Radioactivity Measurements on Glazed Ceramic Surfaces

OpenAIRE

Hobbs, Thomas G.

2000-01-01

A variety of commonly available household and industrial ceramic items and some specialty glass materials were assayed by alpha pulse counting and ion chamber voltage measurements for radioactivity concentrations. Identification of radionuclides in some of the items was performed by gamma spectroscopy. The samples included tableware, construction tiles and decorative tiles, figurines, and other products with a clay based composition. The concentrations of radioactivity ranged from near backgr...

Estimation of alpha radioactivity in some fertilizers and plants

International Nuclear Information System (INIS)

Nain, Mahabir; Chauhan, Pooja; Chauhan, R.P.; Chakarvarti, S.K.

2012-01-01

The uptake of radio nuclides into roots from the soils and phosphate fertilizers along with direct deposition of 210 Pb by rainfall represents the principal mechanism of incorporation of 210 Pb and 210 Po into some plants. Uranium and its decay products present in soil enter the plants through roots and get distributed in various parts of the plants. This phenomenon may cause high intake of uranium and its radioactive decay products leading to harmful effects in human being. In the present work the variation in alpha radioactivity of the leaves of some plants was measured using plastic track detectors LR-115 Type-II manufactured by Kodak. The healthy leaves from different samples of plants at regular interval of were plucked, dried and then sandwiched between two plastic track detectors each of same size (1 cm x 1 cm) by wrapping a cello tape tightly to record the tracks for alpha radiations emitted from both upper and bottom faces of the leaves The radon exhalation rates in different fertilizer samples have also been measured using Canister Technique. At the end of exposure time, the detectors were removed and subjected to a chemical etching process. The detectors were washed, dried and after that, the tracks caused by alpha radiations were counted using an optical Olympus microscope. Measurement of track densities (track cm -2 day -1 ) shows a variation on the upper face and the bottom face of the leaves for the plants. The variation in track density has also been observed with use of different fertilizers with some higher levels in phosphate fertilizers compared with other cases under study. (author)

Alpha radioactivity in Indian cement samples

International Nuclear Information System (INIS)

Nain, M.; Chauhan, R. P.; Chakarvarti, S. K.

2006-01-01

The essential constituents of radioactive and each of cements like lime, silica and alumina are derived from earth's crust in which radioactive elements like uranium, thorium etc are also present in varying amounts almost everywhere. These two elements are considered as the parent elements of uranium and thorium radioactive decay series in which radon and thoron are produced respectively as decay products. In the present study the samples of ordinary Portland cement , Portland pozzolana cement and some other cementious finishing materials like white cement, Plaster of Paris , cement putty etc were collected and analysed for radium and radon concentrations along with radon exhalation rates. Materials and Methods: Alpha sensitive LR-115 Type II plastic track detectors commonly known as S olid State Nuclear Track Detectors w ere used to measure the radium and radon concentration. The alpha particles emitted from the radon causes the radiation damaged tracks. The Chemical etching in NaOH at 60 C for about 90 minutes was done to reveal these latent tracks, which were then scanned and counted by an optical microscope of suitable magnification. By calculating the track density of registered tracks, the radon and radium concentrations along with exhalation rate of radon, were determined using required formulae. Results: The radon and radium concentration in various brands of cements found to vary from 333±9.9 to 506±13.3 Bq m-3 and from 3.7±0.1 to 5.6±0.2 Bq k g-1 while in various cementious finishing materials used in the construction, these were found to vary from 378±19.7 to 550±9.8 Bq m-3 and from 4.2±0.2 to 6.1±0.1 Bq Kg-1, respectively. Based on the data the mass and surface exhalation rates were also calculated Conclusion: The measurements indicate that there is marginal variation of the concentration of radium and radon in various brands of cements in India with lower levels in the cement samples having red oxide and higher levels in fly ash based cement

alpha-particle radioactivity from LR 115 by two methods of analysis

CERN Document Server

Azkour, K; Adloff, J C; Pape, A

1999-01-01

LR115 track detectors were exposed to samples of Moroccan phosphate and phosphogypsum to measure their alpha-particle radioactivity. Then two formalisms were used for the dosimetry: simulation by a Monte Carlo method and determination of concentrations from a numerically integrated track registration equation. The results were compared with those deduced gamma-ray spectrometry.

Elemental analysis of fertilizers using X-ray fluorescence and their impact on alpha radioactivity of plants

International Nuclear Information System (INIS)

Pooja Chauhan; Chauhan, R.P.

2013-01-01

The fertilizers used for plantation contain different elements including some natural radionuclides with their daughter decay products. The radiological impact of the use of fertilizers may be due to internal irradiation of the lung by the alpha particles, short lived radon-thoron progeny and the external irradiation of the body by gamma ray emitted from the radionuclides. The aim of this study was to estimate the enhanced alpha radioactivity in different parts of plants due to fertilizers and to measure the concentration of different elements present in the fertilizers. A control study was carried out on round gourd plants using different fertilizers. Fertilizers were added to the soil just before the plantation of seeds in the pots. For the measurement of alpha track densities in different parts of plants we used α-sensitive LR-115 type II plastic track detectors. The alpha-track density (T cm -2 days -1 ) was measured in leaves of plants at different interval of time. The variation in alpha track densities was also observed in root, stem leaf and grain parts of the plants. In case of the plants grown using some phosphate fertilizers the alpha radioactivity was found to be more compared with others. A positive correlation between alpha track densities and mass exhalation rates of radon from different fertilizers has been observed. The concentration of major elements (Al, Si, P, S, Cl, K) along with other elements present in fertilizer samples was measured by X-ray fluorescence analysis. (author)

Measurement of Gross Alpha and Beta Emission Rates from Ceramic Tiles

International Nuclear Information System (INIS)

Wudthicharoonpun, Piyasak; Chankow, Nares

2007-08-01

Full text: Ceramic tiles normally used to cover floors and walls contain naturally occurring radioactive elements i.e. potassium-40, uranium, thorium and their daughters from raw materials. Thus, radioactivity was dependent upon source of raw materials and the amount used. The objective of this research was to measure gross alpha and beta emission rates to be used as a database for safety assessment and for selection of rooms to measure radioactive radon-222 gas

Alpha radioactivity for proton-rich even Pb isotopes

Indian Academy of Sciences (India)

Alpha radioactivity; proton-rich nuclei; half-life. PACS Nos 23.60.+e; 23.90. ... Z/N ∼= 0.65 to the region close to proton drip line with Z/N ∼= 0.82. The existing ... In the present work we have studied the systematic for alpha emission ..... 80. 0.200. 0.402. 0.497. 8.0. 320.51. 0.333. 0.754. 0.441. 16.0. 1300.72. 0.414. 0.927.

Gamma-spectrometric and total alpha-beta counting methods for radioactivity analysis of deuterium depleted water

International Nuclear Information System (INIS)

Ferdes, Ov. S.; Mladin, C.; Vladu, Mihaela; Bulubasa, G.; Bidica, N.

2008-01-01

According to national regulations, as well as to the EU directive on the quality of drinking water, the radionuclide concentrations represent some of the drinking water quality parameters. Among the most important radioactivity content parameters are: the total alpha and total beta concentration (Bq/l); K-40 content, and the gamma-nuclides volume activities. The paper presents the measuring methods for low-level total alpha and/or beta counting of volume samples, as well as the high-resolution gamma-ray spectrometric method used to measure the volume activity of nuclides in drinking water. These methods are applied to monitor the radioactivity content and quality of the QLARIVIA brand of Deuterium depleted water (DDW). There are discussed the performances of these applied methods as well as some preliminary results. (authors)

Determination of difficult to measure actinides in radioactive liquid waste

International Nuclear Information System (INIS)

Drabova, V.; Galanda, D.; Dulanska, S.; Remenec, B.; Kuruc, J.

2014-01-01

In decommissioning of a nuclear facilities and radioactive waste treatment the activity of various radionuclides need to be measured for the waste characterization. Radiochemical separation of 241 Am, 237 Np and isotopes of plutonium was tested on model solution of evaporator concentrate sample for isolation of each of them for alpha-spectrometry analysis. This paper describes use of the molecular recognition technology product AnaLig(R)Pu-01 gel from IBC Advanced technologies, Inc. to effectively and selectively pre-concentrate, separate and recover difficult-to-measure actinides from model solution of evaporator concentrate samples which belong to the most difficult matrices to analyse. The method is suitable for analysing highly contaminated samples of radioactive waste in a relatively short time. For counting the alpha activity of 241 Am, 239,240 Pu, 238 Pu and 237 Np ORTEC 576A alpha-spectrometer equipped with ULTRA TM ion implanted silicon detectors (600 mm 2 active area) was used. The spectra were processed by using the Alpha-vision TM 32-bit emulation software from the EG and G ORTEC company. (authors)

The dispersion of alpha and beta radioactivity to the environmental from spent fuel testing in RMI

International Nuclear Information System (INIS)

Yuwono, I.; Pudjadi, E.

1996-01-01

The destructive testing of 2 spent fuels in RMI and radioactivity air release monitoring to the environmental have been done. The monitoring equipment used alpha-beta particulate monitor, Berthold LB 150 D type. The calculations using the Gaussian plume model and distributions factor showed there were no radiological effect of alpha and beta radioactivity dispersion and contribution to the environmental. The maximum average construction of alpha and beta radioactivity are 0.002% and 0.05%. (author)

Comparison of filter papers and an electrostatic precipitator for measurements on radioactive aerosols

Energy Technology Data Exchange (ETDEWEB)

Wiener, R

1958-06-15

Measurements in which electrostatic precipitators have been compared with filter papers for collection of air-borne radioactivity as to the accuracy in alpha and beta measurements have been made. The results show that the filter paper method is as good as the electrostatic method in determining beta-activity disregarding clogging and moisture sensitivity of the filter paper but it is inferior for alpha measurements. Experimental values of the alpha absorption factor for different types of filter papers are given.

Spectrometry techniques for radioactivity measurements

International Nuclear Information System (INIS)

Anilkumar, S.

2016-01-01

The energy of the radiation emission following the nuclear decay is unique and the characteristic of the radio nuclide which undergoes decay. Thus measurement of the energy of the radiation offers a method of identifying the radio nuclides. The prime requirement of the energy measurement is a suitable detector which shows response proportional to the energy of the radiation rather than the presence of the radiation. The response from such detectors are suitably processed and distributed with respect to the signal strength which is proportional to incident energy. This distribution is normally referred as energy spectrum and is recorded in the multichannel analyser. The measurement of energy and intensity of radiation from the spectrum is called radiation spectrometry. Thus the radiation spectrometry allows the identification and quantification of radioactive isotopes in variety of matrices. The radiation spectrometry has now become a popular radioanalytical technique in wide area of nuclear fuel cycle programs. The popular spectrometry techniques commonly used for the radioactivity measurement and analysis are Alpha spectrometry, Gamma ray spectrometry and Beta spectrometry

Residual radioactivity of treated green diamonds.

Science.gov (United States)

Cassette, Philippe; Notari, Franck; Lépy, Marie-Christine; Caplan, Candice; Pierre, Sylvie; Hainschwang, Thomas; Fritsch, Emmanuel

2017-08-01

Treated green diamonds can show residual radioactivity, generally due to immersion in radium salts. We report various activity measurements on two radioactive diamonds. The activity was characterized by alpha and gamma ray spectrometry, and the radon emanation was measured by alpha counting of a frozen source. Even when no residual radium contamination can be identified, measurable alpha and high-energy beta emissions could be detected. The potential health impact of radioactive diamonds and their status with regard to the regulatory policy for radioactive products are discussed. Copyright © 2017. Published by Elsevier Ltd.

Measurement of underground water-soil radioactivity at different depths in arsenic prone areas

International Nuclear Information System (INIS)

Ghosh, D.; Deb, A.; Patra, K.K.; Sengupta, R.; Nag, S.K.

2007-01-01

Studies on the presence of alpha emitting nuclides in the environment assume importance since they are found to be carcinogenic. Measurement of radioactivity in arsenic contaminated drinking water has already been reported. To perform a detail study we have undertaken a programme to measure radioactivity in drinking water and soil samples in three different places of North 24 Parganas in West Bengal, India, where arsenic contamination is severe. A detail investigation on soil samples at different depths and soil-water samples at same depth have been made with CR-39 plates -a Solid State Nuclear Track Detector (SSNTD) -a commonly used detector for alpha radiation. The data indicates high alpha activity in soil than water and this ratio is different at different places varying from 1.22 to 2.63. The dependence of the alpha activity in soil on depth is also different at different sites. The data shows some interesting results. (author)

Radioactive check sources for alpha and beta sensitive radiological instrumentation

International Nuclear Information System (INIS)

Barnett, J.M.; Kane, J.E. II.

1994-06-01

Since 1991, the Westinghouse Hanford Company has examined the construction and use of alpha and beta radioactive check sources for calibrating instruments and for performing response checks of instruments used for operational and environmental radiation detection. The purpose of using a radioactive check source is to characterize the response of a radiation monitoring instrument in the presence of radioactivity. To accurately calibrate the instrument and check its response, the check source used must emulate as closely as possible the actual physical and isotopic conditions being monitored. The isotope employed and the physical methods used to fabricate the check source (among other factors) determine instrument response. Although information from applicable national and international standards, journal articles, books, and government documents was considered, empirical data collected is most valuable when considering the type of source to use for a particular application. This paper presents source construction methods, use considerations, and standard recommendations. The results of a Hanford Site evaluation of several types of alpha and beta sources are also given

Measurement of environmental radioactivity with photo-diode and Imaging Plate

International Nuclear Information System (INIS)

Mori, C.; Sumi, T.; Gotoh, S.; Saze, T.; Nishizawa, K.

2000-01-01

Measurement of environmental radioactivity with photo-diode (PD) and Imaging Plate (IP) was tired. Commercially available Si PIN type PD's generally have depletion layer thickness more than a few hundred micrometer, which is enough for alpha particle measurement. PD's have various features: being usable in normal temperature, high energy resolution and low cost. Radon daughter nuclides positively charged in atmosphere were collected on the PD surface with negative electric potential and measured the pulse height spectra of alpha-particles from the daughter nuclides of Radon in thorium oxide, uranium ore, granite, and concrete. Counting of alpha-particles with IP was tired. Lead plates usually contain Pb-210 (RaD) and emit alpha-particles from Po-210. The alpha-particles from the plate were counted with PD and the plate was exposed to IP. By adjusting the gradation level on the reading out of the latent image, it was possible to count alpha-particle incident image one by one, and the number per 1 cm 2 was compared with the number of count with PD. (author)

Alpha and conversion electron spectroscopy of 238,239Pu and 241Am and alpha-conversion electron coincidence measurements

Energy Technology Data Exchange (ETDEWEB)

Dion, Michael P.; Miller, Brian W.; Warren, Glen A.

2016-09-01

A technique to determine the isotopics of a mixed actinide sample has been proposed by measuring the coincidence of the alpha particle during radioactive decay with the conversion electron (or Auger) emitted during the relaxation of the daughter isotope. This presents a unique signature to allow the deconvolution of isotopes that possess overlapping alpha particle energy. The work presented here are results of conversion electron spectroscopy of 241Am, 238Pu and 239Pu using a dual-stage peltier-cooled 25 mm2 silicon drift detector. A passivated ion implanted planar silicon detector provided measurements of alpha spectroscopy. The conversion electron spectra were evaluated from 20–55 keV based on fits to the dominant conversion electron emissions, which allowed the relative conversion electron emission intensities to be determined. These measurements provide crucial singles spectral information to aid in the coincident measurement approach.

Uranium analysis in Cypriot groundwaters by total alpha-radiometry and alpha-spectroscopy

International Nuclear Information System (INIS)

Efstathiou, Maria; Kiliari, Tasoula; Pashalidis, Ioannis

2011-01-01

Two different alpha-radiometric methods (e.g. alpha-spectroscopy and alpha-particle counting) have been applied to the determination of uranium in Cypriot groundwater samples after separation of the radionuclides by cation exchange using Chelex-100 and its electrodeposition on stainless steel planchettes. The data obtained were compared to show the advantages and disadvantages of the two radiometric methods, determine the alpha-radioactivity concentration and the radiation dose associated with the use of the studied groundwaters. Calibration of the methods was performed by means of uranium standard solutions and the corresponding data were used to evaluate linear range, detector efficiency, detection limits, value of the information obtained, and time of analysis of the methods. Comparison of the data obtained from calibration and natural sample measurements has shown that alpha-particle counting with a simple alpha-radiometer (equipped with a semiconductor detector) may offer only an activity value and not detailed information about the isotopic composition but it is the fastest method and the method of choice if only a screening method for the alpha-radioactivity measurement is required. Based on the alpha-radioactivity data, the corresponding radiation dose was estimated for situations where the groundwaters are used for drinking water purposes.

Radioactivity Measurements on Glazed Ceramic Surfaces.

Science.gov (United States)

Hobbs, T G

2000-01-01

A variety of commonly available household and industrial ceramic items and some specialty glass materials were assayed by alpha pulse counting and ion chamber voltage measurements for radioactivity concentrations. Identification of radionuclides in some of the items was performed by gamma spectroscopy. The samples included tableware, construction tiles and decorative tiles, figurines, and other products with a clay based composition. The concentrations of radioactivity ranged from near background to about four orders of magnitude higher. Almost every nuclide identification test demonstrated some radioactivity content from one or more of the naturally occurring radionuclide series of thorium or uranium. The glazes seemed to contribute most of the activity, although a sample of unglazed pottery greenware showed some activity. Samples of glazing paints and samples of deliberately doped glass from the World War II era were included in the test, as was a section of foam filled poster board. A glass disc with known (232)Th radioactivity concentration was cast for use as a calibration source. The results from the two assay methods are compared, and a projection of sensitivity from larger electret ion chamber devices is presented.

Alpha-particle autoradiography by solid state track detectors to spatial distribution of radioactivity in alpha-counting source

International Nuclear Information System (INIS)

Ishigure, Nobuhito; Nakano, Takashi; Enomoto, Hiroko; Koizumi, Akira; Miyamoto, Katsuhiro

1989-01-01

A technique of autoradiography using solid state track detectors is described by which spatial distribution of radioactivity in an alpha-counting source can easily be visualized. As solid state track detectors, polymer of allyl diglycol carbonate was used. The advantage of the present technique was proved that alpha-emitters can be handled in the light place alone through the whole course of autoradiography, otherwise in the conventional autoradiography the alpha-emitters, which requires special carefulness from the point of radiation protection, must be handled in the dark place with difficulty. This technique was applied to rough examination of self-absorption of the plutonium source prepared by the following different methods; the source (A) was prepared by drying at room temperature, (B) by drying under an infrared lamp, (C) by drying in ammonia atmosphere after redissolving by the addition of a drop of distilled water which followed complete evaporation under an infrared lamp and (D) by drying under an infrared lamp after adding a drop of diluted neutral detergent. The difference in the spatial distributions of radioactivity could clearly be observed on the autoradiographs. For example, the source (C) showed the most diffuse distribution, which suggested that the self-absorption of this source was the smallest. The present autoradiographic observation was in accordance with the result of the alpha-spectrometry with a silicon surface-barrier detector. (author)

Water quality - Measurement of gross alpha activity in non-saline water - Thick source method. 2. ed.

International Nuclear Information System (INIS)

2007-01-01

This International Standard specifies a method for the determination of gross alpha activity in non-saline waters for alpha-emitting radionuclides which are not volatile at 350 degree Centigrade. It is possible to determine supported volatile radionuclides measured to an extent determined by half-life, matrix retention (of the volatile species) and the duration of measurement (counting time). The method is applicable to raw and potable waters. The range of application depends on the amount of suspended matter in the water and on the performance characteristics (background count rate and counting efficiency) of the counter. Gross alpha radioactivity is determined by using proportional counting or solid scintillation counting on water residue deposited on a planchet. Due to the strong absorption of the residue deposit, it is considered that the alpha emission from the surface is proportional to the alpha activity of the deposit. Gross alpha determination is not an absolute determination of the sample alpha radioactive content, but a relative determination referring to a specific alpha emitter which constitutes the standard calibration source. This type of determination is also known as alpha index. The sample is acidified to stabilize it, evaporated almost to dryness, converted to the sulfate form and then ignited at 350 degree Centigrade. A portion of the residue is transferred to a planchet and the alpha activity measured by counting in an alpha-particle detector or counting system previously calibrated against an alpha-emitting standard and the alpha activity concentration calculated. The paper provides information about scope, normative references, symbols, definitions and units, principle, reagents and equipment, procedure, contamination check, expression of results and test report

Radioactive Mapping Contaminant of Alpha on The Air in Space of Repair of Hot Cell and Medium Radioactivity Laboratory in Radio metallurgy Installation

International Nuclear Information System (INIS)

Yusuf-Nampira; Endang-Sukesi; S-Wahyuningsih; R-Budi-Santoso

2007-01-01

Hot cell and space of acid laboratory medium activity in Radio metallurgy Installation are used for the examination preparation of fuel nuclear post irradiation. The sample examined is dangerous radioactive material representing which can disseminate passing air stream. The dangerous material spreading can be pursued by arranging air stream from laboratory space to examination space. To know the performance the air stream arrangement is hence conducted by radioactive mapping contaminant of alpha in laboratory / space of activity place, for example, medium activity laboratory and repair space. This mapping radioactivity contaminant is executed with the measurement level of the radioactivity from sample air taken at various height with the distance of 1 m, various distance and from potential source as contaminant spreading access. The mapping result indicate that a little spreading of radioactive material happened from acid cupboard locker to laboratory activity up to distance of 3 m from acid cupboard locker and spreading of radioactive contaminant from goods access door of the hot cell 104 to repair space reach the distance of 2 m from goods door access. Level of the radioactive contamination in the space was far under maximum limitation allowed (20 Bq / m 3 ). (author)

Concentration of Uranium Radioisotopes in Albanian Drinking Waters Measured by Alpha Spectrometry

Science.gov (United States)

Bylyku, Elida; Cfarku, Florinda; Deda, Antoneta; Bode, Kozeta; Fishka, Kujtim

2010-01-01

Uranium is a radioactive material that is frequently found in rocks and soil. When uranium decays, it changes into different elements that are also radioactive, including radon, a gas that is known to cause a lung cancer. The main concern with uranium in drinking water is harm to the kidneys. Public water systems are required to keep uranium levels at or below 500 mBq per liter to protect against kidney damage. Such an interest is needed due to safety, regulatory compliance and disposal issue for uranium in the environment since uranium is included as an obligatory controlled radionuclide in the European Legislation (Directive 98/83 CE of Council of 03.11.1998). The aim of this work is to measure the levels of uranium in drinking and drilled well waters in Albania. At first each sample was measured for total Alpha and total Beta activity. The samples with the highest levels of total alpha activity were chosen for the determination of uranium radioisotopes by alpha spectrometry. A radiochemical procedure using extraction with TBP (Tri-Butyl-Phosphate) is used in the presence of U232 as a yield tracer. Thin sources for alpha spectrometry are prepared by electrodepositing on to stainless steel discs. The results of the U238 activity measured in the different samples, depending from their geological origin range between 0.55-13.87 mBq/l. All samples measured results under the European Directive limits for U238 (5-500 mBq/1), Dose Coefficients according to Directive 96/29 EURATOM.

Measurement of gross alpha and gross beta activity concentrations in human tooth

International Nuclear Information System (INIS)

Soeguet, Omer; Aydin, Mehmet Fatih; Kuecuekoender, Erdal; Zorer, Ozlem Selcuk; Dogru, Mahmut

2010-01-01

The gross alpha and gross beta activity concentrations were measured in human tooth taken from 3 to 6 age-groups to 40 and over ones. Accumulated teeth samples are investigated in two groups as under and above 18 years. The gross alpha and beta radioactivity of human tooth samples was measured by using a gas-flow proportional counter (PIC-MPC 9604-α/β counter). In tooth samples, for female age-groups, the obtained results show that the mean gross alpha and gross beta activity concentrations varied between 0.534-0.203 and 0.010-0.453 Bq g -1 and the same concentrations for male age-groups varied between 0.009-1.168 and 0.071-0.204 Bq g -1 , respectively.

Measurement of fertilizers induced radioactivity in tobacco plants and elemental analysis using ICAP–AES

International Nuclear Information System (INIS)

Chauhan, Pooja; Chauhan, R.P.

2014-01-01

It is widely accepted that tobacco smoke is the leading cause of lung cancer worldwide. The alpha radioactive content present in tobacco smoke and increasing number of lung cancer cases explain the importance of investigation. The use of different fertilizers may cause alteration in the metabolism of plants causing different response towards uptake of different element and radionuclides. In the present study, the estimation of alpha radioactivity induced by use of different fertilizers in tobacco leaves was made using solid state nuclear track detector (LR-115) to identify the relative presence of radionuclides in the plants. The radon exhalation rates from the tobacco plant were carried out to confirm the presence of radium or emission of radon from plant. The elemental analysis of tobacco plant by inductively coupled argon plasma atomic emission spectrometry provides a way to understand the difference occurred in metabolism caused by the use of fertilizers. The alpha track densities were found to vary with nature of fertilizers added to the soil and an increase was also observed with time. The radon mass exhalation rates in various tobacco plants were found to vary with type of fertilizers used. - Highlights: • The study is related to alpha radioactivity measurements in tobacco plants. • The radon mass exhalation rates in various tobacco plants were also measured. • Study is related to analysis of chemical elements in different fertilized tobacco samples

Methods and Data Used to Investigate Polonium-210 as a Source of Excess Gross-Alpha Radioactivity in Ground Water, Churchill County, Nevada

Science.gov (United States)

Seiler, Ralph L.

2007-01-01

Ground water is the major source of drinking water in the Carson River Basin, California and Nevada. Previous studies have shown that uranium and gross-alpha radioactivities in ground water can be greater than U.S. Environmental Protection Agency Maximum Contaminant Levels, particularly in the Carson Desert, Churchill County, Nevada. Studies also have shown that the primary source of the gross-alpha radioactivity and alpha-emitting radionuclides in ground water is the dissolution of uranium-rich granitic rocks and basin-fill sediments that have their origins in the Sierra Nevada. However, ground water sampled from some wells in the Carson Desert had gross-alpha radioactivities greater than could be accounted for by the decay of dissolved uranium. The occurrence of polonium-210 (Po-210) was hypothesized to explain the higher than expected gross-alpha radioactivities. This report documents and describes the study design, field and analytical methods, and data used to determine whether Po-210 is the source of excess gross-alpha radioactivity in ground water underlying the Carson Desert in and around Fallon, Nevada. Specifically, this report presents: 1) gross alpha and uranium radioactivities for 100 wells sampled from June to September 2001; and 2) pH, dissolved oxygen, specific conductance, and Po-210 radioactivity for 25 wells sampled in April and June 2007. Results of quality-control samples for the 2007 dataset are also presented.

Note: Real time optical sensing of alpha-radiation emitting radioactive aerosols based on solid state nuclear track detector

International Nuclear Information System (INIS)

Kulkarni, A.; Bak, M. S.; Ha, S.; Joshirao, P.; Manchanda, V.; Kim, T.

2015-01-01

A sensitive radioactive aerosols sensor has been designed and developed. Its design guidance is based on the need for a low operational cost and reliable measurements to provide daily aerosol monitoring. The exposure of diethylene-glycol bis (allylcarbonate) to radiation causes modification of its physico-chemical properties like surface roughness and reflectance. In the present study, optical sensor based on the reflectance measurement has been developed with an aim to monitor real time presence of alpha radioactive aerosols emitted from thorium nitrate hydrate. The results shows that the fabricated sensor can detect 0.0157 kBq to 0.1572 kBq of radio activity by radioactive aerosols generated from (Th(NO 3 ) 4 ⋅ 5H 2 O) at 0.1 ml/min flow rate. The proposed instrument will be helpful to monitor radioactive aerosols in/around a nuclear facility, building construction sites, mines, and granite polishing factories

Note: Real time optical sensing of alpha-radiation emitting radioactive aerosols based on solid state nuclear track detector

Science.gov (United States)

Kulkarni, A.; Ha, S.; Joshirao, P.; Manchanda, V.; Bak, M. S.; Kim, T.

2015-06-01

A sensitive radioactive aerosols sensor has been designed and developed. Its design guidance is based on the need for a low operational cost and reliable measurements to provide daily aerosol monitoring. The exposure of diethylene-glycol bis (allylcarbonate) to radiation causes modification of its physico-chemical properties like surface roughness and reflectance. In the present study, optical sensor based on the reflectance measurement has been developed with an aim to monitor real time presence of alpha radioactive aerosols emitted from thorium nitrate hydrate. The results shows that the fabricated sensor can detect 0.0157 kBq to 0.1572 kBq of radio activity by radioactive aerosols generated from (Th(NO3)4 ṡ 5H2O) at 0.1 ml/min flow rate. The proposed instrument will be helpful to monitor radioactive aerosols in/around a nuclear facility, building construction sites, mines, and granite polishing factories.

Note: Real time optical sensing of alpha-radiation emitting radioactive aerosols based on solid state nuclear track detector

Energy Technology Data Exchange (ETDEWEB)

Kulkarni, A.; Bak, M. S., E-mail: tkim@skku.edu, E-mail: moonsoo@skku.edu [School of Mechanical Engineering, Sungkyunkwan University, Suwon 440-746 (Korea, Republic of); Ha, S. [SKKU Advanced Institute of Nano Technology (SAINT), Sungkyunkwan University, Suwon 440-746 (Korea, Republic of); Joshirao, P.; Manchanda, V. [Department of Energy Science, Sungkyunkwan University, Suwon 440-746 (Korea, Republic of); Kim, T., E-mail: tkim@skku.edu, E-mail: moonsoo@skku.edu [School of Mechanical Engineering, Sungkyunkwan University, Suwon 440-746 (Korea, Republic of); SKKU Advanced Institute of Nano Technology (SAINT), Sungkyunkwan University, Suwon 440-746 (Korea, Republic of)

2015-06-15

A sensitive radioactive aerosols sensor has been designed and developed. Its design guidance is based on the need for a low operational cost and reliable measurements to provide daily aerosol monitoring. The exposure of diethylene-glycol bis (allylcarbonate) to radiation causes modification of its physico-chemical properties like surface roughness and reflectance. In the present study, optical sensor based on the reflectance measurement has been developed with an aim to monitor real time presence of alpha radioactive aerosols emitted from thorium nitrate hydrate. The results shows that the fabricated sensor can detect 0.0157 kBq to 0.1572 kBq of radio activity by radioactive aerosols generated from (Th(NO{sub 3}){sub 4} ⋅ 5H{sub 2}O) at 0.1 ml/min flow rate. The proposed instrument will be helpful to monitor radioactive aerosols in/around a nuclear facility, building construction sites, mines, and granite polishing factories.

Determining the level of gross alpha and beta radioactivity of water from Marilao river using liquid scintillation counter

International Nuclear Information System (INIS)

Cruz, J.; Magtaka, J.; Balisi, R.; Castaneda, Soledad; De Vero, J.

2009-01-01

This study aims to determine the level of gross alpha- and beta- radioactivity present in the Marilao River. Liquid Scintillation Counter was used to detect samples radioactivity. Water samples were taken along the different spots of Marilao River. The results showed that the radioactivity are below the Philippine National Standard for Drinking Water (PNSDW) which is 0.1 Bq/L for gross alpha activity and 1.0 Bq/L for gross beta activity set by the Dept. of Health. Hence water samples from Marilao River, is safe in terms of the level of radioactivity levels.(author)

Status of foreign practices for the management of alpha-contaminated radioactive wastes

International Nuclear Information System (INIS)

Lakey, L.T.

1982-08-01

Alpha-contaminated radioactive wastes, a product of mixed-oxide fuel fabrication, fuel reprocessing, weapons production and decommissioning programs, are being generated in at least ten countries. There is general agreement worldwide that these wastes should be treated differently than the beta-gamma or low-level waste. There is no consensus, however, on a quantitative definition of alpha-contaminated wastes. Reported definitions vary from > 0.035 nCi/g to > 100 nCi/g. Incineration is the most common treatment, with cement and bitumen the most common fixation agents. The only disposal means in use today are the sea dumping practice by Belgium and the United Kingdom and the surface disposal and deep-well discharge by the USSR. Sea dumping, however, is restricted to low levels of alpha activity, while the USSR appears to be favoring geologic disposal. All countries appear to be moving toward deep geologic repositories as the favored means of disposing of alpha-contaminated radioactive wastes. West Germany has actually disposed of such wastes in the Asse Salt Mine but has discontinued that operation for political reasons. Repository projects are actively under way in Belgium, West Germany, India, Sweden, and the Unted States, with many other countries planning repository programs. One US project, the Waste Isolation Pilot Plant, will, according to present schedules, be the first repository operational since Asse. 6 tables

Measurement of natural radioactivity in chemical fertilizer and agricultural soil: evidence of high alpha activity.

Science.gov (United States)

Ghosh, Dipak; Deb, Argha; Bera, Sukumar; Sengupta, Rosalima; Patra, Kanchan Kumar

2008-02-01

People are exposed to ionizing radiation from the radionuclides that are present in different types of natural sources, of which phosphate fertilizer is one of the most important sources. Radionuclides in phosphate fertilizer belonging to 232Th and 238U series as well as radioisotope of potassium (40K) are the major contributors of outdoor terrestrial natural radiation. The study of alpha activity in fertilizers, which is the first ever in West Bengal, has been performed in order to determine the effect of the use of phosphate fertilizers on human health. The data have been compared with the alpha activity of different types of chemical fertilizers. The measurement of alpha activity in surface soil samples collected from the cultivated land was also performed. The sampling sites were randomly selected in the cultivated land in the Midnapore district, which is the largest district in West Bengal. The phosphate fertilizer is widely used for large agricultural production, mainly potatoes. The alpha activities have been measured using solid-state nuclear track detectors (SSNTD), a very sensitive detector for alpha particles. The results show that alpha activity of those fertilizer and soil samples varies from 141 Bq/kg to 2,589 Bq/kg and from 109 Bq/kg to 660 Bq/kg, respectively. These results were used to estimate environmental radiation exposure on human health contributed by the direct application of fertilizers.

Evaluation of gross radioactivity in foodstuffs

International Nuclear Information System (INIS)

Zorer, Oezlem Selcuk; Oeter, Cigdem

2015-01-01

The paper presents the results of radiological investigations of food products sampled in the summer and fall of 2011 and 2012 in different parts of Van, Turkey. Gross radioactivity measurements in food products were evaluated. Food items were divided into eight groups: (1) water, (2) fish, (3) cheese products, (4) fruits, (5) vegetables, (6) herbs, (7) walnut and (8) rock salt. The levels of the gross alpha and gross beta radioactivity in all food samples varied widely ranging from 0.070 to 10.885 Bq/g and from 0.132 to 48.285 Bq/g on dry mass basis, respectively. In one sample, gross alpha and gross beta activity concentrations were found to be relatively high according to the other samples and in all samples, the gross alpha radioactivity was measured lower than the gross beta radioactivity. The gross α and gross β activities were measured by using α/β counter of the multi-detector low background system (PIC MPC-9604).

Evaluation of gross radioactivity in foodstuffs

Energy Technology Data Exchange (ETDEWEB)

Zorer, Oezlem Selcuk; Oeter, Cigdem [Yuzuncu Yil Univ., Van (Turkey). Dept. of Chemistry

2015-05-15

The paper presents the results of radiological investigations of food products sampled in the summer and fall of 2011 and 2012 in different parts of Van, Turkey. Gross radioactivity measurements in food products were evaluated. Food items were divided into eight groups: (1) water, (2) fish, (3) cheese products, (4) fruits, (5) vegetables, (6) herbs, (7) walnut and (8) rock salt. The levels of the gross alpha and gross beta radioactivity in all food samples varied widely ranging from 0.070 to 10.885 Bq/g and from 0.132 to 48.285 Bq/g on dry mass basis, respectively. In one sample, gross alpha and gross beta activity concentrations were found to be relatively high according to the other samples and in all samples, the gross alpha radioactivity was measured lower than the gross beta radioactivity. The gross α and gross β activities were measured by using α/β counter of the multi-detector low background system (PIC MPC-9604).

Measurement of residual radioactive surface contamination by 2-D laser heated TLD

International Nuclear Information System (INIS)

Jones, S.C.

1997-06-01

The feasibility of applying and adapting a two-dimensional laser heated thermoluminescence dosimetry system to the problem of surveying for radioactive surface contamination was studied. The system consists of a CO 2 laser-based reader and monolithic arrays of thin dosimeter elements. The arrays consist of 10,201 thermoluminescent phosphor elements of 40 micron thickness, covering a 900 cm 2 area. Array substrates are 125 micron thick polyimide sheets, enabling them to easily conform to regular surface shapes, especially for survey of surfaces that are inaccessible for standard survey instruments. The passive, integrating radiation detectors are sensitive to alpha and beta radiation at contamination levels below release guideline limits. Required contact times with potentially contaminated surfaces are under one hour to achieve detection of transuranic alpha emission at 100 dpm/100 cm 2 . Positional information obtained from array evaluation is useful for locating contamination zones. Unique capabilities of this system for survey of sites, facilities and material include measurement inside pipes and other geometrical configurations that prevent standard surveys, and below-surface measurement of alpha and beta emitters in contaminated soils. These applications imply a reduction of material that must be classified as radioactive waste by virtue of its possibility of contamination, and cost savings in soil sampling at contaminated sites

Effects of natural radioactivity on food radioactivity measurement

International Nuclear Information System (INIS)

Ennyu, Atsuhito

2012-01-01

Since the accident of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Company, groups and individuals including local governments, food manufacturers, distribution circles, retail circles, and citizens are eager to measure the radioactivity of food, in order to confirm the safety of food from the concerns about radioactive contamination. The measurement of radioactivity of food is done by quantitatively determining gamma rays due to radioactive cesium that was incorporated into the biosphere cycle after having been released into the environment. As for the radioactivity measurement of food using gamma-ray spectrometry with a potassium iodide scintillation detector, which is very commonly used, this paper describes the handling method of obtained data, the principle of erroneous detection of radioactive cesium and iodine interrupted by natural radionuclides, and countermeasures for it. Major natural radioactivity sources are uranium series and thorium series. This paper explains gamma rays, which are characteristic in the decay process of uranium series and often affect the measurement of radioactive cesium in food and water. (O.A.)

Application of Micro-coprecipitation Method to Alpha Source Preparation for Measuring Alpha Nuclides

International Nuclear Information System (INIS)

Lee, Myung Ho; Park, Jong Ho; Oh, Se Jin; Song, Byung Chul; Song, Kyuseok

2011-01-01

Among the source preparations, an electrodeposition is a commonly used method for the preparation of sources for an alpha spectrometry, because this technique is simple and produces a very thin deposit, which is essential for a high resolution of the alpha peak. Recently, micro-coprecipitation with rare earths have been used to yield sources for -spectrometry. In this work, the Pu, Am and Cm isotopes were purified from hindrance nuclides and elements with an a TRU resin in radioactive waste samples, and the activity concentrations of the Pu, Am and Cm isotopes were determined by radiation counting methods after alpha source preparation like micro coprecipitation. After the Pu isotopes in the radioactive waste samples were separated from the other nuclides with an anion exchange resin, the Am isotopes were purified with a TRU resin and an anion exchange resin or a TRU resin. Activity concentrations and chemical recoveries of 241 Am purified with the TRU resin were similar to those with the TRU resin and anion exchange resin. In this study, to save on the analytical time and cost, the Am isotopes were purified with the TRU resin without using an additional anion exchange resin. After comparing the electrodeposition method with the micro-coprecipitation method, the micro-coprecipitation method was used for the alpha source preparation, because the micro-coprecipitation method is simple and more reliable for source preparation of the Pu, Am and Cm isotopes

Calibration techniques for the in vivo measurement of alpha-emitting actinides

International Nuclear Information System (INIS)

Fleming, R.R.

1976-01-01

Reliable interpretation of in vivo measurements for alpha-emitting actinides deposited in the lungs is largely dependent on three factors: correction of observed count rates for background contributions; correction for photon absorption in the body; and accurate calibration of the counting system. Terrestrial and cosmic radiation contributions can be minimized by extensive shielding and good pulse-shape discrimination. Techniques are available to minimize errors inherent in the calibration of an in vivo counting system. Minimum amounts of alpha-emitting actinides detectable in the lungs are primarily affected by the accuracy of two factors: predicted body background due to 137 Cs and 40 K, and estimated photon absorption in chest-wall tissue. A matched pair of 12.5-cm-dia phoswich detectors, purchased from the Harshaw Chemical Company, are used to measure low-energy photons emitted by the radioactive actinides

Development of a combination detector system for simultaneous measurement of Alpha and Beta/Gamma radioactivity

International Nuclear Information System (INIS)

Thakur, Vaishali M.; Ashokkumar, P.; Rekha, A.K.; Jain, Amit; Rath, D.P.; Chaudhury, Probal; Chaudhari, L.M.

2018-01-01

Analysis of various samples for α and β/γ radioactivity is carried out in radiological laboratories. Using independent α and β/γ counting systems such measurements are done separately for same sample. In order to address the requirement of simultaneous measurement of α and β/γ activity content of radioactive samples, a counting system using combination of two detectors has been developed. Activity deposited on a 2 mm deep 30 mm diameter aluminum planchette was counted under the detector combination consisting of a ZnS(Ag) and plastic scintillator for α and β/γ respectively. The design and fabrication of the combination detector, development of electronics associated with the system, its characterization and application are presented here

Alpha emitters activity measurement using the defined solid angle method

International Nuclear Information System (INIS)

Blanchis, P.

1983-01-01

The defined solid angle counting method can reach a very high accuracy, specially for heavy ions as alpha particles emitted by a radioactive source. The activity measurement of such sources with a relative uncertainty of the order of 0.01% is investigated. Such an accuracy is available only under suitable conditions: the radiation emitted by the source must be isotropic and all the particles emitted in the effective solid angle must be detected. The efficiency detection value must be equal to unity and phenomena such as absorption or scattering must be null. It is shown that corrections often become necessary. All parameters which can influence the measurements are studied [fr

Environmental radioactivity. Measurement and monitoring

International Nuclear Information System (INIS)

2009-11-01

The contribution on environmental radioactivity covers the following issues: natural and artificial radioactivity; continuous monitoring of radioactivity; monitoring authorities and measurement; radioactivity in the living environment; radioactivity in food and feeding stuff; radioactivity of game meat and wild-growing mushrooms; radioactivity in mines; radioactivity in the research center Rossendorf.

Preliminary results of natural radioactivity measurements in the southern part of Ethiopia

International Nuclear Information System (INIS)

Wollel Tiruneh, Getachew; Wodaje Kebede, Worku

2008-01-01

The paper presents the first results of natural radioactivity measurements in the Southern part of Ethiopia (Bale Zone-Oromiya Regional State). The preliminary results indicate that radiation levels in the mining areas of Kallido Mountain are elevated compared with those in the town of Negele Borena (background area). Both external gamma radiation and alpha surface contamination levels are significantly elevated above local background levels

Preliminary results of natural radioactivity measurements in the southern part of Ethiopia

Energy Technology Data Exchange (ETDEWEB)

Wollel Tiruneh, Getachew [Ethiopian Radiation Protection Authority, PO Box 20486 code 1000, Addis-Ababa (Ethiopia)], E-mail: gwollel@yahoo.com; Wodaje Kebede, Worku [Ethiopian Radiation Protection Authority, PO Box 20486 code 1000, Addis-Ababa (Ethiopia)

2008-11-15

The paper presents the first results of natural radioactivity measurements in the Southern part of Ethiopia (Bale Zone-Oromiya Regional State). The preliminary results indicate that radiation levels in the mining areas of Kallido Mountain are elevated compared with those in the town of Negele Borena (background area). Both external gamma radiation and alpha surface contamination levels are significantly elevated above local background levels.

Gross alpha and beta activity analyses in urine-a routine laboratory method for internal human radioactivity detection.

Science.gov (United States)

Chen, Xiaowen; Zhao, Luqian; Qin, Hongran; Zhao, Meijia; Zhou, Yirui; Yang, Shuqiang; Su, Xu; Xu, Xiaohua

2014-05-01

The aim of this work was to develop a method to provide rapid results for humans with internal radioactive contamination. The authors hypothesized that valuable information could be obtained from gas proportional counter techniques by screening urine samples from potentially exposed individuals rapidly. Recommended gross alpha and beta activity screening methods generally employ gas proportional counting techniques. Based on International Standards Organization (ISO) methods, improvements were made in the evaporation process to develop a method to provide rapid results, adequate sensitivity, and minimum sample preparation and operator intervention for humans with internal radioactive contamination. The method described by an American National Standards Institute publication was used to calibrate the gas proportional counter, and urine samples from patients with or without radionuclide treatment were measured to validate the method. By improving the evaporation process, the time required to perform the assay was reduced dramatically. Compared with the reference data, the results of the validation samples were very satisfactory with respect to gross-alpha and gross-beta activities. The gas flow proportional counting method described here has the potential for radioactivity monitoring in the body. This method was easy, efficient, and fast, and its application is of great utility in determining whether a sample should be analyzed by a more complicated method, for example radiochemical and/or γ-spectroscopy. In the future, it may be used commonly in medical examination and nuclear emergency treatment.Health Phys. 106(5):000-000; 2014.

Determination of total alpha activity index in samples of radioactive wastes

International Nuclear Information System (INIS)

Galicia C, F. J.

2015-01-01

This study aimed to develop a methodology of preparation and quantification of samples containing radionuclides beta and/or alpha emitters, to determine the rates of alpha and beta total activity of radioactive waste samples. For this, a device of planchettes preparer was designed, to assist the planchettes preparation in a controlled environment and free of corrosive vapors. Planchettes were prepared in three means: nitrate, carbonate and sulfate, to different mass thickness, natural uranium (alpha and beta emitter) and in case of Sr-90 (beta emitter pure) only in half nitrate; and these planchettes were quantified in an alpha/beta counter, in order to construct the self-absorption curves for alpha and beta particles. These curves are necessary to determine the rate of alpha-beta activity of any sample because they provide the self-absorption correction factor to be applied in calculating the index. Samples with U were prepared with the help of the device of planchettes preparer and subsequently were analyzed in the proportional counter Mpc-100 Pic brand. Samples with Sr-90 were prepared without the device to see if there was a different behavior with respect to obtaining mass thickness. Similarly they were calcined and carried out count in the Mpc-100. To perform the count, first the parameters of counter operating were determined: operating voltages for alpha and beta particles 630 and 1500 V respectively, a count routine was generated where the time and count type were adjusted, and counting efficiencies for alpha and beta particles, with the aid of calibration sources of 210 Po for alphas and 90 Sr for betas. According to the results, the counts per minute will decrease as increasing the mass thickness of the sample (self-absorption curve), adjusting this behavior to an exponential function in all cases studied. The minor self-absorption of alpha and beta particles in the case of U was obtained in sulfate medium. The self-absorption curves of Sr-90 follow the

Radioactivity measurement

International Nuclear Information System (INIS)

Bohme, R.F.; Lazerson, M.M.

1984-01-01

A problem with ore sorting arrangements is that radiation is difficult to measure accurately while particles are moving at speed past the detector. This is particulary so when dealing with ores such as gold ores which have weak emissions. A method of measuring radioactive emissions from moving radioactive material includes the steps of shielding the radiation detector(s) so that the angle of acceptance of the receptor surface is restricted, and further shielding the shielded portion of the detector with a second material which is less radiation emissive than the material of the first shield. This second shield is between the first shield and the detector

Measurement of liquid radioactive materials for monitoring radioactive emissions

International Nuclear Information System (INIS)

1977-10-01

This draft regulation applies to measuring equipment for liquid radioactive materials for the monitoring of the radioactive discharges from stationary nuclear power plants with LWR and HTR reactors. Demands made on the measuring procedure, methods of concentration determination, balancing, indication of limiting values, and inspections are layed down. The draft regulation deals with: 1) Monitoring liquid radioactive discharges: Water and similar systems; radionuclides and their detection limits, radioactively contaminated water (waste water); secondary cooling water; power house cooling water; primary cooling water; flooding water; 2) Layout of the measuring and sampling equipment and demands made on continuous and discontinuous measuring equipment; demands made on discontinuous α and β measuring equipment; 3) Maintenance and repair work; inspections; repair of defects; 4) Demands made on documentation; reports to authorities; 5) Supplement: List of general and reference regulations. (orig./HP) [de

Determination of the concentration of {alpha} emitting radioactive aerosols; Mesure de la concentration des aerosols radioactifs emetteurs {alpha}

Energy Technology Data Exchange (ETDEWEB)

Labeyrie, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1953-06-15

In the first part of this work the techniques used for the quantitative measurement of the concentrations of aerosols carrying short lived (radon or thoron daughters) or long lived (uranium) {alpha} radioactive emitters are described. In the second part the author investigates the problem of the determination of radon concentration in air by means of activity determinations on airborne dusts. Special reference is made to the measurement of the radon active deposit on two types of dusts (iron oxide (yellow) and uranium oxide) in small chambers (6 liters). In the third part are given data resulting from determinations of radon and thoron concentrations in atmospheric air in the south of Paris area using this method. (author) [French] Dans la premiere partie de ce travail on expose les techniques utilisees pour la mesure quantitative des concentrations d'aerosols contenant des emetteurs radioactifs {alpha}, tant pour ceux a vie courte (derives du radon ou du thoron) que pour ceux a vie longue (uranium). Dans la seconde partie on traite le probleme de la determination de la concentration de l'air en radon par la mesure de l'activite des poussieres ayant sejourne dans cet air. En particulier, on indique pour de petits volumes (6 litres) la proportion de depot actif du radon qui est fixee sur deux types de poussieres (limonite et oxyde d'uranium) en fonction de la concentration de celles-ci. Dans la troisieme partie on donne quelques exemples de mesure par cette methode de la concentration en radon et en thoron de l'atmosphere de la region parisienne. (auteur)

Workshop on Precision Measurements of $\\alpha_s$

Energy Technology Data Exchange (ETDEWEB)

Bethke, Siegfried; /Munich, Max Planck Inst.; Hoang, Andre H.; /Vienna U.; Kluth, Stefan; /Munich, Max Planck Inst.; Schieck, Jochen; /Munich U.; Stewart, Iain W.; Aoki, S.; Beneke, M.; Bethke, S.; Blumlein, J.; Brambilla, N.; Brodsky, S.; /MIT, LNS

2011-10-01

These are the proceedings of the Workshop on Precision Measurements of {alpha}{sub s} held at the Max-Planck-Institute for Physics, Munich, February 9-11, 2011. The workshop explored in depth the determination of {alpha}{sub s}(m{sub Z}) in the {ovr MS} scheme from the key categories where high precision measurements are currently being made, including DIS and global PDF fits, {tau}-decays, electro-weak precision observables and Z-decays, event-shapes, and lattice QCD. These proceedings contain a short summary contribution from the speakers, as well as the lists of authors, conveners, participants, and talks.

Radioactivity in food crops

International Nuclear Information System (INIS)

Drury, J.S.; Baldauf, M.F.; Daniel, E.W.; Fore, C.S.; Uziel, M.S.

1983-05-01

Published levels of radioactivity in food crops from 21 countries and 4 island chains of Oceania are listed. The tabulation includes more than 3000 examples of 100 different crops. Data are arranged alphabetically by food crop and geographical origin. The sampling date, nuclide measured, mean radioactivity, range of radioactivities, sample basis, number of samples analyzed, and bibliographic citation are given for each entry, when available. Analyses were reported most frequently for 137 Cs, 40 K, 90 Sr, 226 Ra, 228 Ra, plutonium, uranium, total alpha, and total beta, but a few authors also reported data for 241 Am, 7 Be, 60 Co, 55 Fe, 3 H, 131 I, 54 Mn, 95 Nb, 210 Pb, 210 Po, 106 Ru, 125 Sb, 228 Th, 232 Th, and 95 Zr. Based on the reported data it appears that radioactivity from alpha emitters in food crops is usually low, on the order of 0.1 Bq.g -1 (wet weight) or less. Reported values of beta radiation in a given crop generally appear to be several orders of magnitude greater than those of alpha emitters. The most striking aspect of the data is the great range of radioactivity reported for a given nuclide in similar food crops with different geographical origins

Suma-alpha software description. Study of its applications to detection problems and environmental radioactivity measurements

International Nuclear Information System (INIS)

Gasco, C.; Perez, C.

2010-01-01

Software named suma-espectros has been developed by TECNASA/CIEMAT for adding counts automatically from the alpha spectra, energy to energy, with the purpose of: evaluating real background of alpha spectrometers, studying its temporal variations, increasing the possibilities of isotopes detection -where it has been impossible to detect due elapsed time of the measurement- and implementing other applications. The programme is written in Visual-Basic and it can export data to Excel spreadsheets for later treatment. The software has established by default a channels range for adding the counts energy by energy but it can be adapted to the analysis of different isotopes and backgrounds simply changing a text file that is incorporated to the programme. The description of the programme management is described for whoever can realise its applications immediately. This software has the advantage of emitting an add-spectrum in cnf format that is used by alpha analyst (Genie 2K) for de convoluting spectra or doing calculations. (Author) 3 refs.

Research on the reliability of measurement of natural radioactive nuclide concentration of U-238

Energy Technology Data Exchange (ETDEWEB)

Cha, Seok Ki; Kim, Gee Hyun [Dept. of Nuclear engineering, Univ. of SeJong, Seoul (Korea, Republic of); Joo, Sun Dong; Lee, Hoon [KoFONS, Seongnam (Korea, Republic of)

2016-12-15

Naturally occurred radioactive materials (NORM) can be found all around us and people are exposed to this no matter what they do or where they live. In this study, two indirect measurement methods of NORM U-238 has been reviewed; one that has used HPGe on the basis of the maintenance, and the other is disequilibrium theory of radioactive equilibrium relationships of mother and daughter nuclide at Decay-chain of NORM U-238. For this review, complicated pre-processing process (Breaking->Fusion->Chromatography->Electron deposit) has been used , and then carried out a comparative research with direct measurement method that makes use of and measures Alpha spectrometer. Through the experiment as above, we could infer the daughter nuclide whose radioactive equilibrium has been maintained with U-238. Therefore, we could find out that the daughter nuclide suitable to be applied to Gamma indirect measurement method was Th-234. Due to Pearson Correlation statistics, we could find out the reliability of the result value that has been analyzed by using Th-234.

Radioactivity measurement in spring waters of Cantabria, Spain

International Nuclear Information System (INIS)

Soto Torres, J.; Gomez Arozamena, J.

1999-01-01

A study of the radioactivity existing in a high number of springs located in Cantabria, Northern Spain, was made. The spring analyzed in three sampling campaign's, And alpha and beta total activities and 226 Ra and 222 Rn concentrations were determined for each sample. The measuring techniques employed were gamma spectrometry with Ge detector, counting with gas flow proportional counter, and counting with ZnS(Ag) scintillating detector. Results show that springs with high radon water concentration have high values respect to the national mean. The springs with the highest radium and radon levels have thermal waters and are located on two deep fault, those have historic seismicity and seismical and geomorphological evidences of recent tectonic activity

Alpha radioactivity monitor using ionized air transport technology for large size uranium waste (2). Simulation model reinforcement for practical apparatus design

International Nuclear Information System (INIS)

Asada, Takatoshi; Hirata, Yosuke; Naito, Susumu; Izumi, Mikio; Yoshimura, Yukio

2011-01-01

In alpha radioactivity measurement using ionized air transportation (AMAT), conversion from ion currents to radioactivity accurate is required. An ion transport simulation provides ways of complementarily determining conversion factors. We have developed an ion transport simulation model. Simulation results were compared with experiments with air speeds, faster than 1 m/s, achieving good agreement. In a practical AMAT apparatus, the air-flow at the alpha source may be slower than 1 m/s, and ion loss is likely to be large. Reinforcement of the ion transport model to cover the lower air speed region is effective. Ions are generated by an alpha particle in a very thin column. Since the ion density at this temporal stage is high, the recombination loss, proportional to the square of ion density, is dominant within a few milli-seconds. The spatial and temporal scales of this columnar recombination are too small for CFD simulation. We solve an ion transport equation during the period of columnar recombination with diffusion and recombination terms and incorporated the relation between ion loss and turbulent parameters into CFD. Using this model, simulations have been done for various air speeds and targets. Those for simulation results agree with experiments, showing improvement of simulation accuracy. (author)

Radioactivity in bottled waters sold in Mexico

International Nuclear Information System (INIS)

Davila Rangel, J.I.; Lopez del Rio, H.; Mireles Garcia, F.; Quirino Torres, L.L.; Villalba, M.L.; Colmenero Sujo, L.; Montero Cabrera, M.E.

2002-01-01

Measurements of gross alpha and beta activities were made on 21 domestic and international brands of bottled (purified and mineral) water sold in the Mexican market to assess its radiological quality. Alpha and beta activities were determined using a liquid-scintillation detector with pulse-shape analysis feature. All the purified water had values of beta activity lower than the limit for potable drinking water (1.0 Bq/l), while three brands surpassed the limit of alpha activity (0.1 Bq/l). The limit for alpha radioactivity content was exceed by three mineral waters; the results show a correlation between radioactivity content and mineral salts, which are related with the origin and treatment of the waters

A new method of alpha ray measurement using a Quadrupole Mass Spectrometer

International Nuclear Information System (INIS)

Iwata, Y.; Inoue, Y.; Minowa, M.

2007-01-01

We propose a new method of alpha (α)-ray measurement that detects helium atoms with a Quadrupole Mass Spectrometer (QMS). A demonstration is undertaken with a plastic-covered 241 Am α-emitting source to detect α-rays stopped in the capsule. We successfully detect helium atoms that diffuse out of the capsule by accumulating them for 1-20h in a closed chamber. The detected amount is found to be proportional to the accumulation time. Our method is applicable to probe α-emitting radioactivity in bulk material

Performance Test of Alpha Spectrometry for Environmental Radioactivity Analysis

International Nuclear Information System (INIS)

Choi, Jung Youn; Yoon, Jong-Ho; Han, Ki-Tek; Ahn, Gil Hoon

2015-01-01

Environmental samples are analyzed by various methods such as, ICP-MS (inductively coupled plasma mass spectrometry), AMS (accelerator mass spectrometry) TIMS (thermal ionization mass spectrometry), HRGS (high resolution gamma spectrometry) and alpha /beta particle analysis. In this study, we will described the result of performance test using alpha spectrometry for analyzing environmental samples. Measurement data of the U activity using SRM based on extraction chromatography with UTEVA resin. It should be effective way to separate of uranium isotope for the measurement of alpha spectrometry. But, the result of this measurement data is higher than another recovery data. Also concentration of U data is lack of consistency. We leave out of consideration many effect of factors about influence in the experiment process. In the future work, we will try to reduce the step of experiment process and reflect the uncertainty factors

Radioactivity in food crops

Energy Technology Data Exchange (ETDEWEB)

Drury, J.S.; Baldauf, M.F.; Daniel, E.W.; Fore, C.S.; Uziel, M.S.

1983-05-01

Published levels of radioactivity in food crops from 21 countries and 4 island chains of Oceania are listed. The tabulation includes more than 3000 examples of 100 different crops. Data are arranged alphabetically by food crop and geographical origin. The sampling date, nuclide measured, mean radioactivity, range of radioactivities, sample basis, number of samples analyzed, and bibliographic citation are given for each entry, when available. Analyses were reported most frequently for /sup 137/Cs, /sup 40/K, /sup 90/Sr, /sup 226/Ra, /sup 228/Ra, plutonium, uranium, total alpha, and total beta, but a few authors also reported data for /sup 241/Am, /sup 7/Be, /sup 60/Co, /sup 55/Fe, /sup 3/H, /sup 131/I, /sup 54/Mn, /sup 95/Nb, /sup 210/Pb, /sup 210/Po, /sup 106/Ru, /sup 125/Sb, /sup 228/Th, /sup 232/Th, and /sup 95/Zr. Based on the reported data it appears that radioactivity from alpha emitters in food crops is usually low, on the order of 0.1 Bq.g/sup -1/ (wet weight) or less. Reported values of beta radiation in a given crop generally appear to be several orders of magnitude greater than those of alpha emitters. The most striking aspect of the data is the great range of radioactivity reported for a given nuclide in similar food crops with different geographical origins.

Radioactivity and its measurement

CERN Document Server

Mann, W B; Garfinkel, S B

1980-01-01

Begins with a description of the discovery of radioactivity and the historic research of such pioneers as the Curies and Rutherford. After a discussion of the interactions of &agr;, &bgr; and &ggr; rays with matter, the energetics of the different modes of nuclear disintegration are considered in relation to the Einstein mass-energy relationship as applied to radioactive transformations. Radiation detectors and radioactivity measurements are also discussed

Human skeletal uptake of natural alpha radioactivity from 210Pb-supported 210Po

International Nuclear Information System (INIS)

Oyedepo, A.C.

1998-06-01

This thesis contributes to increasing knowledge on the dosimetry of natural alpha-particle radiation in skeletal tissues, particularly in utero, and associated risks of malignancy. Alpha-particle radiation is an established aetiological factor of cancer. In the human body, polonium-210 decayed from skeletal lead-210 ( 210 Pb/ 210 Po) is the predominant natural alpha-emitter. 210 Pb displaces calcium (Ca) in mineral hydroxyapatite, especially during periods of rapid bone growth and remodelling when Ca is laid down. It was therefore necessary to study alpha activity uptake and calcification concurrently within bone. Human studies were undertaken on: fetal vertebrae, 17 - 42 weeks of gestation, 74 samples; adult vertebrae, 40 - 95 years, 40 samples; and adult ribs, 20 - 95 years, 51 samples. Specimens were unconcentrated and weighed 210 Pb/ 210 Po. Alpha track data were resolved by specially written software named SPATS (Selection Program for Analysing Track Structures). Ca and phosphorus (P) were biochemically determined. Results were examined for trends in bone type, gender and chronological ageing in humans. The main research findings were: 1) The Ca content of fetal vertebrae increased linearly at a weekly rate of 0.2g Ca 100 g -1 wet bone (typical values of 2, 4, 6 g 100 g -1 at 16, 26 and 36 weeks). 2) The P concentration also increased with advancing fetal age. 3) The Ca:P bone weight ratio rose from 1.7 to 2.2 by 32 gestational weeks. 4) The overall range in bone 210 Pb/ 210 Po alpha activity was 0.25 - 1.1 Bq kg -1 with correlation between activity concentration and fetal age (0.47 ± 0.05 Bq kg -1 for 17 - 26 weeks, 0.67 ± 0.04 Bq kg -1 for 32 - 42 weeks). 5) The correlation between increased alpha radioactivity and increased Ca concentration approximating to 0.0046 Bq g -1 of Ca. 6) A decreasing Ca content of adult vertebrae with increasing age from 40 - 95 years, from ∼ 14 to 5 g 100 g-1, but no correlation with age for adult rib Ca content of 10 - 30 g

Report on long range alpha detector (LRAD) performance tests

International Nuclear Information System (INIS)

Kobayashi, Hirohide; Unno, Motoyoshi; Ishikawa, Hisashi; Yoshida, Tadayoshi

2002-10-01

At present, alpha contamination measurement on objects is conducted with ZnS scintillation survey meter (direct method) and smear test (indirect method). But it is difficult to measure large and complicated objects by direct method. Long Range Alpha Detector (LRAD) was produced as a solution for this problem. We carried out performance tests of this LRAD. As a result of the performance tests, we confirmed the linear relation between the measurement values of LRAD and alpha-radioactivity on the surface of objects. (author)

Development of detection method for individual environmental particles containing alpha radioactive nuclides

International Nuclear Information System (INIS)

Esaka, Konomi; Yasuda, Kenichiro; Esaka, Fumitaka; Magara, Masaaki; Sakurai, Satoshi; Usuda, Shigekazu; Nakayama, Shinichi

2006-01-01

Artificial radioactive nuclides have been emitted from various sources and have fallen on the surface of the earth as fine particles. Although the characterization of the individual fallout particles is very important, their analysis is difficult. The purpose of this study is to develop a new detection method for individual objective particles containing radioactive nuclides in the environment. The soil or sediment sample was confined in a plastic film and the locations of objective particles were identified with alpha tracks created in a solid-state detectors (BARYOTRAK, Fukuvi Chemical, Ltd) stuck to the both sides of the plastic film. A piece of the film containing the objective particle was cut with a nitrogen laser for following individual particle analysis. This procedure allowed us to detect the objective particle from innumerable number of particles in the environment and characterize the individual particles. (author)

Measurement of 233U/234U ratios in contaminated groundwater using alpha spectrometry

International Nuclear Information System (INIS)

Harrison, Jennifer J.; Payne, Timothy E.; Wilsher, Kerry L.; Thiruvoth, Sangeeth; Child, David P.; Johansen, Mathew P.; Hotchkis, Michael A.C.

2016-01-01

The uranium isotope 233 U is not usually observed in alpha spectra from environmental samples due to its low natural and fallout abundance. It may be present in samples from sites in the vicinity of nuclear operations such as reactors or fuel reprocessing facilities, radioactive waste disposal sites or sites affected by clandestine nuclear operations. On an alpha spectrum, the two most abundant alpha emissions of 233 U (4.784 MeV, 13.2%; and 4.824 MeV, 84.3%) will overlap with the 234 U doublet peak (4.722 MeV, 28.4%; and 4.775 MeV, 71.4%), if present, resulting in a combined 233+234 U multiplet. A technique for quantifying both 233 U and 234 U from alpha spectra was investigated. A series of groundwater samples were measured both by accelerator mass spectrometry (AMS) to determine 233 U/ 234 U atom and activity ratios and by alpha spectrometry in order to establish a reliable 233 U estimation technique using alpha spectra. The Genie™ 2000 Alpha Analysis and Interactive Peak Fitting (IPF) software packages were used and it was found that IPF with identification of three peaks ( 234 U minor, combined 234 U major and 233 U minor, and 233 U major) followed by interference correction on the combined peak and a weighted average activity calculation gave satisfactory agreement with the AMS data across the 233 U/ 234 U activity ratio range (0.1–20) and 233 U activity range (2–300 mBq) investigated. Correlation between the AMS 233 U and alpha spectrometry 233 U was r 2  = 0.996 (n = 10). - Highlights: • Describes a technique for deconvoluting the combined 233 U and 234 U multiplet in alpha spectra. • Enables 233 U and 234 U activities and 233 U/ 234 U ratios to be quantified without requiring additional analysis and measurement. • Applicable to an environmental matrix (groundwater) using standard alpha spectrometry counting equipment, operation and set-up.

Measurement of activity of radioactive gas

International Nuclear Information System (INIS)

Zhuo Renhong; Lei Jiarong; Wen Dezhi; Cheng Jing; Zheng Hui

2005-10-01

A set of standard instrument system with their accessories for the measurement of activity of radioactive gas have been developed. The specifications and performances of the system have been tested and examined. The conventional true values of activity of radioactive gas have been measured and its uncertainty has been assessed. The technique of the dissemination of the measurement of activity of radioactive gas has been researched. The specification and performance of the whole set of apparatus meet the requirements of the relational standard, critra, regulation, it can be regard as a work standard for the measurement of activity of radioactive gas in CAEP. (authors)

Measurement of relative L X-ray intensity ratio following radioactive decay and photoionization

Energy Technology Data Exchange (ETDEWEB)

Yalcin, P. [Department of Science Education, Faculty of Education, Erzincan University, 24030 Erzincan (Turkey)], E-mail: pasayalcin@hotmail.com; Porikli, S.; Kurucu, Y.; Sahin, Y. [Department of Physics, Faculty of Sciences, Atatuerk University, 25240 Erzurum (Turkey)

2008-05-22

The measurements of the L X-ray intensity ratio I(L{alpha})/I(L{beta}), I(L{alpha})/I(L{gamma}), I(L{alpha})/I(L{iota}), I(L{beta})/I(L{gamma}) and I(L{iota})/I(L{gamma}) for elements Dy, Ho, Yb, W, Hg, Tl and Pb were experimentally determined both by photon excitation, in which 59.5 keV {gamma}-rays from a filtered radioisotope {sup 241}Am was used, and by the radioactive decay of {sup 160}Tb, {sup 160}Er, {sup 173}Lu, {sup 182}Re, {sup 201}Tl, {sup 203}Pb and {sup 207}Bi. L X-rays emitted by samples were counted by a Si(Li) detector with resolution 160 eV at 5.9 keV. Obtained values were compared with the calculated theoretical values. Theoretical values of the I(L{alpha}/L{beta}), I(L{alpha}/L{gamma}), I(L{alpha}/L{iota}), I(L{beta}/L{gamma}) and I(L{iota}/L{gamma}) intensity ratios were calculated using theoretically tabulated values of subshell photoionization cross-section, fluorescence yield, fractional X-ray emission rates, Coster-Kronig transition probabilities. It was observed that present values agree with previous theoretical and other available experimental results.

Measurement of gamma radioactivity in steel

International Nuclear Information System (INIS)

Wachtendonk, H.J. von; Flock, J.; Grientschnig, D.; Kircher, T.; Kroos, J.; Mertens, S.; Mueller, J.; Puchmayr, J.; Schlothmann, B.J.; Schmitz, H.U.; Troebs, V.; Unger, H.

1999-01-01

The steel industry is being confronted increasingly with radioactive scrap from dismantled nuclear facilities. The clearance and release regulations that exist around the world differ very greatly and are difficult to implement. A 'radioactivity measurement' working group has therefore been set up at VDEh to clarify how radioactive measurements can be integrated into the day-to-day production routine. Operating results obtained at Thyssen Krupp Stahl AG with a gamma-ray spectrometer indicate a possibility for the simple detection of radioactive contamination. (orig.) [de

Alpha radioactivity in cigarette smoke

International Nuclear Information System (INIS)

Cohen, B.S.; Eisenbud, M.; Harley, N.H.

1980-01-01

The α activity of cigarette smoke tar deposited onto membrane filters was found to be associated with the relatively insoluble fraction. Perfusion of the tar with physiological saline resulted in no change in the mean measured activity, but there was more variability in the measured values for the perfused tar than for the initial tar samples. Analysis of cigarette smoke condensate shows that radium and thorium are present, but over 99% of the α activity results from 210 Po. Repeat measurements after a time lapse of 2 1/2 years indicate that the initial 210 Pb content of the tar is roughly 30 to 40% of the original 210 Po content for both unprocessed and perfused samples. An increase in the α activity concentration of smoke deposited in lung tissue may result from the lack of solubility of the radioactive material compared with other smoke constituents

Breakout from the hot CNO cycle: the {sup 15}O({alpha},{gamma}) and {sup 18}Ne({alpha},p) reactions

Energy Technology Data Exchange (ETDEWEB)

Bradfield-Smith, W; Laird, A M; Davinson, T; Pietro, A di; Ostrowski, A N; Shotter, A C; Woods, P J [Dept. of Physics and Astronomy, Univ. of Edinburgh (United Kingdom); Cherubini, S; Galster, W; Graulich, J S; Leleux, P; Michel, L; Ninane, A; Vervier, J [Inst. de Physique Nucleaire, UCL, Louvain-la-Neuve (Belgium); Aliotta, M; Cali, D; Cappussello, F; Cunsolo, A; Spitaleri, C [INFN, Catania (Italy); Gorres, J; Wiescher, M [Notre Dame Univ. (United States); Rahighi, J [Van de Graaf Lab., Tehran (Iran, Islamic Republic of); Hinnefeld, J [Indiana Univ., South Bend (United States)

1998-06-01

One of the most important reactions which determines the rate of breakout from the hot CNO cycle is the {sup 15}O({alpha},{gamma}){sup 19}Ne. The reaction {sup 18}Ne({alpha},p){sup 21}Na may also provide an alternative breakout route. Experiments are being undertaken at Louvain-La-Neuve using the radioactive {sup 18}Ne beam to study these reactions by measurement of {alpha}({sup 18}Ne,p){sup 21}Na and d({sup 18}Ne,p){sup 19}Ne{sup *} {yields} {sup 15}O + {alpha} (orig.)

Counting statistics in radioactivity measurements

International Nuclear Information System (INIS)

Martin, J.

1975-01-01

The application of statistical methods to radioactivity measurement problems is analyzed in several chapters devoted successively to: the statistical nature of radioactivity counts; the application to radioactive counting of two theoretical probability distributions, Poisson's distribution law and the Laplace-Gauss law; true counting laws; corrections related to the nature of the apparatus; statistical techniques in gamma spectrometry [fr

Measurement of radioactivity in steel

International Nuclear Information System (INIS)

Wachtendonk, H.-J. von; Luengen, S.; Wilke, N.

1999-01-01

Even after the control of scrap deliveries, there remains a small risk that the radioactive contaminated scrap passes the detecting devices. Therefore, the chemical laboratory takes a role to measure each heat for the absence of artificial radioactive nuclides with a gamma spectrometer equipped with NaI-detector. As the measurement must be performed in sequence with the steel production process, the allowable time for the measurement is quite limited. On the other hand, there could be still some possibility that background radiation might be present as the samples may contain some natural radioactivity. The task is how to differentiate the nature of radioactivity between naturally remaining radioactivity within safe limit and artificial nuclides present in the sample at a low level even though a very small amount of radioactivity could be detected in short time in both cases. We have set the alarm limit to 0.1 Bq/g for Co-60 as indicating nuclide. This limit is set more than 4 s (s = standard deviation) from the average background radiation. Therefore, false alarms are quite improbable. Strategy: The NaI gamma spectrometer performs a gross gamma measurement but it can not differentiate the nature of the nuclides present. If the alarm limit is hurt, the sample is measured on a high resolution gamma spectrometer with Ge-detector for identification of the gamma emitting nuclides. Calibration: Even though no appropriate international standards are adapted and no commercial measuring equipment is commercially available, the desired standard should contain Co-60 in the order of 1 to 100 Bq/g. The presence of other gamma emitting nuclides is desirable. In the Workshop we will present how to surmount this difficulty. (author)

GAMCAT - a personal computer database on alpha particles and gamma rays from radioactive decay

International Nuclear Information System (INIS)

Tepel, J.W.; Mueller, H.W.

1990-01-01

The GAMCAT database is a compilation of data describing the alpha particles and gamma rays that occur in the radioactive decay of all known nuclides, adapted for IBM Personal Computers and compatible systems. These compiled data have been previously published, and are now available as a compact database. Entries can be retrieved by defining the properties of the parent nuclei as well as alpha-particle and gamma-ray energies or any combination of these parameters. The system provides fast access to the data and has been completely written in C to run on an AT-compatible computer, with a hard disk and 640K of memory under DOS 2.11 or higher. GAMCAT is available from the Fachinformationszentrum Karlsruhe. (orig.)

Biodistribution analysis of 125I-albumin-IFN-alpha2b fusion protein in rats

International Nuclear Information System (INIS)

Zhou Yaoyuan; Zhang Rongjun; Cai Gangming; Gu Xiaobo; Jiang Mengjun; Zhang Bo; Yang Min; Cao Guoxian; Yang Jianliang

2009-01-01

125 I-albumin-IFN-alpha2b was prepared with the methods of Ch-T and purified with PD-10 column. The radiochemical purity was measured with TCA (trichloroacetic acid) precipitation. The antiviral activities of 125 I-albumin-IFN-alpha2b and albumin-IFN-alpha2b were compared with WISH/VSV system in vitro. SD rats were injected with 125 I-albumin-IFN-alpha2b subcutaneously and sacrificed at 0.5, 2, 6, 24, 48, 90, 180 and 300 h post-injection. Selected organs were dissected, weighed and their radioactivity was measured using γ-counter. The accumulated radioactivity in the tissues was calculated in terms of percentage of injected dose per gram organ (%ID·g -1 ). The labeling yield was 82.72%. The radiochemical purity of 125 I-albumin-IFN-alpha2b was 95.53%, and its radioactivity was 0.26 MBq/μg. The antiviral bioactivities of albumin-IFN-alpha2b and 125 I-albumin- IFN-alpha2b did not change. Biodistribution analysis of 125 I-albumin-IFN-alpha2b in rats showed that concentrated 125 I-albumin-IFN-alpha2b in blood reached maximum at 6 h post injection, and eliminated slowly. No specific accumulation was seen in other tissues. 125 I-albumin-IFN-alpha2b could maintain in peripheral blood for a long time and it meant albumin-IFN-alpha2b would be an effective long-term interferon. (authors)

Evaluation of NDA techniques applying to the measurement of alpha-activities in medium or low level radioactive reprocessing wastes (part 5). The development of LiF coating semiconductor detector

Energy Technology Data Exchange (ETDEWEB)

Hattori, Takatoshi; Ishii, Keiichiro [Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab.

1988-12-01

In order to design the neutron detection system in the non-destructive assay device applying to the measurement of alpha-activity in medium or low level radioactive reprocessing wastes, we examined the property of the LiF coating semiconductor detector applying to gamma-radiation field. The sensitivity for thermal neutron of LiF coating ion implanted detector is 1.6 cps/nv, and reduced to half in about 300 R/h gamma-radiation field. Compared with the other neutron detectors, for example proportional counters, the performance of this detector is almost similar to that of them. This new detector has a merit to be possible to use a dry battery instead of a high voltage supply. (author).

Calculation of uncertainties associated to environmental radioactivity measurements and their functions. Practical Procedure II

International Nuclear Information System (INIS)

Gascon, C.; Anton, M.P.

1997-01-01

Environmental radioactivity measurements are mainly affected by counting uncertainties. In this report the uncertainties associated to certain functions related to activity concentration calculations are determined. Some practical exercise are presented to calculate the uncertainties associated to: a) Chemical recovery of a radiochemical separation when employing tracers (i.e. Pu and Am purification from a sediment sample). b) Indirect determination of a mother radionuclide through one of its daughters (i. e. ''210 Pb quantification following its daughter ''210 Po building-up activity). c) Time span from last separation date of one of the components of a disintegration chain (i.e. Am last purification date from a nuclear weapons following ''241 Am and ''241 Pu measurements). Calculations concerning example b) and c) are based on Baterman equations, regulating radioactive equilibria. Although the exercises here presented are performed with certain radionuclides, they could be applied as generic procedures for other alpha-emitting radioelements

The Periodic Measurement of the Airborne Radioactivity In Controlled Area of KOMAC

Energy Technology Data Exchange (ETDEWEB)

Park, Jeong-Min; Park, Sung-Kyun; Min, Yi-Sub; Cho, Yong-Sub [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Korea Multipurpose Accelerator Complex (KOMAC) to start the performance operation in the second half of 2013, is currently operated in each beamline 20-MeV and 100-MeV. The accelerator operation period is simply divided by three operation cycles which are the maintenance checks period for accelerator device, the performance test period before driving accelerator and the operation period. During this operation period, beam is irradiated to target. At this time, the proton beams collide with the target material and a high dose of radiations such as gamma ray and neutron occurred. Radiation controlled area at the accelerator facility is divided into accelerator tunnel and beam utilization zone. As a result of measuring the airborne radioactivity in the controlled area in accordance with the operating cycle of the proton accelerator KOMAC, It was confirmed that the value of the airborne radioactivity does not significantly differ according to each accelerator operating cycles. And alpha and beta values measured inside the area that workers primarily work is very low indoor radon level than the value of the recommendations in multiple facilities.

Measurement of radioactivity in rain

International Nuclear Information System (INIS)

Eivindson, T.

1985-01-01

The report gives a description of an ion-exchange surveillance- sampler for routine measurements of radioactivity in rain, and how the measurements are performed. Using the nuclides 85 Sr, 131 I and 137 Cs as tracers, experiments have been performed to determine the distribution of radioactivity in the ion-exchange column and the effectiveness of the column as a function of elutriation rate and temperature

Handbook of radioactivity measurements procedures. Second edition

International Nuclear Information System (INIS)

Anon.

1985-01-01

This report is concerned with the measurement of radioactivity in general, but specifically it deals with radioactive materials that have become available in the last three decades, from nuclear reactors and particle accelerators, for applications in medicine, scientific research, and industry. It is also concerned with low-level radioactivity measurements for the monitoring of radioactivity in environmental media, such as air and water, in connection with the control of radioactive effluents associated with the production of nuclear power or the use of radionuclides. Included in appendices are nuclear decay data for selected radionuclides and statistics of radioactive decay. An extensive bibliography is also included

Innovative alpha radioactivity monitor for clearance level inspection based on ionized air transport technology (2). CFD-simulated and experimental ion transport efficiencies for uranium-attached pipes

International Nuclear Information System (INIS)

Hirata, Yosuke; Nakahara, Katsuhiko; Sano, Akira; Sato, Mitsuyoshi; Aoyama, Yoshio; Miyamoto, Yasuaki; Yamaguchi, Hiromi; Nanbu, Kenichi; Takahashi, Hiroyuki; Oda, Akinori

2007-01-01

An innovative alpha radioactivity monitor for clearance level inspection has been developed. This apparatus measures an ion current resulting from air ionization by alpha particles. Ions generated in the measurement chamber of about 1 m 3 in volume are transported by airflow to a sensor and measured. This paper presents computational estimation of ion transport efficiencies for two pipes with different lengths, the inner surfaces of which were covered with a thin layer of uranium. These ion transport efficiencies were compared with those experimentally obtained for the purpose of our model validation. Good agreement was observed between transport efficiencies from simulations and those experimentally estimated. Dependence of the transport efficiencies on the region of uranium coating was also examined, based on which anticipated errors arising from unclear positions of contamination are also discussed. (author)

Preparation of radioactive ''mixed'' waste samples for measurement of RCRA [Resource Conservation and Recovery Act] organic compounds

International Nuclear Information System (INIS)

Tomkins, B.A.; Caton, J.E.

1987-01-01

A radioactive ''mixed'' waste typically contains alpha-, beta-, or gamma-emitting radionuclides and varying quantities of semivolatile or volatile organic species, some or all of which may be named specifically by the Resource Conservation and Recovery Act (RCRA). Because there are no acceptable means available currently for disposing of these mixed wastes, they are presently stored above-ground in sealed drums. For this reason, analytical procedures which can determine RCRA organics in radioactive waste are necessary for deciding the proper approach for disposal. An important goal of this work is the development of methods for preparing mixed waste samples in a manner which allows the RCRA organics to be measured in conventional organic analysis laboratories without special precautions. Analytical procedures developed for handling mixed waste samples must satisfy not only the usual constraints present in any trace-level organic chemical determination, but also those needed to insure the protection of the operator from radioactive contamination. Consequently, procedures should be designed to use the least amount of radioactive sample commensurate with achieving acceptable sensitivity with the RCRA analytical methods. Furthermore, the unusual laboratory glassware which would normally be used should be replaced with disposable materials wherever possible, in order to reduce the ''clean-up'' time required, and thereby reduce the operator's exposure to radioactivity. Actual sample handling should be reduced to the absolute minimum. Finally, the final isolate must exhibit a sufficiently low level of alpha, beta, or gamma activity to permit detailed characterization in a conventional organic analysis laboratory. 4 refs., 5 tabs

Measuring radioactivity in the body

Energy Technology Data Exchange (ETDEWEB)

NONE

1961-09-15

Techniques of measuring the total amount of radioactivity in the body of a living person as well as the principal applications of such measurements were reviewed at a Symposium on Whole Body Counting held in Vienna from 12 to 16 June 1961. The whole body counters can be divided into two broad groups: (a) counters for the radiation protection surveillance of the general public and radiation workers, capable of detecting extremely low levels of radioactivity in the human body, and (b) counters for medical research and diagnosis, designed to check the retention and excretion of radioactive substances administered to patients for metabolic and pathological studies. In both cases, the primary requirement is that the counter must be able to measure the total activity in the body. In recent years, there has been a remarkable development of the instruments and techniques for such measurements. One of the main purposes of the symposium in Vienna was to discuss how best to use these highly sophisticated instruments.

An Alpha spectrometer for measuring radon daughter individual activity concentration

International Nuclear Information System (INIS)

Berico, M.; Formignani, M.; Mariotti, F.

2001-01-01

In the frame of the program of the Institute for Radiation Protection of ENEA, related to the evaluation of dose from radon and thoron progeny, an alpha spectrometer for the continuous air monitoring (CAM type) of radon and thoron has been realized. The constructive characteristics of the device are here presented together with energy and efficiency calibration. The device allows, by means of a screen type diffusion battery and a filter, to determinate the single radioactivity of each radionuclide of the progeny selecting them in relation to their diffusive behaviour (dichotomous particle size selection). The three-count filter method has been employed to measure the concentrations of 218 Po, 214 Pb and 214 Bi in air. Radon and thoron effective doses using a dosimetric, instead of an epidemiologic approach, will be then evaluated [it

The determination of the national background radioactivity of gross alpha and gross beta in water samples at the PUSPATI site and its neutrons

International Nuclear Information System (INIS)

Rahman, M.T.A.

1983-01-01

The determination of the natural background radioactivity in water samples has been made at the PUSPATI site and its environs. The study was performed in January 1981 until June 1981. Samples of river, rain and tap water are periodically collected and analyzed in order to determine gross alpha and gross beta activity. In general, the total radioactivity of water is considerably low. The mean concentration of gross alpha in river water and tap water samples are 1.2 +- 0.1 and 0.2 +- 0.1 pCi/ respectively. The level of gross alpha in rain water is however, below the background rate of the detector. The mean concentration of gross beta in river water, tap water and rain water samples are 4.2 +- 0.6, 1.6 +- 0.3, and 1.9 +- 0.3 pCi/ respectively. (author)

Radioactivity measurements principles and practice

CERN Document Server

Mann, W B; Spernol, A

2012-01-01

The authors have addressed the basic need for internationally consistent standards and methods demanded by the new and increasing use of radioactive materials, radiopharmaceuticals and labelled compounds. Particular emphasis is given to the basic and practical problems that may be encountered in measuring radioactivity. The text provides information and recommendations in the areas of radiation protection, focusing on quality control and the precautions necessary for the preparation and handling of radioactive substances. New information is also presented on the applications of both traditiona

Estimating the mean and variance of measurements from serial radioactive decay schemes with emphasis on 222Rn and its short-lived progeny

International Nuclear Information System (INIS)

Inkret, W.C.; Borak, T.B.; Boes, D.C.

1990-01-01

Classically, the mean and variance of radioactivity measurements are estimated from poisson distributions. However, the random distribution of observed events is not poisson when the half-life is short compared with the interval of observation or when more than one event can be associated with a single initial atom. Procedures were developed to estimate the mean and variance of single measurements of serial radioactive processes. Results revealed that observations from the three consecutive alpha emissions beginning with 222 Rn are positively correlated. Since the poisson estimator ignores covariance terms, it underestimates the true variance of the measurement. The reverse is true for mixtures of radon daughters only. (author)

Human skeletal uptake of natural alpha radioactivity from {sup 210}Pb-supported {sup 210}Po

Energy Technology Data Exchange (ETDEWEB)

Oyedepo, A.C

1998-06-01

This thesis contributes to increasing knowledge on the dosimetry of natural alpha-particle radiation in skeletal tissues, particularly in utero, and associated risks of malignancy. Alpha-particle radiation is an established aetiological factor of cancer. In the human body, polonium-210 decayed from skeletal lead-210 ({sup 210}Pb/{sup 210}Po) is the predominant natural alpha-emitter. {sup 210}Pb displaces calcium (Ca) in mineral hydroxyapatite, especially during periods of rapid bone growth and remodelling when Ca is laid down. It was therefore necessary to study alpha activity uptake and calcification concurrently within bone. Human studies were undertaken on: fetal vertebrae, 17 - 42 weeks of gestation, 74 samples; adult vertebrae, 40 - 95 years, 40 samples; and adult ribs, 20 - 95 years, 51 samples. Specimens were unconcentrated and weighed <5 g each. TASTRAK alpha-particle autoradiography was used to assess the bone activity concentration and spatial microdistribution of {sup 210}Pb/{sup 210}Po. Alpha track data were resolved by specially written software named SPATS (Selection Program for Analysing Track Structures). Ca and phosphorus (P) were biochemically determined. Results were examined for trends in bone type, gender and chronological ageing in humans. The main research findings were: 1) The Ca content of fetal vertebrae increased linearly at a weekly rate of 0.2g Ca 100 g{sup -1} wet bone (typical values of 2, 4, 6 g 100 g{sup -1} at 16, 26 and 36 weeks). 2) The P concentration also increased with advancing fetal age. 3) The Ca:P bone weight ratio rose from 1.7 to 2.2 by 32 gestational weeks. 4) The overall range in bone {sup 210}Pb/{sup 210}Po alpha activity was 0.25 - 1.1 Bq kg{sup -1} with correlation between activity concentration and fetal age (0.47 {+-} 0.05 Bq kg{sup -1} for 17 - 26 weeks, 0.67 {+-} 0.04 Bq kg{sup -1} for 32 - 42 weeks). 5) The correlation between increased alpha radioactivity and increased Ca concentration approximating to 0

Measurement and analysis of $\\alpha$ particle induced reactions on yttrium

CERN Document Server

Singh, N L; Chintalapudi, S N

2000-01-01

Excitation functions for /sup 89/Y[( alpha ,3n); ( alpha ,4n); ( alpha , p3n); ( alpha , alpha n); ( alpha , alpha 2n)] reactions were measured up to 50 MeV using stacked foil activation technique and HPGe gamma ray spectroscopy method. The experimental data were compared with calculations considering equilibrium as well as preequilibrium reactions according to the hybrid model of Blann (ALICE/90). For ( alpha , xnyp) type of reactions, the precompound contributions are described by the model. There seems to be indications of direct inelastic scattering effects in ( alpha , alpha xn) type of reactions. To the best of our knowledge, the excitation functions for ( alpha ,4n), ( alpha , p3n), ( alpha , alpha n) and ( alpha , alpha 2n) reactions were measured for the first time. (23 refs).

Measurement and analysis of alpha particle induced reactions on yttrium

Energy Technology Data Exchange (ETDEWEB)

Singh, N.L.; Gadkari, M.S. [Baroda Univ. (India). Dept. of Physics; Chintalapudi, S.N. [IUC-DAEF Calcutta Centre, Calcutta (India)

2000-05-01

Excitation functions for {sup 89}Y[({alpha},3n);({alpha},4n);({alpha},p3n);({alpha},{alpha}n);({alpha},{alpha}2n)] reactions were measured up to 50 MeV using stacked foil activation technique and HPGe gamma ray spectroscopy method. The experimental data were compared with calculations considering equilibrium as well as preequilibrium reactions according to the hybrid model of Blann (ALICE/90). For ({alpha},xnyp) type of reactions, the precompound contributions are described by the model. There seems to be indications of direct inelastic scattering effects in ({alpha},{alpha}xn) type of reactions. To the best of our knowledge, the excitation functions for ({alpha},4n), ({alpha},p3n), ({alpha},{alpha}n) and ({alpha},{alpha}2n) reactions were measured for the first time. (orig.)

Measurement of radioactivity in contaminated crops

Energy Technology Data Exchange (ETDEWEB)

Yamada, Y; Hasegawa, M; Kihara, T

1956-01-01

A method called the Direct Method was developed to correct for natural /sup 40/K radiation in plant samples. The K content of the ashed sample is determined by flamephotometry. The radioactivity in a 100 mg sample is measured and the natural radioactivity from /sup 40/K determined by calculation subtracted. Tea samples tested gave evidence of contamination by radioactive fallout.

Radioactivity measurement of radioactive contaminated soil by using a fiber-optic radiation sensor

Science.gov (United States)

Joo, Hanyoung; Kim, Rinah; Moon, Joo Hyun

2016-06-01

A fiber-optic radiation sensor (FORS) was developed to measure the gamma radiation from radioactive contaminated soil. The FORS was fabricated using an inorganic scintillator (Lu,Y)2SiO5:Ce (LYSO:Ce), a mixture of epoxy resin and hardener, aluminum foil, and a plastic optical fiber. Before its real application, the FORS was tested to determine if it performed adequately. The test result showed that the measurements by the FORS adequately followed the theoretically estimated values. Then, the FORS was applied to measure the gamma radiation from radioactive contaminated soil. For comparison, a commercial radiation detector was also applied to measure the same soil samples. The measurement data were analyzed by using a statistical parameter, the critical level to determine if net radioactivity statistically different from background was present in the soil sample. The analysis showed that the soil sample had radioactivity distinguishable from background.

The measurement theory of radioactivity in building materials

International Nuclear Information System (INIS)

Qu Jinhui; Wang Renbo; Zhang Xiongjie; Tan Hai; Zhu Zhipu; Man Zaigang

2010-01-01

Radioactivity in Building Materials is the main source of natural radiation dose that the individual is received, which has caused serious concern of all Social Sector. The paper completely introduce the measurement theory of the Radioactivity in Building Materials along with the measurement principle of natural radioactivity, design of shielding facility, choosing measurement time, sample prepared and spectrum analyzed. (authors)

Proceedings, High-Precision $\\alpha_s$ Measurements from LHC to FCC-ee

Energy Technology Data Exchange (ETDEWEB)

d' Enterria, David [CERN; Skands, Peter Z. [Monash U.

2015-01-01

This document provides a writeup of all contributions to the workshop on "High precision measurements of $\\alpha_s$: From LHC to FCC-ee" held at CERN, Oct. 12--13, 2015. The workshop explored in depth the latest developments on the determination of the QCD coupling $\\alpha_s$ from 15 methods where high precision measurements are (or will be) available. Those include low-energy observables: (i) lattice QCD, (ii) pion decay factor, (iii) quarkonia and (iv) $\\tau$ decays, (v) soft parton-to-hadron fragmentation functions, as well as high-energy observables: (vi) global fits of parton distribution functions, (vii) hard parton-to-hadron fragmentation functions, (viii) jets in $e^\\pm$p DIS and $\\gamma$-p photoproduction, (ix) photon structure function in $\\gamma$-$\\gamma$, (x) event shapes and (xi) jet cross sections in $e^+e^-$ collisions, (xii) W boson and (xiii) Z boson decays, and (xiv) jets and (xv) top-quark cross sections in proton-(anti)proton collisions. The current status of the theoretical and experimental uncertainties associated to each extraction method, the improvements expected from LHC data in the coming years, and future perspectives achievable in $e^+e^-$ collisions at the Future Circular Collider (FCC-ee) with $\\cal{O}$(1--100 ab$^{-1}$) integrated luminosities yielding 10$^{12}$ Z bosons and jets, and 10$^{8}$ W bosons and $\\tau$ leptons, are thoroughly reviewed. The current uncertainty of the (preliminary) 2015 strong coupling world-average value, $\\alpha_s(m_Z)$ = 0.1177 $\\pm$ 0.0013, is about 1\\%. Some participants believed this may be reduced by a factor of three in the near future by including novel high-precision observables, although this opinion was not universally shared. At the FCC-ee facility, a factor of ten reduction in the $\\alpha_s$ uncertainty should be possible, mostly thanks to the huge Z and W data samples available.

The influence of salt aerosol on alpha radiation detection by WIPP continuous air monitors

International Nuclear Information System (INIS)

Bartlett, W.T.; Walker, B.A.

1996-01-01

Alpha continuous air monitors (CAMs) will be used at the Waste Isolation Pilot Plant (WIPP) to measure airborne transuranic radioactivity that might be present in air exhaust or in work-place areas. WIPP CAMs are important to health and safety because they are used to alert workers to airborne radioactivity, to actuate air-effluent filtration systems, and to detect airborne radioactivity so that the radioactivity can be confined in a limited area. In 1993, the Environmental Evaluation Group (EEG) reported that CAM operational performance was affected by salt aerosol, and subsequently, the WIPP CAM design and usage were modified. In this report, operational data and current theories on aerosol collection were reviewed to determine CAM quantitative performance limitations. Since 1993, the overall CAM performance appears to have improved, but anomalous alpha spectra are present when sampling-filter salt deposits are at normal to high levels. This report shows that sampling-filter salt deposits directly affect radon-thoron daughter alpha spectra and overall monitor efficiency. Previously it was assumed that aerosol was mechanically collected on the surface of CAM sampling filters, but this review suggests that electrostatic and other particle collection mechanisms are more important than previously thought. The mechanism of sampling-filter particle collection is critical to measurement of acute releases of radioactivity. 41 refs

Effect of metallic iron on the oxidative dissolution of UO2 doped with a radioactive alpha emitter in synthetic Callovian-Oxfordian groundwater

Science.gov (United States)

Odorowski, Mélina; Jegou, Christophe; De Windt, Laurent; Broudic, Véronique; Jouan, Gauthier; Peuget, Sylvain; Martin, Christelle

2017-12-01

In the hypothesis of direct disposal of spent fuel in a geological nuclear waste repository, interactions between the fuel mainly composed of UO2 and its environment must be understood. The dissolution rate of the UO2 matrix, which depends on the redox conditions on the fuel surface, will have a major impact on the release of radionuclides into the environment. The reducing conditions expected for a geological disposal situation would appear to be favorable as regards the solubility and stability of the UO2 matrix, but may be disturbed on the surface of irradiated fuel. In particular, the local redox conditions will result from a competition between the radiolysis effects of water under alpha irradiation (simultaneously producing oxidizing species like H2O2, hydrogen peroxide, and reducing species like H2, hydrogen) and those of redox active species from the environment. In particular, Fe2+, a strongly reducing aqueous species coming from the corrosion of the iron canister or from the host rock, could influence the dissolution of the fuel matrix. The effect of iron on the oxidative dissolution of UO2 was thus investigated under the conditions of the French disposal site, a Callovian-Oxfordian clay formation chosen by the French National Radioactive Waste Management Agency (Andra), here tested under alpha irradiation. For this study, UO2 fuel pellets doped with a radioactive alpha emitter (238/239Pu) were leached in synthetic Callovian-Oxfordian groundwater (representative of the French waste disposal site groundwater) in the presence of a metallic iron foil to simulate the steel canister. The pellets had varying levels of alpha activity, in order to modulate the concentrations of species produced by water radiolysis on the surface and to simulate the activity of aged spent fuel after 50 and 10,000 years of alpha radioactivity decay. The experimental data showed that whatever the sample alpha radioactivity, the presence of iron inhibits the oxidizing dissolution of

Environmental radioactivity. Measurement and monitoring; Umweltradioaktivitaet. Messung und Ueberwachung

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-11-15

The contribution on environmental radioactivity covers the following issues: natural and artificial radioactivity; continuous monitoring of radioactivity; monitoring authorities and measurement; radioactivity in the living environment; radioactivity in food and feeding stuff; radioactivity of game meat and wild-growing mushrooms; radioactivity in mines; radioactivity in the research center Rossendorf.

Application of solid state nuclear track detectors in measurement of natural alpha- radioactivity in environment

Energy Technology Data Exchange (ETDEWEB)

Maged, A F; El-Behay, A Z; Borham, E [National Center for Radiation Research and Technology, Atomic Energy Authority, Cairo (Egypt)

1997-12-31

The use of solid state nuclear track detectors (SSNTDs) is one of the most convenient techniques to assess the average radiation levels of alpha activities in the environment. This technique has been used to assess radon gas and its daughters in buildings. Exposed SSNTD films are chemically etched in an alkali solution and alpha tracks are evaluated by using the image analyzer system. The detailed procedure for this study and the etched films for conversion of alpha track density to radon concentration in Bq m{sup -}3 are given and discussed in the text.1 fig., 3 tabs.

Conversion of an Alpha CAM Monitor of Victoreen calibrated of factory for plutonium in a measurement monitor of radon in the atmosphere

International Nuclear Information System (INIS)

Moreno y Moreno, A.

2004-01-01

It is presented in this work the conversion of a monitor ALPHA CAM of the monitor Victoreen gauged of it manufactures for plutonium in a monitor for radon mensuration in the atmosphere. Those units in that the radon measures are expressed are: peak curies/unit of volume of air to sampling. This way one has to gauge and to supplement the software and the parts that the old one monitor for plutonium. It requires. This task implies: a) To calibrate and to determine the efficiency of the detector of accustomed to state of 1700 mm 2 for alpha particles coming from the radioactive series of the radon. b) to connect in series and to calibrate a flow measurer of air in it lines with the detector. Measures are presented of the ambient air and other places of the the historical area of the city of Puebla obtained with the team Converted ALPHA-CAM. (Author)

Evaluation Of Radioactivity Of Released Air During Postirradiation Examination At The RMI

International Nuclear Information System (INIS)

Prayitno, B.; Eko, Pudjadi

1998-01-01

Radioactivity evaluation of released air during post-irradiation examination at RMI has been done since january 1993 to december 1996. The released air radioactivity has been observed during post-irradiation examinations of irradiated fuels and structure materials in the hot cell. Analysis method employed has been by air sampling and measurement of the alpha and beta activities by using alpha beta aerosol LB 150 D model. Air release from RMI was sucked by using an air pump having 40 m3/hour capacity which is equipped with a 200 mm diameter filter paper. The filter paper is automatically counted by the detector of the instrument. The average of the daily maximum counting result in a month has been used as monthly data. It has been shown that there have been increase in the released air radioactivity caused by the post-irradiation examination activity. The data of the released air activity obtained have been used to calculate the radioactivity concentration and radioactivity on the soil surface based on Gauss Plumes. The calculation result have shown that the alpha and beta radioactivity concentration at stacks and on the soil surface are less then the set maximum permissible concentration (MPC)

Recent results on atmospheric radioactivity at Ibadan, Nigeria

International Nuclear Information System (INIS)

Adeniyi, M.O.; Oladiran, E.O.

2006-01-01

Measurements of alpha and beta radiations carried out in Ibadan (Nigeria) are presented. Activity of alpha radiation in the air is much lower than that of beta. The mean daily activity (Bq) ranged from 0.013 to 0.075 for alpha and from 1.475 to 76.136 for beta throughout the periods of investigation which include wet, dry and harmattan periods. The highest activity occurred during harmattan followed by wet period and the least was during the dry period. The harmattan dust originating from the Sahara desert is found to be radioactive. During wet period the aerosols and the condensation nuclei present in the atmosphere were also found to be radioactive to some extent. Background beta (β) and alpha (α) activities were found to have increased greatly over those earlier reported in the period between 1986/1987-2001/2002. Beta activity has two peaks at 19 and 6hLT while the peak time of alpha activity varies randomly throughout the periods of observation. The minima activities of alpha and beta occur throughout the day. The results showed that ambient α and β activities were highly correlated to atmospheric potential gradient

Localization of pig Na[sup +], K[sup +]-ATPase [alpha] and [beta] subunit genes to chromosome 4 by radioactive in situ hybridization

Energy Technology Data Exchange (ETDEWEB)

Lahbib-Mansais, Y.; Yerle, M.; Dalens, M.; Chevalet, C.; Gellin, J. (Centre de Recherches de Toulouse (France))

1993-01-01

Two genes coding for Na[sup +],K[sup +] -ATPase [alpha] and [beta] subunits are localized on pig chromosome 4, to the q1.6[yields]q2.3 and 1.3[yields]q2.1 regions, respectively, by radioactive in situ hybridization. According to nucleotide and amino acid sequence comparisons with different human isoforms of Na[sup +] ,K[sup +]-ATPase, these pig [alpha] and [beta] ATPase genes show strong homologies with human [alpha]1 and [beta] subunit ATPase genes, respectively. These results are discussed with respect to comparative mapping data of conserved genes in mammalian species. We showed that the pig cDNA probes encoding ATPase [alpha] and, [beta] genes reveal DNA polymorphism in Meishan an Large White pigs. 35 refs., 4 figs., 2 tabs.

Alpha spectrometry of thick sources. II. Application to the study of radioactive equilibria in uranium ores

International Nuclear Information System (INIS)

Acena Barrenechea, M.L.; Tormo Ferrero, M.J.

1977-01-01

A method for determining nuclide activities in 4n + 2 uranium series using alpha spectrometry of thick sources is described. This method has been applied to several uranium ores, showing different states of radioactive equilibria. The spectra from samples prepared by cold compression show some anomalies, due to the evolution and later decay of 219 Rn and daughters. This phenomenon must be taken in consideration when computing spectra line intensities. (author) [es

Radioactive food and environment contamination

International Nuclear Information System (INIS)

Yousif, A.M.

2001-01-01

The Food and Environment Control Centre of Abu Dhabi Municipality with the help of IAEA has established facilities for regular monitoring of food and environmental samples for radioactive contamination. The Centre is now capable of measuring gamma, beta as well as alpha activity in different types of samples. The main activities in the area of food monitoring are as follows: General monitoring of food gamma radionuclides in foodstuffs by high resolution gamma spectrometry; Determination of specific gamma radionuclides in foodstuffs by high resolution gamma spectrometry; Radiochemical determination of Sr-90 using liquid scintillation analyzer or by gas flow proportional counter; Measurement of gross alpha activity in drinking water

Connection of comparator circuit for pseudocoincidence counting of radioactive aerosols

International Nuclear Information System (INIS)

Fukatko, T.; Hajek, P.; Vidra, M.

1985-01-01

A block diagram is presented of the radioactive aerosol measuring instrument. The first counter records electric pulses corresponding to gross alpha activity and the second indicates pseudocoincidences derived from natural radioactivity. Data from the counters are converted to analog voltages which in the comparator circuit are compared such that the mean value of the output voltage is zero insofar as artificial radioactivity is not present on the filter. The designed connection of the comparator circuit allows the permanent adjustment of the whole measuring equipment to maximum sensitivity. (E.S.)

Alpha-in-air monitor for continuous monitoring based on alpha to beta ratio

International Nuclear Information System (INIS)

Somayaji, K.S.; Venkataramani, R.; Swaminathan, N.; Pushparaja

1997-01-01

Measurement of long-lived alpha activity collected on a filter paper in continuous air monitoring of ambient working environment is difficult due to interference from much larger concentrations of short-lived alpha emitting daughter products of 222 Rn and 220 Rn. However, the ratio between the natural alpha and beta activity is approximately constant and this constancy of the ratio is used to discriminate against short-lived natural radioactivity in continuous air monitoring. Detection system was specially designed for the purpose of simultaneous counting of alpha and beta activity deposited on the filter paper during continuous monitoring. The activity ratios were calculated and plotted against the monitoring duration up to about six hours. Monitoring was carried out in three facilities with different ventilation conditions. Presence of any long-lived alpha contamination on the filter paper results in increase in the alpha to beta ratio. Long-lived 239 Pu contamination of about 16 DAC.h could be detected after about 45 minutes of commencement of the sampling. The experimental results using prototype units have shown that the approach of using alpha to beta activity ratio method to detect long-lived alpha activity in the presence of short-lived natural activity is satisfactory. (author)

An interim report of the Subcommittee on Radioactive Waste Countermeasures: measures for radioactive waste treatment and disposal

International Nuclear Information System (INIS)

1984-01-01

The Subcommittee on Radioactive Waste Countermeasures has studied on the measures for land disposal of low-level radioactive wastes and ultra-low-level radioactive wastes and the measures for treatment and disposal of high-level radioactive wastes and transuranium wastes. The results of studies so far are presented as an interim report. In disposal of low-level radioactive wastes, the land disposal is being required increasingly. The measures according to the levels of radioactivity are necessary. For the ultra-low-level radioactive wastes, their occurrence in large quantities is expected along with reactor decommissioning. In disposal of the high-level radioactive wastes, the present status is a transition toward the practical stages. Transuranium wastes should increase in their arising in the future. (Mori, K.)

Assessment of environmental radioactivity for Sanliurfa region of southeastern Turkey

International Nuclear Information System (INIS)

Bozkurt, Ahmet; Yorulmaz, Nuri; Kam, Erol; Karahan, Gursel; Osmanlioglu, Ahmet Erdal

2007-01-01

This study assesses the level of background radiation for Sanliurfa province of southeastern Turkey. Measurements of outdoor gamma radiation (of terrestrial and cosmic origin) in air were performed at 112 locations using a plastic scintillator and the average absorbed dose was found as 60.9 nGy/h (corresponding to an effective dose of 74.7μSv/y). The radionuclide activity concentrations in 45 soil samples collected from the study area were measured through gamma-ray spectrometry and the average activities were determined as 20.8, 24.95 and 298.6 for the natural radionuclides 238 U, 232 Th and 40 K, respectively, and 9.08 Bq/kg for the fission product 137 Cs. The natural radioactivity sources resulted in an effective dose of 46.9μSv/y. The radioactivity levels of 53 drinking water samples were measured as 0.038 Bq/l for gross-alpha activity and 0.1324 Bq/l for gross-beta activity using gross-alpha and gross-beta counting methods (equivalent to an effective dose of 7.76μSv/y). When compared with the data available for other Turkish cities, the outdoor gamma doses and soil radioactivity concentrations obtained in this study indicate a background radiation level that falls within natural limits. On the other hand, the measured gross-alpha and -beta activities in drinking water are relatively higher

Analyzing relation between the radioactivity in lanthanum products and the origins of RE chlorides

International Nuclear Information System (INIS)

Wan Rongsheng

2004-01-01

Objective: To analyze the relation between the radioactivity in Lanthanum products and the origins of RE Chlorides. Methods: Using JY-38 plus sequential ICP spectrometer to examine the content of the uranium in the RE Chlorides. Using FJ-2603 low background alpha, beta measurement apparatus to measure total alpha and total beta activities of Lanthanum products. Results: The content of the uranium in the RE Chlorides is much lower in Baotou's than Hunan's. The radioactivity in Lanthanum products are made from the RE Chlorides of Baotou is much lower than that in Hunan's too. The radioactivity in Lanthanum products depends on the origins of RE Chlorides. Conclusion: The basic data were provided for radioactivity in Lanthanum products which are made from RE Chlorides of different places of China. The mathematical model was founded for the reasonable use of resource RE Chlorides

Environmental radioactivity measurement. Ispra 1990

International Nuclear Information System (INIS)

Dominici, G.; Risposi, L.

1992-01-01

In this report there are briefly described the measurements of environmental radioactivity performed during 1990 by the site survey group of the Radioprotection Division at the Joint Research Centre Ispra Establishment. Data are give on the concentrations of Sr-90, Cs-137, HTO and other radionuclides in precipitation, air, waters, herbage, milk and radioactive effluents. The environmental contamination is mainly a consequence of the nuclear accident of Chernobyl

Radioactive action code

International Nuclear Information System (INIS)

Anon.

1988-01-01

A new coding system, 'Hazrad', for buildings and transportation containers for alerting emergency services personnel to the presence of radioactive materials has been developed in the United Kingdom. The hazards of materials in the buildings or transport container, together with the recommended emergency action, are represented by a number of codes which are marked on the building or container and interpreted from a chart carried as a pocket-size guide. Buildings would be marked with the familiar yellow 'radioactive' trefoil, the written information 'Radioactive materials' and a list of isotopes. Under this the 'Hazrad' code would be written - three symbols to denote the relative radioactive risk (low, medium or high), the biological risk (also low, medium or high) and the third showing the type of radiation emitted, alpha, beta or gamma. The response cards indicate appropriate measures to take, eg for a high biological risk, Bio3, the wearing of a gas-tight protection suit is advised. The code and its uses are explained. (U.K.)

Naturally-occurring alpha activity

Energy Technology Data Exchange (ETDEWEB)

Mayneord, W V

1960-12-01

In view of the difficulties of assessing the significance of man-made radioactivity it is important to study for comparison the background of natural radioactivity against which the human race has evolved and lives. It is also important to define the present levels of activity so that it will be possible to detect and study as quickly as possible any changes which may occur owing to the release into the environment of new radioactive materials. Moreover, by the study of the behaviour of natural radioactivity light may be shed upon that of the artificially produced isotopes and a number of analogies traced between the two groups. These concepts have led to studies of naturally-occurring radioactive materials alongside a programme of research into fission products in food, water and air, as well as studies of the metabolism of both sets of materials in the human body. Since the last report there has been a useful increase in our knowledge of natural radioactivity in the biosphere, and its levels relative to the new man-made activities. These studies have necessitated technical developments, particularly in the methods of measuring and identifying alpha-ray emitters, to which group many of the more important natural radioactive materials belong.

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

International Nuclear Information System (INIS)

Liu Hongquan; Gan Jinbang; Chen Qi; Zhao Yunqing

1997-08-01

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

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

Closure of an analytical chemistry glove box in alpha laboratory

International Nuclear Information System (INIS)

Adelfang, P.; Aparicio, G.; Cassaniti, P.

1990-01-01

The works with plutonium are performed in gloves box, operated below atmospheric pressure, to protect the experimenters from this alpha-active material. After 12 years of continual processes, it was necessary the decommissioning of the chemistry glove box in our alpha-laboratory. A great deal of our attention was devoted to the working techniques because of extreme care needed to avoid activity release. The decommissioning includes the following main operations: a) Planning and documentation for the regulatory authority. b) Internal decontamination with surface cleaning and chelating agents. c) Measurement of the remainder internal radioactivity. d) Sealing of the glove ports and nozzles. e) Disconnection of the glove box from the exhaust duct. f) Design and construction of a container for the glove box. g) Transportation of the glove box from alpha-laboratory, to a transitory storage until its final disposal. The above mentioned operations are described in this paper including too: data of personal doses during the operations, characteristics and volumes of radioactive wastes and a description of the instrument used for the measurement of inside glove box activity. (Author) [es

Radioactive survey of the environment of the nuclear sites of French Nuclear Board: an overview; Bilan de la surveillance de la radioactivite dans l'environnement des sites du commissariat a l'energie atomique

Energy Technology Data Exchange (ETDEWEB)

Robeau, D; Montjoie, M; Sauve, A M; Laporte, J; Rahaplen, A; Alphonse, L; Huc, C [C.E.A./Institut de Protection et de Surete Nucleaire, Centre d' Etudes de Fontenay-aux-Roses, Fontenay-aux-Roses (France); Bensimon, C; Cissoko, G [Compagnie Internationale de Services Informatiques (France)

1992-07-01

C.E.A. has set up a network of radioactive survey around its nuclear sites. This network involves terrestrial, atmospheric and marine results of radioactive measurements. This survey is structured in four levels. The level 0 homogenizes stations of measurements, level 1 centralizes real-time measurements of gross {alpha} and {beta} measurements of atmospheric radioactivity, level 2 and 3 centralizes postponed {alpha}-{beta} spectrometric measurements of radioactivity on water, deposition, grass, vegetables. People can have a squint at these results of measurements using popular MINITEL telephonic network. (author)

Determination of detailed standards for transportation of radioactive materials by ships

International Nuclear Information System (INIS)

1979-01-01

The notification is defined under the regulations concerning marine transport and storage of dangerous things. Radioactive materials include hereunder uranium 233 and 235, plutonium 238, 239 and 241, their compounds and those materials which contain one or more than two of such materials. Materials whose quantities or quantities of components are less than 15 grams, and natural or depleted uranium are excluded. Permissible surface concentrations are 1/100,000 micro-curie per centi-meter 2 for radioactive materials emitting alpha rays, and 1/10,000 micro-curie per centi-meter 2 for radioactive materials not emitting alpha rays. Radioactive materials to be transported as L loads shall be not dispersing solid substances or those tightly enclosed in capsules, one of whose exterior sides at least is more than 0.5 centi-meter, having other several specified features. Other kinds of liquid and gas L loads are stipulated. Limits of radioactivity of L and A loads are provided for with tables attached. Transport conditions of A, BM and BU loads are fixed with bylaws. Leakages of BM and BU loads are also prescribed. Radioactive loads shall be marked by particular signals. Measures shall be taken to control exposures, which involve measurement of doses and exposure doses on board and appointment of exposure controllers. (Okada, K.)

The measurement of radioactivity in foodstuffs

International Nuclear Information System (INIS)

Maushart, R.

1988-01-01

The fallout of radioactivity from the Chernobyl accident gave rise to the need for large numbers of field and market surveys for radioactivity in foodstuffs in Germany. Due to the implementation of new government-mandated limits and a change in consumer attitudes, this need still persists today. In this article, the various methods available for measuring radioactivity in foodstuffs are reviewed and categorized by the type of information obtained and the degree of sample pretreatment required. A new category of instrument -- a consumer version of a simple NaI(Tl) gross gamma counter -- is introduced

General radioactive contamination of the biosphere measurements in the Netherlands 1974. Annual report Coordination Commission radioactivity measurements and Coordination Commission for the measurements of radioactivity and xenobiotic materials

Energy Technology Data Exchange (ETDEWEB)

1975-07-01

For several years, measurements have been performed in the Netherlands to determine radioactive contamination of the biosphere. These measurements are carried out by various institutes responsible to three ministries: the Ministery of 'Health and Environmental Protection', of 'Agriculture and Fisheries' and of 'Transport and Water', (Dutch: 'Verkeer en Waterstaat', under the supervision of the Coordination Commission Radioactive Measurements (CCRA)). Besides radionuclides, many other elements and compounds are considered harmful for man, animal and the environment. A systematic control of the extent of the contamination of the biosphere, in the same way as is in operation for radionuclides, has been proposed for a number of the most harmful contaminants of the biosphere. The measurements are divided into measurements for the National Measuring Programme and additional Measurements. The former include the analyses essential for an efficacious control of the radioactivity of the biosphere. Measurements are performed in air, soil, surface water, milk and in deposition on the surface of the earth. Besides the determination of the usual radionuclides, as performed up to 1970, deposited radioactivity and surface water are also tested for some other specific radionuclides which may be set free at nuclear installations. Finally, samples of milk and grass from the surroundings of nuclear reactors and water from drinking-waterreservoirs have been analysed. Results are given of determination of tritium in drinking water of four big cities, and of radionuclides in some fishery products from the Dutch coastal waters in view of the potential of some marine organisms to concentrate fission products and especially activated corrosion products from nuclear installations. Adiitionally are given the results of measurements by the licensees of the Dutch nuclear installations of samples from the surroundings of their plants.

The calculation of the detection efficiency in the calibration of gross alpha-beta systems

International Nuclear Information System (INIS)

Marian Romeo Calin; Ileana Radulescu; Alexandru Erminiu Druker

2013-01-01

This paper presents a method for efficiency calibration of a measuring alpha-beta system PROTEAN ORTEC, MPC-2000-DP, using standard radioactive sources. The system is used to measure gross alpha-beta activity concentrations in environmental samples. The calculated efficiencies of detection were subsequently introduced in the system for two working geometries: measuring geometry-gross alpha-beta ε α g = 31,37 ± 0.25 (%)-the alpha efficiency and ε β g 44.94 ± 0.69 (%)-the beta efficiency, where the spillover factor is X talk g = 25.59 ± 0.50 (%) and measuring geometry up alpha-beta ε α u 36.23 ± 0.29 (%)-the alpha efficiency and ε β u = 48.53 ± 0.74 (%)-the beta efficiency, where the spillover factor is X talk u 31.08 ± 0.60 (%). (author)

Report on air and water radioactivity measurement presented to the Commission for Protection against Ionizing Radiations of the State Secretary for Public Health (sessions of the 6 January and 18 February 1957). Report on the determination of radioactivity of mineral waters presented to High Council for Thermal cures of the State Secretary for Public Health (6 February 1957)

International Nuclear Information System (INIS)

Fallot, P.; Bugnard, L.

1957-06-01

The first part of this document discusses radioactivity measurement techniques which seem to be recommended for the monitoring of the release of radio-elements by civil and military applications of nuclear energy. These methods first concern air radioactivity due to uranium ore extraction, ore storage, air-cooling of piles, uranium fuel sheath failure, plutonium extraction and fission product processing, and nuclear explosion. Methods are discussed for the measurement of gas or aerosol radioactivity. The measurement of water radioactivity is then addressed by distinguishing measurements performed on rainfalls or snow, on effluents from nuclear plants. The second part discusses the determination of radioactivity of mineral waters. The authors describe the three main principles on which measurement methods are based: direct measurement of radioactivity of gases contained by water, direct measurement of gas radioactivity by the active deposit method, and measurement of alpha and beta radiations of the evaporation residue or of water precipitation product. Notably about radon measurement in waters, the instrumentation, dosing procedure, measurement sensitivity and precision are presented and discussed

Radioactivity measurements of soil samples in the Region Vranje (Bratoselce Village) for the period 2001-2004

International Nuclear Information System (INIS)

Eremic-savkovic, M.; Pantelic, G.; Tanaskovic, I.; Vuletic, V.; Javorina, L.

2006-01-01

Systematic examination of radioactive contamination of soil samples was established at the Institute for Occupational and Radiological Health. With the bombing of our country (Spring 1999) the monitoring of radioactivity has changed. We also measured the activities of uranium and it descendants. This paper presents the results of radioactivity monitoring of the soil in small area 700 m near village Bratoselce in region Vranje during the period 2001 - 2004. From 2001 to 2004, we collected different samples from this fenced area as well as outside this area assuming not to be contaminated, before, during and after decontamination. Some soil samples were made as a mix of small samples from a large area of location. Other samples were taken at the points formerly designated as contaminated or from shell-craters seen on the fenced area surface. All samples were analyzed by gamma spectrometry and measurements of alpha and beta activity. On the basis of measurements of soil activities, analysis of 238 U and 235 U, as well as in comparison with natural activity ratio being 21.4, it may be concluded that depleted uranium contamination was present both in the fenced area and outside it, because this ratio in the samples of soil was found to be 34 to 73. Natural activity in soil samples was slightly higher in relation to mean soil activity in Serbia. (authors)

Calibration method based on direct radioactivity measurement for radioactive gas monitoring instruments

International Nuclear Information System (INIS)

Yoshida, Makoto; Ohi, Yoshihiro; Chida, Tohru; Wu, Youyang.

1993-01-01

A calibration method for radioactive gas monitoring instruments was studied. In the method, gaseous radioactivity standards were provided on the basis of the direct radioactivity measurement by the diffusion-in long proportional counter method (DLPC method). The radioactivity concentration of the gas mixture through a monitoring instrument was determined by sampling the known volume of the gas mixture into the proportional counter used for the DLPC method. Since oxygen in the gas mixture decreased the counting efficiency in a proportional counter, the influence on calibration was experimentally estimated. It was not serious and able to be easily corrected. By the present method, the relation between radioactivity concentration and ionization current was determined for a gas-flow ionization chamber with 1.5 l effective volume. It showed good agreement with the results in other works. (author)

Determination of alpha particle detection efficiency of an imaging plate (IP) detector

International Nuclear Information System (INIS)

Rahman, N.M; Iida, Takao; Yamazawa, Hiromi; Moriizumi, Jun

2006-01-01

In order to determine the detection efficiency of the imaging plate (IP) detector, the true radioactivity of the alpha particles, which sampled in the collection media, should be known. The true radioactivity could be accurately predicted with the help of the reference alpha spectrometer measurement. The detection efficiency calculated for the IP was estimated with the theoretical curve and the experimental data. It is assumed that the air sample contained the decay products of both 222 Rn and 220 Rn series, the most significant sources of alpha particles. The present study estimated the detection efficiency of the IP as 39.3% with an uncertainty of 2.9 that is well enough to confirm the future use of the IP as a radiation detector. Experimental materials and methods are described. (S.Y.)

Results of radioactivity measurements on foodstuffs in Romania

International Nuclear Information System (INIS)

Ferdes, O.; Cojocariu, T.

1996-01-01

There are presented the results of gamma-spectrometric measurements performed between 1986-1995 on: milk and dairy products; meat and meat products; fish; wheat flour; fresh fruits and vegetables. The foodstuffs are sampled from some representative areas like: Bucharest, Bechet (affected by Kozloduj NPP, Bulgaria), Cernavoda, middle of Transylvania, Neamt. The radioactivity measurements are performed by high-resolution γ-ray spectrometry. There are identified and analysed mainly 134 Cs, 137 Cs, 40 K and, sometimes, other radionuclides. There are pointed out: the constancy of natural radionuclides amounts; the drastic increasing in radioactive concentration in May 1986; the seasonal variation of radioactivity in some food items; the time - exponential diminution of radioactivity in 1991-1995; and the maximum permitted levels of radioactive contamination of foodstuffs following a nuclear accident. (author)

System for measuring radioactivity of labelled biopolymers

International Nuclear Information System (INIS)

Gross, V.

1980-01-01

A system is described for measuring radioactivity of labelled biopolymers, comprising: a set of containers adapted for receiving aqueous solutions of biological samples containing biopolymers which are subsequently precipitated in said containers on particles of diatomite in the presence of a coprecipitator, then filtered, dissolved, and mixed with a scintillator; radioactivity measuring means including a detection chamber to which is fed the mixture produced in said set of containers; an electric drive for moving said set of containers in a stepwise manner; means for proportional feeding of said coprecipitator and a suspension of diatomite in an acid solution to said containers which contain the biological sample for forming an acid precipitation of biopolymers; means for the removal of precipitated samples from said containers; precipitated biopolymer filtering means for successively filtering the precipitate, suspending the precipitate, dissolving the biopolymers mixed with said scintillator for feeding of the mixture to said detection chamber; a system of pipelines interconnecting said above-recited means; and said means for measuring radioactivity of labelled biopolymers including, a measuring cell arranged in a detection chamber and communicating with said means for filtering precipitated biopolymers through one pipeline of said system of pipelines; a program unit electrically connected to said electric drive, said means for acid precipatation of biopolymers, said means for the removal of precipitated samples from said containers, said filtering means, and said radioactivity measuring device; said program unit adapted to periodically switch on and off the above-recited means and check the sequence of the radioactivity measuring operations; and a control unit for controlling the initiation of the system and for selecting programs

Radioactivity concentration measuring device for radiation waste containing vessel

International Nuclear Information System (INIS)

Goto, Tetsuo.

1994-01-01

The device of the present invention can precisely and accurately measure a radioactive concentration of radioactive wastes irrespective of the radioactivity concentration distribution. Namely, a Ge detector having a collimator and a plurality of radiation detectors are placed at the outside of the radioactive waste containing vessel in such a way that it can rotate and move vertically relative to the vessel. The plurality of radiation detectors detect radiation coefficient signals at an assumed segment unit of a predetermined length in vertical direction and for every predetermined angle unit in the rotational direction. A weight measuring device determines the weight of the vessel. A computer calculates an average density of radioactivity for the region filled with radioactivity based on the determined net weight and radiation coefficient signals assuming that the volume of the radioactivity is constant. In addition, the computer calculates the amount of radioactivity in the assumed segment by conducting γ -ray absorption compensation calculation for the material in the vessel. Each of the amount of radioactivity is integrated to determine the amount of radioactivity in the vessel. (I.S.)

Rapid screening of radioactivity in food for emergency response.

Science.gov (United States)

Bari, A; Khan, A J; Semkow, T M; Syed, U-F; Roselan, A; Haines, D K; Roth, G; West, L; Arndt, M

2011-06-01

This paper describes the development of methods for the rapid screening of gross alpha (GA) and gross beta (GB) radioactivity in liquid foods, specifically, Tang drink mix, apple juice, and milk, as well as screening of GA, GB, and gamma radioactivity from surface deposition on apples. Detailed procedures were developed for spiking of matrices with (241)Am (alpha radioactivity), (90)Sr/(90)Y (beta radioactivity), and (60)Co, (137)Cs, and (241)Am (gamma radioactivity). Matrix stability studies were performed for 43 days after spiking. The method for liquid foods is based upon rapid digestion, evaporation, and flaming, followed by gas proportional (GP) counting. For the apple matrix, surface radioactivity was acid-leached, followed by GP counting and/or gamma spectrometry. The average leaching recoveries from four different apple brands were between 63% and 96%, and have been interpreted on the basis of ion transport through the apple cuticle. The minimum detectable concentrations (MDCs) were calculated from either the background or method-blank (MB) measurements. They were found to satisfy the required U.S. FDA's Derived Intervention Levels (DILs) in all but one case. The newly developed methods can perform radioactivity screening in foods within a few hours and have the potential to capacity with further automation. They are especially applicable to emergency response following accidental or intentional contamination of food with radioactivity. Published by Elsevier Ltd.

Rapid screening of radioactivity in food for emergency response

International Nuclear Information System (INIS)

Bari, A.; Khan, A.J.; Semkow, T.M.; Syed, U.-F.; Roselan, A.; Haines, D.K.; Roth, G.; West, L.; Arndt, M.

2011-01-01

This paper describes the development of methods for the rapid screening of gross alpha (GA) and gross beta (GB) radioactivity in liquid foods, specifically, Tang drink mix, apple juice, and milk, as well as screening of GA, GB, and gamma radioactivity from surface deposition on apples. Detailed procedures were developed for spiking of matrices with 241 Am (alpha radioactivity), 90 Sr/ 90 Y (beta radioactivity), and 60 Co, 137 Cs, and 241 Am (gamma radioactivity). Matrix stability studies were performed for 43 days after spiking. The method for liquid foods is based upon rapid digestion, evaporation, and flaming, followed by gas proportional (GP) counting. For the apple matrix, surface radioactivity was acid-leached, followed by GP counting and/or gamma spectrometry. The average leaching recoveries from four different apple brands were between 63% and 96%, and have been interpreted on the basis of ion transport through the apple cuticle. The minimum detectable concentrations (MDCs) were calculated from either the background or method-blank (MB) measurements. They were found to satisfy the required U.S. FDA's Derived Intervention Levels (DILs) in all but one case. The newly developed methods can perform radioactivity screening in foods within a few hours and have the potential to capacity with further automation. They are especially applicable to emergency response following accidental or intentional contamination of food with radioactivity.

Calibration of alpha-track monitors for measurement of thoron

International Nuclear Information System (INIS)

Pearson, M.D.

1990-03-01

The US Department of Energy (DOE) Office of Remedial Action and Waste Technology established the Technical Measurements Center (TMC) at the DOE Grand Junction Projects Office (GJPO) to provide standardization, calibration, verification of data, quality assurance, and cost-effectiveness for environmental measurements associated with the various DOE remedial action programs. The GJPO Radon Laboratory has conducted a number of studies evaluating the precision and accuracy of alpha-track monitors for the measurement of airborne radon (Rn-222) concentration. These studies have demonstrated the usefulness of using alpha-track monitors to measure radon. Alpha-track devices have also been proposed for estimating concentrations of thoron (Rn-220). 9 refs., 7 figs., 4 tabs

Results of radioactivity measurements on foodstuffs in Romania

Energy Technology Data Exchange (ETDEWEB)

Ferdes, O [National Agency for Atomic Energy, Bucharest (Romania); Cojocariu, T [Institute for Food Research, Bucharest (Romania)

1997-12-31

There are presented the results of gamma-spectrometric measurements performed between 1986-1995 on: milk and dairy products; meat and meat products; fish; wheat flour; fresh fruits and vegetables. The foodstuffs are sampled from some representative areas like: Bucharest, Bechet (affected by Kozloduj NPP, Bulgaria), Cernavoda, middle of Transylvania, Neamt. The radioactivity measurements are performed by high-resolution {gamma}-ray spectrometry. There are identified and analysed mainly {sup 134}Cs, {sup 137}Cs, {sup 40}K and, sometimes, other radionuclides. There are pointed out: the constancy of natural radionuclides amounts; the drastic increasing in radioactive concentration in May 1986; the seasonal variation of radioactivity in some food items; the time - exponential diminution of radioactivity in 1991-1995; and the maximum permitted levels of radioactive contamination of foodstuffs following a nuclear accident. (author). 2 figs., 2 tabs., 8 refs.

Radioactivity measurements and control solutions

International Nuclear Information System (INIS)

Bartos, D.; Ciobanu, M.; Constantin, F.; Petcu, M.; Rusu, Al.

2003-01-01

In our department, in the last years, a new line of production has been developed devoted to the radioactivity measurements (portal monitor, gamma source detector, neutron monitor). Instruments of different design (hand-held, portals or steady-state) are intended for detection and locating of radioactive sources. Monitors are intended to detect radioactive and special nuclear materials in vehicles, pedestrians, luggage, as well as for illegal traffic prevention of radioactive sources. Monitors provide audio and visual alarm signals when radioactive and/or special nuclear materials are detected. Neutron dosimeters are designed for the determination of dose equivalent rate around neutron generators or sources. All devices can be recommended for use to officers of customs, border guard and emergency services, civil defense, fire brigades, police and military departments, nuclear research or power facilities. Incorporating micro controllers and new design, our products span almost all the spectra of radioactivity detection (gamma, beta, X and neutrons). No special knowledge is needed to operate these instruments as all service functions are performed automatically (self-tests, background updating and threshold calculation). The Portal monitor is intended to be a checkpoint in contamination control or in unauthorized traffic of radioactive materials. The portal monitor can be installed both in open, unprotected to environmental conditions areas or in enclosed areas. It may be used at pedestrian cross border points, at check points of Nuclear Power Plants, enterprises of nuclear industry, weapons manufacturing and storage plants, nuclear waste disposal and storage sites, at the entrances to steel plants, the post-offices and airports, the governmental offices, banks, private companies etc. The monitor provides audio alarming signals when radioactive and/or special nuclear materials are detected. The monitor consists in a portal frame, which sustains 5 detectors. Each

Radioactivity levels in surface water of lakes around Izmir / Turkey

International Nuclear Information System (INIS)

Doyurum, S.; Turkozu, D. A.; Aslani, M. A. A.; Aytas, S.; Eral, M.; Kaygun, A. K.

2006-01-01

Radioactivity presents in surface continental waters is mainly due to the presence of radioactive elements in the earth's crust, other artificial radionuclides have appeared due to such human activities as nuclear power plants, nuclear weapons testing and manufacture and use of radioactive sources It is well known that natural radionuclides can be effective as tracers for the different processes controlling the distribution of elements among dissolved and particulate phases in aquatic systems. The detection of high radionuclide concentrations was proposed as a public health problem in several areas and consequently studies into the risks of radionuclides were started in the 2000s. Especially, these radioactive substances in groundwater are an unwanted and involuntary risk factor from natural sources, not artificial sources. These radioactive substances include uranium, radon found in uranium series, and other radioactive substances such as radium and gross alpha. Uranium present in rock, soil, and natural materials, and is found in small quantities in air, water, and food that people always contact. In this project, lake water samples were collected from three lakes around Izmir-Turkey. In surface lake water samples, pH, mV and conductivity values were measured and alkaline content was determined titrimetrically. The uranium concentrations in the lake water samples were measured using uranium analyzer. The radioactivity concentrations related to gross radium isotopes, gross-? and gross-? activities in the surface lake water were determined. The correlation among some parameters for water samples and concentrations of uranium, activity concentration of gross radium isotopes, gross alpha and gross beta radioactivity are also discussed

Natural and Artificial Radioactivity in Drinkingwater in Malaga, Spain

Energy Technology Data Exchange (ETDEWEB)

Fernandez, M. C.; Duenas, C.; Gordo, E.; Canete, S. [Department of Applied Physics I, Faculty of Science, University of Malaga (Spain); Perez, M. [Department of Radiology and Health Physics, Faculty of Medicine, University of Malaga, Malaga (Spain)

2013-07-15

The measurement of radioactivity in drinking water permits us to determine the exposure of the population to radiation from the habitual consumption of water. An intensive study of the water supply in the city of Malaga during 2002-2010 has been carried out in order to determine the gross alpha and gross beta activities and natural and artificial radionuclides present in drinking water. A database on natural and artificial radioactivity in water was created. The results indicated that a high percentage of the water sample contains a total gross alpha and beta concentration of less than 0.10 Bq/L and 1 Bq/L, respectively. The main objectives were: (1) to analyse gross alpha and gross beta activities and to know the statistical distributions; (2) to study the levels of natural and artificial radionuclides; (3) to determine a possible mathematical correlation between the radionuclides and several factors. (author)

Measurement of environmental radioactivity. Ispra 1977

International Nuclear Information System (INIS)

Dominici, G.

1979-01-01

In this report there are briefly described the measurements of environmental radioactivity performed during 1977 by the site survey group of the Protection Division of the Euratom joint Research Centre - Ispra Establishement. Data are given on the concentrations of 90 Sr, 137 Cs and other radionuclides in precipitation, air, waters, herbage, milk and radioactive effluents. The environmental contamination is mainly world-wide fall out

Measurements of environmental radioactivity, Ispra 1988

International Nuclear Information System (INIS)

Dominici, G.

1989-01-01

In this report there are briefly described the measurements of environmental radioactivity performed during 1988 by the site survey group of the Radioprotection Division at the Joint Research Centre Ispra Establishment. Data are given on the concentrations of Sr-90, Cs-137, and other radionuclides in precipitation, air, waters, herbage, milk and radioactive effluents. The environmental contamination is mainly a consequence of the nuclear accident of Chernobyl

Measurement of environmental radioactivity. Ispra 1976

International Nuclear Information System (INIS)

Dominici, G.

1977-01-01

In this report there are briefly described the measurements of environmental radioactivity performed during 1976 by the site survey group of the Protection Division of the Euratom Joint Research Centre - Ispra Establisment. Data are given on the concentrations of 90 Sr, 137 Cs and other radionuclides in precipitation, air, waters, herbage milk and radioactive effluents. The environmental contamination is mainly world-wide fall out

Continuous monitoring for airborne alpha emitters in a dusty environment

International Nuclear Information System (INIS)

Seiler, F.A.; Newton, G.J.; Guilmette, R.A.

1988-01-01

Disposal of radioactive wastes in underground facilities requires continuous monitoring for airborne radioactive materials, both on the surface and underground. In addition to a natural background of nonradioactive and radioactive aerosols, there may be a sizeable dust contribution from ongoing work such as mining and vehicular traffic. In the monitoring of alpha-emitting radionuclides, these aerosols may lead to self-absorption in the source and a deterioration of the energy spectrum of the detected alpha particles. In this paper, the influence of a realistic background aerosol on the performance of an alpha monitoring system is evaluated theoretically. It is shown that depositing alpha emitters and background aerosol on a surface for counting leads rapidly to a considerable loss of counts, a deterioration of the alpha spectra, an eventual saturation of the count rates, and interference from the natural background of Rn daughters

Development of monitoring technology for environmental radioactivity

International Nuclear Information System (INIS)

Lee, Chang Woo; Cho, Young Hyun; Lee, M. H.; Choi, K. S.; Hong, K. H.; Sin, H. S.; Kim, M. K.; Pak, J. H.

2000-05-01

The accurate and reliable determination techniques of the radioactive isotopes in environmental samples are very important to protect public health from the potential hazards of radiation. Isolation and purification of radiostrontium from environmental aqueous sample was performed by using strontium selectively binding resin (Sr-spec) and strontium selectively permeable liquid membrane. Radioactivity of radiostrontium was measured by liquid scintillation counter coupled with dual counting window and spectrum unfolding method. With combustion apparatus a new determination of Tc-99 in the environmental samples was developed for overcoming demerits of conventional TBP extraction method. An optimized method for determining beta-emitting 2 41Pu in the presence of alpha-emitting nuclides was developed using a liquid scintillation counting system. A method for measuring Rn-222 and Ra-226 in aqueous sample using liquid scintillation counting technique has studied. On-line measurement system coupled with ion chromatography and portable liquid scintillation detector was developed. U and Th measured by inductively coupled plasma mass spectrometry (ICP-MS). The mehtod of flow-injection preconcentration for the analysis of U and Th in seawater was developed. A new electrodeposition method for alpha spectrometry was developed

Development of monitoring technology for environmental radioactivity

Energy Technology Data Exchange (ETDEWEB)

Lee, Chang Woo; Cho, Young Hyun; Lee, M. H.; Choi, K. S.; Hong, K. H.; Sin, H. S.; Kim, M. K.; Pak, J. H

2000-05-01

The accurate and reliable determination techniques of the radioactive isotopes in environmental samples are very important to protect public health from the potential hazards of radiation. Isolation and purification of radiostrontium from environmental aqueous sample was performed by using strontium selectively binding resin (Sr-spec) and strontium selectively permeable liquid membrane. Radioactivity of radiostrontium was measured by liquid scintillation counter coupled with dual counting window and spectrum unfolding method. With combustion apparatus a new determination of Tc-99 in the environmental samples was developed for overcoming demerits of conventional TBP extraction method. An optimized method for determining beta-emitting {sup 2}41Pu in the presence of alpha-emitting nuclides was developed using a liquid scintillation counting system. A method for measuring Rn-222 and Ra-226 in aqueous sample using liquid scintillation counting technique has studied. On-line measurement system coupled with ion chromatography and portable liquid scintillation detector was developed. U and Th measured by inductively coupled plasma mass spectrometry (ICP-MS). The mehtod of flow-injection preconcentration for the analysis of U and Th in seawater was developed. A new electrodeposition method for alpha spectrometry was developed.

210Po in Nevada groundwater and its relation to gross alpha radioactivity

Science.gov (United States)

Seiler, R.L.

2011-01-01

Polonium-210 (210Po) is a highly toxic alpha emitter that is rarely found in groundwater at activities exceeding 1 pCi/L. 210Po activities in 63 domestic and public-supply wells in Lahontan Valley in Churchill County in northern Nevada, United States, ranged from 0.01 ± 0.005 to 178 ± 16 pCi/L with a median activity of 2.88 pCi/L. Wells with high 210Po activities had low dissolved oxygen concentrations (less than 0.1 mg/L) and commonly had pH greater than 9. Lead-210 activities are low and aqueous 210Po is unsupported by 210Pb, indicating that the 210Po is mobilized from aquifer sediments. The only significant contributors to alpha particle activity in Lahontan Valley groundwater are 234/238U, 222Rn, and 210Po. Radon-222 activities were below 1000 pCi/L and were uncorrelated with 210Po activity. The only applicable drinking water standard for 210Po in the United States is the adjusted gross alpha radioactivity (GAR) standard of 15 pCi/L. 210Po was not volatile in a Nevada well, but volatile 210Po has been reported in a Florida well. Additional information on the volatility of 210Po is needed because GAR is an inappropriate method to screen for volatile radionuclides. About 25% of the samples had 210Po activities that exceed the level associated with a lifetime total cancer risk of 1× 10−4 (1.1 pCi/L) without exceeding the GAR standard. In cases where the 72-h GAR exceeds the uranium activity by more than 5 to 10 pCi/L, an analysis to rule out the presence of 210Po may be justified to protect human health even though the maximum contaminant level for adjusted GAR is not exceeded.

Design of automatic control and measurement software for radioactive aerosol continuity monitor

International Nuclear Information System (INIS)

Mao Yong; Li Aiwu

1997-01-01

The radioactive aerosol continuity measurement is very important for the development of nuclear industry, and it is the major method to measure and find out the leakage of radioactive material. Radioactive aerosol continuity monitor is the advanced method for the radioactive aerosol continuity measurement. With the development of nuclear industry and nuclear power station, it is necessary to design and automatic continuity measurement device. Because of this reason, the authors developed the first unit of radioactive aerosol continuity monitor and adopted the ministry appraisal. The design idea and method of automatic control and measurement for radioactive aerosol continuity monitor are discussed

Sensitive radioimmunoassay for detection of antibodies to recombinant human interferon-alpha A

International Nuclear Information System (INIS)

Palleroni, A.V.; Trown, P.W.

1986-01-01

A radioimmunoassay (RIA) for the detection of antibodies to recombinant human leukocyte interferon A (rHuIFN-alpha A) in human serum has been developed and validated against the standard antiviral neutralization bioassay (ANB). The assay measures the binding of 125 I-labeled rHuIFN-alpha A to immunoglobulins in serum. Aliquots of patients' sera are incubated with 125 I-rHuIFN-alpha A and the complexes formed between antibodies in the sera and the 125 I-rHuIFN-alpha A are precipitated with goat anti-human IgG serum. The radioactivity in the immune precipitate is a measure of the quantity of antibody (if present) in the serum. The sensitivity of this RIA is 5 ng of IgG/ml of serum

Small-scale hot facility for reprocessing and alpha research

International Nuclear Information System (INIS)

Abdel-Rassoul, A.A.

1976-01-01

The experimental hot facility at Inchas is planned for research activities related to the decontamination of radioactive wastes, analytical chemistry of alpha emitters and chemical treatment of spent UO 2 -Mg fuel samples. The design concept permits safe handling of source materials with radioactivity levels up to 10000Ci. The laboratory includes a reception area, process hall, a number of research laboratories and other facilities for chemical and physical analysis, nuclear measurements and health physics control. The radioactive waste management plant allows for control and decontamination of intermediate- and low-level laboratory effluents. Fixation of radioactive residues will be carried out in the sludge immobilization plant. High-level fission-product waste liquors are subject to preconcentration and transformation to a glassy matrix before ultimate storage. (author)

DEVELOPMENT OF AN ON-LINE, REAL-TIME ALPHA RADIATION MEASURING INSTRUMENT FOR LIQUID STREAMS

International Nuclear Information System (INIS)

Unknown

1999-01-01

The US Department of Energy (DOE) has expressed a need for an on-line, real-time instrument for assaying alpha-emitting radionuclides (uranium and the transuranics) in effluent waters leaving DOE sites to ensure compliance with regulatory limits. Due to the short range of alpha particles in water (approximately40 Im), it is necessary now to intermittently collect samples of water and send them to a central laboratory for analysis. A lengthy and costly procedure is used to separate and measure the radionuclides from each sample. Large variations in radionuclide concentrations in the water may go undetected due to the sporadic sampling. Even when detected, the reading may not be representative of the actual stream concentration. To address these issues, the Advanced Technologies Group of Thermo Power Corporation (a Thermo Electron company) is developing a real-time, field-deployable alpha monitor based on a solid-state silicon wafer semiconductor (US Patent 5,652,013 and pending, assigned to the US Department of Energy). The Thermo Water Alpha Monitor will serve to monitor effluent water streams (Subsurface Contaminants Focus Area) and will be suitable for process control of remediation as well as decontamination and decommissioning (D and D) operations, such as monitoring scrubber or rinse water radioactivity levels (Mixed Waste, Plutonium, and D and D Focus Area). It would be applicable for assaying other liquids, such as oil, or solids after proper preconditioning. Rapid isotopic alpha air monitoring is also possible using this technology. This report details the program's accomplishments to date. Most significantly, the Alpha Monitoring Instrument was successfully field demonstrated on water 100X below the Environmental Protection Agency's proposed safe drinking water limit--down to under 1 pCi/1. During the Field Test, the Alpha Monitoring Instrument successfully analyzed isotopic uranium levels on a total of five different surface water, process water, and

Mass measurement of radioactive isotopes

CERN Document Server

Kluge, H J; Scheidenberger, C

2004-01-01

The highest precision in mass measurements on short-lived radionuclides is obtained using trapping and cooling techniques. Here, the experimental storage ring (ESR) at GSI/Darmstadt and the tandem Penning trap mass spectrometer ISOLTRAP at ISOLDE/CERN play an important role. Status and recent results on mass measurements of radioactive nuclides with ESR and ISOLTRAP are summarized.

The French National Network for the Measurement of Environmental Radioactivity

International Nuclear Information System (INIS)

Jaunet, P.

2010-01-01

After Chernobyl accident in 1986, the government began to implement mechanisms to ensure the quality of measurements of environmental radioactivity and to assure the transparency of information on environmental radioactivity monitoring results. Within this context, the French National Network for the Measurement of Environmental Radioactivity (RNM), is created in 2002 under the Public Health Code. This network is developed under the auspices of ASN in collaboration with IRSN and in partnership with government departments, major nuclear licensees, health agencies and environmental protection associations. In order to centralize information on environmental radioactivity and to provide access to measurement results, a single database that includes an the results of measurements of radioactivity in the environment on the national territory is build and a new web-site www.mesure-radioactivite.fr is launched. It provides quick and easy access to this database. The quality of measurements is performed by a laboratory system through an ASN decision. Novel initiative in Europe, the French National Network for the Measurement of Environmental Radioactivity web-site gives the user keys to understand the measurement results on the radiological state of the environment. The site will be improved over the time taking into account the feedback of the users. (author)

TFTR alpha extraction and measurement: Development and testing of advanced alpha detectors: Final report

International Nuclear Information System (INIS)

Wehring, B.W.

1988-01-01

Advanced alpha-particle detectors made of heavy elements were investigated as alternatives to silicon surface-barrier detectors for the ''foil-neutralization technique'' of alpha-particle diagnostics in fusion reactors with high neutron backgrounds. From an extensive literature review, it was decided that HgI 2 would make a more suitable detector for alpha-particle diagnostics than other heavy element detectors such as CdTe. Thus, HgI 2 detectors were designed and fabricated. Experimental tests were performed to determine detector characteristics and detector responses to alpha particles. Radiation noise measurements were also performed using the North Carolina State University PULSTAR nuclear reactor for both the HgI 2 detectors and commercial Si(Au) surface barrier detectors. 15 refs., 1 fig

DEVELOPMENT OF AN ON-LINE, REAL-TIME ALPHA RADIATION MEASURING INSTRUMENT FOR LIQUID STREAMS

International Nuclear Information System (INIS)

1996-01-01

The Department of Energy (DOE) has expressed a need for an on-line, real-time instrument for assaying alpha-emitting radionuclides (uranium and the transuranics) in effluent waters leaving DOE sites to ensure compliance with regulatory limits. Due to the short range of alpha particles in water (approximately40 Tm), it is necessary now to intermittently collect samples of water and send them to a central laboratory for analysis. A lengthy and costly procedure is used to separate and measure the radionuclides from each sample. Large variations in radionuclide concentrations in the water may go undetected due to the sporadic sampling. Even when detected, the reading may not be representative of the actual stream concentration. To address these issues, Tecogen, a division of Thermo Power Corporation, a Thermo Electron company, is developing a real-time, field-deployable, alpha monitor based on a solid-state silicon wafer semiconductor (patent pending, to be assigned to the Department of Energy). The Thermo Alpha Monitor (TAM) will serve to monitor effluent water streams (Subsurface Contaminants Focus Area) and will be suitable for process control of remediation as well as decontamination and decommissioning operations, such as monitoring scrubber or rinse water radioactivity levels (Mixed Waste Focus Area and D and D Focus Area). It would be applicable for assaying other liquids, such as oil, or solids after proper preconditioning. Rapid isotopic alpha air monitoring is also possible using this technology. This instrument for direct counting of alpha-emitters in aqueous streams is presently being developed by Thermo Power under a development program funded by the DOE Environmental Management program (DOE-EM), administered by the Morgantown Energy Technology Center (METC). Under this contract, Thermo Power has demonstrated a solid-state, silicon-based semiconductor instrument, which uses a proprietary film-based collection system to quantitatively extract the

Measurement of radon daughters in air samples by alpha spectroscopy

International Nuclear Information System (INIS)

Acena, M.L.; Crespo, M.T.

1989-01-01

The concentration of radon progeny in air has been determined by alpha spectrometry measurement of polonium 214 and polonium 218. A known volume of air was passed through a filter, then the alpha activity was directly measured on this filter (Author)

Apparatus for measuring radioactive emissions

International Nuclear Information System (INIS)

Bohme, R.C.; Lazerson, M.M.

1984-01-01

Apparatus for measuring radioactive emissions from moving radioactive material comprises at least one radiation detector in a housing serving as a first radiation shield and in which at least one groove is formed to expose at least a portion of a receptor surface of the detector. The groove extends transverse to the direction of movement of the material over the detector. A second radiation shield may be located between at least a portion of the first shield and the detector. The material of the second shield is inherently less contaminated and emits secondary excitation radiation of lower energy than the first material. (author)

Present status of ambient dose equivalent rate and radioactive substance concentration measurements in working environment. (3) Measuring instruments for ionizing radiation in working environments

International Nuclear Information System (INIS)

Matsubara, Shohei

2006-01-01

In order to measure the airborne radioactive substance concentration in working environments, some kinds of sampler such as dust sampler and iodine sampler, measuring instruments (alpha and beta spectrometer, and liquid scintillation counter), monitor (dust-, iodine- and gas-monitor), survey meter for measuring gamma ray dose rate are stated. The measurement method of α, β and γ-ray nuclides and ambient dose-equivalent at 10 mm was explained. Some examples of the list of dust sampler, filter, tritium sampler, dust monitor, iodine monitor, gas monitor, and survey meter on the market are shown. There are so many kinds of measuring instruments for ionizing radiation in working environment that the best instrument for measurement should be selected. The environment conditions such as sample form, temperature and humidity have to be considered in order to evaluate the measurement values. (S.Y.)

Concentration of Radon Progeny in Air by Alpha Spectrometry Measurement

International Nuclear Information System (INIS)

Acena, M. L.; Crespo, M. T.

1989-01-01

The concentration of radon progeny in air has been determined by alpha spectrometry measurement of 214 Po and 318 Po. A known volume of air was passed through a filter, then the alpha activity was directly measured on this filter. (Author) 15 refs

Measurements on radioactive dusts over Calcutta

Energy Technology Data Exchange (ETDEWEB)

Chatterjee, S; Patro, A P; Basu, B; Bhattacharyya, R L; Hosain, F

1955-01-01

A brief report of the measurements of the radioactivity of rain water samples collected in Calcutta from April 29 to the middle of July 1954, is presented. Measurements of energy and half lives indicated that the dusts originated from nuclear explosions.

Measurement of environmental radioactivity in Toki district

International Nuclear Information System (INIS)

1981-11-01

When the Institute of Plasma Physics, Nagoya University, expressed the hope to move into Toki district, the environmental problems accompanying the movement were discussed. The effect of the radioactivity leaking from the nuclear facility on human bodies must be far smaller than that of natural radiation, and for the purpose, the amount and fluctuation range of the natural radiation in the district must be known. The initial objectives of this cooperative research were to study on environmental radiation and to make a Geiger counter for the measurement. In 1981, a scintillation counter will be completed, and using a multi-channel pulse height analyzer, the nuclides which are the source of environmental radiation emission will be identified, and the tritium in natural water will be detected. Thus, the evaluation of environmental radiation can be carried out, and the situation before the movement of the research facility can be grasped. In this paper, the natural radioactivity in earth, atmosphere and water and cosmic ray, artificial radioactivity, and environmental radiation exposure dose are reported. Also, the manufacture of a GM counter measuring instrument and the measurements of cosmic ray background, typical earth samples and environmental radioactivity with the GM counter are reported. The related data are attached. (Kako, I.)

International conventions for measuring radioactivity of building materials

International Nuclear Information System (INIS)

Tan Chenglong

2004-01-01

In buildings, whether civil or industrial, natural radioactivity always occurs at different degrees in the materials (main building materials, decorative materials). Concerns on radioactivity from building materials is unavoidable for human living and developing. As a member of WTO, China's measuring method of radioactivity for building materials, including radionuclides limitation for building materials, hazard evaluation system etc, should keep accordance with the international rules and conventions. (author)

Lifetime and g-factor measurements of excited states using Coulomb excitation and alpha transfer reactions

Energy Technology Data Exchange (ETDEWEB)

Guevara, Z. E., E-mail: zjguevaram@unal.edu.co; Torres, D. A., E-mail: datorresg@unal.edu.co [Physics Department, Universidad Nacional de Colombia, Bogotá D.C. (Colombia)

2016-07-07

In this contribution the challenges in the use of a setup to simultaneously measure lifetimes and g-factor values will be presented. The simultaneous use of the transient field technique and the Doppler Shift Attenuation Method, to measure magnetic moments and lifetimes respectively, allows to obtain a complete characterization of the currents of nucleons and the deformation in excited states close to the ground state. The technique is at the moment limited to Coulomb excitation and alpha-transfer reactions, what opens an interesting perspective to consider this type of experiments with radioactive beams. The use of deep-inelastic and fusion-evaporation reactions will be discussed. An example of a setup that makes use of a beam of {sup 106}Cd to study excited states of {sup 110}Sn and the beam nuclei itself will be presented.

Quantitative autoradiography - a method of radioactivity measurement

International Nuclear Information System (INIS)

Treutler, H.C.; Freyer, K.

1988-01-01

In the last years the autoradiography has been developed to a quantitative method of radioactivity measurement. Operating techniques of quantitative autoradiography are demonstrated using special standard objects. Influences of irradiation quality, of backscattering in sample and detector materials, and of sensitivity and fading of the detectors are considered. Furthermore, questions of quantitative evaluation of autoradiograms are dealt with, and measuring errors are discussed. Finally, some practical uses of quantitative autoradiography are demonstrated by means of the estimation of activity distribution in radioactive foil samples. (author)

Measurements of natural radioactivity in phosphate fertilizers

International Nuclear Information System (INIS)

Ioannides, K.G.; Mertzimekis, T.J.; Papachristodoulou, C.A.; Tzialla, C.E.

1997-01-01

The natural radioactivity, mainly due to radium ( 226 Ra), in phosphate fertilizers used in north-western Greece has been measured by γ-spectroscopy. Also radioactivity measurements were performed in soil samples and were compared to samples from undisturbed soils. 226 Ra belongs to the 238 U chain and is the precursor of radon gas ( 222 Rn). The radon concentrations in warehouses, where large quantities of fertilizers are kept, were measured with CR-39 SSNTDs. The radium concentrations in the fertilizers ranged from 0 to 4584 Bq kg -1 and the radon concentrations in warehouses were measured 540-3320 Bq m -3 . The results are discussed from the radiation protection point of view

Hydration products and mechanical properties of hydroceramics solidified waste for simulated Non-alpha low and intermediate level radioactive wastes

International Nuclear Information System (INIS)

Wang Jin; Hong Ming; Wang Junxia; Li Yuxiang; Teng Yuancheng; Wu Xiuling

2011-01-01

In this paper, simulated non-alpha low and intermediate level radioactive wastes was handled as curing object and that of 'alkali-slag-coal fly ash-metakaolin' hydroceramics waste forms were prepared by hydrothermal synthesis method. The hydration products were analyzed by X ray diffraction. The composition of hydrates and the compressive strength of waste forms were determined and measured. The results indicate that the main crystalline phase of hydration products were analcite when the temperature was 150 to 180 degree C and the salt content ratio was 0.10 to 0.30. Analcite diffraction peaks in hydration products is increasing when the temperature was raised and the reaction time prolonged. Strength test results show that the solidified waste forms have superior compressive strength. The compressive strength gradually decreased with the increase in salt content ratio in waste forms. (authors)

Concept design of a time-of-flight spectrometer for the measurement of the energy of alpha particles.

Science.gov (United States)

García-Toraño, E

2018-04-01

The knowledge of the energies of the alpha particles emitted in the radioactive decay of a nuclide is a key factor in the construction of its decay scheme. Virtually all existing data are based on a few absolute measurements made by magnetic spectrometry (MS), to which most other MS measurements are traced. An alternative solution would be the use of time-of-flight detectors. This paper discusses the main aspects to be considered in the design of such detectors, and the performances that could be reasonably expected. Based on the concepts discussed here, it is estimated that an energy resolution about 2.5keV may be attainable with a good quality source. Copyright © 2017 Elsevier Ltd. All rights reserved.

Turbidimetry: Measurement of X- or γ-Absorption or Measurement of Natural Radioactivity?

International Nuclear Information System (INIS)

Courtois, G.; Anguenot, F.; Magloire, C.

1970-01-01

Turbidity may be measured by radioactive means on the basis of the two following methods: (a) measurement of X- or γ-absorption in a nuclear gauge, corresponding to a measurement of the density of the medium; (b) in-situ measurement of the natural radioactivity of the sediment in suspension. The authors used the two methods simultaneously: by constructing a prototype γ-absorption measuring gauge ( 241 Am) whose characteristics are described and by seeking to determine the true precision of such an apparatus (limit of precision approximately 1.5 g/1 ± 500 mg); carrying out in-situ measurements of natural radioactivity of sediment in suspension, in particular in estuaries (limit for the Loire approximately 0.7 g/l ± 250 mg). The advantages and disadvantages of each of these two methods are critically analysed. It would appear, in particular: that the natural radioactivity gauge is much less sensitive to local salinity and is a valuable tool in estuaries, of which there are many in Europe, of variable salinity and of generally high turbidity; that being robuster and simpler, it is less sensitive to different parameters (electronic drifts, geometric variations, etc. ). On the other hand, it must be calibrated for each site and periodically on the same site. Further, it can only be used in a clayey medium. Particulars are given for the use of each of these instruments. (author) [fr

Turbidimetry: Measurement of X- or γ-absorption or measurement of natural radioactivity?

International Nuclear Information System (INIS)

Courtois, G.; Anguenot, F.; Magloire, C.

1970-01-01

Turbidity may be measured by radioactive means on the basis of the two following methods: (a) measurement of X- or γ-absorption in a nuclear gauge, corresponding to a measurement of the density of the medium; (b) in-situ measurement of the natural radioactivity of the sediment in suspension. The authors used the two methods simultaneously: by constructing a prototype γ-absorption measuring gauge ( 241 Am) whose characteristics are described and by seeking to determine the true precision of such an apparatus (limit of precision approximately 1. 5 g/l ± 500 mg); carrying out in-situ measurements of natural radioactivity of sediment in suspension, in particular in estuaries (limit for the Loire approximately 0.7 g/l ± 250 mg). The advantages and disadvantages of each of these two methods are critically analysed. It would appear, in particular: that the natural radioactivity gauge is much less sensitive to local salinity and is a valuable tool in estuaries, of which there are many in Europe, of variable salinity and of generally high turbidity; that being robuster and simpler, it is less sensitive to different parameters (electronic drifts, geometric variations, etc.). On the other hand, it must be calibrated for each site and periodically on the same site. Further, it can only be used in a clayey medium. Particulars are given for the use of each of these instruments. (author) [fr

Measurements of natural radioactivity in historical glasses

International Nuclear Information System (INIS)

Kierzek, J.; Kunicki-Goldfinger, J.J.; Kasprzak, A.J.

2000-01-01

Natural radioactive components of historical glasses and two methods of the respective measurement of the radioactivity are discussed. The evaluation of radioactivity of glass objects using a Geiger-Mueller counter and high-resolution gamma ray spectrometry is presented. A survey of the Warsaw National Museum glass collection with a Geiger-Mueller counter allowed distinguishing the vessels made of potassium and sodium glass by their level of natural radioactivity. Gamma spectrometry, on the other hand, enables estimating a specific radionuclide content. Special attention is given to uranium glasses. One 19th century Bohemian vessel, coloured with a uranium compound, was carefully examined using gamma spectrometry. K 2 O and U content were estimated to be 16.2 and 0.33%, respectively. (orig.)

Preliminary study on the analysis of alpha emitters at working places in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Kim, Hanna; Kim, Jeong In; Lee, Byoungil [Korea Hydro and Nuclear Power Co., Seoul (Korea, Republic of); Yoon, Suk Won [Korea Institute of Radiological and Medical Sciences National Radiation Emergency Medical Center, Seoul (Korea, Republic of)

2012-10-15

Over sea nuclear power plants have been reported cases of internal contamination by alpha nuclides. In many cases, stations encountered significant alpha contamination when aged/legacy equipment was disturbed or handled. Under normal operating conditions, transuranic radionuclides are contained within the fuel rods and therefore are not a contributor to radioactive contamination within a facility. However, transuranic radionuclides result from the presence of tramp-uranium contamination on the exterior of fuel elements. Fuel failures may develop during operating cycles due to a variety of causes, ranging from manufacturing defects to mechanical or abrasive damage. In case of domestic nuclear power plants, the pressure tube replacements in Wolsong Unit 1 and steam generator replacements in Kori Unit 1 were done. Due to deterioration of equipment in accordance with the long-term operation, the domestic nuclear power plants are expected to improve the facilities and the probability of internal exposure from alpha emitters is increasing. The domestic nuclear power plants are only keeping alpha radionuclides of the effluent from the exterior under constant surveillance. The representative areas of CV are just carried out continuous alpha monitoring in during a unit outage. So far, there is no other case with alpha nuclides analysis. As the domestic nuclear power plants are expected to improve the facilities, it is the time to take proactive measures to deal with internal contamination by alpha emitting radioactive elements. In this paper, the possible risk of internal exposure is based on preliminary experiments on the analysis of alpha emitting radioactive elements at working places in nuclear power plants.

Previous study for the setting up and optimization of detection of ZnS(Ag) scintillation applied to the measure of alpha radioactivity index

International Nuclear Information System (INIS)

Pujol, L.; Suarez-Navarro, J.A.; Montero, M.

1998-01-01

The determination of radiological water quality is useful for a wide range of environmental studies. In these cases, the gross alpha activity is one of the parameters to determine. This parameter permits to decide if further radiological analyses are necessary in order to identify and quantify the presence of alpha emitters in water. The usual method for monitoring the gross alpha activity includes sample evaporation to dryness on a disk and counting using ZnS(Ag) scintillation detector. Detector electronics is provided with two components which are adjustable by the user the high-voltage applied to the photomultiplier tubes and the low level discriminator that is used to eliminate the electronic noise. The high-voltage and low level discriminator optimization are convenient in order to reach the best counting conditions. This paper is a preliminary study of the procedure followed for the setting up and optimization of the detector electronics in the laboratories of CEDEX for the measurement of gross alpha activity. (Author)

The protective role of ceramic filters against natural radioactivity of water

International Nuclear Information System (INIS)

Domanski, T.; Bakir, Y.Y.Y.; El-Zenki, S.; Bem, H.

1992-01-01

The paper presents results of measurements of the natural radioactivity of tap water where samples were taken in front of, and behind the ceramic filter commonly used in houses for the purification of tap water. Altogether, 289 samples were taken, processed and measured during 1985-1986 in Kuwait. Results reveal the fact that ceramic filters reduce substantially the natural radioactivity in water (the 'gross' alpha activity reduced by the factor 2.18 ± 18%; the 'gross' beta by 1.53 ± 1.6%. (author)

Calibration of new measuring systems to detect emissions of radioactive noble gases

International Nuclear Information System (INIS)

Winkelmann, I.; Kreiner, H.J.

1977-12-01

This report describes the calibration of different systems for the integral measurement of radioactive noble gases and the calibration of a measuring chamber for the detection of individual nuclides of radioactive noble gases in the gaseous effluent of nuclear power plants. For these measuring chambers the calibration factors for Kr-85 and Xe-133 are given as well as the detection limits to be obtained with these measuring systems for several radioactive noble gases present in the gaseous effluent at the stack of nuclear power plants. Calibration factors for Kr-85 and Xe-133 and the detection limits of this measuring method for the detections of individual nuclides of radioactive noble gases in air samples are defined taken wirh a high pressure compressor in pressure flasks an measured on a Ge(Li)-semiconductor spectrometer (pressure flask measuring method). A measuring equipment is described and calibrated which allows simultaneous measurement of activity concentration of radioactive noble gases and radioactive aerosols with a sensitivity of 2 x 10 -7 Ci/m 3 for radioactive gases and 1 x 10 -9 Ci/m 3 for radioactive particulates at a background radiation of 1 R/h. This paper is an additional report to our STH-Bericht 3/76, 'Calibration of measuring equipment for monitoring of gaseous effluents from nuclear power plants', which specifies a procedure for the calibration of measuring chambers for monitoring of gaseous radioactive effluents from nuclear power plants /1/. The calibration system used here makes it possible to simultaneously calibrate several noble gas measuring devices. (orig.) [de

Radioactive dust concentration around the Ranger uranium mine

International Nuclear Information System (INIS)

Kavasnicka, Jiri.

1988-07-01

Environmental dust sampling and wind direction/velocity monitory were carried out between July and November 1987 at five points around the Ranger Uranium Mines project near Jabiru, Northern Territory. The measured radioactive dust alpha activities in the air were used to calculate the radioactive dust source-term and develop a site-specific air dispersion model which takes the depletion of the dust plume into account. The above model was used to estimate the effective committed dose equivalent as 15 μSv/year to children in Jabiru East. This corresponds to an increase of 2.6 x 10 -4 Bq. m -3 in the annual average dust alpha activity above the natural background. The dose to the children in Jabiru is about 5 μSv/year, so that the critical group of the public is in Jabiru East. 12 refs., 11 tabs., 2 maps

Distribution measurement of 60Co target radioactive specific activity

International Nuclear Information System (INIS)

Li Xingyan; Chen Zigen; Ren Min

1994-01-01

Radioactive specific activity distribution of cobalt 60 target by irradiation in HFETR is a key parameter. With the collimate principle, the under water measurement device and conversion coefficient which is get by experiments, and the radioactive specific activity distribution is obtained. The uncertainty of measurement is less than 10%

Interpretation of non destructive combined nuclear measurements for the characterization of radioactive wastes and waste packages

International Nuclear Information System (INIS)

Raoux, Anne-Cecile

2000-01-01

Nuclear industry produces radioactive waste and is faced with the problem of their management, especially for those which have a long radioactive decay time. In view to be able to define the best storage solution, alpha bearing solid waste are identified by different specific parameters (alpha, beta activities,... ). Then, the storage and cost optimizations are essential stakes. The quantification of these parameters can be obtained by the implementation of non destructive nuclear measurement methods generally associated with information from the manufacturing process of the waste. The works presented in this report are dedicated to two complementary aspects of the nuclear waste management issue. On the one hand, an experimental study concerning the possibilities of the prompt and delayed neutron counting with only one measurement result from neutron interrogation is presented. On the other hand, an interpretation method allowing the determination of the waste package specific parameters and their uncertainties has been developed. It is based on random trials which allow to describe the parameters as statistical distributions (Monte Carlo method). It was resulting in the realization of a software called RECITAL (information combination and solving process by random trials). This software was applied to the isotopic quantification of "2"3"5U and "2"3"9Pu from prompt and delayed signals of neutron interrogation. It was also used to demonstrate the complementarity of photofission interrogation with neutron interrogation in view to correct "2"3"8U interference on the delayed fission signal, especially when "2"3"8U contribution is similar to "2"3"5U and "2"3"9Pu ones. (author) [fr

Design and construction of a system for determining Radon-222 through Alpha spectroscopy

International Nuclear Information System (INIS)

Bonifacio, J.; Iturbe, J.L.

1992-02-01

The study of the present work consists on designing a system to measure gas 222 Rn, using a surface barrier detector, in order to obtaining a more accuracy measure of this isotope by means of an alpha particle spectra and thus to try to avoid the influence of the radioactivity of the isotope descendants of short half life, which are also emitting of alpha particles, since by other methods its should make a series of corrections to obtain the real value of the radon activity. (Author)

Measurement of weak radioactivity

CERN Document Server

Theodorsson , P

1996-01-01

This book is intended for scientists engaged in the measurement of weak alpha, beta, and gamma active samples; in health physics, environmental control, nuclear geophysics, tracer work, radiocarbon dating etc. It describes the underlying principles of radiation measurement and the detectors used. It also covers the sources of background, analyzes their effect on the detector and discusses economic ways to reduce the background. The most important types of low-level counting systems and the measurement of some of the more important radioisotopes are described here. In cases where more than one type can be used, the selection of the most suitable system is shown.

Modern systems for environmental radioactivity measurements

International Nuclear Information System (INIS)

Cimpean, A.; Borodeanu, C.

1995-01-01

The system for environmental radioactivity measurements with automatic data transmission represents a better solution for nuclear safety assurance. The 'intelligent probe' will be of real use for surveying the environmental radioactivity. The probes work independently. They measure the dose rate and store the data in their internal memory. Many such probes can be spread all over a large area. They are able to measure dose rate from the background level up to high catastrophic levels. A central computer 'asks' periodically the probes to send their stored data. This computer stores the data from many probes over a long time. It can show in 'windows' manner the dose rate from any probe (either in a numerical or graphical way), the position on a map of every probe and the corresponding results of the measurements. In can alert, if an alarm threshold is crossed or it can print on a printer the data for any single probe. (author)

Alpha and beta detection and spectrometry

International Nuclear Information System (INIS)

Saro, S.

1984-01-01

The theory of alpha and beta radioactive decay, the interaction of alpha and beta particles with matter, and their detection and spectrometry are dealt with in seven chapters: 1. Alpha transformation of atomic nuclei; 2. Basic properties of detectors and statistics of detection; 3. Alpha detectors and spectrometers; 4. Applications of alpha detection and spectrometry; 5. Beta transformation of atomic nuclei; 6. Beta particle detectors and spectrometers; 7. Detection of low energy beta particles. Chapter 8 is devoted to sampling and preparation of samples for radiometry. (E.F.)

Estimation of low level gross alpha activities in the radioactive effluent using liquid scintillation counting technique

International Nuclear Information System (INIS)

Bhade, Sonali P.D.; Johnson, Bella E.; Singh, Sanjay; Babu, D.A.R.

2012-01-01

A technique has been developed for simultaneous measurement of gross alpha and gross beta activity concentration in low level liquid effluent samples in presence of higher activity concentrations of tritium. For this purpose, alpha beta discriminating Pulse Shape Analysis Liquid Scintillation Counting (LSC) technique was used. Main advantages of this technique are easy sample preparation, rapid measurement and higher sensitivity. The calibration methodology for Quantulus1220 LSC based on PSA technique using 241 Am and 90 Sr/ 90 Y as alpha and beta standards respectively was described in detail. LSC technique was validated by measuring alpha and beta activity concentrations in test samples with known amount of 241 Am and 90 Sr/ 90 Y activities spiked in distilled water. The results obtained by LSC technique were compared with conventional planchet counting methods such as ZnS(Ag) and end window GM detectors. The gross alpha and gross beta activity concentrations in spiked samples, obtained by LSC technique were found to be within ±5% of the reference values. (author)

The natural radioactivity in Guarani aquifer groundwater, Brazil.

Science.gov (United States)

Bonotto, D M; Bueno, T O

2008-10-01

The measurements of gross alpha and gross beta radioactivity in groundwater samples from Guarani aquifer in Brazil are reported in this paper together with the activity concentration of the natural dissolved radionuclides (40)K, (238)U, (234)U, (226)Ra, (222)Rn, (210)Po, (210)Pb, (232)Th, (228Th), and (228)Ra. Most of the gross alpha radioactivity values were below the critical level of detection corresponding to 1 mBq/L, however, the whole data set for the gross beta radioactivity and radionuclides (40)K, (238)U, (234)U, (226)Ra, (222)Rn, (210)Po, (210)Pb, and (228)Ra was submitted to a statistical treatment, considering class intervals arranged in geometric progression, because of the great variability of the activity. The analysis indicated lognormal distribution of the data, as usually observed in samples taken from the natural context. An inverse relationship between the gross alpha and gross beta activity has been identified and is related to an increase in the K content in the water. The mobility coefficient has been estimated for (238)U, (226)Ra, (232)Th and (228)Ra in Guarani aquifer and the results indicated that the radioelement solubility in the studied system varies according to the following order: radium>uranium>thorium. The implications of the data obtained in terms of standards established for defining the drinking water quality have also been discussed.

Conversion of an Alpha CAM Monitor of Victoreen calibrated of factory for plutonium in a measurement monitor of radon in the atmosphere; Conversion de un monitor Alpha CAM de la Victoreen calibrado de fabrica para plutonio en un monitor para medicion de radon en la atmosfera

Energy Technology Data Exchange (ETDEWEB)

Moreno y Moreno, A. [Departamento de Apoyo en Ciencias Aplicadas, Benemerita Universidad Autonoma de Puebla, Puebla (Mexico)

2004-07-01

It is presented in this work the conversion of a monitor ALPHA CAM of the monitor Victoreen gauged of it manufactures for plutonium in a monitor for radon mensuration in the atmosphere. Those units in that the radon measures are expressed are: peak curies/unit of volume of air to sampling. This way one has to gauge and to supplement the software and the parts that the old one monitor for plutonium. It requires. This task implies: a) To calibrate and to determine the efficiency of the detector of accustomed to state of 1700 mm{sup 2} for alpha particles coming from the radioactive series of the radon. b) to connect in series and to calibrate a flow measurer of air in it lines with the detector. Measures are presented of the ambient air and other places of the the historical area of the city of Puebla obtained with the team Converted ALPHA-CAM. (Author)

Absolute radioactivity measurements

International Nuclear Information System (INIS)

Weiss, H.M.

1983-01-01

The radioactivity of a thin specimen can be determined directly, i.e. without reference to a standard and without knowing decay data, except for half-life, by means of counting at a given solid angle and by 4 πβ-γ coincidence measurement. In accordance with section 7 of the law on units, it is the task of PTB not only to represent the units and its derivation, but also to work out methods of adjusting national prototypes and normals to international prototypes and etalons in accordance with the international metre convention. (DG) [de

Alpha contamination assessment for D ampersand D activities: Technology overview

International Nuclear Information System (INIS)

Conaway, J.G.; Rawool-Sullivan, M.W.; MacArthur, D.W.

1996-02-01

Instruments based on the principle of Long-Range Alpha Detection (LRAD) detect the ions created in ambient air by Ionizing radiation, particularly alpha radiation, interacting with air molecules. Using either an electrostatic field or forced convection, these ions can be transported to a detection grid where the ions produce a small current that is measured with a sensitive electrometer. LRAD-based instruments can give separate, simultaneous measurements of alpha-emitting solids and inert radioactive gases such as radon. LRAD-based instruments assess surface contamination on an entire object or large surface area in a single, rapid measurement, including relatively inaccessible areas such as interior surfaces of pipes and process equipment. The LRAD concept is well proven and has been developed into a range of different radiation detection devices. This paper presents an overview of the technology, while several associated papers explore specific applications in greater detail

Radioactivity in food crops from high background radiation area in southwest area

International Nuclear Information System (INIS)

Shanthi, G.; Maniyan, C.G.; Allan Gnana Raj, G.; Thampi Thanka Kumaran, J.

2009-01-01

The study was carried out to evaluate radioactive concentration in food crops grown in naturally high-background radiation areas in southwest India. Seventeen varieties of food crops were collected from different parts of Kanyakumari district. The gross alpha and beta activities of the collected samples were measured using alpha scintillation counter and low beta counter respectively. The alpha activity was maximum in tapioca (497± 72 Bq kg -1 ) and the beta activity was maximum in paddy grain (10,946±583 Bq kg -1 ). The gamma activity of the food samples was studied by measuring the activity concentration of the radionuclides ( 226 Ra, 228 Th, 238 U, 40 K) in the food crops. The radioactivity content of the food crops from high-background radiation area was higher when compared to similar samples collected from low-background radiation area. The daily radionuclide intake from the food crops grown and consumed by the public was 127.696 Bq and daily internal dose resulting from ingestion of radionuclides in food was 2.34 μSv. (author)

Natural and Artificial Radioactivity in Drinking Water in Malaga, Spain

International Nuclear Information System (INIS)

Duenas, C.; Fernandez, M.C.; Gordo, E.; Canete, S.; Perez, M.

2011-01-01

Water has a vast importance for numerous human activities, so that securing supplies of drinking water of a standard quality is becoming more and more difficult. The measurement of radioactivity in drinking water permits us to determine the exposure of the population to radiation from the habitual consumption of water. The occurrence of radionuclides in drinking water gives rise to internal exposure of humans, directly on the decay of radionuclides taken into the body through ingestion and inhalation and indirectly when they are incorporated as part of the food-chain The measurement of radioactivity in drinking water permits us to determine the exposure of population to radiation from the habitual consumption of water. An intensive study of the water supply in the city of Malaga during 2002-2010 has been carried out in order to determine the gross alpha activities, gross beta activities and natural and artificial radionuclides present in drinking water. A data base on natural and artificial radioactivity in water was produced. The results indicated that a high percentage of the water sample contains a total gross alpha and beta less than 0.10 Bq/l and 1 Bq/l respectively. The main objectives were: 1) to analyses gross alpha and gross beta activities and to know the statistical distributions. 2) to study the levels of natural and artificial radionuclides 3) to determine a possible mathematical correlation between the radionuclides and several factors.

Natural radioactivity (40K) measurement in common food grains using indigenous technology

International Nuclear Information System (INIS)

Narayan, Pradeep; Sahani, R.M.; Damor, S.L.; D'Souza, P.M.

2018-01-01

Ingestion of contaminated food is one of the major causes of internal doses received in various human organs. As there being no material free from radioactivity on this globe; knowledge of natural radioactivity concentration in common food items is very important for judging the origin of contamination due to nuclear emergency or other man-made activities. An indigenous technology for radioactivity measurement in food/bulk items has been developed and tested using live radioactive sources. This has also been explored for natural radioactivity measurement in common food grains consumed by Indian population. This paper reports the measured natural radioactivity ( 40 K) in common Indian food grains using the developed technology

Radioactive contamination of natural and artificial materials

International Nuclear Information System (INIS)

Kovalchuk, E.L.; Pomansky, A.A.; Smolnikov, A.A.; Temmoev, A.H.

1980-01-01

The gamma radiation of different materials was measured in an underground low-background chamber with extraordinary background characteristics. The excellent background conditions of the measurements enabled investigators to see the alpha-particle peaks of the internal radioactive contamination of NaI(Tl) detectors, which were especially made for these measurements. The sensitivity limit of the installation was determined by the internal contamination of the NaI(Tl) detectors alone. Any radiation background, except for three substances, tungsten, copper, and brass, could be registered

Study of the excited levels of 233Pa by the 237Np alpha decay

International Nuclear Information System (INIS)

Gonzalez, J.; Gaeta, R.; Vano, E.; Los Arcos, J. M.

1978-01-01

The excited levels in 233 P a following the 237 N p alpha decay have been studied, by performing different experiences to complete available data and supply new information. Thus, two direct alpha spectrum measurement, one alpha-gamma bidimensional coincidence experiment, three gamma-gamma and gamma-X ray coincidences and some other measurements of the gamma spectrum, direct and coincident with alpha-particles have been made. These last experiences have allowed to obviate usual radiochemical separation methods, the 233 P a radioactive descendent interferences being eliminated by means of the coincidence technic. As a result, a primary decay scheme has been elaborated, including 15 new gamma transitions and two new levels, not observed in the most recent works. (Author) 60 refs

Statistical aspects in radioactivity measurements

International Nuclear Information System (INIS)

Hoetzl, H.

1979-10-01

This report contains a summary of basic concepts and formulae important for the treatment of errors and for calculating lower limits of detection in radioactivity measurements. Special attention has been paid to practical application and examples which are of interest for scientists working in this field. (orig./HP) [de

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)

Measurement of alpha radioactive air pollutants in fly ash brick dwellings

International Nuclear Information System (INIS)

Chauhan, R.P.; Kant, K.; Sharma, S.K.; Chakarvarti, S.K.

2003-01-01

The exposure of population to high concentrations of radon and its daughters for a long period lead to pathological effects like the respiratory functional changes and the occurrence of lung cancer. In the present study indoor radon monitoring has been carried out in fly ash brick dwellings in some villages/towns of district Faridabad, Haryana (India) using alpha sensitive LR-115 type II solid-state nuclear track detectors. The radon concentration levels in fly ash brick dwellings varied from 197 to 448 Bq m -3 with an average of 277±13 Bq m -3 while annual effective dose received by the occupants varied from 3.4 to 7.7 mSv with an average of 4.8±0.2 mSv. These results have been compared with the radon levels found in cemented and mud dwellings taken from our studies for these dwellings. These studies were also made simultaneously along with fly ash dwellings using same technique and in the same regions

Practice and experience in traceability of radioactivity measurements of environmental samples

International Nuclear Information System (INIS)

Huang Zhijian

1990-01-01

This paper discusses some aspects on radioactivity measurement traceability and summarizes the work on quality assurance of radioactivity measurements of environmental samples in the laboratory, including transfer of standards, preparation of reference materials, and calibration of efficiency for volumse surces with Ge(Li) spectrometer. Some practical activitis regarding intercomparison of radioactivity measurements and other traceabillity-related activities are also described. Some sugestions relating to performing quality assurance are made

NPL support for environmental radioactivity measurements in the United Kingdom

International Nuclear Information System (INIS)

Jerome, Simon

2009-01-01

Full text: The United Kingdom was one of the first nations to initiate a civil nuclear power programme in the 1950s, with the first commercial generation of electricity being achieved in 1957. As the civil nuclear programme grew in size, an ongoing programme of environmental monitoring was instituted by central government that placed the responsibility for monitoring radioactivity in the local environment and the measurement of discharges of radioactive gases and liquids with the site operator, the Environment Agency, the Environment and Heritage Service, the Food Standards Agency and the Scottish Environment Protection Agency (or their predecessors). This presentation will discuss the sources of radioactivity in the UK environment from the nuclear industry, natural and other sources, focussing on how these sources of radioactivity are monitored and what future trends may be, taking the Windscale fire of 1957, the Chernobyl accident and the Litvinenko incident of 2006 as examples of how unexpected events have been addressed in the UK. As the national metrology institute for the UK, the NPL is required to provide support to the National Measurement System infrastructure of the UK, including the measurement of radioactivity. The presentation will also describe the absolute standardisation of radioactivity at the NPL, and how this is disseminated to organisations measuring environmental radioactivity in the UK by means of directly traceable standards of radioactivity and through the provision of an ongoing series of proficiency test exercises. The outcomes of some recent proficiency tests will be discussed, with emphasis on how the general performance of laboratories participating in these proficiency tests has matured over the years since their inception in 1989. In addition, the data treatment of such proficiency tests will also be examined in order to illustrate that statutory regulatory bodies, laboratory accreditation organisations and customers are able to

Radon and environmental radioactivity in the Canfranc Underground Laboratory

International Nuclear Information System (INIS)

Bandac, I.; Bettini, A.; Borjabad, S.; Nunez-Lagos, R.; Perez, C.; Rodriguez, S.; Sanchez, P.; Villar, J. A.

2014-01-01

The results of more than one year of measurements of Radon and environmental radioactivity in the Canfranc Underground Laboratory (LSC) are presented. Radon and atmospheric parameters have registered by an Alpha guard P30 equipment and the environmental radioactivity has been measured by means of UD-802A Panasonic thermoluminescent dosimeters (TLD) processed by an UD716 Panasonic unit. Series of results along with their possible correlations are presented. Both the Radon level and the ambient dose equivalent H (10) are much lower than the allowed ones so no radiological risk exists to persons working in the LSC. Also its excellent environmental radiological quality has been confirmed. (Author)

Radioactivity measurements on live Bewick's Swans

International Nuclear Information System (INIS)

Hancock, R.; Wollam, P.B.

1987-01-01

Measurements made on 46 live swans at Slimbridge using portable high resolution hyperpure germanium gamma ray spectrometry equipment are described. Laboratory measurements are also reported on two swans which died of natural causes or of flying accidents. The implications of the measured radioactivity levels are discussed in relation to the suggestion that they might have been affected by the Chernobyl accident on their migration. (UK)

Energy response of detectors to alpha/beta particles and compatibility of the equivalent factors

International Nuclear Information System (INIS)

Lin Bingxing; Li Guangxian; Lin Lixiong

2011-01-01

By measuring detect efficiency and equivalent factors of alpha/beta radiation with different energies on three types of detectors, this paper compares compatibility of their equivalent factors and discusses applicability of detectors to measuring total alpha/beta radiation. The result shows the relationship between efficiency of alpha/beta radiation and their energies on 3 types of detectors, such as scintillation and proportional and semiconductor counters, are overall identical. Alpha count efficiency display exponential relation with alpha-particle energy. While beta count efficiency display logarithm relation with beta-particle energy, but the curves appears deflection at low energy. Comparison test of energy response also shows that alpha and beta equivalent factors of scintillation and proportional counters have a good compatibility, and alpha equivalent factors of the semiconductor counters are in good agreement with those of the above two types of counters, but beta equivalent factors have obvious difference, or equivalent factors of low energy beta-particle are lower than those of other detectors. So, the semiconductor counter can not be used for measuring total radioactivity or for the measurements for the purpose of food safety. (authors)

Fano factor evaluation of diamond detectors for alpha particles

Energy Technology Data Exchange (ETDEWEB)

Shimaoka, Takehiro; Kaneko, Junichi H.; Tsubota, Masakatsu; Shimmyo, Hiroaki [Graduate School of Engineering, Hokkaido University, Kita 13, Nishi 8, Kita-ku, Sapporo, Hokkaido, 060-8628 (Japan); Sato, Yuki [Naraha Remote Technology Development Center, Japan Atomic Energy Agency, Naraha-machi, Futaba-gun, Fukushima, 979-0513 (Japan); Chayahara, Akiyoshi; Umezawa, Hitoshi; Mokuno, Yoshiaki [Advanced Power Electronics Research Center, National Institute of Advanced Industrial Science and Technology, 1-8-31 Midorigaoka, Ikeda, Osaka, 563-8577 (Japan); Watanabe, Hideyuki [Research Institute for Electronics and Photonics, National Institute of Advanced Industrial Science and Technology, 1-1-1 Higashi, Tsukuba, 305-8565 (Japan)

2016-10-15

This report is the first describing experimental evaluation of Fano factor for diamond detectors. High-quality self-standing chemical vapor deposited diamond samples were produced using lift-off method. Alpha-particle induced charge measurements were taken for three samples. A 13.1 ±0.07 eV of the average electron-hole pair creation energy and excellent energy resolution of approximately 0.3% were found for 5.486 MeV alpha particles from an {sup 241}Am radioactive source. The best Fano factor for 5.486 MeV alpha particles, calculated from experimentally obtained epsilon values and the detector intrinsic energy resolution, was 0.382 ± 0.007. (copyright 2016 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

Alpha-gamma pulse shape discrimination in CsI:Tl, CsI:Na and BaF sub 2 scintillators

CERN Document Server

Dinca, L E; Haas, J; Bom, V R; Eijk, C W E

2002-01-01

Some scintillating materials offer the possibility of measuring well separated alpha and gamma scintillation response using a single crystal. Eventually aiming at thermal neutron detection using sup 6 Li or sup 1 sup 0 B admixture, pulse shape discrimination measurements were made on three scintillators: CsI:Tl, CsI:Na and pure BaF sub 2 crystals. A very good alpha/gamma discrimination was obtained using sup 2 sup 2 Na, sup 2 sup 4 sup 1 Am (gamma) and sup 2 sup 4 sup 4 Cm (alpha) radioactive sources.

Clinical studies on the radioimmunodetection of tumors containing alpha-fetoprotein

International Nuclear Information System (INIS)

Goldenberg, D.M.; Kim, E.E.; Deland, F.; Spremulli, E.; Nelson, M.O.; Gockerman, J.P.; Primus, F.J.; Corgan, R.L.; Alpert, E.

1980-01-01

This study reports the use of radiolabeled antibodies to alpha-fetoprotein for the detection and localization of hepatocellular and germ cell carcinomas. Twelve patients with histories of histologically-confirmed neoplasia received a total dose between 1.0 and 4.4 mCi of 131 I-labeled goat IgG prepared against human alpha-fetoprotein. Total-body photoscans were taken with a gamma scintillation camera at various intervals after injection of the radioactive antibody. Computer subtraction of radioactive technetium background images from the antibody 131 I scans permitted the visualization of all tumor sites known to be present in 4 patients with either primary hepatocellular cancer or metastatic germ cell carcinoma of the testis. Among 8 patients with diverse neoplasms not believed to contain alpha-fetoprotein, 5 of 19 tumor sites showed radioactive antibody accretion, although significantly less than in the patients with liver or testicular cancer. This investigation indicates that alpha-fetoprotein-containing tumors can be detected and localized in vivo by the method of radioimmunodetection

Humidity measurement using alpha-ray and beta-ray

International Nuclear Information System (INIS)

Matsumoto, Shigeaki; Kobayashi, Hisanobu

1981-01-01

Two new hygrometers using radioisotopes were proposed, and the results of tests are described. The one is a dew-point hygrometer utilizing the backscattering phenomena of beta-ray by dew, and the other is a hygrometer by measuring the variation of ionization current by alpha ray due to humidity. The backscattering of beta-ray depends on the atomic number of scatters and the energy of beta-ray. Therefore, the backscattering from dew on a gold plate is different from that from the gold itself. The temperature dependence of the backscattering intensity was measured with a GM counter. Decrease of the intensity was seen at the dew point. A control circuit was designed to measure the dew point automatically. The error of the measurement was within 1 degree C. An alpha-ray ionization hygrometer was constructed. The dependence of ionization current on humidity was measured with an operational amplifier. The resolution of humidity measurement was within 5 percent. (Kato, T.)

Assessment of radioactivity in the drinking water of state of Goias, Brazil

International Nuclear Information System (INIS)

Santos, Eliane E.; Costa, Heliana F.; Mignote, Raquel M.; Thome Filho, Jamilo J.; Bakker, Alexandre P. de

2013-01-01

The demand for drinking water is supplied by surface and underground sources such as rivers and streams. However, there is an increasing worldwide concern about the quality of drinking water. As a result, it is a major goal of governments throughout the world to ensure that water is safe for human consumption through the control of microorganisms, chemicals and radioactive substances. The Brazilian Ministry of Health has issued guidelines designed to protect the quality of drinking water. The use of screening measurements for gross alpha and beta radioactivity is recommend since it maximizes cost-effectiveness of assessing the individual radionuclide content of drinking water. In order to do so tests were carried out to determine of gross alpha and beta radioactivity concentrations in drinking water samples from 44 water supply wells within the State of Goias. The technique used was thermal preconcentration and radiometric determination by liquid scintillation spectrometry. The concentrations for gross alpha ranged from < LD at 0.19 ± 0.05 Bq/L. As for gross beta they ranged from < LD at 0.2 ± 0.1 Bq/L. The results were also related with the geological and hydrological data. (author)

Assessment of radioactivity in the drinking water of state of Goias, Brazil

Energy Technology Data Exchange (ETDEWEB)

Santos, Eliane E.; Costa, Heliana F.; Mignote, Raquel M., E-mail: mingote@cnen.gov.br, E-mail: heliana@cnen.gov.br, E-mail: esantos@cnen.gov.br [Centro Regional de Ciencias Nucleares do Centro-Oeste (CRCN-CO/CNEN-GO), Abadias de Goias, GO (Brazil); Thome Filho, Jamilo J., E-mail: jamilothome@gmail.com [Geological Consultant, Cuiaba, MT (Brazil); Bakker, Alexandre P. de [Instituto Nacional do Semiarido (INSA/MCTI), Campina Grande, PB (Brazil)

2013-07-01

The demand for drinking water is supplied by surface and underground sources such as rivers and streams. However, there is an increasing worldwide concern about the quality of drinking water. As a result, it is a major goal of governments throughout the world to ensure that water is safe for human consumption through the control of microorganisms, chemicals and radioactive substances. The Brazilian Ministry of Health has issued guidelines designed to protect the quality of drinking water. The use of screening measurements for gross alpha and beta radioactivity is recommend since it maximizes cost-effectiveness of assessing the individual radionuclide content of drinking water. In order to do so tests were carried out to determine of gross alpha and beta radioactivity concentrations in drinking water samples from 44 water supply wells within the State of Goias. The technique used was thermal preconcentration and radiometric determination by liquid scintillation spectrometry. The concentrations for gross alpha ranged from < LD at 0.19 ± 0.05 Bq/L. As for gross beta they ranged from < LD at 0.2 ± 0.1 Bq/L. The results were also related with the geological and hydrological data. (author)

Apparatus for measuring a concentration of radioactivity

International Nuclear Information System (INIS)

Tabuchi, H.; Ogushi, A.

1978-01-01

Disclosed is an apparatus for measuring concentration of radioactivity in a fluid circulating in a cooling system or a disposal system, etc., of a nuclear power plant (e.g. coolant), the apparatus having a plurality of sampling tubes with different diameters depending on the intensities of radioactivity, and the sampling tubes having valves for switching from one fluid to another fluid. The sampling tubes are connected to the system to a discharge pipe, and are disposed in the proximity of a radiation detector adapted to issue a signal representative of radiation. The issued signal is supplied to a multichannel pulse height analyzer and a data processing system providing an indication of the concentrations of radioactivities for respective radionuclides

Measurements of radioactive dust in high altitude air

International Nuclear Information System (INIS)

Kobayashi, Mika; Kohara, Eri; Muronoi, Naohiro; Masuda, Yousuke; Midou, Tomotaka; Ishida, Yukiko; Shimizu, Toshihiko; Saga, Minoru; Endo, Hiromu

2012-01-01

The radioactivity in samples of airborne dust was measured. The samples had been collected at high altitude by the Japan Air Self-Defense Force. The data were obtained for the gross beta activity, gamma nuclide determination and radiochemical analysis. It was shown that there was no appreciable difference between the activity levels obtained in this time and in the year before. Seasonal variations were not very pronounced. It was found that the radioactivity at high altitude had been stable at a low level. Radioactive gases (gaseous radioiodine and xenon gas) were not detected. This report does not include the result on radionuclide measurements that Technical Research and Development Institute executed for examining the nuclear emergency situation at Fukushima Daiichi and Daini nuclear power plants after Tohoku Region Pacific Ocean Earthquake on March 11, 2011. (author)

Nondestructive measurement of environmental radioactive strontium

Directory of Open Access Journals (Sweden)

Saiba Shuntaro

2014-03-01

Full Text Available The Fukushima Daiichi nuclear power plant accident was triggered by the 2011 Great East Japan Earthquake. The main radioactivity concerns after the accident are I-131 (half-life: 8.0 days, Cs-134 (2.1 years, Cs-137 (30 years, Sr-89 (51 days, and Sr-90 (29 years. We are aiming to establish a new nondestructive measurement and detection technique that will enable us to realize a quantitative evaluation of strontium radioactivity without chemical separation processing. This technique is needed to detect radiation contained in foods, environmental water, and soil, to prevent us from undesired internal exposure to radiation.

Environmental radioactivity in Turkey, 2009

International Nuclear Information System (INIS)

2010-01-01

In this report, the activity concentrations of natural and artificial radionuclides and gross alpha/beta activities measured in the environmental and food samples provided from Turkey's seven geographical regions within the environmental radioactivity monitoring program in 2009 and absorbed gamma dose rates in outdoor obtained by means of car-borne measurement system (Mobysis) are presented. The activity concentrations of the natural and artificial radionuclides and gross alpha/beta activities in the samples were measured by using the gamma spectrometry, the alpha spectrometry, the liquid scintillation counter and the gross alpha /beta counting system. The mean activity concentrations of 2 26Ra, 2 32Th and 4 0K in the analyzed surface samples were found as 34,7 ± 1,7 Bq kg - 1, 35,4 ± 0,8 Bq kg - 1 and 450,0 ± 17,9 Bq kg - 1, respectively, while the mean activity concentration of the fission product 1 37Cs was found as 11,6 ± 0,5 Bq kg - 1. The mean absorbed gamma dose rate in outdoor due to external exposure emitted by natural radionuclides in soil samples and the corresponding annual effective dose were evaluated as 54,6 nGy h - 1 and 0,07 mSv y - 1, respectively. The activity concentrations of 2 38U, 2 32Th and 2 26Ra in the analyzed food samples were lower than the minimum detectable activity (MDA) while 1 34Cs radionuclide was not observed. The mean activity concentrations of 1 37Cs and 9 0Sr radionuclides measured in the milk samples are 0,28 Bq L - 1 and 0.05 Bq L - 1, respectively. These values are lower than the limit value specified for foods subjected to control based on the regulation of the EU 737/90/EC. The total annual effective dose arising from the internal exposure from radiation emitting from 4 0K, l 37Cs and 9 0Sr radionuclides analyzed in the food samples are evaluated as 193,0 μSv. In conclusion, the results of the monitoring programme in 2009 show that the levels of radioactivity in the environment are low and do not pose any significant

Environmental radioactivity measurement intercomparison exercise 1990

International Nuclear Information System (INIS)

Jerome, S.M.

1991-05-01

In a recent national intercomparison exercise, 49 laboratories involved in making environmental radioactivity measurements took part in the analysis of samples supplied by the National Physical Laboratory (NPL) in the United Kingdom. There were two sets of samples; one containing pure β-emitters and one containing β/γ-emitters. Two thirds of the participants measured the β/γ-emitter sample only, the remainder measured both. The results are presented. (author)

Large magnitude gridded ionization chamber for impurity identification in alpha emitting radioactive samples

International Nuclear Information System (INIS)

Santos, R.N. dos.

1992-01-01

This paper refers to a large magnitude gridded ionization chamber with high resolution used in the identification of α radioactive samples. The chamber and the electrode have been described in terms of their geometry and dimensions, as well as the best results listed accordingly. Several α emitting radioactive samples were used with a gas mixture of 90% Argon plus 10% Methane. We got α energy spectrum with resolution around 22,14 KeV in agreement to the best results available in the literature. The spectrum of α energy related to 92 U 233 was gotten using the ionization chamber mentioned in this work; several values were found which matched perfectly well adjustment curve of the chamber. Many other additional measures using different kinds of adjusted detectors were successfully obtained in order to confirm the results gotten in the experiments, thus leading to the identification of some elements of the 92 U 233 radioactive series. Such results show the possibility of using the chamber mentioned for measurements of α low activity contamination. (author)

Integral alpha and gamma radiation measurements in dwelling houses

International Nuclear Information System (INIS)

Paripas, B.; Takacs, S.; Somogyi, G.; Nikl, I.

1984-01-01

A solid state nuclear track detector method is applied to determine radon and total alpha-exposures (time integral of activity concentrations). The mathematical description of the method of measurement by a passive device equipped with two plastic sheets is presented. Measurements have been carried out in 88 houses over a five-month period and in 20 houses every season for a whole year. Simultaneously with the seasonal measurements of alpha-exposures, the gamma doses were also determined by means of TL dosemeters. The mean exposures due to thoron and its progeny have been estimated by statistical methods. A possible connection between the measured quantities and the lung cancer rates in two settlements were examined. (Author)

Measurement and analysis of radioactive substances

International Nuclear Information System (INIS)

2001-01-01

Here are gathered the abstracts presented to the 3. summer university of the year 2001 whose main themes were the destructive (5 conferences) and nondestructive (8 conferences) analyses applied to nuclear industry. The points of view of different organisms (as DSIN: Directorate for the Safety of Nuclear Installations, IPSN: Institute of Nuclear Protection and Safety, OPRI: Office of Protection against Ionizing Radiations, TUI: Institute for Transuranium Elements, COGEMA, EDF: Electric Utilities, ANDRA: French National Agency for Radioactive Waste Management, CRLC Val d'Aurelle, France) concerning the needs involved in nuclear facilities control, the methods of radionuclide speciation in use internationally, the measurements and analyses of radioactive substances are given too as well as some general concepts concerning 1)the laser-matter interaction 2)the ions production 3)the quality applied to the measurements and analyses 4)the standard in activity metrology. (O.M.)

Distribution of radioactive minerals in a granite

Energy Technology Data Exchange (ETDEWEB)

Coppens, R

1949-04-04

The study, by means of a photographic plate, of the radioactivity of a Brittany granite, both of a pulverized sample and of a polished sample, has resulted in a complete determination of the radioactivity present. The ratio of the concentration of Th to that of U i.e., C/sub Th/C/sub U/, was determined as approximately 2.8 using the relationship between the concentration of these elements and the number of ..beta.. particles in a particular range which were detected. Using this ratio and measuring the average number of ..cap alpha.. particles emitted/cm/sup 2//sec, the average activities were found to correspond to concentrations of the order of 10/sup -5/ of both metals. The lack of uniformity in the distribution of the radioactivity within the crystal is noted.

Radioactivity measurement for emergency or post-accident situations

International Nuclear Information System (INIS)

Champion, D.

2010-01-01

Specific objectives have to be achieved by radioactivity measurements during emergency or post-accident situations, which are different from those in normal situation. At the beginning of a nuclear emergency, few radioactivity data will be available, mainly from automatic monitoring systems implemented on the site or in its surrounding. Progressively, measurement programmes will be performed, in priority to get information on dose rate, atmospheric radionuclides and surface activities. In order to avoid excessive exposure of the measure teams, these programmes should be optimized. During early post-accident phase, different types of measurements will be done, following two main objectives: 1) to improve the assessment of the environmental contamination and people exposure; 2) for control purpose, to check the contamination of urban places, foodstuff and other products, compared to specific reference levels. The samples measurement in laboratories would be a challenge: usually, the laboratories involved in routine monitoring have to deal with very low level of radioactivity and a poor diversity of artificial radionuclides; after a reactor accident, the environmental samples to be measured would be more active and with a mixture of radionuclides (mainly with short or middle half-life) difficult to be characterized. So theses laboratories have to be trained and organised before any severe accident. (author)

New measurement techniques of environmental radioactivity. Methods of surveying marine radioactivity

International Nuclear Information System (INIS)

Kobayashi, Yoshii

1994-01-01

Measurements of radioactivity have been carried out in solution or suspension in sea-water, bottom sediments and specific marine organisms. The general approach to radionuclide measurement in seawater and bottom sediments has been concentration by coprecipitation, adsorption, ion exchange or solvent extraction. These methods employed are based primarily on shipboard collection of samples followed by land-based laboratory analyses and are too time-consuming. For rapid measurement, in situ measurement of seawater or seabed gamma-ray has developed. A gamma-ray detecting probe containing the NaI(Tl) scintillation or germanium detector is enclosed in a sealed cylinder. The measurements are made by suspending the probe in a 200-300 liter tank and passing seawater through the tank by means of ship deck pumping system, towing the probe across the seafloor, hanging down the probe to the seabed, or loading the probe on a remotely operated undersea vehicle. In situ measurement of gamma-ray in the marine environment has some application to a mineral exploration and to monitoring of sea areas which may become contaminated as the result of accidents or contamination incidents. This article reviews several gamma-ray detecting probes and describes the recent studies at JAERI on the development of a small electric-cooled Ge gamma-ray detector and a marine environmental radioactivity investigation system for in situ measurement of gamma-ray. (J.P.N.)

Folding model analysis of alpha radioactivity

International Nuclear Information System (INIS)

Basu, D N

2003-01-01

Radioactive decay of nuclei via emission of α-particles has been studied theoretically in the framework of a superasymmetric fission model using the double folding (DF) procedure for obtaining the α-nucleus interaction potential. The DF nuclear potential has been obtained by folding in the density distribution functions of the α nucleus and the daughter nucleus with a realistic effective interaction. The M3Y effective interaction has been used for calculating the nuclear interaction potential which has been supplemented by a zero-range pseudo-potential for exchange along with the density dependence. The nuclear microscopic α-nucleus potential thus obtained has been used along with the Coulomb interaction potential to calculate the action integral within the WKB approximation. This subsequently yields calculations for the half-lives of α decays of nuclei. The density dependence and the exchange effects have not been found to be very significant. These calculations provide reasonable estimates for the lifetimes of α-radioactivity of nuclei

Radioactivity measurements by liquid scintillation spectroscopy

International Nuclear Information System (INIS)

Cassette, Ph.

2004-01-01

The activity measurement techniques by liquid scintillation spectroscopy consist to mix the radioactive solution to measure with a scintillating liquid and to transform the ionizing radiations, resulting from decays, into light, detectable and quantifiable. The main advantages of these techniques are the easiness of preparation of the radioactive sources, the geometric efficiency of detection of 4π and the possibility of detection of low-level energy radiations. There are one of the only methods giving the possibility to measure the activity of pure β radionuclides; indeed, the nuclear disintegration is not accompanied of gamma radiations detectable by other techniques. There are one of the only methods too of measurement of radionuclides which disintegrate by electron capture and especially those leading to the emission of low-level energy ionizing radiations. Liquid scintillation spectroscopy can be used as an absolute method of activity measurement that is to say without the use of a calibration standard. The modern liquid scintillation counting devices can be very sensitive; the measurement of micro-activities being possible. Some of the applications of these activity measurement techniques are the carbon 14 dating and the geological tracing. Their main disadvantage is the global energetic yield which is low and variable in terms of the composition of the scintillation source necessitating to calculate the detection yield for each condition of measurement. (O.M.)

Measurement of very low alpha activity in water

International Nuclear Information System (INIS)

Crespo, M. T.; Acena, M. L.

1987-01-01

Measurement of very low levels of alpha-emitting nuclides in water needs substantial improvements. A system based on the adsorbing properties manganese dioxide eliminates the need for transporting very large volumes of water and increases the sensitivity of the measurement. (Author) 21 refs

Results of questionaire survey for the measurement of radioactivity in waste water

International Nuclear Information System (INIS)

1992-01-01

A questionaire for radioactivity in waste water was sent to 388 facilities, including 158 medical facilities, and all (100%) answered. Information requested included: (1) kinds and annual usage of unsealed RI, (2) measuring method of radioactivity in waste water, (3) kinds of measuring instruments and the detection limits, (4) prior treatment of measurement materials, (5) level of radioactive waste exhausted during 3 months, (6) personnel and time per month required for radioactivity measurement, (7) problems and comments in waste water management, and (8) kinds of facilities. A total of 36 unsealed RI were used. The most commonly used RI was I-125 (n=240), followed by H-3 (n=189) and P-32 (n=179). Annual level of RI was 4 GBq or less in 90% of the facilities. The most common method for measuring radioactivity was sampling method (n=241). The most common instrument for measuring radioactivity was a gamma counter for I-125 (45% of the facilities), and a liquid scintillation counter for P-32 (80%) and for C-14 and H-3 (90%). The detection limits for I-125 exceeded the radioactivity limits in 24% of the facilities. The amount of sampler was 5 cc or less in 80% of the facilities. Prio treatment was not carried out in 62.7%. Prior treatment methods reported were enrichment, evaporation, pH adjustment, and sedimentation. Half of the facilities exhausted 10 cm 3 or less of waste water during 3 months. The number of persons engaging in radioactivity measurement per month was reported to be one in 282 facilities (87%). (N.K.)

Gross alpha and beta activities in drinking water from Goias State, Brazil

Energy Technology Data Exchange (ETDEWEB)

Mingote, Raquel M. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN), Belo Horizonte, MG (Brazil); Nogueira, Regina A.; Costa, Heliana F. da, E-mail: raquel.mingote@cdtn.br, E-mail: rnogueira@cnen.gov.br, E-mail: heliana@cnen.gov.br [Centro Regional de Ciencias Nucleares do Centro-Oeste (CRCN-CO/CNEN), Abadia de Goias, GO (Brazil). Parque Estadual Telma Ortegal

2017-07-01

Detection of gross alpha and beta radioactivity is important for a quick surveying of both natural and anthropogenic radioactivity in water. Furthermore, gross alpha and gross beta parameters are included in Brazilian legislation on quality of drinking water. In this work, a low background liquid scintillation spectrometer was used to simultaneously determine gross alpha and gross beta in samples of the public water supplies in the state of Goias, Brazil, during 2010-2015. Sample preparation involved evaporation to concentrate the sample ten-fold. The results indicate that the water meets the radioactivity standards required by the regulations MS 2914/2011 of the Brazilian Department of Health. Concerning the high level of censored observations, a statistical treatment of data was conducted by using analysis methods of censored data to provide a reference value of the gross alpha and beta radioactivity in drinking water from the state of Goias. The estimated typical activities are very low, 0.030 Bq•L{sup -1} and 0.058 Bq•L{sup -1}, respectively. (author)

Generalized liquid drop model and fission, fusion, alpha and cluster radioactivity and superheavy nuclei

International Nuclear Information System (INIS)

Royer, G.

2012-01-01

A particular version of the liquid drop model taking into account both the mass and charge asymmetries, the proximity energy, the rotational energy, the shell and pairing energies and the temperature has been developed to describe smoothly the transition between one and two-body shapes in entrance and exit channels of nuclear reactions. In the quasi-molecular shape valley where the proximity energy is optimized, the calculated l-dependent fusion and fission barriers, alpha and cluster radioactivity half-lives as well as actinide half-lives are in good agreement with the available experimental data. In this particular deformation path, double-humped potential barriers begin to appear even macroscopically for heavy nuclear systems due to the influence of the proximity forces and, consequently, quasi-molecular isomeric states can survive in the second minimum of the potential barriers in a large angular momentum range

Distribution of radioactive constituents in river waters

International Nuclear Information System (INIS)

Herranz, M.; Elejalde, C.; Legarda, F.; Romero, F.

1994-01-01

For a research project on the distribution and evaluation of natural and artificial radioactive constituents in ecological segments of Biscay (northeast spain), the amounts of nuclides present in the main river waters were measured. Radioactive procedures include i) total alpha and beta indexes with a gas flow detector, dry residues near to 2 and 10 mg/ cm sup 2, respectively and counting periods of 1000 mn, ii) gamma emitters with a low level gamma spectrometer (Ge-HP detector + 8000 channels analyser) using the dry residue from 8 litres and a counting period of 4 days and iii) statistical treatment of data at 95% confidence.In this paper, ten water samples from the nervion river basin are included. Physical and chemical parameters of samples were also determined by standard procedures, because there is a sharp change in the composition of this river in the first part of the course. Radioactive constituents were identified as follows: a sample has a detectable alpha index, all samples contains beta emitters with a high variability, natural nuclides from uranium and thorium families were detected in some cases. A parallel behaviour is found between samples where K-40 and Cs-137 were found. The paper tries at last to find relations among chemical and radioactive constituents by the application of multivariate statistical methods, specially for the case of Cs-137, the only artificial nuclide identified in this work. 1 tab., 2 figs., 5 refs. (author)

Evaluation of surface contamination due to alpha using large area contamination monitors

International Nuclear Information System (INIS)

Raghavayya, M.

1998-01-01

Radioactive contamination at work places is evaluated routinely using either the swipe sampling technique or a contamination monitor. Commercially available alpha probes used for the purpose are usually circular and have a face diameter of 50 or 100 mm. Square faced probes are also available. A thin aluminized mylar membrane of thickness 0.45 to 0.9 mg.cm -2 is used to screen the phosphor in the alpha probe to protect it from external light. The membrane cuts off more alphas from low energy emitters than from higher energy alpha emitters. Moreover the response of the detector for alphas originating at all points under the detector face is not uniform, especially when the large area alpha monitors are used. These factors can introduce errors as high as 40% into the measurements. This paper aims to quantify these errors and describe a procedure to overcome the limitations. (author)

Sampling airborne radioactivity

International Nuclear Information System (INIS)

Cohen, B.S.

1988-01-01

Radioactive contaminants have historically been considered apart from chemical contaminants because it is their radiological properties that determine their biological and environmental impact. Additionally they have been regulated by special government agencies concerned with radiological protection. Radioactive contaminants are also distinguished by the specialized and very sensitive methods available for the detection of radioactivity. Measurements of a few thousand atoms per liter are not uncommon. Radiation detectors in common use are gas filled chambers, scintillation and semiconductor detectors, and the more recently developed thermoluminescent and etched track detectors. Solid-state nuclear track detectors consist of a large group of inorganic and organic dielectrics which register tracks when traversed by heavy charged particles. They do not respond to light, beta particles or gamma ray photons and thus provide a very low background system for the detection of extremely low levels of radioactivity. In addition, no power source or electronic equipment is required. Cellulose nitrate detectors are currently in use for long term integrated sampling of environmental radon. Thermoluminescent dosimeters (TID's) are crystalline materials, in which electrons which have been displaced by an interaction with ionizing radiation become trapped at an elevated energy level and emit visible light when released from that energy level. As which etched-track detectors no power or electronic equipment is needed for the TID's at a measurement site, but they respond to alpha, beta and gamma radiation. Thermoluminescent dosimeters are useful for long term environmental monitoring, and have also been newly incorporated into integrating radon detection systems

Measurement of differential (n,x{alpha}) cross section using 4{pi} gridded ionization chamber

Energy Technology Data Exchange (ETDEWEB)

Sanami, Toshiya; Baba, Mamoru; Matsuyama, Shigeo; Kiyosumi, Takehide; Nauchi, Yasushi; Saito, Keiichiro; Hirakawa, Naohiro [Tohoku Univ., Sendai (Japan). Faculty of Engineering; Kawano, Toshihiko

1997-03-01

We carried out the measurements of high resolution {alpha} emission spectra of {sup 58}Ni and {sup nat}Ni between 4.5 and 6.5 MeV, and {sup 12}C(n,x{alpha}) cross section using a 4{pi} gridded ionization chamber. In Ni measurement, overall energy resolution was improved to around 200 keV by optimizing a sample thickness and a neutron source width. Measured alpha spectra showed separate peaks corresponding to the ground and low-lying excited states of the residual nucleus ({sup 55}Fe). These results were compared with another direct measurement and statistical model calculations. In {sup 12}C measurement, GIC was applied for (n,x{alpha}) reactions of light nuclei. This application is difficult to (n,x{alpha}) cross sections of light nuclei, because of the influences of large recoil energy and multi-body break-up. We developed new methods which eliminate the effects of recoil nuclei and multi-body break-up and applied them to {sup 12}C(n,x{alpha}) reaction at En=14.1 MeV. In our experiment, the {sup 12}C(n,{alpha}{sub 0}){sup 9}Be angular differential cross section and {sup 12}C(n,n`3{alpha}) cross section were obtained. (author)

Measurement of Plutonium-240 Angular Momentum Dependent Fission Probabilities Using the Alpha-Alpha' Reaction

Science.gov (United States)

Koglin, Johnathon

Accurate nuclear reaction data from a few keV to tens of MeV and across the table of nuclides is essential to a number of applications of nuclear physics, including national security, nuclear forensics, nuclear astrophysics, and nuclear energy. Precise determination of (n, f) and neutron capture cross sections for reactions in high- ux environments are particularly important for a proper understanding of nuclear reactor performance and stellar nucleosynthesis. In these extreme environments reactions on short-lived and otherwise difficult-to-produce isotopes play a significant role in system evolution and provide insights into the types of nuclear processes taking place; a detailed understanding of these processes is necessary to properly determine cross sections far from stability. Indirect methods are often attempted to measure cross sections on isotopes that are difficult to separate in a laboratory setting. Using the surrogate approach, the same compound nucleus from the reaction of interest is created through a "surrogate" reaction on a different isotope and the resulting decay is measured. This result is combined with appropriate reaction theory for compound nucleus population, from which the desired cross sections can be inferred. This method has shown promise, but the theoretical framework often lacks necessary experimental data to constrain models. In this work, dual arrays of silicon telescope particle identification detectors and photovoltaic (solar) cell fission fragment detectors have been used to measure the fission probability of the 240Pu(alpha, alpha'f) reaction - a surrogate for the 239Pu(n, f) - and fission of 35.9(2)MeV at eleven scattering angles from 40° to 140° in 10° intervals and at nuclear excitation energies up to 16MeV. Within experimental uncertainty, the maximum fission probability was observed at the neutron separation energy for each alpha scattering angle. Fission probabilities were separated into five 500 keV bins from 5:5MeV to

Natural radioactivity levels in different mineral waters from Bulgaria

Energy Technology Data Exchange (ETDEWEB)

Kamenova-Totzeva, R.; Kotova, R.; Tenev, J.; Ivanova, G.; Badulin, V. [Public Exposure Monitoring Laboratory, National Centre of Radiobiology and Radiation Protection, Sofia (Bulgaria)

2013-07-01

The total radioactivity content of 76 mineral waters from different districts in Bulgaria was determined. Natural radioactivity levels resulting from uranium, radium-226, gross alpha and gross beta activity were measured. The results show that the specific activity range from < 0.02 Bq/l to 1.34 (12) Bq/l and from 0.068 (23) Bq/l to 2.60 (50) Bq/l for gross alpha and gross beta activity respectively. For natural Uranium the results vary between 0.020 (5) μg/l and 180(50) μg/l. Radium-226 content is between < 0.03 Bq/l to 0.296 (75) Bq/l. Due to differences in the geological structure of the aquifer, a large difference in values of the radioactive content was mSv/year. Excluding one value, TID do not exceed the permissible limit of 0.10 mSv/year. The correlations between investigated isotopes and Total Dissolved observed. The estimated Total Indicative Dose (TID) ranged from 0.0113 (57) mSv/year to 0.1713 (481) Solvents (TDS) in water were carried out. The results do not show a strong correlation between TDS values and dissolved radionuclides. (author)

Hydrochemistry and radioactivity in the rivers of Biscay (Spain)

International Nuclear Information System (INIS)

Romero, F.; Herranz, M.; Elejalde, C.; Legarda, F.

1995-01-01

For a research project on the evaluations of radioactive constituents in ecological segments of Biscay (Spain), nuclides in water of the main rivers and hydrochemical parameters (pH, conductivity, temperature, percentage of saturation in oxygen and chemical components) were measured. Radioactive data obtained after statistical treatment at 95% confidence level, were as follows; i) Total alpha and beta idexes with a gas flow detector on dry residues not greater than 2 and 10 mg/cm''2, respectively and ii) gamma emitters with a low level spectrometer (Ge-HP detector + 8000 channels analyser) on the dry residue of more than 8 litres and a counting period of 4 days. This paper include 28 samples from the following rivers: Nervion (10), Ibaizabal (5), Cadagua (8), Barbadun, Butron, Oca, Lea and Artibay. On the basis of average values, studied rivers are characterized as follows: Nervion (important amount of Cs. 137 and the greatest beta index), Ibaizabal (high K.40 contents), Cadagua (the biggest alpha index ) and low radionuclides concentrations in the other rivers. Finally, the application of multivariate statistical techniques, mainly cluster analysis, is tried to find out relations between chemical and radioactive constituents. (Author)

Application of a proportional counter to some particular cases of {alpha} measurements; Applications d'un compteur proportionnel a quelques cas particuliers de mesures {alpha}

Energy Technology Data Exchange (ETDEWEB)

Ferret, J; Gasc, M T; Le Du, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1965-07-01

I - A measurement method based on {alpha} {gamma} coincidences is used for activity measurements on {sup 241}Am in the presence of a strong {alpha} activity due to Pu. The sensitivity of the apparatus makes it possible to detect: less than 10{sup -7} {mu}C {sup 241}Am in the presence of a Pu activities several hundred times greater. II - The same equipment has been used for {alpha} measurements on {alpha}-emitting sources in the presence of very strong {beta} and {gamma} activities. In particular results are given for {alpha}-activity measurements on powder samples. It is even possible in these conditions, to detect or measure {sup 241}Am. III - The equipment makes possible also: - the absolute calibration of a pure {sup 241}Am source - {sup 237}Np measurements - simultaneous measurements of {alpha}, {beta} and {gamma} activities in solid samples in various forms. IV - The assembly includes a small-size proportional counter operating in conjunction with a {gamma} probe, together with auxiliary electronic equipment (stabilized high voltages, amplifiers, a coincidence unit, a sealer). (authors) [French] I - Une methode de mesures par coincidences {alpha} {gamma} est utilisee pour des mesures d'activite de {sup 241}Am en presence d'activite {alpha} (due au Pu) importante. -La sensibilite de l'appareillage permet de deceler: moins de 10{sup -7} {mu}C {sup 241}Am dans les activites {alpha} Pu plusieurs centaines de fois plus importantes. II - Le meme appareillage a ete utilise pour des mesures {alpha} sur des sources emettrices {alpha} en presence d'activites {beta} et {gamma} tres importantes. En particulier des mesures d'activite {alpha} sur des echantillons de poudre sont exposees. Il est meme possible, dans ces conditions, de deceler ou mesurer {sup 241}Am. III - L'ensemble permet egalement: - l'etalonnage absolu d'une source de {sup 241}Am pur - des mesures de {sup 237}Np - des mesures simultanees d'activites {alpha}, {beta} et {gamma} dans des echantillons solides

Measurements of DT alpha particle loss near the outer midplane of TFTR

International Nuclear Information System (INIS)

Zweben, S.J.; Darrow, D.S.; Herrmann, H.W.; Redi, M.H.; Schivell, J.; White, R.B.

1995-07-01

Measurements of DT alpha particle loss to the outer midplane region of TFTR have been made using a radially movable scintillator detector. The conclusion from this data is that mechanisms determining the DT alpha loss to the outer midplane are not substantially different from those for DD fusion products. Some of these results are compared with a simplified theoretical model for TF ripple-induced alpha loss, which is expected to be the dominant classical alpha loss mechanism near the outer midplane. An example of plasma-driven MHD-induced alpha particle loss is shown, but no signs of any ''collective'' alpha instability-induced alpha loss have yet been observed

Incineration technology for alpha-bearing radioactive waste in Germany

International Nuclear Information System (INIS)

Dirks, Friedlich; Pfeiffer, Reinhard

1997-01-01

Since 1971 the Karlsruhe Research Center has developed and operated plants for the incineration of radioactive waste. Three incineration plants for pure β/γ solid, α-bearing solid and radioactive liquid waste have been successfully utilized during last two decades. Recently more than 20 year-old β/γ plant was shut down with the economic point of view, mainly due to the recently reduced volume of burnable β/γ waste. Burnable β/γ solid waste is now being treated with α-bearing waste in a α solid incineration plant. The status of incineration technology for α-bearing waste and other radioactive waste treatment technologies, which are now utilized in Karlsruhe Research Center, such as conditioning of incineration ash, supercompaction, scrapping, and decontamination of solid radioactive waste, etc. are introduced in this presentation. Additionally, operational results of the recently installed new dioxin adsorber and fluidized-bed drier for scrubber liquid in α incineration plant are also described in this presentation. (author) 1 tab., 13 figs

National network of radioactivity measurement in environment

International Nuclear Information System (INIS)

2006-01-01

This document constitutes the report of management for the year 2006 of the national network of measurement of radioactivity in environment, instituted by the article R.1333-11 of the Public Health code. According to the 5. of the decree of 27. june 2005, the Institute of radiation protection and nuclear safety (I.R.S.N.) has for mission to write every year a report of management of the national network of radioactivity measurement in environment. This report has for principal objectives: to do an evaluation on organisation and functioning of the piloting committee; to realize a synthesis on the different tasks lead by the working groups; as well as on the human and financial resources devoted to this project; to debrief on the development project of the national network information system. This report must allow to the network actors, as to the professional people and the public, to understand the functioning of the national network and the process implemented for the development of centralization, management and public diffusion tools, of the radioactivity data in environment. The year 2006 was marked by the opening of an Internet gate of the national network. (N.C.)

Measurement of gross beta radioactivity in high-level liquid waste

International Nuclear Information System (INIS)

Lu Feng; Lin Cansheng; Zhang Xianzi; Chen Guoan; Zhang Chonghai

1992-01-01

Using beta plastic scintillation counter of low level background, gross beta radioactivity of twelve samples for high-level liquid waste is determined directly. Beta efficiency curves of plastic scintillation counter for four mass thickness are calibrated in advance. Determining gross beta radioactivity, gross efficiency of the scintillation counter for various energy beta ray is calculated via weighted mean method with the ratio of radioactivity for each nuclide. The ratio of radioactivity for nuclides which have gamma disintegration is determined in terms of the radioactivity measured by gamma spectrometer. The ratio of the radioactivity for 90 Sr which has purity beta disintegration is calculated in terms of half life time approximation. The ratio of the radioactivity for 147 Pm which also has purity disintegration is calculated by means of apparent cooling-time approximation. The uncertainty of results for the present work is about +-15%

Radiobiological significance of radioactive contamination - summary assessment based on great number of measurements

International Nuclear Information System (INIS)

Angelov, V.; Bonchev, Ts.; Mavrodiev, V.; Kyrdzhilov, N.

1995-01-01

In order to facilitate quantitative and qualitative characterisation of radioactive contamination the authors introduce a relative estimate of radionuclide activity by setting as a reference the most abundant element -Co-60 in the case of the Kozloduy NPP. The ratio η i of the mean annual permissible concentration in air for each radionuclide (RPC-92) to that of Co-60 is calculated. It is found that η i has the same or close values for groups of radionuclides, e.g. η i = 2.10 -4 for 238 Pu, 239 Pu, 240 Pu, 241 Am, 244 Cm; η i = 5 for 89 Sr, 91 Y; 93 Nb, 134 Cs, 137 Cs; η i = 50 for 55 Fe, 63 Ni, 95 Zr, 95 Nb, 140 Ba, 140 La. Then it is compared to the experimentally measured values of the same quantity η iexp , derived from surface contamination data. The ratio η iexp /η i is plotted against log η i . The resulting nomograms give graphic representation of the radiobiological significance of various radionuclide groups. Data from different locations at the Kozloduy NPP are presented. It is found that the alpha emitter contamination has highest values in the Unit 1 (WWER-440) control rooms after repair. The Unit 5 (WWER-1000) has lower alpha contamination compared to WWER-440 units. 1 ref., 5 figs., 1 tab

The natural radioactivity in Guarani aquifer groundwater, Brazil

Energy Technology Data Exchange (ETDEWEB)

Bonotto, D.M. [Departamento de Petrologia e Metalogenia, Universidade Estadual Paulista (UNESP), Av. 24-A No. 1515, C.P. 178, CEP 13506-900, Rio Claro, Sao Paulo (Brazil)], E-mail: danielbonotto@yahoo.com.br; Bueno, T.O. [Departamento de Petrologia e Metalogenia, Universidade Estadual Paulista (UNESP), Av. 24-A No. 1515, C.P. 178, CEP 13506-900, Rio Claro, Sao Paulo (Brazil)

2008-10-15

The measurements of gross alpha and gross beta radioactivity in groundwater samples from Guarani aquifer in Brazil are reported in this paper together with the activity concentration of the natural dissolved radionuclides {sup 40}K, {sup 238}U, {sup 234}U, {sup 226}Ra, {sup 222}Rn, {sup 210}Po, {sup 210}Pb, {sup 232}Th, {sup 228Th}, and {sup 228}Ra. Most of the gross alpha radioactivity values were below the critical level of detection corresponding to 1 mBq/L, however, the whole data set for the gross beta radioactivity and radionuclides {sup 40}K, {sup 238}U, {sup 234}U, {sup 226}Ra, {sup 222}Rn, {sup 210}Po, {sup 210}Pb, and {sup 228}Ra was submitted to a statistical treatment, considering class intervals arranged in geometric progression, because of the great variability of the activity. The analysis indicated lognormal distribution of the data, as usually observed in samples taken from the natural context. An inverse relationship between the gross alpha and gross beta activity has been identified and is related to an increase in the K content in the water. The mobility coefficient has been estimated for {sup 238}U, {sup 226}Ra, {sup 232}Th and {sup 228}Ra in Guarani aquifer and the results indicated that the radioelement solubility in the studied system varies according to the following order: radium>uranium>thorium. The implications of the data obtained in terms of standards established for defining the drinking water quality have also been discussed.

The measurement of the radioactive aerosol diameter by position sensitive detectors, 3

International Nuclear Information System (INIS)

Murakami, Hiroyuki; Nakamoto, Atsushi; Kanamori, Masashi; Seki, Akio.

1981-10-01

The measurement of the diameter of radioactive aerosol, in particular plutonium aerosol, is very important for the internal dose estimation. Determination of the diameter of radioactive aerosol is performed by using the position sensitive detectors. Position sensitive semiconductor detectors and Scintillation detectors with IIT tube are used as the position sensitive detector. The filter paper with the radioactive aerosols is contacted to the PSD which is connected to the data processor so that the diameter of the aerosol is calculated from the measured radioactivity. (author)

Binding of benzo(a)pyrene and (+/-)-7 beta,8 alpha-dihydroxy-9 alpha, 10 alpha-epoxy-7,8,9, 10-tetrahydrobenzo(a)pyrene to histones

International Nuclear Information System (INIS)

Sculley, T.B.; Zytkovicz, T.H.

1983-01-01

AKR-2B mouse embryo cells were incubated for 24 hr with [3H]benzo(a)pyrene, and the histones were isolated and analyzed using one- and two-dimensional gel electrophoresis and autoradiography. The results revealed that (a) histones H1, H2A, and H3 incorporated significant amounts of label whereas little or no label was associated with histones H2B and H4 and (b) electrophoresis of the histones in the Triton: acid: urea gel system caused labeled histones to have a slower migration than did the corresponding unlabeled histones. Additional studies such as incubation of (+/-)-7 beta,8 alpha-[3H]dihydroxy-9 alpha,10 alpha-epoxy-7,8,9,10-tetrahydrobenzo(a)pyrene with nuclei resulted in radioactive labeling of histones H1, H2A, H2B, and H3 and of high-mobility-group proteins HMG1 and HMG2. The low levels of label associated with histone H4 in the whole-cell and nuclear studies were further investigated by incubating isolated histones with (+/-)-7 beta,8 alpha-[3H]dihydroxy-9 alpha,10 alpha-epoxy-7,8,9,10-tetrahydrobenzo(a)pyrene. Under these conditions, negligible amounts of radioactivity were associated with H4, while significant labeling of H1, H2A, H2B, and H3 and other nuclear proteins was observed. The results suggest that factors other than the presence of suitable nucleophilic acceptor sites on the histones may be necessary for carcinogen binding

Measurement and analysis of radioactive substances; Mesure et analyse de substances radioactives

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

Here are gathered the abstracts presented to the 3. summer university of the year 2001 whose main themes were the destructive (5 conferences) and nondestructive (8 conferences) analyses applied to nuclear industry. The points of view of different organisms (as DSIN: Directorate for the Safety of Nuclear Installations, IPSN: Institute of Nuclear Protection and Safety, OPRI: Office of Protection against Ionizing Radiations, TUI: Institute for Transuranium Elements, COGEMA, EDF: Electric Utilities, ANDRA: French National Agency for Radioactive Waste Management, CRLC Val d'Aurelle, France) concerning the needs involved in nuclear facilities control, the methods of radionuclide speciation in use internationally, the measurements and analyses of radioactive substances are given too as well as some general concepts concerning 1)the laser-matter interaction 2)the ions production 3)the quality applied to the measurements and analyses 4)the standard in activity metrology. (O.M.)

The radioactivity measurement in the Loire catchment basin. Actors, networks, data inventory

International Nuclear Information System (INIS)

2008-01-01

The objective of this report on the Loire watershed was to broaden at all the nuclear installations of the watershed the method of synthesis made for Saint-Laurent-des-Eaux nuclear power plant, by resting on the whole of actors doing the radioactivity measurements in environment. This report shows that these actors are numerous. The measurement plans implemented have for objective to establish the radiological situation of environment, near or not the nuclear facilities, to detect the abnormal increase of radioactivity, to evaluate the exposure of populations to the ambient radioactivity, or to check the conformity of practices (nuclear activities) and products. This assessment enlightens the lack of a real global strategy in the organisation of the radioactivity measurement at the level of the watershed. The inventory of available data for the Loire watershed allowed to show the diversity of measurements realised. The I.R.S.N. is face to a complex situation of data return in the frame of the implementation of an information system of the national network of radioactivity measurement in environment. (N.C.)

Alpha and conversion electron spectroscopy of {sup 238,239}Pu and {sup 241}Am and alpha-conversion electron coincidence measurements

Energy Technology Data Exchange (ETDEWEB)

Dion, Michael P., E-mail: michael.dion@pnnl.gov; Miller, Brian W.; Warren, Glen A.

2016-09-11

A technique to determine the isotopic constituents of a mixed actinide sample has been proposed by a coincident alpha-conversion electron measurement. This presents a unique signature to allow the unfolding of isotopes that possess overlapping alpha particle energy and reduce backgrounds of an unseparated sample. The work presented here are results of conversion electron spectroscopy of {sup 241}Am, {sup 238}Pu and {sup 239}Pu using a dual-stage peltier-cooled 25 mm{sup 2} silicon drift detector and alpha spectroscopy with a passivated ion implanted planar silicon detector. The conversion electron spectra were evaluated from 20–55 keV based on fits to the dominant conversion electron emissions, which allowed the relative conversion electron emission intensities to be determined. These measurements provide crucial singles spectral information and calibration to aid in the coincident measurement approach. Furthermore, an alpha-conversion electron spectrometer was assembled using the silicon based detectors described and results of a coincident spectrum analysis is reported for {sup 241}Am.

IGRIS for characterizing low-level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Peters, C.W. [Nuclear Diagnostic Systems, Springfield, VA (United States); Swanson, P.J. [Concord Associates, Knoxville, TN (United States)

1993-03-01

A recently developed neutron diagnostic probe system has the potential to noninvasively characterize low-level radioactive waste in bulk soil samples, containers such as 55-gallon barrels, and in pipes, valves, etc. The probe interrogates the target with a low-intensity beam of 14-MeV neutrons produced from the deuterium-tritium reaction in a specially designed sealed-tube neutron-generator (STNG) that incorporates an alpha detector to detect the alpha particle associated with each neutron. These neutrons interact with the nuclei in the target to produce inelastic-, capture-, and decay-gamma rays that are detected by gamma-ray detectors. Time-of-flight methods are used to separate the inelastic-gamma rays from other gamma rays and to determine the origin of each inelastic-gamma ray in three dimensions through Inelastic-Gamma Ray Imaging and Spectroscopy (IGRIS). The capture-gamma ray spectrum is measured simultaneously with the IGRIS measurements. The decay-gamma ray spectrum is measured with the STNG turned off. Laboratory proof-of-concept measurements were used to design prototype systems for Bulk Soil Assay, Barrel Inspection, and Decontamination and Decommissioning and to predict their minimum detectable levels for heavy toxic metals (As, Hg, Cr, Zn, Pb, Ni, and Cd), uranium and transuranics, gamma-ray emitters, and elements such as chlorine, which is found in PCBs and other pollutants. These systems are expected to be complementary and synergistic with other technologies used to characterize low-level radioactive waste.

Krypton-85 and other airborne radioactivity measurements throughout Ireland

International Nuclear Information System (INIS)

Smith, K.J.; Murray, M.; Wong, J.; Sequeira, S.; Long, S.C.; Rafferty, B.

2004-01-01

In compliance with articles 35 and 36 of the EURATOM Treaty, the Radiological Protection Institute of Ireland (RPII) undertakes a comprehensive programme of radioactivity monitoring in the Irish terrestrial environment. Radioactivity is present in the terrestrial environment due to natural processes, the testing of nuclear weapons in the atmosphere, accidents such as the Chernobyl accident and the routine discharge of radionuclides from nuclear installations. The RPII monitors airborne radioactivity concentrations at ten stations throughout Ireland, of which, nine are equipped with low volume particulate samplers and one, in Dublin, with a high volume particulate sampler. The low volume particulate samples are assessed for total beta activity and high volume samples for gamma emitting radionuclides such as caesium-137 and beryllium-7. In addition, air sampled at the RPII laboratory in Dublin, is monitored for krypton-85, a radioactive noble gas, released into the environment primarily as a result of the reprocessing of nuclear fuel at installations such as Sellafield in the UK and La Hague in France. Since the inception of the krypton measurements in 1993 a trend of increasing atmospheric concentrations has been observed. The results of the krypton-85 monitoring, as well as the airborne radioactivity concentration measurements, will be presented and discussed in this paper. (author)

Measurement of radioactivity in Norway

International Nuclear Information System (INIS)

Berg, T.C.

1989-10-01

A nation-wide network of 11 monotoring stations for continuous registration of radioactivity in the air has been established in Norway. Via the telecommunication network, collected data are dayly automatically transmitted to the Norwegian Institute for Air Research (NILU). High radiation levels trigger an alarn for immediate transmission. The monotoring system and experiences in connection with its operation are described, and results from measurements in 1988 are presented. 14 figs

Measurement of radioactivity in Norway

International Nuclear Information System (INIS)

Berg, T.C.

1990-08-01

A nation-wide network of 11 monitoring stations for continous registration of radioactivity in the air has been established in Norway. Via the telecommunication network, collected data are dayly automatically transmitted to the Norwegian Institute for Air Research (NILU). High radiation levels trigger an alarm for immediate transmission. The monitoring system and experiences in connection with its operation are described. Results from measurements in 1989 are presented. 18 figs

Fundamental symmetries and astrophysics with radioactive beams

International Nuclear Information System (INIS)

Vogt, E.

1996-04-01

A major new initiative at TRIUMF pertains to the use of radioactive beams for astrophysics and for fundamental symmetry experiments. Some recent work is described in which the β-decay-followed by alpha particle emission of 16 N was used to find the resonance parameters dominating the alpha particle capture in 12 C and thus to find the astrophysical S-factor of this reaction which is of crucial importance for alpha-particle burning and the subsequent collapse of stars. In some work underway trapped neural atoms of radioactive potassium atoms will be used to study fundamental symmetries of the weak interactions. Trapping has been achieved and soon 38m K decay will be used to search for evidence of scalar interactions and 37 K decay to search for right-handed gauge-bosom interactions. Future experiments are planned to look for parity non-conservation in trapped francium atoms. This program is part of a revitalization for the TRIUMF laboratory accompanied by the construction of the radioactive beam facility (ISAC). (author)

Calculated /alpha/-induced thick target neutron yields and spectra, with comparison to measured data

International Nuclear Information System (INIS)

Wilson, W.B.; Bozoian, M.; Perry, R.T.

1988-01-01

One component of the neutron source associated with the decay of actinide nuclides in many environments is due to the interaction of decay /alpha/ particles in (/alpha/,n) reactions on low Z nuclides. Measurements of (/alpha/,n) thick target neutron yields and associated neutron spectra have been made for only a few combinations of /alpha/ energy and target nuclide or mixtures of actinide and target nuclides. Calculations of thick target neutron yields and spectra with the SOURCES code require /alpha/-energy-dependent cross sections for (/alpha/,n) reactions, as well as branching fractions leading to the energetically possible levels of the product nuclides. A library of these data has been accumulated for target nuclides of Z /le/ 15 using that available from measurements and from recent GNASH code calculations. SOURCES, assuming neutrons to be emitted isotopically in the center-of-mass system, uses libraries of /alpha/ stopping cross sections, (/alpha/,n) reaction cross reactions, product nuclide level branching fractions, and actinide decay /alpha/ spectra to calculate thick target (/alpha/,n) yields and neutron spectra for homogeneous combinations of nuclides. The code also calculates the thick target yield and angle intergrated neutron spectrum produced by /alpha/-particle beams on targets of homogeneous mixtures of nuclides. Illustrative calculated results are given and comparisons are made with measured thick target yields and spectra. 50 refs., 1 fig., 2 tabs

Innovations in Los Alamos alpha box design

International Nuclear Information System (INIS)

Ledbetter, J.M.; Dowler, K.E.; Cook, J.H.

1985-01-01

Destructive examinations of irradiated fuel pins containing plutonium fuel must be performed in shielded hot cells with strict provisions for containing the plutonium. Alpha boxes provide containment for the plutonium, toxic fission products, and other hazardous highly radioactive materials. The alpha box contains windows for viewing and a variety of transfer systems specially designed to allow transfers in and out of the alpha box without spread of the hazardous materials that are contained in the box. Alpha boxes have been in use in the Wing 9 hot cells at Los Alamos National Laboratory for more than 20 years. Features of the newly designed alpha boxes are presented

Study of the peak shape in alpha spectra measured by liquid scintillation

CERN Document Server

Vera-Tome, F; Martin-Sanchez, A

2002-01-01

Liquid-scintillation counting allows the measurement of alpha and beta activities jointly or only of the alpha-emitting nuclides in a sample. Although the resolution of the alpha spectra is poorer than that attained with semiconductor detectors, it is still an attractive alternative. We describe here attempts to fit a peak shape to experimental liquid-scintillation alpha spectra and discuss the parameters affecting this shape, such as the PSA (pulse-shape analyser) level, vial type, shaking the sample, etc. Spectral analysis has been applied for complex alpha spectra.

Part 1: determination of radioactive disequilibrium in uranium ores by alpha-spectrometry

International Nuclear Information System (INIS)

Killeen, P.G.; Carmichael, C.M.

1976-01-01

An α-spectrometric method of detecting the presence of disequilibrium in the 238 U decay series has been developed. A silicon semi-conductor detector and a 1024 channel pulse height analyzer were used to obtain alpha particle energy spectra of uraniferous rocks and minerals. 'Infinitely thick' sources were used to avoid the problems involved in preparation of 'infinitely thin' sources. The method involves the generation of theoretical energy distributions for infinitely thick sources. Complete theoretical spectra were computed for comparison with experimentally obtained alpha particle energy spectra of rocks and minerals. The presence and extent of disequilibrium in the 238 U decay series in a rock is determined from the residual spectrum obtained by subtracting a fitted theoretical spectrum from the measured spectrum of a rock. (author)

Establishment and application of standard devices for radioactivity measurement

International Nuclear Information System (INIS)

Zhou Changgui; Li Xingyuan; Chen Zigen

1991-03-01

In order to establish the radioactivity measurement standards a 4πβ-γ coincidence apparatus and a 4πγ ionization chamber have been installed in the laboratory. The 4πβ-γ coincidence apparatus is for absolute measurement, and its uncertainty is ±(0.3∼5)%. The 4πγ ionization chamber is for working standard, and its uncertainty is ±(1∼5)%. The combination of these devices can meet the quality requirements controlled by National Verification System in the transfer of radioactivity values

Radioactivity of the JINR site environment

International Nuclear Information System (INIS)

Alenitskaya, S.I.; Bamblevskij, V.P.; Kargin, A.N.; Komochkov, M.M.

1977-01-01

The results of the study of the existing levels of enviromental radioactivity in the JINR region for 1971-1975; content of radioactive products in the grass and surface soil layer, levels of the total alpha - and beta-radioactivity of water of open reservoirs as well as the background of the gamma-radiation and charged particles are presented. The study testifies, that the operation of the JINR nuclear-physical installations does not significantly affect the radioactivity of the environment which is mainly conditioned by the products of the natural origin and the global fallouts

Instruments used to measure or check {alpha}, {beta}, {gamma} activity and neutron emission in the course of processing ore or irradiated fuel; Appareils de mesure ou de controle {alpha}, {beta}, {gamma}, n, des circuits des usines de traitement du minerai ou du combustible irradie

Energy Technology Data Exchange (ETDEWEB)

Blanc, A; Brunet, M; Kermagoret, M; Labeyrie, J; Roux, G; Vasseur, J; Weil, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1959-07-01

One of the methods checking ores in the course of treatment is the rapid quantitative determination of thorium. This measurement is carried out by means of a scintillation instrument which shows the {beta} and {alpha} coincidences of ThC and ThC'. The treatment of irradiated fuel is accompanied by a large number of radioactive checks relative to the performance of the fixation and elution operations of uranium in the ion exchangers, to the concentration of radioactivity of effluent sent from the plant into watercourses. The operations of fixation and elution of the uranium are checked automatically by an instrument which takes a sample of 5 cm{sup 3} of solution, evaporates it and measures its activity every 10 or 20 minutes. Plutonium concentrations are measured: - in the presence of strong {beta} {gamma} activities, by means of rotating cylinder detectors; - in the presence of weak {beta} {gamma} activities, by means of {alpha} detectors scanning a constant level liquid surface; - by means of fission chambers relatively insensitive to {gamma}. Fission product concentrations are measured by chambers, counters or scintillators, according to the amount of {gamma} activity present. Finally, the activity of effluent to be emptied into watercourses is checked by means of a scintillation instrument, which measures the {alpha} activity on the one hand, and on the other hand the {beta} {gamma} activity of residue from a 100 cm{sup 3} sample taken and evaporated in 20 minutes. (author) [French] Parmi les controles relatifs au minerai en cours de traitement, figure le dosage rapide de thorium. Cette mesure est realisee au moyen d'un appareillage a scintillation qui met en evidence la coincidence des emissions {beta} et {alpha} du ThC et du ThC'. Le traitement des combustibles irradies s'accompagne d'un grand nombre de controles radioactifs portant sur le fonctionnement des operations de fixation et d'elution de l'uranium dans les echangeurs d'ions, sur la concentration du

Determination of 210Pb in marine sediment core- A comparison between alpha and gamma techniques

International Nuclear Information System (INIS)

Zal Uyun Wan Mahmood; Yii Mei Wo; Zaharudin Ahmad

2010-01-01

The most commonly used techniques of alpha and gamma spectrometry were performed to measure 210 Pb activity in marine sediment core as a comparison. Alpha analytical technique measured the activity of 210 Pb from its in-grow grand-daughter 210 Po after a chemical separation, assuming radioactive equilibrium between the two radionuclides. Meanwhile, gamma analysis technique allows direct measurement, non-destructive and no preliminary chemical separation. Through the comparison, it is found that both alpha and gamma analysis techniques were slightly difference. Overall, the results from alpha analytical technique were basically higher than those from the gamma analytical techniques. Some logical argument had been discussed to explain this situation. In routine analysis, the analytical technique used should be chosen carefully based on advantages and disadvantages of the each technique and analysis requirements. Therefore, it is recommended to determine exactly the needs and purpose of analysis and to know the sample history before decide the appropriate analytical technique. (author)

Gas lantern mantle: a low activity alpha particle source

International Nuclear Information System (INIS)

Mukherjee, B.; Manzoor, S.

1991-01-01

Commercially available gas lantern mantles contain a substantial amount of radioactive ThO 2 . Gas lantern mantles purchased from a Sydney camping shop were incinerated, deposited as a thin layer on a aluminium planchette, and the emitted alpha spectrum was measured with a silicon surfacer barrier detector. The specific activity of the samples was estimated by high resolution gamma spectroscopy using a high purity germanium detector as well as CR-39 solid state nuclear track detectors. The micro-morphology of the incinerated powder was analysed by scanning electron microscopy. The depth dose and LET distribution of alpha particles in soft tissue were calculated from the energy spectrum. 12 refs., 2 tabs., 5 figs

Alpha liquid-scintillation spectrometry used for the measurement of uranium/thorium-disequilibria in soil samples

International Nuclear Information System (INIS)

Fueeg, B.; Tschachtli, T.; Kraehenbuehl, U.

1997-01-01

For the measurements of low-level radioactivity of natural samples. It is of interest to have a system with high counting efficiency. Alpha liquid-scintillation spectrometry is attractive, because it offers a 4 π geometry. Some chemical separation can be obtained using extractive scintillators. Due to quenching problems for natural samples, additional separation power is needed. A new sample preparation method was developed employing extraction chromatographic resin for measuring 238 U, 234 U, 232 Th, 230 Th, 228 Th and 226 Ra in soil samples, without using any uranium- or thorium-tracer for determining the chemical yields. This method was tested by analyzing the two different reference materials, IAEA-375, soil from Tschernobyl, as well as IAEA SDA-1, a deep-sea sediment with a high calcium content. For all analyzed radionuclides the recoveries were better than 90% with errors (confidence level of 95%) smaller than 5%. The minimal detectable concentration ranges between 0.2 and 0.8 Bq/kg, based on a one gram aliquot of sample and 80'000 seconds counting time. (orig.)

(n, {alpha}) cross section measurement of light nuclei using gridded ionization chamber and gaseous sample

Energy Technology Data Exchange (ETDEWEB)

Sanami, Toshiya; Baba, Mamoru; Saito, Keiichiro; Ibara, Yasutaka; Yamazaki, Tetsuro; Sato, Jun; Hirakawa, Naohiro [Tohoku Univ., Sendai (Japan)

1998-03-01

We have developed a measuring method of (n, {alpha}) cross section by using gaseous sample in a gridded ionization chamber. In this study, we measured the {sup 12}C(n, {alpha}{sub 0}) and the {sup 16}O(n, {alpha}{sub 0}), (n, {alpha}{sub 123}) cross sections for En=11.5 and 12.8 MeV neutrons. We also deduced the {sup 12}C(n, x{alpha}) spectrum and analyzed the data by a kinematic calculation combined with the reaction data of the {sup 12}C(n, n`3{alpha}). (author)

Design and device construction for plane tables preparation for counter alpha/beta total

International Nuclear Information System (INIS)

Galicia C, F. J.; Monroy G, F.

2014-10-01

This work presents the design and assembly of a device for plane tables preparation for quantification alpha/beta total of radioactive waste samples. The determination of the activity index alpha/beta total is used to detect a wide variety of matrices quickly and the concentration of alpha and/or beta emitters of the contained radionuclides in different samples. In particular, the determination of the activity index alpha and beta total of radioactive wastes involves the digestion of samples in aggressive means that will be evaporated to dryness for its quantification. With the purpose of controlling the emission of corrosive gases during the preparation of the plane tables for the quantification of the index alpha and beta total, was designed and built the device in the Radioactive Waste Laboratory that allows to prepare plane tables for proportional counters in a sure and efficient way. The device is constituted by heating equipment, evaporation cylinder and a gases cleaning system. The self-absorption curve got ready starting from the device. (Author)

arXiv Proceedings, High-Precision $\\alpha_s$ Measurements from LHC to FCC-ee Geneva, Switzerland, October 2-13, 2015

CERN Document Server

d'Enterria, David; Alekhin, S.; Banfi, A.; Bethke, S.; Blümlein, J.; Chetyrkin, K.G.; Dissertori, G.; Garcia i Tormo, X.; Hoang, A.H.; Klasen, M.; Klijnsma, T.; Kluth, S.; Kneur, J.-L.; Kniehl, B.A.; Kolodrubetz, D.W.; Kühn, J.; Mackenzie, P.; Malaescu, B.; Mateu, V.; Mihaila, L.; Moch, S.; Mönig, K.; Pérez-Ramos, R.; Pich, A.; Pires, J.; Rabbertz, K.; Salam, G.P.; Sannino, F.; Soto i Riera, J.; Srebre, M.; Stewart, I.W.

2015-01-01

This document provides a writeup of all contributions to the workshop on "High precision measurements of $\\alpha_s$: From LHC to FCC-ee" held at CERN, Oct. 12--13, 2015. The workshop explored in depth the latest developments on the determination of the QCD coupling $\\alpha_s$ from 15 methods where high precision measurements are (or will be) available. Those include low-energy observables: (i) lattice QCD, (ii) pion decay factor, (iii) quarkonia and (iv) $\\tau$ decays, (v) soft parton-to-hadron fragmentation functions, as well as high-energy observables: (vi) global fits of parton distribution functions, (vii) hard parton-to-hadron fragmentation functions, (viii) jets in $e^\\pm$p DIS and $\\gamma$-p photoproduction, (ix) photon structure function in $\\gamma$-$\\gamma$, (x) event shapes and (xi) jet cross sections in $e^+e^-$ collisions, (xii) W boson and (xiii) Z boson decays, and (xiv) jets and (xv) top-quark cross sections in proton-(anti)proton collisions. The current status of the theoretical and experiment...

Measurement methodology of natural radioactivity in the thermal establishments

International Nuclear Information System (INIS)

Ameon, R.; Robe, M.C.

2004-11-01

The thermal baths have been identified as an activity susceptible to expose to ionizing radiations the workers through the natural sources of radon and radon 220. The new regulation obliges these facilities to realize radioactivity measurements. The principal ways of exposure are radon and its daughters inhalation,, exposure to gamma radiation, ingestion of radioelements in thermal waters. I.R.S.N. proposes two methods of measurements of the natural radioactivity in application to the regulation relative to the protection of persons and workers. Some principles to reduce exposure to radon are reminded. (N.C.)

A method to reproduce alpha-particle spectra measured with semiconductor detectors.

Science.gov (United States)

Timón, A Fernández; Vargas, M Jurado; Sánchez, A Martín

2010-01-01

A method is proposed to reproduce alpha-particle spectra measured with silicon detectors, combining analytical and computer simulation techniques. The procedure includes the use of the Monte Carlo method to simulate the tracks of alpha-particles within the source and in the detector entrance window. The alpha-particle spectrum is finally obtained by the convolution of this simulated distribution and the theoretical distributions representing the contributions of the alpha-particle spectrometer to the spectrum. Experimental spectra from (233)U and (241)Am sources were compared with the predictions given by the proposed procedure, showing good agreement. The proposed method can be an important aid for the analysis and deconvolution of complex alpha-particle spectra. Copyright 2009 Elsevier Ltd. All rights reserved.

Environmental radioactive monitoring, evaluation and protection in luminous workshops of a factory

International Nuclear Information System (INIS)

Dai Hanbin; Xiang Ming; Tan Jianzu

2009-01-01

Fluorescent technique is often used to display instrumental indicator in the dark environment. Luminous workshops of a factory smear and depict the glassware by means of fluorescent power with adulterated radioactive matter. Because of adulterated radioactive matters such as 226 Ra, 40 K emit alpha-ray,beta-ray and gamma-ray, while they decay spontaneously, and high dose or cumulative radiation can damage human body in different degrees. Therefore, any radioactive damage to human body caused by over-safety dose should be prevented strictly during the working. To ensure health and safety of working staff in luminous workshop and the public, it is necessary to regularly have radioactive monitoring and evaluation to luminous workshop and its surrounding environment. Through the environment radioactive monitoring, the authors analyze its environmental radioactive level,and try to find out the possible problems so as to propose some protective measures for personal health. (authors)

In-situ measurement of environment radioactivity by mobile nuclear field laboratory (MNFL)

International Nuclear Information System (INIS)

Gopalani, Deepak; Mathur, A.P.; Rawat, D.K.; Barala, S.S.; Singhal, K.P.; Singh, G.P.; Samant, R.P.

2008-01-01

In-situ measurement of environment radioactivity is useful tool for determine the unusual increase of radioactivity at any place due to any nuclear eventuality take place. A mobile nuclear field laboratory has been designed and developed for in-situ measurement of environment radioactivity at any desired location. This vehicle is equipped with different monitoring and analysis instruments. These equipment can be operated while vehicle is moving. The measured data can be stored in computer. This vehicle has the space for storage of various environmental matrices of affected area and these can analysis in laboratory. (author)

Tobacco radioactivity and cancer in smokers

International Nuclear Information System (INIS)

Martell, E.A.

1975-01-01

The recent finding that 210 Pb, which also is present in inhaled mainstream smoke, is highly concentrated in a small number of insoluble smoke particles changes the whole complexion of the problem of possible health effects of the inhaled radioactivity in cigarette smoke. Because 210 Pb has a radioactive half-life of 22 years, the body burden of the radioactive 210 Pb and its radioactive daughter products 210 Bi and 210 Po can continue to build up throughout the period of smoking. Alpha interactions with chromosomes of cells surrounding these insoluble radioactive smoke particles may cause cancer and contribute to early atherosclerosis development in cigarette smokers. (U.S.)

Measurement of artificial radioactivity in the atmosphere at Ottawa, Canada

Energy Technology Data Exchange (ETDEWEB)

Terentiuk, F

1958-01-01

In recent years there has been considerable interest in the artificial radioactivity in the atmosphere originating from atomic and thermonuclear explosions. For the past year daily measurements of radioactivity have been made at Ottawa. The sampling times corresponded to air volumes of 425 cubic metric and 2000 cubic meters, respectively. Filters were kept for a period of 3 days before measurements were made in order to permit natural activity resulting from daughter products of radon and thoron to decay to a negligible value. Measurements of the gross beta activity from the filters were made directly with end-window Geiger tubes. Filters showing considerable initial radioactivity were measured at intervals of a few days in order to obtain the rate of decay of the activity. It was hoped that the data obtained would make it possible to fix the date of the explosion responsible for the filter activity but the fixing of dates was very uncertain.

Review of measurement techniques for stack monitoring of long-lived alpha emitters

International Nuclear Information System (INIS)

Kordas, J.F.; Phelps, P.L.

1978-01-01

As a result of the promulgation of new guidelines by the Environmental Protection Agency (40 CFR 190) for releases of long-lived, alpha-emitting substances, the stack-monitoring requirements for measuring long-lived alpha particles may change in terms of both monitored isotopes and the detection levels. This paper briefly reviews stack-monitoring requirements for long-lived alpha-emitting particles. It also examines the currently deployed alpha-particulate, stack-monitoring systems and discusses prototype systems that may be applicable to stack monitoring

Measurement of natural radioactivity in Chahbahar – Sistan and Blouchestan in Iran

Directory of Open Access Journals (Sweden)

Seyyed Abbas Hosseini

2014-05-01

Full Text Available Background: Natural radioactivity exposes radiation so that it goes whole body through different ways and causes diseases leading to death, if it is more than standard amount by ICRP. The aim of this study was to measure the amount of radioactivity in the soil, water and air of Chabahar city in Sistan and Baluchestan province, Iran. Material and Methods: A few locations of city were chosen as a sampling station. The study of drinking water radioactivity was performed in Bandargah and city square. Soil’ radioactivity tested in Tiss village and Shillat. Radioactivity measurement of air was performed in the above-mention places. The radioactivity of drinking water and soil were measured by using a coaxial detector Germanium with high purity. Results: Average concentrations of Ra-228, Th-222 and K-40 in soil and Ra-228 in piping drinking water and in consumed plant were 450±34.5 Bq/Kg, 28.5±2.5 Bq/Kg, 24.3±2.6 Bq/Kg and <2 Bq/L, respectively. The overall results demonstrated low levels of radioactivity (<2 mBq/L, and less levels of K-40, Ra-228 and Th-232 in soil. The Ra-228 concentrations measured in piping and underground water were generally below the detection limit. As there was lower radioactivity in comparison with international standards, there was not probably any disease. Absorbed dose in air was 485.5±20 nanoGy/h and effective dose was 596±24.5, 5 µSv. Conclusion: It is found that there is a significant difference in average of 228Ra, 40K and 232Th in the area relative to some points in the world that may be because of organic matter and microbial biomass. Different factors effect on radioactivity of samples. This region shows the least ionizing radiation.

Radioactive Beam Measurements to Probe Stellar Explosions

Energy Technology Data Exchange (ETDEWEB)

Smith, Michael Scott [ORNL

2010-01-01

Unique beams of unstable nuclei from the Holi eld Radioactive Ion Beam Facility at Oak Ridge National Laboratory are being used to measure the thermonuclear reactions that occur in novae, X-ray bursts, and supernovae. The astrophysical impact of these measurements is determined by synergistic nuclear data evaluations and element synthesis calculations. Results of recent measurements and explosion simulations are brie y described, along with future plans and software research tools for the community.

Measurements of Radioactivity in Body Organs. Report of a Panel of Experts

International Nuclear Information System (INIS)

1970-01-01

Measurements of radioactivity in body organs in vivo entail physical and other problems which do not arise in measurements of radioactivity in vitro. From 8-12 December 1969 the International Atomic Energy Agency convened at its Headquarters in Vienna a panel of experts to review the existing status of techniques for such measurements

Measurements of astrophysical reaction rates for radioactive samples

International Nuclear Information System (INIS)

Koehler, P.E.; O'Brien, H.A.; Bowman, C.D.

1987-01-01

Reaction rates for both big-bang and stellar nucleosynthesis can be obtained from the measurement of (n,p) and (n,γ) cross sections for radioactive nuclei. In the past, large backgrounds associated with the sample activity limited these types of measurements to radioisotopes with very long half lives. The advent of the low-energy, high-intensity neutron source at the Los Alamos Neutron Scattering CEnter (LANSCE) has greatly increased the number of nuclei which can be studied. Results of (n,p) measurements on samples with half lives as short as fifty-three days will be given. The astrophysics to be learned from these data will be discussed. Additional difficulties are encountered when making (n,γ) rather than (n,p) measurements. However, with a properly designed detector, and with the high peak neutron intensities now available, (n,γ) measurements can be made for nuclei with half lives as short as several weeks. Progress on the Los Alamos (n,γ) cross-section measurement program for radioactive samples will be discussed. 25 refs., 3 figs., 1 tab

Radioactivity of some alpha, beta and gamma emitting radionuclides in surface marine sediments of different bays in Algeria

International Nuclear Information System (INIS)

Noureddine, A.; Baggoura, B.

1999-01-01

Samples of surface (0-15) cm marine sediments of different grain sizes, namely sand, muddy and fine sand, were collected in the western, central and east coast of Algeria, to measure concentrations of natural and artificial radioactivity. The aim of this study is to detect any radioactive contamination, its origin and also to determine the uptake of radioactivity by marine surface sediments

Measurement of radioactivity in Norway

International Nuclear Information System (INIS)

Berg, T.C.

1988-05-01

A nation-wide network of seven monitoring stations for continuous registration of radioactivity in the air has been established in Norway. Via the telecommunication network, collected data are dayly automatically transmitted to the Norwegian Institute for Air Research (NILU). High radiation levels will trigger an alarm for immediate transmission. The monitoring system and field experiences in connection with its operation are described. NILU's directions in the event of radiation alarm are specified and radiation measurements for 1987 are presented

Evaluation of uncertainty and detection limits in radioactivity measurements

Energy Technology Data Exchange (ETDEWEB)

Herranz, M. [Universidad del Pais Vasco/Euskal Herriko Unibertsitatea, Escuela Tecnica Superior de Ingenieria de Bilbao, Alda. Urquijo, s/n, 48013 Bilbao (Spain); Idoeta, R. [Universidad del Pais Vasco/Euskal Herriko Unibertsitatea, Escuela Tecnica Superior de Ingenieria de Bilbao, Alda. Urquijo, s/n, 48013 Bilbao (Spain)], E-mail: raquel.idoeta@ehu.es; Legarda, F. [Universidad del Pais Vasco/Euskal Herriko Unibertsitatea, Escuela Tecnica Superior de Ingenieria de Bilbao, Alda. Urquijo, s/n, 48013 Bilbao (Spain)

2008-10-01

The uncertainty associated with the assessment of the radioactive content of any sample depends on the net counting rate registered during the measuring process and on the different weighting factors needed to transform this counting rate into activity, activity per unit mass or activity concentration. This work analyses the standard uncertainties in these weighting factors as well as their contribution to the uncertainty in the activity reported for three typical determinations for environmental radioactivity measurements in the laboratory. It also studies the corresponding characteristic limits and their dependence on the standard uncertainty related to those weighting factors, offering an analysis of the effectiveness of the simplified characteristic limits as evaluated by various measuring software and laboratories.

Evaluation of uncertainty and detection limits in radioactivity measurements

International Nuclear Information System (INIS)

Herranz, M.; Idoeta, R.; Legarda, F.

2008-01-01

The uncertainty associated with the assessment of the radioactive content of any sample depends on the net counting rate registered during the measuring process and on the different weighting factors needed to transform this counting rate into activity, activity per unit mass or activity concentration. This work analyses the standard uncertainties in these weighting factors as well as their contribution to the uncertainty in the activity reported for three typical determinations for environmental radioactivity measurements in the laboratory. It also studies the corresponding characteristic limits and their dependence on the standard uncertainty related to those weighting factors, offering an analysis of the effectiveness of the simplified characteristic limits as evaluated by various measuring software and laboratories

New measurements of W-values for protons and alpha particles

International Nuclear Information System (INIS)

Giesen, U.; Beck, J.

2014-01-01

The increasing importance of ion beams in cancer therapy and the lack of experimental data for W-values for protons and heavy ions in air require new measurements. A new experimental set-up was developed at PTB and consistent measurements of W-values in argon, nitrogen and air for protons and alpha particles with energies from 0.7 to 3.5 MeV u -1 at PTB, and for carbon ions between 3.6 and 7.0 MeV u -1 at GSI were carried out. This publication concentrates on the measurements with protons and alpha particles at PTB. The experimental methods and the determination of corrections for recombination effects, beam-induced background radiation and additional effects are presented. W-values in argon, nitrogen and air were measured for protons with energies of 1-3 MeV and for alpha particles with energies of 2.7-14 MeV. The energies of the primary particle beam were corrected for energy losses in the gold and Mylar foils, as well as for the kinematic energy loss due to scattering by 45 deg.. Beam-induced radiation backgrounds as well as recombination effects were determined and corrected for. The present results are summarised in Figure 2 for all three gases. The solid lines through the data points for each gas indicate an average W-value for that gas. The higher values for 2.7-MeV alpha particles agree with the trend in previous data towards lower energies. They are excluded from the averages. The relative standard uncertainties of the individual data points range from 1.3 to 3 %. The weighted averages over all energies are W(Ar) = 25.7 eV, W(N 2 ) = 35.6 eV and W(Air) = 34.2 eV. The averages serve as a first comparison and the lines on the plot are to guide the eye and are not meant to imply constant W-values for all energies and particles. The W-values for protons and alpha particles in argon and nitrogen have smaller uncertainties and are lower than the suggested values, but they are still in agreement within the uncertainties. For alpha particles with energies of 12

Croatian-Hungarian cooperation on the Danube river radioactivity measurements

International Nuclear Information System (INIS)

Lulic, S.; Vancsura, P.

2003-01-01

Danube river radioactivity measurements on the border profile Mohac-Batina have been performed since the beginning of 1978 with varying frequency of sampling. Thus, in the period before nuclear power plant Paks started to work joint croatian-hungarian sampling at the border profile was taking place four times a year; the obtained results of measured radioactivity levels were used to assess radioactivity background data. From the start of nuclear power plant Paks running until Chernobyl reactor accident (April 1986) sampling was performed six times a year. After the Chernobyl accident, samples have been taken every month. Since decreased Chernobyl reactor accident influence was estimated until present samples have been taken six times a year. On the Danube river border profile the concentration activity of gamma radionuclides has been determined in water samples (filtered water and suspended matter), and in fish, sediment and Danube river algae samples. (authors)

Increased 5. cap alpha. -reductase activity in idiopathic hirsutism

Energy Technology Data Exchange (ETDEWEB)

Serafini, P.; Lobo, R.A.

1985-01-01

In vitro, genital skin 5..cap alpha..-reductase activity (5..cap alpha..-RA) was measured in ten hirsute women with normal androgen levels (idiopathic hirsutism (IH)) and in ten hirsute women with elevated androgen levels (polycystic ovary syndrome (PCO)) in order to determine the influence of secreted androgens on 5..cap alpha..-RA. In vitro 5..cap alpha..-RA was assessed by incubations of skin with /sup 14/C-testosterone (T) for 2 hours, after which steroids were separated and the radioactivity of dihydrotestosterone (DHT) and 5..cap alpha..-androstane 3..cap alpha..-17..beta..-estradiol (3..cap alpha..-diol) in specific eluates were determined. All androgens were normal in IH with the exception of higher levels of 3..cap alpha..-diol glucuronide which were similar to the levels of PCO. The conversion ratio (CR) of T to DHT in IH and PCO were similar, yet significantly greater than the CR of control subjects. The CR of T to 3..cap alpha..-diol in IH and PCO were similar, yet higher than in control subjects. Serum androgens showed no correlation with 5..cap alpha..-RA, while the CR of T to DHT showed a significant positive correlation with the Ferriman and Gallwey score. The increased 5..cap alpha..-RA in IH appears to be independent of serum androgen levels and is, therefore, an inherent abnormality. The term idiopathic is a misnomer, because hirsutism in these patients may be explained on the basis of increased skin 5..cap alpha..-RA.

Measurement of sup 15 O(. alpha. ,. gamma. ) sup 19 Ne resonance strengths

Energy Technology Data Exchange (ETDEWEB)

Magnus, P V; Smith, M S; Howard, A J; Parker, P D [Yale Univ., New Haven, CT (USA). Nuclear Structure Lab.; Champagne, A E [Princeton Univ., NJ (USA). Dept. of Physics

1990-01-08

States in {sup 19}Ne above the {sup 15}O+{alpha} threshold were populated by means of the {sup 19}F({sup 3}He,t){sup 19}Ne* reaction, and their alpha-particle decays to the {sup 15}O ground state were measured. The branching ratios {Gamma}{sub {alpha}}/{Gamma}{sub total} for the E{sub c.m.}=850-, 1020-, 1971-, 1183- and 1563-keV resonances in {sup 15}O+{alpha} were determined. This information together with alpha-particle and/or gamma-ray partial widths (determined from knowledge of these quantities for the mirror states in {sup 19}F) determines the strengths of these {sup 15}O({alpha},{gamma}){sup 19}Ne resonances and the {sup 15}O({alpha},{gamma}){sup 19}Ne reaction rate for temperatures between 7x10{sup 8} and 3x10{sup 9} K. (orig.).

Estimation of radioactivity in tobacco

International Nuclear Information System (INIS)

Nain, Mahabir; Gupta, Monika; Chauhan, R.P.; Chakarvarti, S.K.; Kant, K.; Sonkawade, R.G.

2010-01-01

The link between cigarette smoke and cancer has long been established. Smokers are ten times at greater risk of developing lung cancer than that of non-smokers. Tobacco fields and plants also have higher concentration of uranium and consequently large contents of 210 Po and 210 Pb belonging to uranium and radium decay series. These radio-nuclides have long association with tobacco plants. 210 Pb and 210 Po, decay products of the uranium series get dissolved in water and are first transported into plants and subsequently to the human being. Also, the uptake of radionuclides into roots from the soils and phosphate fertilizers along with direct deposition of 210 Pb by rainfall represents the principal mechanism of incorporation of 210 Pb and 210 Po into the tobacco plants. Uranium present in soil enters the plants through roots and gets distributed in various parts of the tobacco plants. This phenomenon may cause high intake of uranium and its radioactive decay products leading to harmful effects in human being. In the present work, Gamma spectrometry (HPGe detector of high-resolution gamma spectrometry system) has been used at Inter University Accelerator Center (IUAC), New Delhi, for the measurement of activity concentrations of 238 U, 232 Th and 40 K in some tobacco samples. The alpha radioactivity of the leaves of the tobacco plants was measured using plastic track detectors LR-115 Type-Il manufactured by Kodak. Measurement of track densities (track cm -2 day -1 ) shows variation on the upper face and the bottom face of the leaves for the plants. The track density due to alpha particles is higher at bottom face as compared to top face of the leaves. (author)

Source of gross-alpha radioactivity anomalies in recharge wells, central Florida phosphate district. Final report

International Nuclear Information System (INIS)

Oural, C.R.; Brooker, H.R.; Upchurch, S.B.

1986-01-01

The central Florida phosphate industry utilizes recharge wells to mitigate withdrawals of water from the Florida aquifer and to dewater the surficial aquifer prior to mining. From a water-management point of view, these wells are efficient and serve a vital function. Recent monitoring of the radiation environment in these wells, however, casts doubts on the safety of the wells. While most of the wells conform to state and federal standards for radium, gross-alpha radiation frequently exceeds standards. The purpose of the study was to determine the radionuclide(s) responsible for the high gross-alpha radiation and to identify a method for sampling of the recharge wells that would standardize data across the phosphate district. It was found that excess gross alpha is primarily due to polonium-210. Since gross alpha and polonium-210 measurements are quite sensitive to methods of sample collections, preservation and analyses, standard procedures for sample processing are presented in the report

Synthesis of no-carrier-added alpha-[11C]methyl-L-tryptophan

International Nuclear Information System (INIS)

Chaly, T.; Diksic, M.

1988-01-01

Described here is a synthesis of no-carrier-added alpha-[ 11 C]methyl-L-tryptophan based on alkylation with 11 CH 3 I of an anion generated by reacting the Schiff base of L-tryptophan methyl ester with di-isopropylamine. The synthesis requires approximately 30 min after the end of 11 CO 2 collection and gives alpha-[ 11 C]methyl-L-tryptophan in a 20-25% radiochemical yield calculated at the end of the synthesis and without correction for radioactive decay. The specific activity of the final radiopharmaceutical, measured at the end of the synthesis, was around 2000 Ci/mmol. Data confirming the stereospecificity of the synthesis are also presented

Natural radioactivity in ground water near the Savannah River Site

International Nuclear Information System (INIS)

Price, V. Jr.; Michel, J.

1990-08-01

A study of natural radioactivity in groundwater on and adjacent to the Savannah River Site (SRS) in Aiken (SC) was conducted to determine the spatial and temporal variations in the concentration of specific radionuclides. All available measurements for gross alpha particle activity, gross beta activity, uranium, Ra-226, Ra-228, and radon were collated. Relatively few radionuclide-specific results were found. Twenty samples from drinking water supplies in the area were collected in October 1987 and analyzed for U-238, U-234, Ra-226, Ra-228, and Rn-222. The aquifer type for each public water supply system was determined, and statistical analyses were conducted to detect differences among aquifer types and geographic areas defined at the country level. For samples from the public water wells and distribution systems on and adjacent to the site, most of the gross alpha particle activity could be attributed to Ra-226. Aquifer type was an important factor in determining the level of radioactivity in groundwater. The distribution and geochemical factors affecting the distribution of each radionuclide for the different aquifer types are discussed in detail. Statistical analyses were also run to test for aerial differences, among counties and the site. For all types of measurements, there were no differences in the distribution of radioactivity among the ten counties in the vicinity of the site or the site itself. The mean value for the plant was the lowest of all geographic areas for gross alpha particle activity and radon, intermediate for gross beta activity, and in the upper ranks for Ra-226 and Ra-228. It is concluded that the drinking water quality onsite is comparable with that in the vicinity. 19 refs., 5 figs., 5 tabs

Precision measurements on trapped antihydrogen in the ALPHA experiment

Science.gov (United States)

Eriksson, S.

2018-03-01

Both the 1S-2S transition and the ground state hyperfine spectrum have been observed in trapped antihydrogen. The former constitutes the first observation of resonant interaction of light with an anti-atom, and the latter is the first detailed measurement of a spectral feature in antihydrogen. Owing to the narrow intrinsic linewidth of the 1S-2S transition and use of two-photon laser excitation, the transition energy can be precisely determined in both hydrogen and antihydrogen, allowing a direct comparison as a test of fundamental symmetry. The result is consistent with CPT invariance at a relative precision of around 2×10-10. This constitutes the most precise measurement of a property of antihydrogen. The hyperfine spectrum of antihydrogen is determined to a relative uncertainty of 4×10-4. The excited state and the hyperfine spectroscopy techniques currently both show sensitivity at the few 100 kHz level on the absolute scale. Here, the most recent work of the ALPHA collaboration on precision spectroscopy of antihydrogen is presented together with an outlook on improving the precision of measurements involving lasers and microwave radiation. Prospects of measuring the Lamb shift and determining the antiproton charge radius in trapped antihydrogen in the ALPHA apparatus are presented. Future perspectives of precision measurements of trapped antihydrogen in the ALPHA apparatus when the ELENA facility becomes available to experiments at CERN are discussed. This article is part of the Theo Murphy meeting issue `Antiproton physics in the ELENA era'.

Environmental radioactivity in Turkey, 2010

International Nuclear Information System (INIS)

2011-01-01

In this report, the activity concentrations of natural and artificial radionuclides and gross alpha/beta activities measured in the environmental and food samples provided from 81 provinces of the country within the environmental radioactivity monitoring program in 2010 and outdoor gamma dose rates obtained by means of car-borne measurement system are presented. The activity concentrations of the natural and artificial radionuclides in the samples were measured by using the gamma spectrometry, the alpha spectrometry, the liquid scintillation counter and the gross alpha /beta counting system. The mean activity concentrations of 2 26Ra, 2 32Th and 4 0K in the analyzed surface samples were found as 28.11±1.23 Bq kg - 1, 32.4±1.2 Bq kg - 1 and 430.8±12.5, respectively, while the mean activity concentration of the fission product 1 37Cs was found as 9.78±0.79 Bq kg - 1. The mean absorbed gamma dose rate in outdoor due to external exposure emitted by natural radionuclides in soil samples and the corresponding annual effective dose were evaluated as 50.5 nGy h - 1 and 0.062 mSv y - 1, respectively. Total indicative doses of the analyzed drinking water samples were below the limit values. The activity concentrations of 2 38U, 2 32Th and 2 26Ra in the analyzed food samples were lower than the minimum detectable activity while 1 34Cs radionuclide was not observed. The mean activity concentrations of 1 37Cs and 9 0Sr radionuclides measured in the milk samples are 1.01 Bq L - 1 and 0.29 Bq L - 1, respectively. These values are lower than the limit value specified for foods subjected to control based on the regulation of the EU 737/90/EC. The total annual effective dose arising from the internal exposure from radiation emitting from 4 0K, 1 37Cs and 9 0Sr radionuclides analyzed in the food samples are evaluated as 196.6 Sv. In conclusion, the results of the monitoring program in 2010 show that the levels of radioactivity in the environment are low and do not pose any

Conceptual design report for alpha waste incinerator

International Nuclear Information System (INIS)

1979-04-01

The Alpha Waste Incinerator, a new facility in the SRP H-Area, will process transuranic or alpha-contaminated combustible solid wastes. It will seal the radioactive ash and scrubbing salt residues in cans for interim storage in drums on site burial ground pads. This report includes objectives, project estimate, schedule, standards and criteria, excluded costs, safety evaluation, energy consumption, environmental assessment, and key drawings

Development of a Radioactive Waste Assay System

Energy Technology Data Exchange (ETDEWEB)

Kang, Duck Won; Song, Myung Jae; Shin, Sang Woon; Sung, Kee Bang; Ko, Dae Hach [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Kim, Kil Jeong; Park, Jong Mook; Jee, Kwang Yoong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-12-31

Nuclear Act of Korea requires the manifest of low and intermediate level radioactive waste generated at nuclear power plants prior to disposal sites.Individual history records of the radioactive waste should be contained the information about the activity of nuclides in the drum, total activity, weight, the type of waste. A fully automated nuclide analysis assay system, non-destructive analysis and evaluation system of the radioactive waste, was developed through this research project. For the nuclides that could not be analysis directly by MCA, the activities of the representative {gamma}-emitters(Cs-137, Co-60) contained in the drum were measured by using that system. Then scaling factors were used to calculate the activities of {alpha}, {beta}-emitters. Furthermore, this system can automatically mark the analysis results onto the drum surface. An automated drum handling system developed through this research project can reduce the radiation exposure to workers. (author). 41 refs., figs.

Radioactive decay of sup(91m)Nb

Energy Technology Data Exchange (ETDEWEB)

Lakshminarayana, V.; Venkataratnam, S.; Rao, B.V.T.; Narasimham, K.L.; Chintalapudi, S.N.

1987-08-01

The radioactive decay of sup(91m)Nb, produced by the reaction /sup 89/Y(..cap alpha.., 2n), is studied using Ge(Li), HPGe and Si(Li) detectors. The K-conversion coefficient, ..cap alpha..sub(K), of the 104.5 keV transition is determined accurately, for the first time, from the Nb Ksub(..cap alpha..) x-ray and 104.5 keV gamma-ray intensities. The experimental value of ..cap alpha..sub(K) thus determined is 115(5), in agreement with the value expected for an M4 transition.

Phase I Final Report: Ultra-Low Background Alpha Activity Counter

International Nuclear Information System (INIS)

Warburton, W.K.

2005-01-01

In certain important physics experiments that search for rare-events, such as neutrino or double beta decay detections, it is critical to minimize the number of background events that arise from alpha particle emitted by the natural radioactivity in the materials used to construct the experiment. Similarly, the natural radioactivity in materials used to connect and package silicon microcircuits must also be minimized in order to eliminate ''soft errors'' caused by alpha particles depositing charges within the microcircuits and thereby changing their logic states. For these, and related reasons in the areas of environmental cleanup and nuclear materials tracking, there is a need that is important from commercial, scientific, and national security perspectives to develop an ultra-low background alpha counter that would be capable of measuring materials' alpha particle emissivity at rates well below 0.00001 alpha/cm 2 /hour. This rate, which corresponds to 24 alpha particles per square meter per day, is essentially impossible to achieve with existing commercial instruments because the natural radioactivity of the materials used to construct even the best of these counters produces background rates at the 0.005 alpha/cm 2 /hr level. Our company (XIA) had previously developed an instrument that uses electronic background suppression to operate at the 0.0005 0.005 alpha/cm 2 /hr level. This patented technology sets up an electric field between a large planar sample and a large planar anode, and fills the gap with pure Nitrogen. An alpha particle entering the chamber ionizes the Nitrogen, producing a ''track'' of electrons, which drift to the anode in the electric field. Tracks close to the anode take less than 10 microseconds (us) to be collected, giving a preamplifier signal with a 10 us risetime. Tracks from the sample have to drift across the full anode-sample gap and produce a 35 us risetime signal. By analyzing the preamplifier signals with a digital signal

Survey of radioactive contamination of foodstuffs

International Nuclear Information System (INIS)

Lee, W. R.; Lee, C. W.; Choi, G. S.; Cho, Y. H.; Kang, M. J.; Cheong, K. H.; Kim, H. R.; Kwak, J. Y.

2005-11-01

The purpose of this study is to survey and assess radioactive contamination of foodstuffs in order to reduce the probability of intake of contaminated foodstuffs. Based on survey and assessment, final goal is to improve the public health by radiation protection. Sampled foodstuffs items are collected from the markets : one group are imported foodstuffs and the other group are domestic foodstuffs producted around nuclear facilities. After pretreatments such as drying, ashing, and homogenization, all samples were analyzed by gamma spectrometer system. The 137 Cs radionuclide was only measured among the regulation radionuclides ( 137 Cs, 134 Cs, 131 I) of food code. All radionuclides of the domestic foodstuffs collected around nuclear facilities were below Minimum Detectable Activity (MDA). But the activity concentrations of Inonotus obliquus (Chaga mushooms) from Russia ranged up to 171.27 (average value : 36.65) Bq/kg-fresh. In the case of blueberry jam, the radioactivity of 137 Cs is higher than expected value. Other samples are below MDA except some spices. Based on the previous and present results, it should be strengthen to survey for Inontus obliquus (Chaga mushooms), of which the radioactivity shows the range from MDA up to 800.01 Bq/kg-fresh. It should assess the public radiation exposure via food chain because it has the excess provability of the maximum permitted level of food code, which is regulation of KFDA. The development method based on international standard would be used at radioactive analysis as well as education of practical workers and it could be applied as the basis data for amending the analysis method of food code. Our country only surveys gamma emitting radionuclides till now but international organization or foreign countries for example EU survey alpha and beta emitting radionuclides as well as gamma emitting radionuclides. So our country should also research necessity of survey for alpha and beta emitting radionuclides

Alpha Beam Energy Determination Using a Range Measuring Device for Radioisotope Production

Energy Technology Data Exchange (ETDEWEB)

Choi, Jun Yong; Kim, Byeon Gil; Hong, Seung Pyo; Kim, Ran Young; Chun, Kwon Soo [Korea Institute of Radiological and Medical Sciences, Seoul (Korea, Republic of)

2016-05-15

The threshold energy of the {sup 209}Bi(α,3n){sup 210} At reaction is at about 30MeV. Our laboratory suggested an energy measurement method to confirm the proton-beam's energy by using a range measurement device. The experiment was performed energy measurement of alpha beam. The alpha beam of energy 29 MeV has been extracted from the cyclotron for the production of {sup 211}At. This device was composed of four parts: an absorber, a drive shaft, and a servo motor and a Faraday cup. The drive shaft was mounted on the absorber and connects with the axis of the servo motor and rotates linearly and circularly by this servo motor. A Faraday cup is for measuring the beam flux. As this drive shaft rotates, the thickness of the absorber varies depending on the rotation angle of the absorber. The energy of the alpha particle accelerated and extracted from MC-50 cyclotron was calculated with the measurement of the particle range in Al foil and using ASTAR, SRIM, MCNPX software. There were a little discrepancy between the expected energy and the calculated energy within the 0.5MeV error range. We have a plan to make an experiment with various alpha particle energies and another methodology, for example, the cross section measurement of the nuclear reaction.

Measurement of nuclear cross sections using radioactive beams

International Nuclear Information System (INIS)

Lizcano, D.; Aguilera, E.F.; Martinez Q, E.

1999-01-01

One of the main applications of the production and use of nuclear radioactive beams is the measurement of nuclear cross sections. In this work is used a 6 He nuclear radioactive beam (β emitting with half life 806.7 ms) for the study of the reaction 6 + 209 Bi which could have several products. This investigation was realized in collaboration with the personnel of the Nuclear Structure laboratory at the University of Notre Dame (U.S.A.) and the National institute of Nuclear Research and CONACyT by Mexico. (Author)

DEVELOPMENT OF AN ON-LINE, REAL-TIME ALPHA RADIATION MEASURING INSTRUMENT FOR LIQUID STREAMS

International Nuclear Information System (INIS)

Unknown

1999-01-01

Thermo Power Corporation has proven the technical viability of an on-line, real-time alpha radionuclide instrument for aqueous sample analysis through laboratory and initial field tests of the instrument. The instrument has been shown to be isotonically sensitive to extremely low (ten parts per trillion, or femto Curies per liter) levels of a broad range of radioisotopes. Performance enhancement and other scaling data obtained during the course of this investigation have shown that on-line, real-time operation is possible, with a sub 30-minute response time analyzing 20 ppb (30 pCi/1) natural uranium. Now that these initial field tests in Oak Ridge, Tennessee have been successfully completed, Thermo Power plans to conduct comprehensive field tests of the instrument. The purpose of these endurance tests will be to determine the endurance characteristics of the Thermo Alpha Monitor for Water when it is used by non-Thermo Power personnel in a series of one or more extended field tests. Such endurance testing is the vital next step towards the commercialization of the Alpha Monitor. Subsequently, it will be possible to provide the DOE with an instrument that has the capability of obtaining rapid feedback about the concentrations of alpha-emitting isotope contamination in effluent water streams (Subsurface Contaminants Focus Area). It will also be useful for process control of remediation and D and D operations such as monitoring scrubber/rinse water radioactivity levels (Mixed Waste, Plutonium and D and D Focus Areas)

New systematics of cluster- and alpha-decay half lives

International Nuclear Information System (INIS)

Poenaru, D.N.; Greiner, W.

1994-01-01

Available as short communication only. The cluster (or 'exotic') radioactivities belong to a rich variety of nuclear decay modes which are phenomena intermediate between fission and alpha decay. In this contribution a single universal curve for the logarithm of the partial half-life for each kind of cluster radioactivity of even-even parent nuclei is presented. This handy relationship reproduces well the up to now 14 even-even half-life measurements within a ratio of 3.86 or rms=0.587 orders of magnitude. Its universality consists in the fact that instead of having different lines for various parent nuclei, like in the 'classical' systematics (Geiger-Nuttall plot) one can get practically only one line for each decay mode. (Author) 1 Fig., 2 Refs

From the discovery of radioactivity to the production of radioactive beams

International Nuclear Information System (INIS)

Bimbot, R.

1999-01-01

The evolution of the projectiles used to explore the nucleus influenced strongly the development of Nuclear Physics. The alpha particles from radioactivity were the projectiles mostly used up to the second world war. This period was marked by fundamental discoveries, as those of artificial radioactivity and of fission. From the 1930's to 1070, light accelerated particles (electrons, protons, deuterons, isotopes of helium) became universally used. A third period began in the 1960's with the emergence of heavy ion accelerators, the use of which led to a true revolution in the study of nuclear matter. Finally, the fourth period started in 1985 when the first secondary beams of radioactive nuclei were produced, and opened new ways in physics. (authors)

On-site radioactive soil contamination at the Andreeva Bay shore technical base, Northwest Russia.

Science.gov (United States)

Reistad, O; Dowdall, M; Selnaes, Ø G; Standring, W J F; Hustveit, S; Steenhuisen, F; Sørlie, A

2008-07-01

The radioactive waste (RAW) storage site at Andreeva Bay in the Russian Northwest has experienced radioactive contamination both as a result of activities carried out at the site and due to incidents that have occurred there in the past such as accidental releases of radioactive materials. The site is an interesting case study for decommissioning due to the extremely large amounts of radioactivity present at the site and the conditions under which it is stored; very little has been previously published in the scientific literature about this site. This paper complements the paper describing dose rates at Andreeva Bay which is published in this issue of Journal of Environmental Radioactivity by the same authors. This study presents new data related to the activity concentrations of (137)Cs and (90)Sr in surface soils and measurements of alpha- and beta-particle fluxes taken at different areas around the site. Limited data on 60Co is also presented. The results of the study indicate that the main areas of site contamination are associated with the former spent nuclear fuel storage facility at Building 5, due to accidental discharges which began in 1982. Substantial contamination is also observed at the solid radioactive waste storage facilities, probably due to the ingress of water into these facilities. More than 240 samples were measured: maximum contamination levels were 1 x 10(6)Bq/kg (137)Cs (mean value 4.1 x 10(5)Bq/kg) and 4 x 10(6)Bq/kg (90)Sr (mean value 1.2 x1 0(5)Bq/kg). Localised patches of alpha and beta contamination were also observed throughout the site.

Inventory of radioactive material entering the marine environment: Sea disposal of radioactive waste

International Nuclear Information System (INIS)

1991-03-01

Variable amounts of packaged low level radioactive waste have been disposed at more than 50 sites in the northern parts of the Atlantic and Pacific Oceans. The last known disposal operation was in 1982, at a site about 550 km off the European continental shelf in the Atlantic Ocean. Since 1957, the IAEA has provided specific guidance and recommendations for ensuring that disposal of radioactive wastes into the sea will not result in unacceptable hazards to human health and marine organisms, damage to amenities or interference with other legitimate uses of the sea. In 1972, the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter designated the IAEA as the competent international authority in matters related to sea disposal of radioactive waste. The Contracting Parties requested the IAEA to develop an inventory of radioactive wastes entering the marine environment from all sources as an information base with which the impact of radioactive materials from disposal operations can be more adequately assessed. The continuous compilation of these data could ensure that the IAEA recommendations on the disposal rate in a single basin are not overstepped. The inventory shows that between 1946 to 1982 an estimated 46 PBq 1 (1.24 MCi) of radioactive waste coming from research, medicine, the nuclear industry and military activities were packaged, usually in metal drums lined with a concrete or bitumen matrix, and disposed of at sea. This inventory includes some unpackaged wastes and liquid wastes which were disposed of from 1950 to 1960. Beta-gamma emitters represent more than 98% of the total radioactivity of the waste and tritium alone represents one third of the total radioactivity disposed at the North East Atlantic sites. The other beta-gamma emitters radionuclides include 90 Sr, 137 Cs, 55 Fe, 58 Co, 60 Co, 125 I and 14 C. The wastes also contain low quantities of alpha-emitting nuclides with plutonium and americium isotopes representing

Radiobiological long-term accumulation of environmental alpha radioactivity in extracted human teeth and animal bones in Malaysia

International Nuclear Information System (INIS)

Almayahi, B.A.; Tajuddin, A.A.; Jaafar, M.S.

2014-01-01

In this study, the radiobiological analysis of natural alpha emitters in extracted human teeth and animal bones from Malaysia was estimated. The microdistributions of alpha particles in tooth and bone samples were measured using CR-39 alpha-particle track detectors. The lowest and highest alpha emission rates in teeth in the Kedah and Perak states were 0.0080 ± 0.0005 mBq cm −2 and 0.061 ± 0.008 mBq cm −2 , whereas those of bones in the Perlis and Kedah states were 0.0140 ± 0.0001 mBq cm −2 and 0.7700 ± 0.0282 mBq cm −2 , respectively. The average alpha emission rate in male teeth was 0.0209 ± 0.0008 mBq cm −2 , whereas that of female teeth was 0.0199 ± 0.0010 mBq cm −2 . The alpha emission rate in teeth is higher in smokers (0.0228 ± 0.0008 mBq cm −2 ) than in non-smokers (0.0179 ± 0.0008 mBq cm −2 ). Such difference was found statistically significant (p < 0.01). - Highlights: • Alpha emission rates in teeth from smokers slightly higher than non-smokers. • Difference between alpha rates in male and female tooth not statistically significant. • Alpha particles have the same effect at any age. • Difference between alpha rates in bones was statistically significant

Determination of total alpha activity index in samples of radioactive wastes; Determinacion del indice de actividad alfa total en muestras de desechos radiactivos

Energy Technology Data Exchange (ETDEWEB)

Galicia C, F. J.

2015-07-01

This study aimed to develop a methodology of preparation and quantification of samples containing radionuclides beta and/or alpha emitters, to determine the rates of alpha and beta total activity of radioactive waste samples. For this, a device of planchettes preparer was designed, to assist the planchettes preparation in a controlled environment and free of corrosive vapors. Planchettes were prepared in three means: nitrate, carbonate and sulfate, to different mass thickness, natural uranium (alpha and beta emitter) and in case of Sr-90 (beta emitter pure) only in half nitrate; and these planchettes were quantified in an alpha/beta counter, in order to construct the self-absorption curves for alpha and beta particles. These curves are necessary to determine the rate of alpha-beta activity of any sample because they provide the self-absorption correction factor to be applied in calculating the index. Samples with U were prepared with the help of the device of planchettes preparer and subsequently were analyzed in the proportional counter Mpc-100 Pic brand. Samples with Sr-90 were prepared without the device to see if there was a different behavior with respect to obtaining mass thickness. Similarly they were calcined and carried out count in the Mpc-100. To perform the count, first the parameters of counter operating were determined: operating voltages for alpha and beta particles 630 and 1500 V respectively, a count routine was generated where the time and count type were adjusted, and counting efficiencies for alpha and beta particles, with the aid of calibration sources of {sup 210}Po for alphas and {sup 90}Sr for betas. According to the results, the counts per minute will decrease as increasing the mass thickness of the sample (self-absorption curve), adjusting this behavior to an exponential function in all cases studied. The minor self-absorption of alpha and beta particles in the case of U was obtained in sulfate medium. The self-absorption curves of Sr-90

Implantation of alpha spectrometry methodology for the determination of U and Th isotopes in igneous rocks: application to the study of radioactive desequilibrium in the Trindade Island, Brazil

International Nuclear Information System (INIS)

Santos, Rosana Nunes dos

2001-01-01

This work describes the implementation of experimental procedures for alpha spectrometry measurement of 238 U, 234 U and 230 Th activities in silicates. The best experimental conditions were defined using 233 U, 232 U and 229 Th radioactive tracers and simulating the usual conditions found in processing silicates. The chemical procedures consists of the following steps: radioactive tracer addition and sample dissolution by acid digestion, U and Th pre-concentration by co-precipitation, element separation and purification by ion exchange chromatography and electrodeposition in inox steel disks. In order to evaluate its effectiveness, the procedure was applied to the Brazilian geological standards BB-1 (basalt) and GB-1 (granite). The obtained chemical yields for uranium and thorium are of about 60% and 70%, respectively, for both matrices. The described methodology furnishes activity measurements with less than 4% relative precision and accuracies of about 1%, that are essential for petrogenetic applications. The 238 U and 232 Th series disequilibrium conditions were investigated by alpha spectrometry, together with neutron activation analysis and natural gamma-ray spectrometry. 234 U/ 238 U, 238 U/ 232 Th and 230 Th/ 232 Th activity ratios and the 234 Th, 214 Pb, 214 Bi, 235 U, 228 Ac, 212 Pb, 212 Bi and 208 Tl specific activities were obtained. These results were interpreted with the help of additional constraints given by the larger and smaller elements concentrations, measured by X-ray fluorescence. The 232 Th series is in secular radioactive equilibrium in all analysed samples. In the case of the 238 U series, the equilibrium condition was verified, as expected, in the oldest rocks from the Trindade Island (Trindade Complex and Desejado Sequence). On the other hand, the results show that, in the samples from the last three volcanic episodes in the island (Morro Vermelho Formation, Valado Formation and Vulcao do Paredao), the 230 Th and 238 U are not in

Error calculations statistics in radioactive measurements

International Nuclear Information System (INIS)

Verdera, Silvia

1994-01-01

Basic approach and procedures frequently used in the practice of radioactive measurements.Statistical principles applied are part of Good radiopharmaceutical Practices and quality assurance.Concept of error, classification as systematic and random errors.Statistic fundamentals,probability theories, populations distributions, Bernoulli, Poisson,Gauss, t-test distribution,Ξ2 test, error propagation based on analysis of variance.Bibliography.z table,t-test table, Poisson index ,Ξ2 test

Non-destructive examination and estimation of radioactivity levels for decorative building materials

International Nuclear Information System (INIS)

Mao Yahong; Liu Yigang; Lin Libin

2003-01-01

Measurement of gamma ray intensity from building materials can be substituted by measuring alpha rays following outline of a radionuclide decay. Exposure levels of alpha ray from the surface of decorative materials can be measured non-destructively by placing a detector on the surface of the materials. Authors have studied the relationship between gamma specific activities of natural radionuclides and alpha and beta ray level in building materials used in interior decoration, and the saturated thickness of beta ray from the surface of different materials. The results showed that the range of beta ray with the maximum energy in natural radioactive series is longer than thickness of a piece of decorative materials. So the exposure level of beta ray cannot be used to estimate the limit of external and internal indexes. The polynomial between exposure level of alpha ray from surface (α) and external index (I γ ) for granite is: I γ =0.38 + 49.84α + 288.24α 2 . The measured values were in accordance with the values from the polynomial within 95%. The polynomial between exposure level of alpha ray from surface (α) and external index (Iγ) for polishing tiles is: I γ =0.42 + 343.55α-32999.66α 2 . The measured values were in accordance with the values from the polynomial within 90%

Absolute measurement of the $\\beta\\alpha$ decay of $^{16}$N

CERN Multimedia

We propose to study the $\\beta$-decay of $^{16}$N at ISOLDE with the aim of determining the branching ratio for $\\beta\\alpha$ decay on an absolute scale. There are indications that the previously measured branching ratio is in error by an amount significantly larger than the quoted uncertainty. This limits the precision with which the S-factor of the astrophysically important $^{12}$C($\\alpha, \\gamma)^{16}$O reaction can be determined.

Measurement methodology for fulfilling of waste acceptance criteria for low and intermediate level radioactive waste in storages - 59016

International Nuclear Information System (INIS)

Sokcic-Kostic, M.; Langer, F.; Schultheis, R.

2012-01-01

with half life longer than Cs-137, whereas intermediate level waste is sub-classified as short lived waste and long lived waste. Long lived isotopes are mainly alpha emitters which result from contamination of the RAW by nuclear fuel material and its fission and breeding products. The sub-classification is made on base of mass specific alpha activity of the waste. Before being sent to storage the waste has to be treated. This includes volume reduction by combustion or compaction, depending on the physical properties of the waste, as well as immobilisation by grouting, saving thereby storage space and costs. After the treatment the waste is filled into packages preferably drums or containers. Before the waste is sent to the waste storage a passport is generated which includes all relevant data to show that the waste package fulfils the requirements as defined by the waste storage operating company. NUKEM Technologies has developed a large number of monitors for a radiological waste characterisation. The preferred methods are non-destructive, allowing high throughput and giving detailed information. Parameters that cannot be measured after treatment, have to be measured during the treatment process or data has to be collected from available sources like the origin of the waste or from the waste deliverer. To optimise this process NUKEM Technologies has developed a tracking system which traces the waste during treatment starting from delivery and finishing by the transportation to the final storage. (authors)

Determination of alpha activity and fissile mass content in solid waste by systems using neutron interrogation

International Nuclear Information System (INIS)

Romeyer Dherbey, J.; Lacruche, G.; Berne, R.; Auge, J.; Martin Deidier, L.; Butez, M.

1990-01-01

The Quantitative control (determination of heavy nuclides and alpha activity) of alpha radioactive wastes is necessary, particularly to determine if the waste is in accordance with the surface storage limits. In order to reduce the uncertainty on the alpha activity resulting from unknown isotopic composition, inhomogeneity of heavy nuclides in the matrix, combination of several methods is necessary. In the paper we present the Cadarache development work in the NDA of solid waste using the Californium shuffler, 14 Mev neutron generator, and also passive techniques such as neutron emission measurement and gamma spectrometry. Experimental systems combining active and passive methods are presented (COSAC, BANCO, DANAIDE, PROMETHEE)

Baseline Radioactivity Measurements In The Vicinity Of A Gold ...

African Journals Online (AJOL)

Western Region, Ghana) to obtain baseline radioactivity data prior to the installation of Cs-137 nuclear density gauges for quality control measure-ment of the density of slurry in the pipelines at the plant. A survey meter, gamma spectrometry and ...

Micromegas detector for $^{33}$S(n,$\\alpha$) cross section measurement at n_TOF

CERN Multimedia

The present proposal is a consequence of the successful tests performed in 2011 related to the Letter of Intent CERN-INTC-2010-023/I-092. The main goal of this proposal is a first (n,$\\alpha$) cross section measurement with the Micromegas detector presently running at n_TOF for monitoring purposes and fission cross section measurements. The $^{33}$S(n,$\\alpha$) cross section is of interest in astrophysics mainly due to the origin of $^{36}$S which is still an open question. $^{33}$S is also of interest in medical physics since it has been proposed as a possible/alternative cooperating target to boron neutron capture therapy. Important discrepancies between previous measurements of $^{33}$S(n,$\\alpha$) cross section and especially between the resonance parameters are found in the literature. We propose to measure the (n,$\\alpha$) cross section of the stable isotope $^{33}$S in the energy range up to 300 keV covering the astrophysical range of interest. The possibility of increasing this energy range will be st...

Study on Method of Asphalt Density Measurement Using Low Level Radioactive Isotope

International Nuclear Information System (INIS)

Chung, Jin-young; Kim, Jung-hoon; Whang, Joo-ho

2008-01-01

The fundamental cause of damage to road pavement is insufficient management of asphalt density during construction. Currently, asphalt density in Korea is measured in a laboratory by extracting a core sample after construction. This method delays the overall time of measurement and therefore it is difficult to achieve real-time density management. Using a radioactive isotope for measuring asphalt density during construction reduces measuring time thus enabling realtime measurement. Also, it is provided reliable density measurement to achieve effective density management at work sites. However, existing radiological equipment has not been widely used because of management restrictions and regulations due to the high radiation dose. In this study, we employed a non-destructive method for density measurement. Density is measured by using a portable gamma-ray backscatter device having a radioactivity emission of 100 μCi or less (notice No. 2002-23, Ministry of Science and Technology, standards on radiation protection, etc.), a sealed radioactive source subject to declaration

The diffusion and deposition of the gaseous and solid alpha radionuclides/aerosols in air

International Nuclear Information System (INIS)

Danis, A.; Ciubotariu, M.; Oncescu, M.; Mocsy, I.

1999-01-01

The diffusion and deposition of gaseous and solids alpha radionuclides and aerosols in air are processes which implicate low element amounts and therefore their studies require the using of very accurate and sensitive analysis methods. The alpha track method meets these requirements. The used alpha radionuclides were: Rn-222, as gaseous radionuclide and its solid descendants genetically related as solid radionuclides and the descendants attached to different particles from air as alpha aerosols. All these radionuclides were obtained from a calibrated Ra-226 source. The source was included into an air tight device with a well known volume and used after 40 days when the Ra-226 and its alpha descendants were under radioactive equilibrium. The relative amount and activity of each decay product, at any duration, for any initial mass of Ra-226 parent radionuclide, were calculated using a programme for computation of the U-238 radioactive series gamma accumulation, UURASE, adapted for alpha accumulation as ALFAURASE programme. The radon, Rn-222, as well as the solid alpha radionuclides and aerosols were measured using a new alpha monitoring device with or without paper filter for solid radionuclides and aerosols stopping. The track detectors of CR-39 type were incorporated with these monitoring devices. In order to calibrate the CR-39 detectors, a radon intercomparison programme was established with the participation of the SSNTD group from the Institute of Nuclear Research ATOMKI, Debrecen, Hungary, Institute of Public Health, Cluj-Napoca and SSNTD research group from IFIN-HH. We have used for radon calibration a special experimental device and a Ra-226 source. Using an air tight diffusion and deposition device, coupled with the source device, the concentration of radon and solid alpha radionuclides and aerosols were determined using the alpha track method. The alpha monitoring devices were fixed vertically at different distances from the place of radon penetration into

Measurement of $\\alpha_{s}$ and the non-strange spectral functions in hadronic $\\tau$ decays with OPAL

CERN Document Server

Menke, S

1999-01-01

The spectral functions of the vector current and the axial-vector current have been measured in hadronic tau decays using the OPAL detector at LEP. Within the framework of the Operator Product Expansion a simultaneous determination of the strong coupling constant alpha /sub s/, the non-perturbative operators of dimension 6 and 8 and of the gluon condensate has been performed. Different perturbative descriptions have been compared to the data. The Contour Improved Fixed Order Perturbation Theory gives alpha /sub s/(m/sub tau //sup 2/)=0.348+or-0.009/sub exp/+or-0.019/sub theo/ at the tau - mass scale and alpha /sub s/(m/sub Z//sup 2/)=0.1219+or-0.0010/sub exp/+or-0.0017/sub theo/ at the Z/sup 0/-mass scale. The values obtained for alpha /sub s/(m/sub Z//sup 2/) using Fixed Order Perturbation Theory or Renormalon Chain Resummation are 2.3and 4.1 smaller, respectively. The `running' of the strong coupling between s /sub 0/ approximately=1.3 GeV/sup 2/ and s/sub 0/=m/sub tau //sup 2/ has been tested from direct f...

The management and disposal of alpha-contaminated waste

International Nuclear Information System (INIS)

Duclos, J.; Farges, L.; Lavie, J.M.; Marque, Y.

1981-01-01

The establishment of the French National Agency for Radioactive Waste Management (ANDRA) in November 1979 marked the beginning of industrial management of this type of waste in France. The organization of this Agency is sufficiently flexible to reconcile the need for the assumption of responsibility by the public authorities for a matter having considerable long-term implications; the importance of making available to all radioactive-waste producers the benefits of the research carried out by large national entities; (Commissariat a l'energie atomique, Electricite de France, etc.) and the obligation to satisfy all the scientific and financial requirements regarding optimal radioactive-waste management. The Centre de stockage de la Manche (CSM) is at present concerned with the special requirements relating to alpha waste. These are being analysed, together with their implications for technical specifications and industrial management. A strategy for alpha waste storage is defined in the light of the forecasts of waste deliveries for the next 20 years. (author)

Hand Monitor for Simultaneous Measurements of Alpha and Beta Contamination

Energy Technology Data Exchange (ETDEWEB)

Andersson, I Oe; Braun, J; Soederlund, B

1960-11-15

An instrument is described which measures {alpha} and {beta} contamination of the hands simultaneously. This has been achieved by using as detectors 8 flow counters paired in 4 units of two chambers, one unit for each side of the hand. The inner chamber of every unit (adjacent to the hands) delivers {alpha}-pulses, the outer chambers deliver {beta}-pulses. When two finger contacts are pushed the detectors are closing around the hands and the measurement is started. Audible and visual warnings operate when the MPL is exceeded. Similar warnings ope.rate if hands are removed before the end of the counting period. The activity levels are logarithmically indicated on four pointer instruments, which are automatically zeroed when the next measurement is started. The instrument is now commercially available.

Measurements of radioactive and xenobiotic substances in the biosphere in the Netherlands 1983

International Nuclear Information System (INIS)

1983-01-01

In this annual report the results and conclusions are given of measurements of radioactive and xenobiotic substances in the biosphere of the Netherlands. The measurements are coordinated by the Coordinating Committee for the Monitoring of Radioactive and Xenobiotic Substances (CCRX)

In vivo studies of the biosynthesis of alpha-eleostearic acid in the seed of Momordica charantia L

International Nuclear Information System (INIS)

Liu, L.; Hammond, E.G.; Nikolau, B.J.

1997-01-01

In vivo radiotracer experiments using 14C-labeled acetate, oleate, linoleate, and linolenate were conducted to investigate the biosynthesis of alpha-eleostearic acid in the seeds of Momordica charantia. With the exception of [14C]linolenate, all of these precursors radioactively labeled alpha-eleostearate. Kinetics of the time course of metabolism of the radioactive precursors indicate that linoleate is the acyl precursor of alpha-eleostearate and that its conversion to alpha-eleostearate occurs while the acyl moiety is esterified to PC. Pulse-chase experiments with 14C-labeled acetate or linoleate provided additional corroborative evidence that linoleoyl PC is the precursor of alpha-eleostearoyl PC

Natural radioactivity in groundwater sources in Ireland

Energy Technology Data Exchange (ETDEWEB)

Currivan, L.; Dowdall, A.; Mcginnity, P.; Ciara, M. [Radiological Protection Institute of Ireland (Ireland); Craig, M. [Environmental Protection Agency (Ireland)

2014-07-01

The Radiological Protection Institute of Ireland (RPII) in collaboration with the Irish Environmental Protection Agency (EPA) undertook a national survey of radioactivity in groundwater sources for compliance with parameters set out in the European Communities Drinking Water Directive. The Directive outlines the minimum requirements for the quality of drinking water and water intended for human consumption. Over two hundred samples were screened for radioactivity. Where indicated, analysis for individual radionuclide activity was undertaken and the radiation dose arising calculated. Furthermore, samples were analysed for radon concentration. This survey is the first comprehensive national survey of radioactivity in groundwater sources in Ireland. Approximately 18 per cent of drinking water in Ireland originates from groundwater and springs with the remainder from surface water. Between 2007 and 2011, water samples from a representative network of groundwater sources were analysed and assessed for compliance with the radioactivity parameters set out in the Drinking Water Directive. The assessment was carried out using the methodology for screening drinking water set out by the WHO. For practical purposes the WHO recommended screening levels for drinking water below which no further action is required of 100 mBq/l for gross alpha activity and 1000 mBq/l for gross beta activity were applied. Of the 203 groundwater sources screened for gross alpha and gross beta all met the gross beta activity criteria of less than 1000 mBq/l and 175 supplies had gross alpha activity concentrations of less than 100 mBq/l. For these sources no further analysis was required. The remaining 28 sources required further (radionuclide-specific) analysis from an alpha activity perspective. Results on ranges and distributions of radionuclide concentrations in groundwater as well as ingestion doses estimated for consumers of these water supplies will be presented. Document available in abstract

Effect of water purification process in radioactive content: analysis on small scale purification plants

International Nuclear Information System (INIS)

Lopez del Rio, H.; Quiroga S, J. C.; Davila R, J. I.; Mireles G, F.

2009-10-01

Water from small scale purification plants is a low cost alternative for consumers in comparison to the bottled commercial presentations. Because of its low cost per liter, the consumption of this product has increased in recent years, stimulating in turn the installation of purification systems for these small businesses. The purpose of this study was to estimate the efficiency of small scale purification systems located in the cities of Zacatecas and Guadalupe, Zacatecas, to reduce the radioactive content of water. It was measured the total alpha and beta activity in water samples of entry and exit to process, through the liquid scintillation technique. In general it was observed that the process is more efficient in removing alpha that beta activity. The fraction of total alpha activity removed varied between 27 and 100%, while between 0 and 77% of the total beta activity was removed by the analyzed plants. In all cases, the total radioactivity level was lower than the maximum permissible value settled by the official mexican standard for drinking water. (Author)

The used epoxy matrix in immobilization sludge process of alpha emitter radioactive waste

International Nuclear Information System (INIS)

Walman, E.; Salimin, Z.; Johan, B.

1998-01-01

Immobilization of alpha emitter radioactive waste containing of ion complex of uranyl carbonate on uranium concentration ≤ 50 mg/l has been carried out using epoxy matrix. The first step of process is the coagulation of uranium with 1.3 mole/l of Ca(OH) 2 coagulant concentration on pH 8 to precipitate the calcium uranyl carbonate on uranium concentration ≤ g/l. The immobilization of calcium uranyl carbonate with epoxy matrix was done on variation of the ratio of resin epoxy and hardener of 1 : 1 (giving the maximum value of density and compressive strength), the increasing of precipitate loading capacity give the decreasing of compressive strength of embedded waste. The test of compressive strength and leaching was done for the embedded waste after its curing time using Paul Weber equipment and 7 days immersion of samples in normal water. On the precipitate loading capacity of 70%, the quality of embedded waste still conform to the standard quality value i.e. density 1.2 g/cm 3 , compressive strength 10 kN/cm 2 and there is not any release of radionuclide during leaching test (undetectable).. (author)

Decision for counting condition of radioactive waste activities measuring by Ludlum detector

International Nuclear Information System (INIS)

Bambang-Purwanto

2000-01-01

Radioactive waste must measured for activities before be throw out to environment. Measuring will be important in ordered to know activities can be given management direction. For activities radioactive waste on limit threshold value must processed, but for under limit threshold value activities can be throw out to environment. Activities measuring for solid radioactive waste and liquid by (Total, β, γ) Ludlum detector connected Mode-1000 Scaler Counting. Before measuring for solid waste activities was decisioned optimally counting condition, and be obtained are : sample weight 3.5 gram, heating temperature of 125 o C and heating time at 60 minutes. Activities measuring result by total detector ranges from (0.68-0.71) 10 -1 μCi/gram, β detector ranges from (0.24-0.25) 10 -1 μCi/gram and γ detector ranges from (0.35-0.37) μCi/gram

Portable scintillation gamma-spectrometer for field measurement of radioactivity in extensive objects

International Nuclear Information System (INIS)

Besshejko, O.A.; Vishnevskij, I.N.; Denisenko, R.V.; Malyuk, I.A.; Petrosyan, Eh.E.; Karpenko, S.A.; Prijmak, V.N.

2011-01-01

The portable scintillated gamma-spectrometer for field measurement of radioactivity in the volume objects was designed. The crystal CdWO 4 that has weak dependence of light yield from temperature in combination with PMT was applied as the gamma-rays detector. The design of the device provides the possibility for measuring radioactivity of the extensive objects in 4π-geometry without background measurements. In this case the value of the efficiency needed for specific activity calculation in close approximation depends only from crystal geometry and density of measuring object and may be set as the device parameter without efficiency calibration procedure during the operation. The spectrometer does not have an auxiliary radio-active source and connecting cables in the composition. The smartphone operated under Windows Mobile is used as the control module. Bluetooth connection provides data exchange between smartphone and measurement head.

Thermal treatment of organic radioactive waste

International Nuclear Information System (INIS)

Chrubasik, A.; Stich, W.

1993-01-01

The organic radioactive waste which is generated in nuclear and isotope facilities (power plants, research centers and other) must be treated in order to achieve a waste form suitable for long term storage and disposal. Therefore the resulting waste treatment products should be stable under influence of temperature, time, radioactivity, chemical and biological activity. Another reason for the treatment of organic waste is the volume reduction with respect to the storage costs. For different kinds of waste, different treatment technologies have been developed and some are now used in industrial scale. The paper gives process descriptions for the treatment of solid organic radioactive waste of low beta/gamma activity and alpha-contaminated solid organic radioactive waste, and the pyrolysis of organic radioactive waste

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

Measures Against-Illicit Trafficking of Nuclear Materials and Other Radioactive Sources

International Nuclear Information System (INIS)

Barakat, M.B.; Nassef, M.H.; El Mongy, S.A.

2008-01-01

Since the early nineties, illicit trafficking (IT) of nuclear materials and radioactive sources appeared as a new trend which raised the concern of the international community due to the grave consequences that would merge if these materials or radioactive sources fell into the hands of terrorist groups. However, by the end of the last century illicit trafficking of nuclear materials and radioactive sources lost its considerable salience, in spite of seizure of considerable amounts of 2 '3'5U (76% enrichment) in Bulgaria (May 1999) and also 235 U (30% enrichment) in Georgia (April 2000). Nevertheless, IT should be always considered as a continued and viable threat to the international community. Awareness of the problem should be developed and maintained among concerned circles as the first step towards combating illicit trafficking of nuclear materials and radioactive sources. Illicit trafficking of nuclear and radioactive materials needs serious consideration and proper attention by the governmental law enforcement authorities. Measures to combat with IT of nuclear material or radioactive sources should be effective in recovery, of stolen, removed or lost nuclear materials or radioactive sources due to the failure of the physical protection system or the State System Accounting and Control (SSAC) system which are normally applied for protecting these materials against illegal actions. Measures such as use of modern and efficient radiation monitoring equipment at the borders inspection points, is an important step in preventing the illicit trafficking of nuclear and radioactive materials across the borders. Also providing radiological training to specific personnel and workers in this field will minimize the consequences of a radiological attack in case of its occurrence. There is a real need to start to enter into cooperative agreements to strengthen borders security under the umbrella of IAEA to faster as an international cooperation in the illicit trafficking

Substantiation of the permissible radioactive contamination of working clothes

International Nuclear Information System (INIS)

Shcherbakov, V.L.; Korostin, A.S.

1977-01-01

A permissible level of working clothes contamination was determined on the base of the main migration routes of radioactive contaminants: permeation directly through the clothes into subclothes space on skin surface, emission into the air with amount of contaminants subsequently got by the organism of a working person through inhalation as well as transfer in the process of contacting of contaminated working clothes and surfaces of premises equipment, working person hands with amount of contaminants posteriorly got by the organism by alimentary or inhalation ways. Using the experimental and literature data available the permissible levels of working clothes contamination for the mentioned migration routes of radioactive materials have been calculated. According to the data obtained the permissible levels of working clothes contamination must not exceed 4 alpha-part/(cm 2 xmin) for contamination with high-tonic isotopes, 20 alpha-part./(cm 2 xmin) with other alpha-detine isotopes, 1000 beta-part./(cm 2 xmin) with beta-active ones. The permissible level of contamination of additional materials of the individual protection in the case of their contamination with high-tonic alpha-actine isotopes must not exceed 50 alpha-part./(cm 2 xmin), 200 alpha-part./(cm 2 xmin) for contamination th other alpha-active isotopes and 400 beta-part./(cm 2 xmin) with beta-active isotopes

Manual for target thickness measurement by alpha particle irradiation

International Nuclear Information System (INIS)

Dias, J.F.; Martins, M.N.

1990-04-01

A system is described for thin-target thickness measurement through the alpha particle energy loss when them traverse the target. It is also described the program used in the analysis of the target thickness. (L.C.) [pt

Radioactive Aerosol Size Distribution Measured in Nuclear Workplaces

International Nuclear Information System (INIS)

Kravchik, T.; Oved, S.; German, U.

2002-01-01

Inhalation is the main route for internal exposure of workers to radioactive aerosols in the nuclear industry.Aerosol's size distribution and in particular its activity median aerodynamic diameter (AMAD)is important for determining the fractional deposition of inhaled particles in the respiratory tract and the resulting doses. Respiratory tract models have been published by the International Commission on radiological Protection (ICRP).The former model has recommended a default AMAD of 1 micron for the calculation of dose coefficients for workers in the nuclear industry [1].The recent model recommends a 5 microns default diameter for occupational exposure which is considered to be more representative of workplace aerosols [2]. Several researches on radioactive aerosol's size distribution in nuclear workplaces has supported this recommendation [3,4].This paper presents the results of radioactive aerosols size distribution measurements taken at several workplaces of the uranium production process

Natural radioactivity of building materials coming from a volcanic region

International Nuclear Information System (INIS)

Roca, V.; Pugliese, M.; Sabbarese, C.; D'Onofrio, A.; Lubritto, C.; Terrasi, F.; Ermice, A.; Inglima, I.; Migliore, G.

2004-01-01

Radioactivity was found to be very high in tuff and other materials originating from volcanic lava. Emanation of radon from such materials is appreciably higher than from materials of other origin. This work allowed us to obtain a first complete database of natural radioactivity concentrations in building materials from this region. Measurements were carried out by means of a gamma spectrometry system. Gamma emitting daughter products of 222 Rn were measured to determine 226 Ra. The samples, after a routine treatment, were accommodated in sealed metallic containers for a time sufficient for the equilibrium to establish. The determination of the radon emanation power was carried out by using an electrostatic monitor. Alpha spectroscopy of radon daughters was used to evaluate the content of radon coming from the sample

Spreading Design of Radioactivity in Sea Water, Algae and Fish Samples inthe Coastal of Muria Peninsula Area

International Nuclear Information System (INIS)

Sutjipto; Muryono; Sumining

2000-01-01

Spreading design of radioactivity in sea water, brown algae (phaeopyceae)and kerapu fish (epeniphelus) samples in the coastal of Muria peninsula areahas been studied. This research was carried out with designed beside to knowspreading each radioactivity but also spreading design in relation to thecontent of Pu-239 and Cs-137. Samples taken, preparation and analysis basedon the procedures of environmental radioactivity analysis. The instrumentused for the analysis radioactivity were alpha counter with detector ZnS, lowlevel beta counter modified P3TM-BATAN with detector GM and spectrometergamma with detector Ge(Li). Alpha radioactivity obtained of sea water, algaeand fish were the fluctuation form of the natural background. Radionuclide ofPu-239 in samples not detect, because its concentration/radioactivity stillbelow the maximum concentration detection value of Pu-239 for algae and fishwas that 1.10 Bq/g, whereas for sea water was that 0.07 Bq/mL. Result for theradioactivity which give the highest alpha radioactivity obtained on thekerapu fish was that 1.56 x 10 -3 Bq/g, beta radioactivity on sea water wasthat 1.75 x 10 2 mBq/L, gamma radioactivity of K-40 on brown algae was that3.72 x 10 -2 Bq/g and gamma radioactivity of Tl-208 on fish as mentionedabove was that 1.35 x 10 -2 Bq/g. All the peak spectrum gamma energy ofCs-137 do not detect with gamma counter, so there are not the radionuclide ofCs-137 in the samples. Spreading design of radioactivity which occur in thecoastal of Muria peninsula area for alpha radioactivity was found on kerapufish, beta radioactivities on sea water and gamma radioactivity on brownalgae and kerapu fish. (author)

MONITORING OF RADIOACTIVITY AT DNURT CAMPUS

Directory of Open Access Journals (Sweden)

L. F. Dolina

2016-06-01

Full Text Available Purpose. The research paper aims to determine radioactive contamination on the territory of campus of Dnipropetrovsk National University of Railway Transport named after Academician V. Lazaryan (DNURT. Methodology. The dosimeters measured the radioactive contamination in different places (points of DNURT campus, focusing on public places. The centres of measurements became dormitories, monuments, stops, main entrances of the new and the old buildings, classrooms, basements, a swimming pool, boiler room and others. Findings. The conducted radiation monitoring for the first time in the history of the University discovered the source of radioactive contamination on DNURT territory and campus. The highest radiation background is observed on three points, namely: the pedestal of the monument, the monument to students-soldiers, the main entrance of the new building (columns. This can be explained by granite materials, which the pedestals and the stairs are made of. Originality. The largest contribution to the total value of annual effective dose of human exposure is made by ionizing radiation sources (IRS of building materials (65 - 70%. The radioactivity level of building materials is determined by the content of natural radionuclides that are included in uranium-radium and thorium decay series (18 and 12 radionuclides as well as potassium-40. Radioactivity of building materials is evaluated by the content of dominant radionuclides radium-226, thorium-232 and potassium-40. Their dominant role is explained by the fact that these long-lived high-energy - emitters are the products of decay of radium-226 in uranium series of and radium-224 in thorium series, exposing radioactive gases (radon-222 and radon-220. Radioactive gases are accumulated in the basements of educational buildings; their decay is accompanied by 100% alpha radiation, which is the most dangerous. Practical value. It is necessary to set radioactivity signs near the objects with high

Ultra-high-resolution alpha spectrometry for nuclear forensics and safeguards applications

International Nuclear Information System (INIS)

Bacrania, Minesh K.; Croce, Mark; Bond, Evelyn; Dry, Donald; Moody, W. Allen; Lamont, Stephen; Rabin, Michael; Rim, Jung; Smith, Audrey; Beall, James; Bennett, Douglas; Kotsubo, Vincent; Horansky, Robert; Hilton, Gene; Schmidt, Daniel; Ullom, Joel; Cantor, Robin

2010-01-01

We will present our work on the development of ultra-high-resolution detectors for alpha particle spectrometry. These detectors, based on superconducting transition-edge sensors, offer energy resolution that is five to ten times better than conventional silicon detectors. Using these microcalorimeter detectors, the isotopic composition of mixed-actinide samples can be determined rapidly without the need for actinide separation chemistry to isolate each element, or mass spectrometry to separate isotopic signatures that can not be resolved using traditional alpha spectrometry (e.g. Pu-239/Pu-240, or Pu-238/Am-241). This paper will cover the detector and measurement system, actinide source preparation, and the quantitative isotopic analysis of a number of forensics- and safeguards-relevant radioactive sources.

High α - radioactivity level in betel leaf (Piper Betel) and chewing tobacco

International Nuclear Information System (INIS)

Ghosh, Dipak; Deb, Argha; Maiti, Sunil; Harh, Sadananda

2011-01-01

Studies on alpha emitting radionuclides in tobacco samples is of significant importance as the interaction of alpha particles with cells chromosomes in different organs of tobacco eaters causes to carcinogenic changes in those organs. Apart from smoking, the tobacco products that are smokeless, like ghutka, chewing tobacco, etc., that are directly consumed through orally also contribute to carcinogenic health hazards. They can increase the internal radiation dose and thereby enhance the case of cancer in human population. Another important sample is betel leaf which is largely consumed by people. Since betel leaf is cultivated in lands using fertilizers having high alpha activity. Regular use of betel leaf may cause health hazards if alpha radioactivity is present in harmful quantities. In view of this the present work betel leafs and different type of tobacco products have been collected from the local market in and around Kolkata and alpha activity of those samples have been measured using CR-39 (SSNTD) detectors and dose has been estimated. (author)

Quality Assurance In Radioactivity Measurements

International Nuclear Information System (INIS)

Riekstina, D.; Veveris, O.; Smilskalne, G.

2007-01-01

The credibility of obtained results is ensured by the quality assurance and control. The main requisitions involved in the quality assurance of the laboratory according to the requirements of LVS EN ISO/IEC 17025:2005 are: 1) the use of calibrated equipment only; 2) the regular and long-time use of reference materials in the control of equipment; 3) the estimation of uncertainty sources and determination of uncertainties within the given interval of credibility; 4) the validation and verification. The very important requirement is regular participation in the interlaboratory intercomparison exercises that makes it possible to estimate and find possible error sources and carry out the corrective actions. The measurements of the radioactivity of Cs-137, Co-60, H-3, the natural radioactive nuclides as well as other radionuclides in different environmental (soil, precipitation, different types of water, needles, et al.) samples, and in various radioactive polluted objects are carried out in the Laboratory of Radiation physics. The quality assurance system was implemented in our laboratory in 2000. Since 1999 laboratory is regular participant in the interlaboratory intercomparison exercises, organized by the RISO National Laboratory (Denmark) and IAEA (Vienna). The paper shows the laboratory's system of quality assurance and its implementation. We have the internal quality audit program that takes into account the requirements of LVS EN ISO/IEC 17025: 2005, but the main attention is paid to the intercomparison of the results of analyses of laboratories, their evaluation and interpretation. Only credible and justified results can be the basis for further use in any field, thus making it possible to make legitimate decisions. (Authors)

Usage of portable spectrometers for prevention of radioactive and nuclear materials illicit trafficking

International Nuclear Information System (INIS)

Bystrov, Evgenij; Antonau, Uladzimir; Gurinovich, Uladzimir; Kazhamiakin, Valery; Petrov, Vitaly; Shulhovich, Heorhi; Tischenko, Siarhei

2008-01-01

Full text: It is publicly known that radioactive and nuclear materials can be shielded not only with passive protection but also be masked with legally transported radioactive substances. These radioactive substances can be contained as medical radionuclides incorporated in human body or in cargos with high content of natural isotopes 40 K, 232 Th, 238 U, etc. This constitutes an additional serious obstacle to detection of radioactive substances trafficking. Dosimeters, search monitors or radiation portal monitors have insufficient capability for this objective. It is necessary to use much more intellectual instruments that can detect both gamma radiation and other types of radiation (neutron, alpha, beta), recognize radionuclide type and identify it with high probability. To address these objectives, we have developed portable scintillation gamma spectrometers AT6101 and AT6102 with neutron radiation detection and measurement of surface contamination with alpha and beta particles. Gamma scintillation spectrometry methods using NaI(Tl) crystal allow to detect source of gamma radiation, measure ambient dose rate equivalent of gamma radiation and identify radionuclide composition. The implemented spectrometry method of gamma radiation dose rate measurement using 'spectrum-dose' function allows to measure ambient dose rate equivalent of gamma radiation with relative error up to 20%. Radionuclide identification is based on channel-by-channel spectrum convolution with the second derivative from Gaussian function. Peak search and analysis and peak position comparison to energy values of gamma lines of library radionuclides is performed in convolution spectrum. Analysis of relative intensity of detected gamma lines with peak detection threshold overrun allows qualitative definition of radionuclide composition in object under examination. The special feature of the spectrometers is LED stabilization through spectrometric path. The stabilization system covers PEM, pre

Qualitative chemical analysis of plutonium by Alpha spectroscopy

International Nuclear Information System (INIS)

Ramirez G, J Qumica.J.

1994-01-01

In this work the separation and purification of plutonium from irradiated uranium was done. The plutonium, produced by the irradiation of uranium in a nuclear reactor and the β decay of 239 Np, was stabilized to Pu +4 with sodium nitrite. Plutonium was separated from the fission products and uranium by ion exchange using the resin Ag 1 X 8. It was electrodeposited on stainless steel discs and the alpha radioactivity of plutonium was measured in a surface barrier detector. The results showed that plutonium was separated with a radiochemical purity higher than 99 %. (Author)

Recent developments for field monitoring of alpha-emitting contaminants in the environment

International Nuclear Information System (INIS)

Ahlquist, A.J.; Umbarger, C.J.; Stoker, A.K.

1978-01-01

The Los Alamos Scientific Laboratory has adapted two field methods to assess rapidly locations and concentrations of alpha-emitting contaminants in soil. (1) A ZnS scintillator is used for gross-alpha measurements on soil samples. Sample preparation and the calibration and detection limits of the system are discussed, and results of gross-alpha analysis are compared with results of a 239 Pu radiochemistry analysis. (2) A Phoswich detector is used as a field survey instrument because it can detect lower levels of radioactivity than the FIDLER probe. The electronics are carried in a truck and the probe is connected by an umbilical cord. The system electronics are calibrated with an energy window of 12-40 keV which allows detection of Pu, Am, Th (using daughter L X-rays of the alpha-emitters) and 137 Cs (using its daughter 32 keV X-rays). The bremsstrahlung from 90 Sr can also be detected. (author)

Radioactivity measurements

International Nuclear Information System (INIS)

Schwach, G.

1986-01-01

This is an overview of radioactivity monitoring work done in the Austrian Research Centre Seibersdorf in the wake of the Chernobyl accident. It consists of air, rainwater, food and personnel monitoring. Additional services to the public are: information and development of a database and a computer code for predicting future radionuclide concentration in air, soil, water and food. (G.Q.)

Radiobiological significance of radioactive contamination - summary assessment based on great number of measurements

Energy Technology Data Exchange (ETDEWEB)

Angelov, V [Civil Defence Administration, Sofia (Bulgaria); Bonchev, Ts; Mavrodiev, V; Kyrdzhilov, N [Sofia Univ. (Bulgaria). Fizicheski Fakultet

1996-12-31

In order to facilitate quantitative and qualitative characterisation of radioactive contamination the authors introduce a relative estimate of radionuclide activity by setting as a reference the most abundant element -Co-60 in the case of the Kozloduy NPP. The ratio {eta}{sub i} of the mean annual permissible concentration in air for each radionuclide (RPC-92) to that of Co-60 is calculated. It is found that {eta}{sub i} has the same or close values for groups of radionuclides, e.g. {eta}{sub i} = 2.10{sup -4} for {sup 238} Pu, {sup 239} Pu, {sup 240} Pu, {sup 241} Am, {sup 244} Cm; {eta}{sub i} = 5 for {sup 89} Sr, {sup 91} Y; {sup 93} Nb, {sup 134} Cs, {sup 137} Cs; {eta}{sub i} = 50 for {sup 55} Fe, {sup 63} Ni, {sup 95} Zr, {sup 95} Nb, {sup 140} Ba, {sup 140} La. Then it is compared to the experimentally measured values of the same quantity {eta}{sub iexp}, derived from surface contamination data. The ratio {eta}{sub iexp}/{eta}{sub i} is plotted against log {eta}{sub i}. The resulting nomograms give graphic representation of the radiobiological significance of various radionuclide groups. Data from different locations at the Kozloduy NPP are presented. It is found that the alpha emitter contamination has highest values in the Unit 1 (WWER-440) control rooms after repair. The Unit 5 (WWER-1000) has lower alpha contamination compared to WWER-440 units. 1 ref., 5 figs., 1 tab.

Portable scintillation gamma-spectrometer for field measurement of radioactivity in extensive objects

Directory of Open Access Journals (Sweden)

O. A. Bezshyyko

2011-12-01

Full Text Available The portable scintillated gamma-spectrometer for field measurement of radioactivity in the volume objects was designed. The crystal CdWO4 that has weak dependence of light yield from temperature in combination with PMT was applied as the gamma-rays detector. The design of the device provides the possibility for measuring radioactivity of the extensive objects in 4-geometry without background measurements. In this case the value of the efficiency needed for specific activity calculation in close approximation depends only from crystal geometry and density of measuring object and may be set as the device parameter without efficiency calibration procedure during the operation. The spectrometer does not have an auxiliary radio-active source and connecting cables in the composition. The smartphone operated under Windows Mobile is used as the control module. Bluetooth connection provides data exchange between smartphone and measurement head.

Alpha resonant scattering for astrophysical reaction studies

International Nuclear Information System (INIS)

Yamaguchi, H.; Kahl, D.; Nakao, T.; Wakabayashi, Y.; Kubano, S.; Hashimoto, T.; Hayakawa, S.; Kawabata, T.; Iwasa, N.; Teranishi, T.; Kwon, Y. K.; Binh, D. N.; Khiem, L. H.; Duy, N. G.

2014-01-01

Several alpha-induced astrophysical reactions have been studied at CRIB (CNS Radioactive Ion Beam separator), which is a low-energy RI beam separator at Center for Nuclear Study (CNS) of the University of Tokyo. One of the methods to study them is the α resonant scattering using the thick-target method in inverse kinematics. Among the recent studies at CRIB, the measurement of 7 Be+α resonant scattering is discussed. Based on the result of the experiment, we evaluated the contributions of high-lying resonances for the 7 Be(α,γ) reaction, and proposed a new cluster band in 11 C

Alpha radiation gauge for the measurement of gas density

International Nuclear Information System (INIS)

Lech, M.

1977-01-01

Alpha gauge for the measurement of gas density with thick alfa source, has been developed. The gauge is based on radiation transmission through a space filled with gas and total-count principle. Air density can be measured in the range 1,2 - 1,27 kg m -3 with a maximum standard deviation of 2 x 10 -3 kg m -3 . (author)

Radiobiological long-term accumulation of environmental alpha radioactivity in extracted human teeth and animal bones in Malaysia.

Science.gov (United States)

Almayahi, B A; Tajuddin, A A; Jaafar, M S

2014-03-01

In this study, the radiobiological analysis of natural alpha emitters in extracted human teeth and animal bones from Malaysia was estimated. The microdistributions of alpha particles in tooth and bone samples were measured using CR-39 alpha-particle track detectors. The lowest and highest alpha emission rates in teeth in the Kedah and Perak states were 0.0080 ± 0.0005 mBq cm(-2) and 0.061 ± 0.008 mBq cm(-2), whereas those of bones in the Perlis and Kedah states were 0.0140 ± 0.0001 mBq cm(-2) and 0.7700 ± 0.0282 mBq cm(-2), respectively. The average alpha emission rate in male teeth was 0.0209 ± 0.0008 mBq cm(-2), whereas that of female teeth was 0.0199 ± 0.0010 mBq cm(-2). The alpha emission rate in teeth is higher in smokers (0.0228 ± 0.0008 mBq cm(-2)) than in non-smokers (0.0179 ± 0.0008 mBq cm(-2)). Such difference was found statistically significant (p < 0.01). Copyright © 2014 Elsevier Ltd. All rights reserved.

Measurement of Natural Radioactive Nuclide Concentrations and the Dose Estimation of Workers Originated from Radon in Manganese Ore Mine

International Nuclear Information System (INIS)

Mansour, N.A.; Hassan, N.M.; Blasy, M.R.

2013-01-01

Manganese ore is widely used in many industries. Such as ore contain natural radioactive nuclides at various concentrations. If this ore contain high concentrations of natural radioactive nuclides, workers handling them might be exposed to significant levels of radiation. Therefore it is important to determine the radioactive nuclides in this ore. Also the regulation of radon concentration at workplaces has gained an accentuated importance in all countries. Nevertheless, at this time there is no globally accepted workplace protocol that sets out safe radon concentration values. In this study the radon concentration measured by using an Alpha Guard radon monitor, the equilibrium factor which was greater than the value given in literature, effective radiation dose, which are necessary for the exact estimation of the radiation dose originating from radon. The regulation of radon concentration at workplaces has gained an accentuated importance in all countries. Approach: The natural radionuclides ( 238 U, 232 Th and 40 K) contents of manganese ore samples collected from Umm Bogma, southwest Sinai and from the mountain access Hamid South Eastern Desert, Egypt have been determined by low background spectroscopy using hyper-pure germanium (HPGe) detector. Results: The mean activities due to the three radionuclides ( 238 U, 232 Th and 40 K) were found to be 1500±65, 490±65 and 364±45 Bqkg -1 , respectively. The absorbed dose rate due to the natural radioactivity in samples under investigation ranged from 1522±45 → 1796±43 nGyh -1 . The radium equivalent activity varied from 3807±114→ 4446±133 Bqkg -1 .The representative external hazard index values for the corresponding samples are also estimated. Conclusion: The results of this assessment obtained by the gamma-ray spectroscopic analysis, have indicated that the levels of natural radioactivity were lower than the international recommended limits.

Synthesis of tritium or deuterium labelled 19-nor-3. cap alpha. -hydroxy-5. cap alpha. -androstan-17-one from nortestosterone

Energy Technology Data Exchange (ETDEWEB)

Protiva, J; Klinotova, E [Karlova Univ., Prague (Czechoslovakia). Prirodovedecka Fakulta; Filip, J [Ustav pro Vyzkum, Vyrobu a Vyuziti Radioisotopu, Prague (Czechoslovakia); Hampl, R [Research Inst. of Endocrinology, Praha (Czechoslovakia)

1982-10-20

Tritium and/or deuterium (5-H) labelled 19-nor-3..cap alpha..-hydroxy-5..cap alpha..-androstan-17-one (norandrosterone) was prepared from nortestosterone in view to use it as a radioligand for radioimmunoassay of the main nortestosterone metabolites. Based upon model experiments using testosterone and deuterium labelling, the following four step procedure was established: nortestosterone was oxidized with pyridine chlorochromate and the resulting 19-nor-4-androsten-3,17-dione was tritiated with tritium gas under catalysis with tris(triphenylphosphine)rhodium chloride to give (4,5..cap alpha..-/sup 3/H)19-nor-5..cap alpha..-androstan-3,17-dione. A selective reduction of the latter compound yielded (5-/sup 3/H)19-nor-3..cap alpha..-hydroxy-5..cap alpha..-androstan-17-one of the molar radioactivity 0.3 TBq (8.15 Ci)/mmol.

Study on lowering the specific radioactivity of rare earth chlorides

International Nuclear Information System (INIS)

Shinhuor, Y.; Jyuung, J.; Shyuerjung, T.; Xiangping, L.

1985-01-01

In this paper, the source of radioactivity in rare earth chlorides and the chemical behaviour of its main radionuclides in metallurgy processing are investigated. It is pointed out that the radioactivity in rare earths comes from the long-life radionuclides in three natural radioactive series. Nine of them (/sup 238/U, /sup 234/U, /sup 230/Th, /sup 226/Ra, /sup 210/Po, /sup 232/Th, /sup 228/Th, /sup 235/U, /sup 231/Pa) are alpha-emitters, three of them (/sup 228/Ra, /sup 227/Ac, /sup 210/Pb) are beta-emitters. Among them alpha-emitters contribute the total specific activity of rare earths directly. The rare earths are easily purified in preferential dissolution, radium elimination, and other processes

Determination of detailed regulations concerning transportation of radioactive materials by vehicles

International Nuclear Information System (INIS)

1978-01-01

These provisions are established on the basis of the ''Regulations concerning transportation of radioactive materials by vehicles''. The terms used hereinafter are according to those used in the Regulations. Radioactive materials include uranium 233, uranium 235, plutonium 238, plutonium 239, plutonium 241, the compounds of such materials and the substances containing one or two and more of such materials, excluding the radioactive materials with not more than 15 grams of such uranium and plutonium. The permissible surface density is 1/100,000 microcurie per cm 2 for radioactive materials emitting alpha-ray and 1/10,000 microcurie per cm 2 for such materials which does not emit alpha-ray. For the radioactive materials which can be transported as L type loads, their kinds and quantities are specified in the forms of solid, liquid and gas, respectively. Transporting conditions including the quantity and leakage in A, BM and BU type loads are provided for, respectively, in the lists attached and in the particular sections. (Okada, K.)

The system for measurements of radioactive contamination of environment and food in Poland

International Nuclear Information System (INIS)

Grabowski, D.; Kurowski, W.

1990-01-01

The service for Measurements of Radioactive Contamination comprises a network of 152 measuring stations. They are carrying out continuous measurements of gamma radiation dose rates and radioactivity measurements of 24 hours samples of air (aerosols) and total fallout. On the territory of each province there are selected points for sampling of environmental materials and food. Frequency of sampling depends on material being collected. 1 tab., 2 figs. (A.S.)

First measurements of the radioactivity in atmospheric precipitations

Energy Technology Data Exchange (ETDEWEB)

Santomauro, L; Cigna, A

1953-01-01

Measurements conducted between February 1951 and November 1952 showed that nuclear-weapon tests at Las Vegas, Eniwetok, and Montebello were followed, 1, 2, and 3 weeks later, respectively, by an increase in the radioactive content of rain and snow falling in Italy.

Radioactivity levels in well water supplies within the greater Chicago area

International Nuclear Information System (INIS)

Kristoff, L.M.; Lordi, D.T.; Lue-Hing, C.

1976-01-01

The radiological analysis of well water supplies within the geographical boundaries of the Metropolitan Sanitary District of Greater Chicago was prompted by the relatively high total alpha levels encountered in wastewaters of a MSDGC water reclamation plant as compared to the wastewaters of the other waste treatment plants. Consequently, 87 wells constituting 42 water supplies were sampled and analyzed for total alpha and beta radioactivity. The wells were grouped according to depth. In general, both total alpha and total beta radioactivity concentrations were found to be a function of well depth. The relatively higher total alpha and beta activities in the wastewaters to one of the treatment plants was attributed to the higher levels found in the well water supply. Comparison with the USEPA's Drinking Water Regulations for Radionuclides (July 9, 1976) showed the maximum total alpha level of 15 pCi/liter was exceeded in 3 wells and 32 of the deep well waters had total alpha level greater than 5 pCi/liter. The total beta level of 50 pCi/liter was exceeded in 8 wells

Determination of detailed standards for transportation of radioactive materials by ships

International Nuclear Information System (INIS)

1978-01-01

These provisions are established on the basis of the ''Regulations on the transport and storage of dangerous things by ships''. The terms used hereinafter are according to those used in the Regulations. Radioactive materials, etc., include uranium 233, uranium 235, plutonium 238, plutonium 239, plutonium 241, the compounds of such materials and the substances containing one or two and more of such materials, excluding such materials of not more than 15 grams. The permissible surface density of radioactive materials is 1/100,000 of one microcurie per cm 2 for the radioactive materials emitting alpha-ray and 1/10,000 of one microcurie per cm 2 for the radioactive materials not emitting alpha-ray. For the radioactive materials which can be transported as L type cargo, their quantity of radioactivity is defined in their solid, liquid and gaseous forms. The limit of quantity of such cargo is described in detail in the lists attached. Transporting conditions of A, BM and BU type cargos are specified respectively in the particular sections. (Okada, K.)

Measurement of {alpha} particle energy loss in biological tissue below 2 MeV

Energy Technology Data Exchange (ETDEWEB)

Stella, S. [Department of Nuclear and Theoretical Physics, University of Pavia, Pavia (Italy); National Institute of Nuclear Physics (INFN), Pavia (Italy); Bortolussi, S. [Department of Nuclear and Theoretical Physics, University of Pavia, Pavia (Italy); National Institute of Nuclear Physics (INFN), Pavia (Italy)], E-mail: silva.bortolussi@pv.infn.it; Bruschi, P.; Portella, C. [Department of Nuclear and Theoretical Physics, University of Pavia, Pavia (Italy); Altieri, S. [Department of Nuclear and Theoretical Physics, University of Pavia, Pavia (Italy); National Institute of Nuclear Physics (INFN), Pavia (Italy)

2009-09-01

The energy loss of {alpha} particles crossing biological tissue at energies between 0.8 and 2.2 MeV has been measured. This energy range is very important for boron neutron capture therapy, based on the {sup 10}B(n,{alpha}){sup 7}Li reaction, which emits {alpha} particles with energies of 1.78 and 1.47 MeV. One of the methods used for the measurement of the boron concentration in tissue is based on the deconvolution of the {alpha} spectra obtained from neutron irradiation of thin (70 {mu}m) tissue samples. For this technique, a knowledge of the behaviour of the energy loss of the particles in the irradiated tissue is of critical importance. In particular, the curve of the residual energy as a function of the distance travelled in the tissue must be known. In this paper, the results of an experiment carried out with an {sup 241}Am source and a series of cryostatic sections of rat-lung tissue are presented. The experimental measurements are compared with the results of Monte Carlo calculations performed with the MCNPX code.

National audit of radioactivity measurements in Nuclear Medicine Centres

International Nuclear Information System (INIS)

Ravindra, Anuradha; Kulkarni, D.B.; Joseph, Leena; Babu, D.A.R.

2014-01-01

Routine activity measurements of radiopharmaceutical solutions in Nuclear Medicine Centres (NMC) are carried out with the help of radionuclide calibrators (RC). These solutions are either ingested or injected to the patient for diagnosis or therapy. However, for the realization of an optimized examination, the activity of these radiopharmaceuticals must be determined accurately before administering it to patients. The primary standards are maintained by Radiation Standards Section, Radiological Physics and Advisory Division. National audit programmes of Iodine -131 activity measurements with RCs are conducted biannually to establish traceability to national standards and to check the status of nuclear medicine practice followed at the NMC. The results of fifteenth audit of 131 I activity measurements with RC are presented in this paper. Questionnaires were sent to two hundred and thirty three NMCs in-the country. One hundred and nine NMC's agreed for participation and accordingly, glass vials containing radioactive 131 I solution of nominal activity of 100 MBq were procured from Board of Radiation and Isotope Technology, Mumbai. The radioactivity in each vial was determined with high pressure re-entrant gamma ionisation chamber (GIC), a secondary standard maintained by this laboratory. The sensitivity coefficient of GIC is traceable to the primary standard. The standardized radioactive solution of 131 I in glass vial was sent to each participant. Measurements results were reported in the reporting form sent. This audit was conducted in four schedules in Jan 2013. One hundred and sixty six results were received from one hundred and nine participants as many participants took measurements on more than one isotope calibrator

Radioactive Sources in Medicine: Impact of Additional Security Measures

International Nuclear Information System (INIS)

Classic, K. L.; Vetter, R. J.; Nelson, K. L.

2004-01-01

For many years, medical centers and hospitals have utilized appropriate security measures to prevent theft or unauthorized use of radioactive materials. Recent anxiety about orphan sources and terrorism has heightened concern about diversion of radioactive sources for purposes of constructing a radiological dispersion device. Some medical centers and hospitals may have responded by conducting threat assessments and incorporating additional measures into their security plans, but uniform recommendations or regulations have not been promulgated by regulatory agencies. The International Atomic Energy Agency drafted interim guidance for the purpose of assisting member states in deciding what security measures should be taken for various radioactive sources. The recommendations are aimed at regulators, but suppliers and users also may find the recommendations to be helpful. The purpose of this paper is to describe threat assessments and additional security actions that were taken by one large and one medium-sized medical center and the impact these measures had on operations. Both medical centers possess blood bank irradiators, low-dose-rate therapy sources, and Mo-99/Tc-99m generators that are common to many health care organizations. Other medical devices that were evaluated include high-dose-rate after loaders, intravascular brachytherapy sources, a Co-60 stereotactic surgery unit, and self-shielded irradiators used in biomedical research. This paper will discuss the impact additional security has had on practices that utilize these sources, cost of various security alternatives, and the importance of a security culture in assuring the integrity of security measures without negatively impacting beneficial use of these sources. (Author) 10 refs

Microdistribution of uranium in kidney using alpha radiography of body animal

International Nuclear Information System (INIS)

Cebrian, D.; Morcillo, M. A.

2006-01-01

The radiation dose estimation after an internal contamination by a radionuclide requires the use of biokinetic and dosimetric models, which provide the tools for its calculation. The detailed knowledge of the biokinetic behaviour of the corresponding radionuclide is needed in order to build these models. Laboratory animals are employed to get this knowledge. In this context, the use of appropriate radioactivity measurement techniques is important to follow the distribution of the radionuclide within the organism. In this study an animal model of rat treated with uranyl citrate has been used. Sections of the whole animal are made at different times post-administration, and alpha autoradiography is performed with the slices in order to study the microdistribution of the uranium in the kidney. the utility of the alpha autoradiography whole body animal sections for the detailed study of the alpha emitters biodistribution is shown. (Author) 16 refs

Effective liquid drop description for alpha decay of atomic nuclei

International Nuclear Information System (INIS)

Tavares, O.A.P.; Duarte, S.B.; Rodriguez, O.; Guzman, F.; Goncalves, M.; Garcia, F.

1998-06-01

Alpha decay half-lives are presented in the framework of an effective liquid drop model for different combination of mass transfer descriptions and inertia coefficients. Calculated half-life-values for ground-state to ground-state favoured alpha transitions are compared with available, updated experimental data. Results have shown that the present model is very suitable to treat the alpha decay process on equal foot as cluster radioactivity and cold fission processes. Better agreement with the data is found when the sub-set of even-even alpha emitters are considered in the calculation. (author)

Weak Interaction Measurements with Optically Trapped Radioactive Atoms

International Nuclear Information System (INIS)

Vieira, D.J.; Crane, S.G.; Guckert, R.; Zhao, X.; Brice, S.J.; Goldschmidt, A.; Hime, A.; Tupa, D.

1999-01-01

This is the final report of a three-year, Laboratory-Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The goal of this project is to apply the latest in magneto-optical and pure magnetic trapping technology to concentrate, cool, confine, and polarize radioactive atoms for precise electroweak interaction measurements. In particular, the authors have concentrated their efforts on the trapping of 82 Rb for a parity-violating, beta-asymmetry measurement. Progress has been made in successfully trapping of up to 6 million 82 Rb(t 1/2 =75s) atoms in a magneto-optical trap coupled to a mass separator. This represents a two order of magnitude improvement in the number trapped radioactive atoms over all previous work. They have also measured the atomic hyperfine structure of 82 Rb and demonstrated the MOT-to-MOT transfer and accumulation of atoms in a second trap. Finally, they have constructed and tested a time-orbiting-potential magnetic trap that will serve as a rotating beacon of spin-polarized nuclei and a beta-telescope detection system. Prototype experiments are now underway with the initial goal of making a 1% measurements of the beta-asymmetry parameter A which would match the world's best measurements

Alpha-emitting 'hot particles' in the vicinity of BNFL Sellafield, Cumbria

International Nuclear Information System (INIS)

Whittall, A.J.; Tossell, P.J.

2000-01-01

In a survey of environmental samples in the vicinity of BNFL Sellafield, two alpha-emitting radioactive particles were found in samples of grass. One particle appears to be of mineral origin, the other was not definitively identified, but may be a fragment of fuel cladding. Conservative estimates of the activities of these particles are very low. The abundance of radioactive particles in the terrestrial food chain appears to be low, with no evidence for any alpha-emitting hot particles in foodstuffs for consumption by humans. Results suggest that there is no significant dose to man through inhalation or ingestion pathways. (author)

Low level radioactivity measurements with phoswich detectors using coincident techniques and digital pulse processing analysis.

Science.gov (United States)

de la Fuente, R; de Celis, B; del Canto, V; Lumbreras, J M; de Celis Alonso, B; Martín-Martín, A; Gutierrez-Villanueva, J L

2008-10-01

A new system has been developed for the detection of low radioactivity levels of fission products and actinides using coincidence techniques. The device combines a phoswich detector for alpha/beta/gamma-ray recognition with a fast digital card for electronic pulse analysis. The phoswich can be used in a coincident mode by identifying the composed signal produced by the simultaneous detection of alpha/beta particles and X-rays/gamma particles. The technique of coincidences with phoswich detectors was proposed recently to verify the Nuclear Test Ban Treaty (NTBT) which established the necessity of monitoring low levels of gaseous fission products produced by underground nuclear explosions. With the device proposed here it is possible to identify the coincidence events and determine the energy and type of coincident particles. The sensitivity of the system has been improved by employing liquid scintillators and a high resolution low energy germanium detector. In this case it is possible to identify simultaneously by alpha/gamma coincidence transuranic nuclides present in environmental samples without necessity of performing radiochemical separation. The minimum detectable activity was estimated to be 0.01 Bq kg(-1) for 0.1 kg of soil and 1000 min counting.

International measures needed to protect metal recycling facilities from radioactive materials

International Nuclear Information System (INIS)

Mattia, M.; Wiener, R.

1999-01-01

. The government of every country that licences the use of radioactive material should institute a program to determine both the location of every known source and the effectiveness of current controls over that source. (ii) Control of orphaned material. Each government should institute a program for the safe removal and control of orphaned radioactive sources and material without penalty to the individual that has unintentionally received it. (iii) Transportation rules. International agreements should be developed that allow discovered radioactive material to be easily yet safely transported to either its point of origin or to a facility for its safe disposal. (iv) Registry of events. An international mechanism should be developed for the documentation and reporting of radiation related incidents and the discovery of potentially orphaned radioactive sources and material. (v) Universal measurements. There are several highly technical ways to describe radioactivity. None of these can be easily understood by the individuals who may encounter this material. The international community should agree on how radioactivity will be measured and qualified in a manner that is easily understood by all individuals. (vi) Technology sharing. As new, user-friendly technology is being advanced, the international community should keep track of such advances, share this information, as well as fund the development of technology that will accurately and consistently identify radioactive material that could be found in all forms of metal or containers. (author)

Quality assurance for radioactive measurement in nuclear medicine

International Nuclear Information System (INIS)

2006-01-01

The field of nuclear medicine continues to grow around the world, owing in part to a number of successful programmes carried out by the IAEA to enhance the use of nuclear medicine techniques in Member States. The implementation of quality assurance (QA) programmes to ensure the safe application of radiopharmaceuticals has, however, been variable in many Member States. One possible reason is the lack of a unified set of principles regarding the establishment of such programmes. This publication addresses the issue of QA programmes for radioactivity measurement in nuclear medicine. A group of experts consulted by the IAEA recommended in 2002 that unified principles concerning QA and quality control (QC) procedures for the measurement of radioactivity in nuclear medicine be developed because of its importance in controlling the safety and effectiveness of the use of radiopharmaceuticals. This publication is the result of advice provided to the IAEA by experts in the fields of radionuclide metrology, medical physics and radiopharmacy. This report can be considered to be a more detailed and updated version of IAEA-TECDOC-602, Quality Control of Nuclear Medicine Instruments, published in 1991. Advances in the field of nuclear instrumentation since that report was published, particularly in imaging, and the increased emphasis on QA and QC prompted the need for an update. Moreover, it was realized that the activity measurement and imaging aspects had each become so specialized as to be better treated in separate publications. The present report focuses on the factors affecting radioactivity measurement and the implementation of QA and QC programmes to ensure accurate and consistent results. The IAEA has developed a safety standard on The Management System for Facilities and Activities (IAEA Safety Standards Series No. GS-R-3), which replaces the IAEA publications on QA issued as Safety Series No. 50-C/SG-Q (1996). In GS-R-3, the management system is described as a set of

Occupational exposure of phosphate mine workers: airborne radioactivity measurements and dose assessment

International Nuclear Information System (INIS)

Khater, Ashraf E.; Hussein, M.A.; Hussein, Mohamed I.

2004-01-01

Under the Egyptian program for radiation safety and control, airborne radioactivity measurements and radiological dose assessment were conducted in some phosphate and uranium mines. Abu-Tartor mine is one of the biggest underground phosphate mines in Egypt. Airborne radioactivity, radon ( 222 Rn) and its short-lived decay products (progenies) and thoron ( 220 Rn), were measured in selected locations along the mine. The environmental gamma and workers dose equivalent rate (mSv/y) were measured inside and outside the mine using thermo-luminescence dosimeters (TLD). The results were presented and discussed. The calculated annual effective dose due to airborne radioactivity is the main source of occupational exposure and exceeding the maximum recommended level by ICRP-60 inside the mine tunnels. A number of recommendations are suggested to control the occupational exposures

Treatment and disposal of radioactive wastes and countermeasures

International Nuclear Information System (INIS)

Nomura, Kiyoshi

1990-01-01

The treatment and disposal of radioactive wastes are one of important subjects, together with the development of dismantling techniques accompanying the decommissioning measures for nuclear power plants and the development of reprocessing techniques for nuclear fuel cycle. About 25 years have elapsed since the beginning of commercial nuclear power generation in 1966, and the time that the solution of the problems of waste treatment and disposal must be tackled on full scale has come. The features and the amount of generation of radioactive wastes, the way of thinking on the treatment and disposal, and the present status of the treatment and disposal are outlined. For securing the stable supply of energy and solving the environmental problem of the earth such as acid rain and warming, nuclear power generation accomplishes important roles. The objective of waste treatment is based on the way of thinking of 'as low as reasonably achievable (ALARA)'. The radioactive wastes are classified into alpha waste and beta-gamma waste. The present status of RI wastes, the techniques of treating radioactive wastes, the nuclide separation, extinction treatment and the disposal in strata of high level radioactive wastes and the disposal of low level wastes are reported. (K.I.)

Alpha activity of 190 Pt isotope measured with CR-39 track detector

International Nuclear Information System (INIS)

Tavares, O.A.P.; Terranova, M.L.

1996-11-01

A new method to measure alpha activity of long-lived radioisotopes is reported. The method consists basically in using CR-39 track detectors in close contact with thick samples of the radioelement to be investigated. Accordingly, a long-term exposure experiment has been performed using metallic sheets of natural platinum to measure alpha activity of platinum 190 isotope. The half-life of platinum 190 has been obtained in good agreement with two recent theoretical half-life predictions. (author). 21 refs., 3 figs., 2 tabs

Measures against illicit trafficking of nuclear and other radioactive materials in the Slovak Republic

International Nuclear Information System (INIS)

Bezak, S.

2001-01-01

Full text: This presentation contains description of measures used in the Slovak Republic to combat illicit trafficking of nuclear and other radioactive materials. The main goal of these measures is to allow safe and effective utilization of nuclear and other radioactive materials under surveillance of responsible state authorities as well as recover materials that were removed form legal utilization despite the preventive measures. Prevention is the most effective and the cheapest way how to overcome problems. An important precondition for prevention is existence of a national (or state) system for controlled utilization of nuclear and other radioactive materials completed by an effective physical protection of these materials and facilities involved and supported by sufficient low enforcement. A state system of accounting for and control of nuclear materials in Slovakia is based on the IAEA INFCIRC/153 requirements. A fact that the IAEA inspectors never have recognized any unaccounted nuclear material could be the best proof of its quality. Physical protection system in both Slovak NPPs is based on principles applied in development of advanced physical protection systems used in western NPPs. Technological systems and nuclear materials are categorized into three categories - first one is most sensitive. Barriers of each category zone are equipped with sufficient detection systems and are monitored by TV system. The system is operated by NPPs operators. Entrances are guarded by private security guards. Response forces are created by the police. A legal support provides the Act No. 130/1998 on peaceful use of nuclear energy and regulations on accounting and control of nuclear materials, on physical protection of nuclear facilities and nuclear materials and on transports of nuclear materials and radioactive wastes. The Criminal Code of the Slovak Republic has been amended and an illegal possession of nuclear and radioactive materials is treated as a crime. Response

The influence of salt aerosol on alpha radiation detection by WIPP continuous air monitors

Energy Technology Data Exchange (ETDEWEB)

Bartlett, W.T.; Walker, B.A. [Environmental Evaluation Group, Albuquerque, NM (United States)

1997-08-01

Waste Isolation Pilot Plant (WIPP) alpha continuous air monitor (CAM) performance was evaluated to determine if CAMs could detect accidental releases of transuranic radioactivity from the underground repository. Anomalous alpha spectra and poor background subtraction were observed and attributed to salt deposits on the CAM sampling filters. Microscopic examination of salt laden sampling filters revealed that aerosol particles were forming dendritic structures on the surface of the sampling filters. Alpha CAM detection efficiency decreased exponentially as salt deposits increased on the sampling filters, suggesting that sampling-filter salt was performing like a fibrous filter rather than a membrane filter. Aerosol particles appeared to penetrate the sampling-filter salt deposits and alpha particle energy was reduced. These findings indicate that alpha CAMs may not be able to detect acute releases of radioactivity, and consequently CAMs are not used as part of the WIPP dynamic confinement system. 12 refs., 12 figs., 1 tab.

Radioactivity measurements in Egyptian Phosphate Mines and Their Significance As a Source of Hazardous Radioactive Waste

International Nuclear Information System (INIS)

Hussein, A.Z.; Hussein, M.I.; Abdel Hady, M.L.

1999-01-01

Phosphate mines that may contain radioactive traces in the composition of their ores represent source of hazardous radioactive waste in the environment. Radioactivity measurements have been conducted in nine underground phosphate mines in the Egyptian Eastern Desert in order to estimate the occupational radiation exposure of mine workers in those mining sites. Measurements were carried out of airborne radon and its short- lived decay products (progeny) and thoron progeny, as well as radiation from mines walls, ceilings and floors. Conventional, well established techniques, methods and instrumentation were used to make these measurements. Comparison of experimental data and theoretical predictions showed partial agreement between these two sets of data. This result is partly attributed to the complex layout of these mines, which causes undesirable ventilation conditions, such as recirculation airflow patterns, which could not be adequately identified or quantified. The radiation data obtained were used to estimate the maximum Annual Dose (MAD), and other important occupational radiation exposure variables. These calculations indicate that in eight out of the nine mines surveyed, the MAD exceeded (by a factor of up to 7) the maximum recommended level by ICRP 60. Numbers of suggestions are made in order to reduce the MAD in the affected mines. This study could help in the estimation of the environmental impact of these mine operations on the environment

Direct measurement of alpha_QED(mZ)at the FCC-ee

CERN Document Server

Janot, Patrick

2016-02-08

When the measurements from the FCC-ee become available, an improved determination of the standard-model "input" parameters will be needed to fully exploit the new precision data towards either constraining or fitting the parameters of beyond-the-standard-model theories. Among these input parameters is the electromagnetic coupling constant estimated at the Z mass scale, alpha_QED(mZ). The measurement of the muon forward- backward asymmetry at the FCC-ee, just below and just above the Z pole, can be used to make a direct determination of alpha_QED(mZ) with an accuracy deemed adequate for an optimal use of the FCC-ee precision data.

Processing of combustible radioactive waste using incineration techniques

International Nuclear Information System (INIS)

Maestas, E.

1981-01-01

Among the OECD Nuclear Energy Agency Member countries numerous incineration concepts are being studied as potential methods for conditioning alpha-bearing and other types of combustible radioactive waste. The common objective of these different processes is volume reduction and the transformation of the waste to a more acceptable waste form. Because the combustion processes reduce the mass and volume of waste to a form which is generally more inert than the feed material, the resulting waste can be more uniformly compatible with safe handling, packaging, storage and/or disposal techniques. The number of different types of combustion process designed and operating specifically for alpha-bearing wastes is somewhat small compared with those for non-alpha radioactive wastes; however, research and development is under way in a number of countries to develop and improve alpha incinerators. This paper provides an overview of most alpha-incineration concepts in operation or under development in OECD/NEA Member countries. The special features of each concept are briefly discussed. A table containing characteristic data of incinerators is presented so that a comparison of the major programmes can be made. The table includes the incinerator name and location, process type, capacity throughput, operational status and application. (author)

Radioactive Liquid Waste Treatment Facility Discharges in 2011

Energy Technology Data Exchange (ETDEWEB)

Del Signore, John C. [Los Alamos National Laboratory

2012-05-16

This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one of these pathways was used; all treated water (3,352,890 liters) was fed to the effluent evaporator. The quality of treated water was established by collecting a weekly grab sample of water being fed to the effluent evaporator. Forty weekly samples were collected; each was analyzed for gross alpha, gross beta, and tritium. Weekly samples were also composited at the end of each month. These flow-weighted composite samples were then analyzed for 37 radioisotopes: nine alpha-emitting isotopes, 27 beta emitters, and tritium. These monthly analyses were used to estimate the radioactive content of treated water fed to the effluent evaporator. Table 1 summarizes this information. The concentrations and quantities of radioactivity in Table 1 are for treated water fed to the evaporator. Amounts of radioactivity discharged to the environment through the evaporator stack were likely smaller since only entrained materials would exit via the evaporator stack.

Questionnaire survey report on measurement of radioactivity in working environment of radioisotopes facility

International Nuclear Information System (INIS)

Kawano, Takao; Nomura, Kiyoshi

2008-01-01

To look over the current measurement of radioactivity concentration in working environment of many radioisotopes facilities, a questionnaire survey was carried out under the auspices of the Planning Committee of the Japan Society of Radiation Safety Management. 64 responses were obtained in 128 radiation facilities, which the questionnaires were sent to. The main results were obtained by aggregate analysis of the answers for questionnaires as the followings. Major nuclides subject to measurement were 3 H, 14 C, 32 P and 125 I Sampling of radioisotopes in air was mainly performed using collectors like dust samplers and HC-collectors. Liquid scintillation counters and gamma counters were used to measure β and γ radioactivity contained in airborne particles or gas samples. Contamination by radioactivity was not detected in 55% facilities surveyed, but in 40% facilities at the same level as or at lower levels than a hundredth part of the regulated concentration limit of each nuclide. Almost all facilities is found to consider that the measurement of radioactivity concentration in working environments is not always necessary. (author)

Manche centre. Environment surveillance. Measurement results

International Nuclear Information System (INIS)

1998-11-01

This booklet reports on the environmental radioactivity measurements performed around the Manche plant (France) during the third quarter of 1998 in rainwater, surface and underground waters, air and grass. Measurements concern the alpha and beta activity, tritium, 137 Cs, 241 Am, 7 Be and 40 K. Other pollutant (metals) measurements on rainwater, rivers surface water and sediments are given. (J.S.)

Radioactivity distribution measurement of various natural material surfaces with imaging plate

International Nuclear Information System (INIS)

Mori, C.; Suzuki, T.; Koido, S.; Uritani, A.; Yanagida, K.; Wu, Y.; Nishizawa, K.

1996-01-01

Distribution images of natural radioactivity in natural materials such as vegetables were obtained by using Imaging Platc. In ssuch cases, it is necessary to reduce background radiation intensity by one order or more. Graded shielding is very important. Espacially, the innermost surface of a shielding box sshould be covered with acrylic rein plate. We obtained natural radioactivity distribution images of vegetable, sea food, mea etc. Most β-rays emitted from 40 K print the radioactivity distribution image. Comparison between γ-ray intensity of KCL solution measured with HPGe detector and that of natural material specimen gave the radioactivity around 0.06- 0.04Bq/g depending on the kind and the part of specimens. (author). 6 refs., 5 figs., 1 tab

Quantitative autoradiography of alpha particle emission in geo-materials using the Beaver™ system

International Nuclear Information System (INIS)

Sardini, Paul; Angileri, Axel; Descostes, Michael; Duval, Samuel; Oger, Tugdual; Patrier, Patricia; Rividi, Nicolas; Siitari-Kauppi, Marja; Toubon, Hervé; Donnard, Jérôme

2016-01-01

In rocks or artificial geo-materials, radioactive isotopes emitting alpha particles are dispersed according to the mineralogy. At hand specimen scale, the achievement of quantitative chemical mapping of these isotopes takes on a specific importance. Knowledge of the distribution of the uranium and thorium series radionuclides is of prime interest to several disciplines, from the geochemistry of uranium deposits, to the dispersion of uranium mill tailings in the biosphere. The disequilibrium of these disintegration chains is also commonly used for dating. However, some prime importance isotopes, such as 226 Ra, are complicated to localize in geo-materials. Because of its high specific activity, 226 Ra is found in very low concentrations (~ppq), preventing its accurate localization in rock forming minerals. This paper formulates a quantitative answer to the following question: at hand specimen scale, how can alpha emitters in geo-materials be mapped quantitatively? In this study, we tested a new digital autoradiographic method (called the Beaver™) based on a Micro Patterned Gaseous Detector (MPGD) in order to quantitatively map alpha emission at the centimeter scale rock section. Firstly, for two thin sections containing U-bearing minerals at secular equilibrium, we compared the experimental and theoretical alpha count rates, measured by the Beaver™ and calculated from the uranium content, respectively. We found that they are very similar. Secondly, for a set of eight homemade standards made up of a mixture of inactive sand and low-radioactivity mud, we compared the count rates obtained by the Beaver™ and by an alpha spectrometer. The results indicate (i) a linearity between both count rates, and (ii) that the count obtained by the Beaver™ can be estimated from the count obtained by the alpha spectrometry using a factor of 0.82.

Quantitative autoradiography of alpha particle emission in geo-materials using the Beaver™ system

Energy Technology Data Exchange (ETDEWEB)

Sardini, Paul; Angileri, Axel [IC2MP Equipe HydrASA, 6 Rue Michel Brunet, B35, TSA 51106 Poitiers Cedex 9 (France); Descostes, Michael [AREVA Mines, R& D Department, Paris (France); Duval, Samuel; Oger, Tugdual [AI4R SAS, Nantes (France); Patrier, Patricia [IC2MP Equipe HydrASA, 6 Rue Michel Brunet, B35, TSA 51106 Poitiers Cedex 9 (France); Rividi, Nicolas [Service Camparis, Université Pierre et Marie Curie, Paris (France); Siitari-Kauppi, Marja [Radiochemistry Laboratory, University of Helsinki, Helsinki (Finland); Toubon, Hervé [AREVA Mines, R& D Department, Paris (France); Donnard, Jérôme [AI4R SAS, Nantes (France)

2016-10-11

In rocks or artificial geo-materials, radioactive isotopes emitting alpha particles are dispersed according to the mineralogy. At hand specimen scale, the achievement of quantitative chemical mapping of these isotopes takes on a specific importance. Knowledge of the distribution of the uranium and thorium series radionuclides is of prime interest to several disciplines, from the geochemistry of uranium deposits, to the dispersion of uranium mill tailings in the biosphere. The disequilibrium of these disintegration chains is also commonly used for dating. However, some prime importance isotopes, such as {sup 226}Ra, are complicated to localize in geo-materials. Because of its high specific activity, {sup 226}Ra is found in very low concentrations (~ppq), preventing its accurate localization in rock forming minerals. This paper formulates a quantitative answer to the following question: at hand specimen scale, how can alpha emitters in geo-materials be mapped quantitatively? In this study, we tested a new digital autoradiographic method (called the Beaver™) based on a Micro Patterned Gaseous Detector (MPGD) in order to quantitatively map alpha emission at the centimeter scale rock section. Firstly, for two thin sections containing U-bearing minerals at secular equilibrium, we compared the experimental and theoretical alpha count rates, measured by the Beaver™ and calculated from the uranium content, respectively. We found that they are very similar. Secondly, for a set of eight homemade standards made up of a mixture of inactive sand and low-radioactivity mud, we compared the count rates obtained by the Beaver™ and by an alpha spectrometer. The results indicate (i) a linearity between both count rates, and (ii) that the count obtained by the Beaver™ can be estimated from the count obtained by the alpha spectrometry using a factor of 0.82.

Survey of radioactive contamination of foodstuffs

Energy Technology Data Exchange (ETDEWEB)

Lee, W. R.; Lee, C. W.; Choi, G. S.; Cho, Y. H.; Kang, M. J.; Cheong, K. H.; Kim, H. R.; Kwak, J. Y

2005-11-15

The purpose of this study is to survey and assess radioactive contamination of foodstuffs in order to reduce the probability of intake of contaminated foodstuffs. Based on survey and assessment, final goal is to improve the public health by radiation protection. Sampled foodstuffs items are collected from the markets : one group are imported foodstuffs and the other group are domestic foodstuffs producted around nuclear facilities. After pretreatments such as drying, ashing, and homogenization, all samples were analyzed by gamma spectrometer system. The {sup 137}Cs radionuclide was only measured among the regulation radionuclides ({sup 137}Cs, {sup 134}Cs, {sup 131}I) of food code. All radionuclides of the domestic foodstuffs collected around nuclear facilities were below Minimum Detectable Activity (MDA). But the activity concentrations of Inonotus obliquus (Chaga mushooms) from Russia ranged up to 171.27 (average value : 36.65) Bq/kg-fresh. In the case of blueberry jam, the radioactivity of {sup 137}Cs is higher than expected value. Other samples are below MDA except some spices. Based on the previous and present results, it should be strengthen to survey for Inontus obliquus (Chaga mushooms), of which the radioactivity shows the range from MDA up to 800.01 Bq/kg-fresh. It should assess the public radiation exposure via food chain because it has the excess provability of the maximum permitted level of food code, which is regulation of KFDA. The development method based on international standard would be used at radioactive analysis as well as education of practical workers and it could be applied as the basis data for amending the analysis method of food code. Our country only surveys gamma emitting radionuclides till now but international organization or foreign countries for example EU survey alpha and beta emitting radionuclides as well as gamma emitting radionuclides. So our country should also research necessity of survey for alpha and beta emitting

Radioactivity measurements for some ophthalmic glasses

International Nuclear Information System (INIS)

Badawy, W.M.; Ali, E.M.; Gomaa, M.A.; Hussein, A

2007-01-01

The main aim of the present work is to implant the latest ICRP/IAEA recommendations related to exemption and clearness to the Ophthalmic Glass. As consumer product, glass lenses may contain trace quantities of uranium, thorium and potassium. Glass lenses under investigation were monitored for the detection of gamma rays and beta particles using radiation measuring devices. Using high purity germanium detector radioactivity concentration was estimated in Bq/kg. Activity concentration of 226 Ra, Th-232 and K-40 were determined using the energy gamma lines of 2l4 Pb (352 keV), 212 Pb (238 keV) and 1460 keV gamma line for 40 K respectively .Experimental results showed that radioactivity concentration for radium -226 varies from 0.19 to 4.98 Bq/kg of radium-226, from to 0.18 to 2.83 Bq/kg for thorium -232 and from 0.8 to 1.13 Bq/kg for potassium. Implementing new ICRP recommendation of exemption and clearness indicated that several Ophthalmic Glass should not be in use

Self-absorption alpha particle factor in water: interest in the monitoring of specific military sites

International Nuclear Information System (INIS)

Cazoulat, A.; Lecompte, Y.; Bohand, S.; Gerasimo, P.

2007-01-01

Self-absorption alpha particle factor validation in water: Interest in the monitoring of specific military sites. The population internal intake prevention by radionuclides present in water needs to monitor the radioactive Level of this water. The French public health legislation introduces four radiological parameters for monitoring water, such as the gross alpha radioactivity. Regarding the alpha particle characteristics, a self-absorption factor has to be established beforehand, not to underestimate the real alpha radioactivity in water samples. The aim of this paper is to describe the procedure used by the laboratory of the French army radioprotection service to determine this f factor, which depends on the water residue mass m after evaporation. The relation is f = 0.0253 m + 1.2813. This formula can be employed for such waters used in this experiment and for masses between 0 and 100 mg. The uncertainty associated is about 11% (k = 2). Some water monitoring examples are given. It is specially the case of depleted uranium shells experiment centres, localized in Gramat and Bourges. (authors)

An Alpha Proton X-Ray Spectrometer for Mars-96 and Mars Pathfinder

Science.gov (United States)

Rieder, R.; Wanke, H.; Economou, T.

1996-09-01

Mars Pathfinder and the Russian Mars-96 will carry an Alpha Proton X-Ray Spectrometer (APXS) for the determination of the chemical composition of Martian rocks and soil. The instrument will measure the concentration of all major and many minor elements, including C,N and O, at levels above typically 1%. The method employed consist of bombarding a sample of 50 mm diameter with alpha particles from a radioactive source (50 mCi of Cm-244) and measuring: (i) backscattered alpha particles (alpha mode) (ii) protons from (a,p) reactions with some light elements (proton mode) (iii) characteristic X-rays emitted from the sample (X-ray mode). The APXS has a long standing space heritage, going back to Surveyor V,VI and VII (1967/68) and the Soviet Phobos (1988) missions. The present design is the result of an endeavour to reduce mass and power consumption to 600g/ 300mW. It consist of a sensor head containing the alpha sources, a telescope of a silicon detectors for the detection of the alpha particles and protons and a separate X-ray detector with its preamplifier, and an electronics box (80x70x60 mm) containing a microcontroller based multichannel spectrometer. The paper will describe the APXS flight hardware and present results obtained with the flight instrument that will show the instrument capabili- ties and the expected results to be obtained during surface operations on Mars.

Lyman-alpha detector designed for rocket measurements of the direct solar radiation at 121.5 nm

International Nuclear Information System (INIS)

Guineva, V.; Tashev, V.; Witt, G.; Gumbel, J.; Khaplanov, M.

2007-01-01

Rocket measurements of the direct Lyman-alpha radiation penetrating in the atmosphere were planned during the HotPay I rocket experiment, June 2006, Project ASLAF (Attenuation of the Solar Lyman-Alpha Flux), Andoya Rocket Range (ARR), Norway. The basic goal of ASLAF project was the study of the processes in the summer mesosphere and thermosphere (up to 110 km), at high latitudes using the Lyman-alpha measurements. The resonance transition 2 P- 2 S of the atomic hydrogen (Lyman-alpha emission) is the strongest and most conspicuous feature in the solar EUV spectrum. Due to the favourable circumstance, that the Lyman-alpha wavelength (121.5 nm) coincides with a minimum of the O 2 absorption spectrum, the direct Lyman-alpha radiation penetrates well in the mesosphere. The Lyman-alpha radiation is the basic agent of the NO molecules ionization, thus generating the ionospheric D-layer, and of the water vapour photolysis, being one of the main H 2 O loss processes. The Lyman-alpha radiation transfer depends on the resonance scattering from the hydrogen atoms in the atmosphere and on the O 2 absorption. Since the Lyman-alpha extinction in the atmosphere is a measure for the column density of the oxygen molecules, the atmospheric temperature profile can be calculated thereof. The detector of solar Lyman-alpha radiation was manufactured in the Stara Zagora Department of the Solar-Terrestrial Influences Laboratory (STIL). Its basic part is an ionization chamber, filled in with NO. A 60 V power supply is applied to the chamber. The produced photoelectric current from the sensor is fed to a 2-channels amplifier, providing an analogue signal. The characteristics of the Lyman-alpha detector were studied. It passed successfully all tests and the results showed that the instrument could be used in rocket experiments to measure the Lyman-alpha flux. From the measurements of the detector, the Lyman-alpha vertical profile can be obtained. The forthcoming scientific data analysis will

Measurement of the Strong Coupling Constant $\\alpha_s$ and the Vector and Axial-Vector Spectral Functions in Hadronic Tau Decays

CERN Document Server

Ackerstaff, K; Allison, J; Altekamp, N; Anderson, K J; Anderson, S; Arcelli, S; Asai, S; Ashby, S F; Axen, D A; Azuelos, Georges; Ball, A H; Barberio, E; Barlow, R J; Bartoldus, R; Batley, J Richard; Baumann, S; Bechtluft, J; Behnke, T; Bell, K W; Bella, G; Bentvelsen, Stanislaus Cornelius Maria; Bethke, Siegfried; Betts, S; Biebel, O; Biguzzi, A; Bird, S D; Blobel, Volker; Bloodworth, Ian J; Bobinski, M; Bock, P; Böhme, J; Boutemeur, M; Braibant, S; Bright-Thomas, P G; Brown, R M; Burckhart, Helfried J; Burgard, C; Bürgin, R; Capiluppi, P; Carnegie, R K; Carter, A A; Carter, J R; Chang, C Y; Charlton, D G; Chrisman, D; Ciocca, C; Clarke, P E L; Clay, E; Cohen, I; Conboy, J E; Cooke, O C; Couyoumtzelis, C; Coxe, R L; Cuffiani, M; Dado, S; Dallavalle, G M; Davis, R; De Jong, S; del Pozo, L A; de Roeck, A; Desch, Klaus; Dienes, B; Dixit, M S; Doucet, M; Dubbert, J; Duchovni, E; Duckeck, G; Duerdoth, I P; Eatough, D; Estabrooks, P G; Etzion, E; Evans, H G; Fabbri, Franco Luigi; Fanfani, A; Fanti, M; Faust, A A; Fiedler, F; Fierro, M; Fischer, H M; Fleck, I; Folman, R; Fürtjes, A; Futyan, D I; Gagnon, P; Gary, J W; Gascon, J; Gascon-Shotkin, S M; Geich-Gimbel, C; Geralis, T; Giacomelli, G; Giacomelli, P; Gibson, V; Gibson, W R; Gingrich, D M; Glenzinski, D A; Goldberg, J; Gorn, W; Grandi, C; Gross, E; Grunhaus, Jacob; Gruwé, M; Hanson, G G; Hansroul, M; Hapke, M; Hargrove, C K; Hartmann, C; Hauschild, M; Hawkes, C M; Hawkings, R; Hemingway, Richard J; Herndon, M; Herten, G; Heuer, R D; Hildreth, M D; Hill, J C; Hillier, S J; Hobson, P R; Höcker, Andreas; Homer, R James; Honma, A K; Horváth, D; Hossain, K R; Howard, R; Hüntemeyer, P; Igo-Kemenes, P; Imrie, D C; Ishii, K; Jacob, F R; Jawahery, A; Jeremie, H; Jimack, Martin Paul; Joly, A; Jones, C R; Jovanovic, P; Junk, T R; Karlen, D A; Kartvelishvili, V G; Kawagoe, K; Kawamoto, T; Kayal, P I; Keeler, Richard K; Kellogg, R G; Kennedy, B W; Klier, A; Kluth, S; Kobayashi, T; Kobel, M; Koetke, D S; Kokott, T P; Kolrep, M; Komamiya, S; Kowalewski, R V; Kress, T; Krieger, P; Von Krogh, J; Kyberd, P; Lafferty, G D; Lanske, D; Lauber, J; Lautenschlager, S R; Lawson, I; Layter, J G; Lazic, D; Lee, A M; Lefebvre, E; Lellouch, Daniel; Letts, J; Levinson, L; Liebisch, R; List, B; Littlewood, C; Lloyd, A W; Lloyd, S L; Loebinger, F K; Long, G D; Losty, Michael J; Ludwig, J; Liu, D; Macchiolo, A; MacPherson, A L; Mannelli, M; Marcellini, S; Markopoulos, C; Martin, A J; Martin, J P; Martínez, G; Mashimo, T; Mättig, P; McDonald, W J; McKenna, J A; McKigney, E A; McMahon, T J; McPherson, R A; Meijers, F; Menke, S; Merritt, F S; Mes, H; Meyer, J; Michelini, Aldo; Mihara, S; Mikenberg, G; Miller, D J; Mir, R; Mohr, W; Montanari, A; Mori, T; Nagai, K; Nakamura, I; Neal, H A; Nellen, B; Nisius, R; O'Neale, S W; Oakham, F G; Odorici, F; Ögren, H O; Oreglia, M J; Orito, S; Pálinkás, J; Pásztor, G; Pater, J R; Patrick, G N; Patt, J; Pérez-Ochoa, R; Petzold, S; Pfeifenschneider, P; Pilcher, J E; Pinfold, James L; Plane, D E; Poffenberger, P R; Poli, B; Polok, J; Przybycien, M B; Rembser, C; Rick, Hartmut; Robertson, S; Robins, S A; Rodning, N L; Roney, J M; Roscoe, K; Rossi, A M; Rozen, Y; Runge, K; Runólfsson, O; Rust, D R; Sachs, K; Saeki, T; Sahr, O; Sang, W M; Sarkisyan-Grinbaum, E; Sbarra, C; Schaile, A D; Schaile, O; Scharf, F; Scharff-Hansen, P; Schieck, J; Schmitt, B; Schmitt, S; Schöning, A; Schörner-Sadenius, T; Schröder, M; Schumacher, M; Schwick, C; Scott, W G; Seuster, R; Shears, T G; Shen, B C; Shepherd-Themistocleous, C H; Sherwood, P; Siroli, G P; Sittler, A; Skuja, A; Smith, A M; Snow, G A; Sobie, Randall J; Söldner-Rembold, S; Sproston, M; Stahl, A; Stephens, K; Steuerer, J; Stoll, K; Strom, D; Ströhmer, R; Tafirout, R; Talbot, S D; Tanaka, S; Taras, P; Tarem, S; Teuscher, R; Thiergen, M; Thomson, M A; Von Törne, E; Torrence, E; Towers, S; Trigger, I; Trócsányi, Z L; Tsur, E; Turcot, A S; Turner-Watson, M F; Van Kooten, R; Vannerem, P; Verzocchi, M; Vikas, P; Voss, H; Wäckerle, F; Wagner, A; Ward, C P; Ward, D R; Watkins, P M; Watson, A T; Watson, N K; Wells, P S; Wermes, N; White, J S; Wilson, G W; Wilson, J A; Wyatt, T R; Yamashita, S; Yekutieli, G; Zacek, V; Zer-Zion, D

1999-01-01

The spectral functions of the vector current and the axial-vector current have been measured in hadronic tau decays using the OPAL detector at LEP. Within the framework of the Operator Product Expansion a simultaneous determination of the strong coupling constant alpha_s, the non-perturbative operators of dimension 6 and 8 and of the gluon condensate has been performed. Different perturbative descriptions have been compared to the data. The Contour Improved Fixed Order Perturbation Theory gives alpha_s(mtau**2) = 0.348 +- 0.009 +- 0.019 at the tau-mass scale and alpha_s(mz**2) = 0.1219 +- 0.0010 +- 0.0017 at the Z-mass scale. The values obtained for alpha_s(mz**2) using Fixed Order Perturbation Theory or Renormalon Chain Resummation are 2.3% and 4.1% smaller, respectively. The running of the strong coupling between s_0 ~1.3 GeV**2 and s_0 = mtau**2 has been tested from direct fits to the integrated differential hadronic decay rate R_tau. A test of the saturation of QCD sum rules at the tau-mass scale has been...

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)

Neutronic measurements of radioactive waste; Les mesures neutroniques des dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

Perot, B

1997-12-31

This document presents the general matters involved in the radioactive waste management and the different non destructive assays of radioactivity. The neutronic measurements used in the characterization of waste drums containing emitters are described with more details, especially the active neutronic interrogation assays with prompt or delayed neutron detection: physical principle, signal processing and evaluation of the detection limit. (author).

Radioactivity monitoring of the P.P

Energy Technology Data Exchange (ETDEWEB)

Joksic, J.; Todorovic, D.; Radenkovic, M. [VINCA Institute of Nuclear Sciences, Radiation and Enviro nmental Protecti on Lab., Belgrade (Serbia and Montenegro)

2006-07-01

The radioactivity monitoring in the 'Nikola Tesla' thermo-electric power plant environment comprised the analysis of soil, waters, flying ash, slag and plants. Soil, plant and water samples were taken in the environment of the 'Tent A', 'Tent B', 'Kolubara' and 'Morava' power plants during the two years period 2003-2004 and analyzed b y standard radiometric methods. Naturally occurring radionuclides 226 Ra, 232 Th, 40 K, 235 U, 238 U, 210 Pb are determined by gamma spectrometry using H.P. Ge detector, relative efficiency of 23% and energy resolution of 1.8 keV (1332.5 keV). Ceied reference materials: soil matrix with 55 Na, 57 Co, 60 Co, 89 Y, 133 Ba and 137 Cs (MIX-OMHSZ, National Office of Measures) and grass with 134 Cs, 137 Cs, 40 K and 90 Sr (IAEA-373) were used for calibration. The gross alpha and gross beta activity measurements are carried out using low-level background alpha-beta proportional gas counter. Radiochemical analyzes of soil samples have shown the naturally occurring radionuclides: 226 Ra 35-60 Bq/kg, 232 Th 35-49 Bq/kg, 40 K 513-711 Bq/kg, 210 Pb 14-69 Bq/kg, 238 U 25-80 Bq/kg and 235 U 1.1-4.5 Bq/kg. The 137 Cs was found in concentration 10-57 Bq/kg. Radiochemical analyzes of plant samples have shown the naturally occurring radionuclides: 226 Ra 0.7-6.1 Bq/kg, 232 Th 1-4.8 Bq/kg, 40 K 392-1132 Bq/kg, 210 Pb 5.6-97 Bq/kg, 238 U 2.3-7.4 Bq/kg and 235 U 0.2-0.7 Bq/kg. The 137 Cs was found in concentration 0.13-2.8 Bq/kg. The water samples were within the range of recommended values for drinking waters in Serbia and Montenegro. Total alpha activity was below the lowest limit of detection and total beta activities were up to 0.35 Bq/l. The results of measured radionuclides in soil, plant and water samples do not show any significant radioactive environmental pollution. (authors)

Radioactivity monitoring of the P.P

International Nuclear Information System (INIS)

Joksic, J.; Todorovic, D.; Radenkovic, M.

2006-01-01

The radioactivity monitoring in the 'Nikola Tesla' thermo-electric power plant environment comprised the analysis of soil, waters, flying ash, slag and plants. Soil, plant and water samples were taken in the environment of the 'Tent A', 'Tent B', 'Kolubara' and 'Morava' power plants during the two years period 2003-2004 and analyzed b y standard radiometric methods. Naturally occurring radionuclides 226 Ra, 232 Th, 40 K, 235 U, 238 U, 210 Pb are determined by gamma spectrometry using H.P. Ge detector, relative efficiency of 23% and energy resolution of 1.8 keV (1332.5 keV). Certified reference materials: soil matrix with 55 Na, 57 Co, 60 Co, 89 Y, 133 Ba and 137 Cs (MIX-OMHSZ, National Office of Measures) and grass with 134 Cs, 137 Cs, 40 K and 90 Sr (IAEA-373) were used for calibration. The gross alpha and gross beta activity measurements are carried out using low-level background alpha-beta proportional gas counter. Radiochemical analyzes of soil samples have shown the naturally occurring radionuclides: 226 Ra 35-60 Bq/kg, 232 Th 35-49 Bq/kg, 40 K 513-711 Bq/kg, 210 Pb 14-69 Bq/kg, 238 U 25-80 Bq/kg and 235 U 1.1-4.5 Bq/kg. The 137 Cs was found in concentration 10-57 Bq/kg. Radiochemical analyzes of plant samples have shown the naturally occurring radionuclides: 226 Ra 0.7-6.1 Bq/kg, 232 Th 1-4.8 Bq/kg, 40 K 392-1132 Bq/kg, 210 Pb 5.6-97 Bq/kg, 238 U 2.3-7.4 Bq/kg and 235 U 0.2-0.7 Bq/kg. The 137 Cs was found in concentration 0.13-2.8 Bq/kg. The water samples were within the range of recommended values for drinking waters in Serbia and Montenegro. Total alpha activity was below the lowest limit of detection and total beta activities were up to 0.35 Bq/l. The results of measured radionuclides in soil, plant and water samples do not show any significant radioactive environmental pollution. (authors)

Determination of low levels of α-radioactivity in aqueous wastes

International Nuclear Information System (INIS)

Kapustin, V.K.; Leonov, V.V.; Sokolikov, A.V.

1978-01-01

The method has been proposed for determining total alpha radioactivity of water samples based on the use of solid scintillator with preliminary concentrating alpha emitters on lanthanum hydrooxide. The relationship between sensitivity of the method, concentration of co-precipitator, and salt content of the solution has been studied. Optimum conditions of the analysis have been chosen: Csub(La)=10-70 mg/l, thickness of the K-9 scintillator 20 mg/cm 2 , thickness of an additional K-9 layer 20 mg/cm 3 . Minimum specific alpha-activity being measured is less than 1x10 -12 Ci/l when FEU-49B (photomultiplier) is used, the sample volume is 1 l, total thickness of the K-9 light-composition layer is 40 mg/cm 2 , total time of analysis is 1.5 hour, recorded effectiveness value being 0.80, and relative error of measurement 20%. The possibility is shown of an effective use of the method for controlling the total specific activity of alpha amitters of unknown compositions in sewage of radiochemical plants within the range of 10 -6 -10 -12 Ci/l. The method can be used for determining radon in natural water by short-lived products of its decomposition

Natural radioactivity measurements at the proposed nuclear power plant site

International Nuclear Information System (INIS)

Cojuangco, J.G.; Salomon, A.Ph.

1976-01-01

Natural radioactivity measurement in the Philippines aims to establish baseline radioactivity levels in the environment of items essential to man. In this article, results of the environmental surveillance conducted in Bagac, Bataan from 1973 to 1974 are presented. Analyses were made on air parti-culates, sea and fresh water, grass, and soil samples for gross beta-gamma activities. Results obtained showed activity levels below the maximum permissible concentration recommended by the International Committee on Radiation Protection (ICRP)

Lessons learnt from participation in international inter-comparison exercise for environmental radioactivity measurement

International Nuclear Information System (INIS)

Jha, S.K.; Pulhani, Vandana; Sartandel, Sangeeta

2016-06-01

Environmental Radioactivity Measurement Section of Health Physics Division is regularly carrying out surveillance of the radioactivity concentration in the environment. The laboratory participates in the inter-comparison exercises conducted by various international agencies for quality assurance and quality control of analytical estimations. This report summarizes the results of the analysis of radioactivity in environmental matrices of the inter-comparison exercises. The participation in inter-comparison exercises has demonstrated competence in radionuclide identification and estimations, equivalence with the results of other participating laboratories, validated adopted analytical methods, introduced traceability to measurement etc. at national and international level. (author)

A study of etching model of alpha-recoil tracks in biotite

International Nuclear Information System (INIS)

Dong Jinquan; Yuan Wanming; Wang Shicheng; Fan Qicheng

2005-01-01

Like fission-track dating, alpha-recoil track (ART) dating is based on the accumulation of nuclear particles that the released from natural radioactivity and produce etchable tracks in solids. ARTs are formed during the alpha-decay of uranium and thorium as well as of their daughter nuclei. When emitting an alpha-particle, the heavy remaining nucleus recoils 30-40 nm, leaving behind a trail of radiation damage. Through etching the ART tracks become visible with the aid of an interference phase-contrast microscope. Under the presupposition that all tracks are preserved since the formation of a sample their total number is a measure of the sample's age. The research for etching model is to accurately determine ART volume density, i.e., the number of ARTs per unit volume. The volume density of many dots in many layers may be determined on a sample using this etching model, and as decreasing the error and increasing the accuracy. (authors)

Experimental and numerical study of the degradation of radioactive measurements in the filters of airborne radioactive surveillance systems

International Nuclear Information System (INIS)

Geryes, Tony

2009-01-01

The measurement of radioactivity in the filters of airborne radioactive surveillance systems is a major metrology difficulty due to the fact that the absorption of a radiation in the filter media and the mass of aerosols accumulated distort the nuclear counting response. This thesis focuses on the determination of correction factors for the radioactivity loss in the survey filters. In a first step, radioactive filters representing the atmospheric samples have been prepared using the nuclear test bench ICARE. The experimental study on reference filters provided a database to determine correction factors for various filtration conditions. The second part proposes a new numerical method developed to determine the correction factors. It consists of coupling GeoDict for particles filtration simulations and MCNPX simulations for a transport in matter. The good agreement obtained by comparing the numerical and experimental correction factors has permitted to validate the numerical model

Validation of radioactivity measurements under the Safe Drinking Water Act

International Nuclear Information System (INIS)

Goldin, Abraham S.

1978-01-01

Radioactivity measurements are made under the Safe Drinking Water Act to obtain information on the potential radiological hazard of water and to institute regulatory action when water quality does not meet requirements. Measurements must be both precise and accurate if these goals are to be met. Regulations issued under the act require that analyses be performed by approved (certified) laboratories, which must carry out quality assurance programs. This paper briefly describes the certification requirements and discusses the components of an effective quality assurance program. The Environmental Protection Agency has established procedures for the certification of laboratories making radioactivity measurements of drinking water. These procedures recommend minimum laboratory qualifications for personnel, facilities, equipment, and procedures; proficiency testing by analysis of samples provided by the Agency; and operation of a quality assurance program. A major function of a quality assurance program is to provide the Laboratory Director an ongoing flow of information on laboratory analytical performance. A properly designed and conducted program provides this information in a timely manner, indicates areas where discrepancies exist, and often suggests ways of correcting the discrepancies. Pertinent aspects of radioactivity measurements for drinking water are discussed, including how analyses of blanks, blind duplicates, and reference samples contribute needed information, and evaluations by control charts and statistical analyses. Examples of the usefulness of quality control in correcting both procedural and background problems are given. (author)

Radioactivity measurement of barium carbonate [14C] by liquid scintillation counting

International Nuclear Information System (INIS)

Kobayashi, Katsutoshi; Hoizumi, Kiyoshi

1985-03-01

Two methods of sample preparation for the measurement of specific activity of BaCO 3 [ 14 C] by external standard method in liquid scintillation counting were studied. BaCO 3 [ 14 C] was decomposed by perchloric acid solution and generated CO 2 [ 14 C] was absorbed by ethylene glycol monomethyl ether solution of monoethanolamine as the method 1 or aqueous sodium hydroxide as the method 2. In order to prepare the sample solution of adequate radioactivity concentration, these carbonate solutions by the methods 1 and 2 were diluted with the suitable organic solvent and distilled water respectively. One tenth millilitre of these sample solutions was added into 10 ml of PPO-toluene scintillator containing 0.1 ml of monoethanolamine in a counting vial and homogeneously dissolved with ethyl alcohol. The results of the radioactivity measurement of BaCO 3 [ 14 C] based on the different method agreed within 5 % and the counting rate was found to be stable for as long as 7 deays or more. Both methods of preparation are suitable for the routine measurement because of their simplicity and feasibility. In the case of method 2, the liquid radioactive waste is almost inorganic solution and recovery in the form of BaCO 3 [ 14 C] is easily performed, so that this method is very advantageous from the view point of the radioactive waste treatement. (author)

Evaluation of air pollution due to natural radioactive elements

International Nuclear Information System (INIS)

Perez, B. A.; Lopez, M. E.

2014-08-01

The presence of radioactive materials in the crustal and as consequence present in the surface, originate the natural radioactive contamination in the different solid, liquid and gaseous materials; particularly in the air that we breathe. Among these radioactive materials that contribute to the environmental pollution are the presences of uranium, radio, thorium and their respective disintegration chains, as the gas radon (Rn-222) that spreads in the air; whose presence increases in areas where the seismic activity is notorious or other natural events take place, case of the Lima (Peru) City. In this work we show the measurements realized during two consecutive years in the roof of a building of three floors in the Lima City, with the purpose of establishing the fluctuations of this gassy pollutant in the surrounding air. The measurements were made using nitrocellulose detectors (Lr-115 type 2) applying the nuclear prints technique. The obtained results allowing to have an indicator of the Rn-222 presence in the air during different seasons of the year and also the presence of other possible radioactive pollutants. The use of this technique allows obtaining and studying the prints that generate the alpha particles that are emitted during the Rn-222 disintegration or by means of their descendants or predecessors; also allowing to discriminate between the short-range tracers or lineal type prints and other very different prints obtained during some of the measurements. The results analyzed according to proposed models are presented in this work. (author)

Alpha resonant scattering for astrophysical reaction studies

Energy Technology Data Exchange (ETDEWEB)

Yamaguchi, H.; Kahl, D.; Nakao, T. [Center for Nuclear Study (CNS), University of Tokyo, RIKEN campus, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Wakabayashi, Y.; Kubano, S. [The Institute of Physical and Chemical Research (RIKEN), 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Hashimoto, T. [Research Center for Nuclear Physics (RCNP), Osaka University, 10-1 Mihogaoka, Ibaraki, Osaka 567-0047 (Japan); Hayakawa, S. [Istituto Nazionale Fisica Nucleare - Laboratori Nazionali del Sud (INFN-LNS), Via S. Sofia 62, 95125 Catania (Italy); Kawabata, T. [Department of Physics, Kyoto University, Kita-Shirakawa, Kyoto 606-8502 (Japan); Iwasa, N. [Department of Physics, Tohoku University, Aoba, Sendai, Miyagi 980-8578 (Japan); Teranishi, T. [Department of Physics, Kyushu University, 6-10-1 Hakozaki, Fukuoka 812-8581 (Japan); Kwon, Y. K. [Institute for Basic Science, 70, Yuseong-daero 1689-gil, Yuseong-gu, Daejeon 305-811 (Korea, Republic of); Binh, D. N. [30 MeV Cyclotron Center, Tran Hung Dao Hospital, Hoan Kiem District, Hanoi (Viet Nam); Khiem, L. H.; Duy, N. G. [Institute of Physics, Vietnam Academy of Science and Technology, 18 Hong Quoc Viet, Nghia do, Hanoi (Viet Nam)

2014-05-02

Several alpha-induced astrophysical reactions have been studied at CRIB (CNS Radioactive Ion Beam separator), which is a low-energy RI beam separator at Center for Nuclear Study (CNS) of the University of Tokyo. One of the methods to study them is the α resonant scattering using the thick-target method in inverse kinematics. Among the recent studies at CRIB, the measurement of {sup 7}Be+α resonant scattering is discussed. Based on the result of the experiment, we evaluated the contributions of high-lying resonances for the {sup 7}Be(α,γ) reaction, and proposed a new cluster band in {sup 11}C.

Environmental natural radioactivity concentrations of Tekirdag

International Nuclear Information System (INIS)

Yarar, Y.; Kam, E.

2004-01-01

Full text: In this study, the environmental natural radioactivity concentrations of Tekirdag, a city in the region of Marmara in Turkey, have been measured. Gamma spectrometric analysis of the soil samples collected from 40 points of Tekirdag was performed by using an HPGe detector and the radionuclide concentrations of the decay products of 238 U and 232 Th series, 40K and 137 Cs were determined. Gross alpha and gross beta activities of the water samples taken from municipal supplies, springs, wells and fountains were performed by using the Berthold, LB770-PC 10, a gas-flow proportional counter. Gamma exposure dose rates were measured by using an Eberline Smart Portable scintillation detector and the annual effective dose equivalents caused by exposure gamma dose rates were calculated

Radioautographic studies of the radioactive ashes obtained from the No. 5 Fukuryu Maru

Energy Technology Data Exchange (ETDEWEB)

Kikuchi, T; Akagi, H; Goto, H; Wakisaka, G

1954-01-01

Radioautographic studies have been made of the radioactive ashes obtained from the ship by use of x-ray film, radioautographic stripping plates, and plates of ..cap alpha..-emitters. The radioactivity was found not proportional to the size of the particle, and the distribution of radioactivity in each particle was not uniform.

Transport and extraction of radioactive ions stopped in superfluid helium

NARCIS (Netherlands)

Huang, WX; Dendooven, P; Gloos, K; Takahashi, N; Arutyunov, K; Pekola, JP; Aysto, J

A new approach to convert a high energy beam to a low energy one, which is essential for the next generation radioactive ion beam facilities, has been proposed and tested at Jyvaskyla, Finland. An open Ra-223 alpha-decay-recoil source has been used to produce radioactive ions in superfluid helium.

Determination of radium activity in some natural mineral waters using radioactive chemical extraction method and alpha spectrometry

International Nuclear Information System (INIS)

Nguyen Thi Oanh; Duong Van Thang; Duong Duc Thang; Nguyen Van Khanh; Doan Thuy Hau; Pham Bao Ngoc

2017-01-01

The 226 Ra activity concentration in several of mineral water samples of Northern Vietnam was measured by using alpha spectrometry. Ra adsorption techniques on manganese oxide were applied to produce thin alpha samples. The efficiency of sample preparation process was determined by conducting similar procedures for IAEA reference materials. The 226 Ra content in mineral water ranged from (11.33 ± 1.00) mBq/l to (38.00 ± 4.50) mBq/l. The measured maximum values do not exceed the permissible limit radiation dose for all samples (100 mBq/l - USEPA ). This study may be useful for assessing impacts of radiation dose from mineral water on human health. (author)

Assessment of natural radioactivity and heavy metals in water and soil around seismically active area

International Nuclear Information System (INIS)

Oktay Baykara; Mahmut Dogru; Firat University, Elazig

2010-01-01

The natural radioactivity concentration and some heavy metals in various water and soil samples collected from seismically active area have been determined. Gross-alpha and beta concentrations of different 33 water samples and some heavy metal (Fe, Pb, Cu, K, Mn, Cr and Zn) concentration in 72 soil samples collected from two major fault systems (North and East Anatolian Active Fault Systems) in Turkey have been studied. This survey regarding gross-alpha and beta radioactivity and some heavy metals concentrations was carried out by means of Krieger method using a gross-alpha and beta-counting system and atomic absorption spectrometry (AAS), respectively. Also, gross annual effective dose from the average gross-alpha activity in waters were calculated. (author)

(n,{alpha}) cross section measurement of gaseous sample using gridded ionization chamber. Cross section determination

Energy Technology Data Exchange (ETDEWEB)

Sanami, Toshiya; Baba, Mamoru; Saito, Keiichiro; Ibara, Yasutaka; Hirakawa, Naohiro [Tohoku Univ., Sendai (Japan). Faculty of Engineering

1997-03-01