of radionuclide half-life

    International Nuclear Information System (INIS)

    Towers, S.

    2013-01-01

    Many experiments designed to precisely determine the half-life of a radionuclide employ a long lived reference source to help determine the impact on the data of any systematic variation in the detector and associated electronics. The half-life of the radionuclide of interest is determined from the ratio of its decay rate data to the decay rate data from the reference source. This correction procedure assumes that any underlying systematic affects the data and reference measurements in exactly the same way. In this paper we show that when some systematic effects affect the two differently, the ratio procedure can leave artifacts in the corrected data that can compromise an unbiased and precise assessment of the radionuclide half-life. We describe two methods that can help overcome this problem. We also describe several statistical tests that help determine which effects may underlie systematic variations in the data. We discuss an illustrative example based on previously published 32 Si and 36 Cl data recorded by an experiment at Brookhaven National Laboratory. We correct the data for systematic variation related to climate variation and estimate the 32 Si half-life to be T 1/2 =171.8±1.8. The reduction in uncertainty in the 32 Si half-life, relative to the previous estimate based upon this data, is equivalent to that which would be achieved through increasing the size of the data set by almost 3.5 times. - Author-Highlights: • Isotope decay data and reference source data can have differing systematics. • Differing systematics can inflate uncertainty of isotope half-life estimate. • We describe two methods to overcome this problem. • We describe statistical tests to determine which variables cause systematics. • We analyze Brookhaven 32Si/36Cl decay data as an illustrative example

  4. The radiological situation at the atolls of Mururoa and Fangataufa. Technical report. V. 2. Radionuclide concentrations measured in the aquatic environment of the atolls

    International Nuclear Information System (INIS)

    1998-08-01

    A marine monitoring programme was carried out within the framework of the IAEA's project entitled ''Study of the Radiological Situation at Mururoa and Fangataufa Atolls'' with the aim of assessing present radionuclide concentrations in the marine environment of Mururoa and Fangataufa Atolls. The terms of reference of the marine working group (WG2) included a review of the data provided by the French authorities on radionuclide distributions in the littoral and sub-littoral environments at the atolls. Further, using accredited international laboratories, it was decided to carry out sufficient and new independent monitoring work at and around the atolls in order to validate existing French data and, the same time, to provide a representative and high quality data set on current radionuclide concentrations in the marine environment, with particular reference to the requirement of Task Group A for radiological assessment purposes. This work included measurements of the current radionuclide concentrations in the marine environment, and estimation of concentration factors and K d values appropriate for the region. The variations in activity concentrations in the lagoons over the past few years are discussed, and the likely sources of activity implied by these data are identified where possible

  5. Applications of neutron activation analysis in determination of natural and man-made radionuclides

    International Nuclear Information System (INIS)

    Byrne, A. R.; Benedik, L.

    1998-01-01

    Neutron activation analysis (NAA), being essentially an isotopic and not an elemental method of analysis, is capable of determining a number of important radionuclides of radioecological interest with good precision and accuracy, by transformation into another, more easily quantifiable radionuclide. The nuclear characteristics which favour this technique may be summarized in an advantage factor relative to radiometric analysis of the original radioanalyte. Well known or hardly known examples include 235 U, 238 U, 232 Th, 230 Th, 129 I, 99 Tc, 237 Np and 231 Pa; a number of these are discussed and illustrated in analysis of real samples of environmental and biological origin. The advantages and drawbacks of this technique relative to conventional radiometric analysis and newer, mass spectrometric methods is also discussed. The value of NAA as an independent method in certification of radionuclide reference materials (where much remains to be done) is stressed. Where direct sample analysis is possible, NAA retains the important advantage of being essentially blank-free. Where pre-separation of the analyte is necessary, some suggestions for improving the reliability of pre-separation yields using internal, activable tracers are proposed. The use of NAA to allow 238 U and 232 Th to be used as endogenous (internal) radiotracers in alpha spectrometric analyses of uranium and thorium radioisotopes in radioecological studies is described, also allowing independent data sets to be obtained, of great value in quality control. (author)

  6. Determination of scaling factors to estimate the radionuclide inventory in waste with low and intermediate-level activity from the IEA-R1 reactor

    International Nuclear Information System (INIS)

    Taddei, Maria Helena Tirollo

    2013-01-01

    Regulations regarding transfer and final disposal of radioactive waste require that the inventory of radionuclides for each container enclosing such waste must be estimated and declared. The regulatory limits are established as a function of the annual radiation doses that members of the public could be exposed to from the radioactive waste repository, which mainly depend on the activity concentration of radionuclides, given in Bq/g, found in each waste container. Most of the radionuclides that emit gamma-rays can have their activity concentrations determined straightforwardly by measurements carried out externally to the containers. However, radionuclides that emit exclusively alpha or beta particles, as well as gamma-rays or X-rays with low energy and low absolute emission intensity, or whose activity is very low among the radioactive waste, are generically designated as Difficult to Measure Nuclides (DTMs). The activity concentrations of these DTMs are determined by means of complex radiochemical procedures that involve isolating the chemical species being studied from the interference in the waste matrix. Moreover, samples must be collected from each container in order to perform the analyses inherent to the radiochemical procedures, which exposes operators to high levels of radiation and is very costly because of the large number of radioactive waste containers that need to be characterized at a nuclear facility. An alternative methodology to approach this problem consists in obtaining empirical correlations between some radionuclides that can be measured directly – such as 60 Co and 137 Cs, therefore designated as Key Nuclides (KNs) – and the DTMs. This methodology, denominated Scaling Factor, was applied in the scope of the present work in order to obtain Scaling Factors or Correlation Functions for the most important radioactive wastes with low and intermediate-activity level from the IEA-R1 nuclear research reactor. (author)

  7. Radionuclide detection and differential diagnosis of left-to-right cardiac shunts by analysis of time-activity curves

    International Nuclear Information System (INIS)

    Kim, Ok-Hwa

    1986-01-01

    The noninvasive nature of the radionuclide angiocardiography provided a useful approach for the evaluation of left-to-right cardiac shunts (LRCS). While the qualitative information can be obtained by inspection of serial radionuclide angiocardiograms, the quantitative information of radionuclide angiocardiography can be obtained by the analysis of time-activity curves using advanced computer system. The count ratios method and pulmonary-to-systemic flow ratio (QP/QS) by gamma variate fit method were used to evaluate the accuracy of detection and localization of LRCS. One hundred and ten time-activity curves were analyzed. There were 46 LRCS (atrial septal defects 11, ventricular septal defects 22, patent ductus arteriosus 13) and 64 normal subjects. By computer analysis of time-activity histograms of the right atrium, ventricle and the lungs separately, the count ratios modified by adding the mean cardiac transit time were calculated in each anatomic site. In normal subjects the mean count ratios in the right atrium, ventricle and lungs were 0.24 on average. In atrial septal defects, the count ratios were high in the right atrium, ventricle and lungs, whereas in ventricular septal defects the count ratios were higher only in the right ventricle and lungs. Patent ductus arteriosus showed normal count ratios in the heart but high count ratios were obtained in the lungs. Thus, this count ratios method could be separated normal from those with intracardiac or extracardiac shunts, and moreover, with this method the localization of the shunts level was possible in LRCS. Another method that could differentiate the intracardiac shunts from extracardiac shunts was measuring QP/QS in the left and right lungs. In patent ductus arteriosus, the left lung QP/QS was hight than those of the right lung, whereas in atrial septal defects and ventricular septal defects QP/QS ratios were equal in both lungs. (J.P.N.)

  8. Radionuclide activity and the immune system functioning in residents of radiation contaminated areas

    Directory of Open Access Journals (Sweden)

    V. L. Sokolenko

    2015-09-01

    Full Text Available The objective of this research is to assess the relation of radioactive contamination degree to immune system functioning, in the absence or presence of additional potential immunosuppressants. To achieve the objective, during the period of 1995–2015 we examined 250 people, students of Cherkasy State University, who lived in the areas of enhanced radiation monitoring before. Also we evaluated the additional impact of the emotional stress caused by examinations on examined students. Indicators of cellular immunity were determined by immunophenotyping and dyeing using Romanowsky-Giemsa method. The level of immunoglobulins in blood serum was determined by radial immunodiffusion (Mancini method. The level of cortisol in blood serum was determined by immunoenzyme method. We have found that in absence of the emotional stress among residents of the areas contaminated with radionuclides, cortisol level remained at the upper limit of homeostatic norm. There is an average positive correlation between the activity of radionuclides in the territories of residence and the level of cortisol. There are marked average positive correlations between the activity of radionuclides and the level of neutrophils, and low positive correlations with the levels of IgG and IgM in blood serum. Average negative correlations between the activity of radionuclides and the following parameters are also observed: absolute and relative number of functionally mature T-lymphocytes with phenotype CD3+, absolute and relative number of their helper subpopulation CD4+, absolute and relative number of natural killer cells with phenotype CD16+; and strong negative correlations with immunoregulatory index CD4+/CD8+. Cortisol level shows the similar correlation with the same parameters, but correlation coefficient is lower. Under conditions of additional stress, caused by emotional load during the examinations, cortisol level significantly increases. This enhanced previously discovered

  9. Measurement of absolute left ventricular volume by radionuclide angiography: a technical review

    International Nuclear Information System (INIS)

    Al-Khawaja, I.M.; Lahiri, Avijit; Raftery, E.B.; Medical Research Council, Harrow

    1988-01-01

    Absolute left ventricular volumes have important clinical implications in the evaluation of cardiac performance. Several invasive and noninvasive techniques have been reported, none of which can be considered ideal for this purpose. Contrast angiography, echocardiography and radionuclide ventriculography are open to criticism. Different radioisotopic approaches are described with emphasis on the importance of accurate separation of left ventricular activity, the selection of background activity, and the correction for photon attenuation by body tissues. Improper use of statistics and validation techniques have obscured the value of these techniques. In the absence of a 'gold standard' there should be a 'radioisotopic' left ventricular volume with established independent characteristics, repeatability and reproducibility by which new approaches can be judged. (author)

  10. 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

  11. Report on intercomparison IAEA/AG-B-1 of radionuclide measurements in marine algae sample

    International Nuclear Information System (INIS)

    1985-09-01

    This report includes results of the intercomparison exercise organized to enable analysts involved in measurements to check the analytical performance of their measuring methods on homogeneous seaweed material and also to establish reference values for radionuclides 40 K, 54 Mn, 58 Co, 60 Co, 65 Zn, 134 Cs, 137 Cs, 90 Sr, 99 Tc, 238 Pu, 239+240 Pu, 241 Am, 238 U, 230 Th, 226 Ra, 210 Pb, 210 Po, 232 Th, 228 Ra and 228 Th for the advantage of all those who need well-characterized standard material for calibration purposes. The sample of the brown alga Fucus vesiculosus from the coastal area of the Southwest Baltic near the Swedish nuclear plant at Barseback was made available for intercalibration in 47 laboratories in 26 countries. The results were obtained by gamma spectrometry, alpha spectrometry and beta counting

  12. 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

  13. Natural radionuclides in soils - relation between soil properties and the activities

    International Nuclear Information System (INIS)

    Fujiyoshi, Ryoko; Nakayama, Masashi; Sawamura, Sadashi

    2000-01-01

    Vertical profiles of natural radionuclides (K-40 and Ra-226) have been investigated in a soil core with 8 m in depth to elucidate its relation to the bed rock activity and to several soil properties. Pattern of the Ra-226 activity with soil depth suggests inhomogeneity of this nuclide during the accumulating process. Radiometric sorption experiments with Pb-210 as a tracer gave the result that almost all Pb(II) in the soil solution disappeared to be sorbed to the soil components

  14. Quality audit programme for {sup 99m}Tc and {sup 131}I radioactivity measurements with radionuclide calibrators

    Energy Technology Data Exchange (ETDEWEB)

    Joseph, Leena [Radiation Safety Systems Division, Bhabha Atomic Research Centre, Mumbai 400 085 (India)], E-mail: leena@barc.gov.in; Anuradha, R.; Kulkarni, D.B. [Radiation Safety Systems Division, Bhabha Atomic Research Centre, Mumbai 400 085 (India)

    2008-06-15

    The use of radiopharmaceuticals in nuclear medicine for diagnosis and therapy has increased over the years with {sup 99m}Tc and {sup 131}I being most widely used. Quality audit programmes for radioactivity measurements of {sup 131}I have been ongoing and the 12th audit was recently conducted among seventy nuclear medicine centres (NMC) in India. An audit for the activity measurements of {sup 99m}Tc was conducted for the first time among ten NMCs in Mumbai, India. These programmes for radioactivity measurements have become very important to establish traceability of measurements to national and international standards and ensure accurate calibration of radionuclide calibrators. The results of both the audits are very encouraging. Ninety-four percent of the NMCs for {sup 131}I activity measurements were within a window of {+-}10% and for {sup 99m}Tc one NMC was deviating more than {+-}10%. The methodology adopted for the audit and results are discussed in detail in this paper.

  15. Activity measurements of the radionuclide {sup 57}Co for the NMIJ, Japan and the LNE-LNHB, France in the ongoing comparison BIPM.RI(II)-K1.Co-57

    Energy Technology Data Exchange (ETDEWEB)

    Michotte, C.; Ratel, G.; Courte, S. [Bureau International des Poids et Mesures (BIPM), 92 - Sevres (France); Hino, Y.; Yunoki, A. [National Metrology Institute of Japan (NMIJ), National Institute of Advanced Industrial Science and Technology (AIST), Tsukuba, Ibaraki (Japan); Bobin, C.; Moune, M. [CEA Saclay, Laboratoire National de Metrologie et d' Essais, Laboratoire National Henri Becquerel (LNE-LNHB), 91 - Gif-sur-Yvette (France)

    2009-04-15

    In 2006 and 2007, the National Metrology Institute of Japan (NMIJ) and the Laboratoire national de metrologie et d'essais-Laboratoire national Henri Becquerel (LNE-LNHB) submitted samples of known activity of {sup 57}Co to the International Reference System (SIR). The values of the activity submitted were about 1.7 MBq and 3.7 MBq respectively. The new key comparison results have replaced the previous results for Japan and France. These new results have enabled a re-evaluation of the key comparison reference value. The matrix of degrees of equivalence in the key comparison database that now contains twelve results, identifier BIPM.RI(II)-K1.Co-57, has been updated with the new results. (authors)

  16. Measurements of Sr-90 radionuclide in Slovenian soils before and after Chernobyl accident

    International Nuclear Information System (INIS)

    Krizman, M.J.; Ambroz, S.

    2005-01-01

    Strontium-90 is a long-lived fission product (half life of 28,7 years) that is globally dispersed in the environment. It had been transported by air masses from the nuclear weapon tests sites in the period of 1951-1980 and also from Chernobyl (1986) and deposited elsewhere, especially over northern hemisphere. Contamination of surface layer (0-10 cm) of undisturbed soil in Slovenia was measured in the middle of the seventies (1973-75) and recently (2002). In parallel, long-lived radionuclide, Cs-137 was measured too, the second campaign was performed ten years after Chernobyl accident. Maps on Sr-90 and Cs-137 contents in soil were elaborated, showing different distributions of area contamination and different levels for a case of nuclear weapon tests and due to Chernobyl accident for both radionuclides. The past contamination from atmospheric nuclear tests Sr-90 and Cs-137 in Slovenian territory was characterised with the high values on western part of the country (with the exception of the coastal region) and typical values of 1,5-2 kBq/m 2 for Sr-90 and 3-4 kBq/m 2 for Cs-137. The Chernobyl accident raised the contamination with Cs-137 mostly in northwest part (Alpine region), with an average value of 20-25 kBq/m 2 for the country. Contamination with Sr-90 was much lower, the existing levels increased for about 0,2 kBq/m 2 . Recently measured levels of Sr-90 in the upper layer of soil hardly approach to 0,3 kBq/m 2 . (author)

  17. 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

  18. Measuring Physical Activity Intensity

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    Full Text Available ... using relative intensity, people pay attention to how physical activity affects their heart rate and breathing. The talk test is a simple way to measure relative intensity. ...

  19. Measuring Physical Activity Intensity

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  20. 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

    The use of ion chromatography (IC) for radiochemical separations is a well established technique. IC is commonly used in routine environmental monitoring applications as well as in specialized research applications. Typical usage involves the separation of a single radionuclide from the non-radioactive constituents. During the past decade, a limited amount of research has been conducted using automated IC systems in actinide separation applications (e.g.). More recently, separation procedures for common non-gamma emitting activation and fission products were developed utilizing a high performance liquid chromatography (HPLC) system. In addition, a separation procedure for six common actinides has been developed using a HPLC system. These latter systems used on-line flow-cell detectors for quantification of the radioactive constituents of the effluent stream

  1. Discriminant method for the optimization of radionuclide activity in studies of nuclear medicine

    International Nuclear Information System (INIS)

    Perez Diaz, Marlen

    2003-01-01

    It is presented a method for the optimization of the radionuclidic activity to administer to mature patients in studies of Nuclear Medicine. The method is based in technical of discriminant analysis to build a function that discriminates groups with image quality differed on the base of physical parameters as they are the contrast image and the aleatory noise. The image quality is the dependent variable and it is selected by means of experts' evaluation and technical of clustering. The function is a lineal combination of a reduced group of variables physical-medical, able to discriminate the groups starting from a big group of variables measures. The method allows, also, to establish the relative weight of each discriminant variable selected . The behavior of the same ones is analyzed among studies carried out with different administered activity, with the objective of determining the minimum value of this that still allows good results in the image quality (Approach of activity optimization). It is validated the method by means of results comparison with the grateful Curved ROC in studies carried out with the Mannequins of Jaszczak (for planar studies) and of Insert Heart (for studies of SPECT). The optim activity value of the 99mTc, obtained with the application of the method, was coincident with the one obtained after the application of the method ROC to 6 expert observers as much in planar studies as in SPECT for two different cameras gamma. The method was applied later on in static, dynamic studies and of SPECT carried out with camera gamma to a mature population of 210 patient. The decisive variables of the quality of the image were obtained in the nuclear venticulography in rest, the bony gammagraphy, the nuclear renogram, the renal gammagraphy and the cerebral SPECT, as well as some activity values optimized for the equipment conditions and available radiopharmac in the country, allowing to establish a better commitment relationship between image quality

  2. Performance evaluation of spectral deconvolution analysis tool (SDAT) software used for nuclear explosion radionuclide measurements

    International Nuclear Information System (INIS)

    Foltz Biegalski, K.M.; Biegalski, S.R.; Haas, D.A.

    2008-01-01

    The Spectral Deconvolution Analysis Tool (SDAT) software was developed to improve counting statistics and detection limits for nuclear explosion radionuclide measurements. SDAT utilizes spectral deconvolution spectroscopy techniques and can analyze both β-γ coincidence spectra for radioxenon isotopes and high-resolution HPGe spectra from aerosol monitors. Spectral deconvolution spectroscopy is an analysis method that utilizes the entire signal deposited in a gamma-ray detector rather than the small portion of the signal that is present in one gamma-ray peak. This method shows promise to improve detection limits over classical gamma-ray spectroscopy analytical techniques; however, this hypothesis has not been tested. To address this issue, we performed three tests to compare the detection ability and variance of SDAT results to those of commercial off- the-shelf (COTS) software which utilizes a standard peak search algorithm. (author)

  3. Materials interactions test methods to measure radionuclide release from waste forms under repository-relevant conditions

    International Nuclear Information System (INIS)

    Strickert, R.G.; Erikson, R.L.; Shade, J.W.

    1984-10-01

    At the request of the Basalt Waste Isolation Project, the Materials Characterization Center has collected and developed a set of procedures into a waste form compliance test method (MCC-14.4). The purpose of the test is to measure the steady-state concentrations of specified radionuclides in solutions contacting a waste form material. The test method uses a crushed waste form and basalt material suspended in a synthetic basalt groundwater and agitated for up to three months at 150 0 C under anoxic conditions. Elemental and radioisotopic analyses are made on filtered and unfiltered aliquots of the solution. Replicate experiments are performed and simultaneous tests are conducted with an approved test material (ATM) to help ensure precise and reliable data for the actual waste form material. Various features of the test method, equipment, and test conditions are reviewed. Experimental testing using actinide-doped borosilicate glasses are also discussed. 9 references, 2 tables

  4. Measurement of natural radionuclides in Malaysian bottled mineral water and consequent health risk estimation

    Energy Technology Data Exchange (ETDEWEB)

    Priharti, W.; Samat, S. B.; Yasir, M. S. [School of Applied Physics, Faculty of Science and Technology, Universiti Kebangsaan Malaysia, 43600 UKM Bangi, Selangor (Malaysia)

    2015-09-25

    The radionuclides of {sup 226}Ra, {sup 232}Th and {sup 40}K were measured in ten mineral water samples, of which from the radioactivity obtained, the ingestion doses for infants, children and adults were calculated and the cancer risk for the adult was estimated. Results showed that the calculated ingestion doses for the three age categories are much lower than the average worldwide ingestion exposure of 0.29 mSv/y and the estimated cancer risk is much lower than the cancer risk of 8.40 × 10{sup −3} (estimated from the total natural radiation dose of 2.40 mSv/y). The present study concludes that the bottled mineral water produced in Malaysia is safe for daily human consumption.

  5. Measurement of natural radionuclides in Malaysian bottled mineral water and consequent health risk estimation

    Science.gov (United States)

    Priharti, W.; Samat, S. B.; Yasir, M. S.

    2015-09-01

    The radionuclides of 226Ra, 232Th and 40K were measured in ten mineral water samples, of which from the radioactivity obtained, the ingestion doses for infants, children and adults were calculated and the cancer risk for the adult was estimated. Results showed that the calculated ingestion doses for the three age categories are much lower than the average worldwide ingestion exposure of 0.29 mSv/y and the estimated cancer risk is much lower than the cancer risk of 8.40 × 10-3 (estimated from the total natural radiation dose of 2.40 mSv/y). The present study concludes that the bottled mineral water produced in Malaysia is safe for daily human consumption.

  6. Progress in the methods for analyses and measurements of environmental radionuclides

    International Nuclear Information System (INIS)

    1984-01-01

    The tenth seminar on environment of the National Institute of Radiological Sciences was held in Chiba on December 9 and 10, 1982, under the joint auspices with Japan Health Physics Society. The recent progress of the measuring techniques for environmental radiation substances is remarkable. The Japanese data on environmental radiation presented to the UN Scientific Committee on the Effect of Atomic Radiation have obtained very high esteem because the data have been reliable due to the progress of measuring techniques. However, this field is in steady progress and changes rapidly, therefore, this seminar was planned. In this report, the history of the analysis and measurement of environmental radioactivity, the method of sampling and pretreatment operation for such environmental specimens as gaseous radionuclides, atmospheric floating dust, soil, agricultural products, sea water and sea bottom sediment, marine life, foods and living bodies, the progress of chemical separation process, the automation of analysis and measurement, the progress of the analysis of low level nuclides with long half-value period, the manual for the analysis and measurement, the quality of the analysis and measurement and its assurance are described. (Kako, I.)

  7. Measurement of left-to-right shunts by gated radionuclide angiography: concise communication

    International Nuclear Information System (INIS)

    Rigo, P.; Chevigne, M.

    1982-01-01

    Gated cardiac blood-pool scans allow comparison of left- and right-ventricular stroke volume. We have applied these measurements to the quantification of left-to-right shunts (QP/QS) in nine patients with atrial septal defects, one patients with partial anomalous pulmonary venous return, four patients with ventricular septal defects, and two patients with patent ductus arteriosus. None of these patients had combined lesions. QP/QS was measured as the right-ventricular (RV) stroke counts divided by the left-ventricular (LV) stroke counts and as the LV stroke counts divided by the RV stroke counts in patients with RV and LV diastolic volume overload respectively. All patients had also QP/QS measurements by oximetry and first-pass radionuclide angiography. The stroke-count measurements indicated the overloaded ventricle in all patients. QP/QS determined by equilibrium gated studies correlated well with those obtained by oximetry (r . 0.79). Reproducibility of the equilibrium measurements was good. We conclude that gated cardiac blood-pool scans can measure left-to-right shunts and can distinguish between shunts with RV and LV volume overload

  8. Radionuclides in terrestrial ecosystems

    International Nuclear Information System (INIS)

    Allen, S.E.; Horrill, A.D.; Howard, B.J.; Lowe, V.P.W.; Parkinson, J.A.

    1983-07-01

    The subject is discussed under the headings: concentration and spatial distribution of radionuclides in grazed and ungrazed saltmarshes; incorporation of radionuclides by sheep grazing on an estuarine saltmarsh; inland transfer of radionuclides by birds feeding in the estuaries and saltmarshes at Ravenglass; radionuclides in contrasting types of coastal pastures and taken up by individual plant species found in west Cumbria; procedures developed and used for the measurement of alpha and gamma emitters in environmental materials. (U.K.)

  9. Natural and active chemical remediation of toxic metals and radionuclides in the aquatic environment

    International Nuclear Information System (INIS)

    McPherson, G.; Pintauro, P.; O'Connor, S.; Zhang, J.; Gonzales, R.; Flowers, G.

    1993-01-01

    The focus of this research is the non-biological, chemical remediation of toxic heavy metals and radionuclides in aquatic environments. This Tulane/Xavier group includes researchers from Chemistry, Chemical Engineering, and Geology. Active methods using novel zeolites and ion exchange membranes are currently being evaluated for use in removing heavy metals from natural waters. In addition, field and laboratory studies of metal ion exchange reactions and competitive, heavy metal adsorption on clay substrates are underway to determine sediment metal sequestering capacity. A summary of progress to date and future work is presented

  10. Radionuclide transport in a single fissure

    International Nuclear Information System (INIS)

    Eriksen, T.E.

    1983-01-01

    Radionuclide migration have been studied in natural fissures orieted parallel to the axis of granite drill cores. A short pulse of the radionuclides solution was injected at one end of the fissure and the temporal change in radionuclide concentration of the eluate measured. After several hundred fissure volumes water had been pumped through the fissure following the radionuclide pulse the activity distribution on the fissure surfaces was measured. From the retardation of 152 Eu, 235 Np and 237 Pu it is concluded that these radionuclides are transported in the oxidation states Eu(III), Pu(IV) and Np(V). The distribution coefficients K sub (d) calculated from flow and activity distribution data on the basis of geometric surface area/volume ratios are of the same order as published K sub (d) values obtained from batch equilibrium experiments. (Author)

  11. Radiation protection measures for reduction of incorporations of iodine-131 by the staff of a radionuclide therapy ward

    International Nuclear Information System (INIS)

    Petzold, J.; Meyer, K.; Lincke, T.; Sabri, O.; Alborzi, H.; Lorenz, J.; Schoenmuth, T.; Keller, A.

    2009-01-01

    The air in patient's rooms with thyroid therapies is loaded with iodine 131, which is to be seen as a cause for the incorporation of iodine 131 by the staff. The patients exhale a part of the iodine applied for their intended radionuclide therapy. The activity is concentrated in the saliva and, thereby, the breath air is moistened and iodine reaches the exhaled and compartment air. The detection of iodine in the form of contaminations and/or incorporations with the staff succeeds only after a longer stay in the patient's room. With this, a clear relation between the particular type of work performed in the room and therapy of malignant thyroid disease with high amounts of radioactivity can be found. The measured values of incorporations, obtained with an whole-body counter, are in the range of up to 400Bq. The activity concentration in the compartment air some hours after application of the therapeutic activity reaches a maximum and then decreases with a half-life of about 15 hours. As a protection measure we asked the patients wearing a mask up to 30 hours after application to (orig.)

  12. 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...

  13. The activity of selected gamma radionuclides in the Tatra National Park

    Directory of Open Access Journals (Sweden)

    Kubica Barbara

    2017-01-01

    Full Text Available Cesium is naturally occurring active metal, represented by one stable isotope 133Cs, and number of artificial, unstable, isotopes. The most common artificial isotope of cesium is 137Cs, present in the environment of the Tatra Mountains due to nuclear weapon testing in late `50, and nuclear reactor accident in Chernobyl in 1986. However in recent years the growth in biofuels use for power generation can be the next source of 137Cs emission. Burning wood cultivated on grounds contaminated by 137Cs can introduce secondary emission of this isotope to the atmosphere.This paper presents the results of determination of gamma emitting radionuclides artificial 137Cs and natural 40K in soil samples from the Tatra Mountains. Results show some differences in the vertical distribution of examined radionuclides. It was found that the change of activity of 137Cs in the soil samples depends mostly on the soil density and on the concentration of organic material. The state of “zero” 137Cs activity was developed in the form of maps.

  14. Radionuclides in the food chain

    International Nuclear Information System (INIS)

    Harley, J.H.; Schmidt, G.D.

    1988-01-01

    Radionuclides in the Food Chain reviews past experience in meeting the challenge of radionuclide contamination of foodstuffs and water sources and, in the wake of the reactor accidents at Chernobyl and Three Mile Island, presents current concepts and programs relating to measurement, surveillance, effects, risk management, evaluation guidelines, and control and regulatory activities. This volume, based on a symposium sponsored by the International Life Sciences Institute in association with the International Institute for Applied Systems Analysis, which brought together both radiation experts and food industry policymakers, examines such vital topics as structural problems in large-scale crisis-managment systems; dose assessment from man-made sources; international recommendations on radiation protection; airborne contamination, as well as aquatic and soilborne radionuclides; food-chain contamination from testing nuclear devices; long-term health effects of radionuclides in food and water supplies; and use of mathematical models in risk assessment and management. (orig.)

  15. Radionuclide assay of membrane Na+, K+-ATPase activity of peserved red blood cells

    International Nuclear Information System (INIS)

    Trusov, V.V.; Zelenin, A.A.; Marizin, S.A.

    1986-01-01

    The radionuclide tests were used to investigate the influence of varying blood preservatives on erythrocylic membrane Na + , K + -ATPase activity in samples of whole blood and packed red blood cells from normal donors prepared by standard methods. The tests were performed before and after seven days of preservation under standard conditions. It was found that blood preservations lowered membrane Na + , K + -ATPase activity: its minimum reduction was recorded with citroglucopnosphate, while glugicir induced a significant drop in Na + , K + -ATPase activity of preserved red blood cells regardless of the type of the blood transfusion solution. The assay of membrane Na + , K + -ATPase activity of preserved red blood cells with the use of 86 Rb could be recommended as an evaluation test for preserved blood and its components

  16. Radioactivity measurement of primordial radionuclides in and dose evaluation from marble and glazed tiles used as covering building materials in Turkey

    International Nuclear Information System (INIS)

    Turhan, S.; Varinlioglu, A.

    2012-01-01

    Measurements of the natural radioactivity arising from primordial radionuclides ( 226 Ra, 232 Th and 40 K) in marble and glazed tile samples used covering building materials in Turkey were carried out by gamma-ray spectrometer with a high purity germanium detector. The mean activity concentrations of the 226 Ra, 232 Th and 40 K in marble and glazed tile samples were found as 8.2, 5.5 and 58.1 Bq kg -1 and 81.2, 65.4 and 450.1 Bq kg -1 , respectively. The radiation doses received by occupants of buildings in which the sample marble and glazed tiles might be used are estimated using measured activity concentrations of constituent primordial radionuclides and dose conversion factors evaluated by the European Commission from models of tile use. Results obtained are presented for each radionuclide, analysed and compared with relevant national and international legislation, guidance and report, and with the results obtained from other studies. Results show that the use of such decorative building materials in the construction of domestic homes or workplaces in Turkey is unlikely to lead to any significant radiation exposure to the occupants. (authors)

  17. Activity concentrations of primordial radionuclides in sediments of surface - water dams in southwest Nigeria - a baseline survey

    International Nuclear Information System (INIS)

    Isinkaye, M.O.; Farai, I.P.

    2008-01-01

    The radionuclide contents of sediment samples collected from 20 surface-water dams in southwestern Nigeria have been determined by low-level gamma-spectroscopy. The average concentration of 40 K in each of the dams varied between 110.9±11.9 Bq kg-1 and 1025.9±36.8 Bq kg -1 with an overall mean (±SD) of 549.3 ± 247.6 Bq kg -1 while that of 238 U varied from 17.1±3.6 to 51.9±8.7 Bq kg -1 with an overall mean (±SD) of 27.6±8.5 Bq kg -1 and that of 232 Th varied from 26.2 ±3.6 Bq kg -1 to 130.1±23.7 Bq kg -1 with overall mean (±SD) of 62.0±26.1 Bq kg -1 . The variability of the values shows the wide disparity in the measured activity concentrations. The mean radium equivalent of 158.9 Bq kg -1 was calculated for the sediments in the dams. No artificial gamma emitting radionuclide was detected in the samples. (authors)

  18. Harmonization of standards for permissible radionuclide activity concentrations in foodstuffs in the long term after the Chernobyl accident.

    Science.gov (United States)

    Balonov, Mikhail I; Kashparov, Valery; Nikolaenko, Elena; Berkovsky, Volodymyr; Fesenko, Sergey

    2018-04-16

    The article critically examines the practice of post-Chernobyl standardization of radionuclide concentrations (mainly 137Cs and 90Sr) in food products in the USSR and the successor countries of Belarus, Russia and Ukraine. Recommendations are given on potential harmonization of these standards of radionuclide concentrations in food products among three countries, taking into account substantial international experience. We propose to reduce the number of product groups for standardization purpose from the current several dozens to three to five groups to optimize radiation control and increase the transparency of the process. We recommend five product groups for the standardization of 137Cs and three groups for 90Sr in food in radiocontaminated areas. The values of standards for individual product groups are recommended to be set proportionally to the measured specific activity in each of these groups, which will reduce unreasonable food rejection. The standards might be set for the entire country, and could be also used to control imports from other countries as well as exports to other countries. The developed recommendations were transferred in 2015-2016 to the regulatory authorities of the three countries. © 2018 IOP Publishing Ltd.

  19. Summary of activation cross section measurements at FNS

    International Nuclear Information System (INIS)

    Ikeda, Y.; Konno, C.; Kasugai, Y.; Kumar, A.

    1996-01-01

    Neutron activation cross sections around 14 MeV for seventeen reactions have been measured at the FNS facility in JAERI in order to provide experimental data meeting the requirement in the radioactive wastes disposal assessment in the D-T fusion reactor. This report summarizes contributing data measured in several phases of experiments to the IAEA-CRP on ''Activation Cross sections for the Generation of Long-Lived radionuclides of Importance in Fusion Reactor Technology''. (author). 18 refs, 1 tab

  20. Radionuclide mass inventory, activity, decay heat, and dose rate parametric data for TRIGA spent nuclear fuels

    International Nuclear Information System (INIS)

    Sterbentz, J.W.

    1997-03-01

    Parametric burnup calculations are performed to estimate radionuclide isotopic mass and activity concentrations for four different Training, Research, and Isotope General Atomics (TRIGA) nuclear reactor fuel element types: (1) Aluminum-clad standard, (2) Stainless Steel-clad standard, (3) High-enrichment Fuel Life Improvement Program (FLIP), and (4) Low-enrichment Fuel Life Improvement Program (FLIP-LEU-1). Parametric activity data are tabulated for 145 important radionuclides that can be used to generate gamma-ray emission source terms or provide mass quantity estimates as a function of decay time. Fuel element decay heats and dose rates are also presented parametrically as a function of burnup and decay time. Dose rates are given at the fuel element midplane for contact, 3.0-feet, and 3.0-meter detector locations in air. The data herein are estimates based on specially derived Beginning-of-Life (BOL) neutron cross sections using geometrically-explicit TRIGA reactor core models. The calculated parametric data should represent good estimates relative to actual values, although no experimental data were available for direct comparison and validation. However, because the cross sections were not updated as a function of burnup, the actinide concentrations may deviate from the actual values at the higher burnups

  1. Influence of microbiological activity on the mobility of redoxsensitive radionuclides in sediments

    International Nuclear Information System (INIS)

    Stroetmann, I.; Kaempfer, P.; Dott, W.; Schuele, J.; Sokotnejat, R.; Winkler, A.; Pekdeger, A.

    1994-01-01

    The influence of microbial activity on the transport and migration behaviour of redox-sensitive radionuclides (e.g. Technetium (T c ) and Selenium (Se)) in groundwater environment were investigated within an interdisciplinary research program. Soil material and sediments were investigated with batch- and recirculation column experiments. The number of microorganisms in the water was determined by counting the colony forming units (CFU) on R2A agar at regular periods. The results of sterile and non sterile recirculation column experiments showed within 80 days a high fixation of the radionuclides in the unsterile samples (80% of T c , 50% of Se compared with the initial concentration A 0 ), and no fixation in the sterile samples. There was no difference in the redox values. It could be shown that the immobilisation of the redox-sensitive elements T c and Se are strongly determined by microbial activity, depending on the different sediments and their microbial live stock. There are indications that the microorganisms found in the non sterile columns are allochthonous bacteria which were dragged into the experimental systems and samples during laboratory work and sampling. The composition of the microbial flora was shown to be very heterogeneous and different in each individual column and within the same column at different times. Thus these columns might have been contaminated with microorganisms during sampling and handling of the experimental systems under non sterile conditions, as done generally in most laboratories

  2. Optimization of administered radionuclide activity in renal studies using 99mTc -DMSA in Cuba

    International Nuclear Information System (INIS)

    Diaz Barreto, M.; Perez Diaz, M.; Lopez Bejerano, G. M.; Varela Corona, C.; Paz Viera, J. E.

    2009-01-01

    The present research is focused on the optimization of administered radionuclide activity in renal studies using 9 9mTc-DMSA. The patients sample included 35 subjects, 23 of them were children and the other 12 were adults. Physical and metabolic characteristics of patients, total time of the study as well as radiopharmaceuticals quality and gamma camera performance was considered in the experiments. Image quality of each study was evaluated using subjective criteria from two expert observers, without previous information about administered activity, and objective criteria based on signal/noise ratios and variance of the random noise in the images. They were used to develop clustering and discriminant analysis over the independent variables to detect groups of images with differentiated quality from the physical and mathematical point of view. As a conclusion, we found that it is possible to reduce the given activities in 50%. (Author) 30 refs.

  3. Measurement of radionuclides in various environmental samples and in items of diet of the local population. Part of a coordinated programme on environmental monitoring for radiological protection in Asia and the Far East

    International Nuclear Information System (INIS)

    Aziz, A.

    1980-03-01

    The research covered identification of radionuclides and measurement of their concentration in various environmental media and items of diet of the local population. Biomedia and items of diet selected for study were air, surface water, precipitation, vegetables, meat, poultry and fish etc. Radioactive assays under-taken were gross gamma activity measurements and gamma spectrometric analyses for the determination of gamma emitting radionuclides. These were followed by radiochemical analyses for the separation of Sr 90 and Pu 239. Radiometric measurements for Sr 90 and Pu 239 were performed by low back-ground beta counting and alpha spectrometric analyses respectively

  4. Measurement of the induced radionuclides in production of radiopharmaceuticals for positron emission tomography (PET)

    International Nuclear Information System (INIS)

    Machizuki, Shingo; Ogatam Yoshimune; Ishigure, Nobuhito; Hatano, Kentaro; Abe, Junichiro; Ito, Kengo; Ito, Yoshihiro; Nishino, Masanari; Miyahara, Hiroshi

    2006-01-01

    The radioactive by-products contained in an entire series of target foil, [ 18 O]H 2 O and synthesis apparatus were identified and quantified. From the perspective of waste management, 60 Co induced in Havar foil should be taken into consideration. Because the exempt activity of 60 Co in BSS is 0.1 MBq, the used Havar foil should be managed more than for 20 years. The radionuclides in the [ 18 F]-FDG synthesis apparatus are negligible. Equivalent doses at skin and to tissues were estimated assuming a point source at a distance of 30 cm in air. The annual equivalent doses at skin and equivalent dose at deep tissues of such an operating staff will be 56 and 8.3 μSv, respectively, as two times the remove of the target foil and five hundreds times the synthesis of the [ 18 F]-FDG. When proper radiation protection is provided, the exposure from the cyclotron management and the [ 18 F]-FDG synthesis process will not cause meaningful radiological risk to the operating staff. The activity concentration of 3 H, 180 kBq·cm -3 , detected in the target water, is 3,000 times the legal limit of effluent for 3 H. The operators should take care of the treatment of the target water when they make a distillation for reuse and a disposal. (author)

  5. Methods of measurement and evaluation of natural radionuclide contents in buildings, at building sites, and in building materials and water

    International Nuclear Information System (INIS)

    1998-01-01

    The recommendations should serve as guidelines for specifying the scope of measurement and ways of evaluating the measuring results when satisfying the relevant requirements laid down by the Czech Atomic Act (Act No. 18/1997) and Decree No. 184/1997 in the field of natural radiation sources occurring in the environment without deliberate use. The document consists of the following sections: Methodology for the measurement and assessment of natural exposure of persons in dwelling rooms of buildings; Methodology of determination of the radon risk of building sites; Principles of systematic measurement and evaluation of natural radionuclide contents of building materials; and Principles of systematic measurement and evaluation of natural radionuclide contents of supplied water. (P.A.)

  6. Activity concentration and population dose from natural occurring radionuclide (40K) due to consumption of fresh water fish

    International Nuclear Information System (INIS)

    Jha, M.K.; Patra, A.K.; Jaison, T.J.; Ravi, P.M.; Tripathi, R.M.

    2015-01-01

    The objective of this study was to measure the concentration of natural occurring radionuclide ( 40 K) in different fresh water fish collected from Moticher lake near Kakrapar, Gujarat. The three types of commonly available fresh water fish in Moticher lake are Notopterus sps, Ophiocephalus sps. and Tor sps. The 40 K activity (Bq/kg flesh wt.) was found to be in the range of 38-100 (Notopterus sps.), 33-123 (Ophiocephalus sps.) and 80-116 (Tor sps.) respectively. The ingestion dose (μSv/y) to the adult population around Kakrapar was estimated due to the consumption of fresh water fish and found to be in the range of 7.7-20.5 (Notopterus sps.), 6.8-25.0 (Ophiocephalus sps.) and 16.0-24.0 (Tor sps.) respectively. (author)

  7. Design and manufacturing of nuclear non destructive measurement systems and coupled metrology in order to quantify the radionuclides contaminating the wastes and the processes of the nuclear industry

    International Nuclear Information System (INIS)

    Saurel, N.

    2013-01-01

    The non-destructive nuclear measurement has to provide responses for the main challenges of the nuclear industry such as nuclear facility safety, health, environmental impact, performance, reliability and cost control. The goal of the non-destructive nuclear measurement is to characterize, without any deterioration, an object contaminated by one or more radionuclides. The passive or active nuclear measurement are utilized for quantifying the radionuclides in the effluents, the liquid and solid wastes and the nuclear material hold-up. It is also deployed for the process control. In this case, it is a standard production control but, the most of the time, it controls the validity of the safety domain of the production unit. The results of these measurements are used to establish the radiological inventory or the nuclear material balance. The radiological inventory is needed for the nuclear wastes outlets while the nuclear material balance is needed to follow through with the criticality units. The most important objective is to give the quantitative and/or qualitative value and its uncertainty are confident of the radionuclides contaminating the object. This contaminated object might be of different geometrical shapes, sizes or physico-chemical compositions. In order to be efficient, the non-destructive nuclear measurement has to include the apparatus, the measurement actions, the settings and the use of the coupled methodologies. I relate, in this memoir, my main research and development works that I drove or in which I took part for achieving these goals. These works are about the metrology of nuclear radiations and are used in three main types of measurement which are the gamma spectrometry, the alpha spectrometry and the passive or active neutron counting. (author) [fr

  8. Radionuclide activities and radiological impact from the intake of milk, wheat flour, tea and coffee

    International Nuclear Information System (INIS)

    Nik Nadia Hazwani Nek Kamal; Amran Abdul Majid

    2013-01-01

    Full-text: The annual intake of four naturally occurring radionuclides 226 Ra, 238 U, 232 Th and 40 K from powdered milk, wheat flour, tea and coffee for Malaysian population were estimated using gamma spectrometry system. The radionuclides annual intake of 226 Ra ranged from 6 to 35.7 Bq, 232 Th ranged from 7.6 to 57.7 Bq, 238 U ranged from 6.3 to 63.7 Bq and 40 K ranged from 771.8 to 1707.5 Bq for adults. The means of these intakes were 28.8 Bq for 226 Ra, 38.5 Bq for 232 Th, 28.1 Bq for 238 U and 2921.1 Bq for the 40 K. The annual intake of radionuclide for infants were found to be 66.2 Bq for 226 Ra, 71.6 Bq for 232 Th, 23 Bq for 238 U and 7774.8 Bq for 40 K. the annual internal dose for infants from the intake of powdered milk were 63.5 μSv for 226 Ra, 32.2 μSv for 232 Th, 2.8 μSv for 238 U and 326.5 μSv for 40 K. The measured values also gives annual internal dose of 13.7 μSv 226 Ra, 19 μSv for 232 Th, 4 μSv for 238 U and 24.2 μSv for 40 K for adult population. The net radiological impact of these radionuclides is 425 μSv for infants and 60.9 μSv for adults. This value gives cancer risk factor of 1.8 x 10 -3 for infants and 1.7 x 10 -4 for adults. The probability of cancer risk increment is estimated as 0.18 % for infants (18 person in 10000) and 0.017 % for adults (1.7 person in 10000). Whereas ICRP cancer risk factor for general public is 2.5 x 10 -3 nd the total risk involved from all natural radiation sources based on global average radiation dose of 2.4 mSv is of 6 x 10 -3 . The estimated cancer risk shows that probability of increase of cancer risk from intake of milk, wheat flour, tea and coffee is only a minor fraction of ICRP values. Therefore, the diet does not pose any significant health hazard and is considered safe for human consumption. (author)

  9. Measurement of gamma-ray dose rate in soil and transfer of radionuclides from soil to vegetation

    International Nuclear Information System (INIS)

    Khan, K.; Akhter, P.; Khan, H.M.; Ismail, M.

    2012-01-01

    Analysis of natural radionuclides in soil, vegetation and vegetable samples collected from some Northern areas of Pakistan was carried out by gamma -ray spectrometry (HPGe detector). The activity concentrations in soil ranged from 24.7 to 78.5 Bqkg/sup -1/, 21.7 to 75.3 Bqkg/sup -1/ and 298.5 to 570.8 Bqkg/sup -1/ for /sup 226/Ra, /sup 232/Th, and /sup 40/K with the mean values of 42.1, 43.3 and 418.3 Bqkg/sup -1/, respectively. In the present analysis, /sup 40/K was the major radionuclide present in soil, vegetation, fruit and vegetable samples. The transfer factors of these radionuclides from soil to vegetation, fruit and vegetable were found in the order: /sup 40/K>/sup 232/Th>/sup 226/Ra. The mean value of outdoor and indoor absorbed dose rate (D) in air was 64.61 and 77.54 nGyh/sup -1/. The activity concentrations of radionuclides found in all samples were nominal. Therefore, they are not associated with any potential source of health hazard to the general public. (Orig./A.B.)

  10. A database of radionuclide activity and metal concentrations for the Alligator Rivers Region uranium province.

    Science.gov (United States)

    Doering, Che; Bollhöfer, Andreas

    2016-10-01

    This paper presents a database of radionuclide activity and metal concentrations for the Alligator Rivers Region (ARR) uranium province in the Australian wet-dry tropics. The database contains 5060 sample records and 57,473 concentration values. The data are for animal, plant, soil, sediment and water samples collected by the Environmental Research Institute of the Supervising Scientist (ERISS) as part of its statutory role to undertake research and monitoring into the impacts of uranium mining on the environment of the ARR. Concentration values are provided in the database for 11 radionuclides ( 227 Ac, 40 K, 210 Pb, 210 Po, 226 Ra, 228 Ra, 228 Th, 230 Th, 232 Th, 234 U, 238 U) and 26 metals (Al, As, Ba, Ca, Cd, Co, Cr, Cu, Fe, Hg, K, Mg, Mn, Na, Ni, P, Pb, Rb, S, Sb, Se, Sr, Th, U, V, Zn). Potential uses of the database are discussed. Crown Copyright © 2016. Published by Elsevier Ltd. All rights reserved.

  11. Studies of environmental radioactivity in Cumbria: Part 3. Measurements of radionuclides in airborne and deposited material

    International Nuclear Information System (INIS)

    Pattenden, N.J.; Cambray, R.S.; Playford, K.; Eakins, J.D.; Fisher, E.M.R.

    1980-09-01

    Six stations sampling airborne particulate and deposited material were established in the Cumbrian coastal region. The measurements were undertaken to study current atmospheric levels and to discriminate between material from nuclear weapon tests, routine atmospheric discharges from the nuclear reprocessing works at Windscale and other sources, e.g. the sea. The results show that samples of both airborne and deposited material contain radionuclide concentrations in excess of those expected from nuclear weapon fallout. For Pu and 241 Am isotopes, the excess material comes mainly from a seaward direction. The transfer mechanism is probably resuspension, but the actinide levels are much greater than would be expected from the simple transfer of bulk seawater. For 137 Cs, the material in excess of amounts expected from nuclear weapon fallout can be attributed largely to Windscale discharges to air and seaspray containing the bulk seawater concentration of 137 Cs. Other fission products present in amounts exceeding nuclear weapon fallout were 106 Ru, 125 Sb, 134 Cs and 144 Ce. Tritium was also observed in amounts slightly in excess of nuclear weapon fallout. The highest observed annual average concentration in air for Pu isotopes was 0.2% of the derived air concentration, modified for members of the public, of 2.3 mBq/m 3 . (author)

  12. Criteria for requesting specific radionuclide analysis through gross α and gross β concentration measurements in environmental samples

    International Nuclear Information System (INIS)

    Ferreira, E.G.

    1988-01-01

    This paper suggests some criteria for the decision to proceed with the analysis of specific radionuclides based on results of the determination of gross α and β concentrations in environmental samples of aerosols, water, dairy and agricultural products, soil and sediments. The samples considered are provenient from the environmental surveillance of uranium mining and milling facilities as well as the mining and processing plants of monazite sands. The radionuclides to be analysed are those considered to be the most critical to human health, that is: U-nat; Th-nat; Th-230; Ra-228; Ra-226; Po-210; Pb-210. The measured gross α and β concentrations will be compared with the Maximum Allowable Concentrations for some defined radionuclides. Radiochemical analysis of specific radionuclides may then become necessary, depending upon the results of this comparison. The main goal of the proposed guide is to simplify and to discipline the execution of environmental surveillance programs in a safe and economical way, avoiding unnecessary analysis. (author) [pt

  13. 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

  14. Behaviour of actinides and other radionuclides that are difficult to measure in the melting of contaminated steel

    International Nuclear Information System (INIS)

    Schuster, E.; Haas, E.W.

    1990-01-01

    The research work carried out confirmed the expected homogeneous distribution of the radionuclides selected for the experiments (Fe 55 and Ni 63) in the metal ingot, as was already known from the behaviour of Co 60. The latter radionuclide may be used as an indicator nuclide for Fe 55 and Ni 63 which are both difficult to measure. C 14 also showed homogeneous distribution in the ingot (carbon steel). As expected for the melt technique strontium is released to the slag. In principle this is valid for actinides too, but depends to some extent on their chemical form (elemental uranium, UO 2 ), the added tracer quantity and the quantity of slag forming material. A direct alpha-measurement technique has been developed for steel samples and may be suitable for free release measurements of alpha-emitting steel waste decontaminated by the melt technique

  15. Monte Carlo calculation of correction factors for radionuclide neutron source emission rate measurement by manganese bath method

    International Nuclear Information System (INIS)

    Li Chunjuan; Liu Yi'na; Zhang Weihua; Wang Zhiqiang

    2014-01-01

    The manganese bath method for measuring the neutron emission rate of radionuclide sources requires corrections to be made for emitted neutrons which are not captured by manganese nuclei. The Monte Carlo particle transport code MCNP was used to simulate the manganese bath system of the standards for the measurement of neutron source intensity. The correction factors were calculated and the reliability of the model was demonstrated through the key comparison for the radionuclide neutron source emission rate measurements organized by BIPM. The uncertainties in the calculated values were evaluated by considering the sensitivities to the solution density, the density of the radioactive material, the positioning of the source, the radius of the bath, and the interaction cross-sections. A new method for the evaluation of the uncertainties in Monte Carlo calculation was given. (authors)

  16. Interpreting aerosol lifetimes using the GEOS-Chem model and constraints from radionuclide measurements

    Energy Technology Data Exchange (ETDEWEB)

    Croft, B. [Dalhousie Univ., Halifax (Canada). Dept. of Physics and Atmospheric Science; Pierce, J.R. [Dalhousie Univ., Halifax (Canada). Dept. of Physics and Atmospheric Science; Colorado State Univ., Fort Collins, CO (United States); Martin, R.V. [Dalhousie Univ., Halifax (Canada). Dept. of Physics and Atmospheric Science; Harvard-Smithsonian Center for Astrophysics, Cambridge, MA (United States)

    2014-07-01

    Aerosol removal processes control global aerosol abundance, but the rate of that removal remains uncertain. A recent study of aerosol-bound radionuclide measurements after the Fukushima Daiichi nuclear power plant accident documents {sup 137}Cs removal (e-folding) times of 10.0-13.9 days, suggesting that mean aerosol lifetimes in the range of 3-7 days in global models might be too short by a factor of two. In this study, we attribute this discrepancy to differences between the e-folding and mean aerosol lifetimes. We implement a simulation of {sup 137}Cs and {sup 133}Xe into the GEOS-Chem chemical transport model and examine the removal rates for the Fukushima case. We find a general consistency between modelled and measured e-folding times. The simulated {sup 137}Cs global burden e-folding time is about 14 days. However, the simulated mean lifetime of aerosol-bound {sup 137}Cs over a 6-month post-accident period is only 1.8 days. We find that the mean lifetime depends strongly on the removal rates in the first few days after emissions, before the aerosols leave the boundary layer and are transported to altitudes and latitudes where lifetimes with respect to wet removal are longer by a few orders of magnitude. We present sensitivity simulations that demonstrate the influence of differences in altitude and location of the radionuclides on the mean lifetime. Global mean lifetimes are shown to strongly depend on the altitude of injection. The global mean {sup 137}Cs lifetime is more than one order of magnitude greater for the injection at 7 km than into the boundary layer above the Fukushima site. Instantaneous removal rates are slower during the first few days after the emissions for a free tropospheric versus boundary layer injection and this strongly controls the mean lifetimes. Global mean aerosol lifetimes for the GEOS-Chem model are 3-6 days, which is longer than that for the {sup 137}Cs injected at the Fukushima site (likely due to precipitation shortly after

  17. Natural radionuclides in plants, soils and sediments affected by U-rich coal mining activities in Brazil.

    Science.gov (United States)

    Galhardi, Juliana Aparecida; García-Tenorio, Rafael; Bonotto, Daniel Marcos; Díaz Francés, Inmaculada; Motta, João Gabriel

    2017-10-01

    Mining activities can increase the mobility of metals by accelerating the dissolution and leaching of minerals from the rocks and tailing piles to the environment and, consequently, their availability for plants and subsequent transfer to the food chain. The weathering of minerals and the disposal of coal waste in tailing piles can accelerate the generation of acid mine drainage (AMD), which is responsible for the higher dissolution of metals in mining areas. In this context, the behavior of U, Th and K in soils and sediment, and the transfer factor (TF) of 238 U, 234 U and 210 Po for soybean, wheat, pine and eucalyptus cultivated around a coal mine in southern Brazil was evaluated. Alpha and gamma spectrometry were used for the measurements of the activity concentration of the radioelements. 210 Po was the radionuclide that is most accumulated in the plants, especially in the leaves. When comparing the plant species, pine showed the highest TF values for 234 U (0.311 ± 0.420) for leaves, while eucalyptus showed the highest TF for 238 U (0.344 ± 0.414) for leaves. In general, TF were higher for the leaves of soybean and wheat when compared to the grains, and grains of wheat showed higher TF for 210 Po and 238 U than grains of soybean. Deviations from the natural U isotopic ratio were recorded at all investigated areas, indicating possible industrial and mining sources of U for the vegetables. A safety assessment of transport routes and accumulation of radionuclides in soils with a potential for cultivation is important, mainly in tropical areas contaminated with solid waste and effluents from mines and industry. Copyright © 2017 Elsevier Ltd. All rights reserved.

  18. Tracing the origin of suspended sediment in a large Mediterranean river by combining continuous river monitoring and measurement of artificial and natural radionuclides

    International Nuclear Information System (INIS)

    Zebracki, Mathilde; Eyrolle-Boyer, Frédérique; Evrard, Olivier; Claval, David; Mourier, Brice; Gairoard, Stéphanie

    2015-01-01

    Delivery of suspended sediment from large rivers to marine environments has important environmental impacts on coastal zones. In France, the Rhone River (catchment area of 98,000 km 2 ) is by far the main supplier of sediment to the Mediterranean Sea and its annual solid discharge is largely controlled by flood events. This study investigates the relevance of alternative and original fingerprinting techniques based on the relative abundances of a series of radionuclides measured routinely at the Rhone River outlet to quantify the relative contribution of sediment supplied by the main tributaries during floods. Floods were classified according to the relative contribution of the main subcatchments (i.e., Oceanic, Cevenol, extensive Mediterranean and generalised). Between 2000 and 2012, 221 samples of suspended sediment were collected at the outlet and were shown to be representative of all flood types that occurred during the last decade. Three geogenic radionuclides (i.e., 238 U, 232 Th and 40 K) were used as fingerprints in a multivariate mixing model in order to estimate the relative contribution of the main subcatchment sources—characterised by different lithologies—in sediment samples collected at the outlet. Results showed that total sediment supply originating from Pre-Alpine, Upstream, and Cevenol sources amounted to 10, 7 and 2.10 6 tons, respectively. These results highlight the role of Pre-Alpine tributaries as the main sediment supplier (53%) to the Rhone River during floods. Other fingerprinting approaches based on artificial radionuclide activity ratios (i.e., 137 Cs/ 239+240 Pu and 238 Pu/ 239+240 Pu) were tested and provided a way to quantify sediment remobilisation or the relative contributions of the southern tributaries. In the future, fingerprinting methods based on natural radionuclides should be further applied to catchments with heterogeneous lithologies. Methods based on artificial radionuclides should be further applied to catchments

  19. Tracing the origin of suspended sediment in a large Mediterranean river by combining continuous river monitoring and measurement of artificial and natural radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Zebracki, Mathilde, E-mail: zebracki@free.fr [Laboratoire d' Etudes Radioécologiques en milieu Continental et Marin (LERCM), Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Saint-Paul-lez-Durance (France); Eyrolle-Boyer, Frédérique [Laboratoire d' Etudes Radioécologiques en milieu Continental et Marin (LERCM), Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Saint-Paul-lez-Durance (France); Evrard, Olivier [Laboratoire des Sciences du Climat et de l' Environnement (LSCE/IPSL), Unité Mixte de Recherche 8212 (CEA/CNRS/UVSQ), Gif-sur-Yvette (France); Claval, David [Laboratoire d' Etudes Radioécologiques en milieu Continental et Marin (LERCM), Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Saint-Paul-lez-Durance (France); Mourier, Brice [Université Lyon 1, UMR 5023 Ecologie des Hydrosystèmes Naturels et Anthropisés, ENTPE, CNRS, 3, Rue Maurice Audin, F-69518 Vaulx-en-Velin (France); Université de Limoges, GRESE, EA 4330, 123 avenue Albert Thomas, 87060 Limoges (France); Gairoard, Stéphanie [Centre de Recherche et d' Enseignement de Géosciences de l' Environnement (CEREGE), Unité Mixte 34 (AMU/CNRS/IRD), Aix-en-Provence (France); and others

    2015-01-01

    Delivery of suspended sediment from large rivers to marine environments has important environmental impacts on coastal zones. In France, the Rhone River (catchment area of 98,000 km{sup 2}) is by far the main supplier of sediment to the Mediterranean Sea and its annual solid discharge is largely controlled by flood events. This study investigates the relevance of alternative and original fingerprinting techniques based on the relative abundances of a series of radionuclides measured routinely at the Rhone River outlet to quantify the relative contribution of sediment supplied by the main tributaries during floods. Floods were classified according to the relative contribution of the main subcatchments (i.e., Oceanic, Cevenol, extensive Mediterranean and generalised). Between 2000 and 2012, 221 samples of suspended sediment were collected at the outlet and were shown to be representative of all flood types that occurred during the last decade. Three geogenic radionuclides (i.e., {sup 238}U, {sup 232}Th and {sup 40}K) were used as fingerprints in a multivariate mixing model in order to estimate the relative contribution of the main subcatchment sources—characterised by different lithologies—in sediment samples collected at the outlet. Results showed that total sediment supply originating from Pre-Alpine, Upstream, and Cevenol sources amounted to 10, 7 and 2.10{sup 6} tons, respectively. These results highlight the role of Pre-Alpine tributaries as the main sediment supplier (53%) to the Rhone River during floods. Other fingerprinting approaches based on artificial radionuclide activity ratios (i.e., {sup 137}Cs/{sup 239+240}Pu and {sup 238}Pu/{sup 239+240}Pu) were tested and provided a way to quantify sediment remobilisation or the relative contributions of the southern tributaries. In the future, fingerprinting methods based on natural radionuclides should be further applied to catchments with heterogeneous lithologies. Methods based on artificial radionuclides

  20. Activity size distributions of some naturally occurring radionuclides 7Be, 40K and 212Pb in indoor and outdoor environments

    International Nuclear Information System (INIS)

    Mohamed, A.

    2005-01-01

    The activity size distributions of natural radionuclides 7 Be and 40 K were measured outdoor in El-Minia city, Egypt by means of gamma spectroscopy. A low-pressure Berner cascade impactor was used as a sampling device. The activity size distribution of both 7 Be and 40 K was described by one log-normal distribution, which was represented by the accumulation mode. The activity median aerodynamic diameter (AMAD) of 7 Be and 40 K was determined to be 530 and 1550nm with a relative geometric standard deviation (δ, which was defined as the dispersion of the peak) of 2.4 and 2, respectively. The same sampling device (Berner impactor) and a screen diffusion battery were used to measure the activity size distribution, activity concentration and unattached fraction (f P ) of 212 Pb in indoor air of El-Minia City, Egypt. The mean activity median aerodynamic diameter (AMAD) of the accumulation mode for attached 212 Pb was determined to be 250nm with a mean geometric standard deviation (δ) of 2.6. The mean value of the specific concentration of 212 Pb associated with that mode was determined to be 460+/-20mBqm -3 . The activity median thermodynamic diameter (AMTD) of unattached 212 Pb was determined to be 1.25nm with δ of 1.4. A mean unattached fraction (f p ) of 0.13+/-0.02 was obtained at a mean aerosol particle concentration of 1.8x10 3 cm -3 . The mean activity concentration of unattached 212 Pb was found to be 19+/-3mBqm -3 . It was found that the aerosol concentration played an important role in varying the unattached, attached activity concentration and unattached fraction (f P )

  1. Simulation of deposition and activity distribution of radionuclides in human airways

    International Nuclear Information System (INIS)

    Farkas, A.; Balashazy, I.; Szoke, I.; Hofmann, W.; Golser, R.

    2002-01-01

    The aim of our research activities is the modelling of the biological processes related to the development of lung cancer at the large central-airways observed in the case of uranium miners caused by the inhalation of radionuclides (especially alpha-emitting radon decay products). Statistical data show that at the uranium miners the lung cancer has developed mainly in the 3-4.-5. airway generations and especially in the right upper lobe. Therefore, it is rather important to study the physical and biological effects in this section of the human airways to find relations between the radiation dose and the adverse health effects. These results may provide useful information about the validity or invalidity of the currently used LNT (Linear-No-Threshold) dose-effect hypothesis at low doses

  2. Classification and Reevaluation on Radionuclide and Activity of Contaminated Soil(I)

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Il Sik; Shon, J. S.; Kim, K. J.; Kim, T. K.; Hong, D. S.; Lee, B. C.; Cho, H. S.; Je, W. G

    2006-03-15

    Radioactive wastes generated during the decommissioning process and contaminated soils were transported and have been stored at the waste storage facility. The radioactivity in the wastes has been decayed a lot. The radionuclide and the activity concentration of stored soil wastes were reevaluated. And using the reevaluation results, the soil wastes were classified as either a regulatory clearance wastes or a radioactive waste. The storage space can be secured by storing regulatory clearance wastes in the extra storage facility and self disposing them. Also, the objective is to protect the environment from contamination by observing the related nuclear regulation and managing the radioactive wastes. Through the reevaluation of radioactivity and classification of contaminated soils, the unnecessary decontamination of uncontaminated soil was prevented. It allowed us to save the cost for decontamination and disposal, also we could secure the pretreatment process techniques such as how to sample and analyze the nuclide.

  3. Results of an international comparison for the determination of radionuclide activity in bilberry material

    International Nuclear Information System (INIS)

    Wätjen, U.; Altzitzoglou, T.; Ceccatelli, A.; Dikmen, H.; Emteborg, H.; Ferreux, L.; Frechou, C.; La Rosa, J.; Luca, A.; Moreno, Y.; Oropesa, P.; Pierre, S.; Schmiedel, M.

    2012-01-01

    Radioactivity found in wild food products has assumed greater importance when assessing the total exposure of the population. For this reason, IRMM has been developing a reference material for the activity concentration of three radionuclides in bilberry samples. In order to characterise this new material, a CCRI(II) supplementary comparison was organised. The difficulties encountered in this comparison are discussed, in particular the efficiency calibration for volume sources of gamma-ray emitters, and comparison reference values for 137 Cs and 40 K are calculated. - Highlights: ► CCRI(II) supplementary comparison for Cs-137 and K-40 in bilberry matrix completed. ► Fundamentally different methods used to establish link to SI traceable standards and SIR. ► Variation of results higher than in CCRI(II) key comparisons. ► Comparison reference values will be robust property values of IRMM reference material. ► Certified reference material for radioactivity in food developed.

  4. Calibration and consistency of results of an ionization-chamber secondary standard measuring system for activity

    International Nuclear Information System (INIS)

    Schrader, Heinrich

    2000-01-01

    Calibration in terms of activity of the ionization-chamber secondary standard measuring systems at the PTB is described. The measurement results of a Centronic IG12/A20, a Vinten ISOCAL IV and a radionuclide calibrator chamber for nuclear medicine applications are discussed, their energy-dependent efficiency curves established and the consistency checked using recently evaluated radionuclide decay data. Criteria for evaluating and transferring calibration factors (or efficiencies) are given

  5. Low level measurements of natural radionuclides in soil samples around a coal-fired power plant

    International Nuclear Information System (INIS)

    Rosner, G.; Bunzl, K.; Hoetzl, H.; Winkler, R.

    1984-01-01

    To detect a possible contribution of airborne radioactivity from stack effluents to the soil radioactivity, several radionuclides in the soil around a coal-fired power plant have been determined. A plant situated in a rural region of Bavaria was selected to minimize contributions from other civilisatory sources. The soil sampling network consisted of 5 concentric circles with diameters between 0.4 and 5.2 km around the plant, 16 sampling points being distributed regularly on each circle. Radiochemical analysis techniques for 210 Pb and 210 Po in soil samples of several grams has to be developed. They include a wet dissolution procedure, simultaneous precipitation of lead and polonium as the sulfides, purification via lead sulfate, counting of the lead as the chromate in a low-level beta counter and alpha spectrometric determination of the 210 Po in a gridded ionization chamber. The 238 U, 226 Ra, 232 Th and 40 K were counted by low level gamma spectrometry. Specific activities found were in the range of 0.7 to 2.0 pCi g -1 for 210 Pb and 0.3 to 1.6 pCi g -1 for 226 Ra. The distribution patterns of 210 Po and 210 Pb around the plant were found to be similar. They were different, however, from that of 226 Ra. The highest 210 Pb/ 226 Ra activity ratio was 3.9 at a distance of 0.76 km SSE from the plant. Nevertheless, the evidence is not considered to be sufficient to attribute these observations unambiguously to plant release. (orig.)

  6. Low level measurements of natural radionuclides in soil samples around a coal-fired power plant

    Energy Technology Data Exchange (ETDEWEB)

    Rosner, G.; Bunzl, K.; Hoetzl, H.; Winkler, R. (Gesellschaft fuer Strahlen- und Umweltforschung m.b.H. Muenchen, Neuherberg (Germany, F.R.). Inst. fuer Strahlenschutz)

    1984-06-15

    To detect a possible contribution of airborne radioactivity from stack effluents to the soil radioactivity, several radionuclides in the soil around a coal-fired power plant have been determined. A plant situated in a rural region of Bavaria was selected to minimize contributions from other civilisatory sources. The soil sampling network consisted of 5 concentric circles with diameters between 0.4 and 5.2 km around the plant, 16 sampling points being distributed regularly on each circle. Radiochemical analysis techniques for /sup 210/Pb and /sup 210/Po in soil samples of several grams has to be developed. They include a wet dissolution procedure, simultaneous precipitation of lead and polonium as the sulfides, purification via lead sulfate, counting of the lead as the chromate in a low-level beta counter and alpha spectrometric determination of the /sup 210/Po in a gridded ionization chamber. The /sup 238/U, /sup 226/Ra, /sup 232/Th and /sup 40/K were counted by low level gamma spectrometry. Specific activities found were in the range of 0.7 to 2.0 pCi g/sup -1/ for /sup 210/Pb and 0.3 to 1.6 pCi g/sup -1/ for /sup 226/Ra. The distribution patterns of /sup 210/Po and /sup 210/Pb around the plant were found to be similar. They were different, however, from that of /sup 226/Ra. The highest /sup 210/Pb//sup 226/Ra activity ratio was 3.9 at a distance of 0.76 km SSE from the plant. Nevertheless, the evidence is not considered to be sufficient to attribute these observations unambiguously to plant release.

  7. Radionuclide examinations

    International Nuclear Information System (INIS)

    Lentle, B.C.

    1989-01-01

    This paper reports on radionuclide examinations of the pancreas. The pancreas, situated retroperitonally high in the epigastrium, was a particularly difficult organ to image noninvasively before ultrasonography and computed tomography (CT) became available. Indeed the organ still remains difficult to examine in some patients, a fact reflected in the variety of methods available to evaluate pancreatic morphology. It is something of a paradox that the pancreas is metabolically active and physiologically important but that its examination by radionuclide methods has virtually ceased to have any role in day-to-day clinical practice. To some extent this is caused by the tendency of the pancreas's commonest gross diseases emdash carcinoma and pancreatitis, for example emdash to result in nonfunction of the entire organ. Disorders of pancreatic endocrine function have generally not required imaging methods for diagnosis, although an understanding of diabetes mellitus and its nosology has been advanced by radioimmunoassay of plasma insulin concentrations

  8. Quantitative radionuclide angiocardiography

    International Nuclear Information System (INIS)

    Scholz, P.M.; Rerych, S.K.; Moran, J.F.; Newman, G.E.; Douglas, J.M.; Sabiston, D.C. Jr.; Jones, R.H.

    1980-01-01

    This study introduces a new method for calculating actual left ventricular volumes and cardiac output from data recorded during a single transit of a radionuclide bolus through the heart, and describes in detail current radionuclide angiocardiography methodology. A group of 64 healthy adults with a wide age range were studied to define the normal range of hemodynamic parameters determined by the technique. Radionuclide angiocardiograms were performed in patients undergoing cardiac catherization to validate the measurements. In 33 patients studied by both techniques on the same day, a close correlation was documented for measurement of ejection fraction and end-diastolic volume. To validate the method of volumetric cardiac output calcuation, 33 simultaneous radionuclide and indocyanine green dye determinations of cardiac output were performed in 18 normal young adults. These independent comparisons of radionuclide measurements with two separate methods document that initial transit radionuclide angiocardiography accurately assesses left ventricular function

  9. A general dead-time correction method based on live-time stamping. Application to the measurement of short-lived radionuclides.

    Science.gov (United States)

    Chauvenet, B; Bobin, C; Bouchard, J

    2017-12-01

    Dead-time correction formulae are established in the general case of superimposed non-homogeneous Poisson processes. Based on the same principles as conventional live-timed counting, this method exploits the additional information made available using digital signal processing systems, and especially the possibility to store the time stamps of live-time intervals. No approximation needs to be made to obtain those formulae. Estimates of the variances of corrected rates are also presented. This method is applied to the activity measurement of short-lived radionuclides. Copyright © 2017 Elsevier Ltd. All rights reserved.

  10. THE PROBLEMS OF USING EXEMPTION ACTIVITY VALUES FOR REGULATING THE MANAGEMENT OF SEALED RADIONUCLIDE SOURCES OF GAMMA-RADIATION

    Directory of Open Access Journals (Sweden)

    A. N. Barkovsky

    2017-01-01

    Full Text Available The article focuses on the procedure for exemption of the sealed and unsealed radionuclide sources of gamma radiation from regulatory control. The contradictory nature of the existing set of exemption criteria has been noted, leading, in some cases, to paradoxical situations. It is shown that the exempt activity values determined in NRB-99/2009 and in the international basic safety standards of the IAEA are significantly overestimated (in comparison with the activity values of a point source creating the ambient dose equivalent rate of 1 μSv / h at a distance of 0.1 m for a number of the most widely used gamma-emitting radionuclides, including 22Na, 54Mn, 75Se, 152Eu and 154Eu. It is proposed to revise the current values of exempt activity, bringing them in line with the dose rate criterion for the exempt of sealed radionuclide sources of gamma radiation, and to present them with one significant digit. The corrected values of exempt activity for  seven selected radionuclides are proposed for further use in the process of revision of the national radiation safety standards.

  11. Measuring the availability to sediments and biota of radionuclides in wastes discharged to the sea

    International Nuclear Information System (INIS)

    Nicholson, M.D.; Hunt, G.J.

    1995-01-01

    Radionuclides in waste discharged to the sea are taken up by marine sediments and organisms. The concentrations observed in these materials are determined by a complex process depending upon present and past discharges, and the rates of decay, dispersion, uptake and elimination. A simple, semi-empirical model is derived to predict current concentrations from historical discharges. An important parameter in this model is the mean availability time, the average time for which the radionuclide is effectively available to the material. Maximum likelihood estimates of the model's parameters are derived. The theory is applied to data collected in the marine environment near British Nuclear Fuels plc, Sellafield. (Author)

  12. Influence of microbial activity on the migration behaviour of redox-sensitive radionuclides (technetium and selenium) in loose rock

    International Nuclear Information System (INIS)

    Stroetmann, I.

    1995-01-01

    In closed cycle column tests under sterile conditions there was no or hardly any sorption of the two radionuclides. In closed cycle column tests with unsterile soils, however, the two radionuclides were extremely immobilised (80 % of the output activity of Tc-95m and 40 % of the output activity of Se-75). By inoculation of the sterile columns with mixed soil cultures an increase in sorption of 40 % of the output activity was achieved which is attributed to the microbial activity. The adsorbed radionuclides in unsterile columns could be remobilized by adding a bactericide. In columns with saline water the sorption of radionuclides was slightly lower. Soils with a 5 % organic carbon content showed extremely increased sorption of the two radionuclides. In comparison with closed cycle columns shake tests were carried out. During turbulent intermixing of water and solid, no sorption of technetium was observed in unsterile tests either, while Se-75 added as selenite was strongly adsorbed to the solid. When adding acetate as a C-source, the microbially conditioned reduction of the redox potential to -100 mV and, subsequently, a strong increase of sorption could be observed. A reduction of the pH value in the soils to pH 4, and simultaneous adding of acetate significally reduced the microbial activity and the sorption of technetium, while selenite sorption remained strong as before. Sorption tests with bacteria-pure and mixed cultures showed no sorption of the pertechnetate anion in the oxidation stage (VII). However, when reducing the pertechnetate by means of SnCl2, up to 40 % of the feed activity of killed and living biomass was immobilized. Between 20-30 % of the adsorbed technetium quantity was outside at the membrane, and 40% inside the cells. After a three-day incubation period in a technetium-containing solution, a factor of 15,5 was achieved as the maximum intracellular concentration factor for the isolate 143 (Xanthomas sp.). (orig./MG) [de

  13. Measuring Physical Activity Intensity

    Medline Plus

    Full Text Available ... Needs for Pregnant or Postpartum Women Physical Activity & Health Adding Physical Activity to Your Life Activities for ... Guide Visual Guide Worksite Physical Activity Steps to Wellness Walkability Audit Tool Sample Audit Glossary Selected References ...

  14. Measuring Physical Activity Intensity

    Medline Plus

    Full Text Available ... for Older Adults Needs for Pregnant or Postpartum Women Physical Activity & Health Adding Physical Activity to Your ... Activity, 2014 Recommendations & Guidelines Fact Sheets & Infographics Social Media Tools Community Strategies BE Active: Connecting Routes + Destinations ...

  15. Measuring Physical Activity Intensity

    Medline Plus

    Full Text Available ... Physical Activity Data, Trends and Maps Surveillance Systems Resources & Publications Reports Adults Need More Physical Activity MMWR ... Active: Connecting Routes + Destinations Real-World Examples Implementation Resource Guide Visual Guide Worksite Physical Activity Steps to ...

  16. Measuring Physical Activity Intensity

    Medline Plus

    Full Text Available ... to Your Life Activities for Children Activities for Older Adults Overcoming Barriers ... required by a person to do an activity. When using relative intensity, people pay attention to how physical activity affects their ...

  17. Use of polyamfolit complexes of ethyl-amino-crotonate/acrylic acid with surface-active materials for radionuclide extraction

    International Nuclear Information System (INIS)

    Kabdyrakova, A.M.; Artem'ev, O.I.; Protskij, A.V.; Bimendina, L.A.; Yashkarova, M.G.; Orazzhanova, L.K.

    2005-01-01

    Pentifylline of betaine structure was synthesised on the basis of 3-aminocrotonate and acrylic acid. Polyamfolit composition and its complexes with anionic surface-active material (lauryl sulfate of sodium) were determined. It is revealed that complex formation occurs with [polyamfolit]:[surface active material]=1:1 ratio and is accompanied by significant reduce of system characteristics viscosity. The paper presents results of [polyamfolit]:[surface active material] complex apply experimental investigation for radionuclide directed migration in soil. (author)

  18. 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

  19. Measurement of enzyme activity.

    Science.gov (United States)

    Harris, T K; Keshwani, M M

    2009-01-01

    To study and understand the nature of living cells, scientists have continually employed traditional biochemical techniques aimed to fractionate and characterize a designated network of macromolecular components required to carry out a particular cellular function. At the most rudimentary level, cellular functions ultimately entail rapid chemical transformations that otherwise would not occur in the physiological environment of the cell. The term enzyme is used to singularly designate a macromolecular gene product that specifically and greatly enhances the rate of a chemical transformation. Purification and characterization of individual and collective groups of enzymes has been and will remain essential toward advancement of the molecular biological sciences; and developing and utilizing enzyme reaction assays is central to this mission. First, basic kinetic principles are described for understanding chemical reaction rates and the catalytic effects of enzymes on such rates. Then, a number of methods are described for measuring enzyme-catalyzed reaction rates, which mainly differ with regard to techniques used to detect and quantify concentration changes of given reactants or products. Finally, short commentary is given toward formulation of reaction mixtures used to measure enzyme activity. Whereas a comprehensive treatment of enzymatic reaction assays is not within the scope of this chapter, the very core principles that are presented should enable new researchers to better understand the logic and utility of any given enzymatic assay that becomes of interest.

  20. Primordial radionuclides in drinking water from former tin-mining area elevated activity

    International Nuclear Information System (INIS)

    Adekoya, O. I.; Adewoyin, K. A.; Olaleru, S. A.

    2014-01-01

    The activity concentrations of the primordial radionuclides in drinking water from two former mining areas (Bisichi and Bukuru) in Jos, Plateau State in Nigeria have been studied. The activities were determined by a non-destructive analysis using a computerized gamma ray spectrometry system with high purity germanium (HPGe). The result show the average activity concentration for 226 Ra, 232 Th and 40 K for Bukuru and Bisichi to be respectively 1.20±0.02 Bq/l, 1.93±0.01 Bq/l, 4.75±0.14 Bq/l and 2.03±0.14 Bq/l, 2.20±0.13 Bq/l, 3.26±0.06 Bq/l. The annual effective doses due to the intake of drinking water from both locations approximately 2.80 mSv and 3.32 mSv respectively. These results are much higher then the reference level of a dose of 0.1 mSv/year from the intake of drinking water.

  1. Content of PAHs, activities of γ-radionuclides and ecotoxicological assessment in biochars

    Directory of Open Access Journals (Sweden)

    Gondek Krzysztof

    2016-12-01

    Full Text Available The aim of this research was to determine the effect of thermal conversion temperature and plant material addition to sewage sludge on the PAHs content and the activity of selected γ-radionuclides in biochars, and to conduct an ecotoxicological assessment. The pyrolysis of the mixtures of sewage sludge and plant materials at 300°C and such temperature caused an increase in the contents of 2- and 3-ring hydrocarbons. During the pyrolysis of organic materials at 600°C, the amount of the following compounds was reduced in biochars: benzo[b]fluoranthene, benzo[k]fluoranthene, benzo[a]pyrene, indeno[1,2,3c,d]pyrene, dibenzo[a,h]anthracene, and benzo[g,h,i]perylene. Among γ-radioisotopes of the elements, natural radiogenic isotopes were dominant. 137Cs was the only artificial radioactive isotope. The pyrolysis of the mixtures of municipal sewage sludge and plant materials revealed that isotope 40K had the highest radioactive activity. In the case of other analysed nuclides, activities of 212Pb, 214Pb, 214Bi, and 137Cs were determined after the sample pyrolysis. The extracts from the mixtures of sewage sludge and plant materials were non-toxic to Vibrio fischeri.

  2. Concentration activities of natural radionuclides in three fish species in Brazilian coast and their contributions to the absorbed doses

    International Nuclear Information System (INIS)

    Pereira, Wagner de S.; Py Junior, Delcy de A.; Kelecom, Alphonse

    2009-01-01

    Activity concentrations of U-238, Ra-226, Pb-210, Th-232 e Ra-228 were analysed in three fish species at the Brasilian Coast. The fish 'Cubera snapper' (Lutjanus cyanopterus, Cuvier, 1828), in the region of Ceara and 'Whitemouth croaker' (Micropogonias furnieri, Desmarest, 1823) and 'Lebranche mullet' (Mugil liza, Valenciennes, 1836) in the region of Rio de Janeiro. These concentrations were transformed in absorbed dose rate using a dose conversion factor in unit of gray per year (μGy y -1 ), per becquerel per kilogram (Bq kg -1 ). Only the absorbed dose due to intake of radionuclides was examined, and the contributions due to radionuclides present in water and sediment were disregarded. The radionuclides were considered to be uniformly distributed in the fish body. The limit of the dose rate used, proposed by the Department of Energy of the USA, is equal to 3.65 10 03 mGy y -1 . The average dose rate due to the studied radionuclides is equal to 6.09 10 00 μGy y -1 , a value minor than 0.1% than the limits indicated by DOE, and quite similar to that found in the literature for 'benthic' fish. The most important radionuclides were the alpha emitters Ra-226 having 61 % of absorbed dose rate. U-238 and Th-232, each contributes with approximately 20 % of the absorbed dose rate. These three radionuclides are responsible for almost 100% of the dose rate received by the studied organisms. The beta emitters Ra-228 and Pb-210 account for approximately 1 % of the absorbed dose rate. (author)

  3. A method for determining the analytical form of a radionuclide depth distribution using multiple gamma spectrometry measurements

    Energy Technology Data Exchange (ETDEWEB)

    Dewey, Steven Clifford, E-mail: sdewey001@gmail.com [United States Air Force School of Aerospace Medicine, Occupational Environmental Health Division, Health Physics Branch, Radiation Analysis Laboratories, 2350 Gillingham Drive, Brooks City-Base, TX 78235 (United States); Whetstone, Zachary David, E-mail: zacwhets@umich.edu [Radiological Health Engineering Laboratory, Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Boulevard, 1906 Cooley Building, Ann Arbor, MI 48109-2104 (United States); Kearfott, Kimberlee Jane, E-mail: kearfott@umich.edu [Radiological Health Engineering Laboratory, Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Boulevard, 1906 Cooley Building, Ann Arbor, MI 48109-2104 (United States)

    2011-06-15

    When characterizing environmental radioactivity, whether in the soil or within concrete building structures undergoing remediation or decommissioning, it is highly desirable to know the radionuclide depth distribution. This is typically modeled using continuous analytical expressions, whose forms are believed to best represent the true source distributions. In situ gamma ray spectroscopic measurements are combined with these models to fully describe the source. Currently, the choice of analytical expressions is based upon prior experimental core sampling results at similar locations, any known site history, or radionuclide transport models. This paper presents a method, employing multiple in situ measurements at a single site, for determining the analytical form that best represents the true depth distribution present. The measurements can be made using a variety of geometries, each of which has a different sensitivity variation with source spatial distribution. Using non-linear least squares numerical optimization methods, the results can be fit to a collection of analytical models and the parameters of each model determined. The analytical expression that results in the fit with the lowest residual is selected as the most accurate representation. A cursory examination is made of the effects of measurement errors on the method. - Highlights: > A new method for determining radionuclide distribution as a function of depth is presented. > Multiple measurements are used, with enough measurements to determine the unknowns in analytical functions that might describe the distribution. > The measurements must be as independent as possible, which is achieved through special collimation of the detector. > Although the effects of measurements errors may be significant on the results, an improvement over other methods is anticipated.

  4. Determination of natural occurring radionuclides concentrations

    International Nuclear Information System (INIS)

    Stajic, J.; Markovic, V.; Krstic, D.; Nikezic, D.

    2011-01-01

    Tobacco smoke contains certain concentrations of naturally occurring radionuclides from radioactive chains of uranium and thorium - 214 Pb, 214 Bi, 228 Ac, 208 Tl, 226 Ra, 232 Th and 40 K. Inhaling of tobacco smoke leads to internal exposure of man. In order to estimate absorbed dose of irradiation it is necessary to determine concentrations of radionuclides present in the tobacco leaves. In this paper specific activities of naturally occurring radionuclides were measured in tobacco samples from cigarettes which are used in Serbia. [sr

  5. Measuring Physical Activity Intensity

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  7. Measuring Physical Activity Intensity

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  8. Measuring Physical Activity Intensity

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  9. Measuring Physical Activity Intensity

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    Full Text Available ... an activity. When using relative intensity, people pay attention to how physical activity affects their heart rate ... Physical Activity Overweight & Obesity Healthy Weight Breastfeeding Micronutrient Malnutrition State and Local Programs File Formats Help: How ...

  10. Minimum detectable activities for natural radionuclides for IRIS-XP airborne gamma-spectrometer

    International Nuclear Information System (INIS)

    Ohera, Marcel; Sladek, Petr

    2009-01-01

    To subtract the 90 Sr background in the helicopter (the 90 Sr source is used as a freezing deposit indicator in Mi-17 helicopters), a spectrum at the altitude of more than 500 metre altitude above the ground for 10 minutes was acquired. The spectra at 50, 100 and 150 m altitude were corrected for the aircraft and the cosmics, stripping and height attenuation in K, U and Th peak windows. For IRIS-XP, better results have been obtained than presented so far. The new calculated minimum detectable activities (MDAs) are 114 Bq/kg for 40 K, 16 Bq/kg for 238 U and 8 Bq/kg for 232 Th at 95% confidence interval for 1 second spectra at 100 m altitude. This work deals with counting statistics and the estimate of the MDAs for natural radionuclides for the IRIS-XP airborne gamma-ray spectrometer (4 x 4 litre NaI(Tl)) produced by PICO Envirotec, Inc. in Toronto, Canada. The detection sensitivities (MDA) for 4 x 4 NaI(Tl) crystals at the altitude of 90 m presented by Pico Envirotec, Inc. are too high compared with the detection sensitivities presented by other airborne gamma-ray spectrometer producers. This was the reason why to calculate and verify the MDA for IRIS-XP. Firstly, the minimum detectable activities for IRIS-XP for 4 x 4 litre NaI(Tl) crystals were determined based on the data acquired on the calibration pads at the Holland Landing Airport in Toronto, Canada to test the method of calculation used. This method on calibration pads provides all available window sensitivities, stripping factors and counts in the natural radionuclide windows to verify the computing method. Secondly, the MDAs under the real flight conditions were also estimated for the IRIS-XP (4 x 4 litre NaI(Tl) crystals) which was delivered to the Czech Armed Forces. The MDAs were calculated based on the data acquired during the tests at the Military Training Area in Vyskov, Czech Republic. The data was collected at three different altitudes (50 m, 100 m and 150 m) when the Mi-17 helicopter with IRIS

  11. Measuring Physical Activity Intensity

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  12. 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)

  13. 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)

  14. Whole-body dose meters. Measurements of total activity

    International Nuclear Information System (INIS)

    Koeppe, P.; Klinikum Steglitz, Berlin

    1990-01-01

    By means of measurements using a whole-body dose meter, the course of the incorporation of radionuclides was established between April 1986 and May 1989 for unchanged conditions of alimentation, activity-conscious alimentation, and uniquely increased incorporation. Monitoring covered persons from the most different spheres of life. The incorporation is compared with the one resulting from nuclear weapons explosions in the atmosphere. (DG) [de

  15. Non-conventional measurement techniques for the determination of some long-lived radionuclides produced in nuclear fuel

    International Nuclear Information System (INIS)

    Rosenberg, R.J.

    1992-04-01

    The results of a literature survey on non-radiometric analytical techniques for the determination of long-lived radionuclides are described. The methods which have been considered are accelerator mass spectrometry, inductively coupled plasma mass spectrometry, thermal ionization mass spectrometry, resonance ionization spectrometry, resonance ionization mass spectrometry and neutron activation analysis. Neutron activation analysis has been commonly used for the determination of 129 I and 237 Np in environmental samples. Inductively coupled mass spectrometry seems likely to become the method of choice for the determination of 99 Tc, 237 Np and Pu-isotopes. The methods are discussed and the chemical separation methods described. (orig.)

  16. Radionuclide radiology

    International Nuclear Information System (INIS)

    Scarsbrook, A.F.; Graham, R.N.J.; Perriss, R.W.; Bradley, K.M.

    2006-01-01

    This is the fourth in a series of short reviews of internet-based radiological educational resources, and will focus on radionuclide radiology and nuclear medicine. What follows is a list of carefully selected websites to save time in searching them out. Most of the sites cater for trainee or non-specialist radiologists, but may also be of interest to specialists for use in teaching. This article may be particularly useful to radiologists interested in the rapidly expanding field of positron emission tomography computed tomography (PET-CT). Hyperlinks are available in the electronic version of this article and were all active at the time of going to press (February 2006)

  17. New ways in enhancing the vital activity of plants in order to increase crop yields and to suppress radionuclide accumulation

    International Nuclear Information System (INIS)

    Goncharova, N.; Kislushko, P.; Znebrakova, I.; Matsko, V.

    1994-01-01

    Soil contamination with long-lived isotopes as a result of Chernobyl nuclear accident necessitates substantially of crop raising procedures. It is found that by optimizing the vital activity processes in plants, is possible to reduce radionuclide uptake. In particular application of Fisher's mineral mix in concentration of 100, 200, 300, g/m 2 to soil decreased the 137 Cs accumulation in green material of lupine (Lupinus luteus L.) 1.1:1.3 and 2.2 times respectively and 1.2:1.1 and 1.1 times, respectively in green material of barley (Hordeum Vulgaris L.). The decrease of 90 Sr accumulation in green material of barley and lupine was similar. On the other hand chloroplasts isolated from showed higher activities of photochemical reactions and the light-dependent ATP enzyme. During the whole growing period of such plants the chlorophyll and protein concentration per wet unit mass were higher than those in control, therefore the high vital activity period in the former case was substantially extended. It has been also found that application of biologically active compounds and trace elements enhances photosynthetic and production activities of plants, reducing level radionuclide accumulation in the harvest. It is found that application of protectants and growth regulators to rye crops also reduces 137 Cs accumulation in green material in booting and earing phases. This finding suggests that this compounds activate the photosynthetic apparatus, reducing level radionuclide accumulation. (author)

  18. Measuring Physical Activity Intensity

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  19. Measuring Physical Activity Intensity

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  1. Measuring Physical Activity Intensity

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  5. Measuring Physical Activity Intensity

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    Full Text Available ... Share Compartir For more help with what counts as aerobic activity, watch this video: Windows Media Player, ... The table below lists examples of activities classified as moderate-intensity or vigorous-intensity based upon the ...

  6. Measuring Physical Activity Intensity

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  7. Measuring Physical Activity Intensity

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  8. Measuring Physical Activity Intensity

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    Full Text Available ... for a breath. Absolute Intensity The amount of energy used by the body per minute of activity. ... or vigorous-intensity based upon the amount of energy used by the body while doing the activity. ...

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  10. Activity measurements of radon from construction materials

    Energy Technology Data Exchange (ETDEWEB)

    Fior, L.; Nicolosi Correa, J. [Federal University of Technology - Parana, UTFPR, Av. Sete de Setembro, 3165, Curitiba, PR 80230-901 (Brazil); Paschuk, S.A., E-mail: spaschuk@gmail.com [Federal University of Technology - Parana, UTFPR, Av. Sete de Setembro, 3165, Curitiba, PR 80230-901 (Brazil); Denyak, V.V. [Federal University of Technology - Parana, UTFPR, Av. Sete de Setembro, 3165, Curitiba, PR 80230-901 (Brazil); Schelin, H.R. [Federal University of Technology - Parana, UTFPR, Av. Sete de Setembro, 3165, Curitiba, PR 80230-901 (Brazil); Pele Pequeno Principe Research Institute, Av. Silva Jardim, 1632, Curitiba, PR 80250-200 (Brazil); Soreanu Pecequilo, B.R. [Institute of Nuclear and Energetic Researches, IPEN, Av. Prof. Lineu Prestes, 2242-/05508-000 Sao Paulo (Brazil); Kappke, J. [Federal University of Technology - Parana, UTFPR, Av. Sete de Setembro, 3165, Curitiba, PR 80230-901 (Brazil)

    2012-07-15

    This work presents the results of radon concentration measurements of construction materials used in the Brazilian industry, such as clay (red) bricks and concrete blocks. The measurements focused on the detection of indoor radon activity during different construction stages and the analysis of radionuclides present in the construction materials. For this purpose, sealed chambers with internal dimensions of approximately 60 Multiplication-Sign 60 Multiplication-Sign 60 cm{sup 3} were built within a protected and isolated laboratory environment, and stable air humidity and temperature levels were maintained. These chambers were also used for radon emanation reduction tests. The chambers were built in four major stages: (1) assembly of the walls using clay (red) bricks, concrete blocks, and mortar; (2) installation of plaster; (3) finishing of wall surface using lime; and (4) insulation of wall surface and finishing using paint. Radon measurements were performed using polycarbonate etched track detectors. By comparing the three layers applied to the masonry walls, it was concluded that only the last step (wall painting using acrylic varnish) reduced the radon emanation, by a factor of approximately 2. Samples of the construction materials (clay bricks and concrete blocks) were ground, homogenized, and subjected to gamma-ray spectrometry analysis to evaluate the activity concentrations of {sup 226}Ra, {sup 232}Th and {sup 40}K. The values for the index of the activity concentration (I), radium equivalent activity (Ra{sub eq}), and external hazard index (H{sub ext}) showed that these construction materials could be used without restrictions or concern about the equivalent dose limit (1 mSv/year). - Highlights: Black-Right-Pointing-Pointer Radon activity in air related to building materials was measured. Black-Right-Pointing-Pointer The index of activity concentration of building materials was evaluated. Black-Right-Pointing-Pointer The radium equivalent activity of

  11. Measurement of Physical Activity.

    Science.gov (United States)

    Dishman, Rod K.; Washburn, Richard A.; Schoeller, Dale A.

    2001-01-01

    Valid assessment of physical activity must be unobtrusive, practical to administer, and specific about physical activity type, frequency, duration, and intensity. Assessment methods can be categorized according to whether they provide direct or indirect (e.g., self-report) observation of physical activity, body motion, physiological response…

  12. Report on a workshop on the measurement of soils to plant transfer factors for radionuclides

    International Nuclear Information System (INIS)

    1982-01-01

    This report includes the proceedings of the workshop on soil-plant transfer factors of radionuclides. Part 1 deals with a general introduction of soil-plant transfer factors, recommendations for the determination of these transfer factors and computer listing of transfer factors specified according to nuclide; type of crop; type of soil; and type of experiment. The second part offers the 12 contributions presented, of which several are included in INIS separately. (G.J.P.)

  13. Analytical studies by activation. Part A and B: Counting of short half-life radio-nuclides. Part C: Analytical programs for decay curves

    International Nuclear Information System (INIS)

    Junod, E.

    1966-03-01

    Part A and B: Since a radio-nuclide of short half-life is characterized essentially by the decrease in its activity even while it is being measured, the report begins by recalling the basic relationships linking the half-life the counting time, the counting rate and the number of particles recorded. The second part is devoted to the problem of corrections for counting losses due to the idle period of multichannel analyzers. Exact correction formulae have been drawn up for the case where the short half-life radionuclide is pure or contains only a long half-life radio-nuclide. By comparison, charts have been drawn up showing the approximations given by the so-called 'active time' counting and by the counting involving the real time associated with a measurement of the overall idle period, this latter method proving to be more valid than the former. A method is given for reducing the case of a complex mixture to that of a two-component mixture. Part C: The problems connected with the qualitative and quantitative analysis of the decay curves of a mixture of radioactive sources of which one at least has a short half-life are presented. A mathematical description is given of six basic processes for which some elements of Fortran programs are proposed. Two supplementary programs are drawn up for giving an overall treatment of problems of dosage in activation analysis: one on the basis of a simultaneous irradiation of the sample and of one or several known samples, the other with separate irradiation of the unknown and known samples, a dosimeter (activation, or external) being used for normalizing the irradiation flux conditions. (author) [fr

  14. Scaling model for prediction of radionuclide activity in cooling water using a regression triplet technique

    International Nuclear Information System (INIS)

    Silvia Dulanska; Lubomir Matel; Milan Meloun

    2010-01-01

    The decommissioning of the nuclear power plant (NPP) A1 Jaslovske Bohunice (Slovakia) is a complicated set of problems that is highly demanding both technically and financially. The basic goal of the decommissioning process is the total elimination of radioactive materials from the nuclear power plant area, and radwaste treatment to a form suitable for its safe disposal. The initial conditions of decommissioning also include elimination of the operational events, preparation and transport of the fuel from the plant territory, radiochemical and physical-chemical characterization of the radioactive wastes. One of the problems was and still is the processing of the liquid radioactive wastes. Such media is also the cooling water of the long-term storage of spent fuel. A suitable scaling model for predicting the activity of hard-to-detect radionuclides 239,240 Pu, 90 Sr and summary beta in cooling water using a regression triplet technique has been built using the regression triplet analysis and regression diagnostics. (author)

  15. Concentration of some radionuclides in some popular sudanese medicinal plants

    International Nuclear Information System (INIS)

    Sagiroun, M. I. A.

    2012-10-01

    In this study was measured concentration of naturally occurring radionuclides 2 38U , 2 32T h and 4 0K in samples of sudanese medicinal plants. The radionuclide activity concentrations in samples analyzed ranged from 4.09 to 41.07 Bq kg -1 for 2 38T h and from 353.14 to 2270.21 Bq kg -1 for 4 0k . No trace of artificial radionuclide was determined in all the samples. The effective dose due to the presence of these radionuclides was estimated and found to be 0.524 mSv/year which is well below the permissible levels. (Author)

  16. Measuring Physical Activity Intensity

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  17. Radionuclide trap

    International Nuclear Information System (INIS)

    McGuire, J.C.

    1978-01-01

    The deposition of radionuclides manganese-54, cobalt-58 and cobalt-60 from liquid sodium coolant is controlled by providing surfaces of nickel or high nickel alloys to extract the radionuclides from the liquid sodium, and by providing surfaces of tungsten, molybdenum or tantalum to prevent or retard radionuclide deposition

  18. Quality control for radionuclide determinations in the Saxon state laboratories for environmental radioactivity by intercomparison and comparative measurements

    International Nuclear Information System (INIS)

    Knobus, B.

    2001-01-01

    Quality control for radionuclide analysis is necessary and essential for the quality assurance of the measuring results executing the measuring programmes of surveillance of the radioactivity in the environment and from installations. Acts, ordinances and guidelines require the participation in intercomparisons for authorized institutions detecting the demanded quality of measurements (e.g. trueness, reproducibility) for Federal Authorities. These are mainly those intercomparisons which are prepared, practised and evaluated by the federal laboratories. Comparative measurements are generally organized and executed by the state laboratory itself with a few participants for special measuring tasks. In this paper are described and discussed extend and special results of those intercomparisons and comparative measurements of the Saxon state laboratories for environmental radioactivity from 1992 until 2000. If necessary, there are following improvements for quality assurance. (orig.) [de

  19. Measuring children's physical activity

    DEFF Research Database (Denmark)

    Schneller, Mikkel Bo; Bentsen, Peter; Nielsen, Glen

    2017-01-01

    INTRODUCTION: Accelerometer-based physical activity monitoring has become the method of choice in many large-scale physical activity (PA) studies. However, there is an ongoing debate regarding the placement of the device, the determination of device wear time, and how to solve a lack of participant...

  20. Measuring Children's Physical Activity

    DEFF Research Database (Denmark)

    Schneller, Mikkel Bo; Bentsen, Peter; Nielsen, Glen

    2017-01-01

    INTRODUCTION: Accelerometer-based physical activity monitoring has become the method of choice in many large-scale physical activity (PA) studies. However, there is an ongoing debate regarding the placement of the device, the determination of device wear time, and how to solve a lack of participant...

  1. National comparison on volume sample activity measurement methods

    International Nuclear Information System (INIS)

    Sahagia, M.; Grigorescu, E.L.; Popescu, C.; Razdolescu, C.

    1992-01-01

    A national comparison on volume sample activity measurements methods may be regarded as a step toward accomplishing the traceability of the environmental and food chain activity measurements to national standards. For this purpose, the Radionuclide Metrology Laboratory has distributed 137 Cs and 134 Cs water-equivalent solid standard sources to 24 laboratories having responsibilities in this matter. Every laboratory has to measure the activity of the received source(s) by using its own standards, equipment and methods and report the obtained results to the organizer. The 'measured activities' will be compared with the 'true activities'. A final report will be issued, which plans to evaluate the national level of precision of such measurements and give some suggestions for improvement. (Author)

  2. Development of standard ionization chamber counting system for activity measurements

    International Nuclear Information System (INIS)

    Pyun, Woong Beom; Lee, Hyun Koo; Lee, Hai Yong; Park, Tae Soon

    1998-01-01

    This study is to set up the activity measuring system using a 4π γ ionization chamber as used mainly in national standards laboratories that are responsible for radionuclide metrology. The software for automatic control between the electrometer and personal computer is developed using Microsoft visual basic 4.0 and IEEE488 Interface. The reproducibility of this 4π γ ionization chamber is about 0.02% and the background current is 0.054±0.024 pA. this 4π γ ionization chamber is calibrated by 6 standard gamma emitting radionuclides from KRISS. According to the result of this study, it is revealed that this 4π γ ionization chamber counting system can be used as a secondary standard instrument for radioactivity measurement

  3. Development of standard ionization chamber counting system for activity measurements

    CERN Document Server

    Pyun, W B; Lee, H Y; Park, T S

    1998-01-01

    This study is to set up the activity measuring system using a 4 pi gamma ionization chamber as used mainly in national standards laboratories that are responsible for radionuclide metrology. The software for automatic control between the electrometer and personal computer is developed using Microsoft visual basic 4.0 and IEEE488 Interface. The reproducibility of this 4 pi gamma ionization chamber is about 0.02% and the background current is 0.054+-0.024 pA. this 4 pi gamma ionization chamber is calibrated by 6 standard gamma emitting radionuclides from KRISS. According to the result of this study, it is revealed that this 4 pi gamma ionization chamber counting system can be used as a secondary standard instrument for radioactivity measurement.

  4. Marine biogeochemistry of radionuclides

    International Nuclear Information System (INIS)

    Fowler, S.W.

    1997-01-01

    Radionuclides entering the ocean from runoff, fallout, or deliberate release rapidly become involved in marine biogeochemical cycles. Sources, sinks and transport of radionuclides and analogue elements are discussed with emphasis placed on how these elements interact with marine organisms. Water, food and sediments are the source terms from which marine biota acquire radionuclides. Uptake from water occurs by surface adsorption, absorption across body surfaces, or a combination of both. Radionuclides ingested with food are either assimilated into tissue or excreted. The relative importance of the food and water pathway in uptake varies with the radionuclide and the conditions under which exposure occurs. Evidence suggests that, compared to the water and food pathways, bioavailability of sediment-bound radionuclides is low. Bioaccumulation processes are controlled by many environmental and intrinsic factors including exposure time, physical-chemical form of the radionuclide, salinity, temperature, competitive effects with other elements, organism size, physiology, life cycle and feeding habits. Once accumulated, radionuclides are transported actively by vertical and horizontal movements of organisms and passively by release of biogenic products, e.g., soluble excreta, feces, molts and eggs. Through feeding activities, particles containing radionuclides are ''packaged'' into larger aggregates which are redistributed upon release. Most radionuclides are not irreversibly bound to such particles but are remineralized as they sink and/or decompose. In the pelagic zones, sinking aggregates can further scavenge particle-reactive elements thus removing them from the surface layers and transporting them to depth. Evidence from both radiotracer experiments and in situ sediment trap studies is presented which illustrates the importance of biological scavenging in controlling the distribution of radionuclides in the water column. (author)

  5. Measuring Physical Activity Intensity

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    Full Text Available ... 45 David, Age 65 Harold, Age 67 Data & Statistics Facts About Physical Activity Data, Trends and Maps ... relative intensity and absolute intensity. Relative Intensity The level of effort required by a person to do ...

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    Full Text Available ... The amount of energy used by the body per minute of activity. The table below lists examples ... of Page Moderate Intensity Walking briskly (3 miles per hour or faster, but not race-walking) Water ...

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    Full Text Available ... Walkability Audit Tool Sample Audit Glossary Selected References Discount Fitness Club Network Assessing Need and Interest Selecting ... attention to how physical activity affects their heart rate and breathing. The talk test is a simple ...

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    ... 67 Data & Statistics Facts About Physical Activity Data, Trends and Maps Surveillance Systems Resources & Publications Reports Adults ... CDC’s Example StairWELL Stairwell Appearance Motivational Signs Installing Music Other Ideas to Consider Tracking Stair Usage Project ...

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    Full Text Available ... on this page will be unavailable. For more information about this message, please visit this page: About CDC.gov . ... Resources & Publications Reports Adults Need More Physical Activity ...

  18. The analysis of results of comparison test for radionuclides measurement through γ spectrum analysis from 2007 to 2012

    International Nuclear Information System (INIS)

    Wu Jialong; He Jian; Sun Wei; Wang Yun

    2013-01-01

    In order to test the capability of radionuclides measurement through γ spectrum analysis and improve the ability of the technicians by inter-laboratory comparison test, Gansu Center for Disease Prevention and Control participated in the comparison test organized by China Center for Disease Prevention and Control continuously from 2007 to 2012. All of the measured values are within the scope of qualified, and the relative deviation of measured value in the entire comparison tests is range from -16.31% to 11.83%.The results show that the equipment for γ spectrum measurement works normally, the analysis methods used for radioactive nuclide measuring is correct and the data in issued test report is accurate and reliable. The ability of the γ spectrum analysis satisfies the requirements of China Metrology Accreditation and the occupational health technical service. (authors)

  19. The influence of uncertainties of measurements in laboratory performance evaluation using an intercomparison program of radionuclide assays in environmental samples

    International Nuclear Information System (INIS)

    Tauhata, Luiz; Elizabeth Couto Machado Vianna, Maria; Eduardo de Oliveira, Antonio; Cristina de Melo Ferreira, Ana; Julia Camara da Silva Braganca, Maura; Faria Clain, Almir

    2006-01-01

    To show the influence of measurement uncertainties in performance evaluation of laboratories, data from 42 comparison runs were evaluated using two statistical criteria. The normalized standard deviation, D, used by US EPA, that mainly takes into account the accuracy, and the normalized deviation, E, that includes the individual laboratory uncertainty used for performance evaluation in the key-comparisons by BIPM. The results show that data evaluated by the different criteria give a significant deviation of laboratory performance in each radionuclide assay when we analyse a large quantity of data

  20. The influence of uncertainties of measurements in laboratory performance evaluation by intercomparison program in radionuclide analyses of environmental samples

    International Nuclear Information System (INIS)

    Tauhata, L.; Vianna, M.E.; Oliveira, A.E. de; Clain, A.F.; Ferreira, A.C.M.; Bernardes, E.M.

    2000-01-01

    The accuracy and precision of results of the radionuclide analyses in environmental samples are widely claimed internationally due to its consequences in the decision process coupled to evaluation of environmental pollution, impact, internal and external population exposure. These characteristics of measurement of the laboratories can be shown clearly using intercomparison data, due to the existence of a reference value and the need of three determinations for each analysis. In intercomparison studies accuracy in radionuclide assays in low-level environmental samples has usually been the main focus in performance evaluation and it can be estimated by taking into account the deviation between the experimental laboratory mean value and the reference value. The laboratory repeatability of measurements or their standard deviation is seldom included in performance evaluation. In order to show the influence of the uncertainties in performance evaluation of the laboratories, data of 22 intercomparison runs which distributed 790 spiked environmental samples to 20 Brazilian participant laboratories were compared, using the 'Normalised Standard Deviation' as statistical criteria for performance evaluation of U.S.EPA. It mainly takes into account the laboratory accuracy and the performance evaluation using the same data classified by normalised standard deviation modified by a weight reactor that includes the individual laboratory uncertainty. The results show a relative decrease in laboratory performance in each radionuclide assay: 1.8% for 65 Zn, 2.8% for 40 K, 3.4 for 60 Co, 3.7% for 134 Cs, 4.0% for 137 Cs, 4.4% for Th and U nat , 4.5% for 3 H, 6.3% for 133 Ba, 8.6% for 90 Sr, 10.6% for Gross Alpha, 10.9% for 106 Ru, 11.1% for 226 Ra, 11.5% for Gross Beta and 13.6% for 228 Ra. The changes in the parameters of the statistical distribution function were negligible and the distribution remained as Gaussian type for all radionuclides analysed. Data analyses in terms of

  1. Measuring Physical Activity Intensity

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    Full Text Available ... 10 miles per hour or faster Jumping rope Heavy gardening (continuous digging or hoeing) Hiking uphill or with a heavy backpack Other Methods of Measuring Intensity Target Heart ...

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    Full Text Available ... Hiking uphill or with a heavy backpack Other Methods of Measuring Intensity Target Heart Rate and Estimated ... Help: How do I view different file formats (PDF, DOC, PPT, MPEG) on this site? Adobe PDF ...

  3. Measuring Physical Activity Intensity

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    Full Text Available ... Hiking uphill or with a heavy backpack Other Methods of Measuring Intensity Target Heart Rate and Estimated ... YouTube Instagram Listen Watch RSS ABOUT About CDC Jobs Funding LEGAL Policies Privacy FOIA No Fear Act ...

  4. Measuring Physical Activity Intensity

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    Full Text Available ... Measuring Intensity Target Heart Rate and Estimated Maximum Heart Rate Perceived Exertion (Borg Rating of Perceived Exertion Scale) Get Email Updates To receive email updates about this page, enter your email ... ...

  5. Computation Of The Residual Radionuclide Activity Within Three Natural Waterways At The Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Hiergesell, R. A.; Phifer, M. A.

    2014-01-07

    In 2010 a Composite Analysis (CA) of the U.S. Department of Energy’s (DOE’s) Savannah River Site (SRS) was completed. This investigation evaluated the dose impact of the anticipated SRS End State residual sources of radionuclides to offsite members of the public. Doses were assessed at the locations where SRS site streams discharge into the Savannah River at the perimeter of the SRS. Although the model developed to perform this computation indicated that the dose constraint of 0.3 mSv/yr (30 mrem/yr), associated with CA, was not approached at the Points of Assessment (POAs), a significant contribution to the total computed dose was derived from the radionuclides (primarily Cs-137) bound-up in the soil and sediment of the drainage corridors of several SRS streams. DOE’s Low Level Waste Federal Review Group (LFRG) reviewed the 2010 CA and identified several items to be addressed in the SRS Maintenance Program. One of the items recognized Cs-137 in the Lower Three Runs (LTR) Integrator Operable Unit (IOU), as a significant CA dose driver. The item made the recommendation that SRS update the estimated radionuclide inventory, including Cs-137, in the LTR IOU. That initial work has been completed and its radionuclide inventory refined. There are five additional streams at SRS and the next phase of the response to the LFRG concern was to obtain a more accurate inventory and distribution of radionuclides in three of those streams, Fourmile Branch (FMB), Pen Branch (PB) and Steel Creek (SC). Each of these streams is designated as an IOU, which are defined for the purpose of this investigation as the surface water bodies and associated wetlands, including the channel sediment, floodplain sed/soil, and related biota. If present, radionuclides associated with IOUs are adsorbed to the streambed sediment and soils of the shallow floodplains that lie immediately adjacent to stream channels. The scope of this effort included the evaluation of any previous sampling and

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    Full Text Available ... June 4, 2015 Content source: Division of Nutrition, Physical Activity, and Obesity , National Center for Chronic Disease Prevention and Health Promotion Email Recommend Tweet YouTube Instagram Listen Watch RSS ABOUT About CDC Jobs Funding LEGAL Policies Privacy FOIA No Fear Act ...

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    Full Text Available ... Search Form Controls Search The CDC Cancel Submit Search The CDC Physical Activity Note: Javascript is disabled or is not supported by your browser. For this reason, some items on this page will be unavailable. For more information about this message, please visit this page: About ...

  8. Measuring Physical Activity Intensity

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    Full Text Available ... 67 Data & Statistics Facts About Physical Activity Data, Trends and Maps Surveillance Systems Resources & Publications Reports Adults ... CDC’s Example StairWELL Stairwell Appearance Motivational Signs Installing Music Other Ideas to Consider Tracking Stair Usage Project ...

  9. In situ gamma ray measurements of radionuclides at a disused phosphate mine on the West Coast of South Africa

    International Nuclear Information System (INIS)

    Bezuidenhout, Jacques

    2015-01-01

    High levels of uranium and its radioactive progeny like radium is normally associated with phosphate mining. In Situ gamma ray spectroscopy as a survey tool has been successfully applied to assess radionuclide concentrations in various geographical environments. A transportable and robust gamma ray detection system (GISPI) was therefore employed to determine the concentrations of naturally occurring radionuclides at a disused phosphate mine on the West Coast of South Africa. The concentrations of radium, thorium and potassium were measured and plotted. The measurements showed fairly high concentrations with medians of 320 Bq/kg for "2"2"6Ra, 64 Bq/kg for "2"3"2Th and 390 Bq/kg for "4"0K. The highest concentrations were however confined to specific areas of the mine. The effective dose due to gamma irradiation for the various areas of the mine was also estimated and the highest estimated level was 0.45 mSv/y. The article finally draws conclusions as to the origins and impact of the radiation. - Highlights: • A self-developed transportable and robust gamma ray detection system (the GISPI) was employed in the measurements. • A different mathematical analysis method was used. • QGIS was used extensively. • The results is important for current developments in infrastructure and mining.

  10. Equilibrium radionuclide assessment of left ventricular ejection and filling. Comparison of list mode-and multigated frame-mode measurements

    Energy Technology Data Exchange (ETDEWEB)

    Sugrue, D.D.; McKenna, W.J.; Dickie, S.; Oakley, C.M.; Myers, M.J.; Lavender, J.P. (Royal Postgraduate Medical School, London (UK))

    1983-10-01

    The relationship as studied between radionuclide indices of left ventricular systolic and diastolic function acquired in conventional multigated frame-mode compared to list-mode in patients with sinus rhythm. The study showed that frame-mode and list-mode measurements of ejection and filling indices are not significantly different in these patients but that backward reformatting of data acquired in list-mode is necessary to measure the atrial contribution to LV stroke counts. It was concluded that valid measurements of left ventricular systolic ejection and diastolic filling can be made in patients in sinus rhythm using frame-mode acquisition with the exception of measurements of the contribution from atrial systole to stroke volume.

  11. Radionuclide mobility in the shallow portion of an active high-temperature geothermal system

    International Nuclear Information System (INIS)

    Sturchio, N.C.; Seitz, M.G.

    1984-01-01

    Accurate knowledge of the behavior of radionuclides in natural rock-water systems is crucial for the prediction of the consequences of failure of a high-level nuclear waste repository. Work in progress at Argonne National Laboratory involves the detailed geochemical analysis of rock, mineral, and water samples from shallow drill holes in a thermal area of Yellowstone National Park. This study is designed to provide data that will increase our understanding of the behavior of a group of radionuclides in an environment similar to that of the near field of a high-level nuclear waste repository

  12. Underwater in situ measurements of radionuclides in selected submarine groundwater springs, Mediterranean sea

    International Nuclear Information System (INIS)

    Tsabaris, C.; Scholten, J.; Karageorgis, A. P.; Comanducci, J. F.; Georgopoulos, D.; Liong Wee Kwong, L.; Patiris, D. L.; Papathanassiou, E.

    2010-01-01

    The application of the in situ measurement system 'KATERINA' for monitoring of radon progenies in submarine groundwater discharge (SGD) was investigated at different locations in the Mediterranean Sea (Chalkida, Stoupa, Korfos and Cabbe). At Chalkida and Stoupa radon progenies concentration exhibited almost constant values of 1.2±0.1 and 2.5±0.2 Bq l -1 , respectively. At Korfos these activities ranged between 1.4±0.1 and 2.3±0.2 Bq l -1 exhibiting inverse relationship with salinity. At Cabbe the in situ measured data were compared with radon measurements obtained by liquid scintillation counter. The system also resolved radon progeny variations of SGD on time scales above 1 h. The radioactivity levels of radon progenies from all sites were found considerably lower (approximately 2 orders of magnitude) than the commonly accepted limits for radon in drinking water. (authors)

  13. Applications of neutron activation analysis in determination of natural and man-made radionuclides, including PA-231

    Science.gov (United States)

    Byrne, A. R.; Benedik, L.

    1999-01-01

    Neutron activation analysis (NAA), being essentially an isotopic and not an elemental method of analysis, is capable of determining a number of important radionuclides of radioecological interest by transformation into another, more easily quantifiable radionuclide. The nuclear characteristics which favour this technique may be summarized in an advantage factor relative to radiometric analysis of the original radioanalyte. Well known or hardly known examples include235U,238U,232Th,230Th,129I,99Tc,237Np and231Pa; a number of these are discussed and illustrated in analysis of real samples of environmental and biological origin. In particular, determination of231Pa by RNAA was performed using both postirradiation and preseparation methods. Application of INAA to enable the use of238U and232Th as endogenous (internal) radiotracers in alpha spectrometric analyses of uranium and thorium radioisotopes in radioecological studies is described, also allowing independent data sets to be obtained for quality control.

  14. Assessment of fetal activity concentration and fetal dose for selected radionuclides based on animal and human data

    International Nuclear Information System (INIS)

    Roedler, H.D.

    1987-01-01

    Biokinetic data of selected radionuclide compounds from investigations in man and animal were taken from literature references with the purpose to provide a basis for a comparative assessment of fetal and adult radiation doses after intake or administration of radionuclides. The following ratios of fetal to adult doses were derived from human data: 0.5 for caesium 137 and total body, 2.3 for iron 59 and liver, 0.06 - 0.3 - 1.1 for iodine 131 and thyroid, and 0.1 - 0.3 for strontium 90 and bone. The ratios of activity concentrations in fetal and adult tissues are of considerable variability - up to three orders of magnitude. Further studies on fetal and adult biokinetics specifically designed for comparative dose assessment are indispensable. 106 refs.; 6 tabs

  15. Applicability of alkali activated slag-seeded Egyptian Sinai kaolin for the immobilization of 60Co radionuclide

    International Nuclear Information System (INIS)

    El-Naggar, M.R.

    2014-01-01

    The present work was established to determine the applicability of local Egyptian kaolinite and blast furnace slag (BFS) as raw materials toward the synthesis of geopolymers and subsequent immobilization of cobalt-60, which is one of the most abundant radionuclides generated in radioactive waste streams in Egypt. XRF, XRD, FT-IR, and SEM techniques were used to characterize the local raw materials and their corresponding alkali activated products. Metakaolin (MK) was obtained by thermal treatment of Egyptian Sinai kaolin 750 °C/4 h. MK and five different BFS content (5, 10, 30, 50 and 80%) were used to synthesize geopolymeric matrices using an alkaline activator of Si-modulus = 1.35 at solid/liquid ratios of 0.8. Compressive strength tests were performed indicating that 50% BFS addition gave the highest values of compressive strength. The IAEA standard leaching tests of cobalt-60 from the solidified waste matrices were carried out. The effective diffusion coefficients of cobalt-60 radionuclides from the solidified waste matrices were calculated to be in the order of 10 −14 cm 2 /s. Leaching of radionuclides was examined to be controlled by the wash-off mechanism with very acceptable values. These results gave encouragement that the tested Egyptian raw materials can be conveniently applied for the synthesis of geopolymers that can be used as a low-cost and high-efficiency materials for the immobilization of radioactive waste

  16. Radionuclides in analytical chemistry

    International Nuclear Information System (INIS)

    Tousset, J.

    1984-01-01

    Applications of radionuclides in analytical chemistry are reviewed in this article: tracers, radioactive sources and activation analysis. Examples are given in all these fields and it is concluded that these methods should be used more widely [fr

  17. Mercury mass measurement in fluorescent lamps via neutron activation analysis

    International Nuclear Information System (INIS)

    Viererbl, L.; Vinš, M.; Lahodová, Z.; Fuksa, A.; Kučera, J.; Koleška, M.; Voljanskij, A.

    2015-01-01

    Mercury is an essential component of fluorescent lamps. Not all fluorescent lamps are recycled, resulting in contamination of the environment with toxic mercury, making measurement of the mercury mass used in fluorescent lamps important. Mercury mass measurement of lamps via instrumental neutron activation analysis (NAA) was tested under various conditions in the LVR-15 research reactor. Fluorescent lamps were irradiated in different positions in vertical irradiation channels and a horizontal channel in neutron fields with total fluence rates from 3×10 8 cm −2 s −1 to 10 14 cm −2 s −1 . The 202 Hg(n,γ) 203 Hg nuclear reaction was used for mercury mass evaluation. Activities of 203 Hg and others induced radionuclides were measured via gamma spectrometry with an HPGe detector at various times after irradiation. Standards containing an Hg 2 Cl 2 compound were used to determine mercury mass. Problems arise from the presence of elements with a large effective cross section in luminescent material (europium, antimony and gadolinium) and glass (boron). The paper describes optimization of the NAA procedure in the LVR-15 research reactor with particular attention to influence of neutron self-absorption in fluorescent lamps. - Highlights: • Mercury is an essential component of fluorescent lamps. • Fluorescent lamps were irradiated in neutron fields in research reactor. • 203 Hg induced radionuclide activity was measured using gamma spectrometry. • Mercury mass in fluorescent lamps can be measured by neutron activation analysis.

  18. Activity measurements of radon from construction materials.

    Science.gov (United States)

    Fior, L; Nicolosi Corrêa, J; Paschuk, S A; Denyak, V V; Schelin, H R; Soreanu Pecequilo, B R; Kappke, J

    2012-07-01

    This work presents the results of radon concentration measurements of construction materials used in the Brazilian industry, such as clay (red) bricks and concrete blocks. The measurements focused on the detection of indoor radon activity during different construction stages and the analysis of radionuclides present in the construction materials. For this purpose, sealed chambers with internal dimensions of approximately 60×60×60 cm3 were built within a protected and isolated laboratory environment, and stable air humidity and temperature levels were maintained. These chambers were also used for radon emanation reduction tests. The chambers were built in four major stages: (1) assembly of the walls using clay (red) bricks, concrete blocks, and mortar; (2) installation of plaster; (3) finishing of wall surface using lime; and (4) insulation of wall surface and finishing using paint. Radon measurements were performed using polycarbonate etched track detectors. By comparing the three layers applied to the masonry walls, it was concluded that only the last step (wall painting using acrylic varnish) reduced the radon emanation, by a factor of approximately 2. Samples of the construction materials (clay bricks and concrete blocks) were ground, homogenized, and subjected to gamma-ray spectrometry analysis to evaluate the activity concentrations of 226Ra, 232Th and 40K. The values for the index of the activity concentration (I), radium equivalent activity (Raeq), and external hazard index (Hext) showed that these construction materials could be used without restrictions or concern about the equivalent dose limit (1 mSv/year). Copyright © 2011 Elsevier Ltd. All rights reserved.

  19. Intercomparison of natural radionuclide measurements in marine sediment sample SD-N-1/2

    International Nuclear Information System (INIS)

    1985-06-01

    This intercomparison exercise was organized with the aim of providing to the participating laboratories a possibility of testing the performance of their analytical methods and to acquire basic data for establishing reference values for a number of natural radionuclides in the sediment material SD-N-1/2 from the North Sea floor. In tables are presented results expressed in mBq.g -1 on potassium, uranium isotopes, thorium-232 with the respective decay products, thorium-230, radium-226 and lead-210. Altogether 98 laboratories from 42 Member States joined this intercomparison. The results show generally good agreement, but more analytical work is needed to improve the present status of the lead-210 certification. Gamma and alpha spectroscopy were the most frequently used as the analytical techniques

  20. ''Blood flow measurements in the irradiated pig skin using β emitters radionuclides''

    International Nuclear Information System (INIS)

    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 γ 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 β 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 32 P sources placed at different depths, it was possible to study the degradation of β 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 32 P phosphate administered intravenously in pigs. (author)

  1. Intercomparison of radionuclides measurements in marine cockle flesh sample IAEA-134

    Energy Technology Data Exchange (ETDEWEB)

    Ballestra, S; Gastaud, J; Lopez, J J; Parsi, P; Vas, D

    1993-08-01

    The results of an intercomparison exercise on a cockle flesh sample from Irish Sea, IAEA-134, designed for the determination of artificial and natural radionuclide levels, are reported. The data from 134 laboratories representing 49 countries have been evaluated. The following are the recommended values, with confidence intervals, for {sup 40}K, {sup 60}Co, {sup 137}Cs, and 2{sup 39+240}Pu (Reference date: 1 January 1992). Information values for {sup 90}Sr, {sup 106}Ru, {sup 125}Sb, {sup 134}Cs, {sup 154}Eu, {sup 155}Eu, {sup 210}Pb, {sup 210}Po, {sup 226}Ra, {sup 228}Ra, {sup 228}Th, {sup 230}Th, {sup 232}Th, {sup 234}U, {sup 235}U, {sup 238}U, {sup 238}Pu and {sup 241}Am are also reported. All the following values are expressed in Bq kg{sup -1} (dry weight). (author)

  2. Intercomparison of radionuclides measurements in marine cockle flesh sample IAEA-134

    International Nuclear Information System (INIS)

    Ballestra, S.; Gastaud, J.; Lopez, J.J.; Parsi, P.; Vas, D.

    1993-08-01

    The results of an intercomparison exercise on a cockle flesh sample from Irish Sea, IAEA-134, designed for the determination of artificial and natural radionuclide levels, are reported. The data from 134 laboratories representing 49 countries have been evaluated. The following are the recommended values, with confidence intervals, for 40 K, 60 Co, 137 Cs, and 2 39+240 Pu (Reference date: 1 January 1992). Information values for 90 Sr, 106 Ru, 125 Sb, 134 Cs, 154 Eu, 155 Eu, 210 Pb, 210 Po, 226 Ra, 228 Ra, 228 Th, 230 Th, 232 Th, 234 U, 235 U, 238 U, 238 Pu and 241 Am are also reported. All the following values are expressed in Bq kg -1 (dry weight). (author)

  3. Clinical application of iodine 123 with special consideration of radionuclide purity, measuring accuracy and radiation dose

    International Nuclear Information System (INIS)

    Hermann, H.J.; Ammon, J.; Winkel, K. zum; Haubold, U.

    1975-01-01

    Iodine 123 is a nearly 'ideal' radionuclide for thyroid imaging. The production of Iodine 123 requires cyclotrons or accelerators. The production of multicurie amounts of Iodine 123 has been suggested through the use of high-energy accelerators (> 60 MeV). Most of the methods for the production of Iodine 123 using a compact cyclotron result in contamination with f.e. Iodine 124 which reduces the spatial resolution of imaging procedures and increases the radiation dose to the patient. The radiation dose has been calculated for three methods of production. The various contamination with Iodine 124, Iodine 125 and Iodine 126 result in comparable radiation dose of Iodine 131, provided that the time between production and application is more than four half-live-times of Iodine 123. (orig.) [de

  4. A method of alpha-radiating nuclide activity measuring in aerosol filters

    International Nuclear Information System (INIS)

    Ignatov, V.P.; Galkina, V.N.

    1992-01-01

    Scintillation method of determination of alpha-radiating nuclide activity in aerosol filters was suggested. The method involves dissolution of the filter in organic solvent, introduction of luminophore into solution prepared, drying of the preparation and measurement of radionuclide activity. Dependences of alpha-radiation detection efficiency on the content of luminophore, filter material, colourless and coloured substances in preparations analyzed were considered

  5. Intercomparison of radionuclide measurements in marine fish flesh sample MA-B-3

    International Nuclear Information System (INIS)

    1987-08-01

    This final report presents results of the laboratory intercomparison of the activity concentration determination of 40 K, 90 Sr, 137 Cs, 210 Pb, 210 Po, 226 Ra, 228 Th, 230 Th, 232 Th, 238 U, 239 Pu, 240 Pu and 241 Am in the sample of garpike fish organized by the IAEA's Analytical Quality Control Service. The forty-three laboratories from twenty-three countries have reported results established by different analytical techniques. This sample is intended as a reference material for the measurement of 40 K and 137 Cs in marine biological samples and other similar matrices. 4 refs, 9 tabs

  6. Determination of activity by gamma spectrometry of radionuclides present in drums of residues generated in nuclear centrals

    International Nuclear Information System (INIS)

    Aguiar, J.C.; Fernandez, J.

    2006-01-01

    The generation of radioactive residuals in nuclear centrals as CNA I (Atucha I Nuclear Central) and CNE (Embalse Nuclear Central) makes that the measurement of those radionuclides has been a previous stage to the waste management. A method used in those nuclear centrals it is the gamma spectrometry with HPGe detectors, previous to the immobilization of the residual in a cemented matrix, with this the contact with the external agents and its possible dispersion to the atmosphere in the short term is avoided. The ARN (Nuclear Regulatory Authority) of Argentina it carries out periodically intercomparisons and evaluations of the measurement and procedures systems used in the nuclear power stations for the correct measurement and determination of activity of radioactive residuals by gamma spectrometry. In this work an independent method of measurement is exposed to the nuclear power stations. To determine the activity of the residuals by gamma spectrometry deposited in drums, it is required of the precise knowledge of the efficiency curve for such geometry and matrix. Due to the RNA doesn't have a pattern of these characteristics, a mathematical model has been used to obtain this efficiency curve. For it, it is necessary to determine previously: 1) the geometric efficiency or solid angle sustained by the source-detector system (drum-detector) applying a mathematical model described in this work. 2) To estimate the auto-attenuation factor that present the photons in the cemented matrix, these calculations are carried out with a simple equation and its are verified with the Micro Shield 6.10 program. The container commonly used by these nuclear power stations its are drums for 220 liters constructed with SAE 1010 steel and with a thickness of 0.127 cm, with an approximate weight 7.73 Kg., internal diameter of 57.1 cm, and height: 87 cm. The results obtained until the moment register a discrepancy from 5 to 10% with relationship to the measurements carried out by the

  7. Technical investigation of cerebral blood flow measurements using the Patlak plot method. A contrivance for positioning of the gamma camera at data collection in radionuclide angiography

    Energy Technology Data Exchange (ETDEWEB)

    Takaki, Akihiro; Okada, Kazuhiro; Urata, Johji; Yonehara, Toshiro [Saiseikai Kumamoto Hospital (Japan); Mizuta, Yoshihiko

    1999-02-01

    The time-activity curve for the aortic arch obtained from radionuclide angiography (RNA) is handled as an input function parameter according to the method of Matsuda et al., which determines regional cerebral blood flow non-invasively. The data are collected from a frontal view of the thorax captured by RNA by their method, however we encountered a case in which it was difficult to identify aortic arch in the data collection from the frontal view. The precise identification of the aortic arch was implemented when the RNA data were collected from the left anterior oblique view of the thorax. No significant difference was noted in the measured values between the data collection from the frontal view and from the left anterior oblique view. Our method seems to be useful modification of the Patlak plot method. (author)

  8. Measurement of radionuclides in contaminated environmental matrices: participation in quality assessment programme of U.S. Department of energy's environmental monitoring laboratory

    International Nuclear Information System (INIS)

    SIDDIQUE, N.; Rahman, A.; Waheed, S.; Wasim, M.; Daud, M.; Ahmad, S.

    2006-03-01

    A Quality Assessment Programme (QAP) was initiated by the US, Department of Energy (DOE) in 1998 to establish credibility of radionuclide measurements in contaminated environmental samples, i.e. soil, vegetation and air filters. In this context best-known and pertinent laboratories around the world were identified and invited to participate in this programme. To evaluate the performance of these prestigious laboratories, the Miniature Neutron Source Reactor (MNSR) Neutron Activation Analysis (NAA) Laboratory at NCD, PINSTECH, which is an IAEA declared Regional Resource Unit (IAEA-RRU), along with 76 other laboratories were asked to take part in a regular proficiency exercise. In this report, the performance of the NAA Laboratory throughout the QAP programme (1998-2004) is presented is detail, describing the procedures employed, the problems encountered and the improvement and expertise gained from participating in this assessment programme. (author)

  9. Intercomparison measurements of surface soil contamination with in-situ gamma ray spectrometry. Pt.1. Artificial radionuclides

    International Nuclear Information System (INIS)

    Winkelmann, I.

    1994-01-01

    This intercomparison program was performed by the Federal Office of Radiation Protection in October 1993. It includes seven laboratory teams from five countries and is applied on a pasture in southern Germany having an undisturbed soil profile. The location was chosen because of its relatively high 137 Cs-soil contamination caused by the Chernobyl accident - up to 50 kBq/m 2 . The deposition of 134 Cs and 137 Cs was determined. The comparison demonstrated a good agreement between results from different labs. Additionally, the dose rate at all marked locations was measured and compared to the dose rate of individual radionuclides calculated from the measured spectra. A relatively good agreement was obtained. It is shown that the main contribution to the total dose rate of 70 nSv/h is made by 137 Cs with a value of 5 nSv/h. 4 figs., 2 tabs., 3 refs. (orig.)

  10. Method for measuring the decay rate of a radionuclide emitting β-rays in a liquid sample

    International Nuclear Information System (INIS)

    Horrocks, D.

    1977-01-01

    With this method the decay rate of a radionuclide emitting β-rays, e.g. 3 H or 14 C, in a liquid sample can be measured by means of liquid scintillation counters, at least two different versions of the sample being used with quench effect (shifting of the Compton spectrum). For this purpose each sample is counted with and without a radioactive standard source, e.g. 137 Cs. Then a pulse height will be determined corresponding to a selected point in the pulse height spectrum if the standard source is present. The determination of a zero-threshold sample count rate is then performed by counting the sample in a counting window. In addition standardized values of the measured pulse heights are derived and put in mathematical relation to corresponding pulse count rates, the pulse count rate for a standardized pulse height value thus becoming zero and the sample decay rate in this way being determined. (DG) 891 HP [de

  11. Electrical measurement of sweat activity

    International Nuclear Information System (INIS)

    Tronstad, Christian; Grimnes, Sverre; Martinsen, Ørjan G; Gjein, Gaute E; Fosse, Erik; Krogstad, Anne-Lene

    2008-01-01

    A multichannel logger for long-term measurements of sweat activity is presented. The logger uses skin surface electrodes for unipolar admittance measurements in the stratum corneum. The logger is developed with emphasis on clinical use. The portability of the logger enables recording of sweat activity under circumstances such as daily errands, exercise and sleep. Measurements have been done on 24 healthy volunteers during relaxation and exercise with heart rate monitoring. Recordings of sweat activity during sleep have been done on two healthy subjects. Early results show good agreement with the literature on sweating physiology and electrodermal activity. Results are presented showing measurements related to physical exercise, dermatomes, distribution of sweat glands and sympathetic activity. This study examines the normal sweating patterns for the healthy population, and we present results with the first 24 healthy volunteers. Comparing these results with similar measurements on hyperhidrosis patients will make it possible to find the most useful parameters for diagnosis and treatment evaluation

  12. Radionuclide cardiography in medical practice

    International Nuclear Information System (INIS)

    Strangfeld, D.; Mohnike, W.; Schmidt, J.; Heine, H.; Correns, H.J.

    1986-01-01

    This publication is a compendium on all aspects of radionuclide diagnostics concerning cardiovascular system diseases. Starting with introductory remarks on the control of cardiovascular diseases the contribution of radionuclide cardiology to functional cardiovascular diagnostics as well as pathophysiological and pathobiochemical aspects of radiocardiography are outlined. Radiopharmaceuticals used in radiocardiography, physical and technical problems in application of radionuclides and their measuring techniques are discussed. In individual chapters radionuclide ventriculography, myocardial scintiscanning, circulatory diagnostics, radionuclide diagnostics of arterial hypertension, of thrombosis and in vitro diagnostics of thrombophilia are treated in the framework of clinical medicine

  13. The results of artificial radionuclides monitoring in the Baltic sea

    International Nuclear Information System (INIS)

    Astrauskiene, N.; Lukinskiene, M; Zemaitiene, G.

    1994-01-01

    Long-term radionuclides volume activity (v.a.) monitoring (1976-1990) data showed that measurement results obtained in steady observation station give reliable information of the coastal area of the Baltic sea radioactive equilibrium between atmosphere and surface water was observed in the coastal zone. Chernobyl Power Plant accident influenced upon the Baltic sea coastal water by radionuclides 137 Cs and 144 Ce. Radionuclide 90 Sr volume activity was practically unchangerable. The mechanism of radionuclides fallout from atmosphere are various. lt can be illustrated by 137 Cs and 144 Ce a.v. structure field variations in open sea and coastal zone near Juodkrante. The Baltic sea inhomogeneous contamination by radionuclide 137 Cs in 1988-1990 leads to equalization of 137 Cs v.a. in the surface waters and it causes v.a. increase in coastal waters. (author)

  14. Measurements of 60Co in spoons activated by neutrons during the JCO criticality accident at Tokai-mura in 1999

    International Nuclear Information System (INIS)

    Gasparro, J.; Hult, M.; Komura, K.; Arnold, D.; Holmes, L.; Johnston, P.N.; Laubenstein, M.; Neumaier, S.; Reyss, J.-L.; Schillebeeckx, P.; Tagziria, H.; Van Britsom, G.; Vasselli, R.

    2004-01-01

    Neutron activated items from the vicinity of the place where the JCO criticality accident occurred have been used to determine the fluence of neutrons around the facility and in nearby residential areas. By using underground laboratories for measuring the activation products, it is possible to extend the study to also cover radionuclides with very low activities from long-lived radionuclides. The present study describes γ-ray spectrometry measurements undertaken in a range of underground laboratories for the purpose of measuring 60 Co more than 2 years after the criticality event. The measurements show that neutron fluence determined from 60 Co activity is in agreement with previous measurements using the short-lived radionuclides 51 Cr and 59 Fe. Limits on contamination of the samples with 60 Co are evaluated and shown to not greatly affect the utility of neutron fluence determinations using 60 Co activation

  15. Measurements of 60Co in spoons activated by neutrons during the JCO criticality accident at Tokai-mura in 1999.

    Science.gov (United States)

    Gasparro, J; Hult, M; Komura, K; Arnold, D; Holmes, L; Johnston, P N; Laubenstein, M; Neumaier, S; Reyss, J-L; Schillebeeckx, P; Tagziria, H; Van Britsom, G; Vasselli, R

    2004-01-01

    Neutron activated items from the vicinity of the place where the JCO criticality accident occurred have been used to determine the fluence of neutrons around the facility and in nearby residential areas. By using underground laboratories for measuring the activation products, it is possible to extend the study to also cover radionuclides with very low activities from long-lived radionuclides. The present study describes gamma-ray spectrometry measurements undertaken in a range of underground laboratories for the purpose of measuring (60)Co more than 2 years after the criticality event. The measurements show that neutron fluence determined from (60)Co activity is in agreement with previous measurements using the short-lived radionuclides (51)Cr and (59)Fe. Limits on contamination of the samples with (60)Co are evaluated and shown to not greatly affect the utility of neutron fluence determinations using (60)Co activation.

  16. Review of short-lived radionuclide activities in the United States

    International Nuclear Information System (INIS)

    Sodd, V.J.

    1985-01-01

    A review is given of the accelerator-produced short-lived radionuclides which are used in radiopharmaceuticals available commercially in the US and of the accelerator facilities devoted primarily to their production. Reactions for the efficient production of 67 Ga, 81 Rb → /sup 81m/Kr, 111 In, 201 Tl, and 123 I are given. Methods for the production of higher purity 123 I are suggested

  17. Limiting values for radionuclide concentration in the soil from remote spectrometer measurements

    International Nuclear Information System (INIS)

    Stuart, T.P.

    1977-08-01

    Spectrometers that remotely sense γ-rays in the soil are usually oriented with the normal to a planar surface perpendicular to the air-soil interface. When this is the case, and when the thickness of the detector is not greater than the linear dimensions that determine the aforementioned surface area, simple assumptions can be made to calculate high and low limits for factors that convert from photopeak count rates in the spectrometer to soil concentrations. An H.P. 65 calculator program is developed to calculate these two conversion factors as a function of detector altitude, counting rates from a single measurement with a point calibration source, shielding on the surface of the detector, and depth of activity in the soil. The assumption of an exponential decrease with depth allows the previously reported results of Beck et al to be applied to convert from soil concentration to dose rate at 1 m above the ground

  18. Holmium-166m: multi-gamma standard to determine the activity of radionuclides in semiconductor detectors

    International Nuclear Information System (INIS)

    Bernardes, Estela Maria de Oliveira

    2001-01-01

    The efficiency and calibration curves as function of gamma-ray energy for a germanium detector are usually established by using many standard gamma ray sources of radionuclides decaying with few gamma rays or radionuclides having complex decay scheme, as 152 Eu or 133 Ba. But these radionuclides cannot be used alone, because they have a few gamma lines with high intensity and these lines have a irregular distribution in the energy spectrum. 166m Ho is found to be a convenient single source for such calibration, because it decays by β - with subsequent emission of about 40 strong and well distributed gamma lines between 80 and 1500 keV. Moreover, its long half - life (1200 years) and X-rays characteristics between 40 and 50 keV makes it a good standard for calibration of germanium detectors. However, it is necessary to know with accuracy and precision the gamma ray intensities of their main lines, due to the fact that literature has showed discrepant values. Then, a methodology to determine the emission probability of its main lines is proposed by means of combined use of gamma spectrometry and coincidence 4πβ -γ techniques. The experimental results show consistence to the others authors, with lower or compatible uncertainties. (author)

  19. Response of left ventricular ejection fraction to recovery from general anesthesia: measurement by gated radionuclide angiography

    International Nuclear Information System (INIS)

    Coriat, P.; Mundler, O.; Bousseau, D.; Fauchet, M.; Rous, A.C.; Echter, E.; Viars, P.

    1986-01-01

    To test the hypothesis that, after anesthesia for noncardiac surgical procedures, the increased cardiac work during recovery induces wall motion and ejection fraction (EF) abnormalities in patients with mild angina pectoris, gated radionuclide angiography was performed in patients undergoing simple cholecystectomy under narcotic-relaxant general anesthesia. The ejection fraction was determined during anesthesia at the end of surgery, and then determined 3 min and 3 hr after extubation. A new angiography was performed 24 hr later, and a myocardial scintigraphy (Thallium 201) was performed during infusion of the coronary vasodilator, dipyridamole. In the first part of the investigation, eight patients without coronary artery disease (CAD) (group 1) and 20 patients with mild angina (group 2) were studied. In the second part of the study, seven patients (group 3) with mild angina pectoris received an intravenous infusion of 0.4 microgram X kg-1 X min-1 of nitroglycerin started before surgery and gradually decreased 4 hr after extubation. In group 1, EF remained unchanged at recovery. In contrast in group 2, EF responded abnormally to recovery: EF decreased from 55% during anesthesia to 45% 3 min after extubation (P less than 0.001). Patients in group 3, who received intravenous nitroglycerin, showed no change of EF at recovery. This study demonstrates that recovery from general anesthesia causes abnormalities in left ventricular function in patients suffering from CAD. These abnormalities are prevented by prophylactic intravenous nitroglycerin

  20. Measurement of artificial radionuclides in whole diets around the BNF plc reprocessing plant at Sellafield, Cumbria

    International Nuclear Information System (INIS)

    Mondon, K.J.; Walters, B.

    1993-01-01

    The Ministry of Agriculture, Fisheries and Food has conducted a duplicate diet study around the BNF reprocessing plant of Sellafield in Cumbria. Samples were collected from adults and children. The results of analyses for a number of artificial radionuclides are reported; dose calculations using actual food intakes have also been made. Samples were obtained in both winter (phase 1) and summer (phase 11), between which times the Chernobyl accident occurred, making site-specific dose assessment from caesium isotopes difficult in summer samples. Control diets were collected from a coastal area in Lancashire. Average annual doses based on pre-Chernobyl sampling ranged from 2 μSv in control children to 14 μSv in study adults. This range increased to 9-50 μSv in the second phase of the study. Maximum individual doses were 86 μSv in phase 1 and 102 μ in phase 11, these being well within the government's target dose for members of the public. (author)

  1. Environmental monitoring at the nuclear power plants and Studsvik 1992-1993. Results from measurements of radionuclide contents of environmental samples, and from random checks by SSI

    International Nuclear Information System (INIS)

    Bengtson, P.; Larsson, C.M.; Simenstad, P.; Suomela, J.

    1995-09-01

    Marine samples from the vicinity of the plants show elevated radionuclide concentrations, caused by discharges from the plants. Very low concentrations are noted in terrestrial samples. At several locations, the effects of the Chernobyl disaster still dominates. Control samples measured by SSI have confirmed the measurements performed by the operators. 8 refs, 6 tabs, 46 figs

  2. Radionuclide cisternography

    International Nuclear Information System (INIS)

    Song, H.H.

    1980-01-01

    The purpose of this thesis is to show that radionuclide cisternography makes an essential contribution to the investigation of cerebrospinal fluid (CSF) dynamics, especially for the investigation of hydrocephalus. The technical details of radionuclide cisternography are discussed, followed by a description of the normal and abnormal radionuclide cisternograms. The dynamics of CFS by means of radionuclide cisternography were examined in 188 patients in whom some kind of hydrocephalus was suspected. This study included findings of anomalies associated with hydrocephalus in a number of cases, such as nasal liquorrhea, hygromas, leptomeningeal or porencephalic cysts. The investigation substantiates the value of radionuclide cisternography in the diagnosis of disturbances of CSF flow. The retrograde flow of radiopharmaceutical into the ventricular system (ventricular reflux) is an abnormal phenomenon indicating the presence of communicating hydrocephalus. (Auth.)

  3. Non-invasive measurement of stroke volume and left ventricular ejection fraction. Radionuclide cardiography compared with left ventricular cardioangiography

    DEFF Research Database (Denmark)

    Kelbaek, H; Svendsen, J H; Aldershvile, J

    1988-01-01

    The stroke volume (SV) was determined by first passage radionuclide cardiography and the left ventricular ejection fraction (LVEF) by multigated radionuclide cardiography in 20 patients with ischemic heart disease. The results were evaluated against those obtained by the invasive dye dilution or ...... are reliable. The discrepancy between the non-invasive and invasive LVEF values raises the question, whether LVEF is overestimated by cardioangiography or underestimated by radionuclide cardiography....

  4. Fins coloration of perch in relation to external activity concentration of radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Yegoreichenkov, E.; Pryakhin, E. [Urals Research Center for Radiation Medicine (Russian Federation); Rudolfsen, G. [Norwegian Radiation Protection Authority and University of Tromsoe (Norway)

    2014-07-01

    The Techa River is significantly polluted by radionuclides. This time the content of {sup 90}Sr varies from 5 Bq/l in water of lower Techa to 40 Bq/l in higher Techa, and the concentration of {sup 137}Cs fluctuates from background content to 0,5 Bq/l, and tritium from 100 Bq/l to 450 Bq/l. Miass River are not polluted in the same extent. The perch in these rivers are suitable for examine the potential effect of environmental perturbation on carotenoid based coloration. As vertebrates could not produce carotenoids themselves, and would use more carotenoids due to oxidative stress when exposed radiation, we hypothesized that fish caught in upper part of Techa River will be more pale than fish from lower part and the control river Miass. We used a cost effective method to estimate coloration by photographing the fins in standardized setting. The measuring of fish fins as performed under standardized condition by Adobe Photoshop software in color spaces CIE 1976 L*a*b* and sRGB IEC61966-2.1 was used. In sRGB color space the values of Red, Green, Blue channels were measured and an average wave length was calculated as a function of three elementary light streams of different intensity, appeared as reflection from a fin. In L*a*b color space the values of *a and *b channels shows the position of a color in a color space. To evaluate the red color of a perch fin the most usable channel is the *a channel which shows the position of the color on the red-green axis. Due to low sample size we pooled males and females in our analysis. We used three different station in the Techa: RT-1 in the higher Techa, RT-2 in the middle Techa, and RT-3 in lower Techa. As a control group was taken the fish from Miass river (RM station). Our results shows that perch from RT-3 (570.7 nm) significantly differ in coloration from the perch from RT-2 and RT-1 (p=0.00001 and p=0.0014 respectively, hereinafter used Kruskal-Wallis rank sum test with Nemenyi-Damico-Wolfe-Dunn test as post

  5. Distribution of natural radionuclides and uranium activity ratio in Gulf of Thailand sediments as base line data

    Energy Technology Data Exchange (ETDEWEB)

    Sahoo, S.K.; Hideki, A. [National Institute of Radiological Sciences (Japan); Kritsananuwat, R.; Fukushi, M. [Tokyo Metropolitan University (Japan); Chanyotha, S.; Pangza, K. [Chulalongkorn University (Thailand)

    2014-07-01

    This paper reports distribution of naturally occurring radionuclides and uranium activity ratio in marine sediments from selected coast, along the Gulf of Thailand to establish baseline data. Thailand has a plan to construct nuclear power plants (NPPs) as well as coal-fired thermal power plants to generate adequate and reliable electricity supply for rapid growth of industrialization. Therefore, it is important to focus not only on security and adequacy of power system but also on environmental protection and monitoring and risk assessment. To carry out environmental monitoring, baseline data plays a significant role. These data should be established and available before set up of mega projects that could impact the environment and health. Therefore, we have collected samples from five areas in the Gulf of Thailand, which are proposed as potential sites, to set up power plants by Thailand government. A total number of fifty-four marine sediment samples were collected. Gamma spectroscopy was used to determine the concentration of natural radionuclides e.g. {sup 226}Ra, {sup 228}Ac and {sup 40}K. Activity concentrations of {sup 226}Ra, {sup 228}Ac and {sup 40}K vary from 2.91-67.17 Bq/kg with an average of 26.64±14.57 Bq/kg, 4.42-109.17 Bq/kg with an average of 43.79±23.92 Bq/kg and 3.36-1004.56 Bq/kg with an average of 393.56±208.04 Bq/kg, respectively. The radiation hazard parameters including absorbed dose rate (D), annual effective dose equivalent (AEDE), radium equivalent activity (AGDE) and external hazard index (Hex) were calculated and compared with the international recommended values. We have noticed that sediments from two sites characterized by similar geological nature of landforms with a rocky coast have higher concentration of natural radionuclides. Concentration of uranium was determined using the inductively coupled plasma mass spectrometry (ICP-MS) and isotopic composition of {sup 234}U/{sup 238}U and {sup 235}U/{sup 238}U were determined using

  6. Calculations of the radiological impact of disposal of unit activity of selected radionuclides for use in waste management system studies

    International Nuclear Information System (INIS)

    Smith, G.M.

    1985-03-01

    The purpose of the work described is to provide estimates of the radiological impact following disposal of unit activity via each of several options, including shallow burial, engineered trench disposal, disposal in a geologic repository and disposal on the deep ocean bed. Results are presented for a range of important representative radionuclides. No single option is clearly the best from the radiological point of view. However, in conjunction with waste inventory data the results may be used to provide a preliminary view of the relative radiological merits of the various disposal options. (author)

  7. Activities of radionuclides in the Pacific coastal area of Fukushima since the TEPCO Fukushima Daiichi Nuclear Power Station accident - Activities of radionuclides in the coast area off Fukushima after TEPCO's Fukushima Daiichi Nuclear Power Station accident

    Energy Technology Data Exchange (ETDEWEB)

    Aono, Tatsuo; Fukuda, Miho; Yoshida, Satoshi [National Institute of Radiological Sciences, 263-8555, Chiba (Japan); Sohtome, Tadahiro; Mizuno, Takuji [Fukushima Prefecture Fisheries Experimental Station, 970-0316, Fukushima (Japan); Igarashi, Satoshi [Fukushima Prefecture Fisheries Experimental Station, 970-0316, Fukushima (Japan); Fukushima Prefecture Sea-Farming Association, 970-8044, Fukushima (Japan); Ito, Yukari; Kanda, Jota; Ishimaru, Takashi [Tokyo University of Marine Science and Technology, 108-0075, Tokyo (Japan)

    2014-07-01

    The accident of TEPCO's Fukushima Daiichi Nuclear Power Station (FDNPS) has caused the release of the huge quantities of radionuclide by the 2011 Great East Japan Earthquake and Tsunami, and then the serious problems gave rise to pollution in marine environment widely in the coast area off Fukushima. Monitoring of radioactivity in seawater and biota are important for understanding the dispersion of radionuclides and the effects of radioecology in the marine environment around the coast of Fukushima and the Pacific. The activities of Cs-134 and Cs-137 in seawater decreased exponentially and then were almost same levels before the accident around off Fukushima after about three years from the accident. However, the high activities of radio caesium (Cs) have been monitored in marine biota off Fukushima. The aims of the present study were to examine the temporal changes in radioactivity and to clarify the variation factor and the effect of radioecology in marine biota. Cs-134 and Cs-137, and Ag-110m, were released by this accident, determined in biota sample such as the plankton, fish and benthos, although it is well-known that molluscs and crustaceans concentrate silver in visceral parts. However, Sr-90 was not detected and the activities of plutonium were almost same level before this accident in the marine biota around off Fukushima. Concentration ratios of Cs (CR-Cs) in marine organism were from 2.6 E+1 in the muscle part of squid to 1.0 E+4 in the viscera of clam. The large differences in CR-Cs by the parts of marine organism were not observed. It is suggested that rapid change in the activities of radio Cs and silver in seawater, resuspension of particles from sediments and food chain effects led to high radionuclide activities in marine biota after this accident. CR-Cs in plankton was also calculated with the activities in seawater, which were collected around sampling area during this monitoring period. These resulting values ranged from 5.8 E+1 to 7.8 E+2

  8. Joint release rate estimation and measurement-by-measurement model correction for atmospheric radionuclide emission in nuclear accidents: An application to wind tunnel experiments.

    Science.gov (United States)

    Li, Xinpeng; Li, Hong; Liu, Yun; Xiong, Wei; Fang, Sheng

    2018-03-05

    The release rate of atmospheric radionuclide emissions is a critical factor in the emergency response to nuclear accidents. However, there are unavoidable biases in radionuclide transport models, leading to inaccurate estimates. In this study, a method that simultaneously corrects these biases and estimates the release rate is developed. Our approach provides a more complete measurement-by-measurement correction of the biases with a coefficient matrix that considers both deterministic and stochastic deviations. This matrix and the release rate are jointly solved by the alternating minimization algorithm. The proposed method is generic because it does not rely on specific features of transport models or scenarios. It is validated against wind tunnel experiments that simulate accidental releases in a heterogonous and densely built nuclear power plant site. The sensitivities to the position, number, and quality of measurements and extendibility of the method are also investigated. The results demonstrate that this method effectively corrects the model biases, and therefore outperforms Tikhonov's method in both release rate estimation and model prediction. The proposed approach is robust to uncertainties and extendible with various center estimators, thus providing a flexible framework for robust source inversion in real accidents, even if large uncertainties exist in multiple factors. Copyright © 2017 Elsevier B.V. All rights reserved.

  9. Surfactant-impregnated activated carbon for enhanced adsorptive removal of Ce(IV) radionuclides from aqueous solutions

    International Nuclear Information System (INIS)

    Mahmoud, Mamdoh R.; Sharaf El-deen, Gehan E.; Soliman, Mohamed A.

    2014-01-01

    Highlights: • Activated carbon (AC) was impregnated in this work with CTAB and NaLS surfactants. • The materials were evaluated as a sorbent for adsorption of Ce(IV) radionuclides. • Adsorption capacity of AC–NaLS for Ce(IV) is two-times the capacity of AC. • The kinetic and equilibrium data are fitted to pseudo-second-order and D–R models. • The results suggest the applicability of surface modified AC for waste treatment. - Abstract: The surfactants cetyltrimethylammonium bromide (CTAB) and sodium lauryl sulfate (NaLS) were utilized for modifying the activated carbon’s surface. The materials were characterized using BET–N 2 , scanning electron microscope, and Fourier transform infrared (FT-IR) spectroscopy. Adsorption of Ce(IV) radionuclides from aqueous solutions by activated carbon (AC) and surfactant-impregnated AC was studied. The obtained data showed that adsorption of Ce(IV) is strongly dependent on the solution pH and AC–NaLS exhibits the widest pH-range of maximum removal. The experimental adsorption capacity of AC–NaLS (0.069 mmol/g) for Ce(IV) is found to be nearly twice greater than that of AC (0.036 mmol/g). The adsorption kinetics of Ce(IV) onto AC and AC–NaLS were analyzed by linear and non-linear fittings to the pseudo-first-order, pseudo-second-order and Elovich kinetic models. Of these models, the pseudo-second-order is the best kinetic expression for describing the experimental data. The diffusion studies indicated that adsorption of Ce(IV) radionuclides on AC and AC–NaLS is controlled by film diffusion. Linear and non-linear fittings of the adsorption equilibrium data for Ce(IV) onto AC and AC–NaLS revealed that the Dubinin–Radushkevich (D–R) isotherm model fits the experimental data better than Freundlich and Langmuir models. The values of adsorption free energy, E, calculated from both linear and non-linear methods suggested that Ce(IV) radionuclides are physically adsorbed onto AC and AC–NaLS

  10. Release and transport of artificial radionuclides from nuclear weapons related activities in the Ob River, Siberia over the course of the nuclear age

    International Nuclear Information System (INIS)

    Sayles, F.L.; Kenna, T.C.; Livingston, H.D.

    1999-01-01

    Studies of sediment cores from lakes on the flood plain of the Ob River, Siberia have been used to develop a history of the release, transport, and deposition of artificial radionuclides related to the development and testing of nuclear weapons over the duration of the nuclear age (∼1950 to the present) in this major Arctic river system. The Ob is of particular importance in this regard as two of the former Soviet Union's major weapons production plants, Mayak and Tomsk-7, and the Semipalatinsk test site are located within the Ob drainage basin. Accidents and intentional releases of radionuclides at both plants have been substantial, raising the issue of transport throughout this extensive river system as well as delivery to the Arctic Ocean. Our studies have included determining sediment profiles of 239,240 Pu, 137 Cs, and the natural nuclide 210 Pb and its parent 226 Ra in a number of cores from the Ob delta, as well as analysis of 239 Pu, 240 Pu, and 237 Np. The latter provide sensitive measures of the presence of non-fallout materials derived from weapons production activities

  11. Consultative committee on ionizing radiation: Impact on radionuclide metrology

    International Nuclear Information System (INIS)

    Karam, L.R.; Ratel, G.

    2016-01-01

    In response to the CIPM MRA, and to improve radioactivity measurements in the face of advancing technologies, the CIPM's consultative committee on ionizing radiation developed a strategic approach to the realization and validation of measurement traceability for radionuclide metrology. As a consequence, measurement institutions throughout the world have devoted no small effort to establish radionuclide metrology capabilities, supported by active quality management systems and validated through prioritized participation in international comparisons, providing a varied stakeholder community with measurement confidence. - Highlights: • Influence of CIPM MRA on radionuclide metrology at laboratories around the world. • CCRI strategy: to be the “undisputed hub for ionizing radiation global metrology.” • CCRI Strategic Plan stresses importance of measurement confidence for stakeholder. • NMIs increasing role in radionuclide metrology by designating institutions (DIs). • NMIs and DIs establish quality systems; validate capabilities through comparisons.

  12. How do radionuclides behave in soils

    Energy Technology Data Exchange (ETDEWEB)

    Gerzabek, M

    1986-01-01

    The surface fallout of J, Cs, Ru, Sr and Pu after Chernobyl is given in a table. Another table indicates activities of J, Cs and Ru measured in the soil at different depths up to 200mm. Comments are given on the mobility and spread of radionuclides in the soil. (G.Q.).

  13. The influence of volatile anesthetics on alveolar epithelial permeability measured by noninvasive radionuclide lung scan

    International Nuclear Information System (INIS)

    Hung, Chih-Jen; Wu, Rick Sai-Chuen; Lin, Cheng-Chieh; Kao, Albert; Tsai, Jeffrey J.P.

    2003-01-01

    Many volatile anesthetics have long been thought to affect pulmonary functions including lung ventilation (LV) and alveolar epithelial permeability (AEP). The purpose of this study is to examine the influence of volatile anesthetics on LV and AEP by noninvasive radionuclide lung imaging of technetium-99m labeled diethylene triamine pentaacetic acid radioaerosol inhalation lung scan (DTPA lung scan). Twenty patients undergoing surgery and receiving volatile anesthesia with 1% halothane were enrolled as the study group 1. The other 20 patients undergoing surgery and receiving volatile anesthesia with 1.5% isoflurane were enrolled as the study group 2. At the same time, 20 patients undergoing surgery with intravenous anesthesia drugs were included as a control group. Before surgery, 1 hour after surgery, and 1 week after surgery, we investigated the 3 groups of patients with DTPA lung scan to evaluate LV and AEP by 99m Tc DTPA clearance halftime (T1/2). No significant change or abnormality of LV before surgery, 1 hour after surgery, or 1 week after surgery was found among the 3 groups of patients. In the control group, the 99m Tc DTPA clearance T1/2 was 63.5±16.4, 63.1±18.4, and 62.8±17.0 minutes, before surgery, 1 hour after surgery, and 1 week after surgery, respectively. In group 1, it was 65.9±9.3, 62.5±9.1, and 65.8±10.3 minutes, respectively. No significant change in AEP before surgery, 1 hour after surgery, or 1 week after surgery was found. However, in group 2, the 99m Tc DTPA clearance T1/2 was 65.5±13.2, 44.9±10.5, and 66.1±14.0 minutes, respectively. A significant transient change in AEP was found 1 hour after surgery, but it recovered 1 week after surgery. We conclude that volatile anesthesia is safe for LV and AEP, and only isoflurane can induce transient change of AEP. (author)

  14. Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics

    International Nuclear Information System (INIS)

    Hulse, R.A.

    1991-08-01

    Planning for storage or disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of that waste to estimate volumes, radionuclide activities, and waste forms. Data from existing literature, disposal records, and original research were used to estimate the characteristics and project volumes and radionuclide activities to the year 2035. GTCC LLW is categorized as: nuclear utilities waste, sealed sources waste, DOE-held potential GTCC LLW; and, other generator waste. It has been determined that the largest volume of those wastes, approximately 57%, is generated by nuclear power plants. The Other Generator waste category contributes approximately 10% of the total GTCC LLW volume projected to the year 2035. Waste held by the Department of Energy, which is potential GTCC LLW, accounts for nearly 33% of all waste projected to the year 2035; however, no disposal determination has been made for that waste. Sealed sources are less than 0.2% of the total projected volume of GTCC LLW

  15. Radionuclide carrier

    International Nuclear Information System (INIS)

    Hartman, F.A.; Kretschmar, H.C.; Tofe, A.J.

    1978-01-01

    A physiologically acceptable particulate radionuclide carrier is described. It comprises a modified anionic starch derivative with 0.1% to 1.5% by weight of a reducing agent and 1 to 20% by weight of anionic substituents

  16. Retention of activation and fission radionuclides by mallards from the Test Reactor Area radioactive leaching pond

    International Nuclear Information System (INIS)

    Halford, D.K.; Millard, J.B.; Schreckhise, R.G.

    1978-01-01

    Twenty semi-wild mallard ducks were banded, fitted with dorsal and ventral thermoluminescent dosimeter packets, and released on the Test Reactor Area radioactive leaching ponds. Ducks were live captured after 75 days and 145 days on the pond, placed in metabolic cages and whole-body counted periodically for 52 days. Ducks from each group were sacrificed immediately after capture, dissected, and muscle, feather, gut, and liver samples submitted for analyses. The remaining ducks were also sacrificed and dissected after the 52 day counting period. Concentrations of the 17 gamma emitting radionuclides detected at capture and after 52 days of physical and biological decay were compared. Highest mean radionuclide concentrations were found in feathers followed by gut, liver, and muscle. Effective and biological halflives of Zn-65, Cr-51, Cs-134, Cs-137, and Se-75 were determined and compared with data from previous studies. Samples are currently being analyzed for Pu-238, Pu-239-240, Am-241, Cm-242, Cm-244 and Sr-90. Further data analyses will be completed after data collection has terminated

  17. Radionuclide content of wastewater and solid waste from a low-level effluent treatment plant

    International Nuclear Information System (INIS)

    Muhamat Omar; Zalina Laili; Nik Marzukee Nik Ibrahim; Mat Bakar Mahusin

    2010-01-01

    A study on radioactivity levels of wastewater and solid waste from a Low-level Effluent Treatment Plant has been carried out. The measurement of radionuclide concentration was carried out using gamma spectrometry. Natural and anthropogenic radionuclides were detected in solid radioactive waste recovered from the treatment plant. The presence of radionuclides in waste water varies depending on activities carried out in laboratories and facilities connected to the plant. (author)

  18. EFFECTIVE SPECIFIC ACTIVITY OF NATURAL RADIONUCLIDES FOR THE NORM BELONGED TO 238U AND 232TH SERIES BEING IN THE STATE OF DISTURBED RADIOACTIVE EQUILIBRIUM

    Directory of Open Access Journals (Sweden)

    I. P. Stamat

    2008-01-01

    Full Text Available In the Sanitary Rules SR 2.6.1.1292-03 and SR 2.6.6.1169-02 classification of the industrial waste containing naturally occurring radioactive materials is adopted in accordance to the values of their effective specific activity Aeff. In a case of the disturbed equilibrium in 238U and 232Th series it is necessary to take into consideration actual contribution of the separate natural radionuclides of the mentioned series into the value of gamma dose rate of the waste. This will permit to avoid unjustified overestimating or understating of the waste category which prevents as unjustified expenditures on their treating so undertaking of the necessary measures providing radiation safety.

  19. In vivo detection, localization and measurement of radionuclides in man: a detection system for the localization and measurement of small amounts of photon emitters. Final report

    International Nuclear Information System (INIS)

    Laurer, G.R.

    1985-01-01

    A new detector has been devised which, by providing a significant increase in geometric counting efficiency, allows a concurrent reduction in the amount of radioactivity needed to produce an image of the deposition site(s) of radionuclides in humans and/or experimental animals. Consisting of four wedgeshaped NaI(Tl) crystals in a unique geometrical arrangement, the crystals themselves function as the collimator generally employed in radionuclide imaging applications. The four crystals, when coupled, become a 4-crystal unit detector; joined so their active faces form the silhouette of a pyramid. The outside, vertically oriented, rectangular faces of each crystal are placed back-to-back with those of adjoining detectors. Thus, small or large arrays of the 4-crystal unit detectors may be assembled. In practice, the array of detectors will be moved in fixed, discrete steps over the source of radiation to be imaged. As a result of its shape, each count obtained from each crystal at each counting position is different, relative to its position above the source. The array of counts obtained in this manner is the raw spatial information. They are used in a system of linear, simultaneous equations which relate the position of the detectors to the counts obtained at each position. The solution of these equations - utilizing the predetermined point-source-response (PSR) function of the crystals - yields a two-dimensional image of the deposition site of the radioactivity. 18 figs

  20. System for optimizing activation measurements

    International Nuclear Information System (INIS)

    Antonov, V.A.

    1993-01-01

    Optimization procedures make it possible to perform committed activation investigations, reduce the number of experiments, make them less laborious, and increase their productivity. Separate mathematical functions were investigated for given optimization conditions, and these enable numerical optimal parameter values to be established only in the particular cases of specific techniques and mathematical computer programs. In the known mathematical models insufficient account is taken of the variety and complexity of real nuclide mixtures, the influence of background radiation, and the wide diversity of activation measurement conditions, while numerical methods for solving the optimization problem fail to reveal the laws governing the variations of the activation parameters and their functional interdependences. An optimization method was proposed in which was mainly used to estimate the time intervals for activation measurements of a mononuclide, binary or ternary nuclide mixture. However, by forming a mathematical model of activation processes it becomes possible to extend the number of nuclides in the mixture and to take account of the influence of background radiation and the diversity of the measurement alternatives. The analytical expressions and nomograms obtained can be used to determine the number of measurements, their minimum errors, their sensitivities when estimating the quantity of the tracer nuclide, the permissible quantity of interfering nuclides, the permissible background radiation intensity, and the flux of activating radiation. In the worker described herein these investigations are generalized to include spectrally resolved detection of the activation effect in the presence of the tracer and the interfering nuclides. The analytical expressions are combined into a system from which the optimal activation parameters can be found under different given conditions

  1. Controls of internal contamination from gamma-emitting radionuclides performed whole-body counter measures on children's population from Bjelorussia, Russia and Ucraina

    International Nuclear Information System (INIS)

    Tarroni, G.; Battisti, P.; Castellani, C.M.; Formignani, M.; Rampa, E.; Ticconi, R.

    1994-12-01

    This report summarizes the results obtained in 9 measurement campaigns, performed at the ENEA (Italian Agency for New Technologies, Energy and the Environment) centres of Bologna and Roma-Casaccia from April 1991 to September 1992, for the assessment of internal contamination from gamma-emitting radionuclides. Homogeneous samples were selected for the controls, each one representing the children's population from given area. 15 areas were investigated and 24 examined; 20 of them were from Bjelorussia. 266 children, 124 male and 142 female subjects, were controlled. The instruments were intercalibrated according to the body size, from 20.25 kg to 81 kg. Body contamination only from 1 37 Cs and 1 34 Cs was detected. Evaluations were performed in order to test appropriate use of ICRP caesium biokynetic model for children aged 8 to 15 years. Statistical distribution of body activity data were carefully analyzed. It is demonstrated that the data are well fitted by lognormal distribution and a difference between sexes in terms of activity. A significant difference between sexes was found in terms of activity intake

  2. Efficiency calibration of a HPGe detector for [18F] FDG activity measurements

    International Nuclear Information System (INIS)

    Fragoso, Maria da Conceicao de Farias; Lacerda, Isabelle Viviane Batista de; Albuquerque, Antonio Morais de Sa

    2013-01-01

    The radionuclide 18 F, in the form of flurodeoxyglucose (FDG), is the most used radiopharmaceutical for Positron Emission Tomography (PET). Due to [ 18 F]FDG increasing demand, it is important to ensure high quality activity measurements in the nuclear medicine practice. Therefore, standardized reference sources are necessary to calibrate of 18 F measuring systems. Usually, the activity measurements are performed in re-entrant ionization chambers, also known as radionuclide calibrators. Among the existing alternatives for the standardization of radioactive sources, the method known as gamma spectrometry is widely used for short-lived radionuclides, since it is essential to minimize source preparation time. The purpose of this work was to perform the standardization of the [ 18 F]FDG solution by gamma spectrometry. In addition, the reference sources calibrated by this method can be used to calibrate and test the radionuclide calibrators from the Divisao de Producao de Radiofarmacos (DIPRA) of the Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE). Standard sources of 152 Eu, 137 Cs and 68 Ge were used for the efficiency calibration of the spectrometer system. As a result, the efficiency curve as a function of energy was determined in wide energy range from 122 to 1408 keV. Reference sources obtained by this method can be used in [ 18 F]FDG activity measurements comparison programs for PET services localized in the Brazilian Northeast region. (author)

  3. Applicability of portable spectrometer for activity measurement of contaminated water and soil samples

    International Nuclear Information System (INIS)

    Krishnan, Narayani; Rekha, A.K.; Anilkumar, S.; Sharma, D.N.

    2011-01-01

    The absolute activity measurement is often necessary to assess the impact of radioactivity contamination due to various incidents. Commercially available portable spectrometer cum dose rate meter is used for the identification of radionuclides involved and associated dose rates. In this paper the authors discusses the study carried out on the applicability of portable spectrometer for absolute radioactivity measurements in water and soil matrices. The portable spectrometer and the methodology developed for activity estimation has been used in many insitu applications. (author)

  4. Activation cross sections for the generation of long-lived radionuclides of importance in fusion reactor technology

    International Nuclear Information System (INIS)

    Wang Dahai

    1992-07-01

    Following the recommendations of the International Nuclear Data Committee (INDC), the IAEA Nuclear Data Section has established a Co-ordinated Research Programme (CRP) on activation cross sections for the generation of long-lived radionuclides of importance in concentrating on the cross sections for the reactions suggested by the 16th INDC meeting. The first Research Co-ordination Meeting of the CRP was held at the IAEA Headquarters, Vienna, Austria, from 11 to 12 November 1991. The main objectives of the meeting were to review the results under the CRP and the status of long-lived activation cross section data and to fix the future working programme for the CRP. The proceedings contain the progress reports of the CRP and 12 contributed papers presented at the meeting as well as the summary of the conclusions and recommendations of the meeting. Refs, figs and tabs

  5. An assessment of KW Basin radionuclide activity when opening SNF canisters

    International Nuclear Information System (INIS)

    Bergmann, D.W.; Mollerus, F.J.; Wray, J.L.

    1995-01-01

    N Reactor spent fuel is being stored in sealed canisters in the KW Basin. Some of the canisters contain damaged fuel elements. There is the potential for release of Cs 137, Kr 85, H3, and other fission products and transuranics (TRUs) when canisters are opened. Canister opening is required to select and transfer fuel elements to the 300 Area for examination as part of the Spent Nuclear Fuel (SNF) Characterization program. This report estimates the amount of radionuclides that can be released from Mark II spent nuclear fuel (SNF) canisters in KW Basin when canisters are opened for SNF fuel sampling as part of the SNF Characterization Program. The report also assesses the dose consequences of the releases and steps that can be taken to reduce the impacts of these releases

  6. 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

  7. A systematic investigation of PET Radionuclide Specific Activity on Miniaturization of Radiochemistry

    Energy Technology Data Exchange (ETDEWEB)

    Jeanne M Link, PhD

    2012-03-08

    The PET radionuclides, 18F and 11C consist of very high radiation to mass amounts and should be easily adapted to new technologies such as chip chemistry with nanofluidics. However, environmental contamination with nonradioactive fluorine, carbon and other trace contaminants add sufficient mass, micrograms to milligrams, to prevent adapting PET radiochemistry to the nanochip technologies. In addition, the large volumes of material required for beam irradiation make it necessary to also remove the 18F and 11C from their chemical matrices. These steps add contaminants. The work described in this report was a systematic investigation of sources of these contaminants and methods to reduce these contaminants and the reaction volumes for radiochemical synthesis. Several methods were found to lower the contaminants and matrices to within a factor of 2 to 100 of those needed to fully implement chip technology but further improvements are needed.

  8. TIMED: a computer program for calculating cumulated activity of a radionuclide in the organs of the human body at a given time, t, after deposition

    International Nuclear Information System (INIS)

    Watson, S.B.; Snyder, W.S.; Ford, M.R.

    1976-12-01

    TIMED is a computer program designed to calculate cumulated radioactivity in the various source organs at various times after radionuclide deposition. TIMED embodies a system of differential equations which describes activity transfer in the lungs, gastrointestinal tract, and other organs of the body. This system accounts for delay of transfer of activity between compartments of the body and radioactive daughters

  9. Statistical analysis of radiochemical measurements of TRU radionuclides in REDC waste

    International Nuclear Information System (INIS)

    Beauchamp, J.; Downing, D.; Chapman, J.; Fedorov, V.; Nguyen, L.; Parks, C.; Schultz, F.; Yong, L.

    1996-10-01

    This report summarizes results of the study on the isotopic ratios of transuranium elements in waste from the Radiochemical Engineering Development Center actinide-processing streams. The knowledge of the isotopic ratios when combined with results of nondestructive assays, in particular with results of Active-Passive Neutron Examination Assay and Gamma Active Segmented Passive Assay, may lead to significant increase in precision of the determination of TRU elements contained in ORNL generated waste streams

  10. Modification of the natural radionuclide distribution by some human activities in Canada

    International Nuclear Information System (INIS)

    Knight, G.B.; Makepeace, C.E.

    1980-01-01

    Examples are presented of three types of human activity that have resulted in elevated natural radiation levels. Investigations carried out by a Federal-Provincial Task Force are described. The distributions of grab sample measurements of radon and radon daughter concentrations are compared for the Bancroft area, Cobourg, Deloro, Elliot Lake, and Port Hope in Ontario, and Uranium City in Saskatchewan; it is concluded that the major point of difference between the communities that were investigated and the reference community of Cobourg is the departure from a symmetrical lognormal distribution at the higher concentrations

  11. Status of subseabed repository design concepts and radionuclide

    International Nuclear Information System (INIS)

    Brush, L.H.

    1980-01-01

    Various projects underway in support of the marine disposal of radioactive wastes are described. These include: geochemical studies on sediments; canister-related research and development activities; radionuclide transport studies through smectitic sediments; seawater-sediment interactions under near-field conditions; effects of a radiation field on high temperature, seawater-sediment interactions; sorption of fission products and actinides by deep-sea sediments under far-field (below 100 0 C) conditions; sorption experiments using column diffusion; development of a computer code, IONMIG, to model the migration of radionuclides through undisturbed deep-sea sediments; and planning for a field test of the laboratory measurements and computer models of radionuclide transport

  12. Device-dependent activity estimation and decay correction of radionuclide mixtures with application to Tc-94m PET studies

    International Nuclear Information System (INIS)

    Smith, Mark F.; Daube-Witherspoon, Margaret E.; Plascjak, Paul S.; Szajek, Lawrence P.; Carson, Richard E.; Everett, James R.; Green, Shielah L.; Territo, Paul R.; Balaban, Robert S.; Bacharach, Stephen L.; Eckelman, William C.

    2001-01-01

    Multi-instrument activity estimation and decay correction techniques were developed for radionuclide mixtures, motivated by the desire for accurate quantitation of Tc-94m positron emission tomography (PET) studies. Tc-94m and byproduct Tc isotopes were produced by proton irradiation of enriched Mo-94 and natural Mo targets. Mixture activities at the end of bombardment were determined with a calibrated high purity germanium detector. The activity fractions of the greatest mixture impurities relative to 100% for Tc-94m averaged 10.0% (Tc-94g) and 3.3% (Tc-93) for enriched targets and 10.1% (Tc-94g), 11.0% (Tc-95), 255.8% (Tc-96m), and 7.2% (Tc-99m) for natural targets. These radioisotopes have different half-lives (e.g., 52.5 min for Tc-94m, 293 min for Tc-94g), positron branching ratios (e.g., 0.72 for Tc-94m, 0.11 for Tc-94g) and gamma ray emissions for themselves and their short-lived, excited Mo daughters. This complicates estimation of injected activity with a dose calibrator, in vivo activity with PET and blood sample activity with a gamma counter. Decay correction using only the Tc-94m half-life overestimates activity and is inadequate. For this reason analytic formulas for activity estimation and decay correction of radionuclide mixtures were developed. Isotope-dependent sensitivity factors for a PET scanner, dose calibrator, and gamma counter were determined using theoretical sensitivity models and fits of experimental decay curves to sums of exponentials with fixed decay rates. For up to 8 h after the end of bombardment with activity from enriched and natural Mo targets, decay-corrected activities were within 3% of the mean for three PET studies of a uniform cylinder, within 3% of the mean for six dose calibrator decay studies, and within 6% of the mean for four gamma counter decay studies. Activity estimation and decay correction for Tc-94m mixtures enable routine use of Tc-94m in quantitative PET, as illustrated by application to a canine Tc-94m sestamibi

  13. Determination of the activity concentration levels of the artificial radionuclide137Cs in soil samples collected from Qatar using high-resolution gamma-ray spectrometry

    Science.gov (United States)

    Al-Sulaiti, Huda; Nasir, Tabassum; Al Mugren, K. S.; Alkhomashi, N.; Al-Dahan, N.; Al-Dosari, M.; Bradley, D. A.; Bukhari, S.; Regan, P. H.; Santawamaitre, T.; Malain, D.; Habib, A.; Al-Dosari, Hanan; Daar, Eman

    2016-09-01

    The goal of this study was to establish the first baseline measurements for radioactivity concentration of the artificial radionuclide 137Cs in soil samples collected from the Qatarian peninsula. The work focused on the determination of the activity concentrations levels of man-made radiation in 129 soil samples collected across the landscape of the State of Qatar. All the samples were collected before the most recent accident in Japan, “the 2011 Fukushima Dai-ichi nuclear power plant accident”. The activity concentrations have been measured via high-resolution gamma-ray spectrometry using a hyper-pure germanium detector situated in a low-background environment with a copper inner-plated passive lead shield. A radiological map showing the activity concentrations of 137Cs is presented in this work. The concentration wasfound to range from 0.21 to 15.41 Bq/kg. The highest activity concentration of 137Cs was observed in sample no. 26 in North of Qatar. The mean value was found to be around 2.15 ± 0.27 Bq/kg. These values lie within the expected range relative to the countries in the region. It is expected that this contamination is mainly due to the Chernobyl accident on 26 April 1986, but this conclusion cannot be confirmed because of the lack of data before this accident.

  14. Natural radionuclides concentration in underground mine materials

    Energy Technology Data Exchange (ETDEWEB)

    Santos, T.O.; Rocha, Z.; Taveira, N.F.; Takahashi, L.C.; Pineiro, M.M., E-mail: talitaolsantos@yahoo.com.br, E-mail: rochaz@cdtn.br, E-mail: mayarapinheiroduarte@gmail.com, E-mail: lauratakahashi@hotmail.com, E-mail: natyfontaveira@hotmail.com [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil); Borges, P.F.; Cruz, P.; Gouvea, V.A.; Siqueira, J.B., E-mail: vgouvea@cnen.gov.br, E-mail: flavia.borges@cnen.gov.br, E-mail: pcruz@cnen.gov.br, E-mail: jbsiquei@cnen.gov.br [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    Natural Radionuclides are present in earth's environment since its origin. The main radionuclides present are {sup 40}K, as well as, {sup 238}U and {sup 232}Th with their decay products. These radionuclides occur in minerals in different activity concentration associated with geological and geochemical conditions, appearing at different levels from point to point in the world. Underground mines may present a high natural background radiation which is due to the presence of these radiogenic heavy minerals. To address this concern, this work outlines on the characterization of the natural radionuclides presence in underground mines in Brazil which are located in many cases on higher radiation levels bed rocks. The radon concentration was measured by using E-PERM Electrets Ion Chamber, AlphaGUARD and CR-39 track etch detectors. The radon progeny was determined by using DOSEman detector. Radon concentration measurement in groundwater was performed by using RAD7 detector. The {sup 238}U and {sup 232}Th activity concentration in ore and soil samples were determined by using Neutron Activation Analysis using TRIGA MARK I IPR-R1 Reactor. Gamma spectrometry was used to determine {sup 226}Ra, {sup 228}Ra and {sup 40}K activity concentrations. The results show that the natural radioactivity varies considerably from mine to mine and that there are not risks of radiological damage for exposed workers in these cases. Based on these data, recommendations for Brazilian regulatory standards are presented. (author)

  15. Natural radionuclides concentration in underground mine materials

    International Nuclear Information System (INIS)

    Santos, T.O.; Rocha, Z.; Taveira, N.F.; Takahashi, L.C.; Pineiro, M.M.; Borges, P.F.; Cruz, P.; Gouvea, V.A.; Siqueira, J.B.

    2017-01-01

    Natural Radionuclides are present in earth's environment since its origin. The main radionuclides present are 40 K, as well as, 238 U and 232 Th with their decay products. These radionuclides occur in minerals in different activity concentration associated with geological and geochemical conditions, appearing at different levels from point to point in the world. Underground mines may present a high natural background radiation which is due to the presence of these radiogenic heavy minerals. To address this concern, this work outlines on the characterization of the natural radionuclides presence in underground mines in Brazil which are located in many cases on higher radiation levels bed rocks. The radon concentration was measured by using E-PERM Electrets Ion Chamber, AlphaGUARD and CR-39 track etch detectors. The radon progeny was determined by using DOSEman detector. Radon concentration measurement in groundwater was performed by using RAD7 detector. The 238 U and 232 Th activity concentration in ore and soil samples were determined by using Neutron Activation Analysis using TRIGA MARK I IPR-R1 Reactor. Gamma spectrometry was used to determine 226 Ra, 228 Ra and 40 K activity concentrations. The results show that the natural radioactivity varies considerably from mine to mine and that there are not risks of radiological damage for exposed workers in these cases. Based on these data, recommendations for Brazilian regulatory standards are presented. (author)

  16. Intercomparison of 131I activity measurements in nuclear medicine

    International Nuclear Information System (INIS)

    Kim, G. Y.; Yang, H. K.; Lim, C. I.; Lee, H. K.; Jeong, H. K.

    2004-01-01

    Activity measurements in nuclear medicine using a dose calibrator have been performed for several decades and their reliability has varied. To minimise the radiation dose to patients with radionuclides, it is necessary to ensure that the sample administered is accurately assayed. Recognizing the importance of intercomparison in nuclear medicine and the need to make access to activity standards traceable to the international measurement system, the KFDA, as a national secondary standard dosimetry laboratory (SSDL), started an intercomparison program in 2002. This program was initiated by survey to all nuclear medicine centres regarding general information about their dose calibrators, radioisotopes etc. 71 nuclear medicine centres (79 dose calibrators) participated in the intercomparison program with 131 I isotope. To assess the accuracy of clinical measurements of the activity of 131 I solutions and to determine the reason for the disagreement, an intercomparison was conducted using 4 ml aliquots in 10 ml P6 vial with a total activity in the region of 10 -20 MBq. The reference time of decay for all solutions was 0:00 on 25 September 2002. The half-life used was 8.04 days. For the evaluation of solution in KFDA, a sealed, high pressure and re-entrant ionisation chamber, NPL-CRC radionuclide calibrators were used. The verification of our calibration quality was by means of a comparison with the Korea Primary Standard Laboratory (KRISS). The activity ratio of KFDA to KRISS for the 131 I solutions is 1.011. The difference between the value quoted by the clinic, A hospital and the value obtained by the KFDA, A KFDA , is expressed as a percent deviation, i.e. DEV(%) 100x(A hospital -A KFDA )/A KFDA . From the data obtained it was found that 61% of the calibrators showed a deviation within +/-5%; 23% had a deviation in the range 5% 131 I solution activity measurements, using dose calibrators in Koreas, and also to provide the participants with a traceable standard to

  17. A comparison of measured radionuclide release rates from Three Mile Island Unit-2 core debris for different oxygen chemical potentials

    International Nuclear Information System (INIS)

    Baston, V.F.; Hofstetter, K.J.; Ryan, R.F.

    1987-01-01

    Chemical and radiochemical analyses of reactor coolant samples taken during defueling of the Three Mile Island Unit-2 (TMI-2) reactor provide relevant data to assist in understanding the solution chemistry of the radionuclides retained within the TMI-2 reactor coolant system. Hydrogen peroxide was added to various plant systems to provide disinfection for microbial contamination and has provided the opportunity to observe radionuclide release under different oxygen chemical potentials. A comparison of the radionuclide release rates with and without hydrogen peroxide has been made for these separate but related cases, i.e., the fuel transfer canal and connecting spent-fuel pool A with the TMI-2 reactor plenum in the fuel transfer canal, core debris grab sample laboratory experiments, and the reactor vessel fluid and associated core debris. Correlation and comparison of these data indicate a physical parameter dependence (surface-to-volume ratio) affecting all radionuclide release; however, selected radionuclides also demonstrate a chemical dependence release under the different oxygen chemical potentials. Chemical and radiochemical analyses of reactor coolant samples taken during defueling of the Three Mile Island Unit-2 (TMI-2) reactor provide relevant data to assist in understanding the solution chemistry of the radionuclides retained within the TMI-2 reactor coolant system

  18. Radionuclide generators

    International Nuclear Information System (INIS)

    Lambrecht, R.M.

    1983-01-01

    The status of radionuclide generators for chemical research and applications related to the life sciences and biomedical research are reviewed. Emphasis is placed upon convenient, efficient and rapid separation of short-lived daughter radionuclides in a chemical form suitable for use without further chemical manipulation. The focus is on the production of the parent, the radiochemistry associated with processing the parent and daughter, the selection and the characteristic separation methods, and yields. Quality control considerations are briefly noted. The scope of this review includes selected references to applications of radionuclide generators in radiopharmaceutical chemistry, and the life sciences, particularly in diagnostic and therapeutic medicine. The 99 Mo-sup(99m)Tc generator was excluded. 202 references are cited. (orig.)

  19. The need for standardisation in the analysis, sampling and measurement of deposited radionuclides

    International Nuclear Information System (INIS)

    Tsaturov, Y.S.; De-Cort, M.; Dubois, G.; Izrael, Yu.A.; Stukin, E.D.; Fridman, D.F.; Tabachnyi, L.Ya.; Matveenko, I.I.; Guermenchuk, M.G.; Sitak, V.A.

    1996-01-01

    Following the Chernobyl accident in 1986, diverse sampling and measurement methods for radioactivity deposition have been applied by the various European institutes. When compiling these datasets together on the same data platform, in view of preparing the atlas on cesium contamination in Europe, data quality analysis has shown a lack of harmonisation between these various methods. Because of the necessity to dispose of compatible and representative measurements for further analysis, e.g. time series analysis, and the need for better Standardization methods in the event of a future accident with large transboundary release, several suggestions are made of how such harmonization might be achieved. Also in view of taking appropriate decisions in case of accidental releases by gaining experience in data Standardization, the variety of the sampling and measurement methods of radioactivity currently used are briefly summarized and the results intercompared. In order to improve the quality of datasets, GIS, amongst other methods, can be applied as a useful tool to highlight the lack of harmonisation between the various sampling methodologies by indicating the data uncertainty

  20. New way of demonstrating the competence of a laboratory measuring radionuclides - The international draft standard ISO/IEC DIS 17025

    International Nuclear Information System (INIS)

    Palsson, S.E.

    1999-01-01

    In recent years there has been increased interest, and even need, amongst laboratories performing measurements of radionuclides to obtain accreditation. It has been discussed how this could be achieved with maximum flexibility for the laboratories and with minimum effort. The issuing of a new draft international standard, the ISO/IEC DIS 17025, created speculations whether it could offer a new and better way for laboratories to obtain accreditation. It was decided within the NKS/BOK-1.1 project to explore possible options for obtaining accreditation and what possibilities the new standard could offer. The benefits of computerised document control systems were also explored. The results were reported at the 12th Annual Meeting of the Nordic Society for Radiation Protection, 23-27 August 1999. Since then the final version of the standard has been published. The voting will continue until November 16th 1999 and is not clear at present whether the standard will be accepted or not. The original version of this paper was updated to reflect these recent developments. (au)

  1. Activation cross sections for the generation of long-lived radionuclides of importance in fusion reactor technology

    International Nuclear Information System (INIS)

    Pashchenko, A.B.

    1993-11-01

    The present report contains the Summary of the Second IAEA Research Co-ordination Meeting (RCM) on ''Activation Cross Sections for the Generation of Long-Lived Radionuclides of Importance in Fusion Reactor Technology'' which was hosted by TSI Research at Del Mar near San Diego and held from 29 to 30 April 1993. This RCM was organized by the IAEA Nuclear Data Section (NDS), with the cooperation and assistance of local organizers from TSI Research and Westinghouse Hanford Company. Tables of 14 MeV cross sections and cross sections below 14 MeV are included. The papers prepared and presented by the participants at the meeting has been published as separate report INDC(NDS)-286/L. 3 tabs

  2. Dynamic, diagnostic, and pharmacological radionuclide studies of the esophagus in achalasia: correlation with manometric measurements

    Energy Technology Data Exchange (ETDEWEB)

    Rozen, P.; Gelfond, M.; Zaltzman, S.; Baron, J.; Gilat, T.

    1982-08-01

    The esophagus was evaluated in 15 patients with achalasia by continuous gamma camera imaging following ingestion of a semi-solid meal labeled with /sup 99//sup m/Tc. The images were displayed and recorded on a simple computerized data processing/display system. Subsequent cine' mode images of esophagela emptying demonstrated abnormalities of the body of the esophagus not reflected by the manometric examination. Computer-generated time-activity curves representing specific regions of interest were better than manometry in evaluating the results of myotomy, dilatation, and drug therapy. Isosorbide dinitrate significantly improved esophageal emptying.

  3. Gamma spectrometric validation of measurements test of radionuclides in food matrices; Validacao do ensaio de medidas por espectrometria gama de radionuclideos em matrizes de alimentos

    Energy Technology Data Exchange (ETDEWEB)

    Rosa, Mychelle M.L.; Custodio, Luis G.; Bonifacio, Rodrigo L.; Taddei, Maria Helena T., E-mail: mychelle@cnen.gov.br, E-mail: Igcustodio@hotmail.com, E-mail: rodrigo@cnen.gov.br, E-mail: mhtaddei@cnen.gov [Comissao Nacional de Energia Nuclear (LAPOC/CNEN-MG), de Pocos de Caldas, MG (Brazil). Laboratorio de Pocos de Caldas

    2013-10-01

    In a testing laboratory the quality system encompasses a set of activities planned and systematic, which ensure the traceability process of an analysis, which is based on the standards NBR ISO/TEC 17025. With the need for analysis of radionuclides in food products to meet the requirements of import and export, accreditation of testing on this standard becomes increasingly necessary. The Gamma Spectrometry is a technique used for direct determination of radionuclides in different matrices, among them the food, being possible the simultaneous determination of different radionuclides in the same sample without the need for a chemical separation. In the process of Accreditation the methodology validation is an important step that includes testing accuracy, traceability, linearity and recovery. This paper describes the procedures used to validate the assay for determining radionuclides using gamma spectrometry in food. These procedures were performed through analysis of a certificated reference material by the International Atomic Energy Agency (IAEA Soil 327), analysis of samples of milk powder prepared from the doping with certified liquid standards also by the results obtained in the participation of tests of proficiency in analysis of environmental samples. (author)

  4. In vivo measurements of bone-seeking radionuclides. Annual report, December 1, 1982-November 30, 1983

    International Nuclear Information System (INIS)

    Cohen, N.

    1983-01-01

    This report summarizes results obtained in seven areas. Five subjects with well defined Am-241 body burdens have been measured using NaI-CsI(T1) detectors surrounding the head or positioned over the anterior knee surfaces. The observed ratio of net count-rate at the skull to net count-rate at the anterior knee surfaces was found to vary with values ranging from 1.16 to 2.45. Previously developed calibration values for men have been determined to be inadequate for application to female workers due to the variability in chest wall thickness and different photon attenuation characteristics of breast tissue in women. The relative count-rates for each individual among the counting geometries reflected the attenuation of the Nb-92m x-rays in the overlying tissue. The measurement performed with a single phoswich detector positioned centrally over the sternum surprisingly gave the highest count-rate for two out of the four subjects. It is expected that the net counts/x-ray emitted for each individual, when plotted as a function of overlying absorber thickness, will produce a series of single exponential curves which can be used to predict the absolute calibration value for Nb-92m in the lungs. Additional studies describing the time-related fate and distribution in the body of radon and radon daughters present as a result of drinking this well water are currently in progress. There appears to be a possibility of obtaining a significantly increased and variable whole body count-rate as related to a function of the quantity of water consumed and the time of in vivo measurement. Subjects who were treated therapeutically with radon seeds 25 to 34 years ago were observed in our whole body counting facility using NaI-CsI(T1) detectors. The radiation dose due to the characteristic Pu x-ray, the bremsstrahlung continuum and any beta radiation penetrating the gold sheath, is being determined

  5. Radionuclide - Soil Organic Matter Interactions

    DEFF Research Database (Denmark)

    Carlsen, Lars

    1985-01-01

    Interactions between soil organic matter, i.e. humic and fulvic acids, and radionuclides of primary interest to shallow land burial of low activity solid waste have been reviewed and to some extent studied experimentally. The radionuclides considered in the present study comprise cesium, strontium...

  6. Radionuclides release from re-irradiated fuel under high temperature and pressure conditions. Gamma-ray measurements of VEGA-5 test

    Energy Technology Data Exchange (ETDEWEB)

    Hidaka, Akihide; Kudo, Tamotsu; Nakamura, Takehiko; Kanazawa, Toru; Kiuchi, Toshio; Uetsuka, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-03-01

    The VEGA (Verification Experiments of radionuclides Gas/Aerosol release) program is being performed at JAERI to clarify mechanisms of radionuclides release from irradiated fuel during severe accidents and to improve source term predictability. The fifth VEGA-5 test was conducted in January 2002 to confirm the reproducibility of decrease in cesium release under elevated pressure that was observed in the VEGA-2 test and to investigate the release behavior of short-life radionuclides. The PWR fuel of 47 GWd/tU after about 8.2 years of cooling was re-irradiated at Nuclear Safety Research Reactor (NSRR) for 8 hours before the heat-up test. After that, the two pellets of 10.9 g without cladding were heated up to about 2,900 K at 1.0 MPa under the inert He condition. The experiment reconfirmed the decrease in cesium release rate under the elevated pressure. The release data on short-life radionuclides such as Ru-103, Ba-140 and Xe-133 that have never been observed in the previous VEGA tests without re-irradiation was obtained using the {gamma} ray measurement. (author)

  7. Significance of left ventricular volume measurement after heart transplantation using radionuclide techniques

    International Nuclear Information System (INIS)

    Novitzky, D.; Cooper, D.; Boniaszczuk, J.

    1985-01-01

    Multigated equilibrium blood pool scanning using Technetium 99m labeled red blood cells was used to measure left ventricular volumes in three heterotopic and one orthotopic heart transplant recipient(s). Simultaneously, an endomyocardial biopsy was performed and the degree of acute rejection was assessed by a histological scoring system. The scores were correlated to changes in ejection fraction and heart rate. Technetium 99m scanning data were pooled according to the endomyocardial biopsy score: no rejection; mild rejection; moderate rejection, and severe rejection. In each group, the median of the left ventricular volume parameters was calculated and correlated with the endomyocardial biopsy score, using a non-parametric one-way analysis of variance. A decrease in stroke volume correlated best with the endomyocardial biopsy score during acute rejection. A decrease in end-diastolic left ventricular volumes did not correlate as well. Changes in the end-systolic left ventricular volumes were not statistically significant, but using a simple correlation between end-systolic left ventricular volumes and endomyocardial biopsy the correlation reached significance. Changes in left ventricular volumes measured by Technetium 99m scanning may be useful to confirm the presence or absence of acute rejection in patients with heart grafts

  8. Measurements of natural and artificial radionuclides in food samples and water for human consumption in Austria for the calculation of the ingestion dose

    International Nuclear Information System (INIS)

    Claudia Landstetter; Michael Zapletal; Merita Sinojmeri; Christian Katzlberger

    2013-01-01

    A new report on food habits of the Austrian population in the year 2006/2007 was released in 2008. Mixed diets and foodstuffs are measured within a monitoring program according to the Austrian radiation protection law, food law, and the Commission Recommendation 2000/473/Euratom on the application of Article 36 of the Euratom Treaty concerning the monitoring of the levels of radioactivity in the environment for the purpose of assessing the exposure of the population as a whole. In addition, drinking and mineral water samples are measured for natural and artificial radionuclides. The ingestion dose for the Austrian population is recalculated based on the results of these measurements, literature data, and the data of the new report on food habits. In general, the major part of the ingestion dose is caused by natural radionuclides, especially 40 K. (author)

  9. Environmental methodology. Sampling and preparing fresh water organisms. Measuring of emitting radionuclides

    International Nuclear Information System (INIS)

    Foulquier, Luc; Philippot, J.C.; Baudin-Jaulent, Yvette.

    1982-05-01

    This paper provides some initial responses to questions asked by users of radioecological documents. By using aquatic plants and fish drawn ''in situ'' the authors' results often reveal very low activity levels; they make a point of knowing how to deal with such levels, since the fundamental objective is to interpret transfer mechanisms. The establishment of the environmental level of radioactivity requires that the write-ups produced demonstrate the use of reproducible methods, and contain results for which the extent of reliability is clearly specified. Aquatic plants and fish are, among all fresh water organisms, the most interesting links in the study of artificial and natural radioactivity. By systematically using concrete examples, this work reaffirms the precautions that should be taken in a site study. Once the objective is clearly defined, the properties to give to the sampling can be specified [fr

  10. Investigation of the fluctuation range of activity concentrations of natural radionuclides in surface air

    International Nuclear Information System (INIS)

    Winkler, R.; Hoetzl, H.

    1985-01-01

    Daily and seasonal concentration fluctuations of short-lived Rn fission products observed and the seasonal and long-term concentration fluctuations of Pb-210, Po-210, Ra-226, Ra-228, K-40 and Be-7 are discussed; the frequency distributions of the concentration values are illustrated. For a period of several years, the following mean values of activity concentrations were found (μBq/m 3 ): Pb-210: 600 Ra-226: 1.3 K-40: 13, Po-210: 33 Ra-228: 0.5 Be-7: 3700. In accordance with the origin from the soil, there is a significant correlation between the respective activity concentration and air-borne dust concentration for Ra-226, Ra-228, and K-40. The investigation revealed a most significant correlation between the Pb-210 concentration and the stagnancy index, the latter being a measure for the degree of blending of the surface layer of air. The resuspension factors found for Ra-226 and Pb-210 are discussed. (orig./HP) [de

  11. Radionuclide measuring systems and improved methods of evaluation for the measurement of wear in stationary and mobile systems

    International Nuclear Information System (INIS)

    Lausch, W.

    1976-01-01

    A newly developped flow through measuring unit makes it possible to perform continuous wear measurements on stationary and mobile systems. It was specifically designed for measurements on engine components of passenger cars. For tests of long duration an oil sampling technique was developed. Fully automated measurements are achieved with a sampling device suitable for both stationary and mobile systems. For systems with oil consumption a mathematical model provides for the necessary connection of the loss of wear particles through oil consumption. In certain cases an empirical graphical method can achieve nearly the same results. (orig.) [de

  12. Field surveying of radionuclide contamination in forests

    International Nuclear Information System (INIS)

    Turunen, J.; Rantavaara, A.; Ammann, M.

    2009-01-01

    Field measurements of radionuclides after an accidental contamination of forests assume the capacity for identification of a number of nuclides in varying source geometries. The continuous redistribution of radionuclides in forests through natural processes implies a decrease of prevailing surface contamination of trees and an increase in activity density on the ground. Portable gamma spectrometers have long been based on Na(I) detectors which, due to their low energy resolution, are not the tool for analysis of contamination from accidental releases of fission and activation products in the first days or weeks after a deposition. Data of airborne radionuclides from the Chernobyl accident in April 1986 were used for demonstration of initial and later distribution of radionuclides as sources of air Kerma in forests. Forest model (FDMF, PV. 6.0) of the RODOS system was used for the assessment of time-dependent Kerma rate from different forest compartments. The results show the fast reduction of activities of short-lived nuclides and their contributions to the Kerma rate in the first weeks and months. The results also give an estimate for the time needed until a gamma spectrometer with a low energy resolution would give useful information about long-lived radioactivity on the forest floor. An example is given on a portable high resolution semiconductor spectrometer that has suitable characteristics for field surveying also during occurrence of a great number of radionuclides contributing to the gamma spectrum. The needs for further research of a recently deposited radionuclide contamination on forest vegetation and soil, and the efforts for improvement of portable radiation meters and their use in management planning and radioecological research on contaminated forests are discussed. (au)

  13. Discussion on monitoring items of radionuclides in influents from nuclear power plants

    International Nuclear Information System (INIS)

    Zhang Yanxia; Li Jin; Liu Jiacheng; Han Shanbiao; Yu Zhengwei

    2014-01-01

    For the radionuclide monitoring items of effluents from nuclear power plant, this paper makes some comparisons and analysis from three aspects of the international atomic energy general requirements, the routine radionuclide measurement items of China's nuclear power plant and effluents low level radionuclide experimental research results. Finally, it summarizes the necessary items and recommended items of the radionuclide monitoring of effluents from nuclear power plant, which can provide references for the radioactivity monitoring activities of nuclear power plant effluent and the supervisions of regulatory departments. (authors)

  14. Study of radionuclide and element characterization of Angola marine sediment using low background gamma spectrometry and instrumental neutron activation analysis techniques

    International Nuclear Information System (INIS)

    Teixeira, M.C.P.; Vuong Huu Tan; Truong Y; Ho Manh Dung; Le Nhu Sieu; Cao Dong Vu; Nguyen Thanh Binh

    2007-01-01

    The concentrations of radionuclides and chemical elements in Angola marine sediment samples were determined by using low background gamma (LBG) spectrometry and instrumental neutron activation analysis (INAA). The combination of radionuclide and elemental concentration values yielded synergy in the validation of analytical data and identification of sediment sources modeled by multivariate factor analysis. Varimax rotation factor analysis based on the elemental concentrations revealed five sources contributed to the sediment composition, i.e. crustal, sea-salt, industrial, coal-related and Se-related sources. (author)

  15. Comparative study between in Vivo and Vitro radionuclide technique in measurement of Glomerular filtration rate

    International Nuclear Information System (INIS)

    Ziada, G.; Moustafa, H.; Elhaddad, SH.; Taalab, KH.

    1995-01-01

    Fifty patients were referred to nuclear medicine department in NEMROCK center for measurement of glomerular filtration rate (GFR). The group included 34 males and 16 females with a mean age of 38.3 ± 10.7 years. Estimation of GFR was done using 111-185 mBq of 99m Tc-DTPA with data collected on 128 x 128 matrix on IDAC computer every 15 seconds with calculation of renal uptake and GFR applying Gates method. 72 hours, a dose 3.7 mBq of 51 Cr-EDTA with 2 blood samples taken at 120, 240 minutes with estimation of plasma clearance using Russel et al., method (1985). The mean clearance of 51 Cr-EDTA was 79.61±22.4 ml/min compared to 84.34±26.3 ml/min. Using direct scintigraphic method with positive correlation using regression analysis (r=0.96). Also, both 51 Cr-EDTA and in vivo 99m Tc-DTPA were positively correlated with creatinine clearance (r=0.87 and 0.91 respectively). A modified regression formulas was used for correction of the results of 99m Tc-DTPA values GFR ( 99m Tc-DTPA) x 0.81 + 11 ± 6.4 ml/min. 4 figs., 1 tab

  16. Measurements of low-level anthropogenic radionuclides from soils around Maralinga

    Directory of Open Access Journals (Sweden)

    Tims Stephen G.

    2013-12-01

    Full Text Available The isotopes 239Pu and 240Pu are present in surface soils as a result of global fallout from nuclear weapons tests carried out in the 1950’s and 1960’s. These isotopes constitute artificial tracers of recent soil erosion and sediment movement. In practice the high throughput capabilities and high sensitivity of the AMS technique makes the study of Australia’s geographically large areas viable using Pu isotopes. As part of its weapons development program the United Kingdom carried out a series of atmospheric and surface nuclear weapons tests at Maralinga, South Australia in 1956 and 1957. The contribution from the Maralinga tests to the Pu isotopic abundances present in the region around Maralinga is largely unknown. In global fallout, for example, the 240Pu/239Pu ratio is typically in the range 0.17 - 0.19, but the influence of the regional tests could lead to values outside this range. This would impact on the assessment techniques used in the soil and sediment tracer studies. We report recent measurements on soil samples collected from across the Maralinga Test site.

  17. Comparative study between in Vivo and Vitro radionuclide technique in measurement of Glomerular filtration rate

    Energy Technology Data Exchange (ETDEWEB)

    Ziada, G; Moustafa, H; Elhaddad, SH; Taalab, KH [Nuclear medicine department, Faculty of medicine, Cairo university, Cairo, (Egypt)

    1995-10-01

    Fifty patients were referred to nuclear medicine department in NEMROCK center for measurement of glomerular filtration rate (GFR). The group included 34 males and 16 females with a mean age of 38.3 {+-} 10.7 years. Estimation of GFR was done using 111-185 mBq of {sup 99m} Tc-DTPA with data collected on 128 x 128 matrix on IDAC computer every 15 seconds with calculation of renal uptake and GFR applying Gates method. 72 hours, a dose 3.7 mBq of {sup 51} Cr-EDTA with 2 blood samples taken at 120, 240 minutes with estimation of plasma clearance using Russel et al., method (1985). The mean clearance of {sup 51} Cr-EDTA was 79.61{+-}22.4 ml/min compared to 84.34{+-}26.3 ml/min. Using direct scintigraphic method with positive correlation using regression analysis (r=0.96). Also, both {sup 51} Cr-EDTA and in vivo {sup 99m} Tc-DTPA were positively correlated with creatinine clearance (r=0.87 and 0.91 respectively). A modified regression formulas was used for correction of the results of {sup 99m} Tc-DTPA values GFR ({sup 99m}Tc-DTPA) x 0.81 + 11 {+-} 6.4 ml/min. 4 figs., 1 tab.

  18. Radionuclide generators

    International Nuclear Information System (INIS)

    Lambrecht, R.M.; Wollongong Univ.; Tomiyoshi, K.; Sekine, T.

    1997-01-01

    The present status and future directions of research and development on radionuclide generator technology are reported. The recent interest to develop double-neutron capture reactions for production of in vivo generators; neutron rich nuclides for radio-immunotherapeutic pharmaceuticals: and advances with ultra-short lived generators is highlighted. Emphasis is focused on: production of the parent radionuclide; the selection and the evaluation of support materials and eluents with respect to the resultant radiochemical yield of the daughter, and the breakthrough of the radionuclide parent: and, the uses of radionuclide generators in radiopharmaceutical chemistry, biomedical and industrial applications. The 62 Zn → 62 Cu, 66 Ni → 66 Cu, 103m Rh → 103 Rh, 188 W → 188 Re and the 225 Ac → 221 Fr → 213 Bi generators are predicted to be emphasized for future development. Coverage of the 99 Mo → 99m Tc generator was excluded, as it the subject of another review. The literature search ended June, 1996. (orig.)

  19. Radionuclide scanning

    International Nuclear Information System (INIS)

    Shapiro, B.

    1986-01-01

    Radionuclide scanning is the production of images of normal and diseased tissues and organs by means of the gamma-ray emissions from radiopharmaceutical agents having specific distributions in the body. The gamma rays are detected at the body surface by a variety of instruments that convert the invisible rays into visible patterns representing the distribution of the radionuclide in the body. The patterns, or images, obtained can be interpreted to provide or to aid diagnoses, to follow the course of disease, and to monitor the management of various illnesses. Scanning is a sensitive technique, but its specificity may be low when interpreted alone. To be used most successfully, radionuclide scanning must be interpreted in conjunction with other techniques, such as bone radiographs with bone scans, chest radiographs with lung scans, and ultrasonic studies with thyroid scans. Interpretation is also enhanced by providing pertinent clinical information because the distribution of radiopharmaceutical agents can be altered by drugs and by various procedures besides physiologic and pathologic conditions. Discussion of the patient with the radionuclide scanning specialist prior to the study and review of the results with that specialist after the study are beneficial

  20. Effect of recombinant tissue-type plasminogen activator on acute myocardial infarction; Limitation of infarct size and preservation of left ventricular function evaluated by radionuclide methods

    Energy Technology Data Exchange (ETDEWEB)

    Fukuyama, Takaya; Inou, Tetsuji; Ashihara, Toshiaki; Ogata, Ikuo; Nabeyama, Shouzou; Yamada, Akira; Murakami, Satoshi; Kodama, Mayuko; Matsui, Kanji (Matsuyama Red Cross Hospital, Ehime (Japan))

    1989-12-01

    Radionuclide studies were performed in 18 patients with acute myocardial infarction receiving i.v. injection of recombinant tissue-type plasminogen activator (rt-PA) within 12 hr after an attack. Thallium-201 single photon emission computed tomography revealed that infarct size decreased by 42% in the rt-PA treated group, as compared with 25% in the control group. Left ventricular ejection fraction, as found on first-pass radionuclide angiography with Tc-99m PYP, was significantly higher in the rt-PA treated group than the control group (49% vs 38%). Radionuclide imagings were helpful in confirming myocardial salvage after rt-PA intravenous therapy. It was also considered necessary to perform rt-PA therapy as early as possible after an acute myocardial attack. (N.K.).

  1. Measurement of long-lived radionuclides in surface soil around F1NPP accident site by Accelerator Mass Spectrometry

    Energy Technology Data Exchange (ETDEWEB)

    Miyake, Yasuto; Matsuzaki, Hiroyuki [Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo (Japan); Sasa, Kimikazu; Takahashi, Tsutomu [AMS Group, Tandem Accelerator Complex, Research Facility Center for Science and Technology, University of Tsukuba, Tsukuba, Ibaraki 305-8577 (Japan)

    2015-10-15

    In March 2011, vast amounts of radionuclides were released into the environment due to the Fukushima Daiichi Nuclear Power Plant (F1NPP) accident. However, very little work has been done concerning accident-derived long-lived nuclides such as {sup 129}I (T{sub 1/2} = 1.57 × 10{sup 7} year) and {sup 36}Cl (T{sub 1/2} = 3.01 × 10{sup 5} year). {sup 129}I and {sup 131}I are both produced by {sup 235}U fission in nuclear reactors. Being isotopes of iodine, these nuclides are expected to behave similarly in the environment. This makes {sup 129}I useful for retrospective reconstruction of {sup 131}I distribution during the initial stages of the accident. On the other hand, {sup 36}Cl is generated during reactor operation via neutron capture reaction of {sup 35}Cl, an impurity in the coolant or reactor component. Resulting {sup 36}Cl/Cl ratio within the reactor is thus much higher compared to that in environment. Similar to {sup 129}I, {sup 36}Cl is expected to have leaked out during the accident and it is important to evaluate its effects. In this study, {sup 129}I concentrations were determined in several surface soil samples collected around F1NPP. Average {sup 129}I/{sup 131}I ratio was estimated to be 26.1 ± 5.8 as of March 11, 2011, consistent with calculations using ORIGEN2 code and other published data. {sup 36}Cl/Cl ratios in some of the soil samples were likewise measured and ranged from 1.1 × 10{sup −12} to 2.6 × 10{sup −11}. These are higher compared to ratios measured around F1NPP before the accident. A positive correlation between {sup 36}Cl and {sup 129}I concentration was observed.

  2. Measurement of long-lived radionuclides in surface soil around F1NPP accident site by Accelerator Mass Spectrometry

    Science.gov (United States)

    Miyake, Yasuto; Matsuzaki, Hiroyuki; Sasa, Kimikazu; Takahashi, Tsutomu

    2015-10-01

    In March 2011, vast amounts of radionuclides were released into the environment due to the Fukushima Daiichi Nuclear Power Plant (F1NPP) accident. However, very little work has been done concerning accident-derived long-lived nuclides such as 129I (T1/2 = 1.57 × 107 year) and 36Cl (T1/2 = 3.01 × 105 year). 129I and 131I are both produced by 235U fission in nuclear reactors. Being isotopes of iodine, these nuclides are expected to behave similarly in the environment. This makes 129I useful for retrospective reconstruction of 131I distribution during the initial stages of the accident. On the other hand, 36Cl is generated during reactor operation via neutron capture reaction of 35Cl, an impurity in the coolant or reactor component. Resulting 36Cl/Cl ratio within the reactor is thus much higher compared to that in environment. Similar to 129I, 36Cl is expected to have leaked out during the accident and it is important to evaluate its effects. In this study, 129I concentrations were determined in several surface soil samples collected around F1NPP. Average 129I/131I ratio was estimated to be 26.1 ± 5.8 as of March 11, 2011, consistent with calculations using ORIGEN2 code and other published data. 36Cl/Cl ratios in some of the soil samples were likewise measured and ranged from 1.1 × 10-12 to 2.6 × 10-11. These are higher compared to ratios measured around F1NPP before the accident. A positive correlation between 36Cl and 129I concentration was observed.

  3. Radioactivity: radionuclides in foods

    International Nuclear Information System (INIS)

    Simpson, R.E.; Baratta, E.J.; Jelinek, C.F.

    1977-01-01

    The results are summarized of the analysis for strontium-90, cesium-137, iodine-131, ruthenium-106, and potassium-40, a naturally occurring radionuclide, in samples of total diet and selected import commodities in the foods compliance program of the Food and Drug Administration. On the basis of the radionuclide intake guidelines established by the Federal Radiation Council (FRC), the low content of radionuclides found in the total diet samples for fiscal years 1973 and 1974 demonstrates the need for surveillance only at the present level. The low levels of radionuclides found in a limited number of edible imported commodities indicate that their contribution to the total diet would not increase the levels of these radionuclides above those recommended for only periodic surveillance by the FRC. The potassium levels, determined from potassium-40 activity, found in meats and fish agree with the value for normal muscle tissue for the reference man reported by the International Commission on Radiation Protection. Of the other commodities, nuts contained the highest levels, while sugar, beverages, and processed foods contained the lowest levels of potassium. Although cesium and potassium are chemical analogs with similar metabolic properties, because of their variable content in some leafy samples as a result of surface contamination, a correlation between cesium-137 levels and the cesium-137-to-potassium ratio was inconclusive

  4. Evaluation of DOE radionuclide solubility data and selected retardation parameters: description of calculational and confirmatory experimental activities

    International Nuclear Information System (INIS)

    Kelmers, A.D.; Clark, R.J.; Cutshall, N.H.; Johnson, J.S.; Kessler, J.H.

    1983-01-01

    An experimentally oriented program has been initiated to support the NRC analysis and licensing activities related to high-level nuclear waste repositories. The program will allow the NRC to independently confirm key geochemical values used in the site performance assessments submitted by the DOE candidate repository site projects. Key radionuclide retardation factor values, particularly radionuclide solubility and sorption values under site specific geochemical conditions, are being confirmed. The initial efforts are being directed toward basalt rock/groundwater systems relevant to the BWIP candidate site in the Pasco Basin. Future work will consider tuff (NNWSI candidate site in Yucca Mountain) and salt (unspecified ONWI bedded or domal salt sites) rock/groundwater systems. Initial experimental results with technetium have confirmed the BWIP values for basalt/groundwater systems under oxic redox conditions: high solubility and no sorption. Under reducing redox conditions, however, the experimental work did not confirm the proposed technetium values recommended by BWIP. In the presence of hydrazine to establish reducing conditions, an apparent solubility limit for technetium of about 5E-7 mol/L was encountered; BWIP recommended calculated values of 1E-12 or greater than or equal to 1E-14 mol/L. Experimental evidence concerning sorption of reduced technetium species is incomplete at this time. Equilibrium speciation and saturation indices were calculated for well water data sets from BWIP using the computer code PHREEQUE. Oversaturation was indicated for hematite and quartz in all data sets. Near surface samples were undersaturated with respect to calcite, but most deep samples were oversaturated with respect to calcite and other carbonate minerals

  5. A Monte Carlo program converting activity distribution to absorbed dose distributions in a radionuclide treatment planning system

    International Nuclear Information System (INIS)

    Tagesson, M.; Ljungberg, M.; Strand, S.E.

    1996-01-01

    In systemic radiation therapy, the absorbed dose distribution must be calculated from the individual activity distribution. A computer code has been developed for the conversion of an arbitrary activity distribution to a 3-D absorbed dose distribution. The activity distribution can be described either analytically or as a voxel based distribution, which comes from a SPECT acquisition. Decay points are sampled according to the activity map, and particles (photons and electrons) from the decay are followed through the tissue until they either escape the patient or drop below a cut off energy. To verify the calculated results, the mathematically defined MIRD phantom and unity density spheres have been included in the code. Also other published dosimetry data were used for verification. Absorbed fraction and S-values were calculated. A comparison with simulated data from the code with MIRD data shows good agreement. The S values are within 10-20% of published MIRD S values for most organs. Absorbed fractions for photons and electrons in spheres (masses between 1 g and 200 kg) are within 10-15% of those published. Radial absorbed dose distributions in a necrotic tumor show good agreement with published data. The application of the code in a radionuclide therapy dose planning system, based on quantitative SPECT, is discussed. (orig.)

  6. 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)

  7. Radionuclide activities, geochemistry, and accumulation rates of sediments in the Gulf of Thailand

    International Nuclear Information System (INIS)

    Srisuksawad, K.; Porntepkasemsan, B.; Nouchpramool, S.; Yamkate, P.; Carpenter, R.; Peterson, M.L.; Hamilton, T.

    1997-01-01

    Downcore concentration profiles of 210 Pb , U, and Th isotopes, Al, Fe, Ti, Mn and Sc were measured in sediment box cores collected at 22 stations (16-70 m water depth) covering most of the Thai zone of the Gulf of Thailand. Distributions of excess 210 Pb and the detrital elements were used to study spatial variations in sedimentary processes, mineralogy, and geochemistry between different regions of the gulf. Steady-state depositional concentrations and fluxes of excess 210 Pb are 3-10 times lower in Gulf of Thailand sediments than in sediments from mid-latitudes in the northern hemisphere, reflecting lower 210 Pb inputs from atmospheric fallout at 6-13 o N latitude and from lower production of 210 Pb from 226 Ra in the shallower waters of the Gulf. U and Th concentrations are approximately 2-3 times higher than those in shelf sediments from mid-latitudes of North America, consistent with a higher proportion of granitic source rocks in the Thai environment. Downcore variations in 228 Th/ 232 Th activity ratios and in U activities reveal that exchange of interstitial and overlying waters and their dissolved chemicals occurs down to 20 cm in 8 of 10 cores. This benthic exchange may be important in budgets of fluxes of other soluble chemicals in this shallow shelf sea. A net flux of U isotopes from overlying water into Gulf of Thailand sediments occurs in contrast to their release from sediments of the tropical Amazon shelf. Detectable levels of 137 Cs were found only in sediments near the mouth of the largest river, the Chao Phraya. The detrital elements 232 Th, 230 Th, Al, Ti, and Sc all show relatively uniform downcore concentration profiles. This supports a key assumption in calculations of sediment accumulation rates from downcore profiles of 210 Pb activity, that steady-state depositional conditions exist and that basic sediment mineralogy and grain size does not change. 210 Pb model derived mass accumulation rates vary between 270 and 490 mg/cm 2 per year in

  8. Fallout radionuclide based techniques for assessing the effectiveness of soil conservation measures in different eroded regions of China

    International Nuclear Information System (INIS)

    Yu Hanqing; Li Yong; Liu Guoqiang; Li Junjie; Nguyen, M.L.; Funk, R.

    2012-01-01

    Using fallout radionuclide techniques (FRN), we investigated the extent of soil erosion and to quantify the beneficial effects of soil conservation measures at four sites (Xichang city in the Yangtze upriver, Yan'an in the Loess Plateau, Fengning in the wind erosion region of northern China, and Baiquan in black soil region of north-eastern China) extending from South West (SW) to North East (NE) China. At the Xichang site of SW-China, the combined use of FRN 137 Cs and 210 Pbex measurements demonstrated that the effectiveness of vegetation species in reducing soil erosion decreased in the following order: shrubs > trees with litter layer > grasses > trees without litter layer. At the Yan'an site of Loess Plateau, sediment production estimated by 137 Cs declined by 49% due to terracing and by 80% due to vegetated (with grass forest) compared to the cultivated hillslopes. Vegetated hillslope with grasses and forest increased soil organic matter (SOM) by 255%, soil available N (AN) by 198%, and soil available P (AP) by 18% while terracing increased SOM by 121%, soil AN by 103%, and soil AP by 162% compared with the entire cultivated hillslope. Both terracing and vegetating hillslopes were found to enhance soil porosity as shown by a decrease in soil bulk density (1.6% and 6.4%, respectively). At the Fengning site, data from 7 Be measurements indicated that four years of no tillage with high crop residues (50 ∼ 56 cm depth) reduced soil erosion by 44% and no tillage with low residues (25 cm depth) reduced soil erosion rates by 33% when compared with conventional tillage practices. At the Baiquan site in NE-China, soil loss as measured by 137 Cs tracer, decreased by 14% due to terracing and by 34% due to contoured tillage. Our results suggested that shrub cover and composite structure of forest and grass are the effective practices to control hillslope erosion in SW-China, while terracing forest-grass structure can greatly reduce soil erosion and improve soil quality

  9. Behaviour of uranium series radionuclides in surface water (Crouzille, Limousin). Geochemical implications

    International Nuclear Information System (INIS)

    Moulin, J.

    2008-06-01

    Understanding natural radionuclides behaviour in surface water is a required step to achieve uranium mine rehabilitation and preserve water quality. The first objective of this thesis is to determine which are the radionuclides sources in a drinking water reservoir. The second objective is to improve the knowledge about the behaviour of uranium series radionuclides, especially actinium. The investigated site is a brook (Sagnes, Limousin, France) which floods a peat bog contaminated by a former uranium mine and which empties into the Crouzille lake. It allows studying radionuclides transport in surface water and radionuclides retention through organic substance or water reservoir. Radionuclides distribution in particulate, colloidal and dissolved phases is determined thanks to ultra-filtrations. Gamma spectrometry allows measuring almost all natural radionuclides with only two counting stages. However, low activities of 235 U series radionuclides impose the use of very low background well-type Ge detectors, such as those of the Underground Laboratory of Modane (France). Firstly, this study shows that no or few radionuclides are released by the Sagnes peat bog, although its radioactivity is important. Secondly, it provides details on the behaviour of uranium series radionuclides in surface water. More specifically, it provides the first indications of actinium solubility in surface water. Actinium's behaviour is very close to uranium's even if it is a little less soluble. (author)

  10. Radionuclides in foods

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains data on the levels of radionuclides in the UK foodchain. Most data derive from monitoring programmes that exist around nuclear sites, and in some cases date back to the 1960s. Some comparative data from site operator and government-run programmes are included. Data from monitoring undertaken after the Chernobyl accident are summarised. General monitoring of the foodchain for both artificial and natural radionuclides, and the results of relevant government-sponsored research are also described. The report includes basic information on radioactivity in the environment, radiation protection standards and describes what measures are taken to routinely monitor the foodchain and assess public risk. (Author)

  11. 3D modeling of effects of increased oxygenation and activity concentration in tumors treated with radionuclides and antiangiogenic drugs

    Energy Technology Data Exchange (ETDEWEB)

    Lagerloef, Jakob H.; Kindblom, Jon; Bernhardt, Peter [Department of Radiation Physics, Goeteborg University, Goeteborg 41345 (Sweden); Department of Oncology, Sahlgrenska University Hospital, Goeteborg 41345 (Sweden); Department of Radiation Physics, Goeteborg University, Goeteborg, Sweden and Department of Nuclear Medicine, Sahlgrenska University Hospital, Goeteborg 41345 (Sweden)

    2011-08-15

    Purpose: Formation of new blood vessels (angiogenesis) in response to hypoxia is a fundamental event in the process of tumor growth and metastatic dissemination. However, abnormalities in tumor neovasculature often induce increased interstitial pressure (IP) and further reduce oxygenation (pO{sub 2}) of tumor cells. In radiotherapy, well-oxygenated tumors favor treatment. Antiangiogenic drugs may lower IP in the tumor, improving perfusion, pO{sub 2} and drug uptake, by reducing the number of malfunctioning vessels in the tissue. This study aims to create a model for quantifying the effects of altered pO{sub 2}-distribution due to antiangiogenic treatment in combination with radionuclide therapy. Methods: Based on experimental data, describing the effects of antiangiogenic agents on oxygenation of GlioblastomaMultiforme (GBM), a single cell based 3D model, including 10{sup 10} tumor cells, was developed, showing how radionuclide therapy response improves as tumor oxygenation approaches normal tissue levels. The nuclides studied were {sup 90}Y, {sup 131}I, {sup 177}Lu, and {sup 211}At. The absorbed dose levels required for a tumor control probability (TCP) of 0.990 are compared for three different log-normal pO{sub 2}-distributions: {mu}{sub 1} = 2.483, {sigma}{sub 1} = 0.711; {mu}{sub 2} = 2.946, {sigma}{sub 2} = 0.689; {mu}{sub 3} = 3.689, and {sigma}{sub 3} = 0.330. The normal tissue absorbed doses will, in turn, depend on this. These distributions were chosen to represent the expected oxygen levels in an untreated hypoxic tumor, a hypoxic tumor treated with an anti-VEGF agent, and in normal, fully-oxygenated tissue, respectively. The former two are fitted to experimental data. The geometric oxygen distributions are simulated using two different patterns: one Monte Carlo based and one radially increasing, while keeping the log-normal volumetric distributions intact. Oxygen and activity are distributed, according to the same pattern. Results: As tumor pO{sub 2

  12. Incorporation monitoring by measurements of activity concentrations in air

    International Nuclear Information System (INIS)

    Breukelmann, G.; Dalheimer, A.; Dilger, H.; Henrichs, K.

    1997-01-01

    The incorporation monitoring of workers handling actinides is in many cases not possible by individual methods: The sensitivity of bioassay of methods (in vivo, in vitro) is not sufficient to detect amounts as required by the low annual limits of intake. Similar difficulties may occur with the use of radionuclides with very short physical half-lives. In these cases, the measuring of activity concentrations in the air is the only way to monitor the workers and to meet legal requirements. The essential problem connected with this approach is to make sure, that the air sample analyzed represents the average air inhaled actually. Correspondingly, the new system regulating the incorporation monitoring in Germany requires additional measures to ensure this representatively. (author)

  13. The in vivo measurement of radiocaesium activity in broiler chickens

    International Nuclear Information System (INIS)

    Poeschl, M.; Balas, J.

    2000-01-01

    Contamination of certain areas of Europe with radiocaesium from the Chernobyl accident led to a higher 137 Cs accumulation (i.e. 300-600 Bq kg -1 ) in grain and to potential post-accident contamination of broiler chickens. In future, such contamination may require a simple determination of the 137 Cs activity concentration in broiler chicken meat which would lead to measures for preventing the recommended limits of radionuclide contamination of the meat for human consumption from being exceeded. This paper describes the development of a rapid method for the in vivo monitoring of the broiler chicken using a lead-shielded sodium iodide detector. The method enables simply fixed live chicken to be monitored, the results showing a good correlation (R 2 =0.98) with measurements of meat from chicken previously monitored in vivo prior to slaughter

  14. Measurements of {sup 60}Co in spoons activated by neutrons during the JCO criticality accident at Tokai-mura in 1999

    Energy Technology Data Exchange (ETDEWEB)

    Gasparro, J.; Hult, M. E-mail: mikael.hult@irmm.jrc.be; Komura, K.; Arnold, D.; Holmes, L.; Johnston, P.N.; Laubenstein, M.; Neumaier, S.; Reyss, J.-L.; Schillebeeckx, P.; Tagziria, H.; Van Britsom, G.; Vasselli, R

    2004-07-01

    Neutron activated items from the vicinity of the place where the JCO criticality accident occurred have been used to determine the fluence of neutrons around the facility and in nearby residential areas. By using underground laboratories for measuring the activation products, it is possible to extend the study to also cover radionuclides with very low activities from long-lived radionuclides. The present study describes {gamma}-ray spectrometry measurements undertaken in a range of underground laboratories for the purpose of measuring {sup 60}Co more than 2 years after the criticality event. The measurements show that neutron fluence determined from {sup 60}Co activity is in agreement with previous measurements using the short-lived radionuclides {sup 51}Cr and {sup 59}Fe. Limits on contamination of the samples with {sup 60}Co are evaluated and shown to not greatly affect the utility of neutron fluence determinations using {sup 60}Co activation.

  15. Measurement of soil contamination by radionuclides due to the Fukushima Dai-ichi Nuclear Power Plant accident and associated estimated cumulative external dose estimation

    International Nuclear Information System (INIS)

    Endo, S.; Kimura, S.; Takatsuji, T.; Nanasawa, K.; Imanaka, T.; Shizuma, K.

    2012-01-01

    Soil sampling was carried out at an early stage of the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident. Samples were taken from areas around FDNPP, at four locations northwest of FDNPP, at four schools and in four cities, including Fukushima City. Radioactive contaminants in soil samples were identified and measured by using a Ge detector and included 129m Te, 129 Te, 131 I, 132 Te, 132 I, 134 Cs, 136 Cs, 137 Cs, 140 Ba and 140 La. The highest soil depositions were measured to the northwest of FDNPP. From this soil deposition data, variations in dose rates over time and the cumulative external doses at the locations for 3 months and 1 y after deposition were estimated. At locations northwest of FDNPP, the external dose rate at 3 months after deposition was 4.8–98 μSv/h and the cumulative dose for 1 y was 51 to 1.0 × 10 3 mSv; the highest values were at Futaba Yamada. At the four schools, which were used as evacuation shelters, and in the four urban cities, the external dose rate at 3 months after deposition ranged from 0.03 to 3.8 μSv/h and the cumulative doses for 1 y ranged from 3 to 40 mSv. The cumulative dose at Fukushima Niihama Park was estimated as the highest in the four cities. The estimated external dose rates and cumulative doses show that careful countermeasures and remediation will be needed as a result of the accident, and detailed measurements of radionuclide deposition densities in soil will be important input data to conduct these activities.

  16. Double-radionuclide autoradiographic method using N-isopropyl-iodoamphetamine for sequential measurements of local cerebral blood flow

    International Nuclear Information System (INIS)

    Obrenovitch, T.P.; Clayton, C.B.; Strong, A.J.

    1987-01-01

    A double-radionuclide autoradiographic method has been assessed for sequential determinations of local CBF (LCBF). It is based on two successive intravascular injections of N-isopropyl-p-iodoamphetamine (IMP) labelled with different radionuclides, whose concentrations can later be differentiated in the same tissue section using double-radionuclide autoradiography. Previous studies suggested that the distribution of IMP, up to 30 min after its administration, still represents LCBFs. Our data indicate that, provided the tracer is injected directly into the left ventricle, there is little back diffusion from normal brain to blood under physiological conditions for at least 35 min following the tracer injection and an injection of unlabelled IMP, in a dose larger than that used for blood flow determination, does not displace any labelled IMP previously taken up by the brain, nor does it displace any labelled IMP previously accumulated in the lung that would lead to secondary brain uptake. On the basis of these results, we conclude that sequential autoradiographic determinations of LCBF using IMP labelled with different radionuclides is possible. This is a promising experimental method for the simultaneous investigation of changes in LCBF in several CNS structures

  17. Radionuclide transfer

    International Nuclear Information System (INIS)

    Gerber, G.B.

    1993-01-01

    The research project described here had the aim to obtain further information on the transfer of nuclides during pregnancy and lactation. The tests were carried out in mini-pigs and rats receiving unchanging doses of radionuclides with the food. The following findings were revealed for the elements examined: Fe, Se, Cs and Zn were characterized by very high transfer levels in the mother, infant and foetus. A substantial uptake by the mother alone was observed for Co, Ag and Mn. The uptake by the foetus and infant here was 1 to 10 times lower. A preferential concentration in certain tissues was seen for Sr and Tc; the thyroid levels of Tc were about equally high in mothers and infants, while Sr showed less accumulation in the maternal bone. The lanthanide group of substances (Ce, Eu and Gd as well as Y and Ru) were only taken up to a very limited extent. The uptake of the examined radionuclides (Fe, Co, Ag, Ce) with the food ingested was found here to be ten times greater in rats as compared to mini-pigs. This showed that great caution must be observed, if the behaviour of radionuclides in man is extrapolated from relevant data obtained in rodents. (orig./MG) [de

  18. Review of neutron activation analysis in the standardization and study of reference materials, including its application to radionuclide reference materials

    International Nuclear Information System (INIS)

    Byrne, A.R.

    1993-01-01

    Neutron activation analysis (NAA) plays a very important role in the certification of reference materials (RMs) and their characterization, including homogeneity testing. The features of the method are briefly reviewed, particularly aspects relating to its completely independent nuclear basis, its virtual freedom from blank problems, and its capacity for self-verification. This last aspect, arising from the essentially isotopic character of NAA, can be exploited by using different nuclear reactions and induced nuclides, and the possibility of employing two modes, one instrumental (nondestructive), the other radiochemical (destructive). This enables the derivation of essentially independent analytical information and the unique capacity of NAA for selfvalidation. The application of NAA to quantify natural or man-made radionuclides such as uranium, thorium, 237 Np, 129 I and 230 Th is discussed, including its advantages over conventional radiometric methods and its usefulness in providing independent data for nuclides where other confirmatory analyses are impossible, or are only recently becoming available through newer 'atom counting' techniques. Certain additional, prospective uses of NAA in the study of RMs and potential RMs are mentioned, including transmutation reactions, creation of endogenously radiolabelled matrices for production and study of RMs (such as dissolution and leaching tests, use as incorporated radiotracers for chemical recovery correction), and the possibility of molecular activation analysis for specification. (orig.)

  19. Radionuclides in Canada goose eggs

    International Nuclear Information System (INIS)

    Rickard, W.H.; Sweany, H.A.

    1975-01-01

    Low levels of radionuclides were measured in Canada goose eggs taken from deserted nests from Columbia River islands on the Energy Research and Development Administration's Hanford Reservation. Potassium-40, a naturally occurring radionuclide, was the most abundant radionuclide measured in egg contents and egg shell. Strontium-90 was incorporated into egg shells and cesium-137 into inner egg contents. Manganese-54, cobalt-60, and zinc-65 were more abundant in inner egg contents than in egg shell. Cerium-144 was detected in egg shell but not in inner shell

  20. Radionuclides in soil and vegetables in the Novi Sad area

    International Nuclear Information System (INIS)

    Krmar, M.; Slivka, J.; Djurcic, Z.; Zikic, N.; Bikit, I.; Conkic, Lj.

    1999-01-01

    The results of radiological control of soil from the fields for vegetable breeding in Novi Sad region are presented in this paper. Using obtained values of concentration activity and known transfer-factors contents of some radionuclides in several vegetables was estimated. The values of activity concentration obtained by direct measurements are lower than estimated ones. (author)

  1. Development of portable Liquid Scintillation counters for on-site primary measurement of radionuclides using the Triple-to-Double Coincidence Ratio method

    International Nuclear Information System (INIS)

    Cassette, P.; Capogni, M.; De Felice, P.; Johansson, L.; Sephton, J.; Kossert, K.; Naehle, O.

    2013-06-01

    The Triple-to-Double Coincidence Ratio (TDCR) method in Liquid Scintillation counting (LSC) is a primary radionuclide standardization method widely used in National Metrology laboratories and was primarily developed for the activity measurement of beta emitters. It is based on liquid scintillation: the light is detected by three photomultipliers (PM) and the detection efficiency is evaluated by using a model which uses the ratio of triple-to-double coincidences between the PM tubes. Up to now, most of current TDCR systems were locally-made metrology instruments neither aimed at nor suitable for in-situ measurements. In the framework of the European Metrofission project, a work package was dedicated to the realisation of miniature self-calibrated primary TDCR systems, which are state-of-the-art, for use on-site. The challenge was to develop a versatile portable, table-top designed instrument, from this metrology device. This implied improvements for the miniaturisation of the detection chamber, for the miniaturisation of electronic modules by exploring the possibilities of digital treatment, and for the validation of models and extension of them to nuclides with special beta spectrum shapes, to nuclides with complex decay schemes including many gamma-rays and to nuclides with higher atomic number decaying by electron capture. Four prototypes of counters were built by the Metrofission partners ENEA (Italy), LNHB (France), NPL (UK) and PTB (Germany) using various technical approaches. The paper describes these prototypes and provides some details on the choice of the technical options concerning the design of the optical chamber, of the photodetectors and of the acquisition system. (authors)

  2. Radionuclide methods in pediatric cardiology

    International Nuclear Information System (INIS)

    Reich, O.; Ruth, C.; Samanek, M.

    1990-01-01

    The use of radionuclide methods in pediatric cardiology is discussed for non-invasive evaluation of myocardial function and perfusion, regional lung perfusion and ventilation, and for measuring central and peripheral hemodynamics. (H.W.). 16 refs

  3. Tracing sediment sources in upstream agricultural catchments: contribution of elemental geochemistry, 87Sr/86Sr ratio and radionuclides measurements

    International Nuclear Information System (INIS)

    Le-Gall, Marion

    2016-01-01

    sensitivity of land cultivated with conventional farming practices (downstream contribution), compared to areas cultivated under conservation agriculture (upstream contribution). Coupling several tracers ( 87 Sr/ 86 Sr ratios, elemental concentrations and radionuclides) was shown to improve the understanding of sediment sources and dynamics at the catchment scale and to provide crucial information to guide the implementation of management measures to limit soil erosion. This fingerprinting approach produced an original dataset that may be used to calibrate and validate models simulating erosion and sediment transfers. (author) [fr

  4. Preconcentration and Speciation of Trace Elements and Trace-Element Analogues of Radionuclides by Neutron Activation Analysis

    International Nuclear Information System (INIS)

    Chatt, A.

    1999-01-01

    We have developed a number of preconcentration neutron activation analysis (PNAA) methods in our laboratory for the determination of trace elements in a variety of complex sample matrices. We developed a number of cocrystallization and coprecipitation methods for the determination of trace elements in water samples. We developed several methods for the determination of I in foods and diets. We have developed a number of PNAA methods in our laboratory We determined As and Sb in geological materials and natural waters by coprecipitation with Se and Au in silicate rocks and ores by coprecipitation with Te followed by NAA. We developed an indirect NAA method for the determination of B in leachates of borosilicate glass. We have been interested in studying the speciation of Am, Tc, and Np in simulated vitrified groundwater leachates of high-level wastes under oxid and anoxic conditions using a number of techniques. We then used PNAA methods to study speciation of trace-element analogues of radionuclides. We have been able to apply biochemical techniques and NAA for the separation, preconcentration, and characterization of metalloprotein and protein-bound trace-element species in subcellular fractions of bovine kidneys. Lately, we have concentrated our efforts to develop chemical and biochemical methods in conjunction with NAA, NMR, and MS for the separation and identification of extractable organohalogens (EOX) in tissues of beluga whales, cod, and northern pink shrimp

  5. Stochastic approach for radionuclides quantification

    Science.gov (United States)

    Clement, A.; Saurel, N.; Perrin, G.

    2018-01-01

    Gamma spectrometry is a passive non-destructive assay used to quantify radionuclides present in more or less complex objects. Basic methods using empirical calibration with a standard in order to quantify the activity of nuclear materials by determining the calibration coefficient are useless on non-reproducible, complex and single nuclear objects such as waste packages. Package specifications as composition or geometry change from one package to another and involve a high variability of objects. Current quantification process uses numerical modelling of the measured scene with few available data such as geometry or composition. These data are density, material, screen, geometric shape, matrix composition, matrix and source distribution. Some of them are strongly dependent on package data knowledge and operator backgrounds. The French Commissariat à l'Energie Atomique (CEA) is developing a new methodology to quantify nuclear materials in waste packages and waste drums without operator adjustment and internal package configuration knowledge. This method suggests combining a global stochastic approach which uses, among others, surrogate models available to simulate the gamma attenuation behaviour, a Bayesian approach which considers conditional probability densities of problem inputs, and Markov Chains Monte Carlo algorithms (MCMC) which solve inverse problems, with gamma ray emission radionuclide spectrum, and outside dimensions of interest objects. The methodology is testing to quantify actinide activity in different kind of matrix, composition, and configuration of sources standard in terms of actinide masses, locations and distributions. Activity uncertainties are taken into account by this adjustment methodology.

  6. BIPM comparison BIPM.RI(II)-K1.Eu-152 of activity measurements of the radionuclide 152Eu for the VNIIM (Russia), the LNE-LNHB (France) and the CNEA (Argentina), with linked results for the COOMET.RI(II)-K2.Eu-152 comparison

    International Nuclear Information System (INIS)

    Michotte, C.; Ratel, G.; Courte, S.; Kharitonov, I.A.; Zanevsky, A.V.; Terechtchenko, E.E.; Moune, M.; Aubineau-Laniece, I.; Bobin, C.; Arenillas, P.; Balpardo, C.

    2014-01-01

    Three new participants in the BIPM.RI(II)-K1.Eu-152 comparison have been added to the previous results and this has produced a revised value for the key comparison reference value (KCRV), calculated using the power-moderated weighted mean. A link has been made to the COOMET.RI(II)-K2.Eu-152 comparison held in 2010 through the VNIIM who participated in both comparisons. Three National Metrology Institutes (NMIs) used the K1 or K2 comparisons to update their degree of equivalence. The degrees of equivalence between each equivalent activity measured in the International Reference System (SIR) and the KCRV have been calculated and the results are given in the form of a table for four NMIs in the BIPM.RI(II)-K1.Eu-152 comparison, three participants in the COOMET.RI(II)-K2.Eu-152 comparison and the 18 other participants in the previous CCRI(II)-K2.Eu-152 comparison. A graphical presentation is also given. (authors)

  7. Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    The Department of Energy`s (DOE`s) planning for the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of the waste. This report estimates volumes, radionuclide activities, and waste forms of GTCC LLW to the year 2035. It groups the waste into four categories, representative of the type of generator or holder of the waste: Nuclear Utilities, Sealed Sources, DOE-Held, and Other Generator. GTCC LLW includes activated metals (activation hardware from reactor operation and decommissioning), process wastes (i.e., resins, filters, etc.), sealed sources, and other wastes routinely generated by users of radioactive material. Estimates reflect the possible effect that packaging and concentration averaging may have on the total volume of GTCC LLW. Possible GTCC mixed LLW is also addressed. Nuclear utilities will probably generate the largest future volume of GTCC LLW with 65--83% of the total volume. The other generators will generate 17--23% of the waste volume, while GTCC sealed sources are expected to contribute 1--12%. A legal review of DOE`s obligations indicates that the current DOE-Held wastes described in this report will not require management as GTCC LLW because of the contractual circumstances under which they were accepted for storage. This report concludes that the volume of GTCC LLW should not pose a significant management problem from a scientific or technical standpoint. The projected volume is small enough to indicate that a dedicated GTCC LLW disposal facility may not be justified. Instead, co-disposal with other waste types is being considered as an option.

  8. Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics. Revision 1

    International Nuclear Information System (INIS)

    1994-09-01

    The Department of Energy's (DOE's) planning for the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of the waste. This report estimates volumes, radionuclide activities, and waste forms of GTCC LLW to the year 2035. It groups the waste into four categories, representative of the type of generator or holder of the waste: Nuclear Utilities, Sealed Sources, DOE-Held, and Other Generator. GTCC LLW includes activated metals (activation hardware from reactor operation and decommissioning), process wastes (i.e., resins, filters, etc.), sealed sources, and other wastes routinely generated by users of radioactive material. Estimates reflect the possible effect that packaging and concentration averaging may have on the total volume of GTCC LLW. Possible GTCC mixed LLW is also addressed. Nuclear utilities will probably generate the largest future volume of GTCC LLW with 65--83% of the total volume. The other generators will generate 17--23% of the waste volume, while GTCC sealed sources are expected to contribute 1--12%. A legal review of DOE's obligations indicates that the current DOE-Held wastes described in this report will not require management as GTCC LLW because of the contractual circumstances under which they were accepted for storage. This report concludes that the volume of GTCC LLW should not pose a significant management problem from a scientific or technical standpoint. The projected volume is small enough to indicate that a dedicated GTCC LLW disposal facility may not be justified. Instead, co-disposal with other waste types is being considered as an option

  9. Sedimentology models from activity concentration measurements: application to the 'Bay of Cadiz' Natural Park (SW Spain)

    International Nuclear Information System (INIS)

    Ligero, R.A.; Vidal, J.; Melendez, M.J.; Hamani, M.; Casas-Ruiz, M.

    2009-01-01

    A previous study on seabed sediments of the Bay of Cadiz (SW of Spain) enabled us to identify several relations between sedimentological variables and activity concentrations of environmental radionuclides such as 137 Cs, 226 Ra, 232 Th and 40 K. In this paper the study has been extended to a large neighbouring inter-tidal area in order to establish if the above mentioned models can be generalized. As a result we have determined that the measured activity concentrations are closely to the values predicted by the theoretical models (correlation coefficient range = 0.85-0.93). Furthermore, the proposal model for granulometric facies as a function of activity concentrations of the abovementioned radionuclides provides for the sediments distribution a representation which agrees with the values of the tidal energy distribution obtained using numeric models calibrated with experimental data from current meters and water level recorders

  10. Random summing in a multi-detector counting system measuring mixtures of radionuclides of short and long half-lives

    International Nuclear Information System (INIS)

    Oxby, C.B.; Oldroyd, B.; Graham, S.G.

    1979-01-01

    A method is described for correcting a radiation spectrum for the distortion caused by random summing when a multidetector array is used to acquire events from a mixture of radionuclides whose half-lives may be long or short compared with the counting period. With our own counting system it was found that both the resolving time, and the fractions of the energy of a second signal which may be added to that of the immediately previous signal, i.e., the resolving time function, are dependent upon the energies of these two signals. The method requires knowledge of the losses which occur in a multidetector system e.g., live-time error and blocking losses, the variation of the resolving time function with signal energies, a standard spectrum of each radionuclide of the mixture and the fractions of them which constitute the mixture spectrum, the decay constant of each radionuclide, and the fraction of the total events recorded by the system being received by each detector. (orig.)

  11. The study of specific activity and effect of gamma ray from natural radionuclide to the environment outside Sultan Abdul Aziz Plant Station, Kapar, Klang, Selangor

    International Nuclear Information System (INIS)

    Wan Amar Fikri Wan Ali

    2012-01-01

    Waste resulting from coal combustion process can result in increasing the specific activity of natural radionuclide such as 238 U, 232 Th , 226 Ra and 40 K. Following combustion, radionuclide focused on fly ash, some escape the filtration system in the chimney that causes the gamma ray exposure dose increases. The objective of this study was to calculate the specific activity of natural radionuclide and identifying the gamma ray exposure dose outside the Stesen Janakuasa Elektric Station of Sultan Abdul Aziz further examine the risk of gamma ray exposure dose and specific activity of natural radionuclide to the ecosystem because the station is located close to residential areas and local residents migratory bird stopover. The samples studied are soil, water and sediment that are outside the station. Samples taken with the correct procedures then treated and stored about a month before counting. Gamma ray exposure dose for the seven stations studied are between 0.330 μSv/ h - 1.20 μSv/ h. While the range of specific activities obtained for the 40 K, 238 U, 232 Th and 226 Ra were 201 Bq/ kg - 468 Bq/ kg, 0.480 Bq/ kg - 2.57 Bq/ kg, 12.9 Bq/ kg - 74.5 Bq/ kg and 6.64 Bq/ kg - 11.7 Bq/ kg. While the sediment samples were 216 Bq/ kg - 465 Bq/ kg, 18.1 Bq/ kg - 4.43 Bq/ kg, 24.8 Bq/ kg - 65.3 Bq/ kg, 8.53 Bq/ kg - 11.2 Bq/ kg. For water samples, the specific range of their specific activities are 10.5 Bq/ L - 12.1 Bq/ L, 1.40 Bq/ L - 1.63 Bq/ L, 1.57 Bq/ L - 1.65 Bq/ L and 0 Bq/ L - 1.14 Bq/ L. (author)

  12. Specific activity of radionuclides in technological processing of nettle (urtica) for food

    International Nuclear Information System (INIS)

    Ivanova, T.N.; Odintsov, Yu.A.; Zakharchenko, G.A.; Chernikov, S.A.

    1996-01-01

    Possibility of using nettle (urtica) for food in the regions, contaminated after the Chernobyl accident, is studied. Clear dependence of 137 Cs transport from the soil into the nettle is not determined even in the regions with high density of soil contamination. It is established that nettle wetting during one hour in water completely relieves it from 137 Cs. It is recommended to use the nettle as source material of biologically active substances for nutrition purposes. 6 refs

  13. A study on the improved DTC method for estimations of radionuclide activity in radwaste containers

    International Nuclear Information System (INIS)

    Kang, Sang Hee; Hwang, Ki Ha; Lee, Sang Chul; Lee, Kun Jai; Kim, Tae Wook; Kim, Kyoung Deok; Herr, Young Hoi; Song, Myung Jae

    2004-01-01

    Disposal of rad waste containers requires the assessment of the radioactive contents of each container. Some containers can not be assessed by the γ nuclide analyzer because of time constraint and economical burden. One alternative method, dose to curie conversion (DTC) method can provide an estimate of the container activity. This study evaluates the impact of voids, the chemical composition and density of the material and the distribution of the source related to surface dose rate and the development of the improved DTC method for more accurate assessment

  14. Determination Of Activity Of Radionuclides In Moss-Soil Sample With Self-Absorption Correction

    International Nuclear Information System (INIS)

    Tran Thien Thanh; Chau Van Tao; Truong Thi Hong Loan; Hoang Duc Tam

    2011-01-01

    Hyper Pure Germanium (HPGe) spectrometer system is a very powerful tool for radioactivity measurements. The systematic uncertainty in the full energy peak efficiency is due to the differences between the matrix (density and chemical composition) of the reference and the other bulk samples. For getting precision from the gamma spectrum analysis, the absorbed correction in the sample should be considered. For gamma spectral analysis, a correction for absorption effects in sample should be considered, especially for bulk samples. The results were presented and discussed in this paper. (author)

  15. Method for profile measurement in vivo of small quantities of radionuclides with γ-energies over 1 MeV

    International Nuclear Information System (INIS)

    Falk, R.

    1976-11-01

    A comparison of two different methods to get profiles for the activity distribution in vivo have been performed. Mathematical conection of the transmission through the sides of the collimator showed the best result. The method will be adapted to clinical use for example for measurement of iron-59 at investigation of the bone marrow

  16. Rapid radiochemical separation of short-lived radionuclides in neutron-activated samples

    International Nuclear Information System (INIS)

    Fardy, J.

    1985-11-01

    Radiochemical separation procedures based on the removal of metal ions by columns of C 18 -bonded silica gel after selective complexation are examined and the simplicity of the method demonstrated by its application to determination of Mn, Cu and Zn in neutron-activated biological material from the following solutions (pH 0-10, sulphate concentration 0,18M and 1,44M SO 4 ): 8-hydroxyquinoline (oxine), ammonium pyrrolidinedithiocarbamate (APDC), cupferron (CUP), 1-(2-pyridylazo)-2-naphthol (PAN), 1-(2'-thiazolylazo)-2-naphthol (TAN), 4-(2-pyridylazo) resorcinol (PAR), diethylammonium diethyldithiocarbamate (DDC), potassium ethyl xanthate (PEX), acetylacetone (AcAc) or thenoyltrifluoracetone (TTA). The method is rapid and reliable and readily adaptable in all radiochemical laboratories

  17. Monitoring intervals for measurement of the radionuclides {sup 125} I and {sup 129I} in thyroid glands; Intervalos de monitoreo, para la medicion en la glandula tiroides de los radionucleidos {sup 125}I y {sup 1} {sup 29}I

    Energy Technology Data Exchange (ETDEWEB)

    Simanca, Yoan Yera; Bejerano, Gladys M. Lopez, E-mail: yoan@cphr.edu.cu, E-mail: gladys@cphr.edu.cu [Centro de Proteccion e Higiene de las Radiaciones (CPHR), Cuidad de la Habana (Cuba)

    2013-07-01

    This work shows the monitoring interval, which can be implemented in the Laboratorio de Contaminacion Interna del Centro de Proteccion e Higiene de las Radiaciones, for direct measurement in the thyroid gland of radionuclides {sup 125}I and {sup 129}I . Were used two measuring systems, one employing a scintillating detector and the other detector Phoswich. Both detectors were placed inside a depth camera, 2.5 x 2.5 x 2.5m of dimension covered with 15 cm of steel, 3 mm lead, 1.8 mm tin and 1.5 mm of copper. Was calculated for each system, the minimum detectable activity, and based on this, the monitoring interval is determined. Was obtained, for {sup 125}, all tested intervals, 120, 90,60,30 , 14, and 7 days may be implemented with both systems. In the case of the radionuclide {sup 129} I, with the installation of scintillating detector can only be implemented the intervals 120, 90, and 60 days , and for installation with Phoswich, all evaluated.

  18. Radionuclides Activity and Radiological Hazard Assessment in Bananas Samples Exported to Iraq

    International Nuclear Information System (INIS)

    Al-Juboury, B.Kh.; Akram, M.A.

    2016-01-01

    The average concentration of radio nuclide's in the various banana samples were collected from being the most popular markets in Baghdad city - Iraq were measured by use Sodium Iodide Thallium [NaI(Tl)] detector.The radio nuclide's observed with reliable regularity belonged to the series-decay naturally occurring radionuclide’s headed by 232 U and 232 Th as well as the non-series nuclide, 40 K and 137 Cs.The average concentration of 40 K was found the least average concentration value recorded as 876.74625 Bq kg -1 .The average concentration of 238 U was 28.6425 Bqkg -1 for 232 Th, it was found to have the average concentration 14.1805 Bqkg -1 .The cesium concentration in the sample was found in the healthy range

  19. Measurement of circulating transcripts and gene cluster analysis predicts and defines therapeutic efficacy of peptide receptor radionuclide therapy (PRRT) in neuroendocrine tumors

    International Nuclear Information System (INIS)

    Bodei, L.; Kidd, M.; Modlin, I.M.; Severi, S.; Nicolini, S.; Paganelli, G.; Drozdov, I.; Kwekkeboom, D.J.; Krenning, E.P.; Baum, R.P.

    2016-01-01

    Peptide receptor radionuclide therapy (PRRT) is an effective method for treating neuroendocrine tumors (NETs). It is limited, however, in the prediction of individual tumor response and the precise and early identification of changes in tumor size. Currently, response prediction is based on somatostatin receptor expression and efficacy by morphological imaging and/or chromogranin A (CgA) measurement. The aim of this study was to assess the accuracy of circulating NET transcripts as a measure of PRRT efficacy, and moreover to identify prognostic gene clusters in pretreatment blood that could be interpolated with relevant clinical features in order to define a biological index for the tumor and a predictive quotient for PRRT efficacy. NET patients (n = 54), M: F 37:17, median age 66, bronchial: n = 13, GEP-NET: n = 35, CUP: n = 6 were treated with 177 Lu-based-PRRT (cumulative activity: 6.5-27.8 GBq, median 18.5). At baseline: 47/54 low-grade (G1/G2; bronchial typical/atypical), 31/49 18 FDG positive and 39/54 progressive. Disease status was assessed by RECIST1.1. Transcripts were measured by real-time quantitative reverse transcription PCR (qRT-PCR) and multianalyte algorithmic analysis (NETest); CgA by enzyme-linked immunosorbent assay (ELISA). Gene cluster (GC) derivations: regulatory network, protein:protein interactome analyses. Statistical analyses: chi-square, non-parametric measurements, multiple regression, receiver operating characteristic and Kaplan-Meier survival. The disease control rate was 72 %. Median PFS was not achieved (follow-up: 1-33 months, median: 16). Only grading was associated with response (p < 0.01). At baseline, 94 % of patients were NETest-positive, while CgA was elevated in 59 %. NETest accurately (89 %, χ 2 = 27.4; p = 1.2 x 10 -7 ) correlated with treatment response, while CgA was 24 % accurate. Gene cluster expression (growth-factor signalome and metabolome) had an AUC of 0.74 ± 0.08 (z-statistic = 2.92, p < 0.004) for predicting

  20. Measurement of circulating transcripts and gene cluster analysis predicts and defines therapeutic efficacy of peptide receptor radionuclide therapy (PRRT) in neuroendocrine tumors

    Energy Technology Data Exchange (ETDEWEB)

    Bodei, L. [European Institute of Oncology, Division of Nuclear Medicine, Milan (Italy); LuGenIum Consortium, Milan, Rotterdam, Bad Berka, London, Italy, Netherlands, Germany (Country Unknown); Kidd, M. [Wren Laboratories, Branford, CT (United States); Modlin, I.M. [LuGenIum Consortium, Milan, Rotterdam, Bad Berka, London, Italy, Netherlands, Germany (Country Unknown); Yale School of Medicine, New Haven, CT (United States); Severi, S.; Nicolini, S.; Paganelli, G. [Istituto Scientifico Romagnolo per lo Studio e la Cura dei Tumori (IRST) IRCCS, Nuclear Medicine and Radiometabolic Units, Meldola (Italy); Drozdov, I. [Bering Limited, London (United Kingdom); Kwekkeboom, D.J.; Krenning, E.P. [LuGenIum Consortium, Milan, Rotterdam, Bad Berka, London, Italy, Netherlands, Germany (Country Unknown); Erasmus Medical Center, Nuclear Medicine Department, Rotterdam (Netherlands); Baum, R.P. [LuGenIum Consortium, Milan, Rotterdam, Bad Berka, London, Italy, Netherlands, Germany (Country Unknown); Zentralklinik Bad Berka, Theranostics Center for Molecular Radiotherapy and Imaging, Bad Berka (Germany)

    2016-05-15

    Peptide receptor radionuclide therapy (PRRT) is an effective method for treating neuroendocrine tumors (NETs). It is limited, however, in the prediction of individual tumor response and the precise and early identification of changes in tumor size. Currently, response prediction is based on somatostatin receptor expression and efficacy by morphological imaging and/or chromogranin A (CgA) measurement. The aim of this study was to assess the accuracy of circulating NET transcripts as a measure of PRRT efficacy, and moreover to identify prognostic gene clusters in pretreatment blood that could be interpolated with relevant clinical features in order to define a biological index for the tumor and a predictive quotient for PRRT efficacy. NET patients (n = 54), M: F 37:17, median age 66, bronchial: n = 13, GEP-NET: n = 35, CUP: n = 6 were treated with {sup 177}Lu-based-PRRT (cumulative activity: 6.5-27.8 GBq, median 18.5). At baseline: 47/54 low-grade (G1/G2; bronchial typical/atypical), 31/49 {sup 18}FDG positive and 39/54 progressive. Disease status was assessed by RECIST1.1. Transcripts were measured by real-time quantitative reverse transcription PCR (qRT-PCR) and multianalyte algorithmic analysis (NETest); CgA by enzyme-linked immunosorbent assay (ELISA). Gene cluster (GC) derivations: regulatory network, protein:protein interactome analyses. Statistical analyses: chi-square, non-parametric measurements, multiple regression, receiver operating characteristic and Kaplan-Meier survival. The disease control rate was 72 %. Median PFS was not achieved (follow-up: 1-33 months, median: 16). Only grading was associated with response (p < 0.01). At baseline, 94 % of patients were NETest-positive, while CgA was elevated in 59 %. NETest accurately (89 %, χ{sup 2} = 27.4; p = 1.2 x 10{sup -7}) correlated with treatment response, while CgA was 24 % accurate. Gene cluster expression (growth-factor signalome and metabolome) had an AUC of 0.74 ± 0.08 (z-statistic = 2.92, p < 0

  1. Distribution of naturally occurring radionuclides activity concentration in East Malaysian marine sediment

    Energy Technology Data Exchange (ETDEWEB)

    Yii, M.W. [Malaysian Nuclear Agency (Nuclear Malaysia), Bangi, 43000 Kajang (Malaysia)], E-mail: yii@nuclearmalaysia.gov.my; Zaharudin, A.; Abdul-Kadir, I. [Malaysian Nuclear Agency (Nuclear Malaysia), Bangi, 43000 Kajang (Malaysia)

    2009-04-15

    Studies of naturally occurring radioactive materials (NORM) distribution of {sup 226}Ra, {sup 228}Ra and {sup 40}K in East Malaysia were carried out as part of a marine coastal environment project. The results of measurements will serve as baseline data and background reference level for Malaysia coastlines. Sediments from 21 coastal locations and 10 near shore locations were collected for analyses. The samples were dried, finely ground, sealed in a container and stored for a minimum of 30 days to establish secular equilibrium between {sup 226}Ra and {sup 228}Ra and their respective radioactive progenies. They were counted using a high-purity germanium (HPGe) spectrometer covering the respective progeny energy peak. For {sup 40}K, the presence of this was measured directly via its 1460 keV energy peak. The concentration of {sup 226}Ra, {sup 228}Ra and {sup 40}K in samples obtained from coastal Sarawak ranged between 23 and 41 (mean 30{+-}2) Bq/kg, 27 and 45 (mean 39{+-}4) Bq/kg and 142 and 680 (mean 462{+-}59) Bq/kg, respectively. Meanwhile, the concentration of {sup 226}Ra, {sup 228}Ra and {sup 40}K for samples obtained from coastal Sabah ranged between 16 and 30 (mean 23{+-}2) Bq/kg, 23 and 45 (mean 35{+-}4) Bq/kg and 402 and 842 (mean 577{+-}75) Bq/kg, respectively. For the Sarawak near shore stations, the concentration of {sup 226}Ra, {sup 228}Ra and {sup 40}K ranged between 11 and 36 (mean 22{+-}2) Bq/kg, 21 and 65 (mean 39{+-}5) Bq/kg and 149 and 517 (mean 309{+-}41) Bq/kg, respectively. Meanwhile, the concentration of {sup 226}Ra, {sup 228}Ra and {sup 40}K for samples obtained from Sabah ranged between 9 and 31 (mean 14{+-}2) Bq/kg, 10 and 48 (mean 21{+-}3) Bq/kg and 140 and 580 (mean 269{+-}36) Bq/kg, respectively. The calculated external hazard values of between 0.17 and 0.33 (less than unity) showed that there is little risk of external hazard to the workers handling the sediments.

  2. Geomorphological applications of environmental radionuclides

    International Nuclear Information System (INIS)

    Quine, T.A.; Walling, D.

    1998-01-01

    Geomorphologists have shown increasing interest in environmental radionuclides since pioneering studies by Ritchie and McHenry in the USA and Campbell, Longmore and Loughran in Australia. Environmental radionuclides have attracted this interest because they provide geomorphologists with the means to trace sediment movement within the landscape. They, therefore, facilitate investigation of subjects at the core of geomorphology, namely the rates and patterns of landscape change. Most attention has been focussed on the artificial radionuclide caesium-137 ( 137 Cs) but more recently potential applications of the natural radionuclides lead-210 ( 210 Pb) and beryllium-7( 7 Be) have been investigated (Walling et al., 1995; Wallbrink and Murray, 1996a, 1996b). The origin, characteristics and applications of these radionuclides are summarised. These radionuclides are of value as sediment tracers because of three important characteristics: a strong affinity for sediment; a global distribution and the possibility of measurement at low concentration. Geomorphological applications of environmental radionuclides provide unique access to detailed qualitative data concerning landscape change over a range of timescales

  3. Determination of molybdate mean ionic activity coefficients for the assessment of radionuclide mobility

    International Nuclear Information System (INIS)

    Grambow, B.; Mueller, R.; Rother, A.

    1992-01-01

    Isopiestic tests at 25deg C and solubility tests as temperatures between 22 and 190deg C were used to determine solubility products and activity coefficients in the Nd-Na-Ca-Mg-Cl-MoO 4 -H 2 O system. Pitzer parameters were determined for the binary Na-MoO 4 -H 2 O and Mg-MoO 4 -H 2 O systems, the ternary Na-Cl-MoO 4 -H 2 O and the resiprocal Na-Mg-Cl-MoO 4 -H 2 O system. Solubility products K s0 were determined for MgMoO 4 x5H 2 O, CaMoO 4 x0.2H 2 O and Na 0.5 Nd 0.5 MoO 4 x0.16H 2 O; for the latter two phases the temperature dependence of solubility was determined. Isopiestic tests in concentrated binary and ternary systems with MoO 4 as a main component are consistent with solubility tests, in which MoO 4 is present only as trace component. (orig.)

  4. Calculation method in activation analysis for determination of two different radionuclides with almost the same γ-energy

    DEFF Research Database (Denmark)

    Szabo, A. S.

    1985-01-01

    The method is based on the difference of the half-lives of two dififerent radionuclides, having similar γ-energies. Using the method it is possible to determine the two components in the peaks also in that cases, if the difference between the energies is less, than the energy resolution of the de......The method is based on the difference of the half-lives of two dififerent radionuclides, having similar γ-energies. Using the method it is possible to determine the two components in the peaks also in that cases, if the difference between the energies is less, than the energy resolution...... of the detector. The main point is the perform only one irradiation, but use two different clock times before counting. The criterion of the method can be used when there is significant difference between the half-lives of the radionuclides....

  5. Doses to the embryo/fetus and neonate from intakes of radionuclides by the mother. Part 1: Doses received in utero and from activity present at birth

    International Nuclear Information System (INIS)

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

    2001-01-01

    This report considers the consequences of occupational exposures leading to intakes of radionuclides by women who are, or may become, pregnant. Estimates are given of potential doses to offspring following intakes of a selected range of naturally occurring and artificial radionuclides that might arise for different contamination scenarios in the workplace. The radionuclides covered are of interest from both routine operations and accidental releases. Doses can arise both from the transfer of radionuclides to the embryo and fetus, and from activity in the mother's tissues. The relative contributions of these two sources vary widely depending on the emissions of each radionuclide. Doses are also calculated for the lifetime of the newborn child from activity present at birth. The total dose coefficient for the offspring (the sum of the in utero and postnatal doses) calculated in this report is compared to the dose coefficients recommended by ICRP for workers. Of particular interest are cases where the offspring dose is greater than the worker dose since these are the cases where the normal standards for protection of workers may not afford sufficient protection to the offspring, isotopes of hydrogen, carbon, phosphorus, sulphur, iodine and the alkaline earth elements fall into this category. Isotopes of calcium and phosphorus, show the greatest differences between offspring and worker doses with the ratio of the two being over 15 for ingestion of calcium-45 or phosphorus-32. In utero doses for the actinides such as plutonium-239 are at most only a few per cent of the corresponding worker dose In some cases intakes by the mother that occurred well before pregnancy can lead to significant doses to the fetus; this is of particular relevance to the advance planning of protection for female workers. A general implication of this report is that intakes of some radionuclides may need to be restricted to lower levels than those that would lead to a dose to the worker of 1 m

  6. Doses to the embryo/fetus and neonate from intakes of radionuclides by the mother. Part 1: Doses received in utero and from activity present at birth

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-12-01

    This report considers the consequences of occupational exposures leading to intakes of radionuclides by women who are, or may become, pregnant. Estimates are given of potential doses to offspring following intakes of a selected range of naturally occurring and artificial radionuclides that might arise for different contamination scenarios in the workplace. The radionuclides covered are of interest from both routine operations and accidental releases. Doses can arise both from the transfer of radionuclides to the embryo and fetus, and from activity in the mother's tissues. The relative contributions of these two sources vary widely depending on the emissions of each radionuclide. Doses are also calculated for the lifetime of the newborn child from activity present at birth. The total dose coefficient for the offspring (the sum of the in utero and postnatal doses) calculated in this report is compared to the dose coefficients recommended by ICRP for workers. Of particular interest are cases where the offspring dose is greater than the worker dose since these are the cases where the normal standards for protection of workers may not afford sufficient protection to the offspring, isotopes of hydrogen, carbon, phosphorus, sulphur, iodine and the alkaline earth elements fall into this category. Isotopes of calcium and phosphorus, show the greatest differences between offspring and worker doses with the ratio of the two being over 15 for ingestion of calcium-45 or phosphorus-32. In utero doses for the actinides such as plutonium-239 are at most only a few per cent of the corresponding worker dose In some cases intakes by the mother that occurred well before pregnancy can lead to significant doses to the fetus; this is of particular relevance to the advance planning of protection for female workers. A general implication of this report is that intakes of some radionuclides may need to be restricted to lower levels than those that would lead to a dose to the worker of

  7. Vadose zone microbial community structure and activity in metal/radionuclide contaminated sediments. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Balkwill, David L.

    2002-08-17

    This final technical report describes the research carried out during the final two months of the no-cost extension ending 11/14/01. The primary goals of the project were (1) to determine the potential for transformation of Cr(VI) (oxidized, mobile) to Cr(III) (reduced, immobile) under unsaturated conditions as a function of different levels and combinations of (a) chromium, (b) nitrate (co-disposed with Cr), and (c) molasses (inexpensive bioremediation substrate), and (2) to determine population structure and activity in experimental treatments by characterization of the microbial community by signature biomarker analysis and by RT-PCR and terminal restriction fragment length polymorphism (T-RFLP) and 16S ribosomal RNA genes. It was determined early in the one-year no-cost extension period that the T-RFLP approach was problematic in regard to providing information on the identities of microorganisms in the samples examined. As a result, it could not provide the detailed information on microbial community structure that was needed to assess the effects of treatments with chromium, nitrate, and/or molasses. Therefore, we decided to obtain the desired information by amplifying (using TR-PCR, with the same primers used for T-RFLP) and cloning 16S rRNA gene sequences from the same RNA extracts that were used for T-RFLP analysis. We also decided to use a restriction enzyme digest procedure (fingerprinting procedure) to place the clones into types. The primary focus of the research carried out during this report period was twofold: (a) to complete the sequencing of the clones, and (b) to analyze the clone sequences phylogenetically in order to determine the relatedness of the bacteria detected in the samples to each other and to previously described genera and species.

  8. Experimental implementation and proof of principle for a radionuclidic purity test solely based on half-life measurement

    DEFF Research Database (Denmark)

    Jørgensen, Thomas; Jensen, Mikael

    2016-01-01

    have developed an GUI application for use as an easy and automated test tool in the production procedure.The test results show that this method fully complies with the requirements in the European Pharmacopoeia (Eur. Ph.) for RNP of FDG and F-18 Sodium Fluoride. (C) 2015 Elsevier Ltd. All rights......In this paper we present the results of an experimental implementation of the method (Jorgensen et al., 2012) for testing the radionuclidic purity (RNP) of F-18 compounds.The overall limitations of the experimental methods and their possible impacts on RNP detectability have been identified. We...

  9. Concentration levels of alpha emitting radionuclides in natural waters. Implications in the use of various radionuclides of reference for the determination of total alpha activity index

    International Nuclear Information System (INIS)

    Corbacho, J. A.; Baeza, A.; Guillen, J.; Valles, I.; Serrano, I.; Camacho, A.; Montana, M.

    2013-01-01

    The present study was carried out a statistical evaluation of the natural radioactive contents of a large number of water samples collected at different points of the Spanish geography, in order to meet its controlling radioactive composition and assessing the implications of total alpha activity index can have in this type of samples. (Author)

  10. Determination of scaling factors to estimate the radionuclide inventory in waste with low and intermediate-level activity from the IEA-R1 reactor; Determinacao de fatores de escala para estimativa do inventario de radionuclideos em rejeitos de media e baixa atividades do reator IEA-R1

    Energy Technology Data Exchange (ETDEWEB)

    Taddei, Maria Helena Tirollo

    2013-07-01

    Regulations regarding transfer and final disposal of radioactive waste require that the inventory of radionuclides for each container enclosing such waste must be estimated and declared. The regulatory limits are established as a function of the annual radiation doses that members of the public could be exposed to from the radioactive waste repository, which mainly depend on the activity concentration of radionuclides, given in Bq/g, found in each waste container. Most of the radionuclides that emit gamma-rays can have their activity concentrations determined straightforwardly by measurements carried out externally to the containers. However, radionuclides that emit exclusively alpha or beta particles, as well as gamma-rays or X-rays with low energy and low absolute emission intensity, or whose activity is very low among the radioactive waste, are generically designated as Difficult to Measure Nuclides (DTMs). The activity concentrations of these DTMs are determined by means of complex radiochemical procedures that involve isolating the chemical species being studied from the interference in the waste matrix. Moreover, samples must be collected from each container in order to perform the analyses inherent to the radiochemical procedures, which exposes operators to high levels of radiation and is very costly because of the large number of radioactive waste containers that need to be characterized at a nuclear facility. An alternative methodology to approach this problem consists in obtaining empirical correlations between some radionuclides that can be measured directly – such as {sup 60}Co and {sup 137}Cs, therefore designated as Key Nuclides (KNs) – and the DTMs. This methodology, denominated Scaling Factor, was applied in the scope of the present work in order to obtain Scaling Factors or Correlation Functions for the most important radioactive wastes with low and intermediate-activity level from the IEA-R1 nuclear research reactor. (author)

  11. Mercury mass measurement in fluorescent lamps via neutron activation analysis

    Science.gov (United States)

    Viererbl, L.; Vinš, M.; Lahodová, Z.; Fuksa, A.; Kučera, J.; Koleška, M.; Voljanskij, A.

    2015-11-01

    Mercury is an essential component of fluorescent lamps. Not all fluorescent lamps are recycled, resulting in contamination of the environment with toxic mercury, making measurement of the mercury mass used in fluorescent lamps important. Mercury mass measurement of lamps via instrumental neutron activation analysis (NAA) was tested under various conditions in the LVR-15 research reactor. Fluorescent lamps were irradiated in different positions in vertical irradiation channels and a horizontal channel in neutron fields with total fluence rates from 3×108 cm-2 s-1 to 1014 cm-2 s-1. The 202Hg(n,γ)203Hg nuclear reaction was used for mercury mass evaluation. Activities of 203Hg and others induced radionuclides were measured via gamma spectrometry with an HPGe detector at various times after irradiation. Standards containing an Hg2Cl2 compound were used to determine mercury mass. Problems arise from the presence of elements with a large effective cross section in luminescent material (europium, antimony and gadolinium) and glass (boron). The paper describes optimization of the NAA procedure in the LVR-15 research reactor with particular attention to influence of neutron self-absorption in fluorescent lamps.

  12. Emissions of the corrosion radionuclides in an atmosphere

    International Nuclear Information System (INIS)

    Vardanyan, M.

    2010-01-01

    In area of Armenian nuclear power plant location, in atmospheric air in majority of cases log two technogenic radionuclides: l 37 C s and 9 0 S r. Presence of these radionuclides basically is caused by global fall out (consequences of tests of the nuclear weapon and Chernobyl NPP accident), whose contribution to the contents of these radionuclides in atmosphere is incomparably greater, than emissions from the NPP. However there are some cases when in an atmosphere are registered the technogenic radionuclides, caused by emissions from NPP. In the present work such case is considered. Gas-aerosol releases of NPP in the atmosphere are carefully purified by means of various high-efficiency filters and gas-cleaning systems. Nevertheless, one should forecast and measure, the possible impact of these releases on the environment in the regions surrounding the NPP. Radioactive releases of the Armenian NPP (ANPP) contain the set of radionuclides characteristic for NPPs of this type. They may be divided into three groups: 1 31 I , 1 37 C s, 1 34 C s, 9 0 S r and 8 9 S r fission fragments, isotopes of noble gases krypton and xenon and other radionuclides; corrosion originated radionuclides: 6 0 C o, 1 10m A g, 5 4 M n, 5 l C r and others; activation products of the heat-transfer agent itself. It should be noted that the amount of radioactive materials released in the environment by the ANPP during the whole period of its operation was much lower than the admissible quantities specified in the corresponding legal documents (RSN, NPPSP) acting in Armenia, which are practically identical to the internationally accepted norms. The amounts of releases and their radionuclides composition for the ANPP are given

  13. Radionuclides in food

    International Nuclear Information System (INIS)

    Fernandez Gomez, Isis Maria

    2008-01-01

    The sources of the presence of radionuclides in food are presented: natural radiation and artificial radiation. The transfer of radionuclides through food chains, intakes of radionuclides to the body with its partners effective doses and typical consumption of basic foods of a rural adult population are exposed as main topics. Also the radiation doses from natural sources and exposure to man by ingestion of contaminated food with radionuclides of artificial origin are shown. The contribution of the food ingestion to the man exposure depends on: characteristics of radionuclide, natural conditions, farming practices and eating habits of the population. The principal international organizations in charge of setting guide levels for radionuclides in food are mentioned: standards, rules and the monitoring. It establishes that a guide is necessary for the food monitoring; the alone CODEX ALIMENTARIUS is applicable to emergency situations and the generic action levels proposed by the CODEX not satisfy all needs (no guiding international levels for planned or existing situations such as NORM). There are handled mainly socio-economic and political aspects. Among the actions to be taken are: to assure a public comprehensive information over the risk evaluation in food; to reinforce the collaboration among the different international organizations (WHO, IAEA, ICRP, EC) in relation with the food of set; to give follow-up to the control of the drinkable water and NORM's presence in the food. In addition, it is possible to create the necessary mechanisms to reduce the number of irrelevant measures and bureaucratic useless steps (certificates); to promote the exchange between the different institutions involved in the topic of the food, with relation to the acquired experiences and learned lessons. Likewise, it might examine the possibility of a multidisciplinary approximation (radioactive and not radioactive pollutants); to elaborate a technical guide to assure the

  14. Measurements of {beta} or {alpha} emitter long lived radionuclides using inductively coupled plasma mass spectrometry; Dosage a tres bas niveau de radionucleides a longue periode emetteurs {beta} ou {alpha} par spectrometrie de masse a couplage plasma inductif

    Energy Technology Data Exchange (ETDEWEB)

    Provitina, O

    1993-10-18

    The measurement of long-lived radionuclides is highly important for characterizing nuclear wastes for their later storage. The main techniques are {alpha} spectrometry, {beta} counting and {gamma} spectrometry. The large period of these isotopes leads to low specific activity needing time consuming measurements. Moreover, the radiometric techniques are often limited by problems of interferences involving several steps of pretreatments. Among these steps, the specific extraction with crown ethers is highly selective for the separation of {sup 99}Tc, {sup 129}I and {sup 135}Cs. The radiometric techniques are here replaced by inductively coupled plasma mass spectroscopy (ICP-MS) the advantages of which are: few interferences, sensitivity which does not depend on the radiologic period as compared to radiochemistry. ICP-MS can then measure {sup 237}Np in enriched uranium matrix and reduce by a factor of 4 the sample pretreatment and the duration of the analysis usually performed by {alpha} spectrometry. Another technique, electrothermal vaporization (ETV), is consequently used. Crown ether extraction-ETV-ICP-MS is employed for measuring the long lived radionuclides {sup 99}Tc and {sup 129}I. The conditions of the extraction and the parameters of the ETV and the ICP-MS are studied and optimized. The methods optimized (extraction, electrothermal vaporization) are validated in the case of {sup 99}Tc, in real samples. The spike method is required to quantify technetium, the quantification with calibration leading to bad results. The results obtained are in good agreement with the expected values. Extraction of technetium on anionic resin and its measurement by the spike method with pneumatic nebulization-ICP-MS is also performed on other samples. Measured values are also in agreement with expected values, but the method of extraction is more time consuming (half a day) than the extraction with crown ether (one hour). (author). 54 figs., 38 tabs.

  15. Natural radionuclides in soil profiles surrounding the largest coal-fired power plant in Serbia

    Directory of Open Access Journals (Sweden)

    Tanić Milan N.

    2016-01-01

    Full Text Available This study evaluates the influence of the largest Serbian coal-fired power plant on radionuclide concentrations in soil profiles up to 50 cm in depth. Thirty soil profiles were sampled from the plant surroundings (up to 10 km distance and analyzed using standard methods for soil physicochemical properties and gamma ray spectrometry for specific activities of natural radionuclides (40K, 226Ra and 232Th. Spatial and vertical distribution of radionuclides was determined and analyzed to show the relations between the specific activities in the soil and soil properties and the most influential factors of natural radionuclide variability were identified. The radiological indices for surface soil were calculated and radiological risk assessment was performed. The measured specific activities were similar to values of background levels for Serbia. The sampling depth did not show any significant influence on specific activities of natural radionuclides. The strongest predictor of specific activities of the investigated radionuclides was soil granulometry. All parameters of radiological risk assessment were below the recommended values and adopted limits. It appears that the coal-fired power plant does not have a significant impact on the spatial and vertical distribution of natural radionuclides in the area of interest, but technologically enhanced natural radioactivity as a consequence of the plant operations was identified within the first 1.5 km from the power plant. [Projekat Ministarstva nauke Republike Srbije br. III43009 i br. III41005

  16. Fukushima Daiichi Radionuclide Inventories

    Energy Technology Data Exchange (ETDEWEB)

    Cardoni, Jeffrey N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jankovsky, Zachary Kyle [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-09-01

    Radionuclide inventories are generated to permit detailed analyses of the Fukushima Daiichi meltdowns. This is necessary information for severe accident calculations, dose calculations, and source term and consequence analyses. Inventories are calculated using SCALE6 and compared to values predicted by international researchers supporting the OECD/NEA's Benchmark Study on the Accident at Fukushima Daiichi Nuclear Power Station (BSAF). Both sets of inventory information are acceptable for best-estimate analyses of the Fukushima reactors. Consistent nuclear information for severe accident codes, including radionuclide class masses and core decay powers, are also derived from the SCALE6 analyses. Key nuclide activity ratios are calculated as functions of burnup and nuclear data in order to explore the utility for nuclear forensics and support future decommissioning efforts.

  17. 124Sb - Activity measurement and determination of photon emission intensities

    International Nuclear Information System (INIS)

    Be, M.M.; Chauvenet, B.

    2009-07-01

    The international traceability of antimony 124, in term of activity, is very limited. The results of 124 Sb activity measurements sent to the SIR (BIPM - International System of Reference, BIPM.RI(II)-K1.Sb-124.) are scarce. Up to now, only three laboratories have contributed. Two of them carried out measurements using the 4πβ-γ coincidence counting technique and the third one using the 4πγ method with a well-type crystal detector. The first two results are in agreement but the last one differs significantly from them, by 2 %. The decay scheme consistency cannot be excluded when trying to explain those discrepancies. In other respects, this nuclide emits high-energy gamma rays, and then could be selected as a valuable standard radionuclide for the calibration of gamma-ray detectors in that energy range, given well known photon intensities. Those considerations led to the proposal of an international exercise and to the realisation of this Euromet project, registered as project no. 907, coordinated by CEA-List-LNE/LNHB. The first part of this exercise was dedicated to activity measurements and to their comparison. For this purpose, participants were asked to make use of all the direct measurement techniques available in their laboratory in order to confirm or not the existence of possible biases specific to some measuring methods. In addition, this exercise offered the opportunity of improving the uncertainties of the gamma-ray intensities. Then, participants were asked, in the second part of the exercise, to carry out X-ray and gamma-ray intensity measurements. These results have been compared to previous published values and new decay scheme data are proposed. Eight international laboratories participated in this exercise. (authors)

  18. Radionuclide Retention in Concrete Wasteforms

    Energy Technology Data Exchange (ETDEWEB)

    Bovaird, Chase C.; Jansik, Danielle P.; Wellman, Dawn M.; Wood, Marcus I.

    2011-09-30

    Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how wasteform performance is affected by the full range of environmental conditions within the disposal facility; the process of wasteform aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of wasteform aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the wasteforms come in contact with groundwater. The information present in the report provides data that (1) measures the effect of concrete wasteform properties likely to influence radionuclide migration; and (2) quantifies the rate of carbonation of concrete materials in a simulated vadose zone repository.

  19. Artificial radionuclides in the atmosphere over Lithuania

    International Nuclear Information System (INIS)

    Lujaniene, G.; Sapolaite, J.; Remeikis, V.; Lujanas, V.; Aninkevicius, V.

    2006-01-01

    Systematic observations of radionuclide composition and concentration in the atmosphere have been carried out at the Institute of Physics in Vilnius since 1963. An increase in activity concentration of radionuclides in the atmosphere was observed after nuclear weapon tests and the Chernobyl NPP accident. At present the radiation situation in Lithuania is determined by two main sources of radionuclides, forest fire and resuspension products transferred from highly polluted region of the Ukraine and Belarus. During forest fires the increase in activity concentration of 1 37Cs in the atmosphere was registered in many countries and in Lithuania as well. This work summarizes the experimental data on transport of cesium, plutonium, americium from the highly contaminated territories after the Chernobyl accident. The activity concentrations of 1 37Cs were measured in two - three days samples while plutonium and americium in monthly samples. In addition, the analyses of the events of the increase activity concentration, meteorological situation, speciation of radionuclides and mechanisms of formation and transformation of aerosol carriers of radionuclides are presented. Aerosols were sampled on perchlorvinyl filters and the large volume air samplers with a flow rate from 2400 m 3 /h to about 6000 m 3 /h were used. The radiochemical analyses of monthly samples of aerosol ashes (about 30 g) were performed. For separation of Pu isotopes the TOPO/cyclohexane extraction and radiochemical purification using UTEVA resin were performed, Am was separated after TOPO/cyclohexane extraction using TRU and TEVA resins (100-150 μm). 2 42Pu and 2 43Am were used as tracers in the separation procedure. The alpha spectrometry measurements of Pu and Am isotopes deposited on a stainless steel disc were carried out with the Alphaquattro (Silena) spectrometer. 1 37Cs was determined by gamma-ray spectrometry using the high purity HPGe detector (resolution - 1.9 keV/1.33 Mev, efficiency - 42

  20. The radiological situation at the atolls of Mururoa and Fangataufa. Technical report. V. 1. Radionuclide concentrations measured in the terrestrial environment of the atolls

    International Nuclear Information System (INIS)

    1998-08-01

    This report provides technical details of the terrestrial sampling and measurement campaign undertaken as part of the Study of the Radiological Situation at the Atolls of Mururoa, Fangataufa by the Terrestrial Working Group. The primary objective of this group was to evaluate existing French data on the presence of environmental radionuclides on the atolls of Mururoa, Fangataufa and Tureia in French Polynesia. All aspects of the terrestrial environments of Mururoa and Fangataufa Atolls - the sites of atmospheric and underground nuclear tests - were included in the sampling programme. Tureia Atoll - the nearest inhabited island - was also included in the sampling programme, in order to determine whether deposits from atmospheric testing are detectable there. The task required the co-operation of many different parties in order to provide the supporting logistics for the sampling campaign and the expertise for analysing the different radionuclides of interest in the samples collected. Samples were analysed by members of the IAEA's co-ordinated international network of Analytical Laboratories for Measuring Environmental Radioactivity (ALMERA) and the Agency's laboratories, Seibersdorf. Samples were also sent to the French Service Mixte de Surveillance Radiologique et Biologique (SMSRB)