Sampling procedure, receipt and conservation of water samples to determine environmental radioactivity

International Nuclear Information System (INIS)

Herranz, M.; Navarro, E.; Payeras, J.

2009-01-01

The present document informs about essential goals, processes and contents that the subgroups Sampling and Samples Preparation and Conservation believe they should be part of the procedure to obtain a correct sampling, receipt, conservation and preparation of samples of continental, marine and waste water before qualifying its radioactive content.

A device for fresh water sampling before radioactive measurements

International Nuclear Information System (INIS)

Maubert, Henri; Picat, Philippe.

1982-06-01

On account of the many field operations carried out by the laboratory, a water sampling device has been developed. This portable autonomous device performs in situ water filtration and concentration on ion exchange resins and activated carbon columns. The device is described and the trapping performance for 8 radionuclides is given. A comparison is made with the so-called evaporation method. The effects of the treatment of the filtrating elements on the radioactive results are studied. This sampling method is very sensitive [fr

Wipe sampling for characterization of noncompactable radioactive waste

International Nuclear Information System (INIS)

Barbieri, Aline E.O.; Ferreira, Robson J.; Vicente, Roberto

2009-01-01

Wipe sampling is a method of monitoring radioactive surface contamination on working area and on radioactive, non-compactable wastes, constituted of large pieces of replaced parts of equipment in nuclear and radioactive installations. In this method, sampling is executed by rubbing a disc of filter paper on the contaminated surface in such a way as to collect entirely or partially the deposited material. The target radioisotopes are subsequently measured directly on the wipe or extracted by appropriate radio analytical methods and then qualitatively and quantitatively determined. The collection factor, or the efficiency with which the material is removed from the surface and deposited on the smear, is the main source of error in quantitative measurements. The determination of the collection efficiency is the object of this communication. (author)

Non-destructive nuclear forensics of radioactive samples

Energy Technology Data Exchange (ETDEWEB)

Rogge, R.B. [Canadian Neutron Beam Centre, Chalk River, ON (Canada); Alexander, Q.; Bentoumi, G.; Dimayuga, F. [Atomic Energy of Canada Limited, Chalk River, ON (Canada); Flacau, R. [Canadian Neutron Beam Centre, Chalk River, ON (Canada); Li, G.; Li, L.; Sur, B. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

It is a matter of public safety and security to be able to examine suspicious packages of unknown origin. If the package is radioactive and sealed (i.e., the radioactive materials contained in the package, including their chemical and physical forms, are unknown), there is a significant risk on how to handle the package and eventually safely dispose of its contents. Within the context of nuclear security, nuclear forensics helps address the key issue of identifying the nature and origin of radioactive and nuclear material in order to improve physical protection measures and prevent future theft or diversion of these materials. Nuclear forensics utilizes analytical techniques, destructive and non-destructive, developed for applications related to nuclear fuel cycles. This paper demonstrates the non-destructive examination techniques that can be used to inspect encapsulated radioactive samples. Results of γ spectroscopy, X-ray spectroscopy, neutron imaging, neutron diffraction, and delayed neutron analysis as applied to an examination of sealed capsules containing unknown radioactive materials are presented. The paper also highlights the value of these techniques to the overall nuclear forensic investigation to determine the origin of these unknown radioactive materials. (author)

The measurement of radioactive microspheres in biological samples

International Nuclear Information System (INIS)

Mernagh, J.R.; Spiers, E.W.; Adiseshiah, M.

1976-01-01

Measurements of the distribution of radioactive microspheres are used in investigations of regional coronary blood flow, but the size and shape of the heart varies for different test animals, and the organ is frequently divided into smaller pieces for studies of regional perfusion. Errors are introduced by variations in the distribution of the radioactive source and the amount of Compton scatter in different samples. A technique has therefore been developed to allow the counting of these tissue samples in their original form, and correction factors have been derived to inter-relate the various counting geometries thus encountered. Dogs were injected with microspheres labelled with 141 Ce, 51 Cr or 85 Sr. The tissue samples did not require remodelling to fit a standard container, and allowance was made for the inhomogeneous distribution in the blood samples. The activities in the centrifuged blood samples were correlated with those from the tissue samples by a calibration procedure involving comparisons of the counts from samples of microspheres embedded in sachets of gelatine, and similar samples mixed with blood and then centrifuged. The calibration data have indicated that 51 Cr behaves anomalously, and its use as a label for microspheres may introduce unwarranted errors. A plane cylindrical 10 x 20 cm NaI detector was used, and a 'worst case' correction of 20% was found to be necessary for geometry effects. The accuracy of this method of correlating different geometries was tested by remodelling the same tissue sample into different sizes and comparing the results, and the validity of the technique was supported by agreement of the final results with previously published data. (U.K.)

Environmental sampling program for a solar evaporation pond for liquid radioactive wastes

International Nuclear Information System (INIS)

Romero, R.; Gunderson, T.C.; Talley, A.D.

1980-04-01

Los Alamos Scientific Laboratory (LASL) is evaluating solar evaporation as a method for disposal of liquid radioactive wastes. This report describes a sampling program designed to monitor possible escape of radioactivity to the environment from a solar evaporation pond prototype constructed at LASL. Background radioactivity levels at the pond site were determined from soil and vegetation analyses before construction. When the pond is operative, the sampling program will qualitatively and quantitatively detect the transport of radioactivity to the soil, air, and vegetation in the vicinity. Possible correlation of meteorological data with sampling results is being investigated and measures to control export of radioactivity by biological vectors are being assessed

Ash contents of foodstuff samples in environmental radioactivity analysis

International Nuclear Information System (INIS)

Oikawa, Shinji; Ohta, Hiroshi; Hayano, Kazuhiko; Nonaka, Nobuhiro

2004-01-01

Statistical data of the ash content in various environmental samples obtained from an environmental radioactivity survey project commissioned by the Japanese government of Science and Technology Agency (at present Ministry of Education, Culture, Sports, Sciences and Technology) during the past 10 years are expressed for establishing a standard of ash content in environmental samples based on radioactivity analysis. The ash content for some kinds of environmental samples such as dietary food, milk, Japanese radish, spinach, fish, green tea and potato was reviewed in the light of statistical and stochastic viewpoints. For all of the samples reviewed in this paper, the coefficient of variation varied from 4.7% for milk to 36.3% for cabbage. Dietary food and milk samples were reviewed more than 1900 and 1400 samples, respectively. Especially, ash content of dietary food depended mainly on the dietary culture reflected on the period. However it showed an almost invariant distribution within 18.7% of coefficient of variation during the past 10 years. Pretreatment of environmental samples especially ashing processes are important from the viewpoint on environmental radioactivity analysis, which is one of the especial fields in analytical chemistry. Statistical reviewed data obtained in this paper may be useful for sample preparation. (author)

Natural radioactivity measurements and dosimetric evaluations in soil samples with a high content of NORM

Science.gov (United States)

Caridi, F.; Marguccio, S.; Durante, G.; Trozzo, R.; Fullone, F.; Belvedere, A.; D'Agostino, M.; Belmusto, G.

2017-01-01

In this article natural radioactivity measurements and dosimetric evaluations in soil samples contaminated by Naturally Occurring Radioactive Materials (NORM) are made, in order to assess any possible radiological hazard for the population and for workers professionally exposed to ionizing radiations. Investigated samples came from the district of Crotone, Calabria region, South of Italy. The natural radioactivity investigation was performed by high-resolution gamma-ray spectrometry. From the measured gamma spectra, activity concentrations were determined for 226Ra , 234-mPa , 224Ra , 228Ac and 40K and compared with their clearance levels for NORM. The total effective dose was calculated for each sample as due to the committed effective dose for inhalation and to the effective dose from external irradiation. The sum of the total effective doses estimated for all investigated samples was compared to the action levels provided by the Italian legislation (D.Lgs.230/95 and subsequent modifications) for the population members (0.3mSv/y) and for professionally exposed workers (1mSv/y). It was found to be less than the limit of no radiological significance (10μSv/y).

Recommendations for sampling for prevention of hazards in civil defense. On analytics of chemical, biological and radioactive contaminations. Brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling

International Nuclear Information System (INIS)

Bachmann, Udo; Biederbick, Walter; Derakshani, Nahid

2010-01-01

The recommendation for sampling for prevention of hazards in civil defense is describing the analytics of chemical, biological and radioactive contaminations and includes detail information on the sampling, protocol preparation and documentation procedures. The volume includes a separate brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling.

Studies on radioactivities of dust samples in the air at high altitudes

International Nuclear Information System (INIS)

Kohara, Eri; Muronoi, Naohiro

2015-01-01

The radioactivity concentrations of airborne dust samples were studied. The samples had been collected at high altitude by the Japan Air Self-Defense Force from April 2013 to March 2014. The obtained data were used for gross beta radioactivity analysis and gamma nuclide analysis. It is shown that cesium 137 was mainly detected at the 10 km and 3 km altitude of central area of Japan in several samples. Gaseous radioiodine was not detected in all the samples. Radioactive xenon was detected but the concentration did not show significant difference to the background level. (author)

Results of Self-Absorption Study on the Versapor 3000 Filters for Radioactive Particulate Air Sampling

International Nuclear Information System (INIS)

Barnett, J.M.; Cullinan, Valerie I.; Barnett, Debra S.; Trang-Le, Truc LT; Bliss, Mary; Greenwood, Lawrence R.; Ballinger, Marcel Y.

2009-01-01

Since the mid-1980s, Pacific Northwest National Laboratory (PNNL) has used a value of 0.85 as the correction factor for self absorption of activity for particulate radioactive air samples collected from building exhaust for environmental monitoring. This value accounts for activity that cannot be detected by direct counting of alpha and beta particles. Emissions can be degraded or blocked by filter fibers for particles buried in the filter material or by inactive dust particles collected with the radioactive particles. These filters are used for monitoring air emissions from PNNL stacks for radioactive particles. This paper describes an effort to re-evaluate self-absorption effects in particulate radioactive air sample filters (Versapor(reg s ign) 3000, 47 mm diameter) used at PNNL. There were two methods used to characterize the samples. Sixty samples were selected from the archive for acid digestion to compare the radioactivity measured by direct gas-flow proportional counting of filters to the results obtained after acid digestion of the filter and counting again by gas-flow proportional detection. Thirty different sample filters were selected for visible light microscopy to evaluate filter loading and particulate characteristics. Mass-loading effects were also considered. Filter ratios were calculated by dividing the initial counts by the post-digestion counts with the expectation that post-digestion counts would be higher because digestion would expose radioactivity embedded in the filter in addition to that on top of the filter. Contrary to expectations, the post digestion readings were almost always lower than initial readings and averaged approximately half the initial readings for both alpha and beta activity. Before and after digestion readings appeared to be related to each other, but with a low coefficient of determination (R 2 ) value. The ratios had a wide range of values indicating that this method did not provide sufficient precision to quantify

Specific calibration problems for gammaspectrometric measurements of low-level radioactivity in environmental samples

Energy Technology Data Exchange (ETDEWEB)

Arnold, D [Physikalisch-Technische Bundesanstalt, Braunschweig (Germany); Wershofen, H [Physikalisch-Technische Bundesanstalt, Braunschweig (Germany)

1997-03-01

Gammaspectrometric measurements of low-level radioactivity in environmental samples are always done in a close source detector geometry. This geometry causes coincidence-summing effects for measurements of multi-photon emitting nuclides. The measurements of radioactivity in environmental samples are also influenced by the absorption of photons in the materials which have to be analysed. Both effects must be taken into account by correction factors with respect to an energy-specific calibration of the detector system for a given geometry and a given composition of the calibration source. The importance of these corrections is emphasized. It is the aim of the present paper to compare different experimental and theoretical methods for the determination of these correction factors published by various authors and to report about efforts to refine them. (orig.)

Shielded scanning electron microscope for radioactive samples

International Nuclear Information System (INIS)

Crouse, R.S.; Parsley, W.B.

1977-01-01

A small commercial SEM had been successfully shielded for examining radioactive materials transferred directly from a remote handling facility. Relatively minor mechanical modifications were required to achieve excellent operation. Two inches of steel provide adequate shielding for most samples encountered. However, samples reading 75 rad/hr γ have been examined by adding extra shielding in the form of tungsten sample holders and external lead shadow shields. Some degradation of secondary electron imaging was seen but was adequately compensated for by changing operating conditions

3D reconstruction of radioactive sample utilizing gamma tomography

Science.gov (United States)

Zoul, David; Zháňal, Pavel

2018-07-01

Unique three-dimensional (3D) tomography apparatus was developed and successfully tested at Research Centre Rez, which concentrates at investigation of the degradation of microstructural and mechanical properties of structural materials of nuclear reactors components after a long-term operating exposure. The apparatus allows a 3D view into the interior of low-dimension radioactive samples with a diameter up to several centimeters and a resolution in order of cubic millimeters. It is designed to detect domains with different levels of radioactivity such as cavities, cracks or regions with different chemical composition. The unique collimator design, the use of stepper motors for fine and accurate sample scanning, along with advanced 3D image reconstruction software developed at Research Centre Rez, enables a resolution approaching 1 mm3. Devices working on a similar principle have been used for decades, e.g., in nuclear medicine for the diagnosis of malignant tumors, and are increasingly being applied in the nuclear industry. However, for the first time similar equipment is used for non-destructive testing of low-dimension radioactive samples.

Results of Self-Absorption Study on the Versapor 3000 Filters for Radioactive Particulate Air Sampling

International Nuclear Information System (INIS)

Barnett, J.M.

2008-01-01

Since the mid-1980s the Pacific Northwest National Laboratory (PNNL) has used a value of 0.85 as a correction factor for the self absorption of activity of particulate radioactive air samples. More recently, an effort was made to evaluate the current particulate radioactive air sample filters (Versapor(reg s ign) 3000) used at PNNL for self absorption effects. There were two methods used in the study, (1) to compare the radioactivity concentration by direct gas-flow proportional counting of the filter to the results obtained after acid digestion of the filter and counting again by gas-flow proportional detection and (2) to evaluate sample filters by high resolution visual/infrared microscopy to determine the depth of material loading on or in the filter fiber material. Sixty samples were selected from the archive for acid digestion in the first method and about 30 samples were selected for high resolution visual/infrared microscopy. Mass loading effects were also considered. From the sample filter analysis, large error is associated with the average self absorption factor, however, when the data is compared directly one-to-one, statistically, there appears to be good correlation between the two analytical methods. The mass loading of filters evaluated was <0.2 mg cm-2 and was also compared against other published results. The microscopy analysis shows the sample material remains on the top of the filter paper and does not imbed into the filter media. Results of the microscopy evaluation lead to the conclusion that there is not a mechanism for significant self absorption. The overall conclusion is that self-absorption is not a significant factor in the analysis of filters used at PNNL for radioactive air stack sampling of radionuclide particulates and that an applied correction factor is conservative in determining overall sample activity. A new self absorption factor of 1.0 is recommended

A study for natural radioactivity levels in some soil samples using gamma spectrometry

International Nuclear Information System (INIS)

Mohamed, Yousif Hassab El Rasoul

1997-05-01

The purpose of this study was to investigate a few selected soil samples and to study their natural radioactivity using gamma spectrometry. The first sample was a rock phosphate from Nuba mountains region which is being considered as a low cost fertilizer. Another sample came from Miri lake area (Nuba mountains) which is known to have elevated natural radioactivity level. The other four samples came from different other regions in Sudan for comparison. The idea was to identify the radioactive nuclides present in these soil samples, to trace their sources and to determine the activity present in them. (Author)

Assessment of natural radioactivity and radiation hazard indices in different soil samples from Assiut governorate

International Nuclear Information System (INIS)

Issa, S.A.M.; Uosif, M.A.M.; Hefni, M.A.; El-Kamel, A.H; Nesreen, A.A.

2013-01-01

Natural radioactive materials under certain conditions can reach hazard radiological levels. So, it becomes necessary to study the natural radioactivity levels in soil to assess the dose for the population in order to know the health risks and to have a baseline for future changes in the environmental radioactivity due to human activities. Determine the radioactivity concentration of 226 Ra, 232 Th and 40 K in surface and 20 cm soil samples collected beside Assiut fertilizer plant, Assiut government in south Upper Egypt, to assess their contribution to the external dose exposure. The contents of natural radionuclides 226 Ra, 232 Th and 40 K were measured in investigated samples by using gamma spectrometry [NaI (Tl) 3”x 3”]. The total absorbed dose rate, annual effective dose rate, radium equivalent, excess lifetime cancer risk and the external hazard index, which resulted from the natural radionuclides in soil, were calculated

A software for radioactivity measurement of Ra, Th and K in environmental samples

International Nuclear Information System (INIS)

Miao Zhengqiang; Bao Min; Chang Yongfu

2004-01-01

Radio nuclides of soil, rock, construction material, and almost everything around us. There is growing concern about environmental radioactivity from both scientists and public from an institutional or a common point of view. The regulation and standard on evaluating radioactivity of environmental samples have been issued recently by the authorities. We have developed special purpose Gamma spectra analysis software named ErSpec. The software can effectively process and analyze Gamma spectra measured by a NaI(T1) spectrometry, and can give a relatively precise results of radioactivity of 226 Ra, 232 Th and 40 K in environmental samples. The main functions of ErSpec include, processing and analyzing Gamma spectra, displaying some useful information for users, generating report, managing user's priority, logging user's manipulation, etc. Because environmental samples usually have low radioactivity and have complex measurement conditions, relative method is employed in ErSpec, and Channel-by-Channel Least-Squared Estimation is adopted as spectra analyzing method. The arithmetic make use of information extracted from data of hundreds of channels, then give a rather good result. In ErSpec, by using external call of MatLAB Math Lib in Visual C++, accuracy and speed of calculation and robustness of software are improved distinctly. Object-Oriented Programming Method and ActiveX techniques are also employed in software designing and coding stage. (authors)

Self-attenuation of gamma rays during radioactivity concentration analysis of environmental samples

International Nuclear Information System (INIS)

Watson, D.; Dharmasiri, J.; Akber, R.

2001-01-01

Gamma spectroscopy using HPGe detector systems is a readily used technique for routine analysis of radioactivity in environmental samples. The systems are generally calibrated using standards of known radioactivity and composition. Radioactivity in environmental samples is generally distributed in the bulk of the material. When a sample of finite thickness is analysed through gamma spectroscopy, a proportion of the gamma rays emitted from the sample is either stopped or scattered from the sample material itself. These processes of self-absorption and self-attenuation depend upon the physical and elemental composition of the sample and the energy of the gamma radiation. Since environmental samples vary in composition, instrument calibration using a fixed matrix composition may not be valid for a diversity of samples. We selected and analysed five sample matrices to investigate the influence of self-absorption and self-attenuation in environmental samples. Our selection consisted of bentonite and kaolin representing clay, quartz representing silica, ash representing prepared biota, and analytical grade MnO 2 representing a co-precipitant used for extractive radioactivity from aqueous samples. Our findings show that within 5% of uncertainty the silica based standards can be used to cover the environmental samples of varying clay (silica content). The detection efficiency for ash and MnO 2 could be different particularly in the 30 - 100 keV energy range. The differences in sample behaviour can be explained on the basis of atomic number, mass number and density

Natural Radioactivity Pattern of Surabaya Water Environmental Samples

International Nuclear Information System (INIS)

Rosidi; Agus Taftazani

2007-01-01

The gross β radioactivity and natural radionuclide of Surabaya environmental samples pattern have been evaluated. The environmental samples were chosen randomly at 12 locations. The environment samples were water (fresh, estuary and coastal), sediment, eichhornia crassipes (Mart) Solms, Mangrove (Rhizophora stylosa), (Moolgarda delicatus) fish and (Johnius (Johnieops) borneensis) (Sharpnose hammer croaker) fish. The water sample was evaporated; the sediment sample was dried and ground; the biotic samples was burnt at the temperature 500 °C ; The gross β measurement using GM detector and the radionuclides has been identified by γ spectrometer. From the investigation results could be concluded that the natural radioactivity of environmental samples was very low. gross-β of water samples were lower than the threshold value of local government regulation of Surabaya no: 2 year 2004 (1 Bq/L). The distribution of gross-β activity of eichhornia crassipes (Mart) Solms was higher than the other biotic, water and sediment samples as well as the accumulation of radionuclides in the water organism was taken place. The result of identification using γ spectrometer has detected 7 of radionuclides, i.e 210 Pb, 212 Pb, 214 Pb, 208 Tl, 214 Bi, 228 Ac, and 40 K in all sample. The distribution factor of sediment F D was less than bioaccumulation factor of biotic F B and it indicates that there the radionuclide accumulation migration follows the pattern of water - sediment - biotic sample. (author)

Natural radioactivity in soil samples of Kocaeli basin, Turkey

International Nuclear Information System (INIS)

Karakelle, B.; Oeztuerk, N.; Erkol, A.Y.; Koese, A.; Varinlioglu, A.; Yilmaz, F.

2002-01-01

The city of Kocaeli is in the western part of Anatolia in Turkey and has a population of approximately 1.000.000. There is no information about radioactivity in the Kocaeli soils samples so far. For this reason, the concentrations of the natural radionuclides in soil samples from 27 different sampling stations in Kocaeli Basin and its surroundings have been determined. The results have been compared with other radioactivity measurements in different country's soils. The typical concentrations of 137 Cs, 238 U, 40 K, 226 Ra, 232 Th found in surface soil samples ranged from 2 ± 0.6 to 25 ± 6 Bq/kg, from 11 ± 4 to 49 ± 10 Bq/kg, from 161 ± 30 to 964 ± 127 Bq/kg, from 10 ± 4 to 58 ± 11 Bq/kg, and from 11 ± 3 to 65 ± 13 Bq/kg, respectively. (author)

Micro-PIXE evaluation of radioactive cesium transfer in contaminated soil samples

Science.gov (United States)

Fujishiro, F.; Ishii, K.; Matsuyama, S.; Arai, H.; Ishizaki, A.; Osada, N.; Sugai, H.; Kusano, K.; Nozawa, Y.; Yamauchi, S.; Karahashi, M.; Oshikawa, S.; Kikuchi, K.; Koshio, S.; Watanabe, K.; Suzuki, Y.

2014-01-01

Micro-PIXE analysis has been performed on two soil samples with high cesium activity concentrations. These soil samples were contaminated by fallout from the accident at Fukushima Daiichi Nuclear Power Plant. One exhibits a radioactive cesium transfer of ˜0.01, and the other shows a radioactive cesium transfer of less than 0.001, even though both samples have high cesium activity concentrations exceeding 10,000 Bq/kg. X-ray spectra and elemental images of the soil samples revealed the presence of chlorine, which can react with cesium to produce an inorganic soluble compound, and phosphorus-containing cesium-capturable organic compounds.

Evaluation of the performance of the shields in the EPMAs used for radioactive samples

International Nuclear Information System (INIS)

Matsui, Hiroki; Suzuki, Miho; Obata, Hiroki; Kanazawa, Hiroyuki

2014-06-01

The Reactor Fuel Examination Facility (RFEF) in Japan Atomic Energy Agency (JAEA) has been used for Post Irradiation Examinations (PIEs) to verify the reliability and safety of the nuclear fuels irradiated in commercial reactors. EPMA (Electron Probe Micro Analyzer) has been utilized for the qualitative analysis of the fission product in the fuel pellet and the detailed observation of the oxide layers formed at the inner and outer surfaces of fuel cladding. Commercial EPMAs were remodeled so that the EPMAs can be applied for radioactive samples. Several shields were set in the EPMA to avoid the gamma-rays which radiate from a radioactive sample to the proportional counter in the EPMA. It is important to calculate this shielding performance adequately to maintain the precision of analysis. This report describes the results of re-evaluation of the performance of the shields in the EPMAs in the RFEF by using the Particle and Heavy Ion Transport Code System (PHITS) and the examination results of gamma-ray effect to the X-ray spectrum data by using a radioactive sample. (author)

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

Radioactive contamination of the environmental samples in Hanoi in 1989

International Nuclear Information System (INIS)

Dang Huy Uyen; Bui Van Loat; Dang Phuong Nam; Cao Anh Duc; Pham Quang Dien; Nguyen Hao Quang

1990-01-01

More than 30 environmental samples from soil, paddy, rice, fruits, vegetables and beans, sesame, tea, bananas, fishes at Hanoi markets in 1989 were analysed by gamma ray spectrometry with the low background system for studying natural and artificial radioactive elements. Among several samples from Hanoi in such kind as cultivated soils, tea, dried bamboo shoots, isotope Cs 137 that used be generated from nuclear explosives was found with contents (30 - 1000) x 10 -5 Bq/g; Cs 137 contents in Japanese rice (0.4 - 3) x 10 -5 Bq/g. Cs 137 is radioactive so Cs 137 contents in Vietnamese rice are 300 times higher than Cs 137 contents in Japanese rice but they are hundred times lower than international standard. Among vegetables, fruits, shrimps, fishes in Hanoi markets, artificial isotopes were not found and natural isotopes were few. Even radioactive daughter and granddaughter in uranium series in potatoes were not found. In some samples K 40 was also appeared, for example in cultivated soils (0.78 Bq/g), in dried bamboo shoots (0.73 Bq/g). (author). 2 refs., 3 figs

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

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

Natural radioactivity in different commercial ceramic samples used in Yemeni buildings

International Nuclear Information System (INIS)

Amin, Sahar A.; Naji, Mustafa

2013-01-01

In this work we calculated the radioactivity concentrations of the natural radioactive nuclides 238 U, 232 Th, 226 Ra and 40 K for 10 commercial samples collected from 10 different companies which are used in the construction of Yemeni buildings. Gamma ray spectroscopy was used to analyze the samples and the concentrations of radioisotopes were determined using a hyper-pure germanium (HPGe) detector in Bq/kg dry-weight. The average concentrations of 238 U, 232 Th, 226 Ra and 40 K were found to be 131.4, 83.55, 131.88 and 400.7 Bq/kg respectively. Different hazard indices were also determined. The results showed that the average radium equivalent activity (Ra eq ), the absorbed dose rate (D r ), the annual effective dose equivalent (AEDE), the external hazard index (H ex ) and representation level index (I γ ) were: 307.52 Bq/kg, 139.31 nGy/h, 1.40 mSv/yr, 0.83 and 2.15 respectively. The mean value of (Ra eq ) obtained in this study is in good agreement with that of the international value while the mean values of the other indices are found to be higher than the international reference values. The measured activity concentrations for these radionuclide were compared with the reported data obtained from similar materials used in other countries. - Highlights: ► Concentrations of the natural radioactive nuclides 238 U, 232 Th, 226 Ra and 40 K were measured. ► Ten samples collected from 10 different companies have been analyzed. ► Gamma ray spectroscopy is used to analyze the samples. ► Concentrations in Bq/kg were determined using a HPGe detector. ► Different hazard indices (Ra eq ), (D r ), (AEDE), (H ex ) and (I γ ) were also determined

Natural radioactivity of beach sand samples in Port Sudan, red sea state

International Nuclear Information System (INIS)

Kambal, Wala Haider Hussein

2015-01-01

Natural radioactivity is a source of continuous exposure to human beings. In Port Sudan city, the main port of Sudan, data on the levels of natural radioactivity in soil is required. The aim of this study was to measure the activity concentration as well as the absorbed dose and annual effective dose of the naturally occurring radionuclides 238 U, 232 Th, and 40 K in soil samples collected from different locations around Red Sea costa areas in Port Sudan city. Activity concentrations were measured using gamma ray spectrometry (Nal) detector. Results showed that the average activity concentration of 238 U, 232 Th and 40 K were found to be 21.86, 17.55, 85.50 Bqkg 1 , respectively, with an average absorbed dose of 10.42, 9.40 and 3.57 nGyh 1 , respectively. The average annual effective dose values were found to be 11.89, 11.54 and 4.37 μSvy 1 for 238 U, 232 Th and 40 K, respectively. The measured values were comparable with other global radioactivity measurements and found to be safe for public and environment.(Author)

Biological sampling for marine radioactivity monitoring

International Nuclear Information System (INIS)

Fowler, S.W.

1997-01-01

Strategies and methodologies for using marine organisms to monitor radioactivity in marine waters are presented. When the criteria for monitoring radioactivity is to determine routes of radionuclide transfer to man, the ''critical pathway'' approach is often applied. Alternatively, where information on ambient radionuclide levels and distributions is sought, the approach of selecting marine organisms as ''bioindicators'' of radioactivity is generally used. Whichever approach is applied, a great deal of knowledge is required about the physiology and ecology of the specific organism chosen. In addition, several criteria for qualifying as a bioindicator species are discussed; e.g., it must be a sedentary species which reflects the ambient radionuclide concentration at a given site, sufficiently long-lived to allow long-term temporal sampling, widely distributed to allow spatial comparisons, able to bioconcentrate the radionuclide to a relatively high degree, while showing a simple correlation between radionuclide content in its tissues with that in the surrounding waters. Useful hints on the appropriate species to use and the best way to collect and prepare organisms for radioanalysis are also given. It is concluded that benthic algae and bivalve molluscs generally offer the greatest potential for use as a ''bioindicator'' species in radionuclide biomonitoring programmes. Where knowledge on contribution to radiological dose is required, specific edible marine species should be the organisms of choice; however, both purposes can be served when the edible species chosen through critical pathway analysis is also an excellent bioaccumulator of the radionuclide of interest. (author)

Assessment of Annual Effective Dose for Natural Radioactivity of Gamma Emitters in Biscuit Samples in Iraq.

Science.gov (United States)

Abojassim, Ali Abid; Al-Alasadi, Lubna A; Shitake, Ahmed R; Al-Tememie, Faeq A; Husain, Afnan A

2015-09-01

Biscuits are an important type of food, widely consumed by babies in Iraq and other countries. This work uses gamma spectroscopy to measure the natural radioactivity due to long-lived gamma emitters in children's biscuits; it also estimates radiation hazard indices, that is, the radium equivalent activity, the representative of gamma level index, the internal hazard index, and the annual effective dose in children. Ten samples were collected from the Iraqi market from different countries of origin. The average specific activities for (226)Ra, (232)Th, and (40)K were 9.390, 3.1213, and 214.969 Bq/kg, respectively, but the average of the radium equivalent activity and the internal hazard index were 33.101 Bq/kg and 0.107, respectively. The total average annual effective dose from consumption by adults, children, and infants is estimated to be 0.655, 1.009, and 0.875 mSv, respectively. The values found for specific activity, radiation hazard indices, and annual effective dose in all samples in this study were lower than worldwide median values for all groups; therefore, these values are found to be safe.

Comparison of the image-derived radioactivity and blood-sample radioactivity for estimating the clinical indicators of the efficacy of boron neutron capture therapy (BNCT): 4-borono-2-18F-fluoro-phenylalanine (FBPA) PET study.

Science.gov (United States)

Isohashi, Kayako; Shimosegawa, Eku; Naka, Sadahiro; Kanai, Yasukazu; Horitsugi, Genki; Mochida, Ikuko; Matsunaga, Keiko; Watabe, Tadashi; Kato, Hiroki; Tatsumi, Mitsuaki; Hatazawa, Jun

2016-12-01

In boron neutron capture therapy (BNCT), positron emission tomography (PET) with 4-borono-2- 18 F-fluoro-phenylalanine (FBPA) is the only method to estimate an accumulation of 10 B to target tumor and surrounding normal tissue after administering 10 B carrier of L-paraboronophenylalanine and to search the indication of BNCT for individual patient. Absolute concentration of 10 B in tumor has been estimated by multiplying 10 B concentration in blood during BNCT by tumor to blood radioactivity (T/B) ratio derived from FBPA PET. However, the method to measure blood radioactivity either by blood sampling or image data has not been standardized. We compared image-derived blood radioactivity of FBPA with blood sampling data and studied appropriate timing and location for measuring image-derived blood counts. We obtained 7 repeated whole-body PET scans in five healthy subjects. Arterialized venous blood samples were obtained from the antecubital vein, heated in a heating blanket. Time-activity curves (TACs) of image-derived blood radioactivity were obtained using volumes of interest (VOIs) over ascending aorta, aortic arch, pulmonary artery, left and right ventricles, inferior vena cava, and abdominal aorta. Image-derived blood radioactivity was compared with those measured by blood sampling data in each location. Both the TACs of blood sampling radioactivity in each subject, and the TACs of image-derived blood radioactivity showed a peak within 5 min after the tracer injection, and promptly decreased soon thereafter. Linear relationship was found between blood sampling radioactivity and image-derived blood radioactivity in all the VOIs at any timing of data sampling (p radioactivity measured in the left and right ventricles 30 min after injection showed high correlation with blood radioactivity. Image-derived blood radioactivity was lower than blood sampling radioactivity data by 20 %. Reduction of blood radioactivity of FBPA in left ventricle after 30 min of FBPA

Considerations on measurements of radioactivity in biological samples

International Nuclear Information System (INIS)

Mascanzoni, D.

1986-01-01

Radioactivity in biological samples and particularly in foodstuffs can be measured with several procedures, depending on the type of sample and radiation. In case of a radioactive fallout like the one from Chernobyl 1986, contamination in biological samples varies with time, being high immediately after the accident and decreasing successively with time. During the first stage, accurate measurements of gamma-emission should be made with high-resolution instruments, like HPGe-detectors coupled to multichannel analyzers in order to be able to assess the fallout's composition and separate the different nuclides. Even portable GM-counters and NaI(Tl)-detectors can be used, but they provide very limited information and the resolution of NaI(Tl) is too poor to make them suitable for other than survey purposes. In this case, they can be used for monitoring the activity in a certain area, or scanning a large amount of samples. After some months, when the activity has decayed and only a few nuclides are still active, the most important parameter is not resolution any longer, but sensitivity, since the content of radionuclides has decreased. At this stage NaI(Tl)-detectors assume greater importance and their sensitivity can permit the detection of low activity levels in relatively short time. The laboratory procedures for sample handling and preparation is also very important: established routines concentrated upon reducing the risk of contamination and minimizing sources of error must be used

Radioactivity in waste water samples from COGEMA supplied by Greenpeace

International Nuclear Information System (INIS)

Reinen, H.A.J.M.; Kwakman, P.J.M.; Overwater, R.M.W.; Tax, R.B.; Nissan, L.A.

1999-01-01

The environmental organization Greenpeace sampled waste water from the reprocessing plant COGEMA in La Hague, France, in May 1999. On request of the Inspection Environmental Hygiene, The Dutch National Institute for Public Health and Environmental Protection (RIVM) determined the radioactivity of the waste water samples. 5 refs

Assessment of natural radioactivity levels in soil samples from some areas in Assiut, Egypt.

Science.gov (United States)

El-Gamal, Hany; Farid, M El-Azab; Abdel Mageed, A I; Hasabelnaby, M; Hassanien, Hassanien M

2013-12-01

The natural radioactivity of soil samples from Assiut city, Egypt, was studied. The activity concentrations of 28 samples were measured with a NaI(Tl) detector. The radioactivity concentrations of (226)Ra, (232)Th, and (40)K showed large variations, so the results were classified into two groups (A and B) to facilitate the interpretation of the results. Group A represents samples collected from different locations in Assiut and characterized by low activity concentrations with average values of 46.15 ± 9.69, 30.57 ± 4.90, and 553.14 ± 23.19 for (226)Ra, (232)Th, and (40)K, respectively. Group B represents samples mainly collected from the area around Assiut Thermal Power Plant and characterized by very high activity concentrations with average values of 3,803 ± 145, 1,782 ± 98, and 1,377 ± 78 for (226)Ra, (232)Th, and (40)K, respectively. In order to evaluate the radiological hazard of the natural radioactivity, the radium equivalent activity (Raeq), the absorbed dose rate (D), the annual effective dose rate (E), the external hazard index (H ex), and the annual gonadal dose equivalent (AGDE) have been calculated and compared with the internationally approved values. For group A, the calculated averages of these parameters are in good agreement with the international recommended values except for the absorbed dose rate and the AGDE values which are slightly higher than the international recommended values. However, for group B, all obtained averages of these parameters are much higher by several orders of magnitude than the international recommended values. The present work provides a background of radioactivity concentrations in the soil of Assiut.

Experiments with radioactive samples at the Advanced Photon Source

International Nuclear Information System (INIS)

Veluri, V. R.; Justus, A.; Glagola, B.; Rauchas, A.; Vacca, J.

2000-01-01

The Advanced Photon Source (APS) at Argonne National Laboratory is a national synchrotron-radiation light source research facility. The 7 GeV electron Storage Ring is currently delivering intense high brilliance x-ray beams to a total of 34 beamlines with over 120 experiment stations to members of the international scientific community to carry out forefront basic and applied research in several scientific disciplines. Researchers come to the APS either as members of Collaborative Access Teams (CATs) or as Independent Investigators (IIs). Collaborative Access Teams comprise large number of investigators from universities, industry, and research laboratories with common research objectives. These teams are responsible for the design, construction, finding, and operation of beamlines. They are the owners of their experimental enclosures (''hutches'') designed and built to meet their specific research needs. Fig. 1 gives a plan view of the location of the Collaborative Access Teams by Sector and Discipline. In the past two years, over 2000 individual experiments were conducted at the APS facility. Of these, about 60 experiments involved the use of radioactive samples, which is less than 3% of the total. However, there is an increase in demand for experiment stations to accommodate the use of radioactive samples in different physical forms embedded in various matrices with activity levels ranging from trace amounts of naturally occurring radionuclides to MBq (mCi) quantities including transuranics. This paper discusses in some detail the steps in the safety review process for experiments involving radioactive samples and how ALARA philosophy is invoked at each step and implemented

Study of radioactivity levels in detergent powders samples by gamma spectroscopy

Directory of Open Access Journals (Sweden)

Ali A. Abojassim

2014-10-01

Full Text Available This study focuses on the evaluation of the natural radioactivity levels in ten samples of the detergent powders that available in Iraqi markets. We have determined the specific activities of uranium, thorium and potassium using gamma spectroscopy and calculation of radiation hazard indices. The results of the activities of radionuclides (238U, 232Th, 40K for detergent powders samples, are found that the 238U specific activities were varied from (11.489 ± 2.089 Bq/kg to (36.062 ± 2.478 Bq/kg, while the 232th specific activities were varied from (1.411 ± 0.609 Bq/kg to (9.272 ± 1.642 Bq/kg and 40K were varied from (8.189 ± 2.339 Bq/kg to (91.888 ± 4.164 Bq/kg. These values are always lower than those of raw materials, what is explained by the conservation of radioactive material throughout the manufacturing process. The radium equivalent activity Raeq, the external hazard index Hex and the internal hazard index Hin dose due to natural radioactivity estimated below the regulatory standard recommended which are (370 Bq/kg, 1 and 1 according to OECD 1979 and ICRP 2000, allows us to show that Detergent powders samples products are not contaminated by radioactivity, are healthy and do not have harmful radiological impact on the consumer.

The High Altitude Sampling Program: Radioactivity in the stratosphere: Final report

International Nuclear Information System (INIS)

Leifer, R.; Juzdan, Z.R.

1986-12-01

Radioactivity data are presented from Project Airstream (aircraft) for the year 1983 and for Project Ashcan (balloon) for the years 1982 and 1984. Due to budgetary constraints both Projects Airstream and Ashcan have been terminated. This will be the final report containing radioactivity data collected during projects airstream and ashcan. Included are gross gamma, gamma spectral and radiochemical analyses of filter samples. Quality control samples submitted along with the air filter samples were analyzed and the results are presented. Low activity on many of the filters precludes the estimation of the stratospheric inventories of /sup 239,240/Pu and 90 Sr. Based on data with count errors 90 Sr and /sup 239,240/Pu concentration for November 1983 was 0.2 +- 0.1 and 0.009 +- 0.006 Bq/1000 scm, respectively

Estimation of radioactivity in some sand and soil samples

International Nuclear Information System (INIS)

Gupta, Monika; Chauhan, R.P.; Garg, Ajay; Kumar, Sushil; Sonkawade, R.G.

2010-01-01

Natural radioactivity is composed of the cosmogenic and primordial radionuclides. It is common in the rocks and soil that make up our planet, water and oceans, and in our building materials and homes. Natural radioactivity in sand and soils comes from 238 U and 232 Th series and natural 40 K. Radon is formed from the decay of radium which in turn is formed from uranium. The gaseous radioactive isotope of radon from natural sources has a significant share in the total quantum of natural sources exposure to the human bwings. Gamma radiation from 238 U, 232 Th and 40 K represents the main external source of irradiation of the human body. In the present study, the activity for 238 U, 232 Th and 40 K is found to vary from 45 ± 1.2 to 97 ± 4.9 Bq/kg, 63 ± 2.0 to 132 ± 3.2 Bq/kg and 492 ± 5.9 to 1110 ± 10.5 Bq/kg, respectively in the soil samples while the variations have been observed from 63 ± 3.8 to 65 ± 3.7 Bq/kg, 86 ±2.5 to 96 ± 2.6 Bq/kg and 751 ± 7.7 to 824 ± 8.2 Bq/kg, respectively in the sand samples. (author)

Modification of ion chromatograph for analyses of radioactive samples

International Nuclear Information System (INIS)

Curfman, L.L.; Johnson, S.J.

1979-01-01

In ion chromatographic analysis, the sample is injected through a sample loop onto an analytical column where separation occurs. The sample then passes through a suppressor column to remove or neutralize background ions. A flow-through conductivity cell is used as a detector. Depending upon column and eluent selection, ion chromatography can be used for anion or cation analyses. Ion chromatography has proven to be a versatile analytical tool for the analysis of anions in Hanford waste samples. These radioactive samples range from caustic high salt solutions to hydrochloric acid dissolutions of insoluble sludges. Instrument modifications which provide safe and convenient handling of these samples without lengthening analysis time or altering instrument performance are described

Study of natural radioactivity and 222Rn exhalation rate in soil samples for the assessment of average effective dose

International Nuclear Information System (INIS)

Bangotra, P.; Mehra, R.; Jakhu, R.; Sahoo, B.K

2016-01-01

The natural radioactivity in soil is usually determined from the 226 Ra (Radium), 232 Th (Thorium) and 40 K (potassium). 222 Rn and 220 Rn are produced in soil as a result of the presence of these radionuclides. As 226 Ra decay, the newly created 222 Rn radionuclide recoil from the parent grain and then exhale through the soil. Since 98.5% of radiological effects of 238 U series are produced by 226 Ra and its daughter products. The assessment of gamma radiation dose from natural sources is of particular importance as natural radiation is the largest contributor to the external dose of the world population. Authors are advised to maximize the information content utilizing the full space available. The main objective of the present study is to measure the level of natural radioactivity 226 Ra, 232 Th, 40 K and 222 Rn exhalation rate in the soil samples for health risk assessment

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)

A review of methods for sampling large airborne particles and associated radioactivity

International Nuclear Information System (INIS)

Garland, J.A.; Nicholson, K.W.

1990-01-01

Radioactive particles, tens of μm or more in diameter, are unlikely to be emitted directly from nuclear facilities with exhaust gas cleansing systems, but may arise in the case of an accident or where resuspension from contaminated surfaces is significant. Such particles may dominate deposition and, according to some workers, may contribute to inhalation doses. Quantitative sampling of large airborne particles is difficult because of their inertia and large sedimentation velocities. The literature describes conditions for unbiased sampling and the magnitude of sampling errors for idealised sampling inlets in steady winds. However, few air samplers for outdoor use have been assessed for adequacy of sampling. Many size selective sampling methods are found in the literature but few are suitable at the low concentrations that are often encountered in the environment. A number of approaches for unbiased sampling of large particles have been found in the literature. Some are identified as meriting further study, for application in the measurement of airborne radioactivity. (author)

Measurement of radioactivity in water samples

International Nuclear Information System (INIS)

Richards, L.

1990-01-01

Public concern about the levels of radioactivity release to the environment whether authorised discharges or resulting from nuclear accident, has increased in recent years. Consequently there is increasing pressure for reliable data on the distribution of radioactivity and the extent of its intrusion into food chains and water supplies. As a result a number of laboratories not experienced in radioactivity measurements have acquired nucleonic counting equipment. These notes explore the underlying basics and indicate sources of essential data and information which are required for a better understanding of radioactivity measurements. Particular attention is directed to the screening tests which are usually designated ''gross'' alpha and ''gross'' beta activity measurement. (author)

Sampling and characterization of radioactive liquid wastes; Muestreo y caracterizacion de desechos liquidos radiactivos

Energy Technology Data Exchange (ETDEWEB)

Zepeda R, C.; Monroy G, F.; Reyes A, T.; Lizcano, D. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Cruz C, A. C., E-mail: carla.zepeda@inin.gob.mx [SEP, Instituto Tecnologico de Orizaba, Av. Oriente 9, Col. Emiliano Zapata, 94320 Orizaba, Veracruz (Mexico)

2017-09-15

To define the management of radioactive liquid wastes stored in 200 L drums, its isotope and physicochemical characterization is essential. An adequate sampling, that is, representative and homogeneous, is fundamental to obtain reliable analytical results, therefore, in this work, the use of a sampling mechanism that allows collecting homogenous aliquots, in a safe way and minimizing the generation of secondary waste is proposed. With this mechanism, 56 drums of radioactive liquid wastes were sampled, which were characterized by gamma spectrometry, liquid scintillation, and determined the following physicochemical properties: ph, conductivity, viscosity, density and chemical composition by gas chromatography. 67.86% of the radioactive liquid wastes contains H-3 and of these, 47.36% can be released unconditionally, since it presents activities lower than 100 Bq/g. 94% of the wastes are acidic and 48% have viscosities <50 MPa s. (Author)

Standard guide for sampling radioactive tank waste

CERN Document Server

American Society for Testing and Materials. Philadelphia

2011-01-01

1.1 This guide addresses techniques used to obtain grab samples from tanks containing high-level radioactive waste created during the reprocessing of spent nuclear fuels. Guidance on selecting appropriate sampling devices for waste covered by the Resource Conservation and Recovery Act (RCRA) is also provided by the United States Environmental Protection Agency (EPA) (1). Vapor sampling of the head-space is not included in this guide because it does not significantly affect slurry retrieval, pipeline transport, plugging, or mixing. 1.2 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

A method for estimating radioactive cesium concentrations in cattle blood using urine samples.

Science.gov (United States)

Sato, Itaru; Yamagishi, Ryoma; Sasaki, Jun; Satoh, Hiroshi; Miura, Kiyoshi; Kikuchi, Kaoru; Otani, Kumiko; Okada, Keiji

2017-12-01

In the region contaminated by the Fukushima nuclear accident, radioactive contamination of live cattle should be checked before slaughter. In this study, we establish a precise method for estimating radioactive cesium concentrations in cattle blood using urine samples. Blood and urine samples were collected from a total of 71 cattle on two farms in the 'difficult-to-return zone'. Urine 137 Cs, specific gravity, electrical conductivity, pH, sodium, potassium, calcium, and creatinine were measured and various estimation methods for blood 137 Cs were tested. The average error rate of the estimation was 54.2% without correction. Correcting for urine creatinine, specific gravity, electrical conductivity, or potassium improved the precision of the estimation. Correcting for specific gravity using the following formula gave the most precise estimate (average error rate = 16.9%): [blood 137 Cs] = [urinary 137 Cs]/([specific gravity] - 1)/329. Urine samples are faster to measure than blood samples because urine can be obtained in larger quantities and has a higher 137 Cs concentration than blood. These advantages of urine and the estimation precision demonstrated in our study, indicate that estimation of blood 137 Cs using urine samples is a practical means of monitoring radioactive contamination in live cattle. © 2017 Japanese Society of Animal Science.

Artificial radioactivity in the environmental samples as IAEA reference materials

International Nuclear Information System (INIS)

Salagean, M.; Pantelica, A.

1998-01-01

. Uncontaminated by nuclear activities: IAEA-327, Podsolic soil collected in 1990 from the Moscow region and considered uncontaminated by radionuclides of the Chernobyl accident or by other nuclear activities. The results obtained by our laboratory are in good agreement with the certified IAEA data. Generally, the concentration of the artificial radionuclides in the investigated samples is higher than that expected from the influence of global fallout in the intercomparison materials distributed before Chernobyl accident. Concerning the nature of these investigated IAEA reference materials, very high values for the concentration levels of cesium radionuclides especially in IAEA-373 (grass) and IAEA-375 (soil) samples collected in the vicinity of Chernobyl Power Station after the nuclear accident in 1986 were found. High levels of radioactivities for the artificial radionuclides were also determined in the samples collected in the neighbourhood of the nuclear installations, especially in marine sediment (IAEA-135). It is of interest to point out the high concentration of cesium radionuclides in IAEA-300 sediment collected in 1992 in the Baltic Sea in comparison with the IAEA-306 sediment collected also in the Baltic Sea in 1986. It seems to be an increase of the Baltic Sea artificial radioactivity by accumulation in time. Marine sediment constitutes an important component of marine ecosystem since it represents the final sink for any releases of wastes into the sea. These certified radioactive materials are very useful to all laboratories engaged in the radioactive pollution investigations on environmental samples. (authors)

Assessment of Natural Radioactivity in TENORM Samples Using Different Techniques

International Nuclear Information System (INIS)

Salman, Kh.A.; Shahein, A.Y.

2009-01-01

In petroleum oil industries, technologically-enhanced, naturally occurring radioactive materials are produced. The presence of TENORM constitutes a significant radiological human health hazard. In the present work, liquid scintillation counting technique was used to determine both 222 Rn and 226 Ra concentrations in TENORM samples, by measuring 222 Rn concentrations in the sample at different intervals of time after preparation. The radiation doses from the TENORM samples were estimated using thermoluminenscent detector (TLD-4000). The estimated radiation doses were found to be proportional to both the measured radiation doses in site and natural activity concentration in the samples that measured with LSC

Off-Gas Analysis During the Vitrification of Hanford Radioactive Waste Samples

International Nuclear Information System (INIS)

Ha, B.C.; Ferrara, D.M.; Crawford, C.L.; Choi, A.S.; Bibler, N.E.

1998-01-01

This paper describes the off-gas analysis of samples collected during the radioactive vitrification experiments. Production and characterization of the Hanford waste-containing LAW and HAW glasses are presented in related reports from this conference

Detailed deposition density maps constructed by large-scale soil sampling for gamma-ray emitting radioactive nuclides from the Fukushima Dai-ichi Nuclear Power Plant accident.

Science.gov (United States)

Saito, Kimiaki; Tanihata, Isao; Fujiwara, Mamoru; Saito, Takashi; Shimoura, Susumu; Otsuka, Takaharu; Onda, Yuichi; Hoshi, Masaharu; Ikeuchi, Yoshihiro; Takahashi, Fumiaki; Kinouchi, Nobuyuki; Saegusa, Jun; Seki, Akiyuki; Takemiya, Hiroshi; Shibata, Tokushi

2015-01-01

Soil deposition density maps of gamma-ray emitting radioactive nuclides from the Fukushima Dai-ichi Nuclear Power Plant (NPP) accident were constructed on the basis of results from large-scale soil sampling. In total 10,915 soil samples were collected at 2168 locations. Gamma rays emitted from the samples were measured by Ge detectors and analyzed using a reliable unified method. The determined radioactivity was corrected to that of June 14, 2011 by considering the intrinsic decay constant of each nuclide. Finally the deposition maps were created for (134)Cs, (137)Cs, (131)I, (129m)Te and (110m)Ag. The radioactivity ratio of (134)Cs-(137)Cs was almost constant at 0.91 regardless of the locations of soil sampling. The radioactivity ratios of (131)I and (129m)Te-(137)Cs were relatively high in the regions south of the Fukushima NPP site. Effective doses for 50 y after the accident were evaluated for external and inhalation exposures due to the observed radioactive nuclides. The radiation doses from radioactive cesium were found to be much higher than those from the other radioactive nuclides. Copyright © 2014 The Authors. Published by Elsevier Ltd.. All rights reserved.

Natural radioactivity in soil samples of Yelagiri Hills, Tamil Nadu, India and the associated radiation hazards

International Nuclear Information System (INIS)

Ravisankar, R.; Chandrasekaran, A.; Vijayagopal, P.; Venkatraman, B.; Senthilkumar, G.; Eswaran, P.; Rajalakshmi, A.

2012-01-01

The natural radioactivity of soils at Yelagiri hills has been studied in this paper. The radioactivities of 25 samples have been measured with a NaI(Tl) detector. The radioactivity concentrations of 238 U, 232 Th and 40 K ranged from ≤2.17 to 53.23, 13.54 to 89.89 and from 625.09 to 2207.3 Bq kg −1 , respectively. The measured activity concentrations for these radionuclides were compared with world average activity of soil. The average activity concentration of 232 Th in the present study is 1.19 times higher than world median value while the activity of 238 U and 40 K is found to be lower. In order to evaluate the radiological hazard of the natural radioactivity, the radium equivalent activity Ra eq , the absorbed dose rate D R , the annual effective dose rate and the external hazard index (H ex ) have been calculated and compared with the internationally approved values. The study provides background radioactivity concentrations in Yelagiri hills. - Highlights: ► Soil radioactivity is used for base line data in future impact assessment. ► We report the results of radiation hazard parameters in soils of Yelagiri hills. ► The level of the natural radiation in the studied area does not exceed the norm.

Methodology of testing environmental samples from the area surrounding radioactive waste deposits

International Nuclear Information System (INIS)

Kropikova, S.; Pastuchova, D.

1979-01-01

Methods are described of environmental sample investigation in the area surrounding radioactive waste deposits, namely monitoring ground water, surface water, sediments, water flows and catchments, vegetation and soil. Methods of sample preparation, and methods of radionuclides determination in mixtures are also discussed, as are spot activity measurement methods. (author)

Storing and accessing radioactivity data in environmental samples: the resources of GEORAD

Energy Technology Data Exchange (ETDEWEB)

Silva, Tadeu A. de A.; Gonzalez, Sergio de A.; Reis, Rocio G. dos; Vasconcellos, Luiza M. de H. e; Lauria, Dejanira de C., E-mail: tedsilva@ird.gov.br, E-mail: gonzalez@ird.gov.br, E-mail: rocio@ird.gov.br, E-mail: luiza@ird.gov.br, E-mail: dejanira@ird.gov.br [Isntituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2013-07-01

A georeferenced information system of radioactivity in environmental samples, named GEORAD, was created with the goal of aggregating, storing and promoting the preservation of the data produced by Brazilian researches, and sharing with the research community a database on radioactivity in Brazil. The system provides information on concentrations of the natural series, cosmogenic and fall out radionuclides in samples of soil, water and food, among others, along with the geographical location of the samples. By this way, the location of the sample can be visualized on Brazilian map. A spreadsheet containing all the data and information about the sample can be also obtained. As a result, the database system can enable the available data to be exploited to the maximum potential for further research and allows new research on existing information. The system also provides reference information on where the data information were obtained, that enables data citation and linking data with publications to increase visibility and accessibility of data and the research itself. The GEORAD system has been continuously fed and updated, containing, currently, data from more than 2,000 samples. This paper presents the latest system updates and discusses its resources. (author)

Storing and accessing radioactivity data in environmental samples: the resources of GEORAD

International Nuclear Information System (INIS)

Silva, Tadeu A. de A.; Gonzalez, Sergio de A.; Reis, Rocio G. dos; Vasconcellos, Luiza M. de H. e; Lauria, Dejanira de C.

2013-01-01

A georeferenced information system of radioactivity in environmental samples, named GEORAD, was created with the goal of aggregating, storing and promoting the preservation of the data produced by Brazilian researches, and sharing with the research community a database on radioactivity in Brazil. The system provides information on concentrations of the natural series, cosmogenic and fall out radionuclides in samples of soil, water and food, among others, along with the geographical location of the samples. By this way, the location of the sample can be visualized on Brazilian map. A spreadsheet containing all the data and information about the sample can be also obtained. As a result, the database system can enable the available data to be exploited to the maximum potential for further research and allows new research on existing information. The system also provides reference information on where the data information were obtained, that enables data citation and linking data with publications to increase visibility and accessibility of data and the research itself. The GEORAD system has been continuously fed and updated, containing, currently, data from more than 2,000 samples. This paper presents the latest system updates and discusses its resources. (author)

Radiobiological effects in small mammals populations dwelled at radioactive waste disposal sites

International Nuclear Information System (INIS)

Sypin, V.D.; Osipov, A.N.; Pol'skij, O.G.; Elakov, A.L.; Egorov, V.G.; Synsynys, B.I.

2004-01-01

A major issue in evaluating the ecological acceptability of a disposal system for radioactive waste is in preventing the ecological risk that may arise from exposures in the distant future. There is uncertainty surrounding any estimate of these doses or risks due to lack of knowledge about future conditions. Therefore, the adequate estimation of the ecological acceptability of a radioactive waste disposal system required a complex radioecological and radiobiological approach. Environmental surveillance at the Sergievo-Posadsky radioactive waste disposal system of the Scientific and Industrial Association Radon in additional to a standard complex radiological testing includes also the study of the radiobiological effects in different biological objects sampled from the contaminated areas. In present report the results obtained on small rodents (mice and voles) sampled from the strict mode and fence zones of this disposal system are displayed and discussed. (author)

The inspirations with a radioactive intercomparison on a wine sample

International Nuclear Information System (INIS)

Su Qiong

1993-12-01

The methods used and results in a radioactive intercomparison on a wine sample are reported, which was organized by WHO-IRC in May, 1992. In order to analyse and compare the results obtained by all laboratories from WHO-IRC report (IRC NOTE No.41, 1993) are given. A re-measured new result about nuclide 40 K in the sample is also reported which coincides quite well with the result reported to IRC in a deviation of less than +-1%. And the problems concerning 'reference values' and standard sources etc. are also discussed

Radioactivity And Dose Assessment Of Rock And Soil Samples From Homa Mountain, Homa Bay County, Kenya

International Nuclear Information System (INIS)

Otwoma, D.; Patel, J.P.; Bartilol, S.; Mustapha, A.O.

2013-01-01

The in situ measured average outdoor absorbed dose rate in air was found to vary from 108.4 to 1596.4 n Gy h -1 at Homa Mountain area in southwestern Kenya. Rock and soil samples collected gave average values of the radioactivity concentrations of 40 K, 226 Ra and 232 Th of 915.6, 195.3 and 409.5 Bq kg -1 , respectively. The range of the annual effective dose for a person living in Homa Mountain area calculated varied from 28.6 to 1681.2, with a mean of 470.4 μSv. These results imply Homa Mountain have elevated levels of natural radioactivity thus the region is a high background radiation area

Radioactive particles revealed by electron microscopy. Chemical and physical properties of radioactive particles in aerosol samples emitted during the early stage of Fukushima Dai-ichi Nuclear Power Plant accident

International Nuclear Information System (INIS)

Adachi, Kouji

2015-01-01

Water-insoluble radioactive materials emitted during an early stage of the Fukushima Dai-ichi Nuclear Power Plant accident in 2011 were identified, and their chemical and physical properties were characterized as particulate matters. In this report, studies on radioactive particles collected from filter samples in Tsukuba on March 14–15, 2011 are summarized. Their compositions, chemical states, sizes, shapes, crystallinity, and hygroscopicity were analyzed using microscopic analyses such as electron microscopy and synchrotron with a micro-beam. The results indicate that they include Cs, Fe, and Zn as well as elements from fission products and are water insoluble, spherical-glassy particles with ca. 2 micrometer in size. Understanding of their detailed properties is significant to improve the numerical models during the accident and to understand their occurrences in soil as well as the accident itself. In addition to the water-insoluble radioactive materials, water-soluble radioactive materials, which were likely emitted in different events during the accident, should be investigated to have comprehensive understanding of the accident and its environmental effects. More samples from various environments such as soil will be needed, and more detailed chemical and physical analyses will help to understand their formation process, influences on human health, and long term decrements in ambient conditions. (author)

Measuring radioactive half-lives via statistical sampling in practice

Science.gov (United States)

Lorusso, G.; Collins, S. M.; Jagan, K.; Hitt, G. W.; Sadek, A. M.; Aitken-Smith, P. M.; Bridi, D.; Keightley, J. D.

2017-10-01

The statistical sampling method for the measurement of radioactive decay half-lives exhibits intriguing features such as that the half-life is approximately the median of a distribution closely resembling a Cauchy distribution. Whilst initial theoretical considerations suggested that in certain cases the method could have significant advantages, accurate measurements by statistical sampling have proven difficult, for they require an exercise in non-standard statistical analysis. As a consequence, no half-life measurement using this method has yet been reported and no comparison with traditional methods has ever been made. We used a Monte Carlo approach to address these analysis difficulties, and present the first experimental measurement of a radioisotope half-life (211Pb) by statistical sampling in good agreement with the literature recommended value. Our work also focused on the comparison between statistical sampling and exponential regression analysis, and concluded that exponential regression achieves generally the highest accuracy.

Natural radioactivity in lignite samples from open pit mines "Kolubara", Serbia--risk assessment.

Science.gov (United States)

Ðurašević, M; Kandić, A; Stefanović, P; Vukanac, I; Sešlak, B; Milošević, Z; Marković, T

2014-05-01

Coal as fossil fuel mainly contains naturally occurring radionuclides from the uranium and thorium series and (40)K. Use of coal, primarily in industry, as a result has dispersion of radioactive material from coal in and through air and water. The aim of this study was to determine the activity concentrations of natural radionuclides in coal samples from open pit mines "Kolubara" and to evaluate its effect on population health. The results showed that all measured and calculated values were below the limits recommended in international legislation. © 2013 Published by Elsevier Ltd.

Design of a radioactive gas sampling system for NESHAP compliance measurements of 41Ar

International Nuclear Information System (INIS)

Newton, G.J.; McDonald, M.J.; Ghanbari, F.; Hoover, M.D.; Barr, E.B.

1994-01-01

United States Department of Energy facilities are required to comply with the U.S. Environmental Protection Agency, National Emission Standard for Hazardous Air Pollutants (NESHAP) 40 CFR, part 61, subpart H. Compliance generally requires confirmatory measurements of emitted radionuclides. Although a number of standard procedures exist for extractive sampling of particle-associated radionuclides, sampling approaches for radioactive gases are less defined. Real-time, flow-through sampling of radioactive gases can be done when concentrations are high compared to interferences from background radiation. Cold traps can be used to collect and concentrate condensible effluents in applications where cryogenic conditions can be established and maintained. Commercially available gas-sampling cylinders can be used to capture grab samples of contaminated air under ambient or compressed conditions, if suitable sampling and control hardware are added to the cylinders. The purpose of the current study was to develop an efficient and compact set of sampling and control hardware for use with commercially available gas-sampling cylinders, and to demonstrate its use in NESHAP compliance testing of 41 Ar at two experimental research reactors

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)

New Equipment and Techniques for Remote Sampling of Stored Radioactive Waste

International Nuclear Information System (INIS)

Nance, T.A.

2001-01-01

Radioactive waste is stored at the Savannah River Site (SRS), part of the Department of Energy (DOE) complex. This radioactive waste is stored in buried tanks and management of the waste requires several processes, including material addition, heating, cooling, mixing, and transfer from tank to tank. During waste processing, it is necessary to know the chemical components and their characteristics to determine the steps necessary to maintain the waste form or to manipulate the waste into the form desired. Waste characterization begins by obtaining a sample for analysis. High level radioactive waste sampling is routinely done with simple, standard samplers such as a dip sample. Other sampling is non-routine or specialized, with unique, special requirements, such as sampling remote areas that are difficult to reach. Other specialized sampling includes sampling materials with unknown characteristics or material that must be gathered to obtain an adequate sample or materials that must be broken up to sample or forcibly separated from the tank. The samplers described in this paper are specialized samplers. These samplers include the Dip Filter Sampler, Soft Core Sampler, Hard Core Sampler, Circle Scrape Sampler, Small Scrape Sampler, Suction and Strain Sampler, and Vial Snapper Sampler. The Dip Filter Sampler is used to sample floating particulate matter or floating organic matter. The Soft Core Sampler and Hard Core Sampler are used to obtain samples of solids from the tank floor. The Soft Core Sampler is used on soft solids such as sludge and saltcake and the Hard Core Sampler on hardened solid deposits. The Circle Scrape Sampler is used to obtain solid samples through a small entry riser and out from under the riser. The Small Scrape Sampler enters a small entry riser and is used to scrape a sample from the tank wall. The Suction and Strain Sampler is used to gather a remote submerged sample or filter a solid sample from supernate. The Vial Snapper Grab Sampler is

Natural radioactivity measurement in pumice samples used raw materials in Turkey

International Nuclear Information System (INIS)

Turhan, S.; Yuecel, H.; Guenduez, L.; Sahin, S.; Vural, M.; Parmaksiz, A.; Demircioglu, B.

2007-01-01

The activity concentrations of 232 Th, 226 Ra, and 4 K in different pumice samples have been determined by high-resolution γ-ray spectrometry using a 110% HpGe detector. The radium equivalent activities (Ra eq ), external hazard index (H ex ), and internal hazard index (H in ) associated with the natural radionuclides and representative level index (I γ r ) are calculated to assess the radiation hazard of the natural radioactivity in the pumice samples. The mean values of the measured radioactivity concentrations of 232 Th, 226 Ra, and 4 K for pumice samples from the region of lakes (ROL) are 232.4±8.0, 196.9±7.8, and 1325.8±20.4 Bq kg -1 and for pumice samples from Cukurova region (CR) 16.3±4.0, 16.1±4.9, and 479.7±170.4 Bq kg -1 , respectively. The calculated Ra eq values vary from 435.9±12.5 to 883.6±41.5 Bq kg -1 with a mean of 630.9±20.2 Bq kg -1 for the ROL samples and from 49.7±3.3 to 101.9±7.2 Bq kg -1 with a mean of 76.3±23.7 Bq kg -1 for the CR samples. For the ROL samples, Ra eq are above the limit of 370 Bq kg -1 , equivalent to external γ dose of 1.5 mSv yr -1 , recommended for the safe use of construction materials by NEA-OECD, while for the CR samples, Ra eq values are lower than the limit

Device for sampling radioactive and aggressive liquid and vaporous media

International Nuclear Information System (INIS)

Przibram, E.; Halm, G.

1974-01-01

The equipment enables the taking of samples even of radioactive media from a main pipeline in the through-flow in a closed system. A tap device is attached to the main pipeline which branches into two parts. The one branch contains the actual tap which is closed to both sides with snap closure coupling. It is only used for taking samples. The other branch bridges the tap position as a bypass so that a representative sample is always available. Both branches join up again and lead back to the main pipeline. The sampling can be used in a nuclear power plant for the determination of O 2 , CI, SiO 2 , and Cu. A millilitre collecting cylinder and a millipore filtration device can be connected to the tap for liquid sampling and solid analysis, respectively. The system can be extended to several tap positions. Permanent measuring equipment is attached to the bypass pipe to control the sample liquid. (DG) [de

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)

SCADA based radioactive sample bottle delivery system for fuel reprocessing project

International Nuclear Information System (INIS)

Kaushik, Subrat; Munj, Niket; Chauhan, R.K.; Kumar, Pramod; Mishra, A.C.

2011-01-01

Radioactive samples of process streams need to be analyzed in centralized control lab for measuring concentration of heavy elements as well as activity at various stages of re-processing plants. The sample is taken from biologically shielded process cells remotely through sampling blisters in sample bottles. These are then transferred to control lab located about 50 meters using vacuum transfer system. The bottle movement is tracked from origin to destination in rich HMI SCADA system using Infra-red non contact type proximity sensors located along sampling line and these sensors are connected to PLC in a fail-safe mode. The sample bottle travels at a speed of 10 m/s under vacuum motive force and the detection time is of the order of 1 mS. The contact time Flow meters have been used to know the air flow in sampling line

A preliminary evaluation of comminution and sampling strategies for radioactive cemented waste

Energy Technology Data Exchange (ETDEWEB)

Bilodeau, M.; Lastra, R.; Bouzoubaa, N. [Natural Resources Canada, Ottawa, ON (Canada); Chapman, M. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2011-07-01

Lixiviation of Hg, U and Cs contaminants and micro-encapsulation of cemented radioactive waste (CRW) are the two main components of a CRW stabilization research project carried out at Natural Resources Canada in collaboration with Atomic Energy of Canada Limited. Unmolding CRW from the storage pail, its fragmentation into a size range suitable for both processes and the collection of a representative sample are three essential steps for providing optimal material conditions for the two studies. Separation of wires, metals and plastic incorporated into CRW samples is also required. A comminution and sampling strategy was developed to address all those needs. Dust emissions and other health and safety concerns were given full consideration. Surrogate cemented waste (SCW) was initially used for this comminution study where Cu was used as a substitute for U and Hg. SCW was characterized as a friable material through the measurement of the Bond work index of 7.7 kWh/t. A mineralogical investigation and the calibration of material heterogeneity parameters of the sampling error model showed that Cu, Hg and Cs are finely disseminated in the cement matrix. A sampling strategy was built from the model and successfully validated with radioactive waste. A larger than expected sampling error was observed with U due to the formation of large U solid phases, which were not observed with the Cu tracer. SCW samples were crushed and ground under different rock fragmentation mechanisms: compression (jaw and cone crushers, rod mill), impact (ball mill), attrition, high voltage disintegration and high pressure water (and liquid nitrogen) jetting. Cryogenic grinding was also tested with the attrition mill. Crushing and grinding technologies were assessed against criteria that were gathered from literature surveys, experiential know-how and discussion with the client and field experts. Water jetting and its liquid nitrogen variant were retained for pail cutting and waste unmolding while

A preliminary evaluation of comminution and sampling strategies for radioactive cemented waste

International Nuclear Information System (INIS)

Bilodeau, M.; Lastra, R.; Bouzoubaa, N.; Chapman, M.

2011-01-01

Lixiviation of Hg, U and Cs contaminants and micro-encapsulation of cemented radioactive waste (CRW) are the two main components of a CRW stabilization research project carried out at Natural Resources Canada in collaboration with Atomic Energy of Canada Limited. Unmolding CRW from the storage pail, its fragmentation into a size range suitable for both processes and the collection of a representative sample are three essential steps for providing optimal material conditions for the two studies. Separation of wires, metals and plastic incorporated into CRW samples is also required. A comminution and sampling strategy was developed to address all those needs. Dust emissions and other health and safety concerns were given full consideration. Surrogate cemented waste (SCW) was initially used for this comminution study where Cu was used as a substitute for U and Hg. SCW was characterized as a friable material through the measurement of the Bond work index of 7.7 kWh/t. A mineralogical investigation and the calibration of material heterogeneity parameters of the sampling error model showed that Cu, Hg and Cs are finely disseminated in the cement matrix. A sampling strategy was built from the model and successfully validated with radioactive waste. A larger than expected sampling error was observed with U due to the formation of large U solid phases, which were not observed with the Cu tracer. SCW samples were crushed and ground under different rock fragmentation mechanisms: compression (jaw and cone crushers, rod mill), impact (ball mill), attrition, high voltage disintegration and high pressure water (and liquid nitrogen) jetting. Cryogenic grinding was also tested with the attrition mill. Crushing and grinding technologies were assessed against criteria that were gathered from literature surveys, experiential know-how and discussion with the client and field experts. Water jetting and its liquid nitrogen variant were retained for pail cutting and waste unmolding while

Type A radioactive liquid sample packaging family

International Nuclear Information System (INIS)

Edwards, W.S.

1995-11-01

Westinghouse Hanford Company (WHC) has developed two packagings that can be used to ship Type A quantities of radioactive liquids. WHC designed these packagings to take advantage of commercially available items where feasible to reduce the overall packaging cost. The Hedgehog packaging can ship up to one liter of Type A radioactive liquid with no shielding and 15 cm of distance between the liquid and the package exterior, or 30 ml of liquid with 3.8 cm of stainless steel shielding and 19 cm of distance between the liquid and the package exterior. The One Liter Shipper can ship up to one liter of Type A radioactive liquid that does not require shielding

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.)

Sample taking device for toxic and/or radioactive substances

International Nuclear Information System (INIS)

Finsterwalder, L.; Zeh, H.; Schaarschmidt, U.

1979-01-01

An apparatus for taking samples of toxic and/or radioactive liquid substances by introducing such substances into sample vessels includes a holder for holding such a vessel, at least one needle head filling system composed of upwardly pointing hollow needles for introducing a sample of one such substance into such a vessel at a filling position, and inlet and outlet conduits for pneumatically conveying vessels to or from the holder at a transfer position. The holder is composed of a turntable having a sleeve for accommodating such vessel and is mounted to undergo rotary movement to convey a sample vessel held in the sleeve between the filling and transfer positions. The apparatus further includes a stand supporting the filling system below the holder and a lifting device connected for imparting a translational movement to the holder to bring a vessel in the holder to operative association with the filling system. The lifting device is arranged so that the translational movement which it produces is independent of the rotary movement of the turntable

Extraction and analysis of 14C-carbofuran radioactivity in soil sample

International Nuclear Information System (INIS)

Maizatul Akmam Mhd Nasir; Nashriyah Mat

2005-01-01

Carbofuran insecticide or nematicide sprayed onto soil in the agroecosystem will be taken up by plant. Carbofuran residue will pollute the environment and organisms in the food chain. Extraction and analysis of 14 C-carbofuran in soil from lysimeter were carried out. The Liquid Scintillation Counter (LSC) was used to measure radioactivity of 14 C-carbofuran in soil sample. (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

Radioactive mineral samples from the northwest of Chihuahua City, Mexico

International Nuclear Information System (INIS)

Reyes C, M.; Montero C, M.E.; Renteria V, M.; Fuentes M, L.; Fuentes C, L.; Herrera P, E.F.; Esparza P, H.; Rodriguez P, A.

2007-01-01

The Chihuahua-Sacramento valley is an area of 6 km wide by about 32 km in length, it is located from north to south. In the area, at least two zones exist that may have rocks with radioactive minerals: The Pastorias zone at the SW and the Majalca-San Marcos zone to the NW. The latter, was the object of the present investigation. By studying the geologic conditions and the processes of alteration in the San Marcos deposits, its hydrothermal origin and the different (at least two) alteration stages that has transformed the alkaline rhyolitic rock into per-alkaline were determined, to do more favorable the conditions for the hexavalent uranium minerals deposits. In the mineralogical characterization the following radioactive species were identified: uranofane, meta tyuyamunite and uraninite. These minerals were found also with secondary quartz-feldspar mineralization, with abundant hematization and an advanced process of argillization. The XRD, SEM and optical microscopy analyses of samples were very important for the accomplishment of the present investigation. (Author)

Radioactive mineral samples from the northwest of Chihuahua City, Mexico

Energy Technology Data Exchange (ETDEWEB)

Reyes C, M.; Montero C, M.E.; Renteria V, M.; Fuentes M, L.; Fuentes C, L.; Herrera P, E.F.; Esparza P, H. [Facultad de Ingenieria, Universidad Autonoma de Chihuahua, Nuevo Campus Universitario s/n, Chihuahua, Mexico y Centro de Investigacion en Materiales Avanzados, Miguel de Cervantes 120, 31109 Chihuahua (Mexico); Rodriguez P, A. [World Wildlife Fund (WWF), Chihuahuan Desert Program, Coronado 1005, 31000 Chihuahua (Mexico)]. e-mail: elena.montero@cimav.edu.mx

2007-07-01

The Chihuahua-Sacramento valley is an area of 6 km wide by about 32 km in length, it is located from north to south. In the area, at least two zones exist that may have rocks with radioactive minerals: The Pastorias zone at the SW and the Majalca-San Marcos zone to the NW. The latter, was the object of the present investigation. By studying the geologic conditions and the processes of alteration in the San Marcos deposits, its hydrothermal origin and the different (at least two) alteration stages that has transformed the alkaline rhyolitic rock into per-alkaline were determined, to do more favorable the conditions for the hexavalent uranium minerals deposits. In the mineralogical characterization the following radioactive species were identified: uranofane, meta tyuyamunite and uraninite. These minerals were found also with secondary quartz-feldspar mineralization, with abundant hematization and an advanced process of argillization. The XRD, SEM and optical microscopy analyses of samples were very important for the accomplishment of the present investigation. (Author)

The effect of radioactive aerosols on fog formation

International Nuclear Information System (INIS)

Ali, G.; Khan, E.U.; Ali, N.; Khan, H.A.; Waheed, A.

2011-01-01

This research study has been carried out to explore the dependence of fog formation on radioactive aerosols. The aerosols containing radioactive nuclides are called radioactive aerosols. A large number of radioactive nuclides are present in the atmosphere among which the two most important nuclides, 7Be and 210Pb are considered here in this study. Results for Activity Concentrations of these radio-nuclides in air samples in clear and foggy conditions were comparatively analyzed. About 19% increase in Activity concentration for 210Pb and about 23% increase in Activity Concentration for 7Be was recorded during fog as compared to clear conditions. This increase in Activity Concentration during fog indicates that the presence of aerosols laden with these radio-nuclides is also one of the so many factors responsible for fog formation

Natural radioactivity in lignite samples from open pit mines “Kolubara”, Serbia – risk assessment

International Nuclear Information System (INIS)

Đurašević, M.; Kandić, A.; Stefanović, P.; Vukanac, I.; Šešlak, B.; Milošević, Z.; Marković, T.

2014-01-01

Coal as fossil fuel mainly contains naturally occurring radionuclides from the uranium and thorium series and 40 K. Use of coal, primarily in industry, as a result has dispersion of radioactive material from coal in and through air and water. The aim of this study was to determine the activity concentrations of natural radionuclides in coal samples from open pit mines “Kolubara” and to evaluate its effect on population health. The results showed that all measured and calculated values were below the limits recommended in international legislation. - Highlights: • Activity concentrations of natural radionuclides in coal samples were determined. • Effect on population health due to the activity of these radionuclides was estimated. • All samples were collected at different locations of the open pit mines “Kolubara”. • All measured and calculated values were below the recommended limits. • There is no enhanced radiation hazard for population nearby open pit mines

The radioactivity estimation of 14C and 3H in graphite waste samples of the KRR-2.

Science.gov (United States)

Reyoung Kim, Hee

2013-09-01

The radioactivity of (14)C and (3)H in graphite samples from the dismantled Korea Research Reactor-2 (the KRR-2) site was analyzed by high-temperature oxidation and liquid scintillation counting, and the graphite waste was suggested to be disposed of as a low-level radioactive waste. The graphite samples were oxidized at a high temperature of 800 °C, and their counting rates were measured by using a liquid scintillation counter (LSC). The combustion ratio of the graphite was about 99% on the sample with a maximum weight of 1g. The recoveries from the combustion furnace were around 100% and 90% in (14)C and (3)H, respectively. The minimum detectable activity was 0.04-0.05 Bq/g for the (14)C and 0.13-0.15 Bq/g for the (3)H at the same background counting time. The activity of (14)C was higher than that of (3)H over all samples with the activity ratios of the (14)C to (3)H, (14)C/(3)H, being between 2.8 and 25. The dose calculation was carried out from its radioactivity analysis results. The dose estimation gave a higher annual dose than the domestic legal limit for a clearance. It was thought that the sampled graphite waste from the dismantled research reactor was not available for reuse or recycling and should be monitored as low-level radioactive waste. Copyright © 2013 Elsevier Ltd. All rights reserved.

Studies on methods of measurement of radioactivities of 36Cl and 3H in dual labelled samples

International Nuclear Information System (INIS)

Hirano, Shusuke; Asou, Hiroaki; Oishi, Katsuhiko; Hirano, Kiyoshi; Sato, Isamu

1985-01-01

In order to clarify how chloride molecules are transported into nervous tissue cells, we simultaneously used [ 36 Cl] -NaCl and [ 3 H] -inulin, and added AgNO 3 to the extract from the nervous tissue, obtaining 36 Cl-samples from the AgCl-precipitate and 3 H-samples from the supernatant. As for radioactivity of 36 Cl or 3 H in the dual-labelled samples, the recovery rates by our separation method were about 100%. Using cultured astrocytoma cells, 36 Cl-uptake into the cells, which was calculated by inulin assumption, was investigated. Intracellular 36 Cl-radioactivity changed vis-a-vis with that in the extracellular space. The volume of intracellular water, which was calculated by 3 H-inulin assumption, remained unchanged, even though a few variations in 36 Cl-radioactivity in cells were determined by both our separation method and spill-over method. (author)

Improved metamodel-based importance sampling for the performance assessment of radioactive waste repositories

International Nuclear Information System (INIS)

Cadini, F.; Gioletta, A.; Zio, E.

2015-01-01

In the context of a probabilistic performance assessment of a radioactive waste repository, the estimation of the probability of exceeding the dose threshold set by a regulatory body is a fundamental task. This may become difficult when the probabilities involved are very small, since the classically used sampling-based Monte Carlo methods may become computationally impractical. This issue is further complicated by the fact that the computer codes typically adopted in this context requires large computational efforts, both in terms of time and memory. This work proposes an original use of a Monte Carlo-based algorithm for (small) failure probability estimation in the context of the performance assessment of a near surface radioactive waste repository. The algorithm, developed within the context of structural reliability, makes use of an estimated optimal importance density and a surrogate, kriging-based metamodel approximating the system response. On the basis of an accurate analytic analysis of the algorithm, a modification is proposed which allows further reducing the computational efforts by a more effective training of the metamodel. - Highlights: • We tackle uncertainty propagation in a radwaste repository performance assessment. • We improve a kriging-based importance sampling for estimating failure probabilities. • We justify the modification by an analytic, comparative analysis of the algorithms. • The probability of exceeding dose thresholds in radwaste repositories is estimated. • The algorithm is further improved reducing the number of its free parameters

The real-time fitting of radioactive decay curves. Pt. 3. Counting during sampling

International Nuclear Information System (INIS)

Hartley, B.M.

1994-01-01

An analysis of a least-squares method for the real-time fitting of the theoretical total count function to the actual total count from radioactive decays has been given previously for the case where counting takes place after a sample is taken. The counting may be done in a number of different counting systems which distinguish between different types or energies of radiation emitted from the sample. The method would allow real-time determination of the numbers of atoms and hence activities of the individual isotopes present and has been designated the Time Evolved Least-Squares method (TELS). If the radioactivity which is to be measured exists as an aerosol or in a form where a sample is taken at a constant rate it may be possible to count during sampling and by so doing reduce the total time required to determine the activity of the individual isotopes present. The TELS method is extended here to the case where counting and the evaluation of the activity takes place concurrently with the sampling. The functions which need to be evaluated are derived and the calculations required to implement the method are discussed. As with the TELS method of counting after sampling the technique of counting during sampling and the simultaneous evaluation of activity could be achieved in real-time. Results of testing the method by computer simulation for two counting schemes for the descendants of radon are presented. ((orig.))

Effective extraction of radioactive cesium from various pollutants with a detergent solution including Mg2+ and K+

International Nuclear Information System (INIS)

Noguchi, Yuki; Kida, Toshiyuki; Kato, Eiichi; Akashi, Mitsuru; Shimizu, Kikuo

2015-01-01

Radioactive cesium (Cs) is extracted effectively from various polluted samples such as soil, silt, and burned ash by washing with a detergent solution comprised of KCl, MgCl 2 , and hydroxyethyl cellulose in a 5% H 2 SO 4 aqueous solution. Repeatedly washing extracts more than 65% of the radioactive Cs. (author)

SCADA based radioactive sample bottle delivery system for fuel reprocessing project

International Nuclear Information System (INIS)

Kaushik, Subrat; Munj, Niket; Chauhan, R.K.; Jayaram, M.N.; Haneef, K.K.M.

2014-01-01

Radioactive samples of process streams need to be analyzed in centralized control lab for measuring concentration of heavy elements as well as activity at various stages of re-processing plants. The sample is taken from biologically shielded process cells remotely through sampling blisters in sample bottles. These are then transferred to control lab located about 50 meters using vacuum transfer system. The bottle movement is tracked from origin to destination in rich HMI SCADA system using Infra-red non contact type proximity sensors located along sampling line and these sensors are connected to PLC in a fail-safe mode. The sample bottle travels at a speed of 10 m/s under vacuum motive force and the detection time is of the order of 1 mS. The flow meters have been used to know the air flow in sampling line. The system has been designed, developed, tested and commissioned and in use for four years. (author)

Annual effective dose due to natural radioactivity in drinking water

International Nuclear Information System (INIS)

Padma Savithri, P.; Srivastava, S.K.; Balbudhe, A.Y.; Vishwa Prasad, K.; Ravi, P.M.; Tripathi, R.M.

2014-01-01

Natural radioactivity concentration in drinking water supply in and round Hyderabad, Secunderabad was determined. The observed gross alpha activity found in water samples vary from 0.027±0.014 Bq/L to 0.042±0.015 Bq/L with average 0.035 Bq/L while beta activity in all the samples are less than 0.076 Bq/l. Contributions of the drinking water samples to total annual effective dose equivalent from 238 U, 234 U, 230 Th, 26 Ra, 210 Po, 232 Th, 228 Th 210 Pb and 228 Ra are 1.14, 1.24, 5.30, 7.07, 30.3, 5.81, 1.82, 38.3 and 38.3 μSvy -1 for adults. The results indicate that the annual effective doses are below the WHO recommended reference level for α and β in food and drinking samples. (author)

Recommendations for sampling for prevention of hazards in civil defense. On analytics of chemical, biological and radioactive contaminations. Brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling; Empfehlungen fuer die Probenahme zur Gefahrenabwehr im Bevoelkerungsschutz. Zur Analytik von chemischen, biologischen und radioaktiven Kontaminationen. Kurzanleitung fuer die CBRN-Probenahme

Energy Technology Data Exchange (ETDEWEB)

Bachmann, Udo; Biederbick, Walter; Derakshani, Nahid (and others)

2010-07-01

The recommendation for sampling for prevention of hazards in civil defense is describing the analytics of chemical, biological and radioactive contaminations and includes detail information on the sampling, protocol preparation and documentation procedures. The volume includes a separate brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling.

Determination of 35S-aminoacyl-transfer ribonucleic acid specific radioactivity in small tissue samples

International Nuclear Information System (INIS)

Samarel, A.M.; Ogunro, E.A.; Ferguson, A.G.; Lesch, M.

1981-01-01

Rate determination of protein synthesis utilizing tracer amino acid incorporation requires accurate assessment of the specific radioactivity of the labeled precursor aminoacyl-tRNA pool. Previously published methods presumably useful for the measurement of any aminoacyl-tRNA were unsuccessful when applied to [ 35 S]methionine, due to the unique chemical properties of this amino acid. Herein we describe modifications of these methods necessary for the measurement of 35 S-aminoacyl-tRNA specific radioactivity from small tissue samples incubated in the presence of [ 35 S]methionine. The use of [ 35 S]methionine of high specific radioactivity enables analysis of the methionyl-tRNA from less than 100 mg of tissue. Conditions for optimal recovery of 35 S-labeled dansyl-amino acid derivatives are presented and possible applications of this method are discussed

Radiometric assessment of natural radioactivity levels of agricultural soil samples collected in Dakahlia, Egypt.

Science.gov (United States)

Issa, Shams A M

2013-01-01

Determination of the natural radioactivity has been carried out, by using a gamma-ray spectrometry [NaI (Tl) 3″ × 3″] system, in surface soil samples collected from various locations in Dakahlia governorate, Egypt. These locations form the agriculturally important regions of Egypt. The study area has many industries such as chemical, paper, organic fertilisers and construction materials, and the soils of the study region are used as a construction material. Therefore, it becomes necessary to study the natural radioactivity levels in soil to assess the dose for the population in order to know the health risks. The activity concentrations of (226)Ra, (232)Th and (40)K in the soil ranged from 5.7 ± 0.3 to 140 ± 7, from 9.0 ± 0.4 to 139 ± 7 and from 22 ± 1 to 319 ± 16 Bq kg(-1), respectively. The absorbed dose rate, annual effective dose rate, radium equivalent (Req), excess lifetime cancer risk, hazard indices (Hex and Hin) and annual gonadal dose equivalent, which resulted from the natural radionuclides in the soil were calculated.

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)

Radioactive and electron microscope analysis of effluent monitor sample lines

International Nuclear Information System (INIS)

Kowalski, J.F.

1986-01-01

Effluent air sampling at nuclear power plant often leads to the question ''How representative is the sample of the effluent stream?'' Samples from radiation monitors are typically obtained at great distances from the sample nozzle because of high background concerns under postulated accidents. Sample line plateout during normal effluent sampling becomes the major concern. A US Nuclear Regulatory Commission inspection raised a concern that monitors were not collecting representative samples per ANSI standard N13.1. A comprehensive 2-yr study at Beaver Valley was performed during normal effluent releases in two phases: 1) weekly charcoal and glass fiber filter samples were analyzed for radioactivity for 6 months, and 2) nuclepore membrane filter samples were analyzed by electron microscope for 4- and 6-h periods. A specially designed test nozzle was directly inserted into an effluent stream for comparison with the radiation monitor samples. Particle behavior characteristics can be determined during effluent releases using a simple test probe. While particle plateout was the major purpose of the study, other particle behavior characteristics were evident and equally as important. Particle travel through long sample lines can also lead to (a) agglomeration or the coagulation of smaller particles to form larger ones, (b) particle splitting or fracturing upon impact with the sample line interior walls, and (c) resuspension of large particles in sample lines

Natural Radioactivity Levels in Environmental Samples in North Western Desert of Egypt

International Nuclear Information System (INIS)

El-Daly, A.; Hussein, A.S.

2009-01-01

Soil and sediment samples were collected from North western desert of Egypt. Gamma spectroscopy was used to determine the concentration of naturally occurring radionuclides 238 U, 232 Th and 40 K. The hazard index due to these radionuclides has been calculated. The measurement results obtained from this study indicate that the region has background radioactivity levels within natural limits

Evaluation of induced radioactivity in 10 MeV electron-irradiated spices

Energy Technology Data Exchange (ETDEWEB)

Furuta, Masakazu; Ito, Norio; Mizohata, Akira; Matsunami, Tadao; Katayama, Tadashi; Toratani, Hirokazu (Osaka Prefectural Univ., Sakai (Japan). Research Inst. for Advanced Science and Technology); Takeda, Atsuhiko

1993-10-01

In order to make clear appreciation to induced radioactivity in the irradiated foods, photonuclear reactions which could produce radioactivity at energies up to 10 MeV were listed up from elemental compositions of black pepper, white pepper, red pepper, ginger and turmeric. The samples were irradiated with 10 MeV electron from a linear accelerator to a dose of 100 kGy and radioactivity was measured. Induced radioactivity could not be detected significantly by gamma-ray spectrometry and beta-ray counting in the irradiated samples except for spiked samples which contain some photonuclear target nuclides in the list. From the amount of observed radioactivities of short-lived photonuclear products in the spiked samples and calculation of H[sub 50] according to ICRP Publication 30, it was concluded that the induced radioactivity and its biological effects in the 10 MeV electron-irradiated natural samples were negligible in comparison with natural radioactivity from [sup 40]K contained in the samples. (J.P.N.).

Natural radioactivity measurements in rock samples of Cuihua Mountain National Geological Park (China))

International Nuclear Information System (INIS)

Lu, X.; Zhang, X.

2008-01-01

The concentrations of the natural radionuclides namely 40 K, 232 Th and 226 Ra in rock samples collected from Cuihua Mountain National Geological Park of China have been determined using a NaI(Tl) detector. The concentrations of 226 Ra, 232 Th and 40 K in the studied rock samples range from 10.7 to 34.8, 19.9 to 53.6 and 642.7 to 1609.9 Bq kg -1 with an average of 20.4, 30.1 and 1009.5 Bq kg -1 , respectively. The concentrations of these radionuclides are compared with the typical world values. To evaluate the radiological hazard of the natural radioactivity, the radium equivalent activity, the air absorbed dose rate, the annual effective dose rate, the representative level index and the values of both external and internal hazard indices were evaluated and compared with the internationally approved values. The radium equivalent activity values of all rock samples are lower than the limit of 370 Bq kg -1 . The values of H ex and H in are less than unity. The mean outdoor air absorbed dose rate is 69.7 nGy h -1 , and the corresponding outdoor effective dose rate is 0.086 mSv y -1 . (authors)

Effects of non-radioactive material around radioactive material on PET image quality

International Nuclear Information System (INIS)

Toshimitsu, Shinya; Yamane, Azusa; Hirokawa, Yutaka; Kangai, Yoshiharu

2015-01-01

Subcutaneous fat is a non-radioactive material surrounding the radioactive material. We developed a phantom, and examined the effect of subcutaneous fat on PET image quality. We created a cylindrical non-radioactive mimic of subcutaneous fat, placed it around a cylindrical phantom in up to three layers with each layer having a thickness of 20 mm to reproduce the obesity caused by subcutaneous fat. In the cylindrical phantom, hot spheres and cold spheres were arranged. The radioactivity concentration ratio between the hot spheres and B.G. was 4:1. The radioactivity concentration of B.G. was changed as follows : 1.33, 2.65, 4.00, and 5.30 kBq/mL. 3D-PET image were collected during 10 minutes. When the thickness of the mimicked subcutaneous fat increased from 0 mm to 60 mm, noise equivalent count decreased by 58.9-60.9% at each radioactivity concentration. On the other hand, the percentage of background variability increased 2.2-5.2 times. Mimic subcutaneous fat did not decrease the percentage contrast of the hot spheres, and did not affect the cold spheres. Subcutaneous fat decreases the noise equivalent count and increases the percentage of background variability, which degrades PET image quality. (author)

A simplified system for doing ICP analysis on radioactive samples

International Nuclear Information System (INIS)

McCown, J.J.

1985-11-01

Methods for setting up equipment to perform analyses on radioactive materials vary considerably from one site to another. Factors include the interests of the group involved, i.e., research vs service work; the type of building containing the lab; the arrangement of the lab for contamination control; previous experiences in operating similar equipment; the local interpretation of safety regulations; and the time and money available for the task. The Chemistry and Analysis group of the Westinghouse Hanford Company performs analytical chemistry in support of many Hanford programs. Samples analyzed cover a wide variety of materials with more than 50% involving radioactivity of one type or another. All of the laboratories in the building are connected to a common exhaust system with ductwork leading to the basement. Double HEPA filtration is provided with the first stage in the basement and the final stage done in the exhaust fan and filter building northwest of the main building. In addition, glove boxes are equipped with small HEPA filters on their outlet providing another stage of filtration. 6 figs

Preparation and application of radioactive soil samples for intercomparison

International Nuclear Information System (INIS)

Gao Zequan; Li Zhou; Li Pengxiang; Wang Ruijun; Ren Xiaona

2014-01-01

This article summarized the preparation process and intercomparison results of the simulated environmental radioactive soil samples. The components of the matrix were: SiO 2 , Al 2 O 3 , Fe 2 O 3 , MgO, CaO, NaCl, KCl and TiO 2 . All of the components were milled, oven-dried, sieved and then blended together. The homogeneity test was according to GB 15000. 5-1994, and no significant differences were observed. The 3 H analysis soils were spiked natural soils with the moisture content of 15%. Eight laboratories attended this intercomparison. The results proves that the preparation of the simulated soils were suitable for the inter-laboratories comparison. (authors)

Effect of Radioactivity of Technetium-99m on the Autosterilization Process of non-sterile Tetrofosmin Kits

Directory of Open Access Journals (Sweden)

Widyastuti Widyastuti

2017-03-01

Full Text Available Technetium-99m labeled radiopharmaceutical is commonly used in nuclear medicines as a diagnostic agent, by mixing the sterile kit with Tc-99m. Manufacturing of kits requires an aseptic facility which need to be well designed and maintained according to cGMP, since mostly kits can not be terminally sterilized. Radiopharmaceuticals as pharmaceuticals containing radionuclide is assumed to have an autosterilization property, but correlation between radioactivity and capability of killing microorganisms has to be studied so far. The aim of this study is to investigate the effect of radioactivity on the autosterilization process of radiopharmaceuticals. The study was carried out by adding Tc-99m of various radioactivity into non-sterile tetrofosmin kits, then the samples were tested for sterility. Sterile tetrofosmin kit and non-sterile kit with no Tc-99m added will be used as a negative control and positive control respectively. The sterility was tested using standard direct inoculation method, by inoculating samples in culture media for both bacteria and fungi and observing qualitatively within 14 days. The results showed that the samples with radioactivity of 1, 3 and 5 mCi changed the clarity of the media to turbid, conformed with the performance of positive controls but samples with radioactivity of 10 mCi and 20 mCi did not change the clarity of the media, conformed with the performance of negative control, indicating neither growth of bacteria nor fungi. It is concluded that Tc-99m behaves as an autosterilizing agent at certain radioactivity. Therefore the preparation of Tc-99m radiopharmaceutical can be considered as terminal sterilization rather than aseptic preparation.

Environmental Radioactive Pollution Sources and Effects on Man

International Nuclear Information System (INIS)

El-Naggar, A.M.

1999-01-01

The sources of environmental radioactivity are essentially the naturally occurring radionuclides in the earth,s crust and the cosmogenic radionuclides reaching the environmental ecosystems. The other sources of environmental radioactivity are the man made sources which result from the radioactive materials in human life. The naturally occurring environmental radioactivity is an integral component of the terrestrial and extraterrestrial creation, and therefore it is not considered a source of radioactive pollution to the environment. The radioactive waste from human activities is released into the environment, and its radionuclide content becomes incorporated into the different ecosystems. This results in a situation of environmental radioactive pollution. This review presents the main features of environmental radioactive pollution, the radionuclide behaviour in the ecosystems, pathway models of radionuclides in the body and the probability of associated health hazards. The dose effect relationship of internal radiation exposure and its quantitative aspects are considered because of their relevance to this subject

Evaluation of induced radioactivity in 10 MeV-electron irradiated spices, (1)

International Nuclear Information System (INIS)

Furuta, Masakazu; Katayama, Tadashi; Ito, Norio; Mizohata, Akira; Matsunami, Tadao; Shibata, Setsuko; Toratani, Hirokazu; Takeda, Atsuhiko.

1994-01-01

Black pepper, white pepper, red pepper, ginger and turmeric were irradiated with 10 MeV electrons from a linear accelerator to a dose of 100 kGy and radioactivity was measured in order to estimate induced radioactivity in the irradiated foods. Induced radioactivity could not be detected significantly by γ-ray spectrometry in the irradiated samples except for spiked samples which contain some photonuclear target nuclides in the list of photonuclear reactions which could produce radioactivity below 10 MeV. From the amount of observed radioactivities of short-lived photonuclear products in the spiked samples and calculation of H 50 according to ICRP Publication 30, it was concluded that the induced radioactivity and its biological effects in the 10 MeV electron-irradiated natural samples were negligible in comparison with natural radioactivity from 40 K contained in the samples. (author)

Evaluating the reproducibility of environmental radioactivity monitoring data through replicate sample analysis

International Nuclear Information System (INIS)

Lindeken, C.L.; White, J.H.; Silver, W.J.

1978-01-01

At the Lawrence Livermore Laboratory, about 10% of the sampling effort in the environmental monitoring program represents replicate sample collection. Replication of field samples was initiated as part of the quality assurance program for environmental monitoring to determine the reproducibility of environmental measurements. In the laboratory these replicates are processed along with routine samples. As all components of variance are included in analysis of such field samples, comparison of the analytical data from replicate analyses provides a basis for estimating the overall reproducibility of the measurements. The replication study indicates that the reproducibility of environmental radioactivity monitoring data is subject to considerably more variability than is indicated by the accompanying counting errors. The data are also compared with analyses of duplicate aliquots from a well mixed sample or with duplicate aliquots of samples with known radionuclide content. These comparisons show that most of the variability is associated with the collection and preparation of the sample rather than with the analytical procedures

A destructive sample preparation method for radioactive waste characterization

International Nuclear Information System (INIS)

Olteanu, M.; Bucur, C.

2015-01-01

Acid digestion, using the microwave power, was applied for ''dissolution'' of different materials corresponding to the radioactive waste matrices resulted from a nuclear power plant operation, including exchange resin (cationic and mixed), concrete, paper, textile and activated charcoals. A small aliquot of solid sample (0.1-0.5g) was mixed with a known volume of digestion reagents (HNO3 67% - H2O2 30% or HNO3 67% - HCl 37%, with HF addition if the SiO2 was present in matrices) in a 100 ml PTFE vessel and it was mineralized using a Berghof digestion system, Speedwave 4. Starting from the manufacturer procedures, the technical parameters (temperature and mineralization time), the types and quantities of digestion reagents were optimized. After the mineralization process, the samples were transferred in centrifuge tubes, separated at 3500 rot/min and visually analysed. The obtained solutions were clear, without suspended or deposed materials and separated phases, ready for future separation processes of the ''difficult to measure'' radioisotopes. (authors)

Characterization of a low-level radioactive waste grout: Sampling and test results

International Nuclear Information System (INIS)

Martin, P.F.C.; Lokken, R.O.

1992-12-01

WHC manages and operates the grout treatment facility at Hanford as part of a DOE program to clean up wastes stored at federal nuclear production sites. PNL provides support to the grout disposal program through pilot-scale tests, performance assessments, and formulation verification activities. in 1988 and 1989, over one million gallons of a low-level radioactive liquid waste was processed through the facility to produce a grout waste that was then deposited in an underground vault. The liquid waste was phosphate/sulfate waste (PSW) generated in decontamination of the N Reactor. PNL sampled and tested the grout produced during the second half of the PSW campaign to support quality verification activities prior to grout vault closure. Samples of grout were obtained by inserting nested-tube samplers into the grout slurry in the vault. After the grout had cured, the inner tube of the sampler was removed and the grout samples extracted. Tests for compressive strength, sonic velocity, and leach testing were used to assess grout quality; results were compared to those from pilot-scale test grouts made with a simulated PSW. The grout produced during the second half of the PSW campaign exceeded compressive strength and leachability formulation criteria. The nested tube samplers were effective in collecting samples of grout although their use introduced greater variability into the compressive strength data

Radioactive disequilibria in mineralised drill core samples from the Bjoerklund uranium occurence, northern Sweden

International Nuclear Information System (INIS)

Smellie, J.A.T.

1982-12-01

Forming the basis of a pilot study to investigate the natural mobility of uranium and its daughter products within the geological environment, a series of six samples, chosen from two mineralised fracture zones at depths of 100-130m within a homogeneous leucocratic granite, were examined mineralogically and isotopically to establish the presence or absence of radioactive equilibrium that may indicate recent rock/water interaction processes (i.e. during the last 0.5 m.y.). The results show clear evidence of radioactive disequilibrium, and hence recent rock/water interaction, in four of the six samples. Some is attributable mostly to solution-solid 234 U recoil gain (weakly mineralised zones adjacent to the main mineralisation) and others to solid-solution 234 U recoil loss (moderate to highly mineralised zones). The richer type of impregnation mineralisation indicates apparent radioactive equilibrium. The absence of significant 238 U loss in the samples helps to underline the reducing conditions prevalent within open fracture systems at these depths. This has meant that uraninite, now found in fractured rock at about 100m depth, has been chemically stable in its environment for most, if not all, of its 1750 m.y. existence, including the last 0.5 m.y. when it has been closest to the atmosphere. This could indicate that spent nuclear fuel, which essentially is crystalline UO 2 , and comparable to uraninite once the main fission products have decayed, would also have been stable in this environment for similar periods of time. (Author)

New mass-spectrometric facility for the analysis of highly radioactive samples

International Nuclear Information System (INIS)

Warmack, R.J.; Landau, L.; Christie, W.H.; Carter, J.A.

1981-01-01

A new facility has been completed for the analysis of highly radioactive, gamma-emitting solid samples. A commercial spark-source mass spectrometer was adapted for remote handling and loading. Electrodes are prepared in a hot cell and transported to the adjacent lead-shielded source for analysis. The source was redesigned for ease of shielding, loading, and maintenance. Both solutions and residues from irradiated nuclear fuel dissolutions have been analyzed for elemental concentrations to < 1 ppM; isotopic data have also been obtained

A report on radioactivity measurements of fish samples from the west coast of Canada

International Nuclear Information System (INIS)

Chen, Jing; Cooke, Michael W.; Mercier, Jean-Francois; Ahier, Brian; Trudel, Marc; Workman, Greg; Wyeth, Malcolm; Brown, Robin

2015-01-01

Even though many studies have shown that radioactive caesium levels in fish caught outside of Japan were below experimental detection limits of a few Bq kg -1 , significant public concern has been expressed about the safety of consuming seafood from the Pacific Ocean following the Fukushima-Daiichi nuclear accident. To address the public concerns, samples of commonly consumed salmon and groundfish harvested from the Canadian west coast in 2013 were analysed for radioactive caesium. None of the fish samples analysed in this study contained any detectable levels of 134 Cs and 137 Cs under given experimental setting with the average detection limit of ∼2 Bq kg -1 . Using a conservative worst-case scenario where all fish samples would contain 137 Cs exactly at the detection limit level and 134 Cs at half of the detection limit level (to account for much shorter half-life of 134 Cs), the resulting radiation dose for people from consumption of this fish would be a very small fraction of the annual dose from exposure to natural background radiation in Canada. Therefore, fish, such as salmon and groundfish, from the Canadian west coast are of no radiological health concern. (authors)

Study of Efficiency Calibrations of HPGe Detectors for Radioactivity Measurements of Environmental Samples

International Nuclear Information System (INIS)

Harb, S.; Salahel Din, K.; Abbady, A.

2009-01-01

In this paper, we describe a method of calibrating of efficiency of a HPGe gamma-ray spectrometry of bulk environmental samples (Tea, crops, water, and soil) is a significant part of the environmental radioactivity measurements. Here we will discuss the full energy peak efficiency (FEPE) of three HPGe detectors it as a consequence, it is essential that the efficiency is determined for each set-up employed. Besides to take full advantage at gamma-ray spectrometry, a set of efficiency at several energies which covers the wide the range in energy, the large the number of radionuclides whose concentration can be determined to measure the main natural gamma-ray emitters, the efficiency should be known at least from 46.54 keV ( 210 Pb) to 1836 keV ( 88 Y). Radioactive sources were prepared from two different standards, a first mixed standard QC Y 40 containing 210 Pb, 241 Am, 109 Cd, and Co 57 , and the second QC Y 48 containing 241 Am, 109 Cd, 57 Co, 139 Ce, 113 Sn, 85 Sr, 137 Cs, 88 Y, and 60 Co is necessary in order to calculate the activity of the different radionuclides contained in a sample. In this work, we will study the efficiency calibration as a function of different parameters as:- Energy of gamma ray from 46.54 keV ( 210 Pb) to 1836 keV ( 88 Y), three different detectors A, B, and C, geometry of containers (point source, marinelli beaker, and cylindrical bottle 1 L), height of standard soil samples in bottle 250 ml, and density of standard environmental samples. These standard environmental sample must be measured before added standard solution because we will use the same environmental samples in order to consider the self absorption especially and composition in the case of volume samples.

Determination of /sup 35/S-aminoacyl-transfer ribonucleic acid specific radioactivity in small tissue samples

Energy Technology Data Exchange (ETDEWEB)

Samarel, A.M.; Ogunro, E.A.; Ferguson, A.G.; Lesch, M.

1981-11-15

Rate determination of protein synthesis utilizing tracer amino acid incorporation requires accurate assessment of the specific radioactivity of the labeled precursor aminoacyl-tRNA pool. Previously published methods presumably useful for the measurement of any aminoacyl-tRNA were unsuccessful when applied to (/sup 35/S)methionine, due to the unique chemical properties of this amino acid. Herein we describe modifications of these methods necessary for the measurement of /sup 35/S-aminoacyl-tRNA specific radioactivity from small tissue samples incubated in the presence of (/sup 35/S)methionine. The use of (/sup 35/S)methionine of high specific radioactivity enables analysis of the methionyl-tRNA from less than 100 mg of tissue. Conditions for optimal recovery of /sup 35/S-labeled dansyl-amino acid derivatives are presented and possible applications of this method are discussed.

Determination of specific alpha-radioactivity of flora samples from semipalatinsk test site (STS)

International Nuclear Information System (INIS)

Blekhman, A.M.; Dujsenbaev, A.; Orazova, A.O.

1999-01-01

For further rehabilitation of soil earlier contaminated with radioactive fallout, the method of radionuclide absorption by plants is vital. The last updating of electronic system of the facility meant to analyze impulse shape /2/ helped to enlarge dynamical range of registration and reduction of identification threshold for alpha particles up to 50 keV. We have developed methods for STS flora samples preparation and performed first measurements of their specific alpha activity. Measurement results are in table 1. Measurement results analysis shows that STS flora samples can accumulate considerable concentrations of alpha active nuclides

Study on radioactive fallout from Fukushima nuclear accident by plant samples using an imaging plate system

International Nuclear Information System (INIS)

Minowa, Haruka

2011-01-01

The radioactive fallout from the Fukushima nuclear accident was investigated by the radiation images of plant samples using an Imaging Plate System. Plant samples exposed by an imaging plate BASIII 2040 (Fujifilm, Japan) in overnight to one week, and radiation images were read by Typhoon FLA7000 (GE Healthcare Japan Corp.). Identifying and quantitative analysis of radionuclides were measured by Auto Well Gamma System ARC-380CL (Aloha Co. Ltd., Tokyo, Japan). In the cross-sectional images of the bamboo shoot, the radioactive material is shown in heterogeneous distribution, it was found that it concentrated on the tip of the edible portion, and thin skin. These radionuclides were identified as "1"3"7Cs, "1"3"4Cs, and "4"0K. "4"0K is a natural radionuclide, on the other hand "1"3"7Cs and "1"3"4Cs would be derived from the accident of the Fukushima Daiichi Nuclear Power Plant. A high concentration of "1"3"4Cs was shown at the distance of 150 mm from the base of the bamboo shoot by cross-sectional cutting into the width of about 1 mm. It was estimated about 1 kBq of "1"3"4Cs would be included in about 400 g (wet weight) of this one bamboo shoot in an edible part. Imaging data suggests that the contamination of radioactive cesium in this bamboo shoot was caused not by the extraneous attachment but by the absorption from roots. Because bamboo is gather water from extensive area, bamboo shoot concentrates the radioactive material contained in the rain even at low concentrations of radioactive materials in soil. (author)

Estimation of radon exhalation rate, natural radioactivity and radiation doses in fly ash samples from NTPC Dadri, (UP) India

International Nuclear Information System (INIS)

Gupta, Mamta; Verma, K.D.; Mahur, A.K.; Rajendra Prasad; Sonkawade, R.G.

2010-01-01

Fly ash produced by coal-burning in thermal power station has become a subject of world wide interest in recent years, because of its diverse uses in building materials such as bricks, sheets, cement and land filling etc. The knowledge of radio nuclides in fly ash plays an important role in health physics. Natural radioactivity and radon exhalation rate in fly ash samples collected from NTPC (National Thermal Power Corporation) Dadri, (UP.) India, have been studied. A high resolution gamma ray spectroscopic system has been used for the measurement of natural radioactivity. The activity concentration of natural radionuclides radium ( 226 Ra), thorium ( 232 Th) and potassium ( 40 K) were measured and radiological parameters were calculated. Radium concentration was found to vary from (81.01 ± 3.25) to (177.33 ±10.00) Bq kg -1 . Activity concentration of thorium was found to vary from (111.57 ± 3.21) to (178.50 ± 3.96) Bq kg -1 . Potassium activity was not significant in some samples, whereas, some other samples have shown potassium activity vary from (365.98 ± 4.85) to (495.95 ± 6.23) Bq kg -1 . Radon exhalation rates in these samples were also calculated by 'Sealed Can technique' using LR-115 type II detectors and found to vary from (80 ± 9) to (243 ± 16) mBqm -2 h -1 with an average value (155 ± 13) mBqm -2 h -1 . This study also presents the results of estimation of effective dose equivalent from exhalation rate, radium equivalent, absorbed gamma dose rates, external annual effective dose rate and values of external hazard index for the fly ash samples. (author)

Guide to sampling airborne radioactive materials in nuclear facilities

International Nuclear Information System (INIS)

Glissmeyer, J.A.

1995-01-01

The ANSI N13.1-1969 Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities is currently being revised. The revision is being drafted by a working group under the auspices of the Health Physics Society Standards Committee. The main differences between the original standard and the proposed revision are a narrowed scope, a greater emphasis on the design process, and the verification of meeting performance criteria. Compliance with the revised standard will present new challenges, especially in the area of performance validation. The progress made in the revision and key portions of the standard are discussed. The DOE has recently petitioned EPA for alternate approaches to complying with air-sampling regulations. Dealing with compliance issues until the revised standard is adopted will be a challenge for both designers and regulators. The objective of this paper is to briefly describe the content of the proposed revision in order to point out significant differences from the old standard and to describe the new challenges that the proposed revision will present

Guide to sampling airborne radioactive materials in nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Glissmeyer, J.A. [Pacific Northwest Laboratory, Richland, WA (United States)

1995-02-01

The ANSI N13.1-1969 Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities is currently being revised. The revision is being drafted by a working group under the auspices of the Health Physics Society Standards Committee. The main differences between the original standard and the proposed revision are a narrowed scope, a greater emphasis on the design process, and the verification of meeting performance criteria. Compliance with the revised standard will present new challenges, especially in the area of performance validation. The progress made in the revision and key portions of the standard are discussed. The DOE has recently petitioned EPA for alternate approaches to complying with air-sampling regulations. Dealing with compliance issues until the revised standard is adopted will be a challenge for both designers and regulators. The objective of this paper is to briefly describe the content of the proposed revision in order to point out significant differences from the old standard and to describe the new challenges that the proposed revision will present.

Low-level Radioactivity Measurements

International Nuclear Information System (INIS)

Churtgen, C.

2007-01-01

The low-level radioactivity measurements service performs measurements of alpha or beta emitters on various types of low-radioactivity samples (biological and environmental) from internal and external clients. to maintain and develop techniques concerning the measurement of low-level radioactivity of alpha and beta emitting radionuclides in environmental or biological samples; to measure these samples by means of low-background counters (liquid scintillators, proportional counters, ZnS counters and alpha-spectrometers); to support and advise the nuclear and non-nuclear industry on problems of radioactive contamination or low level radioactivity measurements; to maintain the quality assurance system according to the ISO17025 standard for which we obtained the Beltest accreditation in 1998; to assess the internal dose from occupational intakes of radionuclides for workers of the nuclear industry;

Framework for assessing the effects of radioactive materials transportation

International Nuclear Information System (INIS)

Zoller, J.N.

1996-01-01

Radioactive materials transport may result in environmental effects during both incident-free and accident conditions. These effects may be caused by radiation exposure, pollutants, or physical trauma. Recent environmental impact analyses involving the transportation of radioactive materials are cited to provide examples of the types of activities which may be involved as well as the environmental effects which can be estimated

Radioactivity measurements of soil samples from Raichur of Karnataka, India

International Nuclear Information System (INIS)

Rajesh, S.; Kerur, B.R.; Anilkumar, S.

2016-01-01

Radiations present in environment comprise the terrestrial and extraterrestrial radiations. Natural radioactivity measurement, radiation monitoring of the region, dose assessment and interpretation of radiological related parameters are crucial aspects from the public awareness and environmental safety point of view. It is found that values of the radiological parameters obtained for samples in the study area were found within acceptable or permissible limits. The estimated gamma absorbed dose rate was found to be in the range 32 - 162 nGy h -1 . Higher dose rate than that of the normal dose rate were observed in the regions where granitic, granitic gneiss and schist outcrops were prominent area

Radioactive and Other Effects of Nuclear Explosion

International Nuclear Information System (INIS)

Ilijas, B.; Cizmek, A.; Prah, M.; Medakovic, S.

2008-01-01

As a result of long lasting efforts of international community to definitely ban all test nuclear explosions, the Comprehensive Nuclear-Test-Ban Treaty (CTBT) was opened for signature in New York on 24 September 1996, when it was signed by 71 states, including Croatia. The State Office for Nuclear Safety (SONS) which, as an independent state regulatory authority has a responsibility for activities relating to nuclear safety, including the national authority over this Treaty, is actively engaged in CTBTO activities. The nuclear explosion causes a lot of effects (blast, thermal, radioactive, electromagnetic) which differs a lot in its nature, reach, lasting and other. The longest lasting aftermath is from the radioactive effects that cause a radioactive fallout and a lot of radioactive elements in the environment, created by the influence of a primary beam of radiation. Fission and fusion are the main source of radionuclide created by the nuclear explosion, and the longest lasting aftermaths are by the fission products, namely their offspring in natural disintegration chains. This can make contaminated areas inappropriate for life for very long periods. Even in the case of underground nuclear explosion (when underground cavity is formed with no effects on the surface), a leakage of radioactive gases through cracks is possible. A number of radionuclide is created by the neutron activation of elements naturally present in an environment, because a very strong neutron radiation appears in the moment of nuclear explosion. The abundance of particular radionuclide is a very much dependent of a place of performing nuclear explosion and a composition of soil or water in the vicinity.(author)

Natural radioactivity in various water samples and radiation dose estimations in Bolu province, Turkey.

Science.gov (United States)

Gorur, F Korkmaz; Camgoz, H

2014-10-01

The level of natural radioactivity for Bolu province of north-western Turkey was assessed in this study. There is no information about radioactivity measurement reported in water samples in the Bolu province so far. For this reason, gross α and β activities of 55 different water samples collected from tap, spring, mineral, river and lake waters in Bolu were determined. The mean activity concentrations were 68.11 mBq L(-1), 169.44 mBq L(-1) for gross α and β in tap water. For all samples the gross β activity is always higher than the gross α activity. All value of the gross α were lower than the limit value of 500 mBq L(-1) while two spring and one mineral water samples were found to have gross β activity concentrations of greater than 1000 mBq L(-1). The associated age-dependent dose from all water ingestion in Bolu was estimated. The total dose for adults had an average value exceeds the WHO recommended limit value. The risk levels from the direct ingestion of the natural radionuclides in tap and mineral water in Bolu were determinated. The mean (210)Po and (228)Ra risk the value of tap and mineral waters slightly exceeds what some consider on acceptable risk of 10(-4) or less. Copyright © 2014 Elsevier Ltd. All rights reserved.

Research on atmospheric radioactivity. [In French

Energy Technology Data Exchange (ETDEWEB)

Garrigue, H

1954-01-01

In flight at 2800 m, traces of radioactive particles were gathered, by means of a corona effect similar to that of Sella, and of long period, on April 24, 1954. At Puy-de-Dome (1465 m) after a fall of rain and snow on May 3 to 4, 1954, samples of the fallen residue showed very feeble radioactivity of period 10 days or more. This radioactivity of the airborne particles was independent of their probable natural electrical charge and mobility and was indicative of an atomic cloud.

Simultaneous sampling of indoor and outdoor airborne radioactivity after the Fukushima Daiichi nuclear power plant accident.

Science.gov (United States)

Ishikawa, Tetsuo; Sorimachi, Atsuyuki; Arae, Hideki; Sahoo, Sarata Kumar; Janik, Miroslaw; Hosoda, Masahiro; Tokonami, Shinji

2014-02-18

Several studies have estimated inhalation doses for the public because of the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident. Most of them were based on measurement of radioactivity in outdoor air and included the assumption that people stayed outdoors all day. Although this assumption gives a conservative estimate, it is not realistic. The "air decontamination factor" (ratio of indoor to outdoor air radionuclide concentrations) was estimated from simultaneous sampling of radioactivity in both inside and outside air of one building. The building was a workplace and located at the National Institute of Radiological Sciences (NIRS) in Chiba Prefecture, Japan. Aerosol-associated radioactive materials in air were collected onto filters, and the filters were analyzed by γ spectrometry at NIRS. The filter sampling was started on March 15, 2011 and was continued for more than 1 year. Several radionuclides, such as (131)I, (134)Cs, and (137)Cs were found by measuring the filters with a germanium detector. The air decontamination factor was around 0.64 for particulate (131)I and 0.58 for (137)Cs. These values could give implications for the ratio of indoor to outdoor radionuclide concentrations after the FDNPP accident for a similar type of building.

Fossil fuel produced radioactivities and their effect on foodchains

Energy Technology Data Exchange (ETDEWEB)

Okamoto, K [New South Wales Univ., Kensington (Australia). Dept. of Applied Mathematics

1980-10-01

The environmental impact of radioactivities produced from fossil fuel burning is not necessarily small compared with that of nuclear energy. The effect of these radioactivities on the foodchain through seafoods is discussed.

Equipment and techniques for remote sampling of stored radioactive waste

International Nuclear Information System (INIS)

Nance, T.A.

1996-01-01

Several tools have been developed at the Savannah River Site (SRS) to remotely sample stored radioactive waste. These sampling tools have been developed to determine the chemical characteristics of the waste prior to processing. The processing of waste material varies according to the chemical characteristics of the waste, which change due to additions, settling, mixing, and chemical reactions during storage. Once the waste has been sampled to identify its characteristics, the chemical composition of the waste can then be altered if needed to prepare for processing. Various types of waste material in several types of containment must be sampled at SRS. Stored waste materials consist of liquids, floating organics, sludge, salt and solids. Waste is stored in four basic types of tanks with different means of access and interior obstructions. The waste tanks can only be accessed by small openings: access ports, risers and downcomers. Requirements for sampling depend on the type of tank being accessed, the waste within the tank, and the particular location in the tank desired for taking the sample. Sampling devices have been developed to sample all of the waste material forms found in the SRS tank farms. The fluid type samplers are capable of sampling surface liquid, subsurface liquid at varying depth, surface sludge, subsurface sludge, and floating organics. The solid type samplers are capable of sampling salt, sampling a solid layer on the bottom of the tank, and capturing a small solid mass on the tank bottom. The sampling devices are all designed to access the tanks through small access ports. The samplers are reusable and are designed to allow quick transfer of the samples to shielded packaging for transport, reducing the amount of radiation exposure to sampling personnel. The samplers weigh less than 100 lb. and are designed in sections to allow easy disassembly for storage and transport by personnel. (Abstract Truncated)

Investigation of radioactivities on the wood samples taken from a fishing boat, the 5th Sumiyoshimaru

International Nuclear Information System (INIS)

Shizuma, Kiyoshi; Iwatani, Kazuo; Hasai, Hiromi

1991-01-01

Radioactivity survey has been performed on samples taken from a fishing boat, the 5th Sumiyoshimaru. This boat has been presumed to be exposed to the fallout of Bikini hydrogen bomb test. Gamma-ray measurements have been carried out for six wood samples and two soil samples. Since the 137 Cs concentration estimated for all samples were comparable to the fallout of the nuclear test, it was hard to judge whether the boat was definitely exposed to the Bikini fallout. (author)

Investigation of radioactivities on the wood samples taken from a fishing boat, the 5th Sumiyoshimaru

Energy Technology Data Exchange (ETDEWEB)

Shizuma, Kiyoshi; Iwatani, Kazuo; Hasai, Hiromi (Hiroshima Univ., Higashi-Hiroshima (Japan). Faculty of Engineering)

1991-03-01

Radioactivity survey has been performed on samples taken from a fishing boat, the 5th Sumiyoshimaru. This boat has been presumed to be exposed to the fallout of Bikini hydrogen bomb test. Gamma-ray measurements have been carried out for six wood samples and two soil samples. Since the {sup 137}Cs concentration estimated for all samples were comparable to the fallout of the nuclear test, it was hard to judge whether the boat was definitely exposed to the Bikini fallout. (author).

Monitoring of gross beta radioactivities on water sample environment in the surrounding of kartini reactor at 2011

International Nuclear Information System (INIS)

Siswanti; Munandar, A. Aris

2013-01-01

Measurement of gross beta radioactivities on water environment were done in the PTAPB BATAN has a goal for routine monitoring, with the result that fill RPL has been made and the result equivalented with quality standard were decided by BAPETEN. The water sample taken as much as 2 liter at 18 area were definited on radius 100 m to 5000 m in the surrounding of kartini reactor, vaporin on electric stove till the volume been ± 10 ml, and than pick out to the aluminium planset and drying on hot plate. Sample in the plancet were counted with a Low Background Counter (LBC) for 30 minutes and accounted of gross beta radioactivity water system. The result of gross beta radioactivity water environment at 2011 has a lowest 009, ± 0,06 Bq/I on Tambak Bayan area at june and in the Janti area highest 0,39 ± 0,08 Bq/ at December. The result still under of quality standard were decided by SK BAPETEN. No. 02/Ka- BAPETEN/V-99 is 0,4 Bq/I. (author)

Novel system using microliter order sample volume for measuring arterial radioactivity concentrations in whole blood and plasma for mouse PET dynamic study.

Science.gov (United States)

Kimura, Yuichi; Seki, Chie; Hashizume, Nobuya; Yamada, Takashi; Wakizaka, Hidekatsu; Nishimoto, Takahiro; Hatano, Kentaro; Kitamura, Keishi; Toyama, Hiroshi; Kanno, Iwao

2013-11-21

This study aimed to develop a new system, named CD-Well, for mouse PET dynamic study. CD-Well allows the determination of time-activity curves (TACs) for arterial whole blood and plasma using 2-3 µL of blood per sample; the minute sample size is ideal for studies in small animals. The system has the following merits: (1) measures volume and radioactivity of whole blood and plasma separately; (2) allows measurements at 10 s intervals to capture initial rapid changes in the TAC; and (3) is compact and easy to handle, minimizes blood loss from sampling, and delay and dispersion of the TAC. CD-Well has 36 U-shaped channels. A drop of blood is sampled into the opening of the channel and stored there. After serial sampling is completed, CD-Well is centrifuged and scanned using a flatbed scanner to define the regions of plasma and blood cells. The length measured is converted to volume because the channels have a precise and uniform cross section. Then, CD-Well is exposed to an imaging plate to measure radioactivity. Finally, radioactivity concentrations are computed. We evaluated the performance of CD-Well in in vitro measurement and in vivo (18)F-fluorodeoxyglucose and [(11)C]2-carbomethoxy-3β-(4-fluorophenyl) tropane studies. In in vitro evaluation, per cent differences (mean±SE) from manual measurement were 4.4±3.6% for whole blood and 4.0±3.5% for plasma across the typical range of radioactivity measured in mouse dynamic study. In in vivo studies, reasonable TACs were obtained. The peaks were captured well, and the time courses coincided well with the TAC derived from PET imaging of the heart chamber. The total blood loss was less than 200 µL, which had no physiological effect on the mice. CD-Well demonstrates satisfactory performance, and is useful for mouse PET dynamic study.

Optimum method to determine radioactivity in large tracts of land. In-situ gamma spectroscopy or sampling followed by laboratory measurement

International Nuclear Information System (INIS)

Bronson, Frazier

2008-01-01

In the process of decommissioning contaminated facilities, and in the conduct of normal operations involving radioactive material, it is frequently required to show that large areas of land are not contaminated, or if contaminated that the amount is below an acceptable level. However, it is quite rare for the radioactivity in the soil to be uniformly distributed. Rather it is generally in a few isolated and probably unknown locations. One way to ascertain the status of the land concentration is to take soil samples for subsequent measurement in the laboratory. Another way is to use in-situ gamma spectroscopy. In both cases, the non-uniform distribution of radioactivity can greatly compromise the accuracy of the assay, and makes uncertainty estimates much more complicated than simple propagation of counting statistics. This paper examines the process of determining the best way to estimate the activity on the tract of land, and gives quantitative estimates of measurement uncertainty for various conditions of radioactivity. When the distribution of radioactivity in the soil is not homogeneous, the sampling uncertainty is likely to be larger than the in-situ measurement uncertainty. (author)

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.

Relocation of radioactive residuals store: environment effects statement

International Nuclear Information System (INIS)

1984-11-01

This Environment Effects Statement describes and assesses the likely environmental effects of the proposal to relocate the Health Commission's existing radioactive residuals store to a site within the established Dutson Downs waste disposal area, located 20 km south-east of Sale and 225 km east of Melbourne. The information presented demonstrates that the siting and construction of the proposed radioactive residuals store and the procedures to be adopted for the handling and storage of materials will not present an unacceptable risk to public health and safety, nor will it involve any significant adverse environmental effects

Apparatus for measuring the nuclear radiation of a sequence of radioactive samples

International Nuclear Information System (INIS)

Lohr, W.; Berthold, F.; Allington, R.W.

1977-01-01

To measure the nuclear radiation of a sequence of radioactive samples, magazines that hold sample containers are removably positioned in shuttles, some of which are driven step-by-step by a toothed belt that engates racks on the sides of the shuttles from one compartment to another through a measuring station, with the shuttles that are being driven by the belt driving other shuttles not in engagement with the belt at that time. In the measuring station, the sample containers are released from the magazines one at a time through openings in their bottoms and lowered by a reciprocable support to a position adjacent to a radiation detector for the measurement, after which they are raised by the support to the magazine and the shuttle is driven one more step to the next position. 8 figures

Contents and Sample Arguments of a Safety Case for Near Surface Disposal of Radioactive Waste

International Nuclear Information System (INIS)

2017-06-01

This publication arises from the results of two projects to assist Member States in understanding and developing safety cases for near-surface radioactive waste disposal facilities. The objective of the publication is to give detailed information on the contents of safety cases for radioactive waste disposal and the types of arguments that may be included. It is written for technical experts preparing a safety case, and decision makers in the regulatory body and government. The publication outlines the key uses and aspects of the safety case, its evolution in parallel with that of the disposal facility, the key decision steps in the development of the waste disposal facility, the components of the safety case, their place in the Matrix of Arguments for a Safety Case (the MASC matrix), and a detailed description of the development of sample arguments that might be included in a safety case for each of two hypothetical radioactive waste disposal facilities.

Evaluation of induced radioactivity in 10 MeV-electron irradiated spices, (1); [gamma]-ray measurement

Energy Technology Data Exchange (ETDEWEB)

Furuta, Masakazu; Katayama, Tadashi; Ito, Norio; Mizohata, Akira; Matsunami, Tadao; Shibata, Setsuko; Toratani, Hirokazu (Osaka Prefectural Univ., Sakai (Japan). Research Inst. for Advanced Science and Technology); Takeda, Atsuhiko

1994-02-01

Black pepper, white pepper, red pepper, ginger and turmeric were irradiated with 10 MeV electrons from a linear accelerator to a dose of 100 kGy and radioactivity was measured in order to estimate induced radioactivity in the irradiated foods. Induced radioactivity could not be detected significantly by [gamma]-ray spectrometry in the irradiated samples except for spiked samples which contain some photonuclear target nuclides in the list of photonuclear reactions which could produce radioactivity below 10 MeV. From the amount of observed radioactivities of short-lived photonuclear products in the spiked samples and calculation of H[sub 50] according to ICRP Publication 30, it was concluded that the induced radioactivity and its biological effects in the 10 MeV electron-irradiated natural samples were negligible in comparison with natural radioactivity from [sup 40]K contained in the samples. (author).

Rapid Pneumatic Transport of Radioactive Samples - RaPToRS

Science.gov (United States)

Padalino, S.; Barrios, M.; Sangster, C.

2005-10-01

Some ICF neutron activation diagnostics require quick retrieval of the activated sample. Minimizing retrieval times is particularly important when the half-life of the activated material is on the order of the transport time or the degree of radioactivity is close to the background counting level. These restrictions exist in current experiments performed at the Laboratory for Laser Energetics, thus motivating the development of the RaPToRS system. The system has been designed to minimize transportation time while requiring no human intervention during transport or counting. These factors will be important if the system is to be used at the NIF where radiological hazards will be present during post activation. The sample carrier is pneumatically transported via a 4 inch ID PVC pipe to a remote location in excess of 100 meters from the activation site at a speed of approximately 7 m/s. It arrives at an end station where it is dismounted robotically from the carrier and removed from its hermetic package. The sample is then placed by the robot in a counting station. This system is currently being developed to measure back-to-back gamma rays produced by positron annihilation which were emitted by activated graphite. Funded in part by the U.S. DOE under sub contract with LLE at the University of Rochester.

ICP/AES radioactive sample analyses at Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Matsuzaki, C.L.; Hara, F.T.

1986-03-01

Inductively coupled argon plasma atomic emission spectroscopy (ICP/AES) analyses of radioactive materials at Pacific Northwest Laboratory (PNL) began about three years ago upon completion of the installation of a modified Applied Research Laboratory (ARL) 3560. Funding for the purchase and installation of the ICP/AES was provided by the Nuclear Waste Materials Characterization Center (MCC) established at PNL by the Department of Energy in 1979. MCC's objective is to ensure that qualified materials data are available on waste materials. This paper is divided into the following topics: (1) Instrument selection considerations; (2) initial installation of the simultaneous system with the source stand enclosed in a 1/2'' lead-shielded glove box; (3) retrofit installation of the sequential spectrometer; and (4) a brief discussion on several types of samples analyzed. 1 ref., 7 figs., 1 tab

Radioactive fallout has different effects in Lapland

International Nuclear Information System (INIS)

Rissanen, K.

1993-01-01

The effects of radioactive fallout in Lapland differ from those in southern Finland. The subarctic area is poor in vegetation and nutrients, for which reason radioactive substances enter food chains rapidly. As potassium is low in supply in the north, plants use cesium to replace it. Thus cesium is accumulated very effectively in food chain. When in the food chain, cesium is enriched in reindeer and further in Lapp people, who eat reindeer meat frequently. The Finnish Centre for Radiation and Nuclear Safety established a regional laboratory in northern Finland in the 1970's to monitor radiation and carry out research an the area.(author)

Automated injection of a radioactive sample for preparative HPLC with feedback control

International Nuclear Information System (INIS)

Iwata, Ren; Yamazaki, Shigeki

1990-01-01

The injection of a radioactive reaction mixture into a preparative HPLC column has been automated with computer control for rapid purification of routinely prepared positron emitting radiopharmaceuticals. Using pneumatic valves, a motor-driven pump and a liquid level sensor, two intelligent injection methods for the automation were compared with regard to efficient and rapid sample loading into a 2 mL loop of the 6-way valve. One, a precise but rather slow method, was demonstrated to be suitable for purification of 18 F-radiopharmaceuticals, while the other, due to its rapid operation, was more suitable for 11 C-radiopharmaceuticals. A sample volume of approx 0.5 mL can be injected onto a preparative HPLC column with over 90% efficiency with the present automated system. (author)

Monitoring of the level of radioactivity in different environmental samples within the Slovak Republic, the committed effective doses resulting from the ingestion of different age groups from the public

International Nuclear Information System (INIS)

Durecova, A.; Dubnickova, M.; Cipakova, A.; Missik, J.

2014-01-01

The Slovak Republic has established the facilities necessary to carry out continuous monitoring of the level of radioactivity in the air, water, foodstuffs and soil and to ensure compliance with the basic standards as a member state of the European Union. Data from the monitoring are periodically published, evaluated and sent to the REM database of the European Community. Radioactive contamination of the Slovak Republic following the Chernobyl nuclear accident has raised public concern about food safety. Many people are wondering whether the domestic food samples are safe to eat even 28 years after the accident.Based on monitoring data reported during period 2004 - 2013, 137 Cs and 90 Sr concentrations in fresh cow and sheep milk, whole diet, wild mushrooms, wild boar meat are evaluated. Resulting committed effective doses from annual consumption for the different age group and different foodstuffs are calculated. (authors)

Apparatus and method for radioactive waste screening

Science.gov (United States)

Akers, Douglas W.; Roybal, Lyle G.; Salomon, Hopi; Williams, Charles Leroy

2012-09-04

An apparatus and method relating to screening radioactive waste are disclosed for ensuring that at least one calculated parameter for the measurement data of a sample falls within a range between an upper limit and a lower limit prior to the sample being packaged for disposal. The apparatus includes a radiation detector configured for detecting radioactivity and radionuclide content of the of the sample of radioactive waste and generating measurement data in response thereto, and a collimator including at least one aperture to direct a field of view of the radiation detector. The method includes measuring a radioactive content of a sample, and calculating one or more parameters from the radioactive content of the sample.

A laboratory activity for teaching natural radioactivity

Science.gov (United States)

Pilakouta, M.; Savidou, A.; Vasileiadou, S.

2017-01-01

This paper presents an educational approach for teaching natural radioactivity using commercial granite samples. A laboratory activity focusing on the topic of natural radioactivity is designed to develop the knowledge and understanding of undergraduate university students on the topic of radioactivity, to appreciate the importance of environmental radioactivity and familiarize them with the basic technology used in radioactivity measurements. The laboratory activity is divided into three parts: (i) measurements of the count rate with a Geiger-Muller counter of some granite samples and the ambient background radiation rate, (ii) measurement of one of the samples using gamma ray spectrometry with a NaI detector and identification of the radioactive elements of the sample, (iii) using already recorded 24 h gamma ray spectra of the samples from the first part (from the Granite Gamma-Ray Spectrum Library (GGRSL) of our laboratory) and analyzing selected peaks in the spectrum, students estimate the contribution of each radioactive element to the total specific activity of each sample. A brief description of the activity as well as some results and their interpretation are presented.

Contamination of the air and other environmental samples of the Ulm region by radioactive fission products after the accident of the Chernobyl reactor

International Nuclear Information System (INIS)

Krivan, V.; Egger, K.P.; Hausbeck, R.; Schmid, W.

1986-01-01

Since April 30, 1986, the radioactivity of the fission products released by the accident of the Chernobyl reactor has been measured in the air of the city of Ulm. The airborne dust samples were collected with flow calibrated samplers on cellulose acetate membrane filters and counted with a high resolution gamma ray spectrometer. Later on, the radioactivity measurements were expanded to other relevant environmental samples contaminated by radioactive atmospheric precipitates including grass, spruce needles, mosses, lichens, various kinds of food, drinking water, asphalt and concrete surface layers, municipal sewage sludge and sewage sludge ash. This paper reports the obtained results. (orig.) [de

Setting up experimental incineration system for low-level radioactive samples and combustion experiments

International Nuclear Information System (INIS)

Yumoto, Yasuhiro; Hanafusa, Tadashi; Nagamatsu, Tomohiro; Okada, Shigeru

1997-01-01

An incineration system was constructed which were composed of a combustion furnace (AP-150R), a cyclone dust collector, radioisotope trapping and measurement apparatus and a radioisotope storage room built in the first basement of the Radioisotope Center. Low level radioactive samples (LLRS) used for the combustion experiment were composed of combustible material or semi-combustible material containing 500 kBq of 99m TcO 4 or 23.25 kBq of 131 INa. The distribution of radioisotopes both in the inside and outside of combustion furnace were estimated. We measured radioactivity of a smoke duct gas in terminal exit of the exhaust port. In case of combustion of LLRS containing 99m TcO 4 or 131 INa, concentration of radioisotopes at the exhaust port showed less than legal concentration limit of these radioisotopes. In cases of combustion of LLRS containing 99m TcO 4 or 131 INa, decontamination factors of the incineration system were 120 and 1.1, respectively. (author)

Natural Radioactivity in Geological Samples from Algeria by SSNTD and γ-Ray Spectrometry

International Nuclear Information System (INIS)

Belafrites, A.

2009-01-01

Results of Solid State Nuclear Track Detector (SSNTD) measurements of natural radioactivity using contact autoradiography for the determination of uranium and non-contact autoradiography for radon emanation are presented. The study is complemented by gamma -ray spectrometric results. The SSNTD method applied to geological samples has given uranium concentrations consistent with those found by gamma -ray spectrometry. The results for uranium concentration and radon emanation show excellent agreement with the few values available in other works

Characteristics of a new fully programmable blood sampling device for monitoring blood radioactivity during PET

International Nuclear Information System (INIS)

Boellaard, R.; Lingen, A. van; Balen, S.C.M. van; Hoving, B.G.; Lammertsma, A.A.

2001-01-01

The first performance tests of a new fully programmable blood sampling device for monitoring blood radioactivity during positron emission tomography (PET) are described. Blood is withdrawn through 1-mm internal diameter tubing using an infusion pump which can be operated at rates varying from 0 to 600 ml/h. Activity in blood is measured by a 6-cm-thick bismuth germanate crystal connected to a photomultiplier tube and multichannel analyser (MCA) which are positioned within 6 cm lead shielding. Positioning of the tubing is an exact and simple procedure. The minimal readout time of the MCA is 1 s. Two independent energy windows can be set. Operation of the pump and MCA is fully controlled by a PC, i.e. sampling time, interval time and pump rate can be varied at any time during the PET scan by user-defined scripts. A number of characteristics of the new system were studied, such as sensitivity, dead time, linearity, effect of background radiation and pump rate as a function of input pressure. In addition, dispersion was measured as a function of pump rate. Finally, first clinical results were compared with manual samples. The sensitivity equalled 0.7 and 0.2 cps/Bq for 511- and 1022-keV 30% energy windows, respectively, and the system dead time was 500 ns. The system remained linear within 2% with activity concentrations up to 2.5 MBq/cc. Short-term reproducibility was better than 3% for a 1-h period. Long-term reproducibility was about 5% (1SD), which was mainly caused by variation in the diameter of the tubing. If the device was positioned in such a way that maximum shielding was directed towards the patient, the effects of background radiation from the patient on the measured activity concentration for clinically relevant conditions was minimal ( -1 were observed for pump rates higher than 300 ml/h, indicating that the system dispersion is small. Clinical data showed an excellent agreement to within 3% (1SD) between the results obtained with the new system and

A review of airborne particle sampling with special reference to long-lived radioactive dust

International Nuclear Information System (INIS)

Bigu, J.

1990-03-01

This report reviews some basic aspects related to the sampling of airborne particles with special reference to Long-Lived Radioactive Dust (LLRD). The report covers a number of areas of practical interest such as the production of aerosols, the dynamics of suspended particles, the physical and chemical characteristics and properties of dust clouds, and the inhalation and measurement of dust. It is followed with a brief review of dust sampling instrumentation, and with a short account of the work done on LLRD in Canada with a few references to work done outside this country. (34 figs., 7 tabs., 117 refs.)

Multi-Sampling Ionization Chamber (MUSIC) for measurements of fusion reactions with radioactive beams

International Nuclear Information System (INIS)

Carnelli, P.F.F.; Almaraz-Calderon, S.; Rehm, K.E.; Albers, M.; Alcorta, M.; Bertone, P.F.; Digiovine, B.; Esbensen, H.; Fernández Niello, J.; Henderson, D.; Jiang, C.L.; Lai, J.; Marley, S.T.; Nusair, O.; Palchan-Hazan, T.; Pardo, R.C.; Paul, M.; Ugalde, C.

2015-01-01

A detection technique for high-efficiency measurements of fusion reactions with low-intensity radioactive beams was developed. The technique is based on a Multi-Sampling Ionization Chamber (MUSIC) operating as an active target and detection system, where the ionization gas acts as both target and counting gas. In this way, we can sample an excitation function in an energy range determined by the gas pressure, without changing the beam energy. The detector provides internal normalization to the incident beam and drastically reduces the measuring time. In a first experiment we tested the performance of the technique by measuring the 10,13,15 C+ 12 C fusion reactions at energies around the Coulomb barrier

Multi-Sampling Ionization Chamber (MUSIC) for measurements of fusion reactions with radioactive beams

Energy Technology Data Exchange (ETDEWEB)

Carnelli, P.F.F. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States); Laboratorio TANDAR, Comisión Nacional de Energía Atómica, Av. Gral. Paz 1499, B1650KNA, San Martín, Buenos Aires (Argentina); Consejo Nacional de Investigaciones Científicas y Técnicas, Av. Rivadavia 1917, C1033AAJ Buenos Aires (Argentina); Almaraz-Calderon, S. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States); Rehm, K.E., E-mail: rehm@anl.gov [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States); Albers, M.; Alcorta, M.; Bertone, P.F.; Digiovine, B.; Esbensen, H. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States); Fernández Niello, J. [Laboratorio TANDAR, Comisión Nacional de Energía Atómica, Av. Gral. Paz 1499, B1650KNA, San Martín, Buenos Aires (Argentina); Universidad Nacional de San Martín, Campus Miguelete, B1650BWA San Martín, Buenos Aires (Argentina); Henderson, D.; Jiang, C.L. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States); Lai, J. [Department of Physics and Astronomy, Louisiana State University, Baton Rouge, LA 70803 (United States); Marley, S.T.; Nusair, O.; Palchan-Hazan, T.; Pardo, R.C. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States); Paul, M. [Racah Institute of Physics, Hebrew University, Jerusalem (Israel); Ugalde, C. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States)

2015-11-01

A detection technique for high-efficiency measurements of fusion reactions with low-intensity radioactive beams was developed. The technique is based on a Multi-Sampling Ionization Chamber (MUSIC) operating as an active target and detection system, where the ionization gas acts as both target and counting gas. In this way, we can sample an excitation function in an energy range determined by the gas pressure, without changing the beam energy. The detector provides internal normalization to the incident beam and drastically reduces the measuring time. In a first experiment we tested the performance of the technique by measuring the {sup 10,13,15}C+{sup 12}C fusion reactions at energies around the Coulomb barrier.

Radioactivity in the ocean: laws and biological effects

Energy Technology Data Exchange (ETDEWEB)

Hunsaker, C.T.

1985-01-01

This paper summarizes the literature on US laws and international agreements, experimental and monitoring data, and ongoing studies to provide background information for environmental assessment and regulatory compliance activities for ocean dumping of low-level radioactive waste. The Marine Protection, Research, and Sanctuaries Act is the major US legislation governing ocean disposal of radioactive waste. The major international agreement on ocean dumping is the Convention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter. The United States ended its ocean dumping of radioactive wastes in 1970, but other countries have continued ocean dumping under international supervision in the northeast Atlantic. Monitoring of former US disposal sites has neither revealed significant effects on marine biota nor indicated a hazard to human health. Also, no effects on marine organisms have been found that could be attributed to routine discharges into the Irish Sea from the Windscale reprocessing plant. We must improve our ability to predict the oceanic carrying capacity and the fate and effects of ionizing radiation in the marine environment.

Radioactivity in the ocean: laws and biological effects

International Nuclear Information System (INIS)

Hunsaker, C.T.

1985-01-01

This paper summarizes the literature on US laws and international agreements, experimental and monitoring data, and ongoing studies to provide background information for environmental assessment and regulatory compliance activities for ocean dumping of low-level radioactive waste. The Marine Protection, Research, and Sanctuaries Act is the major US legislation governing ocean disposal of radioactive waste. The major international agreement on ocean dumping is the Convention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter. The United States ended its ocean dumping of radioactive wastes in 1970, but other countries have continued ocean dumping under international supervision in the northeast Atlantic. Monitoring of former US disposal sites has neither revealed significant effects on marine biota nor indicated a hazard to human health. Also, no effects on marine organisms have been found that could be attributed to routine discharges into the Irish Sea from the Windscale reprocessing plant. We must improve our ability to predict the oceanic carrying capacity and the fate and effects of ionizing radiation in the marine environment

Induced radioactivity in LDEF components

Science.gov (United States)

Harmon, B. A.; Fishman, G. J.; Parnell, T. A.; Laird, C. E.

1992-01-01

A systematic study of the induced radioactivity of the Long Duration Exposure Facility (LDEF) is being carried out in order to gather information about the low earth orbit radiation environment and its effects on materials. The large mass of the LDEF spacecraft, its stabilized configuration, and long mission duration have presented an opportunity to determine space radiation-induced radioactivities with a precision not possible before. Data presented include preliminary activities for steel and aluminum structural samples, and activation subexperiment foils. Effects seen in the data show a clear indication of the trapped proton anisotropy in the South Atlantic Anomaly and suggest contributions from different sources of external radiation fluxes.

Mobility of radioactive colloidal particles in groundwater

International Nuclear Information System (INIS)

Nuttall, H.E.; Long, R.L.

1993-01-01

Radiocolloids are a major factor in the rapid migration of radioactive waste in groundwater. For at least two Los Alamos National Laboratory (LANL) sites, researchers have shown that groundwater colloidal particles were responsible for the rapid transport of radioactive waste material in groundwater. On an international scale, a review of reported field observations, laboratory column studies, and carefully collected field samples provides compelling evidence that colloidal particles enhance both radioactive and toxic waste migration. The objective of this project is to understand and predict colloid-contaminant migration through fundamental mathematical models, water sampling, and laboratory experiments and use this information to develop an effective and scientifically based colloid immobilization strategy. The article focuses on solving the suspected radiocolloid transport problems at LANL's Mortandad Canyon site. (author) 6 figs., 5 tabs., 18 refs

Studies of the effect of radioactive waste on the transport phenomena in soil

International Nuclear Information System (INIS)

El-Reefy, A.I.A.F

1992-01-01

This thesis introduces a new concept in the field of soil mechanics. It is an integrated work between soil and radiation in the form of gamma-rays. Chapter II was introduced to cover the basics in geotechnical engineering so as to draw a clearer picture to radiologists. Similarly, Chapter III was introduced to enable geotechnical engineers to comprehend radioactive behaviour in general. Although these two chapters are for further reading they contain various points that will be referred to regularly in the latter pages. The aim of this work is to investigate: - The effect of γ -radiations on the transport phenomena in soil. This was carried out by studying the effect of the following factors on the transmission of γ -rays with different energies: 1) Soil sample thickness 2) Grain size 3)Water content 4) Degree of compaction. - The effect of γ -radiations on moisture movement through soil. -Using the -ray transmission method to determine the soil physical properties. - Improvement of soil to increase its ability to attenuate -radiations. Experimental work took place under strict conditions at the Hot Lab. Center located at Inchas. Soil sample was sought from a nearby site which eventually will be the actual radioactive disposal site. The physical properties of the soil sample were determined as well as its grain size distribution. Accurate and detailed data on the gamma rays transport phenomena in soils was obtained using an up to date γ -radiation measurement technique. Finally, the extensive data obtained throughout this research was recorded and analyzed to ultimately approach our aim

Radioactive contamination in imported foods

International Nuclear Information System (INIS)

Kan, Kimiko; Maki, Toshio; Nagayama, Toshihiro; Hashimoto, Hideki; Kawai, Yuka; Kobayashi, Maki; Shioda, Hiroko; Nishima, Taichiro

1990-01-01

On April 26, 1986, explosion occurred in Chernobyl nuclear power station in USSR, and radioactivity contamination was brought about in almost all countries in the world. In European countries, crops were contaminated directly with radioactive fallout to high concentration. Also in Japan, after one week the radioactivity higher than usual was detected in environment, and also in vegetables, milk, tea leaves and others. Thereafter, in order to cope with the import of contaminated foods, inspection and watch system was strengthened by deciding the interim limit of radioactive concentration. However the cases of exceeding the interim limit were often reported. In order to remove the harmful foods due to radioactive contamination and to meet the fear of consumers, the authors measured the radioactive concentration in foods distributed in Tokyo and investigated the actual state of contamination. The samples were 920 imported foods. The experimental method, the preparation of samples, the method of analysis and the results are reported. The samples in which the radioactive concentration exceeding 50 Bq/kg was detected were 25 cases. The food having the high frequency of detection was flavors. (K.I.)

Radioactivities (dose rates) of rocks in Japan

International Nuclear Information System (INIS)

Matsuda, Hideharu; Minato, Susumu

1995-01-01

The radioactive distribution (radiation doses) of major rocks in Japan was monitored to clarify the factors influencing terrestrial gamma-ray absorbed dose rates. The rock samples were reduced to powder and analyzed by well-type NaI(Tl) scintillation detector and pulse height analyzer. Terrestrial gamma-ray dose rates were estimated in terms of gamma radiation dose rate 1 m above the ground. The radioactivity concentration was highest in acidic rock which contains much SiO 2 among igneous rock, followed by neutral rock, basic rock, and ultrabasic rock. The radioactive concentration was 30-40% lower in acidic and clastic rocks than those of the world average concentration. Higher radioactive concentration was observed in soils than the parent rocks of sedimentary rock and metamorphic rock. The gamma radiation dose rate was in proportion to the radioactive concentration of the rocks. To clarify the radioactive effect in the change course of rocks into soils, comparative measurement of outcrop and soil radioactive concentrations is important. (S.Y.)

Evaluation of induced radioactivity in 10 MeV-Electron irradiated spices, (2)

International Nuclear Information System (INIS)

Katayama, Tadashi; Furuta, Masakazu; Shibata, Setsuko; Matsunami, Tadao; Ito, Norio; Mizohata, Akira; Toratani, Hirokazu; Takeda, Atsuhiko.

1994-01-01

In order to check radioactivity of beta-emmitters produced by (γ, n) reactions which could occur at energies up to 10 MeV, black pepper, white pepper, red pepper, ginger and turmeric were irradiated with 10 MeV electron from a linear accelerator to a dose of 100 kGy. Beta-rays were counted using a 2π gas flow counter and a liquid scintillation counter. Any induced radioactivity could not be detected in irradiated samples. When inorganic compounds containing the nuclides in the list were artificially added in the samples and were irradiated, the β-activities were detected. From the amount of observed radioactivities of β-emmitters produced in the compounds as photonuclear products, it is concluded that the induced radioactivity in natural samples by 10 MeV-electron irradiation were far smaller than natural radioactivity from 40 K contained in the samples and, hence, its biological effects should be negligible. (author)

Measurement of Radioactivity in Some Croatian Regions

International Nuclear Information System (INIS)

Orehovec, Z.; Ilijas, B.; Bokan, S.

2001-01-01

Full text: After Government of Canada expressed its suspicion that Canadian soldiers who were included in UNPROFOR mission in Croatia were exposed to increased radioactivity and possible some chemical influences, a large action of measuring and sampling was undertaken. Canadian and Croatian experts were working together and a very large number of samples was collected. Measurements of alpha, beta and gamma radioactivity on terrain, as well as later analysis of samples showed no increased radioactivity or any other signs of radioactive contamination. The conclusion is that any possible diseases of Canadian soldiers can not originate from radiation or radioactive contamination in Croatia. (author)

Natural radioactivity in environmental samples from an island of volcanic origin (Milos, Aegean Sea)

International Nuclear Information System (INIS)

Florou, H.; Kritidis, P.

1991-01-01

Enhanced concentrations of natural radionuclides occur in volcanic islands such as Milos in the Aegean Sea. The natural gamma radiation status of the entire environment in Milos were studied using gamma radiometry. Gamma spectrometry was used to analyse ore samples, sediments and marine biota. While non-living materials showed enhanced levels of natural radioactivity, most of the marine organisms examined did not seem to reflect this radiological status. (UK)

A method of and apparatus for, monitoring the radioactivity of a plurality of samples incorporating lower energy beta-emitting isotopes

International Nuclear Information System (INIS)

Warner, G.T.; Potter, C.G.

1981-01-01

A method for monitoring the radioactivity of a number of samples incorporating low energy beta-emitting isotopes which allows the simultaneous precipitation of many samples with a minimum of sample handling, is described. The samples are placed on a support so that they are not overlapping, the support and sample are permeated with liquid or gel scintillant and the sample areas are scanned. (U.K.)

Non-radioactive stand-in for radioactive contamination. I. Non-radioactive tests

International Nuclear Information System (INIS)

Rohe, M.J.; Rankin, W.N.; Postles, R.L.

1985-01-01

Candidate non-radioactive materials for use as a stand-in for radioactive contamination during application of a high-pressure, hot water decontamination were identified and evaluated. A stand-in for radioactive contamination is needed to evaluate the decontaminability of replacement canyon cranes at the manufacturers location where actual radioactive contamination cannot be used. This evaluation was conducted using high-pressure, hot-water at 420 psi, 190 0 F, and 20 gal/min through a 1/8-in.-diam nozzle, the decontamination technique preferred by SRP Separations Department for this application. A non-radioactive stand-in for radioactive contamination was desired that would be removed by direct blast stream contact but would remain intact on surfaces where direct contact does not occur. This memorandum describes identification of candidate non-radioactive stand-in materials and evaluation of these materials in screening tests and tests with high-pressure, hot-water blasting. The following non-radioactive materials were tested: carpenter's line chalk; typing correction fluid; dye penetrant developer; latex paint with attapulyite added; unaltered latex paint; gold enamel; layout fluid; and black enamel. Results show that blue layout fluid and gold enamel have similar adherence that is within the range expected for actual radioactive contamination. White latex paint has less adherence than expected for actual radioactive contamination. The film was removed at a rate of 2 . Black enamel has more adherence than expected from actual radioactive contamination. In these tests ASTM No. 2B surfaces were harder to clean than either ASTM No. 1 or electropolished surfaces which had similar cleaning properties. A 90 0 blast angle was more effective than a 45 0 blast angle. In these tests there was no discernible effect of blast distance between 1 and 3 ft

Moessbauer Effect applications using intense radioactive ion beams

International Nuclear Information System (INIS)

Taylor, R.D.

1990-01-01

The Moessbauer Effect is reviewed as a promising tool for a number of new solid state studies when used in combination with radioactive beam/implantation facilities. The usual Moessbauer Effect involves long-lived radioactive parents (days to years) that populate low-lying nuclear excited states that subsequently decay to the ground state. Resonant emission/absorption of recoil-free gamma rays from these states provide information on a number of properties of the host materials. Radioactive ion beams (RIB) produced on-line allow new Moessbauer nuclei to be studied where there is no suitable parent. The technique allows useful sources to be made having extremely low local concentrations. The ability to separate the beams in both Z and A should provide high specific activity ''conventional'' sources, a feature important in some applications such as Moessbauer studies in diamond anvil high pressure cells. Exotic chemistry is proposed using RIB and certain Krypton and Xenon Moessbauer isotopes

Effective Regulatory Control of Radioactive Sources in Taiwan

International Nuclear Information System (INIS)

Liu, W.; Yuan, C.; Fan, S.; Su, S.

2004-01-01

Since the incident of radioactively contaminated buildings first surfaced in Taiwan in 1992, efforts have been made by AEC (Atomic Energy Council) of Taiwan to prevent recurrence of similar incidents involving radioactive materials and to achieve effective regulatory control over radioactive sources. The most important milestone is when AEC began to enforce IRPA he Ionizing Radiation Protection Act with the promulgation of 18 relevant regulations on Feb. 1, 2003. In order to enhance accountability of radioactive material and equipment capable of producing ionizing radiation, AEC develops and begins implementing a RPCS Radiation Protection Control System which is a powerful tool in controlling radiation safety and security. In addition, AEC develops a monthly registration program via internet, an o n-line reporting system f or owners/operators of radioactive sources, to improve monitoring of sealed sources (in-use and not-in-use). The registration requirement applies to 469 licensees possessing about 3,000 sealed sources in Taiwan. Because of the threat of orphan sources, AEC has made great efforts in preventing their contamination of construction steel material by establishing and enforcing the RPMMPIRCB Regulation for Preventive Measures and Management Plans for Incident of Radioactively Contaminated Buildings. To comply with this regulation, all 19 of Taiwan's steel factories with melting furnace have installed portal-type radiation detection system to monitor incoming scrap metal. (Author)

Derivation of residual radioactive material guidelines for uranium in soil at the Middlesex Sampling Plant Site, Middlesex, New Jersey

International Nuclear Information System (INIS)

Dunning, D.E.

1995-02-01

Residual radioactive material guidelines for uranium in soil were derived for the Middlesex Sampling Plant (MSP) site in Middlesex, New Jersey. This site has been designated for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy. The site became contaminated from operations conducted in support of the Manhattan Engineer District (MED) and the Atomic Energy Commission (AEC) between 1943 and 1967. Activities conducted at the site included sampling, storage, and shipment of uranium, thorium, and beryllium ores and residues. Uranium guidelines for single radioisotopes and total uranium were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual living or working in the immediate vicinity of the MSP site should not exceed a dose of 30 mrem/yr following remedial action for the current-use and likely future-use scenarios or a dose of 100 mrem/yr for less likely future-use scenarios. The RESRAD computer code, which implements the methodology described in the DOE manual for establishing residual radioactive material guidelines, was used in this evaluation. Four scenarios were considered for the site. These scenarios vary regarding future land use at the site, sources of water used, and sources of food consumed

Natural radioactivity and radiation hazards assessment of soil samples from the area of Tuzla and Lukavac, Bosnia and Herzegovina.

Science.gov (United States)

Kasumović, Amira; Adrović, Feriz; Kasić, Amela; Hankić, Ema

2015-01-01

The results of activity concentration measurements of natural occurring radioactive nuclides (238)U, (235)U, (232)Th, (226)Ra, and (40)K in surface soil samples collected in the area of cities Tuzla and Lukavac, northeast region of Bosnia and Herzegovina were presented. Soil sampling was conducted at the localities that are situated in the vicinity of industrial zones of these cities. The measured activity was in the range from (8 ± 4) to (95 ± 28) Bq kg(-1) for (238)U, from (0.41 ± 0.06) to (4.6 ± 0.7) Bq kg(-1) for (235)U, from (7 ± 1) to (66 ± 7) Bq kg(-1) for (232)Th, from (6 ± 1) to (55 ± 6) Bq kg(-1) for (226)Ra, and from (83 ± 12) to (546 ± 55) Bq kg(-1) for (40)K. In order to evaluate the radiological hazard of the natural radioactivity for people living near industrial zones, the absorbed dose rate, the annual effective dose and the radium equivalent activity have been calculated and compared with the internationally approved values.

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.

Decoding Environmental Processes Using Radioactive Isotopes for the Post-Radioactive Contamination Recovery Assessment

Science.gov (United States)

Yasumiishi, Misa; Nishimura, Taku; Osawa, Kazutoshi; Renschler, Chris

2017-04-01

The continual monitoring of environmental radioactive levels in Fukushima, Japan following the nuclear plant accident in March 2011 provides our society with valuable information in two ways. First, the collected data can be used as an indicator to assess the progress of decontamination efforts. Secondly, the collected data also can be used to understand the behavior of radioactive isotopes in the environment which leads to further understanding of the landform processes. These two aspects are inseparable for us to understand the effects of radioactive contamination in a dynamic environmental system. During the summer of 2016, 27 soil core samples were collected on a farmer's land (rice paddies and forest) in Fukushima, about 20 km northwest of the nuclear plant. Each core was divided into 2.0 - 3.0 cm slices for the Cs-134, Cs-137, and I-131 level measurement. The collected data is being analyzed from multiple perspectives: temporal, spatial, and geophysical. In the forest area, even on the same hillslope, multiple soil types and horizon depths were observed which indicates the challenges in assessing the subsurface radioactive isotope movements. It appears that although highly humic soils show higher or about the same level of radioactivity in the surface layers, as the depth increased, the radioactivity decreased more in those samples compared with more sandy soils. With regard to the direction a slope faces and the sampling altitudes, the correlation between those attributes and radioactivity levels is inconclusive at this moment. The altitude might have affected the fallout level on a single hillslope-basis. However, to determine the correlation, further sampling and the detailed analysis of vegetation and topography might be necessary. Where the surface soil was scraped and new soil was brought in, former rice paddy surface layers did show three-magnitude levels lower of radioactivity in the top layer when compared with forest soils. At the foot of forest

Arrangement to measure the nuclear radiation of a series of radioactive samples

International Nuclear Information System (INIS)

Lohr, W.; Berthold, F.; Allington, R.W.

1976-01-01

Samples to be counted for radioactivity are contained in vials placed in rows in magazins, and held in position by a grip. The magazins are positioned on a track, and automatically shifted in closed circuit, each at some stage reaching a working station. Here the magazin advances in discrete steps so that the bottom of each vial in turn is placed exactly above a small piston, the grip released, the piston lowered, and the vial slid down to a counting station. After counting the vial is returned to the magazine, gripped, and the magazine moves another step. (DVP) [de

Assessment of Natural Radioactivity and radiation hazards in beach sand samples from Kanyakumari District, TamilNadu

Science.gov (United States)

Ajithra, A. K.; Shanthi, G.

2016-07-01

Natural radionuclides of terrestrial origin have very long half - lives or driven from very long - lived parent radionuclides, which have been created in stellar processes before the earth formation. The study of natural radioactivity in marine and coastal environments is of significant importance for better understanding of oceanographic and sedimentological processes. The sampling sites are selected to cover randomly to cover the southern part. The soil samples have been collected in beach sides. In situ gamma measurements were conducted using a high-purity germanium (HPGe) detector (coaxial cylinder of 50.1 mm in diameter and 44 mm in length) with a relative efficiency of 50% and an energy resolution (FWHM) of 1.8 keV at the 1.33 MeV reference transition of 60Co. The measurements shows that the values of the absorbed dose rates in air in the investigated area are lower than the recommended limit by the United Nations Scientific Committee on the Effect of Atomic Radiation.

The control of water radioactivity

International Nuclear Information System (INIS)

Bovard, P.; Graubey, A.

1962-01-01

This report presents the different apparatuses and devices used to control and adjust routine releases, to detect accidental pollutions, and to identify the origins of an increased radioactivity. The objective is to perform permanent and continuous sampling and measurement. Samplers and measurement devices (Geiger probes, resin-based integrators, dry aerosol radioactivity recorders and dry sample radioactivity recorders) are presented. Water control stations are presented: these stations are either fixed, or mobile or floating

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

Assessment of radioactivity for 24 hours urine sample depending on correction factor by using creatinine

International Nuclear Information System (INIS)

Kharita, M. H.; Maghrabi, M.

2006-09-01

Assessment of intake and internal does requires knowing the amount of radioactivity in 24 hours urine sample, sometimes it is difficult to get 24 hour sample because this method is not comfortable and in most cases the workers refuse to collect this amount of urine. This work focuses on finding correction factor of 24 hour sample depending on knowing the amount of creatinine in the sample whatever the size of this sample. Then the 24 hours excretion of radionuclide is calculated assuming the average creatinine excretion rate is 1.7 g per 24 hours, based on the amount of activity and creatinine in the urine sample. Several urine sample were collected from occupationally exposed workers the amount and ratios of creatinine and activity in these samples were determined, then normalized to 24 excretion of radionuclide. The average chemical recovery was 77%. It should be emphasized that this method should only be used if a 24 hours sample was not possible to collect. (author)

Effects of radioactivity on living organisms

International Nuclear Information System (INIS)

Metivier, H.; Flury-Herard, A.; Cadet, J.

1996-01-01

After the discovery of X-rays by W.C. Roentgen and the discovery of radioactivity by H. Becquerel, about a century ago, the scientists were aware of the damaging effects of ionizing radiations on men. This digest paper describes the biological effects of internal and external irradiations: dose distributions, radio-induced DNA injuries, cells death, DNA mutations, carcinomas, radio-therapy, radiosterilization and ionization of food. (J.S.)

Investigations on the radioactive contamination of crop plants as a result of hydrogen-bomb detonation. I. Radioactive contamination of crop plants and soil

Energy Technology Data Exchange (ETDEWEB)

Mitsui, S; Aso, S; Tensho, K; Kumazawa, K; Miyawaki, K

1956-01-01

Samples (74) of leaves, fruits, and other plant parts were collected in May 1955 after being subjected to radioactive fallout between March and May. Counts/min ranged from 1 to 259 on fresh samples. Radiation was strongest on rough-surfaced plants. Lower leaves of trees and grasses under trees showed only week radiation. Washing with H/sub 2/O was very effective but occassionally imperfect, indicating possible intake of fission products through roots and leaves. In August and September plant tissues were ashed extracted with HCl, and /sup 40/K precipitated with NH/sub 4/OH and (NH/sub 4/)/sub 2/CO/sub 3/. Radioactivity ranged from 0 to 22 counts/min/10g dried plant material. No radioactivity was found in roots. Soil samples tested ranged from 2 to 47 counts/min for 5 g dry sample. Poorly drained soils were highest.

The method of radioactive tracer for measuring the amount of inorganic nanoparticles in biological samples

Science.gov (United States)

Buzulukov, Yu; Antsiferova, A.; Demin, V. A.; Demin, V. F.; Kashkarov, P.

2015-11-01

The method to measure the mass of inorganic nanoparticles in biological (or any other samples) using nanoparticles labeled with radioactive tracers is developed and applied to practice. The tracers are produced in original nanoparticles by radioactive activation of some of their atomic nuclei. The method of radioactive tracers demonstrates a sensitivity, specificity and accuracy equal or better than popular methods of optical and mass spectrometry, or electron microscopy and has some specific advantages. The method can be used for study of absorption, distribution, metabolism and excretion in living organism, as well as in ecological and fundamental research. It was used in practice to study absorption, distribution, metabolism and excretion of nanoparticles of Ag, Au, Se, ZnO, TiO2 as well as to study transportation of silver nanoparticles through the barriers of blood-brain, placenta and milk gland of rats. Brief descriptions of data obtained in experiments with application of this method included in the article. The method was certified in Russian Federation standard system GOST-R and recommended by the Russian Federation regulation authority ROSPOTREBNADZOR for measuring of toxicokinetic and organotropy parameters of nanoparticles.

Measurement of radioactivity in the environment - Soil - Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples

International Nuclear Information System (INIS)

2007-01-01

This part of ISO 18589 specifies the general requirements, based on ISO 11074 and ISO/IEC 17025, for all steps in the planning (desk study and area reconnaissance) of the sampling and the preparation of samples for testing. It includes the selection of the sampling strategy, the outline of the sampling plan, the presentation of general sampling methods and equipment, as well as the methodology of the pre-treatment of samples adapted to the measurements of the activity of radionuclides in soil. This part of ISO 18589 is addressed to the people responsible for determining the radioactivity present in soil for the purpose of radiation protection. It is applicable to soil from gardens, farmland, urban or industrial sites, as well as soil not affected by human activities. This part of ISO 18589 is applicable to all laboratories regardless of the number of personnel or the range of the testing performed. When a laboratory does not undertake one or more of the activities covered by this part of ISO 18589, such as planning, sampling or testing, the corresponding requirements do not apply. Information is provided on scope, normative references, terms and definitions and symbols, principle, sampling strategy, sampling plan, sampling process, pre-treatment of samples and recorded information. Five annexes inform about selection of the sampling strategy according to the objectives and the radiological characterization of the site and sampling areas, diagram of the evolution of the sample characteristics from the sampling site to the laboratory, example of sampling plan for a site divided in three sampling areas, example of a sampling record for a single/composite sample and example for a sample record for a soil profile with soil description. A bibliography is provided

Nuclear radioactive techniques applied to materials research

CERN Document Server

Correia, João Guilherme; Wahl, Ulrich

2011-01-01

In this paper we review materials characterization techniques using radioactive isotopes at the ISOLDE/CERN facility. At ISOLDE intense beams of chemically clean radioactive isotopes are provided by selective ion-sources and high-resolution isotope separators, which are coupled on-line with particle accelerators. There, new experiments are performed by an increasing number of materials researchers, which use nuclear spectroscopic techniques such as Mössbauer, Perturbed Angular Correlations (PAC), beta-NMR and Emission Channeling with short-lived isotopes not available elsewhere. Additionally, diffusion studies and traditionally non-radioactive techniques as Deep Level Transient Spectroscopy, Hall effect and Photoluminescence measurements are performed on radioactive doped samples, providing in this way the element signature upon correlation of the time dependence of the signal with the isotope transmutation half-life. Current developments, applications and perspectives of using radioactive ion beams and tech...

Radioactivity

International Nuclear Information System (INIS)

2002-01-01

This pedagogical document presents the origin, effects and uses of radioactivity: where does radioactivity comes from, effects on the body, measurement, protection against radiations, uses in the medical field, in the electric power industry, in the food (ionization, radio-mutagenesis, irradiations) and other industries (radiography, gauges, detectors, irradiations, tracers), and in research activities (dating, preservation of cultural objects). The document ends with some examples of irradiation levels (examples of natural radioactivity, distribution of the various sources of exposure in France). (J.S.)

Measurements of Background and Fall-out T Radioactivity in Samples from the Baltic Bay of Tvaeren, 1957-1963

Energy Technology Data Exchange (ETDEWEB)

Agnedahl, P O

1965-01-15

To get information on the possible effects of future releases of radioactive effluents into Tvaeren, a bay of the Baltic, the Atomic Energy Company has had to carry out a biological and radiological programme in Tvaeren. The work was scheduled to extend over at least two years but in fact proceeded from 1957 to 1963. Unfortunately, no exact idea of the natural activity could be gained on account of the fallout from the repeated atomic bomb tests. Instead, the work developed into a study of the variations in biological samples caused by these tests. This report studies the correlation between the activity in fallout and that in flora and fauna. The contribution of natural activity from the radionuclide K-40 has been determined and is given for all samples. The following values may be regarded as representative of total {beta}-activity and activity of K-40 in the investigated samples. T 1204 has been used as standard.

Genetic radiation effects and natural radioactivity of human population in Brazil

International Nuclear Information System (INIS)

Freire-Maia, A.

1972-01-01

A study on areas of natural radioactivity is done, covering the genetic effects on human population. The study is done in depth dealing with aspecto such as radioactive area involved, discussion of materials and methods, errors and fallacies, influential factors, models, buildup and natural radioactivity, hypotheses, results and perspectives, etc. It covers 24 localites, 8.572 couples and 43.930 pregnancy cases [pt

Radioactivity. Centenary of radioactivity discovery

International Nuclear Information System (INIS)

Charpak, G.; Tubiana, M.; Bimbot, R.

1997-01-01

This small booklet was edited for the occasion of the exhibitions of the celebration of the centenary of radioactivity discovery which took place in various locations in France from 1996 to 1998. It recalls some basic knowledge concerning radioactivity and its applications: history of discovery, atoms and isotopes, radiations, measurement of ionizing radiations, natural and artificial radioactivity, isotope dating and labelling, radiotherapy, nuclear power and reactors, fission and fusion, nuclear wastes, dosimetry, effects and radioprotection. (J.S.)

Guidance for air sampling at nuclear facilities

International Nuclear Information System (INIS)

Breslin, A.J.

1976-11-01

The principal uses of air sampling at nuclear facilities are to monitor general levels of radioactive air contamination, identify sources of air contamination, and evaluate the effectiveness of contaminant control equipment, determine exposures of individual workers, and provide automatic warning of hazardous concentrations of radioactivity. These applications of air sampling are discussed with respect to standards of occupational exposure, instrumentation, sample analysis, sampling protocol, and statistical treatment of concentration data. Emphasis is given to the influence of spacial and temporal variations of radionuclide concentration on the location, duration, and frequency of air sampling

Radioactive characterization of samples in various geometry by gamma ray spectrometry

International Nuclear Information System (INIS)

Dulama, Cristian; Dobrin, Relu; Toma, Alexandru

2001-01-01

There are certain limitations concerning the usage of standard source method for efficiency calibration of gamma - ray spectrometers measuring in extended geometry. These limitations arise from the great diversity of forms, dimensions and densities of the objects which are to be measured. One of the steps in fuel fabrication cycle is the radioactive waste conditioning. At Institute for Nuclear Research INR a radioactive waste management facility operates both for its own purposes and for providing external services. This facility is able to perform conditioning of liquid and solid wastes for interim storage. During the waste conditioning operations there are certain stages when the radioactive measurement of the storage drums is demanded. In order to be able to establish the radioactive content within storage drums during the various procedures that are performed on them at our waste treatment facility we designed and manufactured a mobile equipment for 'in situ' spectrometry. A portable high purity germanium detector was used together with a compact workstation Canberra INSPECTOR incorporating a multi-channel analyzer, a spectroscopic amplifier and a high voltage power supply. Spectral data are processed on-line with a SubNote IBM 486 compatible PC using GeniePC, an OS/2 based spectroscopy software from Canberra. A compact, modular lead housing for the detector was designed and manufactured at INR, using uncontaminated Pb and an inner layer of copper. In front of the detector a lead collimator with cylindrical hole was used to reduce the range of variation for incidence angle. Hence several collimators were manufactured with 10, 20, 40 and 60 mm diameter holes to be able to ensure a proper counting rate in a large range of drum's specific activities by simply changing the collimator. For the efficiency calibration of the spectrometric chain a computer program was written, based on a Monte Carlo algorithm, using a semiempirical method to determinate the effective

Radioactivity of bone cement

International Nuclear Information System (INIS)

Scherer, M.A.; Winkler, R.; Ascherl, R.; Lenz, E.

1993-01-01

A total of 14 samples of different types of bone cement from five different manufacturers were examined for their radioactivity. Each of the investigated bone cements showed a low radioactivity level, i.e. between [de

Environmental radioactive intercomparison program and radioactive standards program

Energy Technology Data Exchange (ETDEWEB)

Dilbeck, G. [Environmental Monitoring Systems Laboratory, Las Vegas, NV (United States)

1993-12-31

The Environmental Radioactivity Intercomparison Program described herein provides quality assurance support for laboratories involved in analyzing public drinking water under the Safe Drinking Water Act (SDWA) Regulations, and to the environmental radiation monitoring activities of various agencies. More than 300 federal and state nuclear facilities and private laboratories participate in some phase of the program. This presentation describes the Intercomparison Program studies and matrices involved, summarizes the precision and accuracy requirements of various radioactive analytes, and describes the traceability determinations involved with radioactive calibration standards distributed to the participants. A summary of program participants, sample and report distributions, and additional responsibilities of this program are discussed.

Radioactivity measurements and risk assessments in soil samples at south and middle of Qatar

International Nuclear Information System (INIS)

Al-Kinani, A.; Al Dosari, M.; Amr, M.A.; Al-Saad, K.A.; Helal, A.I.

2012-01-01

Health risks associated with the exposure to the natural radioactivity present in soil materials has great concern all over the world. Thus soil samples collected from an urban area at south and middle of Qatar in order to measure natural radioactivity, 40 K, 226 Ra and 232 Th and the artificial 137 Cs using gamma-ray spectrometry method.The soil activity concentrations ranges from 25.01- 40.31 for 226 Ra, 12.37- 4.99 for 232 Th and 133.8 - 250.1 for 40 K with mean values of 57, 87 and 207 Bq/ kg, respectively. The concentrations of these radionuclides are compared with the available data from other countries. The average and ranges of activity concentration of 226 Ra in Qatar soil areas are very much comparable to the world Figures. However, the concentration for 232 Th is comparable to other Gulf area and lower than that for Egypt and the world figures.The concentration for 40 K is lower as compared with Egypt, world, and Kuwait figures but comparable to Oman figures.The radium equivalent activity (Ra eq) in these soil samples ranges from 74.45 Bq/ kg to 41.21 Bq/ kg) with mean value of 57.4 Bq/ kg which is far below the safe limit (permissible) limit (370 Bq/ kg). The calculated values for external hazard index Hex for the soil samples range from 0.102 - 0.21 and average concentration of 0.164 which is lower than other values reported .However these values are lower than unity; therefore, the soil from these regions is safe and can be used as a construction material without posing any significant radiological threat to population.The absorbed dose rate calculated from activity concentration of 226 Ra, 232 Th and 40 K ranges between 11.529 - 21.446, 2.383 - 11.744, and 5.304 -10.357 n Gy/ h, respectively and the total average absorbed dose rate 28.915 n Gy/ h which are lower than the world wide average absorbed dose rate 51 n Gy/ h. The total absorbed dose in the study area ranges from 20.146 - 40.389 n Gy/ h with an average value of 28.915 n Gy/ h .The

The effect of microorganisms on asphaltopropylene concrete in a radioactive waste repository. Part 2

International Nuclear Information System (INIS)

Hlavackova, I.; Hlavacek, I.; Mara, M.; Wasserbauer, R.

1993-11-01

The permeability of asphaltopropylene concrete (APC) was examined after the action of aerobic bacteria and molds, and the changes in its volume, weight and swelling capacity were recorded. APC has been used as a sealing material in low level radioactive waste pits at the Dukovany NPP repository. Results of check-up sampling of microorganisms in the repository are evaluated. Sulphate reducing bacteria, which have been detected in soil near the reactor site, were isolated and their action upon asphaltopropylene (AP) was investigated. The resistance of bitumen layers containing model waste, against the action of aerobic bacteria and molds and against water was also examined. Bitumen samples containing model waste were found to absorb water at low temperatures considerably faster than unfilled bitumen. At elevated temperatures the absorption of water is appreciable, causing high weight losses of the bituminized waste layer due to degradation. The time dependences of the bitumen sample weight at 20 degC and 60 degC in distilled and cement water are given in the Appendix. The results included in the final reports ''Investigation of the effect of microorganisms on asphaltopropylene-based insulating materials employed as sealing in the secondary radioactive waste repository at the Dukovany NPP in relation to the microbial flora present. Bacteria'' and ''Investigation of the impact of biodegradation effects of aerobic and anaerobic microorganisms including molds on asphalt and asphaltopropylene in conditions of the ground repository at the Dukovany NPP'' are also given. (J.B.). 8 tabs., 33 figs

Effect of self-glazing on reducing the radioactivity levels of red mud based ceramic materials

Energy Technology Data Exchange (ETDEWEB)

Qin, Shuo [College of Material Science and Engineering, Guilin University of Technology, Guilin, Guangxi 541004 (China); Wu, Bolin, E-mail: wubolin3211@gmail.com [College of Material Science and Engineering, Guilin University of Technology, Guilin, Guangxi 541004 (China)

2011-12-30

Graphical abstract: Self-glazing red mud based ceramic materials (RMCM) were produced by normal pressure sintering process using the main raw materials of red mud. The properties of the RMCM samples were investigated by the measurements of mechanical properties, radiation measurement, X-ray diffraction (XRD) and scanning electron microscopy (SEM). The results show that the self-glazing RMCM have good mechanical properties (water absorption and apparent porosity approached zero; bulk density, 2.94 g/cm{sup 3}; compressive strength, 78.12 MPa). The radiation level has clear change regularity that the radioactivity levels of red mud (6360 Bq) are obvious declined, and can be reduced to that of the natural radioactive background of Guilin Karst landform, China (3600 Bq). It will not only consume large quantities of red mud, but also decrease the production cost of self-glazing RMCM. And the statement of this paper will offer effective ways to reduce the radioactivity level of red mud. Highlights: Black-Right-Pointing-Pointer The self-glazing phenomenon in red mud system was first discovered in our research. Black-Right-Pointing-Pointer Radiation levels of red mud can be reduced efficiently by self-glazing layer. Black-Right-Pointing-Pointer Red mud based ceramic materials will not cause harm to environment and humans. Black-Right-Pointing-Pointer This research possesses important economic significances to aluminum companies. - Abstract: Self-glazing red mud based ceramic materials (RMCM) were produced by normal pressure sintering process using the main raw materials of red mud. The properties of the RMCM samples were investigated by the measurements of mechanical properties, radiation measurement, X-ray diffraction (XRD) and scanning electron microscopy (SEM). The results show that the self-glazing RMCM have good mechanical properties (water absorption and apparent porosity approached zero; bulk density, 2.94 g/cm{sup 3}; compressive strength, 78.12 MPa). The radiation

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).

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

Environmental radioactivity surveillance programme 1994-1996

International Nuclear Information System (INIS)

Pollard, D.; Smith, V.; Howett, D.; Hayden, E.; Fegan, M.; O'Colmain, M.; Cunningham, J.D.

1997-12-01

This report presents the results of the terrestrial monitoring programme implemented by the Radiological Protection Institute of Ireland during the period 1994 to 1996. This monitoring programme includes the routine sampling and testing for radioactivity of samples of air, rainwater, drinking water and milk. Atmospheric concentrations of krypton-85 continued to rise over the period. No abnormal readings were observed for gamma dose rate, radioactivity in airborne particulates or radioactivity in rainwater. Significant variation in the concentrations of natural radioactivity was observed between drinking water supplies.The levels of anthropogenic radioactivity recorded during this reporting period in air, rainwater, drinking water and milk continue to be insignificant from a radiological safety point of view

Environmental radioactivity survey in Suwon

Energy Technology Data Exchange (ETDEWEB)

Park, Won Keun; Park, Jong Mi [Kyunghee Univ., Suwon (Korea, Republic of)

2003-12-15

The project is carried out to monitor the change of environmental radioactivity in Suwon, and to provide a systematic data for radiation monitoring and counter measurement at a radiological emergency situation. Also the survey of natural environmental radioactivities in the samples was conducted to make the reliable data base for evaluation of internal exposure and environmental contamination of radiation. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Suwon regional monitoring station m 2003. Also it contains the data of natural radioactivity levels of environmental samples such as soil, drinking water, indicator plant(mugwort, pine-needle), agricultural and forest products, and processed food(tea)

Correlation between Asian Dust and Specific Radioactivities of Fission Products Included in Airborne Samples in Tokushima, Shikoku Island, Japan, Due to the Fukushima Nuclear Accident

International Nuclear Information System (INIS)

Sakama, M.; Nagano, Y.; Kitade, T.; Shikino, O.; Nakayama, S.

2014-01-01

Radioactive fission product 131 I released from the Fukushima Daiichi Nuclear Power Plants (FD-NPP) was first detected on March 23, 2011 in an airborne aerosol sample collected at Tokushima, Shikoku Island, located in western Japan. Two other radioactive fission products, 134 Cs and 137 Cs were also observed in a sample collected from April 2 to 4, 2011. The maximum specific radioactivities observed in this work were about 2.5 to 3.5 mBq×m -3 in a airborne aerosol sample collected on April 6. During the course of the continuous monitoring, we also made our first observation of seasonal Asian Dust and those fission products associated with the FDNPP accident concurrently from May 2 to 5, 2011. We found that the specific radioactivities of 134 Cs and 137 Cs decreased drastically only during the period of Asian Dust. And also, it was found that this trend was very similar to the atmospheric elemental concentration (ng×m -3 ) variation of stable cesium ( 133 Cs) quantified by elemental analyses using our developed ICP-DRC-MS instrument

Survey of radioactive contamination for foodstuffs

International Nuclear Information System (INIS)

Lee, Wan No; Lee, Chang Wu; Choi, Geun Sik; Cho, Yeong Hyeon; Kang, Mun Ja; Cheong, Geun Ho; Kim, Hui Ryeong; Park, Du Won; Park, Hyo Guk; Kwak, Ji Yeon

2006-11-01

After the Chernobyl nuclear accident in 1986, a lot of countries including EU, Japan, USA are to strengthen survey of radioactive contamination for foodstuffs. Our country has also surveyed radioactive contamination of the imported foodstuffs and started to check continuously the radioactivity contamination of the open market foodstuffs since 2003. In this year, imported foodstuffs(130 samples) and domestic foodstuffs(10 samples) are analyzed to investigate the radioactive contamination. Sampled foodstuffs items are collected from the open markets; one group is the imported foodstuffs and the other group is the domestic foodstuffs producted around nuclear facilities and northeast of Sokcho city concerning recent situations. Samples are usually bought from traditional markets, mart, department store or the Internet. After pretreatments such as drying, ashing, and homogenization, all samples were analyzed by gamma spectrometer system for survey and assessment of radioactive contamination. The 131 I radionuclide isn't detected among all foodstuffs(imported and domestic). The 137 Cs radionuclide among the regulation radionuclides( 137 Cs, 13 4 C s, 131 I) of food code is only detected at the imported foodstuffs but its level is far below the maximum permitted level. For the improvement of measurement confidence, the developed analysis method is tested by the participation of the national and international intercomparison. The developed method based on test results and international standard would be used at radioactive analysis as well as an education of relative workers. It could be applied as the basis data for amending the analysis method of food code. It is technically supported for radioactive analysis of commercial company and the government including KFDA. Finally these results would be used to solve an ambiguous anxiety of a people for radiation exposure by foodstuffs intake and help the KFDA to manage systematically the radioactive contamination and to give

The determination of radioactive strontium in environmental samples by preferential ion exchange separation from calcium

International Nuclear Information System (INIS)

Fukushima, Hiroto; Nonaka, Nobuhiro; Honda, Tetsutaro; Kimura, Toshimasa; Higuchi, Hideo

1979-01-01

The determination of radioactive strontium in environmental samples involves a difficulty in the separation and purification of strontium from large amounts of calcium. The principal technique employed in this study is based on a cation exchange separation after preferential chelation of calcium over strontium by EDTA. The alkaline earth fraction separated from samples is dissolved in 1.2 M HCl and an equivalent amount of EDTA is added. The solution is passed through a Dowex 50W-X8 ion exchange column at a flow rate of 20 ml/min after the pH has been adjusted to 5.1. A fraction of calcium retained on the resin is eluted out with 1.8 l of 2 w/v% EDTA solution at pH 5.1. Then the strontium is eluted with 450 ml of 2 M HCl. The strontium carbonate is precipitated, and the chemical yield is determined. After standing for 14 days to reach the radioactive equilibrium of 90 Sr - 90 Y, the activity of 89 Sr + 90 Sr + 90 Y is measured. Then the activity of 90 Sr + 90 Y is measured by milking the 90 Y. The proposed procedure has been applied to sea water, soil and various ash samples of vegetables, seaweeds and daily foods. The results obtained are in good agreement with those by a classical fuming nitric acid precipitation method. The detection limits are 0.1 pCi/l for 10 l of sea water, 10 pCi/kg for 100 g of soil and 1 pCi/kg-fresh for 20 g ash samples, respectively. (author)

Characterization of HLW glass samples Task 3 Characterization of radioactive waste forms a series of final reports (1985-89) No 20

International Nuclear Information System (INIS)

Malow, G.; Behrend, U.; Schubert, P.

1991-01-01

Due to a delay in the melting of the highly radioactive SON68 glass, a short-term post-investigation of the highly radioactive glass from the Pamela plant in Mol (Belgium) has been carried out, the aim being a check-up of the active LEWC glass SM 513 LW11. The results were compared with those obtained for non-radioactive glass samples. The final report of the present CEC programme shortly describes the planned investigations of the glass R7T7 for the whole period of the research contract and the results of the short-term post-investigation of the Pamela glass. 11 refs.; 9 figs.; 4 tabs

Natural radioactivity in building materials in Iran

International Nuclear Information System (INIS)

Mehdizadeh, S.; Faghihi, R.; Sina, S.

2011-01-01

This work presents a comprehensive study of natural radioactivity in building materials used in Iran. For this purpose, 177 samples of five types of building material, i.e. cement, gypsum, cement blocks, gravel and brick, were gathered from different regions of the country and analyzed by gamma spectroscopy to quantify radioactivity concentrations using a high purity germanium (HPGe) detector and a spectroscopy system. According to the results of this investigation, cement samples had maximum values of the mean Ra-226 and Th-232 concentrations, 39.6 and 28.9 Bq/kg, respectively, while the lowest value for mean concentration of these two radionuclides were found in gypsum samples 8.1 and 2.2 Bq/kg, respectively. The highest (851.4 Bq/kg) and lowest (116.2 Bq/kg) value of K-40 mean concentration were found in brick and gypsum samples, respectively. The absorbed dose rate and the annual effective dose were also calculated from the radioactivity content of the radionuclides. The results show that the maximum values of dose rate and annual effective dose equivalent were 53.72 nGy/h and 0.37 mSv/y in brick samples. The radium equivalent activities R eq calculated were below the permissible level of 370 Bq/kg for all building materials. The values of hazard indexes were below the recommended levels, therefore, it is concluded that the buildings constructed from such materials are safe for the inhabitants. The results of this study are consistent with the results of other investigations in different parts of the world. (authors)

Determination of naturally occurring radioactive materials and heavy metals in soil sample at industrial site area Gebeng, Pahang

International Nuclear Information System (INIS)

Muhammad Dzulkhairi Zulkifly

2012-01-01

A study has been carried out to determine the natural occurring radioactivity and heavy metal at an industrial site area Gebeng, Pahang. Sampling has been done in four different stations. This study has been carried out to determine the natural radioactivity ( 238 U, 232 Th, 40 K and 226 Ra) and heavy metal in soil sample. Natural radioactivities were determined using Gamma Spectrometry System, the heavy metal determination was done using Inductively Coupled Plasma-Mass Spectrometry (ICP-MS). The result for analysis radioactivity concentration showed that Uranium-238 were in the range of 28.18 ± 4.78 Bq/ kg - 39.63 ± 4.79 Bq/ kg, while the concentration for Thorium-232 were in the range of 45.66 ± 5.49 Bq/ kg - 72.43 ± 9.47 Bq/ kg and for the Radium-226, the concentration were in the range of 8.93 ± 1.15 Bq/ kg - 14.29 ± 2.61 Bq/ kg. The concentration of Potassium-40 were in the range of 51.06 ± 12.18 Bq/ kg - 426.28 ± 137.70 Bq/ kg. 8 heavy metals have been found from the four different stations which are Al, Fe, V, Mn, Cr, Cu, Zn and Pb. Fe show the highest concentration among the other heavy metal while Pb show the lowest concentration. From this study, the specific activities of natural radionuclide in almost all stations were below the world limit average for soil, which is 35 Bq/ kg for Uranium-238 and Radium-226, while Thorium-232 and Potassium-40 were above the world limit average which are 30 Bq/ kg and 400 Bq/ kg. (author)

Radioactive cesium elution speed in dried wild Mushrooms collected in 2015

International Nuclear Information System (INIS)

Yamaguchi, Toshiro; Arai, Hirotsugu; Ohnuma, Tohru; Arai, Hiromu; Takyu, Sodai; Matsuyama, Tetsuo; Ishii, Keizo

2016-01-01

Dried wild mushrooms (12 species, 13 samples) collected in Nagano, Fukushima, and Miyagi Prefectures, Japan, in 2015 were immersed in water for 1,440 min. The elution rate of radioactive cesium (Cs) was calculated based on its radioactivity, which was measured with a high-purity germanium semiconductor detector (GX2018; CANBERRA Industries, Meriden, CT, USA) before and after immersion for each mushroom. Immersion fluid was sampled after 10, 30, 60, 180, 360, and 1,440 min of immersion and dried on aluminum foil. Then, imaging plates (BAS-III, Fujifilm, Tokyo, Japan) exposed to the dried immersion fluid were measured with a Bio-imaging Analyzer System-1800 II (Fujifilm). The 50% elution time of each wild mushroom was calculated based on the photo stimulated luminescence density of the autoradiographs. The radioactive Cs elution rate was > 80% for 11 samples (84% of total) comprising 11 mushroom species. Moreover, the 50% elution time was < 30 min for 9 samples (69% of total) comprising 9 species. This shows that the radioactive Cs elution rate and elution speed were not constant among mushroom species. Based on these results, immersing the mushrooms, which were dried, in water for at least 120 min is an effective method for removing radioactive Cs from wild mushrooms. (author)

Sampling methods for pasture, soil and deposition for radioactivity emergency preparedness in the Nordic countries

International Nuclear Information System (INIS)

Isaksson, M.

2002-01-01

The aim of this work was to compare sampling techniques for pasture, soil and deposition, planned for radioactivity surveillance in emergency situations in the Nordic countries. The basis of the survey was a questionnaire, sent to radiation protection authorities and laboratories. Sampling of pasture is performed with a cutting height between 1 and 5 cm above the ground from an area of about 1 m 2 . The sampling plots are usually randomly positioned. Soil samples, 3 to 20 cores in various patterns, are generally taken by a corer of varying diameter. For deposition sampling, precipitation collectors of different sizes are used. When comparing results, the differences between laboratories should be borne in mind so that proper corrections can be made. It is, however, important to consider that, especially in an emergency situation, the use of standardised methods may worsen the results if these methods are not part of the daily work. (orig.)

Low-level Radioactivity Measurements

International Nuclear Information System (INIS)

Hurtgen, C.

2002-01-01

The objectives of the research performed in the area of low-level radioactivity measurements are (1) to maintain and develop techniques for the measurement of low-level environmental and biological samples, (2) to measure these samples by means of low-background counters (liquid scintillators, proportional counters, ZnS counters, alpha spectrometry), (3) to support and advise the nuclear and non-nuclear industry on problems of radioactive contamination and low-level radioactivity measurements; (4) to maintain and improve the quality assurance system according to the ISO17025 standard; and (5) to assess the internal dose from occupational intakes of radionuclides of workers of the nuclear industry. Progress and achievements in these areas in 2001 are reported

Low-level Radioactivity Measurements

International Nuclear Information System (INIS)

Hurtgen, C.

2001-01-01

The objectives of the research performed in the area of low-level radioactivity measurements are (1) to maintain and develop techniques for the measurement of low-level environmental and biological samples, (2) to measure these samples by means of low-background counters (liquid scintillators, proportional counters, ZnS counters, alpha spectrometry), (3) to support and advice the nuclear and non-nuclear industry in matters concerning radioactive contamination and/or low-level radioactivity measurements; (4) to maintain the quality assurance system according to the EN45001/ISO17025 standard; and (5) to assess the internal dose from occupational intakes of radionuclides of workers of the nuclear industry. Progress and achievements in these areas in 2000 are reported

Investigation of radioactive contamination at non-radioactive drains of the Tsuruga Nuclear Power Station

International Nuclear Information System (INIS)

Koide, Hiroaki; Imanaka, Tetsuji; Ebisawa, Toru; Kawano, Shinji; Kobayashi, Keiji.

1982-05-01

In April, 1981, it was disclosed that a drainage area at the Tsuruga Nuclear Power Station was so much contaminated with radioactivites. Although Ministry of International Trade and Industry (MITI) officially provided an explanation of a process that resulted in the contamination, many problems remain unsolved on account of insufficient and limited investigations. The authors collected mud samples from contaminated manholes and examined radioactivities in them through the measurement of #betta#- and #betta#-spectra. Chemical separation of the samples was carried out in order to obtain precise concentration of radioactive cesium. Results are as follows: i) the concentration of radioactivities does not show monotonous decrease along the stream line but an anomalous peak at downstream manholes, ii) at the manhole specified No. 6 located rather downstream, 137 Cs concentration is significantly high and the composition of radioactive nuclides is quite different from that in the other manholes, and iii) additional radioactive contamination was observed in other manholes of non-radioactive drains which would not be influenced by the accident explained by MITI. Our present work has provided much more data than by MITI and made it clear that the overall data cnnot be consistent with the simple MITI explanation; a single radioactive release accident caused the disclosed contamination. It is concluded that non-radioactive water drains at the Tsuruga Nuclear Power Station had been under continual contamination. (author)

Radioactivity Monitoring of the Irish Environment 2003-2005

International Nuclear Information System (INIS)

Ryan, R.W.; Dowdall, A; Fegan, M.F.; Hayden, E.; Kelleher, K.; Long, S.; McEvoy, I.; McKittrick, L.; McMahon, C.A.; Murray, M.; Smith, K.; Sequeira, S.; Wong, J.; Pollard, D.

2007-05-01

fuel. During the reporting period, levels of radionuclides in airborne radioactivity were low and consistent with measurements in previous years. External gamma dose rates were monitored continuously at twelve stations. No abnormal levels were observed during the period. In accordance with the RPII's drinking water monitoring protocol, major public water supplies from each county are sampled at least every four years while supplies to certain major population centres are sampled annually. During the period 2003 to 2005, water supplies from fourteen counties were sampled and all of the waters tested were found to be within the parametric values for radioactivity set out in the relevant national standards. The RPII sampled and measured levels of radioactivity in mixed diet, milk and miscellaneous other foodstuffs including milk products, baby foods, beef, lamb, poultry and vegetables. These measurements show that levels of anthropogenic radioactivity in the Irish diet continue to be low. Approximately 300 samples of fish, shellfish, seaweed, seawater and sediment were collected in each of the years covered by this report. The samples were analysed for a range of radionuclides. The main pathway contributing to the exposure of the Irish public to anthropogenic radioactivity from the marine environment was found to be the consumption of seafood. Between 2003 and 2005, the mean annual committed effective dose to a heavy consumer of seafood from the Irish Sea was 0.85 ?Sv. Caesium-137 was the dominant radionuclide, accounting for approximately 60-70% of the total dose. The dose to the Irish population due to this radionuclide has declined significantly over the last two decades corresponding to the reduction in discharges of this radionuclide from Sellafield. Along the Irish coastline the highest activity concentrations observed are in the north-east. The doses incurred by the Irish public as a result of anthropogenic radioactivity in the environment do not constitute a

Understanding radioactive waste

International Nuclear Information System (INIS)

Murray, R.L.

1989-01-01

This book discusses the sources and health effects of radioactive wastes. It reveals the techniques to concentrate and immobilize radioactivity and examines the merits of various disposal ideas. The book, which is designed for the lay reader, explains the basic science of atoms,nuclear particles,radioactivity, radiation and health effects

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.

The management of radioactive materials spills

International Nuclear Information System (INIS)

Ryan, M.T.; Ebenhack, D.G.

1985-01-01

The management and handling of a radioactive materials spill must be swift and effective to reduce or mitigate any adverse impacts on public health and safety. Spills within nuclear facilities generally pose less of a public health impact than spills in areas of public access. The essential elements of spill management include prior planning by agencies which may be required to respond to a spill. Any plan for the management of radioactive materials spills must be flexible enough to be applied in a variety of situations. The major elements of a radioactive materials spill plan, however, apply in every case. It is essential that communications be clear and effective, that the management of a spill be directed by a responsible party whose authority is recognized by everyone involved and that the actions, according to the principles discussed above, be taken to assure the safety of any injured personnel, containment and stabilization and clean up the spill and to verify through radiological surveys and sample analyses that the clean up is complete. Any spill of radioactive materials, minor or major, should be assessed so that similar spills or accidents can be prevented

Effect of radioactive chromate on the corrosion and polarisation of mild steel in sodium chloride solution

International Nuclear Information System (INIS)

Subramanyan, N.; Ramakrishnaiah, K.; Iyer, S.V.; Kapali, V.

1980-01-01

Corrosion tests of mild steel in 0.01% sodium chloride containing radioactive chromate and non-radioactive chromate have been carried out. It has been observed that the labelled sodium chromate has a deleterious effect on the inhibitive action of non-radioactive chromate. The effect of radioactive chromate on the potentiostatic polarization of m.s. in sodium chloride solution containing non-radioactive sodium chromate has also been studied. It is observed that both the cathodic and the anodic polarisation of the metal is diminished in the presence of radioactive chromate. The behaviour of the system in the presence of radioactive chromate is attributed both to the action of depolarisers produced by radiolysis of water and to the effect of gamma radiation on the metal. (author)

Forage: a sensitive indicator of airborne radioactivity

International Nuclear Information System (INIS)

Jackson, W.M.; Noakes, J.E.; Spaulding, J.D.

1981-01-01

This paper presents the results of using Ge(Li) γ-ray spectroscopy to measure radioactivity concentration of forage in the vicinity of the Joseph M. Farley Nuclear Plant, Houston County, AL., over a 31/2 yr period. The report period includes 2 yr of pre-operational and 11/2 yr of operational sampling. Although the objective of forage sampling was the measurement of manmade airborne fallout radioactivity, several natural radioisotopes were also found to be present. A summary of natural radioactivity data for all samples measured during the period from August 1975 to December 1978 is given. Approximately 10 days after each of four Chinese atmospheric nuclear tests conducted during the sampling period fresh fission product fallout was measured on the forage. The information from these nuclear tests shows forage sampling to be a convenient and sensitive monitoring tool for airborne fallout radioactivity. (author)

Radioactive decay and labeled compounds

International Nuclear Information System (INIS)

Anon.

1991-01-01

This chapter on radioactive decay and labeled compounds has numerous intext equations and worked, sample problems. Topics covered include the following: terms and mathematics of radioactive decay; examples of calculations; graphs of decay equations; radioactivity or activity; activity measurements; activity decay; half-life determinations; labeled compounds. A 20 problem set is also included. 1 ref., 4 figs., 1 tab

Evaluation of induced radioactivity in 10 MeV-Electron irradiated spices, (2); [beta]-ray counting

Energy Technology Data Exchange (ETDEWEB)

Katayama, Tadashi; Furuta, Masakazu; Shibata, Setsuko; Matsunami, Tadao; Ito, Norio; Mizohata, Akira; Toratani, Hirokazu (Osaka Prefectural Univ., Sakai (Japan). Research Inst. for Advanced Science and Technology); Takeda, Atsuhiko

1994-02-01

In order to check radioactivity of beta-emmitters produced by ([gamma], n) reactions which could occur at energies up to 10 MeV, black pepper, white pepper, red pepper, ginger and turmeric were irradiated with 10 MeV electron from a linear accelerator to a dose of 100 kGy. Beta-rays were counted using a 2[pi] gas flow counter and a liquid scintillation counter. Any induced radioactivity could not be detected in irradiated samples. When inorganic compounds containing the nuclides in the list were artificially added in the samples and were irradiated, the [beta]-activities were detected. From the amount of observed radioactivities of [beta]-emmitters produced in the compounds as photonuclear products, it is concluded that the induced radioactivity in natural samples by 10 MeV-electron irradiation were far smaller than natural radioactivity from [sup 40]K contained in the samples and, hence, its biological effects should be negligible. (author).

Classification of sand samples according to radioactivity content by the use of euclidean and rough sets techniques

International Nuclear Information System (INIS)

Abd El-Monsef, M.M.; Kozae, A.M.; Seddeek, M.K.; Medhat, T.; Sharshar, T.; Badran, H.M.

2004-01-01

Form the geological point of view, the origin and transport of black and normal sands is particularly important. Black and normal sands came to their places along the Mediterranean-sea coast after transport by some natural process. Both types of sands have different radiological properties. This study is, therefore, attempts to use mathematical methods to classify Egyptian sand samples collected from 42 locations in an area of 40 x 19 km 2 based on their radioactivity contents. The use of all information resulted from the experimental measurements of radioactivity contents as well as some other parameters can be a time and effort consuming task. So that the process of eliminating unnecessary attributes is of prime importance. This elimination process of the superfluous attributes that cannot affect the decision was carried out. Some topological techniques to classify the information systems resulting from the radioactivity measurements were then carried out. These techniques were applied in Euclidean and quasi-discrete topological cases. While there are some applications in environmental radioactivity of the former case, the use of the quasi-discrete in the so-called rough set information analysis is new in such a study. The mathematical methods are summarized and the results and their radiological implications are discussed. Generally, the results indicate no radiological anomaly and it supports the hypothesis previously suggested about the presence of two types of sand in the studied area

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

Virtual cascade impactors for the collection of radioactive atmospheric aerosols

International Nuclear Information System (INIS)

Berner, A.

1988-01-01

Starting from impaction theory, the properties of virtual impaction stages are discussed and compared to classical impactors. Virtual impaction stages offer the benefit of sampling coarse particles without bouncing and reentrainment, but turbulent mixing affects the performance of virtual stages. Future research should concentrate on special configurations for reducing the effects of turbulent mixing. Virtual impaction stages for sampling radioactive aerosols are to be designed in regard of the analytical requirements, the purpose of the measurements, and the aerosol. Therefore, the aerosol components expected in radioactive aerosols are discussed on the background of the multimodal model, which relates the size distribution to the genesis and the history of the aerosol. Reference is made to recent data of the radioactive atmospheric aerosol

Correlation between Asian Dust and Specific Radioactivities of Fission Products Included in Airborne Samples in Tokushima, Shikoku Island, Japan, Due to the Fukushima Nuclear Accident

Energy Technology Data Exchange (ETDEWEB)

Sakama, M., E-mail: minorusakama@tokushima-u.ac.jp [Department of Radiological Science, Division of Biomedical Information Sciences, Institute of Health Biosciences, The University of Tokushima, Tokushima 770-8509 (Japan); Nagano, Y. [Department of Radiological Science, Division of Biomedical Information Sciences, Institute of Health Biosciences, The University of Tokushima, Tokushima 770-8509 (Japan); Kitade, T. [Department of Laboratory, M and S Instruments Inc., Osaka 532-0005 (Japan); Shikino, O. [Department of Inorganic Analysis, PerkinElmer Japan Co. Ltd., Yokohama 240-0005 (Japan); Nakayama, S. [Department of Nuclear Science, Institute of Socio-Arts and Sciences, The University of Tokushima, Tokushima 770-8502 (Japan)

2014-06-15

Radioactive fission product {sup 131}I released from the Fukushima Daiichi Nuclear Power Plants (FD-NPP) was first detected on March 23, 2011 in an airborne aerosol sample collected at Tokushima, Shikoku Island, located in western Japan. Two other radioactive fission products, {sup 134}Cs and {sup 137}Cs were also observed in a sample collected from April 2 to 4, 2011. The maximum specific radioactivities observed in this work were about 2.5 to 3.5 mBq×m{sup -3} in a airborne aerosol sample collected on April 6. During the course of the continuous monitoring, we also made our first observation of seasonal Asian Dust and those fission products associated with the FDNPP accident concurrently from May 2 to 5, 2011. We found that the specific radioactivities of {sup 134}Cs and {sup 137}Cs decreased drastically only during the period of Asian Dust. And also, it was found that this trend was very similar to the atmospheric elemental concentration (ng×m{sup -3}) variation of stable cesium ({sup 133}Cs) quantified by elemental analyses using our developed ICP-DRC-MS instrument.

Radioactivity in the environment and its effects on health

International Nuclear Information System (INIS)

Sene, Monique; Schuler, Matthieu; Couvez, Celine; Rollinger, Francois; Bruno, Valerie; Renaud, Philippe; Laurier, Dominique; Gariel, Jean-Christophe; Estevao, Mathieu; Le Berre, David; Quere, Emmanuel; Josset, Mylene; Bernollin, Antoine; Saut, Catherine; Mailliat, Alain; Dryjanski, Claudie; Varin, Jean-Christophe; Villers, Anita; Gazal, Suzanne; Gerber, Mariette; Reynal, Nathalie; Vicaud, Alain; Renaud, Philippe; Roussel-Debet, S.; Leprieur, F.; Pourcelot, L.; Saey, L.; Tournieux, D.; Caldeira-Ideias, P.; Manificat, G.; Grammont, Vincent; Behar, Abraham; Gerber, Mariette

2015-11-01

This document gathers Power Point presentations. After a presentation of the new public portal of the French national network of measurements of radioactivity in the environment, a first session addressed the control of the environment by the different actors present on a territory (associations like CLI or ACRO or ATMO, operators like Areva). The addressed issues have been: the control performed by a CLI (Paluel-Penly) with the support of a departmental laboratory, the radiological monitoring of the environment about the Brennilis site, the study of an environmental marker (tritium in hive products), the specific study of the Durance region, the control of ambient radioactivity on the Nord-Pas-de-Calais coast, and the monitoring of the environment by the operator around La Hague site. The second session addressed the building up of reference radiological assessments: lessons learned from radiological assessments implemented by the IRSN, a citizen mapping of radioactivity in France, and improvement orientations for the monitoring of the environment by different actors. The third session addressed issues spanning from the environment to health: assessment of doses based on the control of the environment, global health impact for a set of nuclear power plants, assessment of the health impact of releases, knowledge status on the effects of low doses, and possible improvements of knowledge on the effects of radioactivity on health

Environmental radioactivity monitoring in Republic of Serbia

International Nuclear Information System (INIS)

Joksic, J.; Radenkovic, M.; Tanaskovic, I.; Vujovic, M.; Vuletic

2011-01-01

According to environmental radioactivity monitoring programme continuous measurements of radioactivity in different samples are performed. Measurements are performed in aerosol samples, fallout, soil, surface waters, drinking water, food of animal and plant origin, milk and feeding stuffs. [sr

Natural radioactivity and Rare Earth elements in feldspar samples, Central Eastern desert, Egypt

International Nuclear Information System (INIS)

Walley El-Dine, Nadia; El-Shershaby, Amal; Afifi, Sofia; Sroor, Amany; Samir, Eman

2011-01-01

The pegmatite bodies of the Eastern Desert of Egypt are widely distributed especially along the Marsa-Alam-Idfu road. The Abu Dob area covers about 150 km 2 of the Arabian Nubian shield at the central part of the Eastern Desert of Egypt. Most of the pegmatite is zoned; the zonation starts with milky quartz at the core followed by alkali feldspar at the margins. The feldspars vary in color from rose to milky and in composition from K-feldspar to Na-feldspar, sometimes interactions of both types are encountered. Thirteen feldspar samples were collected from different locations in the Abu Dob area for measuring the natural radioactivity of 238 U, 232 Th and 40 K using an HPGe detector. The variation in concentration of radionuclides for the area under investigation can be classified into regions of high, medium and low natural radioactivity. The average concentration in BqKg -1 has been observed to be from 9.5 to 183675.7 BqKg -1 for 238 U, between 6.1 and 94,314.2 BqKg -1 for 232 Th and from 0 to 7894.6 BqKg -1 for 40 K. Radium equivalent activities (Ra eq ), dose rate (D R ) and external hazard (H ex ) have also been determined. In the present work, the concentration of rare earth elements are measured for two feldspar samples using two techniques, Environmental Scanning Electron microscope XIL 30 ESEM, Philips, and Inductively Coupled Plasma Mass Spectroscopy (ICP-MS). The existence of rare earth elements in this area are very high and can be used in different important industries.

Natural radioactivity and Rare Earth elements in feldspar samples, Central Eastern desert, Egypt

Energy Technology Data Exchange (ETDEWEB)

Walley El-Dine, Nadia, E-mail: nadia_walley5@hotmail.co [Department of physics, Faculty of girls for Art, Science and Education, Ain Shams University, Heliopolis, Cairo (Egypt); El-Shershaby, Amal [Department of physics, Faculty of girls for Art, Science and Education, Ain Shams University, Heliopolis, Cairo (Egypt); Afifi, Sofia [Nuclear Materials Authority (Egypt); Sroor, Amany; Samir, Eman [Department of physics, Faculty of girls for Art, Science and Education, Ain Shams University, Heliopolis, Cairo (Egypt)

2011-05-15

The pegmatite bodies of the Eastern Desert of Egypt are widely distributed especially along the Marsa-Alam-Idfu road. The Abu Dob area covers about 150 km{sup 2} of the Arabian Nubian shield at the central part of the Eastern Desert of Egypt. Most of the pegmatite is zoned; the zonation starts with milky quartz at the core followed by alkali feldspar at the margins. The feldspars vary in color from rose to milky and in composition from K-feldspar to Na-feldspar, sometimes interactions of both types are encountered. Thirteen feldspar samples were collected from different locations in the Abu Dob area for measuring the natural radioactivity of {sup 238}U, {sup 232}Th and {sup 40}K using an HPGe detector. The variation in concentration of radionuclides for the area under investigation can be classified into regions of high, medium and low natural radioactivity. The average concentration in BqKg{sup -1} has been observed to be from 9.5 to 183675.7 BqKg{sup -1} for {sup 238}U, between 6.1 and 94,314.2 BqKg{sup -1} for {sup 232}Th and from 0 to 7894.6 BqKg{sup -1} for {sup 40}K. Radium equivalent activities (Ra{sub eq}), dose rate (D{sub R}) and external hazard (H{sub ex}) have also been determined. In the present work, the concentration of rare earth elements are measured for two feldspar samples using two techniques, Environmental Scanning Electron microscope XIL 30 ESEM, Philips, and Inductively Coupled Plasma Mass Spectroscopy (ICP-MS). The existence of rare earth elements in this area are very high and can be used in different important industries.

Evaluation of Radioactivity in Dusty Storm

International Nuclear Information System (INIS)

Mohammed, A.S; Majeed, N. A.; Nasaer, M.H.; Hoshi, H.; Abood, M.

2013-01-01

sample had been collected from the powder of the dusty storms which had been moved over Baghdad for a different months of a year 2011 by using metal containers that had manufactured locally and had been mounted over the roof of houses in particular regions of Baghdad (Kerkh and Risafa).The radioactive concentration of dust samples had been measured and analyzed by using the Gamma Spectroscopy analyzing System which consist of high purity Germanium detector of efficiency of 40 %, resolution 2keV at 1.332 MeV (Co-60) , DSA 2000 system which protective barrier made in Canberra Company , the developed Genie 2000Program and using personal computer. The measurement system for energy calibration and efficiency had been calibrated by using a standard point sources and standard source of a multi energy made by the American Canberra company. The Marnelli geometrical shape had been used to measure the activity of the samples. Results indicated the existence of the natural radioactive isotopes such as K-40, Be-7 which has been composed of as a result of the nuclear reaction between the Cosmic ray and some other elements of the atmosphere like Oxygen and Nitrogen besides the existence of radioactive isotopes which belongs to the natural Uranium series and the natural Thorium series. Highest measurements indicated the existence of industrial radioactive isotope Cs-137.The highest value of concentration for Be-7 was (381.5 Bq/kg) at Al-Shaab region, and the highest value of concentration for K-40 was (467.7 Bq/kg) and some other radioactive isotopes which belong to the series of U-238 as follows:- Bi -214 (32.6 Bq/kg), Pb-214 (33.6 Bq/kg), and radioactive isotopes which belong to the series Th-232 as follows:- Bi-212(18.6Bq/kg), Pb-212 (18.8Bq/kg),Ac-228 (30.3 Bq/kg),the highest value of concentration for the industrial Cs-137 was (26,8 Bq/kg) it was at Al-shaab region ,and this concentration is relatively high in comparison to the levels of normal concentration which exist in

Radioactivity in waters in SR Slovenia

International Nuclear Information System (INIS)

Kobal, I.; Mihailovic, M.; Shkofljanec, M.; Zhlebnik, L.; Drobne, F.

1977-12-01

The radioactivity of samples of rivers Brebovscica and Sava with its contributaries was monitored. The Brebovscica was found to have an enchanced radioactivity due to the geological and mining excavations in the uranium mine Zirovski vrh. This radioactivity is lowered by a dillution in the Poljanska Sora where the radioactive contamination has been hardly detected. The radioactivity in the Sava is relatively low though a few places with enchanced values were found may be due to radioactive pollutants from conventional industries. But this ought to be confirmed in the future

Application of mercurometric analysis methods to radioactive (and/or toxic) samples: Pycnometry and porosimetry

International Nuclear Information System (INIS)

Sannen, L.

1991-01-01

The analytical tools and methods used in the laboratory of High and Medium Activity of the Nuclear Research Centre in Mol to determine the density and the open porosity of radioactive (and/or toxic) samples are described. The density is determined by a vacuum pycnometer with plunger displacement. This home-made apparatus has been automated up to a high degree so that operation is easily performed in the remote handling conditions of a hot cell environment. The amount of mercury displaced by the sample is measured. The accuracy is better than 0.2 %. The porosimeter is a commercial apparatus which was modified to improve the hot cell compatibility and to provide fast processing of the data. The open porosity and its pore size distribution are determined from the measurement of the amount of mercury intruded into the sample under increasing pressure. The paper describes both instruments and the working methods. Also included are some examples of measurement results. (author). 5 figs

Tools for Inspecting and Sampling Waste in Underground Radioactive Storage Tanks with Small Access Riser Openings

International Nuclear Information System (INIS)

Nance, T.A.

1998-01-01

Underground storage tanks with 2 inches to 3 inches diameter access ports at the Department of Energy's Savannah River Site have been used to store radioactive solvents and sludge. In order to close these tanks, the contents of the tanks need to first be quantified in terms of volume and chemical and radioactive characteristics. To provide information on the volume of waste contained within the tanks, a small remote inspection system was needed. This inspection system was designed to provide lighting and provide pan and tilt capabilities in an inexpensive package with zoom abilities and color video. This system also needed to be utilized inside of a plastic tent built over the access port to contain any contamination exiting from the port. This system had to be build to travel into the small port opening, through the riser pipe, into the tank evacuated space, and out of the riser pipe and access port with no possibility of being caught and blocking the access riser. Long thin plates were found in many access riser pipes that blocked the inspection system from penetrating into the tank interiors. Retrieval tools to clear the plates from the tanks using developed sampling devices while providing safe containment for the samples. This paper will discuss the inspection systems, tools for clearing access pipes, and solvent sampling tools developed to evaluate the tank contents of the underground solvent storage tanks

A semi-empirical approach to analyze the activities of cylindrical radioactive samples using gamma energies from 185 to 1764 keV.

Science.gov (United States)

Huy, Ngo Quang; Binh, Do Quang

2014-12-01

This work suggests a method for determining the activities of cylindrical radioactive samples. The self-attenuation factor was applied for providing the self-absorption correction of gamma rays in the sample material. The experimental measurement of a (238)U reference sample and the calculation using the MCNP5 code allow obtaining the semi-empirical formulae of detecting efficiencies for the gamma energies ranged from 185 to 1764keV. These formulae were used to determine the activities of the (238)U, (226)Ra, (232)Th, (137)Cs and (40)K nuclides in the IAEA RGU-1, IAEA-434, IAEA RGTh-1, IAEA-152 and IAEA RGK-1 radioactive standards. The coincidence summing corrections for gamma rays in the (238)U and (232)Th series were applied. The activities obtained in this work were in good agreement with the reference values. Copyright © 2014 Elsevier Ltd. All rights reserved.

Radioactive wastes

International Nuclear Information System (INIS)

Teillac, J.

1988-01-01

This study of general interest is an evaluation of the safety of radioactive waste management and consequently the preservation of the environment for the protection of man against ionizing radiations. The following topics were developed: radiation effects on man; radioactive waste inventory; radioactive waste processing, disposal and storage; the present state and future prospects [fr

Environmental radioactivity monitoring around Jeongeup ARTI in 2009

Energy Technology Data Exchange (ETDEWEB)

Lee, Yun Jong; Kwon, Ho Je; Kang, Tai Jin [KAERI, Daejeon (Korea, Republic of)

2010-08-15

In Advanced Radiation Technology Institute (ARTI), the environmental radioactivity monitoring programme has been enforced since 2007. This study has been done to guarantee the local residence radiation safety by detecting in early stage a possible radiological effect due to the operation of the ARTI facilities. For the radioactivity measurement, fourteen selected samples were gathered not only monthly, quarterly, half-yearly but also in the harvesting season. Measurement and analysis were done on the samples collected in and around the ARTI. The gamma exposure rates measured in and around ARTI was in the range of 0.05{approx}0.3 {mu}Sv/h. The range of gross-beta-radioactivity analyzed for the water samples except waste water was from <3.451 to 288 mBq/L. The range of 3H concentration detected in the rain sample collected in the ARTI site was 0.951{approx}2.34 Bq/L. 90Sr was not detected from all the samples of soil and honey, pine needles. The above results confirmed that there has been no influence due to operation of the ARTI facilities.. The analysis result reveals that there is no radiological influence due to operation of the ARTI facilities. Also, it is judged that the samples analyzed for the first time in 2009 have to be continuously evaluated afterward

Computed tomography of radioactive objects and materials

International Nuclear Information System (INIS)

Sawicka, B.D.; Murphy, R.V.; Tosello, G.; Reynolds, P.W.; Romaniszyn, T.

1990-01-01

Computed tomography (CT) has been performed on a number of radioactive objects and materials. Several unique technical problems are associated with CT of radioactive specimens. These include general safety considerations, techniques to reduce background-radiation effects on CT images and selection criteria for the CT source to permit object penetration and to reveal accurate values of material density. In the present paper, three groups of experiments will be described, for objects with low, medium and high levels of radioactivity. CT studies on radioactive specimens will be presented. They include the following: (1) examination of individual ceramic reactor-fuel (uranium dioxide) pellets, (2) examination of fuel samples from the Three Mile Island reactor, (3) examination of a CANDU (CANada Deuterium Uranium: registered trademark) nuclear-fuel bundle which underwent a simulated loss-of-coolant accident resulting in high-temperature damage and (4) examination of a PWR nuclear-reactor fuel assembly. (orig.)

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)

Effects of radioactivity in the sea

Energy Technology Data Exchange (ETDEWEB)

NONE

1961-04-15

The Agency's regulatory work has proved even more important than was originally expected. It is clear that these activities must be continued for several years, as there are several fields not yet covered, and several which must be followed through by incorporation into international conventions or other administrative frameworks. Research in this field is to be conducted under a trilateral agreement between the International atomic Energy Agency, the Government of the Principality of Monaco and the Institute of Oceanography in Monaco. The program will have three major objectives. Firstly, it will be aimed at acquiring knowledge about the movement of water and marine organisms and the deposition of organic and inorganic matter. Secondly, there will be a special study of the distribution in marine organisms of radioactive materials already existing or that may be introduced into various locations. And thirdly, there will be a study of the effects of radioactive materials at various concentration levels on the marine ecology.

Terrain and building effects on the transport of radioactive material at a nuclear site

International Nuclear Information System (INIS)

Jeong, Hyojoon; Park, Misun; Jeong, Haesun; Hwang, Wontae; Kim, Eunhan; Han, Moonhee

2014-01-01

Highlights: • This study is to quantify the building and terrain effects on the atmospheric dispersion. • Statistical methods with AERMOD-PRIME and CFD were used. • To assess the risk in nuclear power plants, terrain and building effects have to be considered. - Abstract: This study identified the terrain and building effects on the atmospheric dispersion of radioactive materials at the Wolsong Nuclear Site. To analyze the atmospheric dispersion of radioactive materials, the AERMOD-PRIME model, CFD model and meteorological data from 2010 were used. The terrain and building effects on the atmospheric dispersion of radioactive materials within a 1 km radius of the site were statistically significant. The maximum concentration of the radioactive material increased by 7 times compared to the concentration when the terrain and building effects were not considered. It was found that the terrain and building influenced the decrease in the concentration of radioactive material in a concentric circle with a 914 m radius from the center of the site. The concentration of radioactive material in a concentric circle with a 350 m radius was two-times higher than the concentration estimated at the backside of the building, which is the downwind side, without any consideration of the terrain and building effects. In consideration of the Korean situation, in which multiple nuclear reactors are built on the same nuclear site, it is necessary to evaluate the risk that may affect workers and nearby residents by reflecting the terrain and building effects

Metrological system for y-ray spectrometry measurement of the specific activity and mass fraction of natural radioactive elements in soil and rock samples

International Nuclear Information System (INIS)

Khaikovich, I.M.; Fominykh, V.I.; Kirisyuk, E.M.; Belyachkov, Y.A.

1994-01-01

In the last few years a great deal of attention has been devoted to the study of the radiation conditions, which in some regions change markedly as a result of intense human activity. One reason for radioactive contamination of an area is dissemination during extraction and processing of radioactive ores or other minerals of natural radioactive elements with a high content of potassium, uranium (radium), and thorium. Estimation of the level of radioactive contamination is one of the main problems of ecological monitoring, and the quality of the measurements sometimes plays a deciding role in the fate of the object being investigated. This also pertains to, in particular, estimation of radioactive contamination of minerals employed for building homes and factories and other industrial structures. In order to draw unequivocal and well-founded conclusions from measurements of the content of natural radioactive elements in soil and rock samples, collected at the object being investigated, a great deal of attention must be devoted during the organization of the measurements to the metrological system

Field manual for geohydrological sampling as applied to the radioactive waste disposal program

International Nuclear Information System (INIS)

Levin, M.

1983-08-01

This report serves as a manual for geohydrological sampling as practised by NUCOR's Geology Department. It discusses systematically all aspects concerned with sampling and stresses those where negligence has caused complications in the past. Accurate, neat and systematic procedures are emphasised. The report is intended as a reference work for the field technician. Analytical data on water samples provide an indication of the geohydrological processes taking place during the interaction between groundwater and the enclosing aquifers. It is possible to identify water bodies, using some of a multitude of parameters such as major ions, trace elements and isotopes which may give clues as to the origin, directions of flow and age of groundwater bodies. The South African Radioactive Waste Project also requires this information for determining the direction of migration of the radionuclides in the environment in the event of a spillage. The sampling procedures required for water, and in particular groundwater, must be applied in such a manner that the natural variation of dissolved species is not disturbed to any significant degree. With this in mind, the operator has to exercise meticulous care during initial preparation, collection, storing, preserving and handling of the water samples. This report is a field manual and describes the procedures adopted for the Radwaste Project geohydrological investigations in the Northwest Cape

Solidification of liquid radioactive concentrates by fixation with cement

International Nuclear Information System (INIS)

Pekar, A.; Breza, M.; Timulak, J.; Krajc, T.

1985-01-01

In testing the technology of liquid radioactive wastes cementation, the effect was mainly studied of the content of boric acid and its salts on cement solidification, the effect of additives on radionuclide leachability and the effect of the salt content on the cementation product. On the basis of experimental work carried out on laboratory scale with model samples and samples of radioactive concentrate from the V-1 nuclear power plant, the following suitable composition of the cementation mixture was determined: 40% Portland cement, 40% zeolite containing material and 20% power plant ash. The most suitable ratio of liquid radioactive wastes and the cementation mixture is 0.5. As long as in such case the salt content of the concentrate ranges between 20 and 25%, the cementation product will have a maximum salt content of 10% and a leachability of the order of 10 -3 to 10 -4 g/cm 2 per day with a mechanical strength allowing safe handling. It was also found that the quality processing of the cement paste with degassing, e.g., by vibration, is more effective for the production of a pore-free cementation product than the application of various additives which are supposed to eliminate pore formation. (Z.M.)

Laboratory Enrichment of Radioactive Assemblages and Estimation of Thorium and Uranium Radioactivity in Fractions Separated from Placer Sands in Southeast Bangladesh

International Nuclear Information System (INIS)

Sasaki, Takayuki; Rajib, Mohammad; Akiyoshi, Masafumi; Kobayashi, Taishi; Takagi, Ikuji; Fujii, Toshiyuki; Zaman, Md. Mashrur

2015-01-01

The present study reports the likely first attempt of separating radioactive minerals for estimation of activity concentration in the beach placer sands of Bangladesh. Several sand samples from heavy mineral deposits located at the south-eastern coastal belt of Bangladesh were processed to physically upgrade their radioactivity concentrations using plant and laboratory equipment. Following some modified flow procedure, individual fractions were separated and investigated using gamma-ray spectrometry and powder-XRD analysis. The radioactivity measurements indicated contributions of the thorium and uranium radioactive series and of 40 K. The maximum values of 232 Th and 238 U, estimated from the radioactivity of 208 Tl and 234 Th in secular equilibrium, were found to be 152,000 and 63,300 Bq/kg, respectively. The fraction of the moderately conductive part in electric separation contained thorium predominantly, while that of the non-conductive part was found to be uranium rich. The present arrangement of the pilot plant cascade and the fine tuning of setting parameters were found to be effective and economic separation process of the radioactive minerals from placer sands in Bangladesh. Probable radiological impacts and extraction potentiality of such radioactive materials are also discussed

Implication of sample preparation procedures in determination of 137Cs radioactivity in muscle of marine organisms and the radioactivity concentration in the recent years

International Nuclear Information System (INIS)

Oikawa, Shinji; Isoyama, Naohiko; Misonoo, Jun

2009-01-01

Long-term fluctuation of the yield and ash content of muscle dissected from marine organisms were investigated for establishing a standard of pretreatment procedure based on the data on radioactivity analyses of various biological samples such as fish and shellfish which were collected from 15 sea areas adjacent to nuclear power stations in Japan. The muscle yield in terms of the percentage of muscle weight to the whole raw weight as well as ash content were obtained for 53 species during the period from 1983 to 2007 and subjected to a statistical scrutiny. There was no significant change in general in the muscle yield and ash content, with the exception of some species due to modification of pretreatment method. However those exceptions would not have resulted in a critical change of the level of 137 Cs concentration in marine organisms as a whole in the sea areas of concern, because it was usually expressed as the average for three different species in the present study. The ash content would be useful, nevertheless, as an index to assure the comparability of sample preparation technique. The 137 Cs radioactivity concentration in muscle of marine organisms gradually decreased year by year from 1990 after the Chernobyl nuclear accident, and would not be more than 0.24 Bq/kg-wet, the maximum level during 2003 to 2007, in the future from the viewpoint of fail-safe approaching. (author)

Bulletin of the radioactivity. No. 83. January-December, 1999

International Nuclear Information System (INIS)

2001-01-01

This report contains the result of observations by the Japan Meteorological Agency (JMA) of atmospheric and seawater radioactivity for the year 1999. The sampling, measurement methods and results of gross beta-radioactivity in precipitation, radioactivity in airborne dust, monthly mean 90 Sr concentration in airborne dust, gross beta-radioactivity in seawater, deposition of 89 Sr, 90 Sr and 137 Cs, natural background radioactivity and vertical distribution of atmospheric radioactivity are described. The results of special observations on the criticality accident at an uranium processing plant, Tokai-mura, Japan showed that gamma-ray spectrum analysis in airborne dust indicated Cs-137 ND (lower than detection limit) and I-131 ND in Sendai and Tokyo at sampling at 99/10/1. 09h-99/10/1,14h and in Tsukuba at sampling 99/09/30, 09h-99/10/01, 09h. Gross beta-radioactivity in precipitation showed 40 MBq/km 2 deposition in Hachijo-jima at sampling 99/09/30,09h-99/10/01, 09h, but no precipitation in Sendai, Akita, Tokyo and Wajima. Mean gamma-radiation dose rate in Wajima indicated 9.8 cps at monitoring 99/09/30-99/10/01,15h. (S.Y.)

Bonding of radioactive contamination. IV. Effect of surface finish

International Nuclear Information System (INIS)

Rankin, W.N.

1983-01-01

The mechanisms by which radioactive contamination would be bonded to a DWPF canister are being investigated. Previous investigations in this series have examined the effects of temperature, oxidation before contamination, and atmosphere composition control on the bonding of contamination. This memorandum describes the results of tests to determine the effect of special surface finishes on the bonding of contamination to waste glass canisters. Surface pretreatments which produce smoother canister surfaces actually cause radioactive contamination to be more tightly bonded to the metal surface than on an untreated surface. Based on the results of these tests it is recommended that the canister surface finish be specified as having a bright cold rolled mill finish equivalent to ASTM No. 2B. 7 references, 3 figures, 3 tables

Statistical analysis of radioactivity in the environment

International Nuclear Information System (INIS)

Barnes, M.G.; Giacomini, J.J.

1980-05-01

The pattern of radioactivity in surface soils of Area 5 of the Nevada Test Site is analyzed statistically by means of kriging. The 1962 event code-named Smallboy effected the greatest proportion of the area sampled, but some of the area was also affected by a number of other events. The data for this study were collected on a regular grid to take advantage of the efficiency of grid sampling

Radioactivity of some dried fruits

International Nuclear Information System (INIS)

Akhmedova, G.; Mamatkulov, O.B.; Hushmuradov, Sh.H.

2004-01-01

Full text: Radioactivity radiation from natural and artificial sources often acts at the same time in complicated combinations and without exception on all inhabitants of our planet. Natural and artificial radioactive isotopes pass into living organism by biological chain: soil-water-air-plants-foodstuffs-person and can be sources of inside irradiation. Accumulation of radionuclides in living organism in large quantities limit permissible concentration (LPC) can lead to pathological changes in organism. With above mentioned at the radioecological investigations, researches and control of changes of radionuclides concentration in environmental objects have important interests. Investigations of determination of radioactivity of environmental objects, which began in 1960 by professor Muso Muminov are continued in the department of nuclear physics of Samarkand State University. We work out semiconducting gamma-spectrometric method of determination of radionuclides concentration in weak -active environmental samples. We investigated radioactivity of different samples of natural environment and generalized results. In this work the results of investigation of radioactivity of same dried fruits are presented. The spectra of γ-radiation of following dried fruits as grapes, apricot, apple and peach was investigated. In measured gamma-radiation spectra of these samples gamma-transitions of 226 Ra, 232 Th, 40 K natural radionuclides and product of 137 Cs division. The specific gamma-activities these radionuclides were determined. The 40 K have most specific activity and 137 Cs - least. The calculated quantities of specific gamma-activity of radionuclides in gamma-spectra of investigated samples can replace to following row: 40 K > 232 Th > 226 Ra > 137 Cs

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

Thermal effects on clay rocks for deep disposal of high-level radioactive waste

Directory of Open Access Journals (Sweden)

Chun-Liang Zhang

2017-06-01

Full Text Available Thermal effects on the Callovo-Oxfordian and Opalinus clay rocks for hosting high-level radioactive waste were comprehensively investigated with laboratory and in situ experiments under repository relevant conditions: (1 stresses covering the range from the initial lithostatic state to redistributed levels after excavation, (2 hydraulic drained and undrained boundaries, and (3 heating from ambient temperature up to 90 °C–120 °C and a subsequent cooling phase. The laboratory experiments were performed on normal-sized and large hollow cylindrical samples in various respects of thermal expansion and contraction, thermally-induced pore water pressure, temperature influences on deformation and strength, thermal impacts on swelling, fracture sealing and permeability. The laboratory results obtained from the samples are consistent with the in situ observations during heating experiments in the underground research laboratories at Bure and Mont-Terri. Even though the claystones showed significant responses to thermal loading, no negative effects on their favorable barrier properties were observed.

Radioactivity and wildlife

International Nuclear Information System (INIS)

Kennedy, V.H.; Horrill, A.D.; Livens, F.R.

1990-01-01

The official assumption is that if levels of radioactivity are safe for humans, they are safe for wildlife too. NCC sponsored a research project by the Institute of Terrestrial Ecology to find out what was known in this field. It appears that the assumption is justified to a certain extent in that mammals are identified as the organisms most vulnerable to the damaging effects of radioactivity. Other general principles are put forward: where there are radioactive discharges to the marine environment, coastal muds and saltmarshes can be particularly contaminated; upland habitats, with low nutrient status and subject to high rainfall, are likely to accumulate radioactivity from atmospheric discharges (e.g. Chernobyl, the wildlife effects of which are reported here). The document concludes that no deleterious effects of radioactivity on wild plants and animals have been detected in the UK, but acknowledges that there are still many gaps in our knowledge of the behaviour of radioisotopes in the natural environment. (UK)

Surveillance of the environmental radioactivity

International Nuclear Information System (INIS)

Schneider, Th.; Gitzinger, C.; Jaunet, P.; Eberbach, F.; Clavel, B.; Hemidy, P.Y.; Perrier, G.; Kiper, Ch.; Peres, J.M.; Josset, M.; Calvez, M.; Leclerc, M.; Leclerc, E.; Aubert, C.; Levelut, M.N.; Debayle, Ch.; Mayer, St.; Renaud, Ph.; Leprieur, F.; Petitfrere, M.; Catelinois, O.; Monfort, M.; Baron, Y.; Target, A.

2008-01-01

The objective of these days was to present the organisation of the surveillance of the environmental radioactivity and to allow an experience sharing and a dialog on this subject between the different actors of the radiation protection in france. The different presentations were as follow: evolution and stakes of the surveillance of radioactivity in environment; the part of the European commission, regulatory aspects; the implementation of the surveillance: the case of Germany; Strategy and logic of environmental surveillance around the EDF national centers of energy production; environmental surveillance: F.B.F.C. site of Romans on Isere; steps of the implementation 'analysis for release decree at the F.B.F.C./C.E.R.C.A. laboratory of Romans; I.R.S.N. and the environmental surveillance: situation and perspectives; the part of a non institutional actor, the citizenship surveillance done by A.C.R.O.; harmonization of sampling methods: the results of inter operators G.T. sampling; sustainable observatory of environment: data traceability and samples conservation; inter laboratories tests of radioactivity measurements; national network of environmental radioactivity measurement: laboratories agreements; the networks of environmental radioactivity telemetry: modernization positioning; programme of observation and surveillance of surface environment and installations of the H.A.-M.A.V.L. project (high activity and long life medium activity); Evolution of radionuclides concentration in environment and adaptation of measurements techniques to the surveillance needs; the national network of radioactivity measurement in environment; modes of data restoration of surveillance: the results of the Loire environment pilot action; method of sanitary impacts estimation in the area of ionizing radiations; the radiological impact of atmospheric nuclear tests in French Polynesia; validation of models by the measure; network of measurement and alert management of the atmospheric

Urine sample collection protocols for bioassay samples

Energy Technology Data Exchange (ETDEWEB)

MacLellan, J.A.; McFadden, K.M.

1992-11-01

In vitro radiobioassay analyses are used to measure the amount of radioactive material excreted by personnel exposed to the potential intake of radioactive material. The analytical results are then used with various metabolic models to estimate the amount of radioactive material in the subject`s body and the original intake of radioactive material. Proper application of these metabolic models requires knowledge of the excretion period. It is normal practice to design the bioassay program based on a 24-hour excretion sample. The Hanford bioassay program simulates a total 24-hour urine excretion sample with urine collection periods lasting from one-half hour before retiring to one-half hour after rising on two consecutive days. Urine passed during the specified periods is collected in three 1-L bottles. Because the daily excretion volume given in Publication 23 of the International Commission on Radiological Protection (ICRP 1975, p. 354) for Reference Man is 1.4 L, it was proposed to use only two 1-L bottles as a cost-saving measure. This raised the broader question of what should be the design capacity of a 24-hour urine sample kit.

Urine sample collection protocols for bioassay samples

Energy Technology Data Exchange (ETDEWEB)

MacLellan, J.A.; McFadden, K.M.

1992-11-01

In vitro radiobioassay analyses are used to measure the amount of radioactive material excreted by personnel exposed to the potential intake of radioactive material. The analytical results are then used with various metabolic models to estimate the amount of radioactive material in the subject's body and the original intake of radioactive material. Proper application of these metabolic models requires knowledge of the excretion period. It is normal practice to design the bioassay program based on a 24-hour excretion sample. The Hanford bioassay program simulates a total 24-hour urine excretion sample with urine collection periods lasting from one-half hour before retiring to one-half hour after rising on two consecutive days. Urine passed during the specified periods is collected in three 1-L bottles. Because the daily excretion volume given in Publication 23 of the International Commission on Radiological Protection (ICRP 1975, p. 354) for Reference Man is 1.4 L, it was proposed to use only two 1-L bottles as a cost-saving measure. This raised the broader question of what should be the design capacity of a 24-hour urine sample kit.

ORNL radioactive waste operations

International Nuclear Information System (INIS)

Sease, J.D.; King, E.M.; Coobs, J.H.; Row, T.H.

1982-01-01

Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards

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.

An assessment of radioactivity in the environs of a titanium dioxide plant at Bunbury, Western Australia

International Nuclear Information System (INIS)

Cooper, M.B.; Williams, G.A.

1984-03-01

A study of radioactivity levels in environmental samples collected from the environs of a ttanium dioxide plant at Bunbury in Western Australia is described. Radioactivity levels were determined in samples of sediment, water, algae and seafood (crabs and mussels) from the Leschenault Inlet, close to the site at which the plant's liquid effluent is disposed, and from other areas along the south-west coast. Samples of town drinking water were also analysed. Radioactivity levels in the ilmenite feed and effluent of the plant are approximately half those observed in an earlier study. There is evidence for an enhancement of radionuclide concentrations in sediment from Leschenault Inlet originating from the plant effluent. Despite this effect, radioactivity levels in the sediment of the Inlet are no greater than those that occur at certain other locations along the south-west coast. The investigation of radioactivity levels in water, algae and seafood indicates that the only significant transfer of radionuclides from the sediment is the bioaccumulation of radium in algae. There is effectively no risk to the health of members of the public who consume crab flesh or mussels from Leschenault Inlet

The Tradescantia micronucleus assay is a highly sensitive tool for the detection of low levels of radioactivity in environmental samples.

Science.gov (United States)

Mišík, Miroslav; Krupitza, Georg; Mišíková, Katarina; Mičieta, Karol; Nersesyan, Armen; Kundi, Michael; Knasmueller, Siegfried

2016-12-01

Environmental contamination with radioactive materials of geogenic and anthropogenic origin is a global problem. A variety of mutagenicity test procedures has been developed which enable the detection of DNA damage caused by ionizing radiation which plays a key role in the adverse effects caused by radioisotopes. In the present study, we investigated the usefulness of the Tradescantia micronucleus test (the most widely used plant based genotoxicity bioassay) for the detection of genetic damage caused by environmental samples and a human artifact (ceramic plate) which contained radioactive elements. We compared the results obtained with different exposure protocols and found that direct exposure of the inflorescences is more sensitive and that the number of micronuclei can be further increased under "wet" conditions. The lowest dose rate which caused a significant effect was 1.2 μGy/h (10 h). Comparisons with the results obtained with other systems (i.e. with mitotic cells of higher plants, molluscs, insects, fish and human lymphocytes) show that the Tradescantia MN assay is one to three orders of magnitude more sensitive as other models, which are currently available. Taken together, our findings indicate that this method is due to its high sensitivity a unique tool, which can be used for environmental biomonitoring in radiation polluted areas. Copyright © 2016 Elsevier Ltd. All rights reserved.

Radioactive ores from Agostinho field, Pocos de Caldas (MG), Brazil

International Nuclear Information System (INIS)

Fujimori, K.

1974-01-01

Aiming to characterize the radioactive minerals of Campo Agostinho, Pocos de Caldas - Brazil, the survey of all natural radiactive elements and their geochemical behaviors, decays and radioactive equilibrium was done. Several models of radioactive instability of the minerals or the radioactive samples were proposed to characterize the geochemistry and the mineralization of radioactive elements. The complete isotopic analysis of the elements was done by high resolution gamma spectrometry, using a Ge(Li) detector, at the temperature of liquid nitrogen, coupled to a multichannel analyser. The sample in radioactive equilibrium of Atomic Energy Comission of United States - A.S. n.6, NBL - New Brunswick Laboratory, was considered as standard sample. Fluorite, zircons, pirite, molibinite, rutile, anatase, niobophyllite, and in small ratio (bellow 0.1%) uranothorianite, coffinite, pyrochlore, monazite and apatite. (M.C.K.) [pt

Natural atmospheric radioactivity

International Nuclear Information System (INIS)

Renoux, A.

1986-01-01

After having summed up the different old or new units, used in radioactivity and radioprotection, the origins of atmospheric radioactivity are reported. Next the authors deal with the air content in radon, thoron and their radioactive descendants, insisting on the variations of the radon air content and on the radioactive balance between radon and its descendants. Then a few notions concerning the natural radioactive aerosol are developed: electric charge state, granulometric distribution. The possible effects of natural atmospheric radioactivity on man are studied with a distinction between inner irradiation and outer irradiation, an average assessment is shown. Finally the important problem of radon in inhabitations is approached [fr

Radioactivity distribution of the fruit trees ascribable to radioactive fall out. A study on stone fruits cultivated in low level radioactivity region

International Nuclear Information System (INIS)

Takata, Daisuke; Yasunaga, Eriko; Nakanishi, Tomoko M.; Sasaki, Haruto; Oshita, Seiichi; Tanoi, Keitaro

2012-01-01

After the accident of Fukushima Daiichi Nuclear Power Plant, radioactivity of fruit trees grown at an experimental farm of Nishi-Tokyo City in Tokyo, which was located about 230 km away from the power plant, was measured. Each organ of Japanese apricot and peach trees was taken at harvesting stage, respectively, and the radioactivity of 134 Cs and 137 Cs was measured. Although radioactivity of orchard soil and tree each organ were low generally, that of bark sampled from 3-old-year branch was as high as 1570 Bq/kg-dry weight. The total radioactivity of 134 Cs and 137 Cs in edible portion was far lower than that of the regulation level. (author)

Increasing for effectiveness of inspection of the use of radioactive substances well logging

International Nuclear Information System (INIS)

Hesty Rimadianny

2015-01-01

One of the utilization of nuclear power is the use of radioactive substances for well logging. To ensure the achievement of radiation safety and security in the use of radioactive substances for well logging activities BAPETEN carries out inspections in accordance with the mandate as sepulated in the Government Regulation No. 29 of 2008 on the Licensing Resource Utilization Ionizing Radiation and Nuclear Materials. Besides referring to the implementation of Government Regulation inspection also refers to BAPETEN Chairman Regulation No. 5 of 2009 on Radiation Safety in the Use of Radioactive material for well logging. In 2014, of 18 facilities inspected the most significant findings include the availability of equipment safety and security of radioactive substances, as well as the availability and suitability of documents and records of safety and security of radioactive substances for well logging activities. Based on these findings BAPETEN needs to make efforts to increase the effectiveness of inspections on the use of radioactive substances for well logging. Increasing the effectiveness of these inspections include a commitment for the frequency of well logging inspection, the number of qualified of inspectors in accordance with the established procedures and optimizing the law enforcement process which includes the application of administrative sanctions in the form of a written warning, license suspension, revocation until reporting to law enforcement. Besides, BAPETEN need to improve the effectiveness of outreach programs and legal guidance as a precaution in the long run. (author)

Survey monitoring of environmental radioactivity in Gangneung area

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Hwa; An, Mi Jung [Gangnung Regional Radiation Monitoring Station, Gangneung (Korea, Republic of)

2003-12-15

The objectives of the project are to get a systematic data for the distribution of environmental radioactivity levels in Gangnung provinces, and use them as a baseline data for the health of the peoples. To monitor the environmental radiation/radioactivity, gross beta activities and gamma exposure rate in the airborne-dust, fallout, precipitation and tap water were measured in Gangnung province during the period of January 1 - December 31, 2003. Waters from drinking water reservoirs, agricultural and marine products were sampled and measured by the HPGe(High Purity Ge)detector for the analysis from some selected areas to make sure of the effect of the fallout due to the atmospheric weapons test. The radioactivity in Kangnung was all about the past data.

Survey monitoring of environmental radioactivity in Gangneung area

Energy Technology Data Exchange (ETDEWEB)

An, Dong Wan; An, Mi Jeong [Gangnung Regional Radiation Monitoring Station, Gangneung (Korea, Republic of)

2001-12-15

The objectives of the project are to get a systematic data for the distribution of environmental radioactivity levels in Gangnung provinces, and use them as a baseline data for the health of the peoples. To monitor the environmental radiation/radioactivity, gross beta activities and gamma exposure rate in the airborne-dust, fallout, precipitation and tap water were measured in Kangnung province during the period of January 1- December 31, 2001. Waters from drinking water reservoirs, agricultural and marine products were sampled and measured by the HPGe(High Purity Ge)detector for the analysis from some selected areas to make sure of the effect of the fallout due to the atmospheric weapons test. The radioactivity in Kangnung was all about the past data.

Survey monitoring of environmental radioactivity in Gangneung area

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Hwa; An, Mi Jung [Gangnung Regional Radiation Monitoring Station, Gangneung (Korea, Republic of)

2002-12-15

The objectives of the project are to get a systematic data for the distribution of environmental radioactivity levels in Gangnung provinces, and use them as a baseline data for the health of the peoples. To monitor the environmental radiation/radioactivity, gross beta activities and gamma exposure rate in the airborne-dust, fallout, precipitation and tap water were measured in Kangnung province during the period of January 1- December 31, 2002. Waters from drinking water reservoirs, agricultural and marine products were sampled and measured by the HPGe(High Purity Ge)detector for the analysis from some selected areas to make sure of the effect of the fallout due to the atmospheric weapons test. The radioactivity in Kangnung was all about the past data.

Environmental radioactivity networks in Italy, 1994-1997

International Nuclear Information System (INIS)

Belli, M.; Notaro, M.; Rosamilia, S.; Sansone, U.

1999-01-01

This report contains the environmental radioactivity data collected in Italy from 1994 to 1997 by the National Environmental Radioactivity Networks of Italy. The National Environmental Protection Agency (ANPA) is law-fully responsible for publishing the environmental and dietary contamination data, provided by the organisations participating to the National Environmental Radioactivity Networks. The complete list of the participants is reported at the end of the present document. The National Environmental Radioactivity Networks of Italy are aimed at survey of the pattern of environmental and dietary contamination in order to assess the radiation doses which the Italian population may receive. The sampling networks have been designed on regional basis, to provide information on the average extent of environmental and dietary contamination. The sampling programmes are planned to obtain representative samples able to reveal the average situation both in time and space. To guarantee that the laboratories of the organisations participating to the National Environmental Radioactivity Networks, perform measurements with a certain degree of accuracy and maintain the quality of their systems, the National Environmental Protection Agency organises yearly an intercalibration programme of the analytical methods used for measuring radioactivity in food and environmental samples. The calibration programme is performed with the collaboration of the National Institute of Ionising Radiation Metrology (ENEA). Routine tests with transfer standards are used for accurate calibration, so that the results can be traceable to a common reference point [it

Biogenesis of tritiated and carbon-14 methane from low-level radioactive waste

International Nuclear Information System (INIS)

Francis, A.J.; Dobbs, S.; Doering, R.F.

1980-01-01

Methane bacteria were detected in leachate samples collected from commercial low-level radioactive waste disposal sites. Significant amounts of tritiated and carbon-14 methane were generated by a mixed methanogenic culture from a leachate sample collected from the low-level radioactive waste disposal site, Maxey Flats, KY. Tritiated methane was produced by methane bacteria from synthetic media containing 2 mCi of tritium as tritiated water or tritiated acetate, and the level of tritium added to the medium had no effect on methanogenesis. Under anaerobic conditions the organic compounds containing 14 C and 3 H activity and tritiated water in the waste are metabolized by microorganisms and they produce radioactive gases which escape into the environment from the disposal sites. 4 figures, 3 tables

A simple and feasible method of effectiveness evaluation on radioactive decontamination action

International Nuclear Information System (INIS)

Chen Lin; Geng Xiaobing; Sun Jian; Wang Jihong; Guo Lijun

2012-01-01

Radioactive decontamination is a vital task in nuclear emergency response. The assessment of decontamination effectiveness is of great importance to decision-making. An index system for effectiveness evaluation of radioactive decontamination action in nuclear emergency response is produced. A method of decontamination effectiveness evaluation based on analytic hierarchy process and fuzzy comprehensive evaluation is presented. Index weights are determined through analytic hierarchy process. And scores of objects in each hierarchy are judged by fuzzy comprehensive evaluation. Then comprehensive effectiveness of the top object can be obtained, which can offer a basis for decision-making of decontamination action. (authors)

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.

Sampling methods and non-destructive examination techniques for large radioactive waste packages

International Nuclear Information System (INIS)

Green, T.H.; Smith, D.L.; Burgoyne, K.E.; Maxwell, D.J.; Norris, G.H.; Billington, D.M.; Pipe, R.G.; Smith, J.E.; Inman, C.M.

1992-01-01

Progress is reported on work undertaken to evaluate quality checking methods for radioactive wastes. A sampling rig was designed, fabricated and used to develop techniques for the destructive sampling of cemented simulant waste using remotely operated equipment. An engineered system for the containment of cooling water was designed and manufactured and successfully demonstrated with the drum and coring equipment mounted in both vertical and horizontal orientations. The preferred in-cell orientation was found to be with the drum and coring machinery mounted in a horizontal position. Small powdered samples can be taken from cemented homogeneous waste cores using a hollow drill/vacuum section technique with the preferred subsampling technique being to discard the outer 10 mm layer to obtain a representative sample of the cement core. Cement blends can be dissolved using fusion techniques and the resulting solutions are stable to gelling for periods in excess of one year. Although hydrochloric acid and nitric acid are promising solvents for dissolution of cement blends, the resultant solutions tend to form silicic acid gels. An estimate of the beta-emitter content of cemented waste packages can be obtained by a combination of non-destructive and destructive techniques. The errors will probably be in excess of +/-60 % at the 95 % confidence level. Real-time X-ray video-imaging techniques have been used to analyse drums of uncompressed, hand-compressed, in-drum compacted and high-force compacted (i.e. supercompacted) simulant waste. The results have confirmed the applicability of this technique for NDT of low-level waste. 8 refs., 12 figs., 3 tabs

Contamination and decontamination of vehicles driven in radioactive areas

International Nuclear Information System (INIS)

Ulvsand, T.; Nygren, U.

1999-03-01

There is reason to ask whether it is beneficial to decontaminate vehicles, in view of the great effort applied. If the level of contamination is low before the decontamination process, then the cost is not motivated, even if the decontamination is shown to be effective in relative terms. The report describes two trials at the National NBC Defence School in Umeaa and one trial at the French test site in Bourges. The aim is to investigate how vehicles are contaminated and at which ground deposition levels troublesome levels of contamination will arise. In the trials, a non-radioactive agent substituting real radioactivity was used. The trials in Sweden so far have used the oversnow vehicle BV 206, during both winter and summer conditions. The vehicles were driven a specific distance along a road on which a known amount of the test substance had been dispersed. Samples were taken on pre-determined areas on one side of the vehicles to measure the amount of test substance. Later, the vehicles continued along a 'clean' road where additional samples were taken, but on the other side of the vehicles. The largest amount of test substance was collected on the tracks and on the back of the vehicle. The tracks and mud-flaps were effectively decontaminated when the vehicles were driven along a clean road, while most of the contamination remained on the backside. The purpose of the trials in France was to compare the results from our non-radioactive and their radioactive method, based on the radioactive La-140. Due to ground conditions, the level of contamination on the vehicles was much less than in the trials in Umeaa, but the effect decontamination could be measured after all

Natural radioactivity measurements in building materials used in Samsun, Turkey.

Science.gov (United States)

Tufan, M Çagatay; Disci, Tugba

2013-01-01

In this study, radioactivity levels of 35 different samples of 11 commonly used building materials in Samsun were measured by using a gamma spectrometry system. The analysis carried out with the high purity Germanium gamma spectrometry system. Radioactivity concentrations of (226)Ra, (232)Th and (40)K range from 6 to 54 Bq kg(-1), 5 to 88 Bq kg(-1) and 6 to 1070 Bq kg(-1), respectively. From these results, radium equivalent activities, gamma indexes, absorbed dose rates and annual effective doses were calculated for all samples. Obtained results were compared with the available data, and it was concluded that all the investigated materials did not have radiological risk.

Natural and induced radioactivity in food

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-04-01

One of the first questions often asked about irradiated food is whether it is radioactive. Not many people understand that food and any natural substance contains natural radioactivity which can be measurable. It is therefore important to put the issue on natural radioactivity and possible induced radioactivity in food in perspective. While there is a clear consensus among the scientific community that no radioactivity is induced when food is irradiated by gamma rays from cobalt-60 or cesium-137, electron generated by a machine with energy less than 10 million electron volt (MeV) or X rays produced generated by a machine with energy less than 5 MeV. However, data to this effect were published many years ago and are not easy to find. As food irradiation is gaining wide acceptance in many countries, it was considered timely to compile data on natural and induced radioactivity in food into one document. We are grateful to A. Brynjolfsson, one of the few experts who have the knowledge on this subject as well as wide experience on food irradiation, who collected, compiled and evaluated all data on this subject into one report. This publication provides clear explanations not only why radioactivity cannot be induced in food irradiated by radiation sources mentioned above but to what extent the increase in dose or energy level of radiation sources would induce significantly radioactivity in food. The compilation of such data was prompted by a desire to increase the energy limit and the absorbed dose based on the need to irradiate thicker samples of food and to use sterilizing dose up to 60 kGy. This publication concluded that the increase in radiation background dose from consumption of food irradiated to an average dose up to 60 kGy with gamma rays from cobalt- 60 or cesium-137, with 10 MeV electrons or with 5 MeV X rays is insignificant. In addition, food irradiated with X ray with energy up to 7.5 MeV to a dose of 30 kGy has radioactivity well below natural

Natural and induced radioactivity in food

International Nuclear Information System (INIS)

2002-04-01

One of the first questions often asked about irradiated food is whether it is radioactive. Not many people understand that food and any natural substance contains natural radioactivity which can be measurable. It is therefore important to put the issue on natural radioactivity and possible induced radioactivity in food in perspective. While there is a clear consensus among the scientific community that no radioactivity is induced when food is irradiated by gamma rays from cobalt-60 or cesium-137, electron generated by a machine with energy less than 10 million electron volt (MeV) or X rays produced generated by a machine with energy less than 5 MeV. However, data to this effect were published many years ago and are not easy to find. As food irradiation is gaining wide acceptance in many countries, it was considered timely to compile data on natural and induced radioactivity in food into one document. We are grateful to A. Brynjolfsson, one of the few experts who have the knowledge on this subject as well as wide experience on food irradiation, who collected, compiled and evaluated all data on this subject into one report. This publication provides clear explanations not only why radioactivity cannot be induced in food irradiated by radiation sources mentioned above but to what extent the increase in dose or energy level of radiation sources would induce significantly radioactivity in food. The compilation of such data was prompted by a desire to increase the energy limit and the absorbed dose based on the need to irradiate thicker samples of food and to use sterilizing dose up to 60 kGy. This publication concluded that the increase in radiation background dose from consumption of food irradiated to an average dose up to 60 kGy with gamma rays from cobalt- 60 or cesium-137, with 10 MeV electrons or with 5 MeV X rays is insignificant. In addition, food irradiated with X ray with energy up to 7.5 MeV to a dose of 30 kGy has radioactivity well below natural

Laboratory Enrichment of Radioactive Assemblages and Estimation of Thorium and Uranium Radioactivity in Fractions Separated from Placer Sands in Southeast Bangladesh

Energy Technology Data Exchange (ETDEWEB)

Sasaki, Takayuki, E-mail: sasaki@nucleng.kyoto-u.ac.jp [Kyoto University, Department of Nuclear Engineering (Japan); Rajib, Mohammad [Bangladesh Atomic Energy Commission, Nuclear Minerals Unit, Atomic Energy Research Establishment (Bangladesh); Akiyoshi, Masafumi; Kobayashi, Taishi; Takagi, Ikuji [Kyoto University, Department of Nuclear Engineering (Japan); Fujii, Toshiyuki [Kyoto University, Research Reactor Institute (Japan); Zaman, Md. Mashrur [Bangladesh Atomic Energy Commission, Nuclear Minerals Unit, Atomic Energy Research Establishment (Bangladesh)

2015-06-15

The present study reports the likely first attempt of separating radioactive minerals for estimation of activity concentration in the beach placer sands of Bangladesh. Several sand samples from heavy mineral deposits located at the south-eastern coastal belt of Bangladesh were processed to physically upgrade their radioactivity concentrations using plant and laboratory equipment. Following some modified flow procedure, individual fractions were separated and investigated using gamma-ray spectrometry and powder-XRD analysis. The radioactivity measurements indicated contributions of the thorium and uranium radioactive series and of {sup 40}K. The maximum values of {sup 232}Th and {sup 238}U, estimated from the radioactivity of {sup 208}Tl and {sup 234}Th in secular equilibrium, were found to be 152,000 and 63,300 Bq/kg, respectively. The fraction of the moderately conductive part in electric separation contained thorium predominantly, while that of the non-conductive part was found to be uranium rich. The present arrangement of the pilot plant cascade and the fine tuning of setting parameters were found to be effective and economic separation process of the radioactive minerals from placer sands in Bangladesh. Probable radiological impacts and extraction potentiality of such radioactive materials are also discussed.

Radioactivity; La radioactivite

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

This pedagogical document presents the origin, effects and uses of radioactivity: where does radioactivity comes from, effects on the body, measurement, protection against radiations, uses in the medical field, in the electric power industry, in the food (ionization, radio-mutagenesis, irradiations) and other industries (radiography, gauges, detectors, irradiations, tracers), and in research activities (dating, preservation of cultural objects). The document ends with some examples of irradiation levels (examples of natural radioactivity, distribution of the various sources of exposure in France). (J.S.)

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

Comparative effect of radioactive radiation on roots in a coastal and ...

African Journals Online (AJOL)

The detection of the radiation levels in root crops from Ibeno (an oil producing area) and Uyo, (a non oil producing area) in Akwa Ibom state was carried out. The radioactivity level in Cassava, Potato, Sweet yam, water yam and cocoyam was investigated. Result shows that the radiation level in root samples in Uyo ranges ...

Development of radioactive seawater monitors, 1

International Nuclear Information System (INIS)

Fukushima, Masanori

1989-01-01

Applicability of some adsorptive materials to monitoring of radioactive seawater is generalized. Studied techniques that allow utilization of adsorptive materials in monitoring radioactive seawater are the substitute methods using sampled seawater or indicator plants such as gulfweed and the method using adsorptive materials for continuous monitoring of underwater radioactivity, the method using them for field measurement of under water radioactivity from a boat, and the method using an adsorptive material moored underwater for integration monitoring of underwater radioactivity. Selected adsorptive materials that were judged suitable for monitoring radioactive seawater is the one composed of some kind of adsorptive compound (manganese dioxide or ferrocyan cobalt potassium) fixed to crylic cellulose. This adsorptive material permits selective scavenging radioactive Cs, Mn, Co, Zn, Ce, Fe, Ru, Ra Th, Pu and Am from seawater. (aurhor)

Natural radioactivity and dose rates for soil samples around Tiruchirapalli, South India using γ-ray spectrometry

International Nuclear Information System (INIS)

Senthilkumar, Bojarajan; Manikandan, Sabapathy; Musthafa, Mohamed Saiyad

2012-01-01

The activity concentrations and the gamma-absorbed dose rates of the naturally occurring radionuclides 226 Ra, 232 Th, and 40 K were determined for 40 soil samples collected from Tiruchirapalli, South India, using γ-ray spectrometry. The average activity concentrations of 226 Ra, 232 Th, and 40 K in the soil samples were found to be 29.9, 39.0, and 369.7 Bq kg -1 , respectively. The measured activity concentrations of both 226 Ra and 40 K in the soil were lower than the world average, whereas, the activity of 232 Th was higher than the world average. The concentrations of these radionuclides were also compared with the average activity of the Indian soil. The radiological hazard index was calculated and compared with the internationally approved values. The average external absorbed gamma dose rate was observed to be 79.9 nGy h -1 , with a corresponding average annual effective dose of 97.9 mSv y -1 , which was above the world average values. The values of Ra eq and H ex were found to be within the criterion limit, whereas, the radioactivity level index (l γ ) and total gamma dose rate were above the worldwide average values. (author)

Determination of technetium-99 in environmental and radioactive waste samples

International Nuclear Information System (INIS)

Ferencova, M.; Peter Tkac, P.

2007-01-01

Technetium is known for its high mobility in a soil-water system in non-reducing aerobic condition and also high bio-availability for plants, because the most stable form of technetium in natural surface environment is pertechnetate which is highly soluble. The chemical form of technetium changes with environmental conditions. Concentration of technetium in the environment is very low, therefore many separation steps are needed for technetium determination. It has been developed a method for the routine determination of technetium-99 from environmental matrices and radioactive wastes using technetium-99m as an internal yield monitor. Technetium-99 is extracted from the soil samples with nitric acid. Many contaminants are co-precipitated with ferric hydroxide and technetium in the supernatant is pre-concentrated and further purified using anion exchange chromatography. Final separation of technetium was achieved by extraction with tetraphenylarsonium chloride in chloroform from sulphuric acid or pure water. The chemical yield is determined through the measurement of technetium-99m by scintillation counting system and the technetium-99 activity is measured using proportional counter after decay of the technetium-99m activity. Typical recoveries for this method are in the order 50-60 % (authors)

Recommendations for sampling for prevention of hazards in civil defense. On analytics of chemical, biological and radioactive contaminations. 2. ed.; Empfehlungen fuer die Probenahme zur Gefahrenabwehr im Bevoelkerungsschutz. Zur Analytik von chemischen, biologischen und radioaktiven Kontaminationen

Energy Technology Data Exchange (ETDEWEB)

Bachmann, Udo; Derakshani, Nahid; Drobig, Matthias; Koenig, Mario; Mentfewitz, Joachim; Prast, Hartmut; Uelpenich, Gerhard; Vidmayer, Marc; Wilbert, Stefan; Wolf, Manfred

2016-07-01

The recommendations for sampling for prevention of hazards in civil defense (analytics of chemical, biological and radioactive contaminations) cover the following topics: Requirements for sampling, description of the materials (chemical, biological and radioactive contaminated materials), decontamination, sample transport and protocol documents.

Environmental radioactivity survey in Andong

Energy Technology Data Exchange (ETDEWEB)

Yoon, Zi Hong; Jo, Kum Ju [Andong Regional Radioactivity Monitoring Station, Andong National Univ., Andong (Korea, Republic of)

2003-12-15

The objectives of the project are to monitor an abnormal level in Andong area and to provide a base line data on environmental radiation/radioactivity levels in case of any radiological emergency situation. The project is important in view of protecting the public health from the potential hazards of radiation and keeping up the clean environment. This report simonizes and interprets environmental radiation/radioactivity monitoring samples : Gamma exposure rates, airborne dust, precipitation, fall out and drinking-water. Environmental samples 2 kinds of indicator plant, 4 kinds of mushroom, 7 kinds of nut and seeds, and drinking waters. Among the all 2003 radiological monitoring and environmental data in Andong area were not found the extraordinary data. And a nation-wide environmental radiation/radioactivity level survey results were all background levels attributed to terrestrial and cosmic radiation.

Environmental radioactivity survey in Andong

Energy Technology Data Exchange (ETDEWEB)

Yoon, Zi Hong; Jo, Kum Ju [Andong Regional Radioactivity Monitoring Station, Andong National Univ., Andong (Korea, Republic of)

2002-12-15

The objectives of the project are to monitor an abnormal level in Andong area and to provide a base-line data on environmental radiation/radioactivity levels in case of any radiological emergency situation. The project is important in view of protecting the public health from the potential hazards of radiation and keeping up the clean environment. This report summarizes and interprets environmental radiation/radioactivity monitoring samples Gamma exposure rates, airborne dust, precipitation, fall-out and drinking-water. Environmental samples 2 kinds of indicator plant, 4 kinds of mushroom, 7 kinds of nut and seeds, and drinking waters. Among the all 2002 radiological monitoring and environmental data in Andong area were not found the extraordinary data. And a nation-wide environmental radiation/radioactivity level survey results were all background levels attributed to terrestrial and cosmic radiation.

Radioactive decontamination methods and their effectiveness as a function of terrain

Energy Technology Data Exchange (ETDEWEB)

Straume, T; Kellner, C R; Oswald, K M [California Univ., Mercury, NV (USA). Lawrence Radiation Lab.

1978-08-01

A large area of rugged terrain on the Nevada Test Site was contaminated following a spill of radioactively contaminated drilling mud. The contamination was shown to consist of /sup 103/Ru and /sup 106/(Ru-Rh) with total estimated activity at release time of 38 and 6 Ci, respectively. Several decontamination methods were used and their effectiveness assessed by determining the fraction of radioactivity remaining (FR) following each. In flat areas, the front end loader was by far the most efficient method, removing large quantities of dirt in relatively short periods of time. FRs of 10-/sup 22/ were achieved. In canyon areas, flushing with water was most effective on rocky surfaces with FRs of 10/sup -3/, while shoveling and bagging in evaporated mud collection ponds worked well and resulted in FRs of 10/sup -2/. The FR in rocky cracks was about 10/sup -1/ following flushing with water. In Locations where radioactive mud/water had not penetrated the ground surface to more than 1-2in., such as fine grain, flat compact dirt, vacuuming was very effective achieving FRs of 10/sup -3/. However, unless the contaminated area was very small (e.g. dropping from front end loading operations), vacuuming was too slow to be of practical value. Under the supervision of experienced radiation monitors, the radioactive mud spill area was safely cleaned up using, for the most part, standard earth moving equipment and personnel untrained in decontamination procedures.

Radioactive decontamination methods and their effectiveness as a function of terrain

International Nuclear Information System (INIS)

Straume, T.; Kellner, C.R.; Oswald, K.M.

1978-01-01

A large area of rugged terrain on the Nevada Test Site was contaminated following a spill of radioactively contaminated drilling mud. The contamination was shown to consist of 103 Ru and 106 [Ru-Rh] with total estimated activity at release time of 38 and 6 Ci, respectively. Several decontamination methods were used and their effectiveness assessed by determining the fraction of radioactivity remaining (FR) following each. In flat areas, the front end loader was by far the most efficient method, removing large quantities of dirt in relatively short periods of time. FRs of 10- 22 were achieved. In canyon areas, flushing with water was most effective on rocky surfaces with FRs of 10 -3 , while shoveling and bagging in evaporated mud collection ponds worked well and resulted in FRs of 10 -2 . The FR in rocky cracks was about 10 -1 following flushing with water. In Locations where radioactive mud/water had not penetrated the ground surface to more than 1-2in., such as fine grain, flat compact dirt, vacuuming was very effective achieving FRs of 10 -3 . However, unless the contaminated area was very small (e.g. dropping from front end loading operations), vacuuming was too slow to be of practical value. Under the supervision of experienced radiation monitors, the radioactive mud spill area was safely cleaned up using, for the most part, standard earth moving equipment and personnel untrained in decontamination procedures. (author)

Method Validation for the Gamma-ray Spectrometric Determination of Natural Radioactive Nuclides in NORM Samples - Method Validation for the Gamma-ray Spectrometric Determination of Natural Radionuclides in raw materials and by-products

Energy Technology Data Exchange (ETDEWEB)

Ji, Young-Yong; Lim, Jong-Myoung; Jang, Mee; Kim, Chang-Jong; Chung, Kun Ho; Kang, Mun Ja; Choi, Geun-Sik [Environmental Radioactivity Assessment Team, Korea Atomic Energy Research Institute, 111, Daedeok-daero 989, Yuseong, Daejeon, 305-353 (Korea, Republic of)

2014-07-01

It has established the 'Act on safety control of radioactive rays around living environment' in Korea, since 2011, to protect the public from natural occurring radioactive materials (NORM) and their by-products. The increasing concerns regarding the radioactivity of those materials therefore dictate many demands for the radioactive analysis for them. There are several methods to determine the concentration of natural radionuclides, such as {sup 235}U, {sup 238}U, {sup 226}Ra, {sup 232}Th, and so on, through a radiochemical analysis using an alpha spectrometer, mass spectrometer and liquid scintillation counter. However, gamma-ray spectroscopy still has an effect on the assessment of radioactive concentration for these nuclides and their progenies. To adapt a gamma spectrometer to the determination of natural radionuclides, the feasibility of their analysis methods should be first verified and validated with respect to accuracy and time and cost constraints. In general, one of the well-known processes in analyzing uranium with a gamma spectrometer is an indirect measurement using the secular equilibrium state with their progenies in a sample. This method, however, demands the time elapsed about 3 weeks to reach the equilibrium state between {sup 226}Ra and {sup 222}Rn and the sufficient integrity of a sample bottle to prevent the leakage of radon isotopes which is a form of noble gas. The simple and quick method is to directly measure a full energy absorption peak of 186.2 keV from {sup 226}Ra without the secular equilibrium state between {sup 226}Ra and {sup 222}Rn in the common sample bottle. However, this direct measurement also has difficulties about the interference with a full energy absorption peak of 185.7 keV from {sup 235}U. In this study, direct measurement with the interference correction technique, which uses several reference peaks for gamma-rays from {sup 235}U and {sup 234}Th, and indirect measurement, which means the identification of {sup

Preparation of in-house calibration source for the use in radioactivity analysis of the environmental samples. Consideration of homogeneity

International Nuclear Information System (INIS)

Aba, A.; Ismaeel, A.

2013-01-01

An in-house reference material has been prepared in Kuwait Institute for Scientific Research radioecology laboratory, for quality control purposes of gamma spectrometer systems. The material contains a known amount of uranium ore reference material (prepared by the International Atomic Energy Agency and coded as IAEA-RGU-1) which is mixed with marine sediment collected from Kuwait bay. The IAEA-RGU-1 has been certified that it is in equilibrium state with the decay daughters, and stable to be used for quality control purposes. Nevertheless, the homogeneous distribution of the doped material with the prepared source should be verified. This has been examined using gamma spectrometry measurements in conjunction with analysis of variance statistical tools, Dixon, box plots and Grubbs tests. The calculated total uncertainty has been utilized to establish the recommended specific activity ranges of 226 Ra, 224 Th, 214 Pb, 214 Bi and 210 Pb radioisotopes in the prepared source. The obtained results showed that the estimated uncertainty arising from the sample inhomogeneity has a significant contribution in the total uncertainty. The stability control charts of the ultra-low background gamma spectrometry system demonstrated the suitability of the prepared material for the purpose of quality control. However, the emitted gamma-rays from the prepared source covers the required energy range for determination of natural and artificial radionuclides in different species of environmental samples such as marine sediment, soil samples, and samples contaminated by naturally occurring radioactive material produced by oil industry. In addition, the material might be used for system calibration in case its traceability is proven. The experimental data revealed the significance of the homogeneity in preparing environmental samples for radioactivity measurements; in particular when small sample quantities of environmental samples are required to be analyzed. (author)

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)

Radioactive waste vitrification offgas analysis proposal

International Nuclear Information System (INIS)

Nelson, C.W.; Morrey, E.V.

1993-11-01

Further validation of the Hanford Waste Vitrification Plant (HWVP) feed simulants will be performed by analyzing offgases during crucible melting of actual waste glasses and simulants. The existing method of vitrifying radioactive laboratory-scale samples will be modified to allow offgas analysis during preparation of glass for product testing. The analysis equipment will include two gas chromatographs (GC) with thermal conductivity detectors (TCD) and one NO/NO x analyzer. This equipment is part of the radioactive formating offgas system. The system will provide real-time analysis of H 2 , O 2 , N 2 , NO, N 2 O, NO 2 , CO, CO 2 , H 2 O, and SO 2 . As with the prior melting method, the product glass will be compatible with durability testing, i.e., Product Consistency Test (PCT) and Material Characterization Center (MCC-1), and crystallinity analysis. Procedures have been included to ensure glass homogeneity and quenching. The radioactive glass will be adaptable to Fe +2 /ΣFe measurement procedures because the atmosphere above the melt can be controlled. The 325 A-hot cell facility is being established as the permanent location for radioactive offgas analysis during formating, and can be easily adapted to crucible melt tests. The total costs necessary to set up and perform offgas measurements on the first radioactive core sample is estimated at $115K. Costs for repeating the test on each additional core sample are estimated to be $60K. The schedule allows for performing the test on the next available core sample

Analysis of radioactivity concentration in naturally occurring radioactive materials used in coal-fired plants in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Yong Geom; Kim, Si Young; Ji, Seung Woo; Park, Il; Kim, Min Jun; Kim, Kwang Pyo [Dept. of Nuclear Engineering, Kyung Hee University, Yongin (Korea, Republic of)

2017-02-15

Coals and coal ashes, raw materials and by-products, in coal-fired power plants contain naturally occurring radioactive materials (NORM). They may give rise to internal exposure to workers due to inhalation of airborne particulates containing radioactive materials. It is necessary to characterize radioactivity concentrations of the materials for assessment of radiation dose to the workers. The objective of the present study was to analyze radioactivity concentrations of coals and by-products at four coal-fired plants in Korea. High purity germanium detector was employed for analysis of uranium series, thorium series, and potassium 40 in the materials. Radioactivity concentrations of {sup 226}Ra, {sup 228}Ra, and {sup 40}K were 2⁓53 Bq kg{sup -1}, 3⁓64 Bq kg{sup -1}, and 14⁓431 Bq kg{sup -1} respectively in coal samples. For coal ashes, the radioactivity concentrations were 77⁓133 Bq kg{sup -1}, 77⁓105 Bq kg{sup -1}, and 252⁓372 Bq kg{sup -1} in fly ash samples and 54⁓91 Bq kg{sup -1}, 46⁓83 Bq kg{sup -1}, and 205⁓462 Bq kg{sup -1} in bottom ash samples. For flue gas desulfurization (FGD) gypsum, the radioactivity concentrations were 3⁓5 Bq kg{sup -1}, 2⁓3 Bq kg{sup -1}, and 22⁓47 Bq kg{sup -1}. Radioactivity was enhanced in coal ash compared with coal due to combustion of organic matters in the coal. Radioactivity enhancement factors for {sup 226}Ra, {sup 228}Ra, and {sup 40}K were 2.1⁓11.3, 2.0⁓13.1, and 1.4⁓7.4 for fly ash and 2.0⁓9.2, 2.0⁓10.0, 1.9⁓7.7 for bottom ash. The database established in this study can be used as basic data for internal dose assessment of workers at coal-fred power plants. In addition, the findings can be used as a basic data for development of safety standard and guide of Natural Radiation Safety Management Act.

A kinematic model to estimate effective dose of radioactive substances in a human body

Science.gov (United States)

Sasaki, S.; Yamada, T.

2013-05-01

The great earthquake occurred in the north-east area in Japan in March 11, 2011. Facility system to control Fukushima Daiichi nuclear power station was completely destroyed by the following giant tsunami. From the damaged reactor containment vessels, an amount of radioactive substances had leaked and diffused in the vicinity of this station. Radiological internal exposure became a serious social issue both in Japan and all over the world. The present study provides an easily understandable, kinematic-based model to estimate the effective dose of radioactive substances in a human body by simplifying the complicated mechanism of metabolism. International Commission on Radiological Protection (ICRP) has developed a sophisticated model, which is well-known as a standard method to calculate the effective dose for radiological protection. However, owing to that ICRP method is fine, it is rather difficult for non-professional people of radiology to gasp the whole images of the movement and the influences of radioactive substances in a human body. Therefore, in the present paper we propose a newly-derived and easily-understandable model to estimate the effective dose. The present method is very similar with the traditional and conventional tank model in hydrology. Ingestion flux of radioactive substances corresponds to rain intensity and the storage of radioactive substances to the water storage in a basin in runoff analysis. The key of the present method is to estimate the energy radiated in the radioactive nuclear disintegration of an atom by using classical theory of β decay and special relativity for various kinds of radioactive atoms. The parameters used in this model are only physical half-time and biological half-time, and there are no operational parameters or coefficients to adjust our theoretical runoff to ICRP. Figure shows the time-varying effective dose with ingestion duration, and we can confirm the validity of our model. The time-varying effective dose with

The effect of microorganisms on asphaltopropylene concrete in a radioactive waste repository. Part 1

International Nuclear Information System (INIS)

Hlavackova, I.; Hlavacek, I.; Mara, M.; Wasserbauer, R.

1993-10-01

The properties were examined of asphaltopropylene concrete (APC), which has been used as a sealing material in low level radioactive waste pits at the Dukovany NPP repository. APC consists of aggregates and filler material which constitute 80%, the rest is a 75:5 asphalt/propylene mixture. The sample preparation and experimental procedures are described. The experiments were aimed at determining the permeability of APC after radiation and thermal stress and, in particular, the effect of bacteria and molds from the repository. The possibility of the asphaltopropylene binder (AP) in APC being degraded due to the effect of bacteria and molds in aerobic conditions is discussed. Changes in APC caused by chemicals were also examined, and the most marked effects were found for oxalic and citric acid, at elevated temperatures in particular. Results of irradiation of the APC samples, gas chromatographic data of AP, the upper and lower limits of AP ductility, mechanical data of AP, the microbiological report, and results of geotechnological laboratory tests are given in the Appendix. (J.B.). 11 tabs., 39 figs., 11 refs

Natural Radioactivity Measurements in Soil and Phosphate Samples from El-Sabaea, Aswan, Egypt

International Nuclear Information System (INIS)

Harb, S.; Abbady, A.; El-Kamel, A.H.; Abd El-Mageed, A.I.; Negm, H.H.

2009-01-01

The knowledge on radioactivity content of the various radionuclides in the soil and rocks play an important role in health physics. The main aim of this work is to estimate the concentrations of natural radionuclides 226 Ra, 228 Ra, 228 Th, 232 Th and 40 k in soil and phosphate samples and, impact of the El-Sabaea phosphate factory on the human health. This can be investigated via gamma-ray spectroscopy by 2 x 2 inch NaI(Tl) scintillation detector. The range of 226 Ra, 232 Th and 40k were from 59.7±6.7 to 638.3±31.0, from 9.4±1.4 to 40.6±6.3, from 213.1±9.5 to 798.9±30.6 in Bq/kg respectively

An assessment of the natural radioactivity distribution and radiation hazard in soil samples from Qatar using high-resolution gamma-ray spectrometry

International Nuclear Information System (INIS)

Al-Sulaiti, Huda; Al Mugren, K.S.; Bradley, D.A.; Regan, P.H.; Santawamaitre, T.; Malain, D.; Habib, A.; Nasir, Tabassum; Alkhomashi, N.; Al-Dahan, N.; Al-Dosari, M.; Bukhari, S.

2017-01-01

We establish baseline measurements for radioactivity concentration in the soil samples collected from the Qatarian peninsula. The work focused on the naturally occurring and technically enhanced levels of radiation associated with 235,8 U and 232 Th natural decay chains and the long-lived naturally occurring radionuclide 40 K in 129 soil samples collected across the landscape of the State of Qatar. Three radiological distribution maps showing the activity concentrations of 226 Ra, 232 Th and 40 K were constructed. Two soil samples were found to be elevated to the favour of 226 Ra concentration and significantly above the average and global values. Notably, these samples were collected from an area within an oil field (NW Dukhan). The mean values of activity concentrations of 226 Ra, 232 Th and 40 K for the full cohort of samples were found to be 17.2±1.6, 6.38±0.26 and 169±5 Bq/kg, respectively. These values lie within the expected range relative to the world average values in soil samples of 30, 35 and 400 Bq/kg, respectively. - Highlights: • This study aimed to establish a baseline for soil radioactivity in Qatar. • The work focused on measurement of NORM levels in 129 samples using HPGe detector. • The mean values lie within the range relative to the world average values. • The Ac of Dukhan soil samples were elevated. • The mean of D, Ra eq , H ex and AEDE had all normal levels of radiation.

Radioactive-site-remediation technologies seminar. Speaker slide copies

International Nuclear Information System (INIS)

1992-06-01

The contents of this report include the following: approaches to sampling radioactive heterogeneous waste; soil characterization methodology for determining application of soil washing; vorce (volume reduction/chemical extraction) program; treatment of radioactive compounds in water; polymer solidification of low-level radioactive, hazardous, and mixed waste; in situ vitrification of soils contaminated with radioactive and mixed wastes; decontamination of contaminated buildings; incineration of radioactive waste; in situ stabilization/solidification with cement-based grouts; environmental restoration and waste management; removal of contaminants from soils by electrokinetics; and treatment, compaction, and disposal of residual radioactive waste

Biological effects of water reservoir radioactive contamination

International Nuclear Information System (INIS)

Mashneva, N.I.

1983-01-01

Radiation damage to fresh water fishes at early stages of ontogenesis is revealed only during the spawn incubation in a solution with 10 -5 to 10 -3 Cu/l radioactivity and at relatively high dosages exceeding 500-1000 rad. Damaging effect of a fission product mixture of 9, 30 and 100 day age as well as of several separate radionuclides on embryogenesis of freshwater fishes depends mainly on fish species, concentration, toxicity, chemical form of radionuclides in the residence medium, on peculiarities of metabolism between the aqueous medium and an organism, stage of the embryo development by the moment of radiation effect and duration of this effect

Radioactivity around naval nuclear bases

International Nuclear Information System (INIS)

1989-02-01

Between 12th July and 2nd August 1988, Greenpeace took sediment samples from around four Royal Navy bases in the United Kingdom. Faslane, where nuclear powered submarines are berthed; Devonport and Rosyth where refit work is carried out and Portsmouth where US and UK nuclear submarines often visit. Samples were also taken from the US Navy base at Holy Loch, Scotland, where nuclear powered ballistic missile submarines are based. The samples were analysed at St Bartholomew Hospital Medical School, London. Identical samples were provided to the MoD personnel at Faslane and Devonport on the date taken. The purpose of carrying out the sampling programme was to highlight the fact that publicly available statistics from Ministry of Agriculture Fisheries and Food (MAFF) are too limited in range, concentrating as they do merely on radioactive levels found between tides. The findings point to the necessity of monitoring subtidal as well as intertidal areas since levels of radioactivity found in the samples at Faslane and Holy Loch were four to nine times the figures published by MAFF. Until such time as nuclear power is no longer used at sea, it is the contention of Greenpeace that a more independent and comprehensive picture of the nature of radioactive contamination from around UK naval establishments must be obtained, than that presently available from MAFF. (author)

Radioactive rare gases emission at underground nuclear explosions

International Nuclear Information System (INIS)

Dubasov, Yu.V.

2016-01-01

The examples of radioactive rare gases emission at underground nuclear explosions conducted in the USSR on the Novaya Zemlya and Semipalatinsk test sites are considered. It is pointed out that in the case of evasive explosion in vertical wells without apparent radioactive gases emission the samples of subsurface gas must contain the traces of radioactive rare gases. Under the inspection of evasive explosion in horizontal workings of rock massif, one should guided by the analysis of atmospheric air samples in the inspected area [ru

The use of ceramic membranes for radioactive solutions purification

International Nuclear Information System (INIS)

Zakrzewska-Trznadel, G.

2002-01-01

Membrane permeation combined with complexation was tested for radioactive wastes processing purpose. The results of experiments with MEMBRALOX and CeRAM INSIDE filtering elements are presented in the paper. The pore size of ceramic membranes was in 1kD-100 nm range. The experiments were performed with non-active and with radioactive model solutions and original radioactive waste samples. To achieve high decontamination factors the process was enhanced by chemical complexation. Such complexants as poly(acrylic) acid and polyacrylic)acid salts of different crosslinking, polyethylenimine and cyanoferrates were tested. The experiments showed the significant increase of retention and decontamination factors while before ultrafiltration macromolecular ligands were added. The effectiveness of complexation by each ligand is strongly dependent on pH and alkali metals concentration. (author)

Some statistical and sampling needs for detecting spills or migration at commercial low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Thomas, J.M.; Eberhardt, L.L.; Skalski, J.R.; Simmons, M.A.

1984-05-01

As part of a larger study funded by the US Nuclear Regulatory Commission we have been investigating field sampling strategies and compositing as a means of detecting spills or migration at commercial low-level radioactive waste disposal sites. The overall project is designed to produce information for developing guidance on implementing 10 CFR part 61. Compositing (pooling samples) for detection is discussed first, followed by our development of a statistical test to allow a decision as to whether any component of a composite exceeds a prescribed maximum acceptable level. The question of optimal field sampling designs and an Apple computer program designed to show the difficulties in constructing efficient field designs and using compositing schemes are considered. 6 references, 3 figures, 3 tables

Some bioindicators of radioactive contamination

International Nuclear Information System (INIS)

Cosma, C.; Cozmuta, I.; Micu, C.

1996-01-01

The lessons that could be learned from the Chernobyl accident were numerous and encompassed all areas. One of those lead to the discovery of new monitoring methods which also supply to cost-effective solutions to control contaminant radioactive discharges in the environment. Through the measurements performed, we discovered that some samples, because of their radioactive content restrained also for long periods of time, can be used as bioindicators. Hen eggs between May 1-30 1986 were analysed (identification of radionuclides with a Ge(Li) detector and measuring of total gamma activity with NaI(T1)). Various aspects pursued revealed that eggs are precious witness of vegetable food contamination with fission products, especially Ba-140 and I-131, behaving as radionuclide separators (Ba-140 in egg shell -301 Bq/egg and I-131 in the content - 182 Bq/egg). Some of the most important pharmaceutical plants from Transylvania measured during 1986-1994 period presents high cesium radioactivity. The perennial plants (as Lichen Islandicus) for the same period accumulated a greater activity that the annual ones. Especially the lichen, because of the their slow decreasing activity are suitable as biological detectors also in retrospective measurements. Measuring the activity of some pollen samples was rediscovered. The pollen grains, during their transport in air by the bees, are acting like a filter for radionuclides so that we could use they to monitor the deliverance of these substances in air. (author)

Assessment of natural radioactivity and associated radiation indices in soil samples from the high background radiation area, Kanyakumari district, Tamil Nadu, India

Directory of Open Access Journals (Sweden)

A K Ajithra

2017-01-01

Full Text Available Assessment of natural radioactivity is very important from different points of view, especially for assessment of radiation exposure to human. In the present study, natural radionuclide concentrations of 238U, 232Th, and 40K were measured by gamma spectrometry using HPGe detector in soil samples collected from Southwest coast of Kanyakumari district, Tamil Nadu. The radiological index parameters due to natural radionuclides such as radium equivalent activity, absorbed dose rate, annual effective dose rate, external hazard index, internal hazard index, and gamma index were calculated for the soil samples. All the calculated radiological index values are higher than world average values and the recommended safety limits. Multivariate statistical techniques such as Pearson correlation, principal component analysis, and cluster analysis were applied to know the relation between radionuclides and radiological parameters and to study the spatial distribution of radionuclides.

Contamination and decontamination of vehicles when driven in radioactive areas

International Nuclear Information System (INIS)

Ulvsand, T.; Nygren, U.

1999-10-01

There is reason to ask whether it is beneficial to decontaminate vehicles, in view of the great effort applied. If the level of contamination is low before the decontamination process, then the cost is not motivated, even if the decontamination is shown to be effective in relative terms. The report describes two trials at the National NBC Defence School in Umeaa and one trial at the French test site in Bourges. The aim is to investigate how vehicles are contaminated and at which ground deposition levels troublesome levels of contamination will arise. In the trials, a non-radioactive agent substituting real radioactivity was used. The trials in Sweden so far have used the oversnow vehicle BV 206, during both winter and summer conditions. The vehicles were driven a specific distance along a road on which a known amount of the test substance had been dispersed. Samples were taken on pre-determined areas on one side of the vehicles to measure the amount of test substance. Later, the vehicles continued along a 'clean' road where additional samples were taken, but on the other side of the vehicles. The largest amount of test substance was collected on the tracks and on the back of the vehicle. The tracks and mud-flaps were effectively decontaminated when the vehicles were driven along a clean road, while most of the contamination remained on the backside. The purpose of the trials in France was to compare the results from our non-radioactive and their radioactive method, based on the radioactive La-140. Due to ground conditions, the level of contamination on the vehicles was much less than in the trials in Umeaa, but the effect decontamination could be measured after all

Environmental radioactivity in Hungary

International Nuclear Information System (INIS)

Kovacs, J.; Predmerszky, T.

1979-01-01

A comprehensive examination of radioactive contamination in air, soil, surface waters and food products, and of natural radioactiviy in air, soil, and building materials has been carried out. The investigated factors were as follows: a) air samples: yearly and monthly beta- and gamma activities of fallout, precipitation and aerosols in the period 1955-1976 in Budapest and some other towns; b) soil samples: 90 Sr concentration of soils of different quality and cultivation originating from sixteen regions of Hungary measured in the period 1974-1976; c) surface waters: annual mean beta activity of five rivers and of the Lake Balaton in the period 1965-1976, 3 H, 137 Cs and 90 Sr activity of the Danube in the year 1976; d) food products: radioactive contamination of spinach, lettuce and oxalis, originating from three different regions in the period 1959-1976 and mean radioactivity of fodder, corn, tobacco, milk, fish and animal bones in a period of 5-10 years; e) natural radioactivity: radon- and toron concentration of air, activity of 226 Ra fallout of the soil in the vicinity of power plants, 226 Ra, 228 Th and 40 K activity of different building materials, radiation doses inside buildings constructed by different technics. (L.E.)

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.

Measurement of radioactive lines in powdered milk samples in Londrina (Parana State, Brazil) region

International Nuclear Information System (INIS)

Melquiades, Fabio Luiz

2000-01-01

This work deals with the measurement of radioactive lines in powdered milk, with high resolution gamma spectrometry, using a HPGe detector with relative efficiency of 10%, coupled to the electronic nuclear chain and a multichannel card of 8192 channels. Some tests were realized before beginning the measurements. The first of them was to define the shield to be used, making several measured with different shields according to the available materials, opting finally for a shield composed of bricks of lead (10 cm thickness), plates of iron (4nm thickness) and of aluminum (2 mm thickness). Four different geometries for the samples recipients were tested, and the Marinelli beaker of 2,1 liters totally filled was the one which supplied the best peak/background ratio. A statistical inference was also realized to determine the sampling that represents each one of the lots of milk to be measured, resulting in a number of 6 samples, for a confidence level of 95%. Two different kinds of powdered milk produced at Londrina were analyzed, Integral Powdered Milk Cativa and Integral Powdered Milk Polly. The samples were properly put in the Marinelli beaker of 2,1 L, sealed and kept for 40 days to reach the secular equilibrium. The counting time for each measurement was two days. It was possible to identify the radionuclides 40 K, 137 Cs and 232 Th (from 208 Tl), whose activities were calculated according to the International Atomic Energy Agency norms (IAEA, 1989). The detector efficiency was measured using calibrated samples, prepared with the certified reference materials IAEA-326 and IAEA-375. Corrections for self-absorption were accomplished, based on measures of samples with different densities. The results obtained for the powdered milk Cativa were: 464± 12 Bq/kg for 40 K, 3,46 ± 1,05 and 0,46 ± 1,05 and 0,46 ± 0,16 Bq/kg for the minimum detectable activities of 137 Cs and 232 Th, respectively. For the milk Polly, the results were: 452±10 Bq/kg for 40 K, 3,19 ± 0

Learning more about radioactivity

International Nuclear Information System (INIS)

2008-01-01

This digest brochure explains what radioactivity is, where it comes from, how it is measured, what are its effects on the body and the way to protect it against these effects, the uses of radioactivity (In the medical field, In industry, In the food industry, and In the cultural world). It ends with some examples of irradiation levels, of natural radioactivity and with the distribution in France of various sources of exposure. (J.S.)

Inductively coupled plasma mass spectrometer installation modifications in a radioactive contaminated laboratory for the analysis of DOE radioactive waste streams

International Nuclear Information System (INIS)

Giaquinto, J.M.; Keller, J.M.; Meeks, A.M.

1998-01-01

The operation and maintenance of a complex analytical instrument such as an inductively coupled plasma mass spectrometer in a radioactive contaminated environment presents unique problems and challenges that have to be considered in the purchasing and installation process. Considerations such as vendor experience, typical radiation levels, sample matrices encountered during sample analysis, instrument accessibility for maintenance, and upkeep must be incorporated into the decision process. The Radioactive Materials Analytical Laboratory (RMAL) at Oak Ridge National Laboratory (ORNL) recently purchased and installed an inductively coupled plasma mass spectrometer for the analysis of Department of Energy (DOE) radioactive waste streams. This presentation will outline the purchasing decision, installation of the instrument, and how the modifications needed to operate in a radioactive contaminated laboratory do not significantly impact the daily operation and maintenance requirements of the instrument. Also, a contamination survey of the system will be presented which demonstrates the contamination levels in the instrument from the sample introduction system to the detector. (author)

Inductively coupled plasma mass spectrometer installation modifications in a radioactive contaminated laboratory for the analysis of DOE radioactive waste streams

International Nuclear Information System (INIS)

Giaquinto, J.M.; Keller, J.M.; Meeks, A.M.

1997-04-01

The operation and maintenance of a complex analytical instrument such as an inductively coupled plasma mass spectrometer in a radioactive contaminated environment presents unique problems and challenges that have to be considered in the purchasing and installation process. Considerations such as vendor experience, typical radiation levels, sample matrices encountered during sample analysis, instrument accessibility for maintenance, and upkeep must be incorporated into the decision process. The Radioactive Materials Analytical Laboratory (RMAL) at Oak Ridge National Laboratory (ORNL) recently purchased and installed an inductively coupled plasma mass spectrometer for the analysis of Department of Energy (DOE) radioactive waste streams. This presentation will outline the purchasing decision, installation of the instrument, and how the modifications needed to operate in a radioactive contaminated laboratory do not significantly impact the daily operation and maintenance requirements of the instrument. Also, a contamination survey of the system will be presented which demonstrates the contamination levels in the instrument from the sample introduction system to the detector

Assessment of alpha radioactivity in Indian tobacco leaf-a detailed study with SSNTD

International Nuclear Information System (INIS)

Ghosh, Dipak; Deb, Argha; Sengupta, Rosalima; Patra, K.K.; Halder, S.; Maiti, S.

2009-01-01

People who inhale tobacco smoke are exposed to higher concentrations of radioactivity since tobacco contains polonium ( 210 Po) and lead ( 210 Pb) both of which are radioactive elements of radon decay series. Among these 210 Po emits damaging type of radiation-alpha radiation is 1000 times more carcinogenic than gamma radiation (DiFranza and Winters, 1982). It generates the localized radiation dose and the health of common people gets affected seriously. In view of this a detail measurement of radioactivity of tobacco leaf is essential. This paper presents a detail investigation on the measurement of alpha radioactivity in raw tobacco leaves, in a few commonly used Indian brand cigarettes and in packed chewing tobacco materials with solid state nuclear track detector (SSNTD). The study reveals the presence of pronounced alpha activity in cigarette tobacco and chewing tobacco samples ranging from 60-75 mBq/gm and 60- 75 mBq/gm. The alpha activity value is comparatively lower in raw tobacco leaves (9-50 mBq/gm). The annual committed effective dose of the smokers of these branded cigarettes has estimated to be 50-700 (μSv/y), whereas the effective dose value in raw tobacco leaves and chewing tobacco samples is 54-201 μSv/y and 230-290 μSv/y, respectively which are within the range found in cigarette samples. (author)

The natural radioactivity measurements in coastal sediment samples along the East Coast of Tamilnadu using gamma spectrometry technique

Energy Technology Data Exchange (ETDEWEB)

Chandramohan, J. [E.G.S Pillay Engineering College, Nagapattinam, 611002, Tamilnadu (India); Tholkappian, M. [Sri Vari College of Education, Then Arasampattu, Tiruvannamalai, 606611, Tamilnadu (India); Harikrishnan, N.; Ravisankar, R., E-mail: ravisankarphysics@gmail.com [Post Graduate and Research Department of Physics, Government Arts College, Tiruvannamalai 606603, Tamilnadu (India)

2015-08-28

The natural radioactivity concentration in beach sediment samples collected from Pattipulam to Devanampattinam of East Coast of Tamilnadu have been determined by NaI (TI) gamma ray spectrometer. The specific activity concentrations range from ≤ 2.21 (BDL) to 37.02 Bq kg{sup −1} with a mean of 3.79 Bqkg{sup −1} for {sup 238}U, ≤ 2.11 (BDL) to 643.77 Bqkg{sup −1} with a mean of 49.60 Bqkg{sup −1} for {sup 232}Th and 300.34 Bqkg{sup −1} to 449.08 Bqkg{sup −1} with a mean of 360.23 Bqkg{sup −1} for {sup 40}K. The potential radiological hazards due to natural radionuclides content such as Radium Equivalent activity (Ra{sub eq}), Representative level index (RLI), External hazard index (H{sub ex}), absorbed gamma does rate (D{sub R}), and Annual effective dose rate (AEDR) are estimated to assess the radiation hazard associated with the sediments. The obtained data are compared with the recommended safety limits and international approved values. All the values are well below the recommended safety limits indicating that radiation levels do not poses any significant health hazard to the public in the area as a result of the natural radioactivity of beach sediments. This study may help the baseline data for more extensive works in the same subjects of future studies.

Assessment of natural radioactivity in ceramics imported of Sudan

International Nuclear Information System (INIS)

Suliman, Mohamed Abdelgadir

2017-08-01

The study presents the radioactivity concentration of 238 U, 232 Th and 40 K for 25 commercial ceramic samples, which is used as building materials in Sudan, Imported from China. A total of 25 different consignment samples were analyzed and the concentrations of radioisotopes were determined by Gamma spectroscopy using (Nal) detector. The detected values of concentrations of 238 U, 232 Th and 40 K were 182.9, 51.18 and 237.67 Bq/kg dry-weight respectively. Five different radiation indices, namely average radium equivalent (Ra eq ), the absorbed dose rate (D), the annual effective dose equivalent (AEDE), the external hazard index (H ex ), and the radioactivity level index (I x ) which indicate hazardous radiation were also determined. The results revealed that the average radium equivalent (Ra aq ), the absorbed dose rate (D), the annual effective dose equivalent (AEDE), external hazard index (H ex ), and the radioactivity level index (I x ) were 274.3915 Bq/kg, 122.02 nGy/h, the external hazard index (H ex ), and the radioactivity level index (I x ) were 274.3915 Bq/KG, 122.02 nGy/h, 122 mSv/yr, 0.74 and 1.89, respectively. The mean values of Ra ex obtained were in good agreement with the international values, while the mean of D, and I x were higher than the international values, and it found that.The results of AEDE for 14 samples are bout 10 -101% higher than the result international value (1mSv/yr) for the public the rest is lower than the permissible value for the international values. The measured activity concentrations for these radionuclides were compared with the reported data obtained from similar materials used in other countries and with typical world values. (Author)

Radioactivity in fine papers

International Nuclear Information System (INIS)

Taylor, H.W.; Singh, B.

1993-01-01

The radioactivity of fine papers has been studied through γ-ray spectroscopy with an intrinsic Ge detector. Samples of paper from European and North American sources were found to contain very different amounts of 226 Ra and 232 Th. The processes which introduce radionuclides into paper are discussed. The radioactivity from fine papers makes only a small contribution to an individual's annual radiation dose; nevertheless it is easily detectable and perhaps, avoidable. (Author)

Radioactive isotope and isomer separation with using light induced drift effect

International Nuclear Information System (INIS)

Hradecny, C.; Slovak, J.; Tethal, T.; Ermolaev, I.M.; Shalagin, A.M.

1991-01-01

The isotope separation with using light induced drift (LID) is discussed. The basic theoretical characteristics of the method are deduced: separation simultaneously with an arbitrary high enrichment and without significant losses; separation productivity up to 100 μg/h. These characteristics are sufficient and very convenient for separation of expensive radioactive isotopes and isomers which are applied in medicine and science. The first experimental separation of the radioactive isotopes ( 22,24 Na) by using the LID effect is reported. 13 refs.; 5 figs

Effect of background radiation shielding on natural radioactivity distribution measurement with imaging plate

International Nuclear Information System (INIS)

Mori, C.; Suzuki, T.; Koido, S.; Uritani, A.; Miyahara, H.; Yanagida, K.; Miyahara, J.; Takahashi, K.

1996-01-01

Distribution images of natural radioactivity contained in various natural materials such as vegetable, animal meat and pottery work can be obtained with an imaging plate which has high sensitivity for nuclear radiations. For such very low levels of radioactivity, natural background radiations must be reduced using a shielding box. The lining, on the inside of the box, with low atomic number material such as acrylic resin is very effective in reducing electrons, β-rays and low energy X- and γ-rays emitted from the inner surface of the shielding material. Some images of natural radioactivity distribution were obtained and the radioactivity, mainly 40 K, contained in natural materials was measured by using an HPGe detector and also the imaging plate itself. (orig.)

A Low Level Radioactivity Monitor for Aqueous Waste

International Nuclear Information System (INIS)

Quirk, E.J.M.

1968-04-01

A system is described for continuous monitoring of very low levels of radioactivity in waste water containing typically 3.5 g/l dissolved solids. Spray evaporation of the water enables the dissolved solids to be recovered in the form of an aerosol and collected on a filter tape where the radioactivity is measured by a radiation detector. The advantage of this method compared with a direct measurement is that the attenuating effect of the water is removed and thus greater sensitivity is obtained. Compensation for background and any contamination is achieved by feeding distilled water to the aerosol generator every alternate sampling period and recording the count difference between two successive sampling periods . A printed record of the totalised count difference is obtained once per hour during the integration time of one month. For β radioactivity the minimum values of specific activity measurable extend from 1 x 10 -6 Ci/m 3 to 6 x 10 -8 Ci/m depending on the B end-point energy in the range 167 KeV to 2.26 MeV. The estimated minimum measurable specific activity is 6 x 10 -8 Ci/m 3

A Low Level Radioactivity Monitor for Aqueous Waste

Energy Technology Data Exchange (ETDEWEB)

Quirk, E J.M.

1968-04-15

A system is described for continuous monitoring of very low levels of radioactivity in waste water containing typically 3.5 g/l dissolved solids. Spray evaporation of the water enables the dissolved solids to be recovered in the form of an aerosol and collected on a filter tape where the radioactivity is measured by a radiation detector. The advantage of this method compared with a direct measurement is that the attenuating effect of the water is removed and thus greater sensitivity is obtained. Compensation for background and any contamination is achieved by feeding distilled water to the aerosol generator every alternate sampling period and recording the count difference between two successive sampling periods . A printed record of the totalised count difference is obtained once per hour during the integration time of one month. For {beta} radioactivity the minimum values of specific activity measurable extend from 1 x 10{sup -6} Ci/m{sup 3} to 6 x 10{sup -8} Ci/m depending on the B end-point energy in the range 167 KeV to 2.26 MeV. The estimated minimum measurable specific activity is 6 x 10{sup -8} Ci/m{sup 3}.

Radioactive rare gas recoverying device

International Nuclear Information System (INIS)

Kasai, Shigeo

1989-01-01

The apparatus of the present invention comprises a vessel for containing coolants, an introduction valve and an introduction pipe for introducing radioactive rare gases and an adsorption floor disposed in the coolants. A josephson device is disposed being immersed in the coolants between a radiation detector for detecting the radioactive level adsorbed to the adsorption floor and a driving section for driving the introduction valve by the signal from the detector. With this constitution, radioactive rare gases introduced into the coolants and then cooled and liquefied are recovered by the adsorption floor. As the adsorption proceeds and when the radioactivity level exceeds a maximum level in the effective shielding range of the recovery apparatus, the signal current from the radiation detector also exceeds a predetermined level. If radioactivity exceeds the maximum level, the electrical resistance of the josephson device is increased infinitely by the josephson effect to close the introduction valve. Accordingly, the radioactivity is not absorbed beyond the effective shielding range. (I.S.)

Radioactivity studies in the Romanian national repository for radioactive waste - Baita, Bihor region, during 14 years of resource development

International Nuclear Information System (INIS)

Dragolici, F.; Rotarescu, G.; Luca, A.; Peic, T.; Postelnicu, C.; Dragolici, A.C.

2000-01-01

The main objective of the study is focused on active surveillance, by periodic measurements of the radioactivity and the possible migration, during the last 14 years, of the radioactive elements stored at the Romanian National Repository for Radioactive Waste-Baita, Bihor region. Hence, water, soil and vegetation samples were collected every three months, from 57 points, chosen in agreement with the National Commission for Nuclear Activities Control and with the local Public Health Institutions. After the sample collection, radiometric measurements were made. The main steps of the study were: the collection of the samples, radiometric measurements, radiochemical analysis of the uranium and progeny, processing and the interpretation of the obtained data; detection of any gamma radionuclides using gamma spectrometry; and the processing, interpretation and intercomparison of the results. Throughout the 14 years of surveillance, it was demonstrated that the National Repository for Radioactive Waste activity has had no negative impact on the operator staff, environment and population. Also, no migration of the deposited radionuclides was detected throughout the whole area. (author)

Radioactivity survey data in Japan, no. 55

International Nuclear Information System (INIS)

1980-12-01

Gamma-ray spectrometry with Ge (Li) detectors was applied to all samples. Artificial radionuclides such as Cs-137, Mn-54 and Co-60 were identified, and their concentrations were determined. Samples were cultured fish, caught fish and marine sediment. The important species were selected in consideration of their importance as ecological indicators and natural resources. The indicator species were selected in consideration of their significant characteristics of accumulating the radionuclides. The treatment of fish and sediment for the measurement is described. The radioactivity of the samples was measured with Ge (Li) detectors for 20 to 24 hours. Radioactive background was measured for 40 to 48 hours at intervals of one week. The radionuclides were identified by analyzing the observed gamma-ray spectra. The corresponding peak area of each radionuclide was calculated, and radioactive background was subtracted. The amounts of the radioactive nuclides were estimated from these net peak areas by correcting them with the counting efficiency of the detectors, sample geometry and others. Besides the detectors, a pulse height analyzer and data output equipments were used. The criteria for the precision of measurement are defined, and the results of analysis are reported for the samples collected from December, 1978, to February, 1980. This report was drawn up by the National Institute of Radiological Sciences. (Kako, I.)

Rapid method for the radioactive strontium determination in natural samples; Brza metoda za odredjivanje radioaktivnog stroncija u prirodnim uzorcima

Energy Technology Data Exchange (ETDEWEB)

Grahek, Z; Kosutic, K; Lulic, S [Rudjer Boskovic Institute, Zagreb (Croatia)

1997-12-31

Radioactive strontium isotopes belong to the group of isotopes that are very dangerous for human health. Therefore radioactive strontium is regularly determined in natural samples. When determining strontium isotopes in natural samples, it is necessary to isolate strontium from the sample because strontium isotopes are pure {beta}-emitters. As natural samples contain much more calcium and sodium than strontium it is necessary to isolate a small quantity of strontium from large sample with simultaneous separation of calcium and other interfering elements. For this purposes an elegant method based on ion exchange chromatography has been developed. Namely, examinations with model system have shown that strontium may be separated from calcium on the column filled with anion exchanger and the mixture of the methanol and nitric acid as eluent. It was also shown that yttrium does not separate from strontium but elutes almost simultaneously with it. Yttrium may be separated from strontium on the column filled with cation exchanger DOWEX 50X8 and nitric acid as eluent. According to the above examinations, the procedure of isolation of strontium and yttrium from natural sample has been created (on assumption that {sup 90}Sr and {sup 90}Y in secular equilibrium in sample). Strontium and yttrium have been isolated from natural sample (standard IAEA A-7) on the column filled with the exchanger AMBERLITE CG-400 and the mixture of methanol and nitric acid as eluent. Strontium and yttrium have been separated on the column with cation exchanger. {sup 90}Sr has been determined through {sup 90}Y by counting the solid yttrium oxalate immediately upon isolation and separation from strontium. {sup 90}Sr has also been determined by counting {sup 90}Sr-{sup 90}Y in secular equilibrium after 15 days. The obtained results of determination of {sup 90}Sr through {sup 90}Y and through secular equilibrium {sup 90}Sr-{sup 90}Y correspond to the declared values of standard. (author). 2 figs., 1

Fully automated gamma spectrometry gauge observing possible radioactive contamination of melting-shop samples

International Nuclear Information System (INIS)

Kroos, J.; Westkaemper, G.; Stein, J.

1999-01-01

At Salzgitter AG, several monitoring systems have been installed to check the scrap transport by rail and by car. At the moment, the scrap transport by ship is reloaded onto wagons for monitoring afterwards. In the future, a detection system will be mounted onto a crane for a direct check on scrap upon the departure of ship. Furthermore, at Salzgitter AG Central Chemical Laboratory, a fully automated gamma spectrometry gauge is installed in order to observe a possible radioactive contamination of the products. The gamma spectrometer is integrated into the automated OE spectrometry line for testing melting shop samples after performing the OE spectrometry. With this technique the specific activity of selected nuclides and dose rate will be determined. The activity observation is part of the release procedure. The corresponding measurement data are stored in a database for quality management reasons. (author)

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)

Radioactivity in surface waters and its effects

International Nuclear Information System (INIS)

Stoeber, I.

1987-01-01

In consequence of the reactor accident in Chernobyl, the State Office for Water and Waste Disposal of North-Rhine Westphalia implemented immediate programmes for monitoring radioactivity in surface waters, including their sediments and organisms. Of the initially-measured radionuclides, only cesium-137, with its long half-life of 30 years, is of interest. Only trace amounts of the almost equally long-lived strontium 90 (half-life 28 years) were present in rainfall. Cs-137 is a non-natural-radionuclide, occurring solely as a by-product of nuclear installations and atomic bomb tests. Following the ban on surface testing of nuclear weapons, the Cs-137 content of surface waters had fallen significantly up to April 1986. The load due to the reactor disaster is of the same order of magnitude as that produced by atomic testing at the end of the nineteen-sixties. The paper surveys radioactive pollution of surface waters in North-Rhine Westphalia and its effects on water use, especially in regard to potable water supplies and the fish population. (orig./HSCH) [de

Natural radioactivity in granite stones used as building materials in Iran.

Science.gov (United States)

Asgharizadeh, F; Abbasi, A; Hochaghani, O; Gooya, E S

2012-04-01

Due to increasing concern about environmental radiological protection, specific radioactivity concentrations of (226)Ra, (232)Th and (40)K in different types of commonly used granite stone samples collected from the Tehran city of Iran have been determined by means of a high-resolution HPGe gamma-spectroscopy system. The activity concentrations of (232)Th, (226)Ra and (40)K in the selected granite samples ranged from 18 to 178, 6 to 160 and 556 to 1539 Bq kg(-1), respectively. The radium equivalent activities (Ra(eq)) are lower than the limit of 370 Bq kg(-1) set by NEA-OECD [Nuclear Energy Agency. Exposure to radiation from natural radioactivity in building materials. Report by NEA Group of Experts. OECD (1979)], except in two samples. The internal hazard indexes have been found well below the acceptable limit in most of the samples. Five samples of investigated commercial granite stones do not satisfy the safety criterion illustrated by UNSCEAR (United Nations Scientific Committee on the Effects of Atomic Radiation. Exposure from natural sources of radiation. Report to the General Assembly (1993). Applying dose criteria recently recommended by the EC [European Commission Report on Radiological Protection Principles Concerning the Natural Radioactivity of Building Materials. Radiation Protection 112 (1999)] for superficial materials, all investigated samples meet the exemption dose limit of 0.3 mSv y(-1).

General principles governing sampling and measurement techniques for monitoring radioactive effluents from nuclear facilities

International Nuclear Information System (INIS)

Fitoussi, L.

1978-01-01

An explanation is given of the need to monitor the release of radioactive gases and liquid effluents from nuclear facilities, with particular emphasis on the ICRP recommendations and on the interest in this problem shown by the larger international organizations. This is followed by a description of the classes of radionuclides that are normally monitored in this way. The characteristics of monitoring 'in line' and 'by sample taking' are described; the disadvantages of in line monitoring and the problem of sample representativity are discussed. There follows an account of the general principles for measuring gaseous and liquid effluents that are applied in the techniques normally employed at nuclear facilities. Standards relating to the specifications for monitoring instruments are at present being devised by the International Electrotechnical Commission, and there are still major differences in national practices, at least as far as measurement thresholds are concerned. In conclusion, it is shown that harmonization of practices and standardization of equipment would probably help to make international relations in the field more productive. (author)

Natural radioactivity levels in lake sediment samples

International Nuclear Information System (INIS)

Eroglu, H.; Kabadayi, O.

2013-01-01

The radioactivity concentrations of nuclides 238 U, 232 Th and 40 K in lake sediments collected from 15 different stations at Altinkaya dam lake and 12 different stations at Derbent dam lake in Turkey were measured using high-resolution gamma-ray spectrometry. The measurement was done using a coaxial HPGe detector system coupled to the Ortec-Dspect jr digital MCA system. The average measured activity concentrations of the nuclides 238 U, 232 Th and 40 K were found to be 19.5, 27.7 and 460 Bq kg -1 in Altinkaya dam, whereas the activity concentrations were 18.8, 25.5 and 365 Bq kg -1 in Derbent dam, respectively. The measured activity concentrations in the present study have been compared with similar measurements from different locations in the world. (authors)

Radioactive waste management in Tanzania

International Nuclear Information System (INIS)

Banzi, F.P.; Bundala, F.M.; Nyanda, A.M.; Msaki, P.

2002-01-01

Radioactive waste, like many other hazardous wastes, is of great concern in Tanzania because of its undesirable health effects. The stochastic effects due to prolonged exposure to ionizing radiation produce cancer and hereditary effects. The deterministic effects due to higher doses cause vomiting, skin reddening, leukemia, and death to exposed victims. The aim of this paper is to give an overview of the status of radioactive wastes in Tanzania, how they are generated and managed to protect humans and the environment. As Tanzania develops, it is bound to increase the use of ionizing radiation in research and teaching, industry, health and agriculture. Already there are more than 42 Centers which use one form of radioisotopes or another for these purposes: Teletherapy (Co-60), Brach-therapy (Cs-137, Sr-89), Nuclear Medicine (P-32, Tc-99m, 1-131, 1-125, Ga-67, In-111, Tl-206), Nuclear gauge (Am-241, Cs- 137, Sr-90, Kr-85), Industrial radiography (Am-241, C-137, Co-60, lr-92), Research and Teaching (1-125, Am241/Be, Co-60, Cs-137, H-3 etc). According to IAEA definition, these radioactive sources become radioactive waste if they meet the following criteria: if they have outlived their usefulness, if they have been abandoned, if they have been displaced without authorization, and if they contaminate other substances. Besides the origin of radioactive wastes, special emphasis will also be placed on the existing radiation regulations that guide disposal of radioactive waste, and the radioactive infrastructure Tanzania needs for ultimate radioactive waste management. Specific examples of incidences (theft, loss, abandonment and illegal possession) of radioactive waste that could have led to serious deterministic radiation effects to humans will also be presented. (author)

Radioactive contamination monitoring device for off-gas in ventilation system

International Nuclear Information System (INIS)

Osaki, Masahiko; Watabe, Atsushi; Kaneko, Itaru; Kubokoya, Takashi.

1990-01-01

In a conventional method of detecting leakage for primary coolants, radioactive iodine in off-gases was detected while going up the off-gas system. As an event resulting in abnormality to radioactive rare gas level, leakage of water, leakage in cleanup system-recycling system, leakage in main steams and leakage from wastes processing system are considered. An off-gas system to be measured is selectively sampled by a sample changer in order to measure radioactive rare gases in the off-gases, and sample gases are introduced to detect radioactivity. Detection signals are received for analysis and quantitative determination, the result of the analysis is diagnosed and the presence or absence of abnormality in an object to be measured is determined. Subsequently, an abnormality alarm and the result of the analysis are outputted. Since the radioactive rare gases are chemically inactive, they are neither combined with other materials nor deposited to wall surfaces. Abnormality can be easily detected by always monitoring a composition pattern and a radioactivity level. (N.H.)

Air modelling as an alternative to sampling for low-level radioactive airborne releases

International Nuclear Information System (INIS)

Morgenstern, M.Y.; Hueske, K.

1995-01-01

This paper describes our efforts to assess the effect of airborne releases at one DOE laboratory using air modelling based on historical data. Among the facilities affected by these developments is Los Alamos National Laboratory (LANL) in New Mexico. RCRA, as amended by the Hazardous and Solid Waste Amendments (HSWA) in 1984, requires all facilities which involve the treatment, storage, and disposal of hazardous waste obtain a RCRA/HSWA waste facility permit. LANL complied with CEARP by initiating a process of identifying potential release sites associated with LANL operations prior to filing a RCRA/HSWA permit application. In the process of preparing the RCRA/HSWA waste facility permit application to the U.S. Environmental Protection Agency (EPA), a total of 603 Solid Waste Management Units (SWMUs) were identified as part of the requirements of the HSWA Module VIH permit requirements. The HSWA Module VIII permit requires LANL to determine whether there have been any releases of hazardous waste or hazardous constituents from SWMUs at the facility dating from the 1940's by performing a RCRA Facility Investigation to address known or suspected releases from specified SWMUs to affected media (i.e. soil, groundwater, surface water, and air). Among the most troublesome of the potential releases sites are those associated with airborne radioactive releases. In order to assess health risks associated with radioactive contaminants in a manner consistent with exposure standards currently in place, the DOE and LANL have established Screening Action Levels (SALs) for radioactive soil contamination. The SALs for each radionuclide in soil are derived from calculations based on a residential scenario in which individuals are exposed to contaminated soil via inhalation and ingestion as well as external exposure to gamma emitters in the soil. The applicable SALs are shown

Correlation between phosphorylation ratios by matrix-assisted laser desorption/ionization time-of-flight mass spectrometry analysis and radioactivities by radioactive assay.

Science.gov (United States)

Tsuchiya, Akira; Asai, Daisuke; Kang, Jeong-Hun; Mori, Takeshi; Niidome, Takuro; Katayama, Yoshiki

2012-02-15

To investigate the correlation between the counts per minute (CPM) by radioactivity assay and the phosphorylation ratio by matrix-assisted laser desorption/ionization time-of-flight mass spectrometry (MALDI-TOF MS) analysis, we prepared 136 peptide substrates. The correlation coefficient of phosphorylation ratios to CPM was 0.77 for all samples. However, the more the numbers of positively charged amino acids increased, the more the correlation coefficient increased. Although positively charged amino acids can have an effect on the correlation results, MALDI-TOF MS analysis is a useful means for monitoring phosphorylated peptide and protein kinase activity instead of radioactivity assays. Copyright © 2011 Elsevier Inc. All rights reserved.

Environmental radioactivity survey in Andong area

Energy Technology Data Exchange (ETDEWEB)

Yoon, Zi Hong; Jo, Kum Ju [Andong Regional Radioactivity Monitoring Station, Andong National Univ., Andong (Korea, Republic of)

2001-12-15

The objectives of the project are to monitor an abnormal level in Andong area and to provide a base-line data on environmental radiation/radioactivity levels in case of any radiological emergency situation. The project is important in view of protecting the public health from the potential hazards of radiation and keeping up the clean environment. This report summarizes and interprets environmental radiation/radioactivity monitoring samples Gamma exposure rates, airborne dust, precipitation, fall-out and drinking-water. Environmental samples : vegetables, fishes/shellfishes, fruits, starch and starch roots and drinking waters. Among the all 2001 radiological monitoring and environmental data in Andong area were not found the extraordinary data. And a nation-wide environmental radiation/radioactivity level survey results were all background levels attributed to terrestrial and cosmic radiation.

Environmental aspects of commercial radioactive waste management

International Nuclear Information System (INIS)

1979-05-01

Volume 2 contains chapters 6 through 10: environmental effects related to radioactive waste management associated with LWR fuel reprocessing - mixed-oxide fuel fabrication plant; environmental effects related to transporting radioactive wastes associated with LWR fuel reprocessing and fabrication; environmental effects related to radioactive waste management associated with LWR fuel reprocessing - retrievable waste storage facility; environmental effects related to geologic isolation of LWR fuel reprocessing wastes; and integrated systems for commercial radioactive waste management

Supporting Sampling and Sample Preparation Tools for Isotope and Nuclear Analysis

International Nuclear Information System (INIS)

2016-03-01

Nuclear and related techniques can help develop climate-smart agricultural practices by optimizing water and nutrient use efficiency, assessing organic carbon sequestration in soil, and assisting in the evaluation of soil erosion control measures. Knowledge on the behaviour of radioactive materials in soil, water and foodstuffs is also essential in enhancing nuclear emergency preparedness and response. Appropriate sampling and sample preparation are the first steps to ensure the quality and effective use of the measurements and this publication provides comprehensive detail on the necessary steps

32-Week Holding-Time Study of SUMMA Polished Canisters and Triple Sorbent Traps Used To Sample Organic Constituents in Radioactive Waste Tank Vapor Headspace

International Nuclear Information System (INIS)

Evans, John C.; Huckaby, James L.; Mitroshkov, Alexandre V.; Julya, Janet L.; Hayes, James C.; Edwards, Jeffrey A.; Sasaki, Leela M.

1997-01-01

Two sampling methods[SUMMA polished canisters and triple sorbent traps (TSTs)] were compared for long-term storage of trace organic vapor samples collected from the headspaces of high-level radioactive waste tanks at the U.S. Department of Energy's Hanford Site in Washington State. Because safety, quality assurance, radiological controls, the long-term stability of the sampling media during storage needed to be addressed. Samples were analyzed with a gas chromatograph/mass spectrometer (GC/MS) using cryogenic reconcentration or thermal desorption sample introduction techniques. SUMMA canister samples were also analyzed for total non-methane organic compounds (TNMOC) by GC/flame ionization detector (FID) using EPA Compendium Method TO-12 . To verify the long-term stability of the sampling media, multiple samples were collected in parallel from a typical passively ventilated radioactive waste tank known to contain moderately high concentrations of both polar and nonpolar organic compounds. Analyses for organic analytes and TNMOC were conducted at increasing intervals over a 32-week period to determine whether any systematic degradation of sample integrity occurred. Analytes collected in the SUMMA polished canisters generally showed good stability over the full 32 weeks with recoveries at the 80% level or better for all compounds studied. The TST data showed some loss (50-80% recovery) for a few high-volatility compounds even in the refrigerated samples; losses for unrefrigerated samples were far more pronounced with recoveries as low as 20% observed in a few cases

Determination of radioactivity in Cisadane River

International Nuclear Information System (INIS)

Tarigan, C.; Lubis, E.

1993-01-01

Determination of radioactivity in Cisadane river. The determination of radioactivity in water and sediment samples from Cisadane river in the period of March 1989 through March 1990 has been carried out. The aim of the study is to get some information on the radionuclides species and its quantities in water and sediment samples. Sampling was done at randon from 12 stations of 5 km apart. Result of the determination showed that the average total α activity in water was 18.10 ± 13.26 mBq/l and in sediment 34.96 ± 9.99 Bq/kg. Total β activities in water was 129.95 ± 148.14 mBq/l and in sediment 275.94 ± 41.63 Bq/kg. Activities of K-40 and Ra-226 in water was 6.39 ± 2.16 Bq/l and 7.34 ± 1.61 Bq/l and in sediment 6.58 ± 1.80 Bq/kg for Ra-226 and 84.87 ± 16.55 Bq/kg for K-40. Compared to environmental quality standard data for water group A total α and β activities showed good quality river water. Compared to data from UNSCEAR, for similar sample the radioactivity level in Cisadane river was normal. This result gave an indication that total α and β radioactivities in the water and sediment are due to natural radionuclides. (authors). 6 refs., 8 tabs., 9 figs

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

Evaluation of radiological impacts for environmental radioactivity distribution in the Kartini reactor area

International Nuclear Information System (INIS)

Yazid, M.; Suratman; Sutresna, G.; Aminjoyo, S.

1996-01-01

This evaluation covered of gross radioactivity. K-40 radioactivity in the water, soil and grass samples. The measurement of Cs-137 and Sr-90 radioactivity in the water samples have also been done. The aim of this research was determined of radiological impacts in the environment around the Kartini reactor. The water, soil and plant samples were counted of gross beta, Sr-90 activity by beta counter and for K-40, Cs-137 activity by low background gamma spectrometer. For this evaluation can be concluded there are no indication of the radioactivity release from the Kartini reactor operation. Gross beta radioactivity in the water, soil and grass sample are between 0.06-0.61 Bq/l, 0.24-0.79 Bq/g and 3.47-5.70 Bq/g ash. Radioactivity of K-40 in the water, soil and grass sample are between 0.09-0.56 Bq/l, 0.12-0.59 Bq/g and 0.29-0.93 Bq/g ash. The radioactivity of Cs-137 in the water samples are between under limit detectable level to 88.62 mBq/l and Sr-90 are between under limit detectable level to 24.22 mBq/l. (author)

Lipid spectrum of the newborn rats' blood at the radioactive and chemical effects in the prenatal period

International Nuclear Information System (INIS)

Buzan, Kh.

1998-01-01

The radioactive and chemical factors used in complex or separately during the prenatal period in the experiment induce ambiguous effects on the lipid metabolism in blood plasma and erythrocytes of newborn rats. The chemicals cause more significant changes in the blood plasma lipid metabolism than the radioactive irradiation does. Being used combined the radioactive and chemical factors do not increase each other's effect- their effects have opposite directions. The radiochemical exposure induce more significant shifts in the lipid spectrum in erythrocytic membranes than the separate factors

The changes in the ecology and physiology of soil invertebrates under influences of radioactive contamination

International Nuclear Information System (INIS)

Maksimova, S.

2006-01-01

The soil biota is important in building and maintaining soil structure and fertility. Invertebrates are ideal as potential bio indicators of the environmental impact of radioactive contamination: they are widely distributed, often abundant and generally thought of as having low dispersive capacity. They can use as test organisms to detect the side-effects of radioactive contamination. The long-term analysis of ecological and physiological after-effects and biodiversity changes had been studied in the zone of radioactive contamination. Material was collected in the Gomel Region (Belarus), 30 km away from the CNPP in 1986-2004 applying usual pedobiological techniques (soil samples and Barber's pitfall traps) at reference points subjected to radioactive contamination. Soil samples were collected at 0 to 25 cm depth. Samples were taken in locations, which had received considerable radionuclide contaminations. These sites differed in contamination by the composition of fall-out, the forms of radionuclide content in soils, their intake into trophic chains and accumulation in animal and plant organisms. The impacts have been investigated at the: 1) organism and population levels , in terms of individual life histories (birth rate, growth, mortality) or species selection; 2) at the community level: to species diversity and to effects on trophic structure. The invertebrates were determined to species or genera, including juvenile stages. Radioactive contamination caused a distinct decrease in species number; the dominance structure of the community changed. The saprophagous are especially sensitive to environmental disturbances. An initial sharp reduction of animal biodiversity and simplification of the community structure of soil fauna were observed, followed by a long-term process of returning to the initial parameters. Changes in hemolymph, necroses of epithelium and cell structure in connective tissue were registered. The most drastic after-effects were manifested in

Comparison of radioactivity data measured in PM10 aerosol samples at two elevated stations in northern Italy during the Fukushima event.

Science.gov (United States)

Tositti, Laura; Brattich, Erika; Cinelli, Giorgia; Previti, Alberto; Mostacci, Domiziano

2012-12-01

The follow-up of Fukushima radioactive plume resulting from the 11th March 2011 devastating tsunami is discussed for two Italian stations in the northern Apennines: Mt. Cimone (Modena) and Montecuccolino (Bologna). Radioactivity data collected at both stations are described, including comparison between local natural background of airborne particulate and artificial radioactivity referable to the arrival of the radioactive plume and its persistence and evolution. Analysis of back-trajectories was used to confirm the arrival of artificial radionuclides following atmospheric transport and processing. The Fukushima plume was first detected on 3rd April 2011 when high volume sampling revealed the presence of the artificial radionuclides (131)I, (137)Cs and (134)Cs. The highest activity concentrations of these nuclides were detected on 5th April 2011 at the Montecuccolino site. Fukushima radioactivity data at the two stations were usually comparable, suggesting a good vertical mixing of the plume; discrepancies were occasional and attributed to different occurrence of wet removal, typically characterized by a scattered spatial pattern. To understand the relevance to the local population of the extra dose due to the Fukushima plume, atmospheric activities of the related artificial nuclides were compared to those of the main natural radionuclides in ambient particulate, and found to be lower by over one order of magnitude. Radiation doses referable to Fukushima, maximized for a whole year occurrence at the highest activity level observed at our stations in the weeks affected by the Japanese plume, were estimated at 1.1 μSv/year. Copyright © 2012 Elsevier Ltd. All rights reserved.

Influence of weather conditions on natural radioactivity

International Nuclear Information System (INIS)

Simion, Florin; Simion, Elena; Cuculeanu, Vasile; Mihalcea, Ion

2011-01-01

This paper presents the dependence of the natural radioactivity on atmospheric weather conditions: air temperature, atmospheric pressure, wind speed, atmospherical precipitations and relative humidity. The values used in the paper were taken from the environmental radioactivity monitoring in Botosani city, Romania, as measured by the Environmental Radioactivity Surveillance Station. Daily global measurements of atmospheric deposition beta and atmospheric aerosols as well were carried out, including the indirect determination of radon and thoron, and the absorbed gamma dose rate in air, as well. Sampling and measurement frequency depended on the type of sample analyzed as follows: atmospheric deposition were taken daily, atmospheric aerosols were collected 4 times/day, with a sampling interval of 5 hours while the air absorbed dose rate was determined at a hourly rate. The coefficient of multiple correlation between the type of analysis and weather conditions, was determined. By using multiple linear regression it was highlighted the natural radioactivity dependence on the atmospheric conditions and meteorological parameters by a mathematical expression that can be used to determine missing values in a time series of measured data. By predicting the measured values our procedure can be considered as a validation process of the measurement accuracy

In situ vitrification pilot-scale radioactive test

International Nuclear Information System (INIS)

Timmerman, C.L.; Oma, K.H.

1984-10-01

Pacific Northwest Laboratory (PNL) is developing in situ vitrification (ISV) as an in-place stabilization technique for selected liquid radioactive waste disposal sites. The process melts the wastes and surrounding soil to produce a durable glass and crystalline waste form. These ISV process development testing and evaluation studies are being conducted for the US Department of Energy. The results of an ISV pilot-scale test conducted in June of 1983 in which soils contaminated with actual radioactive transuranic and mixed fission product elements were vitrified are discussed. The primary objectives of the radioactive test were to: demonstrate containment and confinement of the radioactive material; verify equipment performance of the power and off-gas systems; identify losses to the off-gas system; and characterize the behavior of the radioactive material in the vitrified soil. The test successfully demonstrated the processing containment of radionuclides both within the vitrified mass and in the off-gas system. No environmental release of radioactive material was measured during testing operations. The vitrified soil had a greater than 99% retention of all radionuclides. Losses to the off-gas system varied from less than or equal to 0.03% for particulate materials (plutonium and strontium) to 0.8% for cesium which is a more volatile element. The off-gas system effectively contained both volatile and entrained radioactive materials. Analysis of the vitrified soil revealed that all radionuclides were distributed throughout the vitrified zone, some more uniformly than others. No migration of radionuclides outside the vitrification zone occurred, as indicated by analysis of soil samples from around the block. Previous waste form leaching studies indicate an acceptable durability of the ISV product. 8 references, 34 figures, 8 tables

In situ vitrification pilot-scale radioactive test

Energy Technology Data Exchange (ETDEWEB)

Timmerman, C.L.; Oma, K.H.

1984-10-01

Pacific Northwest Laboratory (PNL) is developing in situ vitrification (ISV) as an in-place stabilization technique for selected liquid radioactive waste disposal sites. The process melts the wastes and surrounding soil to produce a durable glass and crystalline waste form. These ISV process development testing and evaluation studies are being conducted for the US Department of Energy. The results of an ISV pilot-scale test conducted in June of 1983 in which soils contaminated with actual radioactive transuranic and mixed fission product elements were vitrified are discussed. The primary objectives of the radioactive test were to: demonstrate containment and confinement of the radioactive material; verify equipment performance of the power and off-gas systems; identify losses to the off-gas system; and characterize the behavior of the radioactive material in the vitrified soil. The test successfully demonstrated the processing containment of radionuclides both within the vitrified mass and in the off-gas system. No environmental release of radioactive material was measured during testing operations. The vitrified soil had a greater than 99% retention of all radionuclides. Losses to the off-gas system varied from less than or equal to 0.03% for particulate materials (plutonium and strontium) to 0.8% for cesium which is a more volatile element. The off-gas system effectively contained both volatile and entrained radioactive materials. Analysis of the vitrified soil revealed that all radionuclides were distributed throughout the vitrified zone, some more uniformly than others. No migration of radionuclides outside the vitrification zone occurred, as indicated by analysis of soil samples from around the block. Previous waste form leaching studies indicate an acceptable durability of the ISV product. 8 references, 34 figures, 8 tables.

Underground radioactive waste tank remote inspection and sampling

International Nuclear Information System (INIS)

Bzorgi, F.M.; Kelsey, A.P.; Van Hoesen, S.D.; Wiles, C.O.

1996-01-01

Characterization is a critical step in the remediation of contaminated materials and facilities. Severe physical- and radiological-access restrictions made the task of characterizing the World War II-era underground radioactive storage tanks at the Oak Ridge National Laboratory (ORNL) particularly challenging. The innovative and inexpensive tank characterization system (TCS) developed to meet this challenge at ORNL is worthy of consideration for use in similar remediation projects. The TCS is a floating system that uses the existing water in the tank as a platform that supports instruments and samplers mounted on a floating boom. TCS operators feed the unit into an existing port of the tank to be characterized. Once inserted, the system's position is controlled by rotation and by insertion and withdrawal of the boom. The major components of the TCS system include the following: (1) boom support system that consists of a boom support structure and a floating boom, (2) video camera and lights, (3) sludge grab sampler, (4) wall chip sampler, and (5) sonar depth finder. This simple design allows access to all parts of a tank. Moreover, the use of off-the-shelf components keeps the system inexpensive and minimizes maintenance costs. The TCS proved invaluable in negotiating the hazards of ORNL's Gunite and Associated Tanks, which typically contain a layer of radioactive sludge, have only one to three access ports that are usually only 12- or 24-in. in diameter, and range from 12 to 50 ft in diameter. This paper reviews both the successes and the difficulties encountered in using the TCS for treatability studies at ORNL and discusses the prospects for its wider application in remediation activities

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)

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)

Chernobyl radioactivity and high altitude air-particulate monitoring at Islamabad

International Nuclear Information System (INIS)

Bhatti, M.S.; Ihsanullah; Shafiq, M.; Perveen, N.; Orfi, S.D.

1987-11-01

High altitude sampling of air particulates for radioactivity monitoring was conducted at Islamabad after the CHERNOBYL accident. Smears from aeroplanes flying at varying altitudes were collected and analysed for fresh fission products mainly gamma emitters e.g. Ru-103 and Cs-137 etc. The maximum radioactivity observed was of the order of 15Bq/sample for Ru-103 and 9Bq/sample for Cs-137 respectively. The study was purely qualitative in nature indicated the presence of fresh fission radioactivity at high altitudes over Islamabad. For quantitative measurements at high altitudes sophisticated instrumentation/procedure needs to be adopted. (author)

Considerations about radioactive events and their psycho social effects

International Nuclear Information System (INIS)

Vasconcelos, Laercia Abreu

1995-01-01

This study presents some behavioral patterns which are observed in the context of a radioactive accident. Comparing three different situations involving radioactive elements, Three Mile Island (USA), Chernobyl (ISC) and Goiania (Brazil), it is observed that, despite the differences in radiological levels, the populations involved show similar response characteristics. The impact of the radioactive events on health has been the main concern of the exposed population, and the response patterns observed in the different radioactive events seem to be less variable than it was proposed in the first studies. (author)

Investigations of the populations of introduced and resident micro-organisms in deep repositories and their effects on containment of radioactive wastes

International Nuclear Information System (INIS)

West, J.M.; Christofi, N.; Philip, J.C.; Arme, S.C.

1985-04-01

The potential role of microbes in the containment of radioactive waste has been described in several papers but can be briefly summarised as: (1) near field effects ((a) biodeterioration of repository structural materials; (b) mobilisation of waste); (2) far field effects ((a) change in ground water chemistry eg pH, Eh; (b) changes in radionuclide sorption characteristics (speciation, retardation)). The present study has sought to establish the presence of microbes in relevant formations, determine their potential role in disposal and make preliminary investigations on their ability to tolerate extreme environmental conditions and change migration characteristics. As the ultimate goal of this work is to try and model the effect of microorganisms on containment and radionuclide migration, an attempt to define the geochemical constraints on their growth has been attempted within the present study. Several sites of relevance to radioactive waste disposal have been sampled for microbiological content according to a protocol defined in pilot studies. These sites have been in Britain and in mainland Europe. Results have shown that the microbiota of each site is unique but that certain groups are of more importance eg sulphate reducing bacteria, sulphur oxidisers, and that their presence in future sampling should be ascertained as a first priority. (author)

A comparison study on radioactive waste management effectiveness in various nuclear fuel cycles

International Nuclear Information System (INIS)

Ko, Won Il; Kim, Ho Dong

2001-07-01

This study examines whether the DUPIC (Direct Use of Spent PWR Fuel In CANDU) fuel cycle make radioactive waste management more effective, by comparing it with other fuel cycles such as the PWR (Pressurized Water Reactor) once-through cycle, the HWR (Pressurized Heavy Water Reactor) once-through cycle and the thermal recycling option to use an existing PWR with MOX (Mixed Oxide) fuel. This study first focuses on the radioactive waste volume generated in all fuel cycle steps, which could be one of the measures of effectiveness of the waste management. Then the total radioactive waste disposition cost is estimated based on two units measuring; m3/GWe-yr and US$/GWe-yr. We find from the radioactive waste volume estimation that the DUPIC fuel cycle could have lower volumes for milling tailings, low level waste and spent fuel than those of other fuel cycle options. From the results of the disposition cost analysis, we find that the DUPIC waste disposition cost is the lowest among fuel cycle options. If the total waste disposition cost is used as a proxy for quantifying the easiness or difficulty in managing wastes, then the DUPIC option actually make waste management easier

'Intelligent' approach to radioimmunoassay sample counting employing a microprocessor controlled sample counter

International Nuclear Information System (INIS)

Ekins, R.P.; Sufi, S.; Malan, P.G.

1977-01-01

The enormous impact on medical science in the last two decades of microanalytical techniques employing radioisotopic labels has, in turn, generated a large demand for automatic radioisotopic sample counters. Such instruments frequently comprise the most important item of capital equipment required in the use of radioimmunoassay and related techniques and often form a principle bottleneck in the flow of samples through a busy laboratory. It is therefore particularly imperitive that such instruments should be used 'intelligently' and in an optimal fashion to avoid both the very large capital expenditure involved in the unnecessary proliferation of instruments and the time delays arising from their sub-optimal use. The majority of the current generation of radioactive sample counters nevertheless rely on primitive control mechanisms based on a simplistic statistical theory of radioactive sample counting which preclude their efficient and rational use. The fundamental principle upon which this approach is based is that it is useless to continue counting a radioactive sample for a time longer than that required to yield a significant increase in precision of the measurement. Thus, since substantial experimental errors occur during sample preparation, these errors should be assessed and must be releted to the counting errors for that sample. It is the objective of this presentation to demonstrate that the combination of a realistic statistical assessment of radioactive sample measurement, together with the more sophisticated control mechanisms that modern microprocessor technology make possible, may often enable savings in counter usage of the order of 5-10 fold to be made. (orig.) [de

Development of In-situation radioactivity Inspection system

International Nuclear Information System (INIS)

Min, Sujung; Lee, Sanghun; Kim, Miyoung; Kim, Myungjin; Lee, Unjang; Park, Jungkyun

2015-01-01

Many Korean people worry about radioactive contamination of Japanese and Korean marine products. Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time will be developed. The system is to measure the radioactivity level of farm and marine products continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Product performance assessment and tests will be conducted later. When the system develops and its commercialization begins, people's anxiety about radioactive contamination of foods after the Fukushima nuclear accident will be eased and people will be able to trust the radioactive inspection

Development of In-situation radioactivity Inspection system

Energy Technology Data Exchange (ETDEWEB)

Min, Sujung; Lee, Sanghun; Kim, Miyoung; Kim, Myungjin; Lee, Unjang [ORIONENC Co., Seoul (Korea, Republic of); Park, Jungkyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

Many Korean people worry about radioactive contamination of Japanese and Korean marine products. Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time will be developed. The system is to measure the radioactivity level of farm and marine products continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Product performance assessment and tests will be conducted later. When the system develops and its commercialization begins, people's anxiety about radioactive contamination of foods after the Fukushima nuclear accident will be eased and people will be able to trust the radioactive inspection.

90Sr- 90Y and 89Sr beta radioactivity measurement in milk samples using a proportional counter

International Nuclear Information System (INIS)

Mananes, A.; Perez Santos, C.; Martinez Churiaque, F.

1987-01-01

A thin window glas flow proportional counter is used to measure the 90 Sr- 90 Y and 89 Sr beta radioactivity in milk samples. A chemical procedure is used to separate strontium-yttrium from the other radionuclides present in milk. A calculation of the total efficiency of the system is performed which includes an empirical estimation of the backscattering factor. The calibration of the whole process allows the determination of the 90 Sr activity within 10% relative error in spite of uncertainties in the recovery yields of strontium and yttrium. No 89 Sr activity has been detected, and the mean value obtained for the 90 Sr activity in nine milk samples of Cantabria is 0.115 Bq/1 with a minimum detectable activity of 0.0105 Bq. (author) 18 refs

Radioactivity Monitoring of the Irish Environment 2009

International Nuclear Information System (INIS)

McGinnity, P.; Currivan, L.; Dowdall, A.; Fegan, M.; Hanley, O.; Kelleher, K.; McKittrick, L.; Somerville, S.; Wong, J.; Pollard, D.

2010-12-01

This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) during 2009. The RPII has routinely monitored levels of radioactivity in the environment since 1982 and this is the latest in the RPII's series of environmental monitoring reports. The RPII reviews and updates its environmental programme annually so as to ensure it remains relevant and continues to focus on the most important sources of radioactivity in the environment. The principal aims of the RPII's monitoring programme are; to assess the level of radioactivity to which the Irish population is exposed as a result of radioactivity in the environment; to study trends and establish the geographical distribution of contaminating radionuclides so as to better understand the long term behaviour of artificial radioactivity in the food chain and the environment; to ensure that any increase in radiation levels resulting from an accidental release of radioactivity to the environment is detected and assessed rapidly. During 2009 radioactivity was measured in a wide range of foods and environmental materials including: air, water, milk, seafood, foodstuffs and complete meals. The most significant source of artificial radioactivity in the Irish marine environment is the discharge of low level liquid radioactive waste from the Sellafield Nuclear Fuel Reprocessing Plant on the north east coast of England. In order to assess the exposure arising from the source extensive sampling of fish and shellfish landed at ports along the north east coast of Ireland is undertaken. The most exposed group of individuals to discharges from Sellafield have been identified as commercial oyster and mussel farmers working along the north east coastline and their families. Manmade radioactivity is also present in the terrestrial environment due primarily to residual global fallout arising primarily from atmospheric testing of nuclear

Radioactivity Monitoring of the Irish Environment 2008

International Nuclear Information System (INIS)

Fegan, M.; Currivan, L.; Dowdall, A.; Hanley, O.; Hayden, E.; Kelleher, K.; Long, S.; McKittrick, L.; Somerville, S.; Wong, J.; Pollard, D.

2010-01-01

This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) during 2008. The RPII has routinely monitored levels of radioactivity in the environment since 1982 and this is the latest in the RPII's series of environmental monitoring reports. The RPII reviews and updates its environmental programme annually so as to ensure it remains relevant and continues to focus on the most important sources of radioactivity in the environment. The principal aims of the RPII's monitoring programme are; to assess the level of radioactivity to which the Irish population is exposed as a result of radioactivity in the environment; to study trends and establish the geographical distribution of contaminating radionuclides so as to better understand the long term behaviour of artificial radioactivity in the food chain and the environment; to ensure that any increase in radiation levels resulting from an accidental release of radioactivity to the environment is detected and assessed rapidly. During 2008 radioactivity was measured in a wide range of foods and environmental materials including: air, water, milk, seafood, foodstuffs and complete meals. The most significant source of artificial radioactivity in the Irish marine environment is the discharge of low level liquid radioactive waste from the Sellafield Nuclear Fuel Reprocessing Plant on the north east coast of England. In order to assess the exposure arising from the source extensive sampling of fish and shellfish landed at ports along the north east coast of Ireland is undertaken. The most exposed group of individuals to discharges from Sellafield have been identified as commercial oyster and mussel farmers working along the north east coastline and their families. Manmade radioactivity is also present in the terrestrial environment due primarily to residual global fallout arising primarily from atmospheric testing of nuclear

Natural radioactivity of airbone particulates in coal-ash disposal sites

International Nuclear Information System (INIS)

Fukushima, Masanori; Tsukamoto, Masaki

1984-01-01

An investigation was made on the actual concentrations of U, Th and Po in air-borne dust and soil around coal power stations, to study the effect of coal-ash disposal site on natural radioactivity of environmental samples. Samples were collected at a coal-ash disposal and its reference places. The results obtained are summaried as follows; (1) Concentrations of U, Th and Po in air-borne dust at the disposal place was nealy equal to those at the reference place. (2) Origin of those α-emitting elements in the dust was successfully deduced, on the basis of correlating concentrations of Sc and Cl elements in the dust. (3) It was inferred that elements of both U and Po in the dust at disposal site came from soil by about 80% and artificial origin such as exhausted gas by remainder. Almost all Th element were from soil. It was therefore concluded that effect of disposal site on radioactivity concentrations of dusts was negligible. (author)

Radioactivity Monitoring of the Irish Environment 2007

International Nuclear Information System (INIS)

Fegan, M.; Dowdall, A.; Hanley, O.; Hayden, E.; Kelleher, K.; Long, S.; Smith, V.; Somerville, S.; Wong, J.; Pollard, D.

2008-10-01

This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) in 2007. This programme aims to assess the exposure of the Irish population to artificial radioactivity in the envorinment, to review the temporal and geographical distribution of contaminating radionuclides and to maintain systems and procedures which would allow a rapid assessment of environmental contamination to be made in the event of a radiological emergency. In additiopn, some natural radioactivity exposure pathways are included in the programme including radioactivity in surface and ground drinking water. Radioactivity is present in the environment due to natural oprocesses, the testing of nuclear weapons in the atmosphere, past nuclear accidents such as that at Chernobyl in the Ukraine and the routine discharge of radionuclides from nuclear installations. Liquid discharges from the British Nuclear Group reprocessing plant at Sellafield in Cumbria in the north-west of England continue to be the dominant source of artificial radioactivity in the Irish marine environment. The key elements of the monitoring programme implemented by the RPII in 2007 included; assessment of ambient radioactivity based on measurements of radioactivity in air and of external gamma dose rate at permanent monitoring stations located throughout the country; assessment of levels of radioactivity in drinking water; assessment of levels of radioactivity in foodstuffs based on measurements of total diet, milk and various ingredients; assessment of levels of radioactivity in the Irish marine environment based on sampling and measurement of seawater, sediment, seaweed, fish and shellfish. The RPII monitored airborne radioactivity at twelve stations located throughout the country. One of these stations is equipped with a high volume sampler, which allows background concentrations of caesium-137 to be measured; another is equipped to

Assessment of natural radioactivity levels and associated dose rates in soil samples from historical city Panipat, India

Directory of Open Access Journals (Sweden)

Amanjeet

2017-07-01

Full Text Available The natural radioactivity levels have been determined by means of gamma ray spectroscopy in surface soil samples collected from the historical city Panipat and its surrounding areas. The activity concentrations are estimated for 238U (range from 14.82 ± 0.26 to 42.82 ± 0.84 Bq/kg, 232Th (from 12.94 ± 0.32 to 43.48 ± 0.96 Bq/kg and 40K (from 238.05 ± 0.28 to 348.50 ± 0.95 Bq/kg. Radium equivalent activities are calculated to be in the range of 82.24–108.49 Bq/kg with an average value of 92.21 Bq/kg. Absorbed dose rates in air outdoors are measured in the range of 32.01–56.47 nGy/h with an average value of 44.16 nGy/h. The corresponding effective dose rates (indoor and outdoor are calculated to be in the range of 0.09–0.158 mSv/y and 0.039–0.069 mSv/y respectively. The internal and external hazard index varies from 0.234 to 0.339 and 0.207 to 0.286 respectively. The activities of radium equivalent in all the soil samples are lesser than the limit (370 Bq/kg recommended in the Organization for Economic Cooperation and Development (OECD report and the annual effective dose was within the safe limit of 1 mSv/y.

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

The overall results of a study on the stimulatory effects of topical application of radioactive lantern mantle powder

International Nuclear Information System (INIS)

Mortazavi, S.M.J.; Rahmani, M.R.; Rahnama, A.; Saeed-Pour, A.; Nouri, E.; Hosseini, N.; Aghaiee, M.M.

2007-01-01

Complete text of publication follows. Background: Over the past 3 years we have studied the bio-stimulatory effects of the topical application of radioactive lantern mantle powder on rats' neck wounds. Poor educated people in some parts of Iran use burned mantles as a wound healing powder to prevent the bleeding and infections caused by injuries. Some lantern mantles contain low levels of radioactive thorium for maximizing the light output, while non-radioactive mantles contain yttrium. Although radioactive lantern mantles present a minimal radiation health hazard, it is generally believed when inhaled or ingested, thorium containing mantle powder, will be dangerous. In this paper the overall bio-stimulatory effects of burned radioactive lantern mantles on wound healing are presented. Materials and Methods: To perform surface area measurement, twenty rats were divided randomly into two groups of 10 animals each. After inducing general anesthesia, full thickness excision wound was made on the dorsal neck in all animals. The 1st group received topical burned radioactive lantern mantle powder at 1st-3rd day after making excision wounds. The 2nd group received non-radioactive lantern mantle powder at the same days. Accurate blind surface measurement of the wounds by transparency tracing was used for assessment of the wound healing at 1st, 3rd, 7th, 10th and 15th days after making wounds. For histological study, 36 male rats randomly divided into two groups of 18 animals each. Full thickness excision wound (314±31.4 mm2) was made on the dorsal neck in all animals after inducing general anesthesia. For the first 3 days, cases received topical application of the radioactive lantern mantle powder while controls received non-radioactive lantern mantle powder. Three, seven and fourteen days after wounding, 6 rats were chosen by random in each group for wound sampling. Finally to measure the tensile strength, an incision was made on the dorsal neck of the rats. Samples were

Retention of radioactive particles and associated effects in the filter-feeding marine mollusc Mytilus edulis

Energy Technology Data Exchange (ETDEWEB)

Jaeschke, B.C., E-mail: Ben.Jaeschke@gmail.com [Department of Ecology Environment and Plant Sciences, Stockholm University, SE-106 91 Stockholm (Sweden); CERAD CoE, Department of Environmental Sciences, Norwegian University of Life Sciences (NMBU), P.O. Box 5003, N-1432 Ås (Norway); Lind, O.C. [CERAD CoE, Department of Environmental Sciences, Norwegian University of Life Sciences (NMBU), P.O. Box 5003, N-1432 Ås (Norway); Bradshaw, C. [Department of Ecology Environment and Plant Sciences, Stockholm University, SE-106 91 Stockholm (Sweden); Salbu, B. [CERAD CoE, Department of Environmental Sciences, Norwegian University of Life Sciences (NMBU), P.O. Box 5003, N-1432 Ås (Norway)

2015-01-01

Radioactive particles are aggregates of radioactive atoms that may contain significant activity concentrations. They have been released into the environment from nuclear weapons tests, and from accidents and effluents associated with the nuclear fuel cycle. Aquatic filter-feeders can capture and potentially retain radioactive particles, which could then provide concentrated doses to nearby tissues. This study experimentally investigated the retention and effects of radioactive particles in the blue mussel, Mytilus edulis. Spent fuel particles originating from the Dounreay nuclear establishment, and collected in the field, comprised a U and Al alloy containing fission products such as {sup 137}Cs and {sup 90}Sr/{sup 90}Y. Particles were introduced into mussels in suspension with plankton-food or through implantation in the extrapallial cavity. Of the particles introduced with food, 37% were retained for 70 h, and were found on the siphon or gills, with the notable exception of one particle that was ingested and found in the stomach. Particles not retained seemed to have been actively rejected and expelled by the mussels. The largest and most radioactive particle (estimated dose rate 3.18 ± 0.06 Gy h{sup −1}) induced a significant increase in Comet tail-DNA %. In one case this particle caused a large white mark (suggesting necrosis) in the mantle tissue with a simultaneous increase in micronucleus frequency observed in the haemolymph collected from the muscle, implying that non-targeted effects of radiation were induced by radiation from the retained particle. White marks found in the tissue were attributed to ionising radiation and physical irritation. The results indicate that current methods used for risk assessment, based upon the absorbed dose equivalent limit and estimating the “no-effect dose” are inadequate for radioactive particle exposures. Knowledge is lacking about the ecological implications of radioactive particles released into the environment

Retention of radioactive particles and associated effects in the filter-feeding marine mollusc Mytilus edulis

International Nuclear Information System (INIS)

Jaeschke, B.C.; Lind, O.C.; Bradshaw, C.; Salbu, B.

2015-01-01

Radioactive particles are aggregates of radioactive atoms that may contain significant activity concentrations. They have been released into the environment from nuclear weapons tests, and from accidents and effluents associated with the nuclear fuel cycle. Aquatic filter-feeders can capture and potentially retain radioactive particles, which could then provide concentrated doses to nearby tissues. This study experimentally investigated the retention and effects of radioactive particles in the blue mussel, Mytilus edulis. Spent fuel particles originating from the Dounreay nuclear establishment, and collected in the field, comprised a U and Al alloy containing fission products such as 137 Cs and 90 Sr/ 90 Y. Particles were introduced into mussels in suspension with plankton-food or through implantation in the extrapallial cavity. Of the particles introduced with food, 37% were retained for 70 h, and were found on the siphon or gills, with the notable exception of one particle that was ingested and found in the stomach. Particles not retained seemed to have been actively rejected and expelled by the mussels. The largest and most radioactive particle (estimated dose rate 3.18 ± 0.06 Gy h −1 ) induced a significant increase in Comet tail-DNA %. In one case this particle caused a large white mark (suggesting necrosis) in the mantle tissue with a simultaneous increase in micronucleus frequency observed in the haemolymph collected from the muscle, implying that non-targeted effects of radiation were induced by radiation from the retained particle. White marks found in the tissue were attributed to ionising radiation and physical irritation. The results indicate that current methods used for risk assessment, based upon the absorbed dose equivalent limit and estimating the “no-effect dose” are inadequate for radioactive particle exposures. Knowledge is lacking about the ecological implications of radioactive particles released into the environment, for example

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

Potential effects on health of radioactive waste disposal

International Nuclear Information System (INIS)

Sousselier, Y.; Parmentier, N.

1983-07-01

Radioactive waste is considered to represent a potential health risk for future generation by a section of the public. The main point is that waste management must follow very strict guidelines. The radioactive waste treatment, packaging and disposal are rewieved and discussed from a safety point of view. Health physics aspects are then analysed. The major difficulties for the prediction of exposure are mainly due to the very long time periods involved. Models are studied and carried out for the prediction of radiological consequences for the transport of radioactivity through the different modules

On - Site Assessment Methods For Environmental Radioactivity

International Nuclear Information System (INIS)

Petrinec, B.; Babic, D.; Bituh, T.

2015-01-01

A method for the rapid determination of radioactivity in cases of release into the environment as well as in cases of nuclear/radiological accidents is described. These measurements would enable a direct risk assessment for humans and biota, without any sampling and at a considerably larger number of locations than in previous studies. Thus obtained, the substantially expanded dataset is expected to shed more light on the properties of environmental radioactivity both in the region studied and in other similar areas. Field measurements will be performed and samples of soil and biota will be collected in order to compare field results with laboratory measurements. Once the method has been validated, previously unexplored locations will be included in the study. Our measurements at numerous locations will also provide control values for comparison in cases of any unplanned or accidental radiological event. An assessment of the possible effects of radionuclide concentrations on the human food chain and biota will be performed within the appropriate models used worldwide exactly for this purpose. In this way, the project should contribute to regional, European, and global efforts towards understanding the radiological impact on ecosystems. Field measurements will also address certain issues in the environmental metrology of radioactive substances, e.g., simultaneous determination of activity concentrations and related dose rates. This will serve as a tool for rapid risk assessment in emergency situations. (author).

Investigations of the detection of α-radioactivity in samples of effluent water primary circuit and exhaust air of nuclear power plants in the FRG in the years 1973-1975

International Nuclear Information System (INIS)

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

1976-05-01

Since the middle of 1973 the α-radioactivity of aerosol filters from the stack monitoring system and since the middle of 1974 the α-radioactivity in samples from the primary cycle of the KRB was monitored. Effluent water samples of all nuclear power reactors of the FRG were also examined from the middle of 1973 till 1974. Furthermore, aerosol filters sampled in 1973 and 1974 from various places at the KRB and some aerosol filters from the stack monitoring systems of KWW (1973), KWO (1974) and KKS (1975) were also measured. Essentially, the following procedures of sample preparation for α-spectrometry of the samples in large-area gridded ionization chambers were used: cold ashing of the aerosol samples in 'excited' oxygen; coprecipitation of the alpha emitters from the effluent water samples with iron hydroxide and subsequent cold ashing of the precipitate; evaporation of the samples from the primary cycle on SS plates. The following transuranium nuclides, or some of them, were found in the samples of the primary coolant and in several aerosol filter samples: Pu-239/240, Pu-238 and/or Am-241, Cm-242 and Cm-244. Cm-242 contributes most to the α-radioactivity in fresh samples. In the effluent water samples Cm-242. Pu-239/240 and Pu-238 and/or Am-241 were identified in some cases, in one case also Cm-244. The aim of these investigations is to establish procedures for the measurement and surveillance of α-emitting nuclides in the emissions of power reactors in order to study the contribution of transuranium nuclides to the radiation exposure of the population living in the vicinity of nuclear power stations. (orig.) [de

Determination of Natural Radioactivity in Groundwater in Tanke ...

African Journals Online (AJOL)

User

A study of the radioactivity in groundwater from Tanke-Ilorin, Nigeria, has been carried out. Ten water ... et al., 1995) and soil/water samples obtained around production .... radioactive elements 238U and 232Th. The activity of naturally ...

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

A system for mapping radioactive specimens

International Nuclear Information System (INIS)

Britten, R.J.; Davidson, E.H.

1988-01-01

A system for mapping radioactive specimens comprises an avalanche counter, an encoder, pre-amplifier circuits, sample and hold circuits and a programmed computer. The parallel plate counter utilizes avalanche event counting over a large area with the ability to locate radioactive sources in two dimensions. When a beta ray, for example, enters a chamber, an ionization event occurs and the avalanche effect multiplies the event and results in charge collection on the anode surface for a limited period of time before the charge leaks away. The encoder comprises a symmetrical array of planar conductive surfaces separated from the anode by a dielectric material. The encoder couples charge currents, the amlitudes of which define the relative position of the ionization event. The amplitude of coupled current, delivered to pre-amplifiers, defines the location of the event. (author) 12 figs

Natural radioactivity product from coal burning in PLTU Pacitan

International Nuclear Information System (INIS)

Sukirno; Sri Murniasih; Rosidi; Sutanto WW

2016-01-01

Monitoring of radioactivity in the coal-fired power plant has been carried out in the CAST-NAA laboratory at 2015. Monitoring includes analysis of soil, water, fly ash, bottom ash and coal. The basic purpose of this work is the investigation of natural radionuclide contents in coal and the actual product samples in the Pacitan power plant as a first step to estimate the radioactive in the vicinity. This paper presents the results of the analysis of radioactivity in samples of coal, fly ash and bottom ash as well as environment samples of soil and water. Ra-226, Th-232, K-40, U-235, U-238, and Pb-210 Natural radionuclides are determined by gamma spectrometry with HPGe detector. Natural radionuclide in fine grain coal, bottom ash and fly ash have concentrations range (162.182 to 0.057) Bq/kg. Radioactivity contained in soil ranges (0.041 to 169.34) Bq/kg, whereas in water ranges (0.003 to 0.045) Bq/L. According Perka BAPETEN. No. 7 of 2013. On Boundary Value Environmental Radioactivity, the results of measurement analysis contained water around the power plant Pacitan still below the limit values allowed by BAPETEN. (author)

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)

Investigations on the populations of introduced and resident micro-organisms in deep repositories and their effects on containment of radioactive wastes

International Nuclear Information System (INIS)

West, J.M.; Arme, S.C.; Christofi, N.; Philp, J.C.

1986-01-01

The present study has sought to establish basic facts concerning the importance of microbial presence in a radioactive waste repository. These are: (1) establishing the presence of microbes in relevant geological formations; (2) defining the importance of isolated groups to radioactive waste containment; (3) establishing the ability of sampled microbes to tolerate repository environmental conditions; (4) conducting preliminary work on microbial ability to influence radionuclide migration characteristics; (5) attempting basic modelling of the effects of micro-organisms on containment and radionuclide migration. Results have shown that micro-organisms of significance (e.g. sulphur cycle bacteria) are present in relevant formations. These groups can tolerate repository conditions and influence migration studies. Their growth, however, would seem to be limited by the nutrient availability. Simple modelling has concentrated on conservative calculations on the constraints of maximum effects of microbial contamination of a high-level waste repository

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.)

Survey monitoring of environmental radioactivity in Chuncheon area

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Ki.; Hwang, Sang Kyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

2000-12-15

Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2000 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137}Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs and {sup 226}Ra etc. concentrations in the 23 foodstuffs(potato, sweet potato, bean sprout, onion, pumpkin, spinach, welsh onion, radish leaves, red pepper, garlic, lettuce, apple, persimmon, orange, pear, grape, mackerel, Alaska pollack, hairtail, squid oyster, baby clam, mussed) and 5 tap water sampled in Youngsoe area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA value, except {sup 40}K nuclide. The concentrations of {sup 137}Cs and {sup 226}Ra nuclide in tap water are less(or is slightly higher in one sample) than the MDA value.

Radioactivity level of soil around Baqiao coal-fired power plant in China

International Nuclear Information System (INIS)

Lu, Xinwei; Zhao, Caifeng; Chen, Cancan; Liu, Wen

2012-01-01

Natural radioactivity level of soil around Baqiao coal-fired power plant in China was determined using gamma ray spectrometry. The concentrations of 226 Ra, 232 Th and 40 K in the studied soil samples range from 27.6 to 48.8, 44.4 to 61.4 and 640.2 to 992.2 Bq kg −1 with an average of 36.1, 51.1 and 733.9 Bq kg −1 , respectively, which are slightly higher than the average values of Shaanxi soil. The radium equivalent activity, the air absorbed dose rate and the annual effective dose rate were calculated and compared with the internationally reported or reference values. The radium equivalent activities of the studied samples are below the internationally accepted values. The air absorbed dose rate and the annual effective dose rate received by the local residents due to the natural radionuclides in soil are slightly higher than the mean value of Xi'an and worldwide. - Highlights: ► Natural radioactivity in soil around the coal-fired power plant was determined. ► Radiological parameters were used to assess radiation hazard. ► The coal-fired power plant has affected the local radioactivity level.

Determination of lead and radioactivity in cosmetics products: Hazard assessment

Directory of Open Access Journals (Sweden)

Medhat Moustafa E.

2015-01-01

Full Text Available In the proposed work, an investigation on hazard assessment by lead element and natural radioactivity in cosmetic samples collected from various countries is presented. These samples were face powder, eyebrow paint and henna. The lead element in cosmetic samples was determined using particle-induced X-ray emission. Maximum natural radioactivity concentrations of 226Ra and 40K were found in khol and make-up cosmetic samples, respectively. The qualitative analysis of cosmetic samples showed that lead is the most toxic element found in eyebrow paint samples.

An 'intelligent' approach to radioimmunoassay sample counting employing a microprocessor-controlled sample counter

International Nuclear Information System (INIS)

Ekins, R.P.; Sufi, S.; Malan, P.G.

1978-01-01

The enormous impact on medical science in the last two decades of microanalytical techniques employing radioisotopic labels has, in turn, generated a large demand for automatic radioisotopic sample counters. Such instruments frequently comprise the most important item of capital equipment required in the use of radioimmunoassay and related techniques and often form a principle bottleneck in the flow of samples through a busy laboratory. It is therefore imperative that such instruments should be used 'intelligently' and in an optimal fashion to avoid both the very large capital expenditure involved in the unnecessary proliferation of instruments and the time delays arising from their sub-optimal use. Most of the current generation of radioactive sample counters nevertheless rely on primitive control mechanisms based on a simplistic statistical theory of radioactive sample counting which preclude their efficient and rational use. The fundamental principle upon which this approach is based is that it is useless to continue counting a radioactive sample for a time longer than that required to yield a significant increase in precision of the measurement. Thus, since substantial experimental errors occur during sample preparation, these errors should be assessed and must be related to the counting errors for that sample. The objective of the paper is to demonstrate that the combination of a realistic statistical assessment of radioactive sample measurement, together with the more sophisticated control mechanisms that modern microprocessor technology make possible, may often enable savings in counter usage of the order of 5- to 10-fold to be made. (author)

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)

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

Survey monitoring of environmental radioactivity in Daegu area

Energy Technology Data Exchange (ETDEWEB)

Kang, H. D.; Lee, S. Y. [Kyungpook National Univ., Daegu (Korea, Republic of)

1998-01-15

The objectives of the project are to monitor an abnormal radiation level in Taegu and Kyungpook region, and to enhance our ability to prepare for the radiological emergency situation by establishing the radioactivity monitoring system in Taegu and Kyungpook region. Gross beta activities were measured and gamma radionuclides were analysed for the environmental samples of air-borned dust. precipitation. fallout and drinking water collected in Taegu radioactivity monitoring center. and gamma exposure rates were also measured. To establish the basic data base on the environmental radioactivity, gamma radionuclide analyses were carried out for the samples of soil, drinking water, grain, vegetable, milk, and fish which were obtained from 31 different areas, and the spatial gamma exposure rates from 61 different points were also measured in Taegu and Kyungpook region. In conclusion, it didn't appear any evidence for newly pollution of artificial radioactivity in Taegu and Kyungpook region.

Effects of cooking process on the changes of concentration and total amount of radioactive caesium in beef, wild plants and fruits

International Nuclear Information System (INIS)

Nabeshi, Hiromi; Tsutsumi, Tomoaki; Uekusa, Yoshinori; Matsuda, Rieko; Akiyama, Hiroshi; Teshima, Reiko; Hachisuka, Akiko

2016-01-01

In order to obtain information about effects of the cooking process on the changes of concentration and amount of radioactive materials in foods, we determined the concentration of radioactive caesium in several foods such as beef, edible wild plants, blueberries and mushrooms, before and after cooking. Our results showed that drying after soaking in liquid seasoning and the removal of astringent taste were effective in removing radioactive caesium from foods. More than 80% of radioactive caesium could be removed by these cooking methods. These results suggest that cooking processes such as boiling and soaking in liquid seasoning or water are effective to remove radioactive caesium from foods. Moreover, appropriate food additives such as baking soda were useful to promote the removal of radioactive caesium from foods. On the other hand, simple drying, jam making, grilling and tempura cooking could not remove radioactive caesium from foods. In addition, we showed that the concentration of radioactive caesium in foods was raised after simple drying, although the amount of radioactive caesium was unchanged. It would be necessary to monitor radioactive caesium concentration in processed foods because they might have undergone dehydration by cooking, which could result in concentrations exceeding regulatory levels. (author)

Quality checking of radioactive and hazardous waste

International Nuclear Information System (INIS)

Billington, D.M.; Burgoyne, S.M.J.; Dale, C.J.

1992-01-01

This report describes the work of the HMIP Waste Quality Checking Laboratory (WQCL) for the period September 1989 -August 1991. The WQCL has conducted research and development of procedures for the receipt, sampling and analysis of low level solid radioactive waste (LLW), intermediate level radioactive waste (ILW) and hazardous chemical waste (HW). Operational facilities have been commissioned for quality checking both LLW and HW. Waste quality checking has been completed on LLW packages seized from the UK waste disposal route by HMIP Inspectors. Packages have ranged in size from the 200 litre steel drum to half-height ISO freight container. Development work was continued on methods of sample extraction and radio-chemical analysis for cement encapsulated ILW in the form of magnox, graphite and stainless steel. This work was undertaken on non-radioactive simulants. (author)

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 level of different cinnamon samples

Energy Technology Data Exchange (ETDEWEB)

Czegledi, P; Cieleszky, V [Institut of Nutrition, Budapest (Hungry); Andrasi, A; Zombori, P [Koezponti Fizikai Kutato Intezet, Budapest (Hungary)

1980-06-01

/sup 40/K, /sup 90/Sr, /sup 137/Cs, /sup 226/Ra, and /sup 232/Th were determined in cinnamon samples from China, Sri Lanka and Indonesia. The Chinese sample contained an extremenly high quantity of /sup 90/Sr and its /sup 137/Cs content was also considerably higher than that of the other samples.

Radioactivity Monitoring of the Irish Environment 2006

International Nuclear Information System (INIS)

Smith, V.; Dowdall, A; Fegan, M.; Hayden, E.; Kelleher, K.; Long, S.; McEvoy, I.; Somerville, S.; Wong, J.; Pollard, D.

2007-10-01

This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) in 2006. This programme aims to assess the exposure of the Irish population to artificial radioactivity in the environment, to review the temporal and geographical distribution of contaminating radionuclides and to maintain systems and procedures which would allow a rapid assessment of environmental contamination to be made in the event of a radiological emergency. Radioactivity is present in the environment due to natural processes, the testing of nuclear weapons in the atmosphere, past nuclear accidents such as that at Chernobyl in Ukraine and the routine discharge of radionuclides from nuclear installations. Liquid discharges from the British Nuclear Group reprocessing plant at Sellafield in Cumbria in the north-west of England, which are licensed by the UK Environment Agency, continue to be the dominant source of artificial radioactivity in the Irish marine environment. The key elements of the monitoring programme implemented by the RPII in 2006 included; assessment of ambient radioactivity based on measurements of radioactivity in air and of external gamma dose rate at permanent monitoring stations located throughout the country; assessment of levels of radioactivity in drinking water; assessment of levels of radioactivity in foodstuffs based on measurements of total diet, milk and various ingredients; assessment of levels of radioactivity in the Irish marine environment based on sampling and measurement of seawater, sediment, seaweed, fish and shellfish. The RPII monitored airborne radioactivity at ten stations located throughout the country. One of these stations is equipped with a high volume sampler, which allows concentrations of caesium-137 to be measured; another is equipped to detect the presence of the gas krypton-85. This gas is released into the environment primarily as a result of the

Radioactive iodine therapy: Effect on functioning metastases of adenocarcinoma of the thyroid

Energy Technology Data Exchange (ETDEWEB)

Seidlin, S.M.; Marinelli, L.D.; Oshry, E. (Montefiore Hospital, New York, NY (USA))

1990-09-01

A case of metastatic adenocarcinoma of the thyroid is reported in which treatment by means of radioactive iodine has been successful. The patient was completely thyroidectomized for malignant adenoma in 1923, with neither thyrotoxicosis then nor hypothyroidism postoperatively; 15 years later there developed classic symptoms of hyperthyroidism and severe pain in the lower back. In October 1939 a pulsating tumor removed from the level of the 12th thoracic vertebra proved to be metastatic thyroid adenocarcinoma (histologically well differentiated, with small follicles and colloid). In the next two years hyperthyroidism increased and roentgenograms revealed new metastases in the lungs, upper part of the right femur, second rib on the left side, left ilium, and skull. Roentgenologic irradiation of the metastases proved ineffectual. In March 1943 a tracer dose of radioactive iodine revealed iodine retention by all the known lesions and no evidence of residual thyroid tissue in the neck. Therapeutic amounts of radioactive iodine were administered orally between May and October 1943. Definite and lasting clinical improvement followed. In April 1944 and March 1945 additional I* was administered with a resultant disappearance of pain, increase in weight, and progressive change in all clinical criteria in the direction of hypothyroidism. Roentgenographic evidence pointed to an arrest if not a regression of the disease. No untoward effects followed this therapy. Radioactive iodine seems to be an effective therapeutic agent in the control of this type of tumor.

Radioactive iodine therapy: Effect on functioning metastases of adenocarcinoma of the thyroid

International Nuclear Information System (INIS)

Seidlin, S.M.; Marinelli, L.D.; Oshry, E.

1990-01-01

A case of metastatic adenocarcinoma of the thyroid is reported in which treatment by means of radioactive iodine has been successful. The patient was completely thyroidectomized for malignant adenoma in 1923, with neither thyrotoxicosis then nor hypothyroidism postoperatively; 15 years later there developed classic symptoms of hyperthyroidism and severe pain in the lower back. In October 1939 a pulsating tumor removed from the level of the 12th thoracic vertebra proved to be metastatic thyroid adenocarcinoma (histologically well differentiated, with small follicles and colloid). In the next two years hyperthyroidism increased and roentgenograms revealed new metastases in the lungs, upper part of the right femur, second rib on the left side, left ilium, and skull. Roentgenologic irradiation of the metastases proved ineffectual. In March 1943 a tracer dose of radioactive iodine revealed iodine retention by all the known lesions and no evidence of residual thyroid tissue in the neck. Therapeutic amounts of radioactive iodine were administered orally between May and October 1943. Definite and lasting clinical improvement followed. In April 1944 and March 1945 additional I* was administered with a resultant disappearance of pain, increase in weight, and progressive change in all clinical criteria in the direction of hypothyroidism. Roentgenographic evidence pointed to an arrest if not a regression of the disease. No untoward effects followed this therapy. Radioactive iodine seems to be an effective therapeutic agent in the control of this type of tumor

Natural and artificial radioactivity distribution In soil of Fars province (IR)

International Nuclear Information System (INIS)

Faghihi, R.; Mehdizadeh, S.; Sina, S.

2011-01-01

Fars province is a large populated large province located in the southwest of Iran. This work presents a study of natural and radioactivity levels in soil samples of this province. For this purpose, 126 samples were gathered from different regions of the province and analysed by gamma spectroscopy to quantify radioactivity concentrations of radionuclides using a high-purity germanium detector and spectroscopy system. The results of this investigation show the average concentrations of 271 ± 28 Bq kg -1 , 6.37 ± 0.5 Bq kg -1 , 14.9 ± 0.9 Bq kg -1 and 26.3 ± 1.9 Bq kg -1 for 40 K, 137 Cs, 232 Th and 238 U in soil, respectively. Finally, baseline maps were established for the concentrations of each of the radionuclides in different regions. The absorbed dose rate and the annual effective dose (AED) were also calculated for the radionuclides according to the guidelines of UNSCEAR 2000. The average AED from the radioactivity content of soil in this province was found to be 39.9 ± 1.8 μSv. (authors)

Analysis on the influence of forest soil characteristics on radioactive Cs infiltration and evaluation of residual radioactive Cs on surfaces.

Science.gov (United States)

Mori, Yoshitomo; Yoneda, Minoru; Shimada, Yoko; Fukutani, Satoshi; Ikegami, Maiko; Shimomura, Ryohei

2018-03-29

We investigated the depth profiles of radioactive Cs, ignition loss, and cation exchange capacity (CEC) in five types of forest soils sampled using scraper plates. We then simulated the monitored depth profiles in a compartment model, taking ignition loss as a parameter based on experimental results showing a positive correlation between ignition loss and the CEC. The calculated values were comparable with the monitored values, though some discrepancy was observed in the middle of the soil layer. Based on decontamination data on the surface dose rate and surface contamination concentration, we newly defined a surface residual index (SRI) to evaluate the residual radioactive Cs on surfaces. The SRI value tended to gradually decrease in forests and unpaved roads and was much smaller in forests and on unpaved roads than on paved roads. The radioactive Cs was assumed to have already infiltrated underground 18 months after the nuclear power plant accident, and the sinking was assumed to be ongoing. The SRI values measured on paved roads suggested that radioactive Cs remained on the surfaces, though a gradual infiltration was observed towards the end of the monitoring term. The SRI value is thought to be effective in grasping the rough condition of residual radioactive Cs quickly at sites of decontamination activity in the field. The SRI value may be serviceable for actual contamination works after further research is done to elucidate points such as the relation between the SRI and the infiltration of radioactive Cs in various types of objects.

Elemental and radioactive analysis of commercially available seaweed

International Nuclear Information System (INIS)

Van Netten, C.; Hoption Cann, S.A.; Van Netten, J.P.; Morley, D.R.

2000-01-01

Edible seaweed products have been used in many countries, specifically Japan, as a food item. Recently these products have become popular in the food industry because of a number of interesting medicinal properties that have been associated with certain edible marine algae. Very little control exists over the composition of these products, which could be contaminated with a number of agents including heavy metals and certain radioactive isotopes. Fifteen seaweed samples (six local samples from the coast of British Columbia, seven from Japan, one from Norway and one undisclosed) were obtained. All samples were analyzed for multiple elements, using ICP mass spectrometry and for radioactive constituents. It was found that six of eight imported seaweed products had concentrations of mercury orders of magnitude higher than the local products. Lead was found at somewhat higher concentrations in only one local product. Laminaria japonica had the highest level of iodine content followed by Laminaria setchellii from local sources. Only traces of cesium-137 were found in a product from Norway and radium-226 was found in a product from Japan. Arsenic levels were found to be elevated. In order to estimate the effect of these levels on health, one needs to address the bioavailability and the speciation of arsenic in these samples

Elemental and radioactive analysis of commercially available seaweed

Energy Technology Data Exchange (ETDEWEB)

Van Netten, C. [Department of Health Care and Epidemiology, James Mather Building, University of British Columbia, 5804 Fairview Avenue, V6T 1Z3 Vancouver, BC (Canada); Hoption Cann, S.A.; Van Netten, J.P. [Special Development Laboratory, Royal Jubilee Hospital, V8X 1P2 Victoria, BC (Canada); Morley, D.R. [Radiation Protection Branch, Ministry of Health, 4940 Canada Way, V5G 4K6 Burnaby, BC (Canada)

2000-06-08

Edible seaweed products have been used in many countries, specifically Japan, as a food item. Recently these products have become popular in the food industry because of a number of interesting medicinal properties that have been associated with certain edible marine algae. Very little control exists over the composition of these products, which could be contaminated with a number of agents including heavy metals and certain radioactive isotopes. Fifteen seaweed samples (six local samples from the coast of British Columbia, seven from Japan, one from Norway and one undisclosed) were obtained. All samples were analyzed for multiple elements, using ICP mass spectrometry and for radioactive constituents. It was found that six of eight imported seaweed products had concentrations of mercury orders of magnitude higher than the local products. Lead was found at somewhat higher concentrations in only one local product. Laminaria japonica had the highest level of iodine content followed by Laminaria setchellii from local sources. Only traces of cesium-137 were found in a product from Norway and radium-226 was found in a product from Japan. Arsenic levels were found to be elevated. In order to estimate the effect of these levels on health, one needs to address the bioavailability and the speciation of arsenic in these samples.

Oceanographic survey for radioactivity analysis in the South Sea of Korea

International Nuclear Information System (INIS)

Jung, Kyu Kui; Jeong, Chang Soo; Choi, Yang Ho

2006-12-01

The objectives of this work are to collect and provide the samples for radioactivity analysis and the fundamental data for the understanding of distribution and function of radioactive materials through oceanographic investigation and analysis in the South Sea of Korea. To achieve the objectives, we conducted twice oceanographic surveys and analyzed the oceanographic characteristics in the South Sea of Korea. In addition, for the radioactivity analysis, water samples and various marine organism were collected and provided to KINS

Oceanographic survey for radioactivity analysis in the South Sea of Korea

International Nuclear Information System (INIS)

Choi, Yong Kyu; Lee, Sam Keum; Lee, Yong Hwa; Choi, Ok In; Oh, Hyun Ju; Seo, Young Il; Yang, Jun Hyuk; Jung, Ra Young

2005-12-01

The objectives of this work are to collect and provide the samples for radioactivity analysis and the fundamental data for the understanding of distribution and function of radioactive materials through oceanographic investigation and analysis in the South Sea of Korea. To achieve the objectives, we conducted twice oceanographic surveys and analyzed the oceanographic characteristics in the South Sea of Korea. In addition, for the radioactivity analysis, water samples and various marine organism were collected and provided to KINS

Radioactivity in food and the environment, 1996

International Nuclear Information System (INIS)

1997-09-01

This report continues the series which combines the results of the radioactivity monitoring programmes previously published by MAFF in two documents: the 'Terrestrial Radioactivity Monitoring Programme (TRAMP) Report: Radioactivity in food and agricultural products in England and Wales' and the 'Aquatic Environment Monitoring Report: Radioactivity in surface and coastal waters of the British Isles' (AEMR). For the first time the report includes the results of all environmental monitoring for radioactivity carried out on behalf of the regulatory authority in Scotland. These results were previously presented in the 'Statistical Bulletin: Environmental Monitoring for Radioactivity in Scotland' (e.g. The Scottish Office, (1996). Measurements in 1996 included the analysis of samples of food and other materials from the environment and detection of beta and gamma dose rates in the environment. The results show that radionuclide concentrations and radiation dose rates were generally similar to those in 1995. However, near Sellafield, despite the general downward trend in disposals from the site during 1996, there were some increases in concentrations of technetium-99 and carbon-14 in marine foodstuffs reflecting disposals from and operations on the site in previous years. These operations included processing of stored wastes and the operation of the Enhanced Actinide Removal Plant (EARP). The Thermal Oxide Reprocessing Plant (THORP) continued its commissioning phase in 1996 and its disposals had little effect on food and the marine environment. The results of the monitoring have been interpreted in terms of public radiation exposures using data on activity levels in food and local surveys to establish potential 'critical groups' of people likely to be most exposed. (author)

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