Natural radioactivity in the Dutch outdoor environment. The explanation of uncomprehended variations in the background

International Nuclear Information System (INIS)

Blaauboer, R.O.; Smetsers, R.C.G.M.

1996-01-01

In the Netherlands and many other countries research in the field of natural radioactivity is focused on the prevention of radon in the indoor environment. However, also the occurrence of natural radioactivity in the outdoor environment is an interesting subject to be studied. The natural background radiation in the outdoor environment, in particular its variations, hinders the verification of radiation level standards, caused by human activities. An analysis of the data of the Dutch National Monitoring Network for Radioactivity (LMR) provided more insight into those variations. This article is a summary of the authors' thesis on the subject. 5 figs., 8 refs

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)

DIRADTM - a system for real time detection and identification of radioactive objects

International Nuclear Information System (INIS)

Guillot, L.; Reboli, A.

2009-01-01

The authors present the DIRAD system (DIRAD stands for Detection and Identification of Radionuclides), an automatic system for real time identification of a radioactive anomaly and its interpretation in terms of risk level. It can be adapted to different contexts: pedestrian control, parcel or luggage control, road traffic control, and so on. In case of risk detection, an alert is transmitted in real time to a supervision station along with the whole set of spectral data

Qualitative values of radioactivity, area and volumetric: Application on phantoms (target and background)

Energy Technology Data Exchange (ETDEWEB)

Abdel-Rahman Al-Shakhrah, Issa [Department of Physics, University of Jordan, Queen Rania Street, Amman (Jordan)], E-mail: issashak@yahoo.com

2009-04-15

The visualization of a lesion depends on the contrast between the lesion and surrounding background (T/B; (target/background) ratio). For imaging in vivo not only is the radioactivity in the target organ important, but so too is the ratio of radioactivity in the target versus that in the background. Nearly all studies reported in the literature have dealt with the surface index, as a standard factor to study the relationship between the target (tissue or organ) and the background. It is necessary to know the ratio between the volumetric activity of lesions (targets) and normal tissues (background) instead of knowing the ratio between the area activity, the volume index being a more realistic factor than the area index as the targets (tissues or organs) are real volumes that have surfaces. The intention is that this work should aid in approaching a quantitative relationship and differentiation between different tissues (target/background or abnormal/normal tissues). For the background, square regions of interest (Rios) (11x11 pixels in size) were manually drawn by the observer at locations far from the border of the plastic cylinder (simulated organ), while an isocontour region with 50% threshold was drawn automatically over the cylinder. The total number of counts and pixels in each of these regions was calculated. The relationship between different phantom parameters, cylinder (target) depth, area activity ratio (background/target, A(B/T)) and real volumetric activity ratio (background/target, V(B/T)), was demonstrated. Variations in the area and volumetric activity ratio values with respect to the depth were deduced. To find a realistic value of the ratio, calibration charts have been constructed that relate the area and real volumetric ratios as a function of depth of the tissues and organs. Our experiments show that the cross-sectional area of the cylinder (applying a threshold 50% isocontour) has a weak dependence on the activity concentrations of the

Qualitative values of radioactivity, area and volumetric: Application on phantoms (target and background)

International Nuclear Information System (INIS)

Abdel-Rahman Al-Shakhrah, Issa

2009-01-01

The visualization of a lesion depends on the contrast between the lesion and surrounding background (T/B; (target/background) ratio). For imaging in vivo not only is the radioactivity in the target organ important, but so too is the ratio of radioactivity in the target versus that in the background. Nearly all studies reported in the literature have dealt with the surface index, as a standard factor to study the relationship between the target (tissue or organ) and the background. It is necessary to know the ratio between the volumetric activity of lesions (targets) and normal tissues (background) instead of knowing the ratio between the area activity, the volume index being a more realistic factor than the area index as the targets (tissues or organs) are real volumes that have surfaces. The intention is that this work should aid in approaching a quantitative relationship and differentiation between different tissues (target/background or abnormal/normal tissues). For the background, square regions of interest (Rios) (11x11 pixels in size) were manually drawn by the observer at locations far from the border of the plastic cylinder (simulated organ), while an isocontour region with 50% threshold was drawn automatically over the cylinder. The total number of counts and pixels in each of these regions was calculated. The relationship between different phantom parameters, cylinder (target) depth, area activity ratio (background/target, A(B/T)) and real volumetric activity ratio (background/target, V(B/T)), was demonstrated. Variations in the area and volumetric activity ratio values with respect to the depth were deduced. To find a realistic value of the ratio, calibration charts have been constructed that relate the area and real volumetric ratios as a function of depth of the tissues and organs. Our experiments show that the cross-sectional area of the cylinder (applying a threshold 50% isocontour) has a weak dependence on the activity concentrations of the

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.

Identification and characterization of Department of Energy special-case radioactive waste

International Nuclear Information System (INIS)

Williams, R.E.; Kudera, D.E.

1990-01-01

This paper identifies and characterizes Department of Energy (DOE) special-case radioactive wastes. Included in this paper are descriptions of the special-case waste categories and their volumes and curie contents, as well as discussions of potential methods for management of these special-case wastes. Work on extensive inventories of DOE-titled special-case waste are still in progress. All radioactive waste is characterized to determine its waste category. Some wastes may have characteristics of more than one of the major waste types. These characteristics may prevent such wastes from being managed as typical high-level, low-level, or transuranic waste. DOE has termed these wastes special-case wastes. Special-case wastes may require special management and disposal schemes. Because of these special considerations, DOE-Headquarters (HQ) required the identification of all existing and potential DOE-owned special case waste to determine future management planning and funding requirements. The inventory effort includes all commercially held, DOE-owned radioactive materials

Site Study Plan for background environmental radioactivity, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

International Nuclear Information System (INIS)

1987-06-01

The Background Environmental Radioactivity Site Study Plan describes a field program consisting of an initial radiological survey and a radiological sampling program. The field program includes measurement of direct radiation and collection and analysis of background radioactivity samples of air, precipitation, soil, water, milk, pasture grass, food crops, meat, poultry, game, and eggs. The plan describes for each study: the need for the study, the study design, data management and use, schedule of proposed activities, and quality assurance requirements. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Project (SRP) Requirements Document. 50 refs., 11 figs., 7 tabs

China's deep geological disposal program for high level radioactive waste, background and status 1998

International Nuclear Information System (INIS)

Ju Wang; Xu Guoqing; Guo Yonghai

2001-01-01

This paper presents the background and progress made in the study of China's high level radioactive waste, including site screening, site evaluation, the study on radionuclide migration, bentonite, natural analogue studies, and performance assessment, etc. The study on Beishan area, the potential area for China's geological repository, is also presented in this paper. (author)

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.

The MOON-1 detector construction and the study of backgrounds from radioactive isotopes

International Nuclear Information System (INIS)

Ogama, T; Nakamura, H; Ejiri, H; Fushimi, K; Ichihara, K; Matsuoka, K; Nomachi, M; Hazama, R; Umehara, S; Yoshida, S; Sakiuchi, T; Hai, V H; Sugaya, Y

2006-01-01

MOON is a multilayer system of plastic scintillators and 100 Mo films for 100 Mo 0νββ decays. A prototype detector MOON-1 was built with 6 layers of plastic scintillators and 142g of 100Mo films for background (BG), energy and position resolution studies of the MOON detector. No serious BG from natural radioactive isotopes (RI) for 0νββ detection was found

Radioactive background of Granito Madeira, north Amazonas, Brazil

Energy Technology Data Exchange (ETDEWEB)

Moura, Vanderlei; Pereira, Claubia; Martins, Agnaldo Kenji, E-mail: vandermoura@gmail.com, E-mail: claubia@nuclear.ufmg.br, E-mail: amartins@mtaboca.com.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Mineracao Taboca S.A., Presidente Figueiredo, AM (Brazil)

2017-11-01

Naturally occurring radionuclides, such as the uranium and thorium decay chains, are present in rocks and soils. But its distribution is not homogeneous: it depends on the type of rock being that those of volcanic origin have higher concentrations of uranium and thorium. These are NORM. Locations with NORM present higher dose rates than the world average. Thus, the determination of the natural radioactivity of a NORM region is of extreme importance since it provides data for the estimation of human exposure to natural radiation. In addition, if there is a mining company exploring NORM, the background radiation estimation should be considered in the decommissioning and future planning. There are places in Brazil, such as Granito Madeira in the state of Amazonas, in the north of Brazil, where NORM is present. It is an extremely remote area located within the Amazon Forest currently in the process of open cast mining. In this study, the iodide scintillator detector was used to measure and map the natural background radiation of the Granito Madeira using a scintillator detector of sodium iodide that was transported in tracks within the forest. The data obtained were georeferenced, classified and used to obtain the annual dose related to gamma radiation. The results are presented in frequency histograms and maps. The annual average was (6.0 ± 3.0) mSv.y{sup -1}. These data were compared to those available from other regions with NORM in Brazil and the 2010 UNSCEAR report. (author)

Radioactive background of Granito Madeira, north Amazonas, Brazil

International Nuclear Information System (INIS)

Moura, Vanderlei; Pereira, Claubia; Martins, Agnaldo Kenji

2017-01-01

Naturally occurring radionuclides, such as the uranium and thorium decay chains, are present in rocks and soils. But its distribution is not homogeneous: it depends on the type of rock being that those of volcanic origin have higher concentrations of uranium and thorium. These are NORM. Locations with NORM present higher dose rates than the world average. Thus, the determination of the natural radioactivity of a NORM region is of extreme importance since it provides data for the estimation of human exposure to natural radiation. In addition, if there is a mining company exploring NORM, the background radiation estimation should be considered in the decommissioning and future planning. There are places in Brazil, such as Granito Madeira in the state of Amazonas, in the north of Brazil, where NORM is present. It is an extremely remote area located within the Amazon Forest currently in the process of open cast mining. In this study, the iodide scintillator detector was used to measure and map the natural background radiation of the Granito Madeira using a scintillator detector of sodium iodide that was transported in tracks within the forest. The data obtained were georeferenced, classified and used to obtain the annual dose related to gamma radiation. The results are presented in frequency histograms and maps. The annual average was (6.0 ± 3.0) mSv.y"-"1. These data were compared to those available from other regions with NORM in Brazil and the 2010 UNSCEAR report. (author)

Measurements of the background radioactivity in a salt mine in Remolinos (Zaragoza, Spain)

International Nuclear Information System (INIS)

Gerona, G.; Morales, A.; Nunez-Lagos, R.; Puimedon, J.; Villar, J.A.

1986-01-01

Measurements of the background radioactivity in a salt mine in Remolinos (Zaragoza) have been performed. The site was 200 mwe deep in a gallery far (1 Km) from the actual mining area. The detector has been a 120 cm 3 Ge(Li) with conventional electronic and magnetic read-out. Neutron induced radiation was detected by surrounding the detector with borax. Different shieldings have been studied. Results are compared with laboratory data of Zaragoza. (author)

Identification and determination of natural radioactive impurities in rare earth chlorides

International Nuclear Information System (INIS)

Gu, M.J.; Cen, Y.H.; Tang, T.Y.; Chang, J.X.

1988-01-01

227 Ac, 228 Th, 226 Ra, 210 Po and 210 Pb can be present at rare earth chlorides. A radiochemical procedure is presented for the identification and determination of natural radioactive impurities in rare earth chlorides. The determination limits for these radionuclides were 1.5x10 -4 to 3x10 -1 Bq/g. The relative standard deviations for determining 10 -2 Bq/g radionuclides were usually less than +-7%. (author) 9 refs.; 3 figs.; 2 tabs

Radioactive background in principal components of the Jihlava River ecosystem

International Nuclear Information System (INIS)

Stanek, Z.; Penaz, M.; Trnkova, J.; Wohlgemuth, E.

1980-01-01

In 1976 through to 1978, the radioactive background was investigated in the various components of the Jihlava River ecosystem. The investigations involved total β-activity, 40 K, residual β-activity, sup(nat)U, 226 Ra and, in some of the samples, also 210 Pb, 90 Sr and 137 Cs. The analyses included water, bottom sediments, samples of aquatic macrophytes (Batrachium fluitans), samples of aquatic invertebrates (Herpobdella octoculata, Anodonta cygnea, Asellus aquaticus, larval Ephemeroptera, larval Trichoptera, exuviae of pupae of Chironomidae) and samples of the tissues of 8 species of fishes (Salmo trutta m. fario, Cyprinus carpio, Rutilus rutilus, Leuciscus cephalus, Leuciscus leuciscus, Chondrostoma nasus, Gobio gobio, Barbus barbus). The activity of the radionuclides under study corresponded to the values reported for uncontaminated streams. (author)

Real breakthrough in detection of radioactive sources by portal monitors with plastic detectors and New Advanced Source Identification Algorithm (ASIA-New)

Energy Technology Data Exchange (ETDEWEB)

Stavrov, Andrei; Yamamoto, Eugene [Rapiscan Systems, Inc., 14000 Mead Street, Longmont, CO, 80504 (United States)

2015-07-01

Radiation Portal Monitors (RPM) with plastic detectors represent the main instruments used for primary border (customs) radiation control. RPM are widely used because they are simple, reliable, relatively inexpensive and have a high sensitivity. However, experience using the RPM in various countries has revealed the systems have some grave shortcomings. There is a dramatic decrease of the probability of detection of radioactive sources under high suppression of the natural gamma background (radiation control of heavy cargoes, containers and, especially, trains). NORM (Naturally Occurring Radioactive Material) existing in objects under control trigger the so-called 'nuisance alarms', requiring a secondary inspection for source verification. At a number of sites, the rate of such alarms is so high it significantly complicates the work of customs and border officers. This paper presents a brief description of new variant of algorithm ASIA-New (New Advanced Source Identification Algorithm), which was developed by the Rapiscan company. It also demonstrates results of different tests and the capability of a new system to overcome the shortcomings stated above. New electronics and ASIA-New enables RPM to detect radioactive sources under a high background suppression (tested at 15-30%) and to verify the detected NORM (KCl) and the artificial isotopes (Co- 57, Ba-133 and other). New variant of ASIA is based on physical principles, a phenomenological approach and analysis of some important parameter changes during the vehicle passage through the monitor control area. Thanks to this capability main advantage of new system is that this system can be easily installed into any RPM with plastic detectors. Taking into account that more than 4000 RPM has been installed worldwide their upgrading by ASIA-New may significantly increase probability of detection and verification of radioactive sources even masked by NORM. This algorithm was tested for 1,395 passages of

Background studies: human-induced effects on the evolution of shallow land burial sites for radioactive waste disposal

International Nuclear Information System (INIS)

1987-11-01

This report presents the results of a programme of background research on the human-induced effects on the long term evolution of shallow disposal sites for low level radioactive wastes. The work is intended to support development and use of the TIME2 simulation code. Within the context of climatic change up to the next glacial maximum three areas are addressed: planning and legislative control over site usage, biosphere state changes and intrusion. An appendix presents a discussion of some planning aspects of radioactive waste disposal. (author)

Relation between distribution coefficient of radioactive strontium and solid-liquid distribution ratio of background stable strontium

International Nuclear Information System (INIS)

Igarashi, Toshifumi; Mahara, Yasunori; Okamura, Masaki; Ashikawa, Nobuo.

1992-01-01

Distribution coefficients (K d ) of nuclides, which are defined as the ratio of the adsorbed concentration to the solution concentration, are important in predicting nuclide migration in the subsurface environment. This study was undertaken to contrust an effective method of determining the most pertinent K d value for simulating in situ distribution phenomena between the solid and liquid phases, by using background stable isotopes. This paper describes the applicability of this method to Sr by carrying out a batch Sr adsorption experiment where stable Sr coexisted with the radioactive isotope, 85 Sr, and by comparing the concentration distribution ratio of the background stable Sr with the K d value obtained by the batch experiment. The results showed that the K d of 85 Sr (K d85 ) agreed well with the K d of the coexisting stable Sr (K ds ) and that the two values decreased with an increase in the concentration of the stable Sr, when sand was used as an adsorbent. In addition, the K d85 corresponded to the ratio of the exchangeable solid-phase concentration of background stable Sr to the concentration of the background stable Sr in groundwater when the concentration of the coexisting stable Sr approached the background level. On the other hand, when powdered rock samples were used, the K d85 did not agree with the K ds , and the concentration distribution ratio of the background stable Sr was greater than the K d85 . This discrepancy might be due to the disequilibrium resulting from grinding the rock matrices. This suggests that measurement of the background stable Sr distribution ratio between the solid and liquid phases can be an effective method of estimating the K d of radioactive Sr when the groundwater is in satisfactory contact with the adsorption medium. (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)

Radiation after-effects in daughter generations of barley grown under conditions of enhanced radioactive background

International Nuclear Information System (INIS)

Popova, O.N.; Shershunova, V.I.; Taskaev, A.I.

1978-01-01

Stimulation of growth and development was observed in the first daughter generation of barley plants grown under conditions simulating an enhanced radioactive background. The stimulatory effect was partially reproduced in the second generation, and signs of depression of initial growth of plants were found in the third generation. A great number of alterations and their regular occurrence allow to refer them to lingering modifications originating under the effect of a radiation factor on vegetating plants

Disposal of radioactive and other hazardous wastes

International Nuclear Information System (INIS)

Boge, R.; Bergman, C.; Bergvall, S.; Gyllander, C.

1989-01-01

The purpose of the workshop was discuss legal, scientific and practical aspects of disposal of low- and intermediate-level radioactive waste and other types of hazardous waste. During the workshop the non-radioactive wastes discussed were mainly wastes from energy production, but also industrial, chemical and household wastes. The workshop gave the participants the opportunity to exchange information on policies, national strategies and other important matters. A number of invited papers were presented and the participants brought background papers, describing the national situation, that were used in the working groups. One of the main aims of the workshop was to discuss if the same basic philosophy as that used in radiation protection could be used in the assessment of disposal of non-radioactive waste, as well as to come up with identifications of areas for future work and to propose fields for research and international cooperation. The main text of the report consists of a summary of the discussions and the conclusions reached by the workshop

Some historical background to the IAEA Definition and Recommendations concerning high-level radioactive wastes or other high-level radioactive matter unsuitable for dumping at sea

International Nuclear Information System (INIS)

Nishiwaki, Y.

1981-01-01

The need for internationally acceptable standards and regulations for preventing pollution of the sea by radioactive materials was recognized by the United Nations Conference on the Law of the Sea, which adopted the Convention on the High Seas in April 1958. Article 25 of the Convention provides that ''every State shall take measures to prevent pollution of the seas from the dumping of radioactive wastes, taking into account any standards and regulations which may be formulated by the competent international organizations.'' The Conference also adopted a resolution recommending that the IAEA pursue studies and take action to assist States in controlling the discharge of radioactive materials into the sea. When the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter was adopted at the Intergovernmental Conference in London, 1972, the IAEA was given specific responsibilities to define criteria and standards for dealing with the questions of sea disposal of radioactive wastes. The IAEA Definition and Recommendations concerning ''high-level radioactive wastes or other high-level radioactive matter unsuitable for dumping at sea'' identify material, the radioactive content of which is at such a level that the Parties to the Convention would wish to prevent any participating State from issuing a special permit even after a detailed appraisal of the safety of the proposed operation, and even for the sector of the marine environment furthest removed from man, i.e. the deep sea with depth greater than 4000 m. Some historical background to these problems is discussed and some of the Japanese findings of the deep sea survey in the Pacific are introduced for comparison with the North Atlantic data which formed a basis of the IAEA Definition and Recommendations for the London Dumping Convention

High-level radioactive waste in Canada. Background paper

International Nuclear Information System (INIS)

Fawcett, R.

1993-11-01

The disposal of radioactive waste is one of the most challenging environmental problems facing Canada today. Since the Second World War, when Canadian scientists first started to investigate nuclear reactions, there has been a steady accumulation of such waste. Research reactors built in the early postwar years produced small amounts of radioactive material but the volume grew steadily as the nuclear power reactors constructed during the 1960s and 1970s began to spawn used fuel bundles. Although this radioactive refuse has been safely stored for the short term, no permanent disposal system has yet been fully developed and implemented. Canada is not alone in this regard. A large number of countries use nuclear power reactors but none has yet put in place a method for the long-term disposal of the radioactive waste. Scientists and engineers throughout the world are investigating different possibilities; however, enormous difficulties remain. In Canada, used fuel bundles from nuclear reactors are defined as high-level waste; all other waste created at different stages in the nuclear fuel cycle is classified as low-level. Although disposal of low-level waste is an important issue, it is a more tractable problem than the disposal of high-level waste, on which this paper will concentrate. The paper discusses the nuclear fuel waste management program in Canada, where a long-term disposal plan has been under development by scientists and engineers over the past 15 years, but will not be completed for some time. Also discussed are responses to the program by parliamentary committees and aboriginal and environmental groups, and the work in the area being conducted in other countries. (author). 1 tab

High-level radioactive waste in Canada. Background paper

Energy Technology Data Exchange (ETDEWEB)

Fawcett, R [Library of Parliament, Ottawa, ON (Canada). Science and Technology Div.

1993-11-01

The disposal of radioactive waste is one of the most challenging environmental problems facing Canada today. Since the Second World War, when Canadian scientists first started to investigate nuclear reactions, there has been a steady accumulation of such waste. Research reactors built in the early postwar years produced small amounts of radioactive material but the volume grew steadily as the nuclear power reactors constructed during the 1960s and 1970s began to spawn used fuel bundles. Although this radioactive refuse has been safely stored for the short term, no permanent disposal system has yet been fully developed and implemented. Canada is not alone in this regard. A large number of countries use nuclear power reactors but none has yet put in place a method for the long-term disposal of the radioactive waste. Scientists and engineers throughout the world are investigating different possibilities; however, enormous difficulties remain. In Canada, used fuel bundles from nuclear reactors are defined as high-level waste; all other waste created at different stages in the nuclear fuel cycle is classified as low-level. Although disposal of low-level waste is an important issue, it is a more tractable problem than the disposal of high-level waste, on which this paper will concentrate. The paper discusses the nuclear fuel waste management program in Canada, where a long-term disposal plan has been under development by scientists and engineers over the past 15 years, but will not be completed for some time. Also discussed are responses to the program by parliamentary committees and aboriginal and environmental groups, and the work in the area being conducted in other countries. (author). 1 tab.

Transportation of radioactive, hazardous, and mixed wastes: Material identification is the key

International Nuclear Information System (INIS)

Stancell, D.F.; Willaford, D.M.

1992-01-01

This paper will discuss how material identification and classification will result in an accurate determination of regulatory requirements, and will assure safe and compliant shipment of radioactive, hazardous, and mixed wastes. The primary focus of the paper is a discussion of lessons learned by the Department of Energy in making waste shipments, and how this can be applied to future mixed waste shipments. There will be a brief discussion of the Department's regulatory compliance program, including a presentation of compliance audit results, and how regulatory issues are addressed through effective information exchange, technical assistance, and compliance training. A detailed discussion will follow, which describes cases involving material identification and classification problems. Examples will include both RCRA waste and uranium mill tailings shipments. The paper will conclude with a discussion concerning the application of these lessons to future mixed waste shipments proposed by the Department. (author)

REAL-TIME IDENTIFICATION AND CHARACTERIZATION OF ASBESTOS AND CONCRETE MATERIALS WITH RADIOACTIVE CONTAMINATION

International Nuclear Information System (INIS)

XU, X. George; Zhang, X.C.

2002-01-01

Concrete and asbestos-containing materials were widely used in DOE building construction in the 1940s and 1950s. Over the years, many of these porous materials have been contaminated with radioactive sources, on and below the surface. To improve current practice in identifying hazardous materials and in characterizing radioactive contamination, an interdisciplinary team from Rensselaer has conducted research in two aspects: (1) to develop terahertz time-domain spectroscopy and imaging system that can be used to analyze environmental samples such as asbestos in the field, and (2) to develop algorithms for characterizing the radioactive contamination depth profiles in real-time in the field using gamma spectroscopy. The basic research focused on the following: (1) mechanism of generating of broadband pulsed radiation in terahertz region, (2) optimal free-space electro-optic sampling for asbestos, (3) absorption and transmission mechanisms of asbestos in THz region, (4) the role of asbestos sample conditions on the temporal and spectral distributions, (5) real-time identification and mapping of asbestos using THz imaging, (7) Monte Carlo modeling of distributed contamination from diffusion of radioactive materials into porous concrete and asbestos materials, (8) development of unfolding algorithms for gamma spectroscopy, and (9) portable and integrated spectroscopy systems for field testing in DOE. Final results of the project show that the combination of these innovative approaches has the potential to bring significant improvement in future risk reduction and cost/time saving in DOE's D and D activities

Equipment for the continuous measurement and identification of gamma radioactivity on aerosols

Energy Technology Data Exchange (ETDEWEB)

De Blas, Alfredo; Tapia, Carlos; Riego, Albert; Garcia, Roger; Dies, Javier; Diaz, Pedro [Nuclear Engineering Research Group, Departament of Physics and Nuclear Engineering, Technical University of Catalonia, Barcelona (Spain); Toral, Juan [Raditel Serveis. Tarragona (Spain); Batalla, Enric [Radiological Activities Corrdination Service - SCAR, Generalitat de Catalunya, Barcelona (Spain)

2015-07-01

Presentation the Equipment for the Continuous Measurement and Identification of Gamma Radioactivity on Aerosols developed by the Nuclear Engineering Research Group (NERG) from the Technical University of Catalonia (UPC) and the Raditel Company. The device is based on a fixed filter of glass fiber (100% borosilicate), this allows determine the concentration of activity of gamma emitters on aerosols in air. A specifically developed Spectrometry Analysis System has been developed. The analysis of the spectra allows the identification of the emitters and determine the concentration of activity. Nowadays four Stations with this equipment are operating on the Environmental Radiological Surveillance Network of the Catalonian Generalitat (Spain): two near the Asco and Vandellos Nuclear Power Plants in the province of Tarragona and one in the city of Barcelona. Soon a fourth monitor will be incorporated at Roses (province of Girona) and a fifth in Puigcerda (province of Barcelona). We present measurements and analysis of the evolution of the emitters identified on different stations of the Network. (authors)

Identification and summary characterization of materials potentially requiring vitrification: Background information

International Nuclear Information System (INIS)

Croff, A.G.

1996-01-01

This document contains background information for the Workshop in general and the presentation entitled 'Identification and Summary Characterization of Materials Potentially Requiring Vitrification' that was given during the first morning of the workshop. summary characteristics of 9 categories of US materials having some potential to be vitrified are given. This is followed by a 1-2 page elaborations for each of these 9 categories. References to more detailed information are included

Environmental Radioactivity. Chapter 4

International Nuclear Information System (INIS)

Muhamat Omar; Ismail Sulaiman; Zalina Laili

2015-01-01

This chapter explains several things which consist radioactivity measurements, regular and high background radioactivity, radioactive contaminated soil and radioactivity in fertilizers, rocks, building materials, food, water, environments, sediments, flora and fauna. Besides, the natural radioactive gas concentration of radon and toron in the environment also been discussed specifically in this chapter.

On-orbit real-time robust cooperative target identification in complex background

Directory of Open Access Journals (Sweden)

Wen Zhuoman

2015-10-01

Full Text Available Cooperative target identification is the prerequisite for the relative position and orientation measurement between the space robot arm and the to-be-arrested object. We propose an on-orbit real-time robust algorithm for cooperative target identification in complex background using the features of circle and lines. It first extracts only the interested edges in the target image using an adaptive threshold and refines them to about single-pixel-width with improved non-maximum suppression. Adapting a novel tracking approach, edge segments changing smoothly in tangential directions are obtained. With a small amount of calculation, large numbers of invalid edges are removed. From the few remained edges, valid circular arcs are extracted and reassembled to obtain circles according to a reliable criterion. Finally, the target is identified if there are certain numbers of straight lines whose relative positions with the circle match the known target pattern. Experiments demonstrate that the proposed algorithm accurately identifies the cooperative target within the range of 0.3–1.5 m under complex background at the speed of 8 frames per second, regardless of lighting condition and target attitude. The proposed algorithm is very suitable for real-time visual measurement of space robot arm because of its robustness and small memory requirement.

Considerations concerning the secure transport of radioactive materials in Romania

International Nuclear Information System (INIS)

Vieru, Gheorghe

2002-01-01

As UNO member and founding member of the IAEA, Romania has implemented national regulations concerning the transport of radioactive materials in complete safety, complying with recommendations by IAEA and other international organizations. Accordingly, the National Commission for Nuclear Activities Control, CNCAN, issued the Directive no. 374/October 2001 which provides the rules for secure radioactive material transport in Romania on roads, rail ways, sea/fluvial and air ways. The paper presents the main sources of producing radioactive materials focussing the following: mining of natural uranium ore, nuclear fuel fabrication plants, nuclear power plants operation, nuclear research reactors, industrial use of radioactive sources (as gamma radiography), use of radioisotope in scientific, educational or medical units. The paper pays attention to the special routes and containers adopted for most secure transport of radioactive waste. Finally, one presents specific issues relating to identification and evaluation of the risk factors occurring at the transport of radioactive waste, as well as the potential radiological consequences upon population and environment. Estimated are the collective risk doses for different categories of populations from areas adjacent to the routes of radioactive materials transportation. It is stressed that the annual collective dose which the population is exposed to in case of accident is comparable with the dose from the natural (cosmic radiation background)

Radioactivity observed in scintillation counters during the HEAO-1 mission

Science.gov (United States)

Gruber, D. E.; Jung, G. V.; Matteson, J. L.

1989-01-01

Results are reported from an analysis of radioactivity induced in the NaI medium-energy detector of the hard X-ray and low-energy gamma-ray experiment during the HEAO-1 satellite mission (1977-1978). Consideration is given to the instrument characteristics, the origin and variability of background, and the separation of cosmic-ray activity from the internal activity due to South Atlantic Anomaly trapped protons. Energy spectra and tables listing the nuclide identifications are provided.

Re-Identification of the Many-World Background of Special Relativity as Four-World Background. Part II

Directory of Open Access Journals (Sweden)

Adekugbe A. O. J.

2011-01-01

Full Text Available The re-identification of the many-world background of the special theory of relativity (SR as four-world background in the first part of this paper (instead of two-wold background isolated in the initial papers, is concluded in this second part. The flat two-dimensional intrinsic spacetime, which underlies the flat four-dimensional spacetime in each universe, introduced as ansatz in the initial paper, is derived formally within the four-world picture. The identical magnitudes of masses, identical sizes and identical shapes of the four members of every quartet of symmetry-partner particles or objects in the four universes are shown. The immutability of Lorentz invariance on flat spacetime of SR in each of the four universes is shown to arise as a consequence of the perfect symmetry of relative motion at all times among the four members of every quartet of symmetry-partner particles and objects in the four universes. The perfect symmetry of relative motions at all times, coupled with the identical magnitudes of masses, identical sizes and identical shapes, of the members of every quartet of symmetry-partner particles and objects in the four universes, guarantee perfect symmetry of state among the universes.

Location and identification of radioactive waste in Massachusetts Bay

International Nuclear Information System (INIS)

Colton, D.P.; Louft, H.L.

1993-01-01

The accurate location and identification of hazardous waste materials dumped in the world's oceans are becoming an increasing concern. For years, the oceans have been viewed as a convenient and economical place to dispose of all types of waste. In all but a few cases, major dump sites have been closed leaving behind years of accumulated debris. The extent of past environmental damage, the possibility of continued environmental damage, and the possibility of hazardous substances reaching the human food chain need to be carefully investigated. This paper reports an attempt to accurately locate and identify the radioactive component of the waste material. The Department of Energy's Remote Sensing Laboratory (RSL), in support of the US Environmental Protection Agency (EPA), provided the precision navigation system and prototype underwater radiological monitoring equipment that were used during this project. The paper also describes the equipment used, presents the data obtained, and discusses future equipment development

Identification and age estimation of blood stains on colored backgrounds by near infrared spectroscopy

NARCIS (Netherlands)

Edelman, Gerda; Manti, Vicky; van Ruth, Saskia M.; van Leeuwen, Ton; Aalders, Maurice

2012-01-01

Non-destructive identification and subsequent age estimation of blood stains are significant steps in forensic casework. The latter can provide important information on the temporal aspects of a crime. As previously shown, visible spectroscopy of blood stains on white backgrounds can successfully be

Implementation of an Imaging Spectrometer for Localization and Identification of Radioactive Sources

International Nuclear Information System (INIS)

Hermine, Lemaire; Carrel, Frederick; Gmar, Mehdi; Menesguen Yves; Normand, Stephane; Schoepff, Vincent; Abou-Khalil, Roger; Amgarou, Khalil; Menaa, Nabil; Tebug, Timi; Angelique, Jean-Claude; Bonnet, Florent; De-Toro, Daniel; Giarmana, Olivier; Patoz, Audrey; Talent, Philippe

2013-06-01

Spatial localization of radioactive sources is currently a main issue interesting nuclear industry as well as homeland security applications, and can be achieved using gamma cameras. For several years, CEA LIST has been designing a new system, called GAMPIX, with improved sensitivity, portability and ease of use. The main remaining limitation is the lack of spectrometric information, preventing radioactive materials identification. This article describes the development of an imaging spectrometer based on the GAMPIX technology. Experimental tests have been carried out according to both spectrometric methods enabled by the pixelated Timepix readout chip used in the GAMPIX gamma camera. The first method is based on the size of the impacts produced by a gamma-ray energy deposition in the detection matrix. The second one uses the Time over Threshold (ToT) mode of the Timepix chip and deals with time spent by pulses generated by charge preamplifiers over a user-specified threshold. Both energy resolution and sensitivity studies proved the superiority of the ToT approach that will consequently be further explored. Energy calibration, tests of several pixel sizes and use of the Medipix3 readout chip are tracks to improve performances of the newly implemented imaging spectrometer. (authors)

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

Disposal options for disused radioactive sources

International Nuclear Information System (INIS)

2005-01-01

This report presents a review of relevant information on the various technical factors and issues, as well as approaches and relevant technologies, leading to the identification of potential disposal options for disused radioactive sources. The report attempts to provide a logical 'road map' for the disposal of disused radioactive sources, taking into consideration the high degree of variability in the radiological properties of such types of radioactive waste. The use of borehole or shaft type repositories is highlighted as a potential disposal option, particularly for those countries that have limited resources and are looking for a simple, safe and cost effective solution for the disposal of their radioactive source inventories. It offers information about usage and characteristics of radioactive sources, disposal considerations, identification and screening of disposal options as well as waste packaging and acceptance criteria for disposal. The information provided in the report could be adapted or adopted to identify and develop specific disposal options suitable for the type and inventory of radioactive sources kept in storage in a given Member State

Instrumental and atmospheric background lines observed by the SMM gamma-ray spectrometer

Science.gov (United States)

Share, G. H.; Kinzer, R. L.; Strickman, M. S.; Letaw, J. R.; Chupp, E. L.

1989-01-01

Preliminary identifications of instrumental and atmospheric background lines detected by the gamma-ray spectrometer on NASA's Solar Maximum Mission satellite (SMM) are presented. The long-term and stable operation of this experiment has provided data of high quality for use in this analysis. Methods are described for identifying radioactive isotopes which use their different decay times. Temporal evolution of the features are revealed by spectral comparisons, subtractions, and fits. An understanding of these temporal variations has enabled the data to be used for detecting celestial gamma-ray sources.

Radioactivity in the environment

International Nuclear Information System (INIS)

Costello, J.M.

1983-01-01

Radioactivity is a natural phenomenon. Out of 1700 known isotopes of 104 chemical elements, only about 16 per cent are stable. Seventy-three radioactive isotopes of 39 elements occur naturally in the terrestrial environment. The significance of environmental radioactivity lies in the contribution to the annual exposure of the general population to ionising radiation. This exposure results largely from natural sources of radioactivity and radiation together with applications of radiation in medicine. Minor contributions are from nuclear weapons tests, nuclear power production and the nuclear fuel cycle, and consumer products including luminous clocks and watches, television receivers and smoke detectors. The natural background radiation level varies substantially with altitude and geographic location. Although no satisfactory evidence is available that natural variations in background radiation levels are detrimental to humans, upper limits of risk have been estimated for possible somatic and genetic effects from these levels of radiation. Contributory sources of and variability in the radiation background are reviewed and the relation between effective dose equivalent and associated detriment outlined. The risk from exposure to an average level of background radiation is compared with risks from other human activities

Methods for Characterisation of unknown Suspect Radioactive Samples

International Nuclear Information System (INIS)

Sahagia, M.; Grigorescu, E.L.; Luca, A.; Razdolescu, A.C.; Ivan, C.

2001-01-01

Full text: The paper presents various identification and measurement methods, used for the expertise of a wide variety of suspect radioactive materials, whose circulation was not legally stated. The main types of examined samples were: radioactive sources, illegally trafficked; suspect radioactive materials or radioactively contaminated devices; uranium tablets; fire detectors containing 241 Am sources; osmium samples containing radioactive 185 Os or enriched 187 Os. The types of analyses and determination methods were as follows: the chemical composition was determined by using identification reagents or by neutron activation analysis; the radionuclide composition was determined by using gamma-ray spectrometry; the activity and particle emission rates were determined by using calibrated radiometric equipment; the absorbed dose rate at the wall of all types of containers and samples was determined by using calibrated dose ratemeters. The radiation exposure risk for population, due to these radioactive materials, was evaluated for every case. (author)

Technically enhanced naturally occurring radioactive materials; identification, characterization and treatment

International Nuclear Information System (INIS)

Aly, H.F.

2001-01-01

Radioactive materials (TENORM) is produced in a relatively large amount with relatively small radioactivity, however in many instances the radioactivity levels exceeds that permissible. In this presentation, the different industries where enhanced levels of natural radioactivity is identified and characterized will be given. The different approaches for treatment of this enhanced radioactivity will be addressed. Finally, our research and development activities in characterization and treatment of TENORM produced from the oil fields in Egypt will be presented. (authors)

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)

Background studies: climatic and geomorphological aspects of the evolution of shallow land burial sites for radioactive waste disposal

International Nuclear Information System (INIS)

1988-04-01

This report presents the results of a programme of background research into some climatic and geomorphological aspects of the evolution of shallow land disposal environments for radioactive wastes in Britain. The work has supported development of the TIME2 simulation code. Modelling approaches are presented and discussed, along with supporting data, for climatic change, ice sheet growth and decay, groundwater effects and denudation. The potential effects of periglacial processes on a repository are also briefly discussed. (author)

Identification of radioactive sources and devices. Reference manual

International Nuclear Information System (INIS)

2007-01-01

This publication is intended to be a basic guide and not a comprehensive tool kit to identify and provide detailed emergency handling instructions for radioactive sources, devices and transport containers. In addition, this publication helps to identify sources and highlight the risks they present, and provides information on appropriate action. It is a small but significant step in the international community's continuing efforts to strengthen control of radioactive sources and nuclear material, increase safety and security, and thereby make the benefits of radioactive sources ever more broadly accessible. This publication was partly funded through the Nuclear Security Fund established under the Nuclear Security Plan

Radioactivity in the groundwater of a high background radiation area.

Science.gov (United States)

Shabana, E I; Kinsara, A A

2014-11-01

Natural radioactivity was measured in groundwater samples collected from 37 wells scattered in an inhabited area of high natural background radiation, in a purpose of radiation protection. The study area is adjacent to Aja heights of granitic composition in Hail province, Saudi Arabia. Initial screening for gross α and gross β activities showed levels exceeded the national regulation limits set out for gross α and gross β activities in drinking water. The gross α activity ranged from 0.17 to 5.41 Bq L(-)(1) with an average value of 2.15 Bq L(-)(1), whereas gross β activity ranged from 0.48 to 5.16 Bq L(-)(1), with an average value of 2.60 Bq L(-)(1). The detail analyses indicated that the groundwater of this province is contaminated with uranium and radium ((226)Ra and (228)Ra). The average activity concentrations of (238)U, (234)U, (226)Ra and (228)Ra were 0.40, 0.77, 0.29 and 0.46 Bq L(-)(1), respectively. The higher uranium content was found in the samples of granitic aquifers, whereas the higher radium content was found in the samples of sandstone aquifers. Based on the obtained results, mechanism of leaching of the predominant radionuclides has been discussed in detail. Copyright © 2014 Elsevier Ltd. All rights reserved.

The effect of background and illumination on color identification of real, 3D objects.

Science.gov (United States)

Allred, Sarah R; Olkkonen, Maria

2013-01-01

For the surface reflectance of an object to be a useful cue to object identity, judgments of its color should remain stable across changes in the object's environment. In 2D scenes, there is general consensus that color judgments are much more stable across illumination changes than background changes. Here we investigate whether these findings generalize to real 3D objects. Observers made color matches to cubes as we independently varied both the illumination impinging on the cube and the 3D background of the cube. As in 2D scenes, we found relatively high but imperfect stability of color judgments under an illuminant shift. In contrast to 2D scenes, we found that background had little effect on average color judgments. In addition, variability of color judgments was increased by an illuminant shift and decreased by embedding the cube within a background. Taken together, these results suggest that in real 3D scenes with ample cues to object segregation, the addition of a background may improve stability of color identification.

The effect of background and illumination on color identification of real, 3D objects

Directory of Open Access Journals (Sweden)

Sarah Ray Allred

2013-11-01

Full Text Available For the surface reflectance of an object to be a useful cue to object identity, judgments of its color should remain stable across changes in the object's environment. In 2D scenes, there is general consensus that color judgments are much more stable across illumination changes than background changes. Here we investigate whether these findings generalize to real 3D objects. Observers made color matches to cubes as we independently varied both the illumination impinging on the cube and the 3D background of the cube. As in 2D scenes, we found relatively high but imperfect stability of color judgments under an illuminant shift. In contrast to 2D scenes, we found that background had little effect on average color judgments. In addition, variability of color judgments was increased by an illuminant shift and decreased by embedding the cube within a background. Taken together, these results suggest that in real 3D scenes with ample cues to object segregation, the addition of a background may improve stability of color identification.

Identification of Radioactive Pilot-Plant test requirements

Energy Technology Data Exchange (ETDEWEB)

Powell, W.J.; Riebling, E.F.

1995-05-09

Radioactive Pilot-Plant testing needs and alternatives are evaluated for enhanced Sludge Washing and High and Low-Level Vitrification efforts. Also investigated was instrument and equipment testing needs associated with the vitrification and retrieval process. The scope of this document is to record the existing March 1994 letter report for future use. A structured Kepner-Trego{trademark} decision analysis process was used to assist analysis of the testing needs. This analysis provided various combinations of laboratory and radioactive (hot) and cold pilot testing options associated with the above need areas. Recommendations for testing requirements were made.

Identification of Radioactive Pilot-Plant test requirements

International Nuclear Information System (INIS)

Powell, W.J.; Riebling, E.F.

1995-01-01

Radioactive Pilot-Plant testing needs and alternatives are evaluated for enhanced Sludge Washing and High and Low-Level Vitrification efforts. Also investigated was instrument and equipment testing needs associated with the vitrification and retrieval process. The scope of this document is to record the existing March 1994 letter report for future use. A structured Kepner-Trego trademark decision analysis process was used to assist analysis of the testing needs. This analysis provided various combinations of laboratory and radioactive (hot) and cold pilot testing options associated with the above need areas. Recommendations for testing requirements were made

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)

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.

Management of radioactive wastes

International Nuclear Information System (INIS)

Hendee, W.R.

1984-01-01

The disposal of radioactive wastes is perhaps the most controversial and least understood aspect of the use of nuclear materials in generating electrical power, the investigation of biochemical processes through tracer kinetics, and the diagnosis and treatment of disease. In the siting of nuclear power facilities, the disposal of radioactive wastes is invariably posed as the ultimate unanswerable question. In the fall of 1979, biochemical and physiologic research employing radioactive tracers was threatened with a slowdown resulting from temporary closure of sites for disposal of low-level radioactive wastes (LLW). Radioactive pharmaceuticals used extensively for diagnosis and treatment of human disease have increased dramatically in price, partly as a result of the escalating cost of disposing of radioactive wastes created during production of the labeled pharmaceuticals. These problems have resulted in identification of the disposal of LLW as the most pressing issue in the entire scheme of management of hazardous wastes. How this issue as well as the separate issue of disposal of high-level radioactive wastes (HLW) are being addressed at both national and state levels is the subject of this chapter

Technical testing of portable isotope identification instruments

International Nuclear Information System (INIS)

Smith, D.E.

2001-01-01

radioactive shipment. Response summaries in the form of a pass/fail listing for isotope identification for each of the three classes of gamma emitters (SNM, medical, and industrial) were recorded. Each instrument was then tested for response to the neutron source, Cf-252, a spontaneous fission isotope. Each instrument's ability to identify several pairs of isotopes was determined. This test was intended to verify if the instrument could detect SNM when accompanied by a masking isotope. Finally, each instrument's dose rate response to different energy gamma emitters was measured. One section of this test was conducted at a very low exposure rate, 10 microR/hr above background, and the second section conducted at 2 mR/hr above background. The latter dose rate represented the expected maximum exposure rate for a properly packaged medical isotope shipment. A third dose rate, 200mR/hr, was also used. Tests also were conducted to determine the instrument's display visibility, audio alarms, and operational characteristics in electromagnetic fields and high humidity conditions. (author)

A unique automation platform for measuring low level radioactivity in metabolite identification studies.

Directory of Open Access Journals (Sweden)

Joel Krauser

Full Text Available Generation and interpretation of biotransformation data on drugs, i.e. identification of physiologically relevant metabolites, defining metabolic pathways and elucidation of metabolite structures, have become increasingly important to the drug development process. Profiling using (14C or (3H radiolabel is defined as the chromatographic separation and quantification of drug-related material in a given biological sample derived from an in vitro, preclinical in vivo or clinical study. Metabolite profiling is a very time intensive activity, particularly for preclinical in vivo or clinical studies which have defined limitations on radiation burden and exposure levels. A clear gap exists for certain studies which do not require specialized high volume automation technologies, yet these studies would still clearly benefit from automation. Use of radiolabeled compounds in preclinical and clinical ADME studies, specifically for metabolite profiling and identification are a very good example. The current lack of automation for measuring low level radioactivity in metabolite profiling requires substantial capacity, personal attention and resources from laboratory scientists. To help address these challenges and improve efficiency, we have innovated, developed and implemented a novel and flexible automation platform that integrates a robotic plate handling platform, HPLC or UPLC system, mass spectrometer and an automated fraction collector.

A Unique Automation Platform for Measuring Low Level Radioactivity in Metabolite Identification Studies

Science.gov (United States)

Krauser, Joel; Walles, Markus; Wolf, Thierry; Graf, Daniel; Swart, Piet

2012-01-01

Generation and interpretation of biotransformation data on drugs, i.e. identification of physiologically relevant metabolites, defining metabolic pathways and elucidation of metabolite structures, have become increasingly important to the drug development process. Profiling using 14C or 3H radiolabel is defined as the chromatographic separation and quantification of drug-related material in a given biological sample derived from an in vitro, preclinical in vivo or clinical study. Metabolite profiling is a very time intensive activity, particularly for preclinical in vivo or clinical studies which have defined limitations on radiation burden and exposure levels. A clear gap exists for certain studies which do not require specialized high volume automation technologies, yet these studies would still clearly benefit from automation. Use of radiolabeled compounds in preclinical and clinical ADME studies, specifically for metabolite profiling and identification are a very good example. The current lack of automation for measuring low level radioactivity in metabolite profiling requires substantial capacity, personal attention and resources from laboratory scientists. To help address these challenges and improve efficiency, we have innovated, developed and implemented a novel and flexible automation platform that integrates a robotic plate handling platform, HPLC or UPLC system, mass spectrometer and an automated fraction collector. PMID:22723932

Radiological emergencies due to postulated events of melted radioactive material mixed in steel reaching public domain

International Nuclear Information System (INIS)

Meena, T.R.; Anoj Kumar; Patra, R.P.; Vikas; Patil, S.S.; Chatterjee, M.K.; Sharma, Ranjit; Murali, S.

2014-01-01

National level response mechanism is developed at emergency response centres of DAE (DAE-ERCs) at 22 different locations spread all over the country and National Disaster Response Forces with National Disaster Management Authority (NDMA). ERCs are equipped with radiation monitors, radionuclide identifinders, Personnel Radiation Dosimeters (PRD) with monitoring capabilities of the order of tens of nGy/h (μR/hr) above the radiation background at any suspected locations. Even if small amounts of radioactive material is smuggled and brought in some other form into public domain, ERCs are capable to detect, identify and segregate the radioactive material from any inactive scrap. DAE-ERCs have demonstrated their capability in source search, detection, identification and recovery during the radiological emergency at Mayapuri, New Delhi

Radiological emergencies due to postulated events of melted radioactive material mixed in steel reaching public domain

Energy Technology Data Exchange (ETDEWEB)

Meena, T. R.; Kumar, Anoj; Patra, R. P.; Vikas,; Patil, S. S.; Chatterjee, M. K.; Sharma, Ranjit; Murali, S., E-mail: tejram@barc.gov.in [Radiation Safety Systems Division, Bhabha Atomic Research Centre, Mumbai (India)

2014-07-01

National level response mechanism is developed at emergency response centres of DAE (DAE-ERCs) at 22 different locations spread all over the country and National Disaster Response Forces with National Disaster Management Authority (NDMA). ERCs are equipped with radiation monitors, radionuclide identifinders, Personnel Radiation Dosimeters (PRD) with monitoring capabilities of the order of tens of nGy/h (μR/hr) above the radiation background at any suspected locations. Even if small amounts of radioactive material is smuggled and brought in some other form into public domain, ERCs are capable to detect, identify and segregate the radioactive material from any inactive scrap. DAE-ERCs have demonstrated their capability in source search, detection, identification and recovery during the radiological emergency at Mayapuri, New Delhi.

Continuous Tracking of RFID Tagged Radioactive Sources

International Nuclear Information System (INIS)

Broide, A.; Marcus, E.; Gabay, Y.; Miron, E.; Seif, R.; Wengrowicz, U.; Kadmon, Y.; Tirosh, D.

2008-01-01

The prevention of radiation hazards due to radioisotopes is one of the concerns of the Atomic Energy Agency (IAEA). In a series of international conferences held in the last five years) this issue was discussed thoroughly. One of the conclusions was that strict management of radioactive sources is essential. The management of radioactive sources would help to prevent transference of radioactive materials to unauthorized personal. For this purpose, states should make a concerted effort to follow the principles of the Code of Conduct on the Security of Radioactive Sources(2). In this context, the identification of roles and responsibilities of governments, licensees and international organizations is vital(3). The referred activities are primarily related to control over radioactive sources and enhance the tracking ability of radiation sources . In this paper, a proposed Radioactive Sources Tracking System is presented. This system facilitates real time monitoring capability of fixed and mobile radiation sources. The system provides the location of the source and indication whether the source is inside or outside the shielding container. The information about the sources location and condition can be used to coordinate a fast response in case of any attempt to steal or tamper with a source. These goals are achieved by using GPS (Global Positioning System), RFID (Radio Frequency Identification) and control and management software

Radioactive air sampling methods

CERN Document Server

Maiello, Mark L

2010-01-01

Although the field of radioactive air sampling has matured and evolved over decades, it has lacked a single resource that assimilates technical and background information on its many facets. Edited by experts and with contributions from top practitioners and researchers, Radioactive Air Sampling Methods provides authoritative guidance on measuring airborne radioactivity from industrial, research, and nuclear power operations, as well as naturally occuring radioactivity in the environment. Designed for industrial hygienists, air quality experts, and heath physicists, the book delves into the applied research advancing and transforming practice with improvements to measurement equipment, human dose modeling of inhaled radioactivity, and radiation safety regulations. To present a wide picture of the field, it covers the international and national standards that guide the quality of air sampling measurements and equipment. It discusses emergency response issues, including radioactive fallout and the assets used ...

LRT 2006: 2. topical workshop in low radioactivity techniques

International Nuclear Information System (INIS)

Cushman, P.; Piquemal, F.; Ford, R.; Yakushev, E.; Pandola, L.; Franco, D.; Bellini, F.; Hubert, Ph.; Laubenstein, M.; Abt, I.; Bongrand, M.; Schnee, R.; Dusan, B.; Chen, M.; Piquemal, F.; Nachab, A.; Zuzel, G.; Simgen, H.; Navick, X.F.; Pedretti, M.; Wojcik, M.; Sekiya, H.; Kim, Y.; Kishimoto, T.; Dawson, J.; Borjabad, S.; Perrot, F.; Gurriaran, R.; Nikolayko, A.; Hubert, Ph.

2006-01-01

This second topical workshop in low radioactivity techniques is intended to bring together experts in the field of low background techniques, especially applied to dark matter experiments, double beta decay experiments and neutrino detection in underground laboratories. This workshop has been organized into 7 sessions: 1) underground facilities (where a worldwide review is made), 2) neutron and muon induced background, isotope production, 3) low background counting techniques and low background detectors, 4) techniques for radon reduction, purified noble gases and liquid scintillator purification, 5) low levels on Pb-Bi-Po 210 and surface background, 6) low radioactivity detector components and material purification, and 7) low radioactive techniques in other applications (particularly to check the geographical origin of food-products or to date wine. This document is made up of the slides of the presentations

LRT 2006: 2. topical workshop in low radioactivity techniques

Energy Technology Data Exchange (ETDEWEB)

Cushman, P; Piquemal, F; Ford, R; Yakushev, E; Pandola, L; Franco, D; Bellini, F; Hubert, Ph; Laubenstein, M; Abt, I; Bongrand, M; Schnee, R; Dusan, B; Chen, M; Piquemal, F; Nachab, A; Zuzel, G; Simgen, H; Navick, X F; Pedretti, M; Wojcik, M; Sekiya, H; Kim, Y; Kishimoto, T; Dawson, J; Borjabad, S; Perrot, F; Gurriaran, R; Nikolayko, A; Hubert, Ph

2006-07-01

This second topical workshop in low radioactivity techniques is intended to bring together experts in the field of low background techniques, especially applied to dark matter experiments, double beta decay experiments and neutrino detection in underground laboratories. This workshop has been organized into 7 sessions: 1) underground facilities (where a worldwide review is made), 2) neutron and muon induced background, isotope production, 3) low background counting techniques and low background detectors, 4) techniques for radon reduction, purified noble gases and liquid scintillator purification, 5) low levels on Pb-Bi-Po{sup 210} and surface background, 6) low radioactivity detector components and material purification, and 7) low radioactive techniques in other applications (particularly to check the geographical origin of food-products or to date wine. This document is made up of the slides of the presentations.

Radioactivity Measurements on Glazed Ceramic Surfaces

OpenAIRE

Hobbs, Thomas G.

2000-01-01

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

Having your radioactive objects identified and collected

International Nuclear Information System (INIS)

2012-12-01

This brochure explains the risks linked with some ancient radioactive objects of domestic use (like radium products of medical use), how to identify them and to have them collected by the French national agency of radioactive wastes (Andra) for further processing. Some advice are given regarding the identification of the objects, their relative hazardousness and the precautions to take for their handling

Investigation of radioactivity-induced backgrounds in EXO-200

Energy Technology Data Exchange (ETDEWEB)

Albert, J. B.; Auty, D. J.; Barbeau, P. S.; Beck, D.; Belov, V.; Benitez-Medina, C.; Breidenbach, M.; Brunner, T.; Burenkov, A.; Cao, G. F.; Chambers, C.; Cleveland, B.; Coon, M.; Craycraft, A.; Daniels, T.; Danilov, M.; Daugherty, S. J.; Davis, C. G.; Davis, J.; Delaquis, S.; Der Mesrobian-Kabakian, A.; DeVoe, R.; Didberidze, T.; Dolgolenko, A.; Dolinski, M. J.; Dunford, M.; Fairbank, W.; Farine, J.; Feldmeier, W.; Fierlinger, P.; Fudenberg, D.; Giroux, G.; Gornea, R.; Graham, K.; Gratta, G.; Hall, C.; Herrin, S.; Hughes, M.; Jewell, M. J.; Jiang, X. S.; Johnson, A.; Johnson, T. N.; Johnston, S.; Karelin, A.; Kaufman, L. J.; Killick, R.; Koffas, T.; Kravitz, S.; Kuchenkov, A.; Kumar, K. S.; Leonard, D. S.; Licciardi, C.; Lin, Y. H.; Ling, J.; MacLellan, R.; Marino, M. G.; Mong, B.; Moore, D.; Nelson, R.; Odian, A.; Ostrovskiy, I.; Piepke, A.; Pocar, A.; Prescott, C. Y.; Rivas, A.; Rowson, P. C.; Russell, J. J.; Schubert, A.; Sinclair, D.; Smith, E.; Stekhanov, V.; Tarka, M.; Tolba, T.; Tsang, R.; Twelker, K.; Vuilleumier, J. -L.; Waite, A.; Walton, J.; Walton, T.; Weber, M.; Wen, L. J.; Wichoski, U.; Wood, J.; Yang, L.; Yen, Y. -R.; Zeldovich, O. Ya.

2015-07-15

The search for neutrinoless double-beta decay ( 0 ν β β ) requires extremely low background and a good understanding of their sources and their influence on the rate in the region of parameter space relevant to the 0 ν β β signal. We report on studies of various β and γ backgrounds in the liquid-xenon-based EXO- 200 0 ν β β experiment. With this work we try to better understand the location and strength of specific background sources and compare the conclusions to radioassay results taken before and during detector construction. Finally, we discuss the implications of these studies for EXO-200 as well as for the next-generation, tonne-scale nEXO detector.

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;

Radioactivity in fossils at the Hagerman Fossil Beds National Monument.

Science.gov (United States)

Farmer, C Neal; Kathren, Ronald L; Christensen, Craig

2008-08-01

Since 1996, higher than background levels of naturally occurring radioactivity have been documented in both fossil and mineral deposits at Hagerman Fossil Beds National Monument in south-central Idaho. Radioactive fossil sites occur primarily within an elevation zone of 900-1000 m above sea level and are most commonly found associated with ancient river channels filled with sand. Fossils found in clay rich deposits do not exhibit discernable levels of radioactivity. Out of 300 randomly selected fossils, approximately three-fourths exhibit detectable levels of natural radioactivity ranging from 1 to 2 orders of magnitude above ambient background levels when surveyed with a portable hand held Geiger-Muller survey instrument. Mineral deposits in geologic strata also show above ambient background levels of radioactivity. Radiochemical lab analysis has documented the presence of numerous natural radioactive isotopes. It is postulated that ancient groundwater transported radioactive elements through sand bodies containing fossils which precipitated out of solution during the fossilization process. The elevated levels of natural radioactivity in fossils may require special precautions to ensure that exposures to personnel from stored or displayed items are kept as low as reasonably achievable (ALARA).

Radioactive substances in the Danish building materials

International Nuclear Information System (INIS)

Ulbak, K.

1986-01-01

Building materials as any other materials of natural occurrence contain small concentrations of natural radioactive elements. This natural radioactivity affects people inside buildings. This publiccation refers measurements of the Danish building materials, and radiation doses originating from this source affecting the Danish population are related to the other components of background radioactivity. (EG)

DEPO-related to Radioactive Sources.

Energy Technology Data Exchange (ETDEWEB)

Miller, James Christopher [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-02-24

Design and Evaluation Process Outline (DEPO) is discussed as it pertains to protection of radioactive sources. The bulk of the report describes features of various kinds of detection systems, and follows this with systems for entry control and personnel identification.

The regulatory action in the problem of radioactive sources processed as scrap

International Nuclear Information System (INIS)

Truppa, Walter Adrian; Cateriano, Miguel Angel

2005-01-01

The loss of control of a radioactive source can result in a radiological emergency, especially if that source is treated as scrap. This paper presents a case registered in Argentina about discovery of a radioactive source of Kr-85, 9.25 GBq, used in a computer for industrial measurement of thickness. The radioactive source, without registration or identification, was registered by a portal for detection of radioactive material in the middle of the scrap that entered daily in the oven of a important steel company. From there, the Nuclear Regulatory Authority (RNA) conducted an investigation to determine the origin of the radioactive source, and in parallel made, in the laboratories of measurement, identification of radioactive material inside the source. This led to a company in financial and judicial bankruptcy, which had not notified the RNA about this situation, and also possessed, according to records, other eleven sources with similar characteristics. Finally the actions and regulatory effort allowed the localization of all the radioactive sources of this company, and its storage and deposit in an authorised repository

The Identification of Factors Influencing College Students' Attitudes toward Radioactivity.

Science.gov (United States)

Crater, Harold L., Jr.

The two basic questions considered in this study were: (1) What attitudes do college students hold toward radioactivity? and (2) What are some characteristics associated with the college students who hold the more favorable attitudes toward radioactivity? The sample studied included 1,205 mostly undergraduate students at the University of Texas at…

Radioactive waste integrated management system

International Nuclear Information System (INIS)

Song, D. Y.; Choi, S. S.; Han, B. S.

2003-01-01

In this paper, we present an integrated management system for radioactive waste, which can keep watch on the whole transporting process of each drum from nuclear power plant temporary storage house to radioactive waste storage house remotely. Our approach use RFID(Radio Frequency Identification) system, which can recognize the data information without touch, GSP system, which can calculate the current position precisely using the accurate time and distance measured from satellites, and the spread spectrum technology CDMA, which is widely used in the area of mobile communication

Radioactive waste integrated management system

Energy Technology Data Exchange (ETDEWEB)

Song, D Y; Choi, S S; Han, B S [Atomic Creative Technology, Taejon (Korea, Republic of)

2003-10-01

In this paper, we present an integrated management system for radioactive waste, which can keep watch on the whole transporting process of each drum from nuclear power plant temporary storage house to radioactive waste storage house remotely. Our approach use RFID(Radio Frequency Identification) system, which can recognize the data information without touch, GSP system, which can calculate the current position precisely using the accurate time and distance measured from satellites, and the spread spectrum technology CDMA, which is widely used in the area of mobile communication.

Radioactivity in the Romanian sector of the Black Sea

International Nuclear Information System (INIS)

Osvath, I.; Dovlete, C.; Bologa, A.

2004-01-01

The study of marine radioactivity in Romanian waters has been performed jointly by the Romanian marine research institute (RMRI) and the environmental radioactivity research laboratory of the Institute of meteorology and hydrology, presently the environmental radioactivity laboratory (ERL) of the Institute of environmental research and engineering, along two directions: 1. Marine radioactivity monitoring, 2. Studied on the distribution of radionuclides among the components of the marine environment and its time evolution. Assessment of distribution coefficients and concentration factors for radionuclides in the marine environment. Identification and study of the bioindicator species

Radioactivity of the JINR site environment

International Nuclear Information System (INIS)

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

1977-01-01

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

Collecting and identifying the radioactive waste

International Nuclear Information System (INIS)

Dogaru, C. GH.

2001-01-01

The procedure 'Collecting and identifying the radioactive waste' applied by the Radioactive Waste Management Department, STDR, complies with the requirements of the competent authority concerning the radioactive source management. One of the most important tasks, requiring the application of this procedure, is collecting and identification of 'historical wastes' for which a complete book keeping does not exist from different reasons. The chapter 1 presents the procedure's goal and the chapter 2 defines the applicability field. Chapter 3 enlists the reference documents while the chapter 4 gives the definitions and abbreviations used in the procedure. Chapter 5 defines responsibilities of the operators implied in collecting, identification and characterization of the radioactive wastes, the producers of the radioactive wastes being implied. Chapter 6 gives the preliminary conditions for applying the procedure. Among these, the transport, collecting, processing, storing and characterization costs are implied, as well as the compliance with technical and different other condition. The procedure structure is presented in the chapter 7. In collecting radioactive wastes, two situations are possible: 1- the producer is able to prepare the wastes for transport and to deliver them to STDR; 2 - the wastes are received from the producer by a delegate STDR operator, properly and technically prepared. The producer must demonstrate by documents the origin and possession, analysis bulletins specifying, the radionuclides activity and measurement date, physical state and, in addition, for spent radiation sources, the series/number of the container and producer. In case the producer is not able to display all this information, the wastes are taken into custody by the STDR labs in view of their analysis. A record in writing is completed specifying the transfer of radioactive wastes from the producer to the STDR, a record which is sent to the national authority in charge with the

Guidance on accidents involving radioactivity

International Nuclear Information System (INIS)

1989-01-01

This annex contains advice to Health Authorities on their response to accidents involving radioactivity. The guidance is in six parts:-(1) planning the response required to nuclear accidents overseas, (2) planning the response required to UK nuclear accidents a) emergency plans for nuclear installations b) nuclear powered satellites, (3) the handling of casualties contaminated with radioactive substances, (4) background information for dealing with queries from the public in the event of an accident, (5) the national arrangements for incident involving radioactivity (NAIR), (6) administrative arrangements. (author)

Radioisotope identification method for poorly resolved gamma-ray spectrum of nuclear security concern

Energy Technology Data Exchange (ETDEWEB)

Ninh, Giang Nguyen; Phongphaeth, Pengvanich, E-mail: phongphaeth.p@chula.ac.th; Nares, Chankow [Nuclear Engineering Department, Faculty of Engineering, Chulalongkorn University, 254 Phayathai Road, Pathumwan, Bangkok 10330 (Thailand); Hao, Quang Nguyen [Vietnam Atomic Energy Institute, Ministry of Science and Technology, Hanoi (Viet Nam)

2016-01-22

Gamma-ray signal can be used as a fingerprint for radioisotope identification. In the context of radioactive and nuclear materials security at the border control point, the detection task can present a significant challenge due to various constraints such as the limited measurement time, the shielding conditions, and the noise interference. This study proposes a novel method to identify the signal of one or several radioisotopes from a poorly resolved gamma-ray spectrum. In this method, the noise component in the raw spectrum is reduced by the wavelet decomposition approach, and the removal of the continuum background is performed using the baseline determination algorithm. Finally, the identification of radioisotope is completed using the matrix linear regression method. The proposed method has been verified by experiments using the poorly resolved gamma-ray signals from various scenarios including single source, mixing of natural uranium with five of the most common industrial radioactive sources (57Co, 60Co, 133Ba, 137Cs, and 241Am). The preliminary results show that the proposed algorithm is comparable with the commercial method.

Radioisotope identification method for poorly resolved gamma-ray spectrum of nuclear security concern

International Nuclear Information System (INIS)

Ninh, Giang Nguyen; Phongphaeth, Pengvanich; Nares, Chankow; Hao, Quang Nguyen

2016-01-01

Gamma-ray signal can be used as a fingerprint for radioisotope identification. In the context of radioactive and nuclear materials security at the border control point, the detection task can present a significant challenge due to various constraints such as the limited measurement time, the shielding conditions, and the noise interference. This study proposes a novel method to identify the signal of one or several radioisotopes from a poorly resolved gamma-ray spectrum. In this method, the noise component in the raw spectrum is reduced by the wavelet decomposition approach, and the removal of the continuum background is performed using the baseline determination algorithm. Finally, the identification of radioisotope is completed using the matrix linear regression method. The proposed method has been verified by experiments using the poorly resolved gamma-ray signals from various scenarios including single source, mixing of natural uranium with five of the most common industrial radioactive sources (57Co, 60Co, 133Ba, 137Cs, and 241Am). The preliminary results show that the proposed algorithm is comparable with the commercial method

International Catalogue of Sealed Radioactive Sources and Devices

International Nuclear Information System (INIS)

2010-01-01

The international catalogue of sealed radioactive sources and devices have two major objectives. The first objective is to provide vital information for a wide range of individuals and organizations on industrially manufactured radioactive sources and devices. The second objective is to facilitate identification of design specifications based on limited information from orphan sources and devices to allow safe handling of these items.

Dose for background radioactivity in areas with high radioactivity levels in the Pinar del Rio province

International Nuclear Information System (INIS)

Alcaide Orpi, J.; Oliveira Acosta, J.; Valdes Hernadez, G.M.; Leal Ramirez, M.R.; Blanco Jorrin, N.

1998-01-01

The objective the work is to know the areas with high natural radiation doses, for they were used it the data obtained by the studies it has more than enough favorability for radioactive minerals carried out in different regions to the Pinar del Rio province in the 1986 to 1993 years and the doses calculations they were carried out according to the effective methodology

Integrating the radioactive waste management system into other management systems

International Nuclear Information System (INIS)

Silva, Ana Cristina Lourenco da; Nunes Neto, Carlos Antonio

2007-01-01

Radioactive waste management is to be included in the Integrated Management System (IMS) which pursues the continuous improvement of the company's quality, occupational safety and health, and environment protection processes. Radioactive waste management is based on the following aspects: optimization of human and material resources for execution of tasks, including the provision of a radiation protection supervisor to watch over the management of radioactive waste; improved documentation (management plan and procedures); optimization of operational levels for waste classification and release; maintenance of generation records and history through a database that facilitates traceability of information; implementation of radioactive waste segregation at source (source identification, monitoring and decontamination) activities intended to reduce the amount of radioactive waste; licensing of initial storage site for radioactive waste control and storage; employee awareness training on radioactive waste generation; identification and evaluation of emergency situations and response planning; implementation of preventive maintenance program for safety related items; development and application of new, advanced treatment methodologies or systems. These aspects are inherent in the concepts underlying quality management (establishment of administrative controls and performance indicators), environment protection (establishment of operational levels and controls for release), occupational health and safety (establishment of operational controls for exposure in emergency and routine situations and compliance with strict legal requirements and standards). It is noted that optimizing the addressed aspects of a radioactive waste management system further enhances the efficiency of the Integrated Management System for Quality, Environment, and Occupational Safety and Health. (author)

Identification of tetraphenylborate radiolysis products in a simulated feedstock for radioactive waste processing

International Nuclear Information System (INIS)

Eibling, R.E.; Bartlett, M.G.; Carlson, R.E.; Testino, S.A. Jr.; Kunkel, G.J.; Browner, R.F.; Busch, K.L.

1994-01-01

The first step towards immobilization of the soluble radioactive species in borosilicate glass is the addition of sodium tetraphenylborate (TPB) and sodium titanate to the radioactive aqueous solution. Initial studies of the TPB hydrolysis process have found that some component of the radiolysis mixture inactivates the Cu catalyst. The interaction of organic materials with the catalyst, and the subsequent interference with the hydrolysis process, would have presented problems with the use of the vitrification process. Prevention of the catalyst deactivation is obtained by washing the irradiated TPB precipitate in the Late Wash Facility prior to hydrolysis to remove the soluble radiolysis products. Identification of the organic radiolysis products, their distribution in the Late Wash Facility, and their interactions with the Cu catalyst has become an important analytical issue. To further investigate the reaction products of the TPB precipitation process, a simulated feedstock was created from compounds known to be present in the starting materials. This simulated feedstock was precipitated with sodium TPB and then exposed to Co-60 gamma radiation to simulate two years of additional storage time prior to the hydrolysis process. The irradiated product was divided into two parts, the filtered supernatant liquid and the precipitate slurry, which contains the TPB and the solid sodium titanate. Using gas chromatography/mass spectrometry, liquid secondary ion mass spectrometry, inductively coupled plasma/mass spectrometry, ion chromatography, and high performance liquid chromatography, over 50 organic and inorganic species have been identified in the aqueous portion of a simulated feedstock for TPB hydrolysis. The major organic species present are benzene, phenol, benzamide and a variety of substituted phenylphenols. The major inorganic species present are sodium, nitrite, and oxalate ions

SHIPPING OF RADIOACTIVE ITEMS

CERN Multimedia

TIS/RP Group

2001-01-01

The TIS-RP group informs users that shipping of small radioactive items is normally guaranteed within 24 hours from the time the material is handed in at the TIS-RP service. This time is imposed by the necessary procedures (identification of the radionuclides, determination of dose rate and massive objects require a longer procedure and will therefore take longer.

High-Level Radioactive Waste.

Science.gov (United States)

Hayden, Howard C.

1995-01-01

Presents a method to calculate the amount of high-level radioactive waste by taking into consideration the following factors: the fission process that yields the waste, identification of the waste, the energy required to run a 1-GWe plant for one year, and the uranium mass required to produce that energy. Briefly discusses waste disposal and…

Environmental radioactivity in the antarctic station

International Nuclear Information System (INIS)

Gonzalez, S.; Osores, J.; Martinez, J.; Lopez, E.; Jara, R.

1998-01-01

Study about environmental radioactivity in the Peruvian antarctic station Machu Pichu they were carried out during the last three periods to the southern summer. The objective of the project it is to evaluate environmental component in order to elaborate a study it base on the levels background radioactivity and artificial in the antarctic region

Tools for forming strategies for remediation of forests and park areas in northern Europe after radioactive contamination: background and techniques

International Nuclear Information System (INIS)

Hubbard, L.; Rantavaara, A.; Andersson, K.; Roed, J.

2002-01-01

This report compiles background information that can be used in planning appropriate countermeasures for forest and park areas in Denmark, Sweden, Finland and Norway, in case a nuclear accident results in large-scale contamination of forests. The information is formulated to inform the forestry sector and radiation protection experts about the practicality of both forest management techniques and mechanical cleanup methods, for use in their planning of specific strategies that can lead to an optimal use of contaminated forests. Decisions will depend on the site and the actual situation after radioactive deposition to forested areas, but the report provides background information from investigations performed before an accident occurs that will make the process more effective. The report also discusses the radiological consequences of producing energy from biomass contaminated by a major nuclear accident, both in the context of normal bio-fuel energy production and as a means of reducing potentially severe environmental problems in the forest by firing power plants with highly contaminated forest biomass. (au)

Phytoindication of radioactive pollution in environment

International Nuclear Information System (INIS)

Zacharova, A.; Ollerova, H.

2014-01-01

The poster is focused on phytoindicators of radioactivity pollution. There are discussed standard bioindication methods as well as plant species use for monitoring of radioactivity in environment. The work represents theoretical base for further study and identification of sensitive and accumulative phytoindicators as well as resistant plants to radionuclide and their input into plant biomass. The issue is part of research, which study an interaction between plants and radiation, what is finally in compliance with calls up of international organisations as for example Euratom. (authors)

Social impacts of radioactive waste disposal

International Nuclear Information System (INIS)

1985-11-01

In this report an approach is developed for the assessment of socio-economic impacts from radioactive waste disposal. The approach provides recommendations on procedures to be used in identification and prediction of impacts. Two decision-aiding methods are also included. The first provides for the identification of key issues and the illustration of the trade-offs involved in the decision. Multi-attribute scoring and weighting techniques are then proposed for the illustration of impacts using quantitative measures. (author)

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

Regulations on radioactive waste in hospitals

International Nuclear Information System (INIS)

Beiso, M.L.

2017-01-01

In hospitals that have a radiotherapy service, the contaminated sewage follows a specific way, first it comes from specific toilets that must be use by patients undergoing a radiotherapy treatment, and secondly it is stored in tanks and its radioactivity is measured regularly and when the radioactivity level is in conformity with regulations, sewage is disposed as any non-contaminated sewage. Regulations impose a radioactive level below 100 Becquerel per liter for I 131 and 10 Becquerel per liter for other nuclides for the sewage to be disposed. A new system named ST-10 allows the in-line and real-time measurement and the identification of nuclides in sewage and can say if the measured values are consistent with the patient treatment. (A.C.)

Crystal identification for a dual-layer-offset LYSO based PET system via Lu-176 background radiation and mean shift algorithm

Science.gov (United States)

Wei, Qingyang; Ma, Tianyu; Xu, Tianpeng; Zeng, Ming; Gu, Yu; Dai, Tiantian; Liu, Yaqiang

2018-01-01

Modern positron emission tomography (PET) detectors are made from pixelated scintillation crystal arrays and readout by Anger logic. The interaction position of the gamma-ray should be assigned to a crystal using a crystal position map or look-up table. Crystal identification is a critical procedure for pixelated PET systems. In this paper, we propose a novel crystal identification method for a dual-layer-offset LYSO based animal PET system via Lu-176 background radiation and mean shift algorithm. Single photon event data of the Lu-176 background radiation are acquired in list-mode for 3 h to generate a single photon flood map (SPFM). Coincidence events are obtained from the same data using time information to generate a coincidence flood map (CFM). The CFM is used to identify the peaks of the inner layer using the mean shift algorithm. The response of the inner layer is deducted from the SPFM by subtracting CFM. Then, the peaks of the outer layer are also identified using the mean shift algorithm. The automatically identified peaks are manually inspected by a graphical user interface program. Finally, a crystal position map is generated using a distance criterion based on these peaks. The proposed method is verified on the animal PET system with 48 detector blocks on a laptop with an Intel i7-5500U processor. The total runtime for whole system peak identification is 67.9 s. Results show that the automatic crystal identification has 99.98% and 99.09% accuracy for the peaks of the inner and outer layers of the whole system respectively. In conclusion, the proposed method is suitable for the dual-layer-offset lutetium based PET system to perform crystal identification instead of external radiation sources.

Sponsored research on radioactive waste management

International Nuclear Information System (INIS)

1983-01-01

The report is in chapters entitled: introduction (background, responsibilities, options, structure of the programme); strategy development; disposal of accumulations; disposal of radioactive waste arisings; quality assurance for waste conditioning quality assurance related to radioactive waste disposal (effectiveness of different rock types as natural barriers to the movement of radioactivity, and non-site specific factors in the design of repositories; radiological assessment; environmental studies; research and development to meet requirements specific to UKAEA wastes; long term research (processes for the solidification of highly active liquid wastes); plutonium contamination waste minimisation. (U.K.)

A new approach to estimate nuclide ratios from measurements with activities close to background

International Nuclear Information System (INIS)

Kirchner, G.; Steiner, M.; Zaehringer, M.

2009-01-01

Measurements of low-level radioactivity often give results of the order of the detection limit. For many applications, interest is not only in estimating activity concentrations of a single radioactive isotope, but focuses on multi-isotope analyses, which often enable inference on the source of the activity detected (e.g. from activity ratios). Obviously, such conclusions become questionable if the measurement merely gives a detection limit for a specific isotope. This is particularly relevant if the presence of an isotope, which shows a low signal only (e.g. due to a short half-life or a small transition probability), is crucial for gaining the information of interest. This paper discusses a new approach which has the potential to solve these problems. Using Bayesian statistics, a method is presented which allows statistical inference on nuclide ratios taking into account both prior knowledge and all information collected from the measurements. It is shown that our method allows quantitative conclusion to be drawn if counts of single isotopes are low or become even negative after background subtraction. Differences to the traditional statistical approach of specifying decision thresholds or detection limits are highlighted. Application of this new approach is illustrated by a number of examples of environmental low-level radioactivity measurements. The capabilities of our approach for spectrum interpretation and source identification are demonstrated with real spectra from air filters, sewage sludge and soil samples.

Radioactive waste management for a radiologically contaminated hospitalized patient

International Nuclear Information System (INIS)

Pina Jomir, G.; Michel, X.; Lecompte, Y.; Chianea, N.; Cazoulat, A.

2015-01-01

Radioactive waste management in the post-accidental phase following caring for a radiologically contaminated patient in a hospital decontamination facility must be anticipated at a local level to be truly efficient, as the volume of waste could be substantial. This management must comply with the principles set out for radioactive as well as medical waste. The first step involves identification of radiologically contaminated waste based on radioactivity measurement for volume reduction. Then, the management depends on the longest radioactive half-life of contaminative radionuclides. For a half-life inferior to 100 days, wastes are stored for their radioactivity to decay for at least 10 periods before disposal like conventional medical waste. Long-lived radioactive waste management implies treatment of liquid waste and special handling for sorting and packaging before final elimination at the French National Agency for Radioactive Waste Management (ANDRA). Following this, highly specialized waste management skills, financial responsibility issues and detention of non-medical radioactive sources are questions raised by hospital radioactive waste management in the post-accidental phase. (authors)

Knowing One's Place: Parental Educational Background Influences Social Identification with Academia, Test Anxiety, and Satisfaction with Studying at University.

Science.gov (United States)

Janke, Stefan; Rudert, Selma C; Marksteiner, Tamara; Dickhäuser, Oliver

2017-01-01

First-generation students (i.e., students whose parents did not attend university) often experience difficulties fitting in with the social environment at universities. This experience of personal misfit is supposedly associated with an impaired social identification with their aspired in-group of academics compared to continuing-generation students (i.e., students with at least one parent with an academic degree. In this article, we investigate how the postulated differences in social identification with the group of academics affect first-generation students' satisfaction with studying and test anxiety over time. We assume that first-generation students' impaired social identification with the group of academics leads to decreased satisfaction with studying and aggravated test anxiety over the course of the first academic year. In a longitudinal study covering students' first year at a German university, we found that continuing-generation students consistently identified more strongly with their new in-group of academics than first-generation students. The influence of social identification on test anxiety and satisfaction with studying differed between groups. For continuing-generation students, social identification with the group of academics buffered test anxiety and helped them maintain satisfaction with studying over time. We could not find these direct effects within the group of first-generation students. Instead, first-generation students were more sensitive to effects of test anxiety on satisfaction with studying and vice versa over time. The results suggest that first-generation students might be more sensitive to the anticipation of academic failure. Furthermore, continuing-generation students' social identification with the group of academics might have buffered them against the impact of negative experiences during the entry phase at university. Taken together, our findings underscore that deficit-driven approaches focusing solely on first

Method to determine the radioactivity of radioactive waste packages. Basic procedure of the method used to determine the radioactivity of low-level radioactive waste packages generated at nuclear power plants: 2007

International Nuclear Information System (INIS)

2008-03-01

This document describes the procedures adopted in order to determine the radioactivity of low-level radioactive waste packages generated at nuclear power plants in Japan. The standards applied have been approved by the Atomic Energy Society of Japan after deliberations by the Subcommittee on the Radioactivity Verification Method for Waste Packages, the Nuclear Cycle Technical Committee, and the Standards Committee. The method for determining the radioactivity of the low-level radioactive waste packages was based on procedures approved by the Nuclear Safety Commission in 1992. The scaling factor method and other methods of determining radioactivity were then developed on the basis of various investigations conducted, drawing on extensive accumulated knowledge. Moreover, the international standards applied as common guidelines for the scaling factor method were developed by Technical Committee ISO/TC 85, Nuclear Energy, Subcommittee SC 5, Nuclear Fuel Technology. Since the application of accumulated knowledge to future radioactive waste disposal is considered to be rational and justified, such body of knowledge has been documented in a standardized form. The background to this standardization effort, the reasoning behind the determination method as applied to the measurement of radioactivity, as well as other related information, are given in the Annexes hereto. This document includes the following Annexes. Annex 1: (reference) Recorded items related to the determination of the scaling factor. Annex 2 (reference): Principles applied to the determining the radioactivity of waste packages. (author)

An ultralow background germanium gamma-ray spectrometer

International Nuclear Information System (INIS)

Reeves, R.H.; Brodzinski, R.L.; Hensley, W.K.; Ryge, P.

1984-01-01

The monitoring of minimum detectable activity is becoming increasingly important as environmental concerns and regulations require more sensitive measurement of the radioactivity levels in the workplace and the home. In measuring this activity, however, the background becomes one of the limiting factors. Anticoincidence systems utilizing both NaI(T1) and plastic scintillators have proven effective in reducing some components of the background, but radiocontaminants in the various regions of these systems have limited their effectiveness, and their cost is often prohibitive. In order to obtain a genuinely low background detector system, all components must be free of detectable radioactivity, and the cosmic ray produced contribution must be significantly reduced. Current efforts by the authors to measure the double beta decay of Germanium 76 as predicted by Grand Unified Theories have resulted in the development of a high resolution germanium diode gamma spectrometer with an exceptionally low background. This paper describes the development of this system, outlines the configuration and operation of its preamplifier, linear amplifier, analog-to-digital converter, 4096-channel analyzer, shielding consisting of lead-sandwiched plastic scintillators wrapped in cadmium foil, photomultiplier, and its pulse generator and discriminator, and then discusses how the system can be utilized to significantly reduce the background in high resolution photon spectrometers at only moderate cost

Radioactive elements in Pennsylvania waters

International Nuclear Information System (INIS)

Rose, A.W.

1990-01-01

The first recognition of radioactive elements in natural waters dates back many years, but interest has accelerated in recent years with the advent of concern about the health effects of radioactivity. At the present time, extensive monitoring of public water supplies for radioactive substances is mandated by federal and state law, and monitoring near nuclear facilities is required by federal regulations, so that a great deal of information is accumulating on the amount and distribution of radioactivity in natural waters. These results reveal that small amounts of radioactive elements are universally present in natural waters, and that the concentration vary over an appreciable range as a result of natural processes and human activities. The purpose of this paper is to summarize the origin, behavior, abundance and hazard of the main radioactive species in Pennsylvania surface and ground waters. This treatment is intended to provide background to the interested reader in comprehending questions such as the hazard of radon in homes with private wells and pollution related to the nuclear power cycle

Siting of a low-level radioactive waste disposal facility

International Nuclear Information System (INIS)

Alvarado, R.A.

1983-01-01

The Texas Low-Level Radioactive Waste Disposal Authority was established by the 67th Legislature to assure safe and effective disposal of the state's low-level radioactive waste. The Authority operates under provisions of the Texas Low-Level Radioactive Waste Disposal Authority Act, VACS 4590f-1. In Texas, low-level radioactive waste is defined as any radioactive material that has a half-life of 35 years or less or that has less than 10 nanocuries per gram of transuranics, and may include radioactive material not excluded by this definition with a half-life or more than 35 years if special disposal criteria are established. Prior to beginning the siting study, the Authority developed both exclusionary and inclusionary criteria. Major requirements of the siting guidelines are that the site shall be located such that it will not interfere with: (1) existing or near-future industrial use, (2) sensitive environmental and ecological areas, and (3) existing and projected population growth. Therefore, the site should be located away from currently known recoverable mineral, energy and water resources, population centers, and areas of projected growth. This would reduce the potential for inadvertent intruders, increasing the likelihood for stability of the disposal site after closure. The identification of potential sites for disposal of low-level radioactive waste involves a phased progression from statewide screening to site-specific exploration, using a set of exclusionary and preferential criteria to guide the process. This methodology applied the criteria in a sequential manner to focus the analysis on progressively smaller and more favorable areas. The study was divided into three phases: (1) statewide screening; (2) site identification; and (3) preliminary site characterization

Planning for environmental restoration of radioactively contaminated sites in central and eastern Europe. V.1: Identification and characterization of contaminated sites. Proceedings of a workshop held within the technical co-operation project

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

The radioactive contaminant materials resulting from diverse activities in relation to the nuclear fuel cycle, defense related operations, and various industries in addition to medical and research facilities represent perhaps the most severe and immense pollution left from a past era. The political changes in central and eastern Europe (CEE) not only brought some disclosure of the radioactively contaminated sites, but also resulted in a political condition in which this region became receptive to co-operation from a range of outside countries. The subject of the first workshop held in Budapest, 4-8 October 1993, was the identification and characterization of radioactively contaminated sites in the region. Refs, figs and tabs.

Planning for environmental restoration of radioactively contaminated sites in central and eastern Europe. V.1: Identification and characterization of contaminated sites. Proceedings of a workshop held within the technical co-operation project

International Nuclear Information System (INIS)

1996-02-01

The radioactive contaminant materials resulting from diverse activities in relation to the nuclear fuel cycle, defense related operations, and various industries in addition to medical and research facilities represent perhaps the most severe and immense pollution left from a past era. The political changes in central and eastern Europe (CEE) not only brought some disclosure of the radioactively contaminated sites, but also resulted in a political condition in which this region became receptive to co-operation from a range of outside countries. The subject of the first workshop held in Budapest, 4-8 October 1993, was the identification and characterization of radioactively contaminated sites in the region. Refs, figs and tabs

SHIPPING OF RADIOACTIVE ITEMS

CERN Multimedia

TIS/RP Group

2001-01-01

The TIS-RP group informs users that shipping of small radioactive items is normally guaranteed within 24 hours from the time the material is handed in at the TIS-RP service. This time is imposed by the necessary procedures (identification of the radionuclides, determination of dose rate, preparation of the package and related paperwork). Large and massive objects require a longer procedure and will therefore take longer.

Summary of industrial impacts from recycled radioactive scrap metals

International Nuclear Information System (INIS)

Dehmel, J.-C.; Harrop, J.; MacKinney, J.A.

1995-01-01

During operation, decontamination, and dismantlement, nuclear facilities are generating significant quantities of radioactive scrap metal (RSM). Future decommissioning will generate even more RSM. The petroleum industry also generates RSM in the form of equipment contaminated with naturally occurring radioactivity. Finally, the accidental melting of radioactive sources in steel mills has generated smaller amounts of contaminated metals. Steel mills, smelters, and foundries could recycle these materials, which might then appear in finished products or as feedstocks used by other industries. If introduced in this manner, residual radioactivity can adversely affect the performance of certain products. Such products include computers and other devices that rely on integrated circuits. The most important effect of residual radioactivity on integrated circuits is a phenomenon known as 'single event upsets or soft errors.' Radioactivity can also adversely affect the performance of products such as photographic film and components designed to measure the presence of radioactivity. Radioactivity that raises background count-rates to higher levels could affect the performance of radiation monitoring systems and analytical equipment. Higher background count-rates would lead to reduced sensitivity and lower resolution in spectroscopic systems. The computer, photographic, and radiation measurement industries have taken steps to minimize the impact of residual radioactivity on their products. These steps include monitoring manufacturing processes, specifying material acceptance standards, and screening suppliers. As RSM is recycled, these steps may become more important and more costly. This paper characterizes potentially impacted industries and vulnerability and effects due to the presence of residual radioactivity. Finally, the paper describes practices used to limit the impact of residual radioactivity. (J.P.N.)

Source, transport and dumping of radioactive waste

International Nuclear Information System (INIS)

1980-03-01

The results of an examination into the problems of radioactive waste are presented, in particular the sources, transport and dumping and the policy considerations in favour of specific methods. The theoretical background of radioactive waste is described, including the physical and chemical, ecological, medical and legal aspects. The practical aspects of radioactive waste in the Netherlands are considered, including the sources, the packaging and transport and dumping in the Atlantic Ocean. The politics and policies involved in this process are outlined. (C.F.)

Radioactive tracer profiling system and apparatus

International Nuclear Information System (INIS)

Wiley, R.; Veach, L.

1977-01-01

A radioactive charge is ejected into the borehole and a subsurface unit including a radiation detector is moved upwardly through this charge a number of times. The total radiation count as the unit moves up through the charge is obtained by integrating the output of the radiation detector during the period when the counter output exceeds the background radiation. The integrated count is displayed on a digital display unit. Compensation is provided for background radiation within the borehole. Also correction is made for the dead time of the radiation detector so that an accurate indication of the total amount of radioactivity remaining in the borehole during successive runs is obtained. 22 claims, 6 figures

Using the IEC standard to describe low-background detectors -- What can you expect?

International Nuclear Information System (INIS)

Keyser, R.M.; Wagner, S.

1998-01-01

Many measurements for environmental levels of the radioactive content require that the gamma-ray detector be low background, that is, free of any radioactive content. This is, of course, not possible, but the radioactivity in the detector must be reduced to as low a value as possible. The description or specification of the background spectrum necessary to achieve the desired results is needed. The new International Electrotechnical Commission (IEC) standard for describing the background makes the specification of the background in a high-purity germanium (HPGe) detector simple, unambiguous, and related to how the detector will be used. Users and manufacturers will finally be speaking the same language on this subject. Because this standard extends the specification of the performance of an HPGe detector, there is little history available for comparison and thus no means of determining a good value. To develop a history, the background spectrum for 500 low-background HPGe ORTEC detectors were all counted in similar low-background shields. These detectors were in a variety of mechanical cryostat and endcap configurations. The continuum background is a function of energy and detector size/configuration. The peak area for the peak energies listed in the standard is a function of detector size and configuration. The results thus give practical guidance for obtaining the most appropriate low-background detector for a specific measurement problem

A performance assessment methodology for low-level radioactive waste disposal

International Nuclear Information System (INIS)

Derring, L.R.

1990-01-01

To demonstrate compliance with the performance objectives governing protection of the general population in 10 CFR 61.41, applicants for land disposal of low-level radioactive waste are required to conduct a pathways analysis, or quantitative evaluation of radionuclide release, transport through environmental media, and dose to man. The Nuclear Regulatory Commission staff defined a strategy and initiated a project at Sandia National Laboratories to develop a methodology for independently evaluating an applicant's analysis of postclosure performance. This performance assessment methodology was developed in five stages: identification of environmental pathways, ranking the significance of the pathways, identification and integration of models for pathway analyses, identification and selection of computer codes and techniques for the methodology, and implementation of the codes and documentation of the methodology. This paper summarizes the NRC approach for conducting evaluations of license applications for low-level radioactive waste facilities. 23 refs

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. An extra issue: background of the geological disposal

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, an extra issue of the progress report, was prepared for the expected readers of the report to have background information on the geological disposal. Thus it gives information about (1) generation of high-level radioactive wastes, (2) history of plans proposed for HLW disposal in Japan, and (3) procedure until the geological disposal plan is finally adopted and basic future schedules. It further discusses on such problems in HLW treatment and disposal, as for example a problem of reliable safety for a very long period. (Ohno, S.)

Report on the radioactive mineral development project in Negros Island

International Nuclear Information System (INIS)

Santos, G. Jr.

1981-12-01

A reconnaissance radiometric and stream sediment survey was conducted in Negros Island from April to May 1980. An area in Mabinay, Negros Oriental with significant above-background uranium in stream sediment was delineated in Upper Miocene to Pliocene continental clastic associated with silty limestone. In general, Negros has low radioactivity except for isolated points which have 2-3 times above-the-background radioactivity. Other areas in the western part of the island with high radioactivity and above-normal uranium in stream sediments were delineated. However, these above-normal observations were noted in areas underlain by recent volcanic sediments which were probably derived from Mt. Kanlaon. (author)

AIR RADIOACTIVITY MONITOR

Science.gov (United States)

Bradshaw, R.L.; Thomas, J.W.

1961-04-11

The monitor is designed to minimize undesirable background buildup. It consists of an elongated column containing peripheral electrodes in a central portion of the column, and conduits directing an axial flow of radioactively contaminated air through the center of the column and pure air through the annular portion of the column about the electrodes. (AEC)

Security of Radioactive Waste

International Nuclear Information System (INIS)

Goldammer, W.

2003-01-01

Measures to achieve radioactive waste security are discussed. Categorization of waste in order to implement adequate and consistent security measures based on potential consequences is made. The measures include appropriate treatment/storage/disposal of waste to minimize the potential and consequences of malicious acts; management of waste only within an authorised, regulated, legal framework; management of the security of personnel and information; measures to minimize the acquisition of radioactive waste by those with malicious intent. The specific measures are: deter unauthorized access to the waste; detect any such attempt or any loss or theft of waste; delay unauthorized access; provide timely response to counter any attempt to gain unauthorised access; measures to minimize acts of sabotage; efforts to recover any lost or stolen waste; mitigation and emergency plans in case of release of radioactivity. An approach to develop guidance, starting with the categorisation of sources and identification of dangerous sources, is presented. Dosimetric criteria for internal and external irradiation are set. Different exposure scenarios are considered. Waste categories and security categories based on the IAEA INFCIRC/225/Rev.4 are presented

Knowing One’s Place: Parental Educational Background Influences Social Identification with Academia, Test Anxiety, and Satisfaction with Studying at University

Directory of Open Access Journals (Sweden)

Stefan Janke

2017-08-01

Full Text Available First-generation students (i.e., students whose parents did not attend university often experience difficulties fitting in with the social environment at universities. This experience of personal misfit is supposedly associated with an impaired social identification with their aspired in-group of academics compared to continuing-generation students (i.e., students with at least one parent with an academic degree. In this article, we investigate how the postulated differences in social identification with the group of academics affect first-generation students’ satisfaction with studying and test anxiety over time. We assume that first-generation students’ impaired social identification with the group of academics leads to decreased satisfaction with studying and aggravated test anxiety over the course of the first academic year. In a longitudinal study covering students’ first year at a German university, we found that continuing-generation students consistently identified more strongly with their new in-group of academics than first-generation students. The influence of social identification on test anxiety and satisfaction with studying differed between groups. For continuing-generation students, social identification with the group of academics buffered test anxiety and helped them maintain satisfaction with studying over time. We could not find these direct effects within the group of first-generation students. Instead, first-generation students were more sensitive to effects of test anxiety on satisfaction with studying and vice versa over time. The results suggest that first-generation students might be more sensitive to the anticipation of academic failure. Furthermore, continuing-generation students’ social identification with the group of academics might have buffered them against the impact of negative experiences during the entry phase at university. Taken together, our findings underscore that deficit-driven approaches

Knowing One’s Place: Parental Educational Background Influences Social Identification with Academia, Test Anxiety, and Satisfaction with Studying at University

Science.gov (United States)

Janke, Stefan; Rudert, Selma C.; Marksteiner, Tamara; Dickhäuser, Oliver

2017-01-01

First-generation students (i.e., students whose parents did not attend university) often experience difficulties fitting in with the social environment at universities. This experience of personal misfit is supposedly associated with an impaired social identification with their aspired in-group of academics compared to continuing-generation students (i.e., students with at least one parent with an academic degree. In this article, we investigate how the postulated differences in social identification with the group of academics affect first-generation students’ satisfaction with studying and test anxiety over time. We assume that first-generation students’ impaired social identification with the group of academics leads to decreased satisfaction with studying and aggravated test anxiety over the course of the first academic year. In a longitudinal study covering students’ first year at a German university, we found that continuing-generation students consistently identified more strongly with their new in-group of academics than first-generation students. The influence of social identification on test anxiety and satisfaction with studying differed between groups. For continuing-generation students, social identification with the group of academics buffered test anxiety and helped them maintain satisfaction with studying over time. We could not find these direct effects within the group of first-generation students. Instead, first-generation students were more sensitive to effects of test anxiety on satisfaction with studying and vice versa over time. The results suggest that first-generation students might be more sensitive to the anticipation of academic failure. Furthermore, continuing-generation students’ social identification with the group of academics might have buffered them against the impact of negative experiences during the entry phase at university. Taken together, our findings underscore that deficit-driven approaches focusing solely on first

Background simulation for the GENIUS project

International Nuclear Information System (INIS)

Ponkratenko, O.A.; Tretyak, V.I.; Zdesenko, Yu.G.

1999-01-01

The background simulations for the GENIUS experiment were performed with the help of GEANT 3.21 package and event generator DECAY 4.Contributions from the cosmogenic activity produced in the Ge detectors and from its radioactive impurities as well as from contamination of the liquid nitrogen and other materials were calculated.External gamma and neutron background were taking into consideration also.The results of calculations evidently show feasibility of the GENIUS project,which can substantially promote development of modern astroparticle physics

Survey on non-nuclear radioactive waste

International Nuclear Information System (INIS)

2003-11-01

On request from the Swedish Radiation Protection Authority, the Swedish government has in May 2002 set up a non-standing committee for non-nuclear radioactive waste. The objective was to elaborate proposals for a national system for the management of all types of non-nuclear radioactive wastes with special consideration of inter alia the polluter pays principle and the responsibility of the producers. The committee will deliver its proposals to the government 1 December 2003. SSI has assisted the committee to the necessary extent to fulfill the investigation. This report is a summery of SSI's background material concerning non-nuclear radioactive waste in Sweden

Development of radioactive materials inspection system

International Nuclear Information System (INIS)

Yang Lu; Wang Guobao; Chen Yuhua; Li Latu; Zhang Sujing

2005-01-01

Radioactive materials inspection system which is applied to inspect the horror activities of radioactive materials and its illegal transfer. The detector sections are made of highly stable and credible material. It has high sensitivity to radioactive materials. The inspect lowest limit of inspection is the 2-3 times to the background, the energy range is 30 keV-2.5 MeV and the response time is 0.5 s. Inspection message can be transmitted through wired or wireless web to implement remote control. The structure of the system is small, light and convenient. It is ideal for protecting society and public from the harm of the radiation. (authors)

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

Medium-Sized Mammals around a Radioactive Liquid Waste Lagoon at Los Alamos National Laboratory: Uptake of Contaminants and Evaluation of Radio-Frequency Identification Technology

Energy Technology Data Exchange (ETDEWEB)

Leslie A. Hansen; Phil R. Fresquez; Rhonda J. Robinson; John D. Huchton; Teralene S. Foxx

1999-11-01

Use of a radioactive liquid waste lagoon by medium-sized mammals and levels of tritium, other selected radionuclides, and metals in biological tissues of the animals were documented at Technical Area 53 (TA-53) of Los Alamos National Laboratory during 1997 and 1998. Rock squirrel (Spermophilus variegates), raccoon (Procyon lotor), striped skunk (Mephitis mephitis), and bobcat (Lynx rufus) were captured at TA-53 and at a control site on the Santa Fe National Forest. Captured animals were anesthetized and marked with radio-frequency identification (RFD) tags and/or ear tags. We collected urine and hair samples for tritium and metals (aluminum, antimony, arsenic, barium, beryllium, cadmium, chromium, copper, lead, mercury, nickel, selenium, silver, and thallium) analyses, respectively. In addition, muscle and bone samples from two rock squirrels collected from each of TA-53, perimeter, and regional background sites were tested for tritium, {sup 137}Cs, {sup 90}Sr, {sup 238}Pu, {sup 239,240}Pu, {sup 241}Am, and total uranium. Animals at TA-53 were monitored entering and leaving the lagoon area using a RFID monitor to read identification numbers from the RFID tags of marked animals and a separate camera system to photograph all animals passing through the monitor. Cottontail rabbit (Sylvilagus spp.), rock squirrel, and raccoon were the species most frequently photographed going through the RFID monitor. Less than half of all marked animals in the lagoon area were detected using the lagoon. Male and female rock squirrels from the lagoon area had significantly higher tritium concentrations compared to rock squirrels from the control area. Metals tested were not significantly higher in rock squirrels from TA-53, although there was a trend toward increased levels of lead in some individuals at TA-53. Muscle and bone samples from squirrels in the lagoon area appeared to have higher levels of tritium, total uranium, and {sup 137}Cs than samples collected from perimeter and

An approach in determining the baseline data on the natural background radioactivity of Batanes province, its implications to national security

International Nuclear Information System (INIS)

Reyes, Rolando Y.

2005-01-01

Since the dropping of the first atomic bombs in Hiroshima and Nagasaki on August 1945, the world has lived under the shadow of nuclear threat. This was heightened by the Chernobyl nuclear accident in 1986 and magnified by the September 11, 2001 terrorist attack of the World Trade Center in the USA. While the threat is global, nuclear security is a national responsibility. The Philippine government is presently formulating the Philippine Nuclear Security Plan (PNSP) to address nuclear security and terrorism. It is in this light that this research study was undertaken whose product can be used as input in the PNSP, particularly in the emergency preparedness and response strategy of the plan. The purpose of the study is to pilot a baseline study on the natural background radioactivity of Batan Island, Batanes province, and develop a scheme for replicating the Batan baseline study in other selected sites in the Philippines. Establishing a baseline data on the natural background radioactivity of the country is a proactive stand of trying to be prepared for any untoward nuclear event that can pose harm of the nation, people and environment. The baseline data will provide an important point of reference in assessing increases of radiation caused by serious nuclear and/or radiological incident, either accidentally or intentionally that may occur within and outside the national territory. A modified ground gamma ray spectrometric survey technique with the use of a portable gamma ray spectrometer and global positioning system was used in determining the distribution and abundance of the naturally occurring radioelements potassium (K), uranium (U), thorium (Th) and total natural radiation (TNR) of Batan Island. Prior to the field survey, a thorough calibration of the portable gamma ray instrument was instituted that converted the measured gamma-ray count data into ground concentrations of K, U and Th. This allowed the systematic measurement of 73 sampling/data stations for

Radioactive wastes in Oklo

International Nuclear Information System (INIS)

Balcazar, M.; Flores R, J.H.; Pena, P.; Lopez, A.

2006-01-01

The acceptance of the Nuclear Energy as electric power supply implies to give answer to the population on the two main challenges to conquer in the public opinion: the nuclear accidents and the radioactive wastes. Several of the questions that are made on the radioactive wastes, its are the mobility migration of them, the geologic stability of the place where its are deposited and the possible migration toward the aquifer mantels. Since the half lives of the radioactive waste of a Nuclear Reactor are of several hundred of thousands of years, the technical explanations to the previous questions little convince to the public in general. In this work summary the results of the radioactive waste generated in a natural reactor, denominated Oklo effect that took place in Gabon, Africa, it makes several thousands of millions of years, a lot before the man appeared in the Earth. The identification of at least 17 reactors in Oklo it was carried out thanks to the difference in the concentrations of Uranium 235 and 238 prospective, and to the analysis of the non-mobility of the radioactive waste in the site. It was able by this way to determine that the reactors with sizes of hardly some decimeter and powers of around 100 kilowatts were operating in intermittent and spontaneous form for space of 150,000 years, with operation cycles of around 30 minutes. Recent studies have contributed information valuable on the natural confinement of the radioactive waste of the Oklo reactors in matrixes of minerals of aluminum phosphate that caught and immobilized them for thousands of millions of years. This extracted information from the nature contributes guides and it allows 'to verify' the validity of the current proposals on the immobilization of radioactive wastes of a nuclear reactor. This work presents in clear and accessible form to the public in general on the secure 'design', operation, 'decommissioning' and 'storage' of the radioactive waste of the reactors that the nature put

An overview of the AECB's strategy for regulating radioactive waste management activities

International Nuclear Information System (INIS)

Hamel, P.E.; Smythe, W.D.; Duncan, R.M.; Coady, J.R.

1982-07-01

The goal of the Canadian Atomic Energy Control Board in regulating the management of radioactive wastes is to ensure the protection of people and the environment. A program of cooperation with other agencies, identification and adoption of baselines for describing radioactive wastes, development of explicit criteria and requirements, publication of related regulatory documents, establishment of independent consultative processes with technical experts and the public, and maintenance of awareness and compatibility with international activities is underway. Activities related to high-level radioactive waste, uranium mine and mill tailings, low- and medium-level wastes, radioactive effluents from nuclear facilities, and decommissioning and decontamination are described

Research of high energy radioactivity identification detector

Energy Technology Data Exchange (ETDEWEB)

Kim, Yong Kyun; Lee, Yong Bum; Hwang, Jong Sun; Choi, Seok Ki

1998-07-01

{Delta} {Epsilon}-{Epsilon} telescope high radioactivity detector was designed, fabricated, and tested at the 35 MeV proton energy. We developed the computer code to calculate the energy loss of projectile ions in the matter. Using the code, we designed and fabricated a detector to measure 15-50 MeV protons. The detector was successfully tested to measure the energy of protons and deuterons and to identify the ions. In future, we would like to extend the present result to the development of a higher energy proton detector and a heavy ion detector. (author). 10 refs., 3 tabs., 14 figs

Investigation On Natural Background Radioactivity At TanLong, Lagi, BinhThuan Residential Area On Ilmenite Deposit Location

International Nuclear Information System (INIS)

Pham Thi Kim Loan; Tran Van Luyen; Thai Khac Dinh

2008-01-01

An Ilmenite deposit zone located at TanLong, Lagi, Binh Thuan province. After the year of 2000, a new village of population has set up at this place. To estimate the effect on the human health of radioactivity accompanying with the deposit, the sand samples were collected and natural radioactive analyzed at center for nuclear techniques. The average year doses D annual , hazard radiation exposed index H ex and Radium equivalence Ra eq were calculated based on the natural radioactivities. The results show that these factors are overcome the international average as well as southern Vietnam values. (author)

Measurement of Background Gamma Radiation Levels at Two ...

African Journals Online (AJOL)

MICHAEL

ABSTRACT: An in-situ measurement of the background radiation level was carried out at the vicinity of three ... Soil contains small quantities of radioactive elements along with their progeny. .... assessment for soil samples from Kestanbol.

The investment of radioactivity background in agroenvironment around Daya-Bay NPP

International Nuclear Information System (INIS)

Hou Lanxing; Xu Shiming; Zhao Wenhu; Shang Zhaorong; Li Xia

1996-03-01

The investigation of radioactivity and γ absorbed dose rate in free air were taken in soil organisms water around Daya-Bay NPP 50 km radius in 1985 and 1987. The result shows that the difference of total radioactivity in soil in same soil section between up and down is few, but the diversity among soil points is big. The order of natural radionuclides in top soil is 40 K> 232 Th> 238 U> 226 Ra. The diversity among soil point of 137 Cs is very big (0∼15.32 Bq) and the average value is 4.16 Bq. The total β activity in every kilogram water is 1.75∼1148.76 Bq and the order is sea water>pond water>river water>spring water. The total β activity in every kilogram fresh organisms is 5.2∼903.3 Bq and the order is rice straw>peanut kernel>peanut shell>rice hull>fish bone>leaf vegetables (green vegetable>romaine lettuce)>rice>meat (pork>chicken)>fish>milk>egg (duck's egg>layer's egg)>sugercane. The total α activity in every kilogram fresh organisms is 0.05∼283.6 Bq and the order is rice straw>peanut shell>fish bone>rice hull>peanut kernel>egg>leaf vegetables>rice>sugercane>meat>milk. The diversity of γ absorbed dose rate in free air between inside and out of house is 11.1∼17.8 Gy·h -1

Application of a background-compensated Geiger-Mueller counter to a survey meter

International Nuclear Information System (INIS)

Mori, C.; Kumanomido, H.; Watanabe, T.

1984-01-01

A background-compensated Geiger-Mueller counter was used as a probe for a GM survey meter to obtain a net count rate of β-rays from a radioactive source in a quick survey. Although a background counting ratio between the two parts in the counter, front and rear, varied somewhat depending on the incident direction of background γ-rays, it was possible to compensate the background counts by subtracting a part of the rear counts, which were background counts, from the front counts, which contained β-ray counts and background counts. Undesirable small pulses generated during the recovering time after a full Geiger discharge were eliminated by an anticoincidence gating method. The survey meter with this counter and a differential ratemeter is useful for obtaining a net count rate of β-rays emitted from a surface radioactive-contamination or from a source being put near the window of the counter with nearly the same accuracy in half the measuring time as compared with conventional GM counters. (orig.)

Processor core for real time background identification of HD video based on OpenCV Gaussian mixture model algorithm

Science.gov (United States)

Genovese, Mariangela; Napoli, Ettore

2013-05-01

The identification of moving objects is a fundamental step in computer vision processing chains. The development of low cost and lightweight smart cameras steadily increases the request of efficient and high performance circuits able to process high definition video in real time. The paper proposes two processor cores aimed to perform the real time background identification on High Definition (HD, 1920 1080 pixel) video streams. The implemented algorithm is the OpenCV version of the Gaussian Mixture Model (GMM), an high performance probabilistic algorithm for the segmentation of the background that is however computationally intensive and impossible to implement on general purpose CPU with the constraint of real time processing. In the proposed paper, the equations of the OpenCV GMM algorithm are optimized in such a way that a lightweight and low power implementation of the algorithm is obtained. The reported performances are also the result of the use of state of the art truncated binary multipliers and ROM compression techniques for the implementation of the non-linear functions. The first circuit has commercial FPGA devices as a target and provides speed and logic resource occupation that overcome previously proposed implementations. The second circuit is oriented to an ASIC (UMC-90nm) standard cell implementation. Both implementations are able to process more than 60 frames per second in 1080p format, a frame rate compatible with HD television.

Impurities in radioactive solutions for gamma spectroscopy

International Nuclear Information System (INIS)

Delgado, J.U.

1990-01-01

The absolute and relative methods for radioactive sources calibration, like 4 Πβ-γ and 4Πγ ionization chamber respectively, allows to reach 0,1% of exactiness in activity measurement, but cannot distinguish radioactive impurities that interfere in the activity. Then, one of the problems associated to a quality control of calibrated sources furnished to users is the identification and quantification of the impurities. In this work, a routine technical procedure, using the facilities of gamma spectrometry method that allows to identify and to determine the impurities relative contribution to the source main radionuclide activity, is described. (author) [pt

Introduction to radioactive waste management issues in Wisconsin

International Nuclear Information System (INIS)

Anon.

1977-01-01

This brief focused on wastes from commercial production of electricity and various industrial, medical and research applications of radioactive materials. Only traditionally solid wastes are dealt with. It was organized into five parts. Part I presented an introduction to radioactivity - what it is and the biological hazards associated with it. Federal regulation of the management of radioactive wastes was discussed in Part II. Existing state laws and bills currently before the Wisconsin Legislature were described in Part III. Part IV gave background information on specific areas of potential inquiry related to radioactive wastes in Wisconsin. Part V summarized the issues identified in the brief. 2 figures, 7 tables

Optimization of the energy resolution and of the radioactive background rejection for ionization-heat detectors equipped with thermometric thin films for the direct WIMPs detection

International Nuclear Information System (INIS)

Dolgorouky, Y.W.

2008-09-01

The EDELWEISS experiment aims at the direct detection of WIMPs as possible candidates for dark matter. It uses heat-and-ionization detectors that can discriminate these particles from the radioactive background. To date, this method is limited by events with incomplete charge collection that occur just beneath the detectors electrodes. In order to identify and reject these undesirable events, we have developed detectors equipped with thin films used both as thermometers - and hence sensitive to the transient athermal regime - and as electrodes for the charge collection. This thesis focuses on the optimization of such thin films regarding surface events rejection and on the modelling of the physical processes enabling this identification. The optimization must both maximize the fiducial volume and conserve an energy resolution such that the recoil energy threshold is of the order of 30 keV. Our work explores four generations of detectors each of which corresponds to successive evolutions in their conception. In all cases, the electrode-thermometer is an amorphous Anderson insulator NbSi thin film polarized by two interleaved comb-shaped niobium electrodes. In spite of constant progress in the successive detectors performances, the latest generation does not display the performances required for the EDELWEISS II experiment. Our work has shown the difficulty of the transient thermal signal modelling due to the complex contribution of the charge collection. This works has lead to new ideas regarding the detectors configuration, so that the athermal regime can be optimized to enhance both the rejection capability and the resolution. (author)

Natural radioactivity and associated radiation characteristic of the new high background radiation area of lambwe east southern Kenya

International Nuclear Information System (INIS)

Achola, S.O.; Patel, J.P.; Angeyo, H.K.; Mustapha, A.O.

2010-01-01

Rocks and soils from a number of areas underlined by carbonatite rocks in Kenya have been associated with high levels of natural background radioactivity. People in such high background radiation areas (HBRA), are exposed to abnormally high annual absorbed dose (that have health implications) than the global normal 1 mSvyr-1. In this paper, results of field background radiation measurements, activity concentrations of primordial radionuclides in (mainly carbonatite rock and soil) matrices, and estimated annual external effective dose rates are presented for South and North Ruri hills in Lambwe East location of Suba District, which lies roughly between latitudes 0°30'S and 1°00'S, bounded on the east by longitude 34°30'E and on the west by the shores of Lake Victoria 16 and Winnam Gulf. Altitudes in the region range from about 1000 m on the shores of Lake Victoria to above 1800 m on top of the Ruri hills. The main geological features are carbonatite formations. Twenty one samples were analyzed using high-purity germanium (HPGe) gamma-ray spectrometer. The activity concentrations ranged 14.18 - 6559.99 Bqkg-1 (average: 1396.85 Bqkg-1) for Th-232; 2.73 - 499.24 Bqkg-1 (average: 178.69 Bqkg-1) for U-238; and 56.67 - 1454.73 Bqkg-1 (average: 508.67 Bqkg-1) for K-40. The variability in Th distribution could be due to another contributing factor apart from carbonatite: Homa hills geothermal field fluids might be responsible for delivery of Th to surface rocks; some hot spots have travertine deposits. Measured absorbed dose rates in air outdoors range 700 - 6000.00 nGyh-1 (mean: 2325.84 nGy h-1); assuming 0.4 occupancy factor, these values correspond to individual annual effective dose rates of 1.717 - 14.717 mSvyr-1 (mean: 5.705 mSv yr-1). Measured absorbed dose rates are higher than calculated values since they include the contribution of cosmic rays. The natural radioactivity is fractionated with higher levels in the soils than carbonatite rocks

Method and apparatus for determining accuracy of radiation measurements made in the presence of background radiation

International Nuclear Information System (INIS)

Horrocks, D.L.

1977-01-01

A radioactivity measuring instrument, and a method related to its use, for determining the radioactivity of a sample measured in the presence of significant background radiation, and for determining an error value relating to a specific probability of accuracy of the result are presented. Error values relating to the measurement of background radiation alone, and to the measurement of sample radiation and background radiation together, are combined to produce a true error value relating to the sample radiation alone

Handbook of high-level radioactive waste transportation

International Nuclear Information System (INIS)

Sattler, L.R.

1992-10-01

The High-Level Radioactive Waste Transportation Handbook serves as a reference to which state officials and members of the general public may turn for information on radioactive waste transportation and on the federal government's system for transporting this waste under the Civilian Radioactive Waste Management Program. The Handbook condenses and updates information contained in the Midwestern High-Level Radioactive Waste Transportation Primer. It is intended primarily to assist legislators who, in the future, may be called upon to enact legislation pertaining to the transportation of radioactive waste through their jurisdictions. The Handbook is divided into two sections. The first section places the federal government's program for transporting radioactive waste in context. It provides background information on nuclear waste production in the United States and traces the emergence of federal policy for disposing of radioactive waste. The second section covers the history of radioactive waste transportation; summarizes major pieces of legislation pertaining to the transportation of radioactive waste; and provides an overview of the radioactive waste transportation program developed by the US Department of Energy (DOE). To supplement this information, a summary of pertinent federal and state legislation and a glossary of terms are included as appendices, as is a list of publications produced by the Midwestern Office of The Council of State Governments (CSG-MW) as part of the Midwestern High-Level Radioactive Waste Transportation Project

Environmental radioactivity in the Netherlands. Results in 2009

Energy Technology Data Exchange (ETDEWEB)

Knetsch, G J; Groot, M C.E. [eds.

2011-11-15

In 2009 the Netherlands fulfilled the European obligation to annually measure radioactivity in the environment and in food. According to the Euratom Treaty of 1957, all Member States of the European Union are obliged to perform these measurements each year. Euratom has provided guidelines for performing the measurements uniformly since 2000. However, Member States are not obliged to comply with these recommended guidelines. In the Netherlands, in 2009 strontium-90 was also determined (for the first time) in a mixed food package for which the above recommendations had been fulfilled. The National Institute for Public Health and the Environment (RIVM) reports on behalf of the Netherlands to the European Union about radioactivity in the environment. Moreover, this information provides background values and/or amounts of radioactivity that are present under normal circumstances. These background values can be used as reference values, for instance, during a disaster.

An integrated approach to the management of radioactive waste in Australia

International Nuclear Information System (INIS)

Woollett, S.M.

2002-01-01

This paper draws attention to the practices and progress in radioactive waste management in Australia. A National Repository for the disposal of low-level and short-lived intermediate- level radioactive waste and a National Store for the storage of long-lived intermediate-level radioactive waste are presently being established. This has necessitated considerable activity in addressing emerging issues in the management of radioactive waste. The Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) has a major role in developing an integrated approach to manage radioactive waste in Australia. This approach begins with the development of a radioactive waste management policy and identification of the issues in radioactive waste management requiring attention. ARPANSA is developing national standards and guidance documents for the safe and responsible management of waste prior to its acceptance at the National Repository or National Store. This contributes to the Agency's promotion of uniformity of radiation protection and nuclear safety policy and practices across Australia's Commonwealth, State and Territory jurisdictions. (author)

Biosphere models for safety assesment of radioactive waste disposal

Energy Technology Data Exchange (ETDEWEB)

Proehl, G; Olyslaegers, G; Zeevaert, T [SCK/CEN, Mol (Belgium); Kanyar, B [University of Veszprem (Hungary). Dept. of Radiochemistry; Pinedo, P; Simon, I [Centro de Investigaciones Energeticas Medioambientales y Tecnologicas (CIEMAT), Madrid (Spain); Bergstroem, U; Hallberg, B [Studsvik Ecosafe, Nykoeping (Sweden); Mobbs, S; Chen, Q; Kowe, R [NRPB, Chilton, Didcot (United Kingdom)

2004-07-01

The aim of the BioMoSA project has been to contribute in the confidence building of biosphere models, for application in performance assessments of radioactive waste disposal. The detailed objectives of this project are: development and test of practical biosphere models for application in long-term safety studies of radioactive waste disposal to different European locations, identification of features, events and processes that need to be modelled on a site-specific rather than on a generic base, comparison of the results and quantification of the variability of site-specific models developed according to the reference biosphere methodology, development of a generic biosphere tool for application in long term safety studies, comparison of results from site-specific models to those from generic one, Identification of possibilities and limitations for the application of the generic biosphere model. (orig.)

Biosphere models for safety assessment of radioactive waste disposal

International Nuclear Information System (INIS)

Proehl, G.; Olyslaegers, G.; Zeevaert, T.; Kanyar, B.; Bergstroem, U.; Hallberg, B.; Mobbs, S.; Chen, Q.; Kowe, R.

2004-01-01

The aim of the BioMoSA project has been to contribute in the confidence building of biosphere models, for application in performance assessments of radioactive waste disposal. The detailed objectives of this project are: development and test of practical biosphere models for application in long-term safety studies of radioactive waste disposal to different European locations, identification of features, events and processes that need to be modelled on a site-specific rather than on a generic base, comparison of the results and quantification of the variability of site-specific models developed according to the reference biosphere methodology, development of a generic biosphere tool for application in long term safety studies, comparison of results from site-specific models to those from generic one, Identification of possibilities and limitations for the application of the generic biosphere model. (orig.)

Radioactive contamination of natural and artificial materials

International Nuclear Information System (INIS)

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

1980-01-01

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

The edge artifact in the point-spread function-based PET reconstruction at different sphere-to-background ratios of radioactivity.

Science.gov (United States)

Kidera, Daisuke; Kihara, Ken; Akamatsu, Go; Mikasa, Shohei; Taniguchi, Takafumi; Tsutsui, Yuji; Takeshita, Toshiki; Maebatake, Akira; Miwa, Kenta; Sasaki, Masayuki

2016-02-01

The aim of this study was to quantitatively evaluate the edge artifacts in PET images reconstructed using the point-spread function (PSF) algorithm at different sphere-to-background ratios of radioactivity (SBRs). We used a NEMA IEC body phantom consisting of six spheres with 37, 28, 22, 17, 13 and 10 mm in inner diameter. The background was filled with (18)F solution with a radioactivity concentration of 2.65 kBq/mL. We prepared three sets of phantoms with SBRs of 16, 8, 4 and 2. The PET data were acquired for 20 min using a Biograph mCT scanner. The images were reconstructed with the baseline ordered subsets expectation maximization (OSEM) algorithm, and with the OSEM + PSF correction model (PSF). For the image reconstruction, the number of iterations ranged from one to 10. The phantom PET image analyses were performed by a visual assessment of the PET images and profiles, a contrast recovery coefficient (CRC), which is the ratio of SBR in the images to the true SBR, and the percent change in the maximum count between the OSEM and PSF images (Δ % counts). In the PSF images, the spheres with a diameter of 17 mm or larger were surrounded by a dense edge in comparison with the OSEM images. In the spheres with a diameter of 22 mm or smaller, an overshoot appeared in the center of the spheres as a sharp peak in the PSF images in low SBR. These edge artifacts were clearly observed in relation to the increase of the SBR. The overestimation of the CRC was observed in 13 mm spheres in the PSF images. In the spheres with a diameter of 17 mm or smaller, the Δ % counts increased with an increasing SBR. The Δ % counts increased to 91 % in the 10-mm sphere at the SBR of 16. The edge artifacts in the PET images reconstructed using the PSF algorithm increased with an increasing SBR. In the small spheres, the edge artifact was observed as a sharp peak at the center of spheres and could result in overestimation.

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.

Transportation accidents/incidents involving radioactive materials (1971--1991)

International Nuclear Information System (INIS)

Cashwell, C.E.; McClure, J.D.

1992-01-01

The Radioactive Materials Incident Report (RMIR) database contains information on transportation-related accidents and incidents involving radioactive materials that have occurred in the United States. The RMIR was developed at Sandia National Laboratories (SNL) to support its research and development program efforts for the US Department of Energy (DOE). This paper will address the following topics: background information on the regulations and process for reporting a hazardous materials transportation incident, overview data of radioactive materials transportation accidents and incidents, and additional information and summary data on how packagings have performed in accident conditions

U.S. port commerce in radioactive materials

International Nuclear Information System (INIS)

Marti, B.E.

1987-01-01

Much attention has focused on the movement of radioactive materials over land transport systems. On the other hand, maritime flow and associated throughput studies of such substances have been neglected. Although several peaks and troughs are evident between 1972 and 1981, radioactive tonnage moving through U.S. port facilities steadily increasing. In the ten-year period assessed, total radioactive materials handled at U.S. ports expanded by over 19,000 tons, which amounts to almost a 173 percent growth rate. The purpose of this exploratory research is threefold. First, it identifies all U.S. ports which were involved in loading or discharging radioactive materials. The major goal of the identification process is to broaden public awareness of these types of movement. Second, it classifies U.S. seaports based on the magnitude of radioactive tonnage handled. The function of the classification is to impose some order on the varied data, while at the same time categorizing large, medium, and small facilities. Finally, it seeks to verify whether or not a long term trend exists. The objective of the verification process is to ascertain if the distribution of radioactive materials handled at individual ports has remained constant. Port safety and contingency planning are clearly within the purview of coastal zone management. The results of this preliminary research should form a foundation for future studies which compare and evaluate local, state, and federal regulatory policy pertaining to port operations involving radioactive materials, including waste

Radioactive mineral occurences of Colorado and bibliography

International Nuclear Information System (INIS)

Nelson-Moore, J.L.; Collins, D.B.; Hornbaker, A.L.

1978-01-01

This two-part report provides an essentially complete listing of radioactive occurrences in Colorado, with a comprehensive bibliography and bibliographic cross-indexes. Part 1 lists approximately 3000 known radioactive occurrences with their locations and brief accounts of the geology, mineralogy, radioactivity, host rock, production data, and source of data for each. The occurrences are classified by host rock and plotted on U.S. Geological Survey 1 0 x 2 0 topographic quadrangle maps with a special 1 : 100,000-scale base map for the Uravan mineral belt. Part 2 contains the bibliography of approximately 2500 citations on radioactive mineral occurrences in the state, with cross-indexes by county, host rock, and the special categories of ''Front Range,'' ''Colorado Plateau,'' and ''thorium.'' The term ''occurrence'' as used in this report is defined as any site where the concentration of uranium or thorium is at least 0.01% or where the range of radioactivity is greater than twice the background radioactivity. All citations and occurrence data are stored on computer diskettes for easy retrieval, correction, and updating

Identification of hand motion using background subtraction method and extraction of image binary with backpropagation neural network on skeleton model

Science.gov (United States)

Fauziah; Wibowo, E. P.; Madenda, S.; Hustinawati

2018-03-01

Capturing and recording motion in human is mostly done with the aim for sports, health, animation films, criminality, and robotic applications. In this study combined background subtraction and back propagation neural network. This purpose to produce, find similarity movement. The acquisition process using 8 MP resolution camera MP4 format, duration 48 seconds, 30frame/rate. video extracted produced 1444 pieces and results hand motion identification process. Phase of image processing performed is segmentation process, feature extraction, identification. Segmentation using bakground subtraction, extracted feature basically used to distinguish between one object to another object. Feature extraction performed by using motion based morfology analysis based on 7 invariant moment producing four different classes motion: no object, hand down, hand-to-side and hands-up. Identification process used to recognize of hand movement using seven inputs. Testing and training with a variety of parameters tested, it appears that architecture provides the highest accuracy in one hundred hidden neural network. The architecture is used propagate the input value of the system implementation process into the user interface. The result of the identification of the type of the human movement has been clone to produce the highest acuracy of 98.5447%. The training process is done to get the best results.

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

Energy Technology Data Exchange (ETDEWEB)

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

1961-07-01

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

Pulse shape discrimination of plastic scintillator EJ 299-33 with radioactive sources

Science.gov (United States)

Pagano, E. V.; Chatterjee, M. B.; De Filippo, E.; Russotto, P.; Auditore, L.; Cardella, G.; Geraci, E.; Gnoffo, B.; Guazzoni, C.; Lanzalone, G.; De Luca, S.; Maiolino, C.; Martorana, N. S.; Pagano, A.; Papa, M.; Parsani, T.; Pirrone, S.; Politi, G.; Porto, F.; Quattrocchi, L.; Rizzo, F.; Trifirò, A.; Trimarchi, M.

2018-05-01

The present study has been carried out in order to investigate about the possibility of using EJ 299-33 scintillator in a multi-detector array to detect neutrons along with light charged particles. In a reaction induced by stable and exotic heavy-ions beams, where copious production of neutrons and other light charged particles occurs, discrimination with low identification threshold of these particles are of great importance. In view of this, EJ 299-33 scintillator having dimension of 3 cm × 3 cm × 3 cm backed by a photomultiplier tube was tested and used under vacuum to detect neutrons, gamma-rays and alpha particles emitted by radioactive sources. Anode pulses from the photomultiplier tube were digitized through GET electronics, recorded and stored in a data acquisition system for the purpose of an off-line analysis. The measurements, under vacuum and low background conditions, show good pulse shape discrimination properties characterized by low identification threshold for neutrons, gamma-rays and alpha particles. The Figures of Merit for neutron-gamma and alpha particles-gamma discriminations have been evaluated together with the energy resolution for gamma-ray and alpha particles.

On the variation of environmental radioactivity in Dae-Jeon area (Jan. 1977-Dec. 1981)

International Nuclear Information System (INIS)

Oh, H.P.; Oh, H.J.

1982-01-01

This study concerns with gamma-ray exposure in natural background radiation and radioactivities in the air-borne dust, the fall-out, and the rain-out which had been measured in Dae-Jeon area during the period of five years from Jan. 1, 1977 to Dec. 31, 1981. The special survey results from the 22th, 23th, and 24th nuclear explosion tests carred out by Red China are included in this paper. The results of these measurements are as follows: 1. The average value of natural background radiation in the laboratory 20.69μR/hr, and it is found that the natural background was not affected by the nuclear explosion tests. 2. The average value of radioactivity in the air-borne dust is 0.11pμci/cc, and the maximum value of radioactivity during the period is 0.47pμci/cc. 3. The average value of radioactivity of the fall-out is 0.09mci/km 2 -10d, and the maximum value of radioactivity during the period is 0.84mci/km 2 -10d. 4. The average value of radioactivity in the rain-out is 0.45 x 10 -8 μci/cc, and the maximum value of radioactivity during the period is 1.97 x 10 -8 μci/cc. (Author)

Radioactive-nuclide decay data in science and technology

International Nuclear Information System (INIS)

Reich, C.W.; Helmer, R.G.

1975-01-01

The scope of ENDF/B has recently been expanded to include radioactive-nuclide decay data. In this paper, the content and organization of the decay data which are included in ENDF/B are presented and discussed. The application of decay data in a wide variety of nuclear-related activities is illustrated by a number of examples. Two items pointed up by the ENDF/B decay-data compilation effort are treated: the identification of deficiencies in the data; and the importance of a radioactive-nuclide metrology effort oriented toward supplying these needs in a systematic fashion. 3 figures, 2 tables

Radioactive-nuclide decay data in science and technology

International Nuclear Information System (INIS)

Reich, C.W.; Helmer, R.G.

1975-01-01

The scope of ENDF/B has recently been expanded to include radioactive-nuclide decay data. In this paper, the content and organization of the decay data which are included in ENDF/B are presented and discussed. The application of decay data in a wide variety of nuclear-related activities is illustrated by a number of examples. Two items pointed up by the ENDF/B decay-data compilation effort are treated: the identification of deficiencies in the data; and the importance of a radioactive-nuclide metrology effort oriented toward supplying these needs in a systematic fashion. (3 figures, 1 table)

Safety in transport and storage of radioactive materials

International Nuclear Information System (INIS)

Mezrahi, A.; Xavier, A.M.

1987-01-01

The increasing utilization of radioisotopes in Industrial, Medical and Research Facilities as well as the processing of Nuclear Materials involve transport activities in a routine basis. The present work has the following main objectives: I) the identification of the safety aspects related to handling, transport and storage of radioactive materials; II) the orientation of the personnel responsible for the radiological safety of Radioactive Installations viewing the elaboration and implementation of procedures to minimize accidents; III) the report of case-examples of accidents that have occured in Brazil due to non-compliance with Transport Regulations. (author) [pt

Contamination due to radioactive materials

International Nuclear Information System (INIS)

Woodhead, D.S.

1984-01-01

The peaceful exploitation of radioactivity and the expansion of the nuclear power programme ensure that the disposal of radioactive wastes will cause contamination of the marine environment in the foreseeable future. The exposure of marine organisms to radioactivity from wastes has been studied in depth and related to exposure to natural background radiation. Concentrations of natural radionuclides and those from marine waste disposal have been measured at various stations in the oceans and seas around the world. The fate of radionuclides at four representative sites has been studied and the concentrations of radionuclides in oysters, porphyra, plaice in the Windscale discharge area have been measured. The extent of human exposure, particularly with reference to seafood consumption in local fishing communities, has been assessed. Effects of radiation on developing fish embryos and eggs and genetic radiation effects in aquatic organisms has been studied. The above studies reveal that the controls applied to the discharge of radioactive wastes to limit hazards to humans also provide adequate protection for populations of marine organisms. (U.K.)

Technology developments for the identification, mapping, characterisation and segregation of radioactive contamination

International Nuclear Information System (INIS)

Smith, R.; Beddow, H.; Adsley, T.; Pearman, I.; Sweeney, A.; Smith, W.; Blythe, M.; Davies, M.

2015-01-01

The history of activities in the UK dealing with radioactive materials has led to many sites being contaminated by various radioactive isotopes. These come from a number of industries and educational activities such as nuclear power development, luminising works, research facilities and the oil and gas industry. These isotopes include radium, lead, polonium, thorium, uranium and trans-uranic elements. To remediate these sites it is essential that the isotopes are identified and quantified to enable the appropriate strategy to be developed and the most cost-efficient decontamination or sorting processes to be implemented. Nuvia has developed and implemented a suite of technologies to map the location of and to recover and process radioactive materials during remedial operations. These have been developed over a number of years to meet the requirements for both an effective remediation operation and to comply with the relevant regulatory requirements. This paper will describe these developments and give examples of their deployment in a diverse range of situations.(authors)

Issues and trends in radioactive waste management in Turkey

International Nuclear Information System (INIS)

Osmanlioglu, A.E.

2002-01-01

This paper focuses on issues associated with the waste management aspects of Turkey. Predisposal management of radioactive wastes covers a broad range of activities. This also includes waste identification, characterization and conditioning. Experience gained over years shows that current predisposal waste management practices are well advanced. The paper concludes these activities based on experience gained by CWPSF (CNAEM Waste Processing and Storage Facility) and includes issues and trends in radioactive waste management. In addition general information is presented on ongoing national projects and IAEA research projects on various issues of waste management. (author)

MEGA: A Low-Background Radiation Detector

International Nuclear Information System (INIS)

Kazkaz, Kareem; Aalseth, Craig E.; Hossbach, Todd W.; Gehman, Victor M.; Kephart, Jeremy; Miley, Harry S.

2004-01-01

The multiple-element gamma assay (MEGA) is a low-background detector designed to support environmental monitoring and national security applications. MEGA also demonstrates technology needed or Majorana, a next generation neutrino mass experiment. It will also exploit multicoincidence signatures to identify specific radioactive isotopes. MEGA is expected to begin testing in late 2003 for eventual installation at the Waste Isolation Plant, Carlsbad, NM

Estimation of thyroid gland state of voles natural populations from increased radioactive background territories

Energy Technology Data Exchange (ETDEWEB)

Raskosha, O.; Ermakova, O.; Kaneva, A. [Institute of Biology of Komi Scientific Center, Ural Division of Russian Academy of Science (Russian Federation)

2014-07-01

Investigation of effects caused in biological objects by chronic low-intensity radiation in their natural habitats is one of the most important problems of modern radioecology. The aim of our work - complex estimation of state of thyroid gland of voles inhabiting increased radioactive background territories. We investigated tundra voles (Microtus oeconomus Pall.) that were sampled at different stages of population cycle from the experimental and the control sites in the Uhta region of the Komi Republic, Russia. Experimental site contamination resulted from commercial extraction od radium between the 1930's and 1950's. Irradiation exposure dose at the site was 50-2000 mR/h (at the control site 10-15 mR/h). Complex estimation of thyroid was made by histological, morpho-metrical, radioimmunological and cytogenetic methods. Results showed high sensitivity of thyroid gland of tundra voles from chronically irradiated natural populations. We found reliable changes in morphological features of thyroid, in the level of thyroidal hormones and increased frequency of cells with micro-nucleuses in animals sampled from the experimental site as compared with the control ones. It was also showed, that chronic exposure of ionizing irradiation at the same range of absorbed doses can cause different effects in animals depending on sex, age and the stage of population cycle. This confirms the need of including these biological factors to analysis of low doses effects in the natural populations during radioecological studies. Investigations were supported by RFBR grants No. 13-04-01750? and No. 13-04-90351-RBUa. Document available in abstract form only. (authors)

Measurement of gross beta radioactivity in high-level liquid waste

International Nuclear Information System (INIS)

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

1992-01-01

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

Background gamma radiation mapping in forest ecosystem of Bangladesh: A study on the radioactivity distribution in the national reserve forest of Gazipur

Directory of Open Access Journals (Sweden)

Sheikh Shariful Islam

2017-01-01

Full Text Available Natural and artificial radioactivity appears to be different in different geological regions. Moreover, the radionuclides may migrate to the deeper region of the earth after deposition, and the depth profile of a radionuclide reveals information on the rate of migration. Countrywide background gamma radiation mapping program has been initiated in Bangladesh by dividing the whole country primarily into ~2 km × ~2 km (1' ×1' in Global Positioning System scale systematic square grids to formulate the radioactivity profile. About 28 km × 30 km area of forest land of Gazipur district called the “BhawalGahr” including the Bhawal National Park was selected for sampling. Soil samples from 0 to 5 cm, 5 to 15, cm and 15 to 30 cm depth were collected from the 27 grid node points of the square grids. A total of 81 samples were collected for the current study. The samples were subjected to elemental and radioactivity analyses. The elements found in the samples were in decreasing order as Fe>K>Ti>Ca>Co>Mn>V>Cr>Ni. The calculated activity concentration of natural radionuclides 226Ra, 232Th, and 40K for surface soil samples (0–5 cm depth ranged from 44.2 ± 5.7 to 84.5 ± 10.2 Bq/kg, 75.6 ± 8.3 to 126.5 ± 8.3 Bq/kg, and 263.7 ± 92.3 to 606.7 ± 107.9 Bq/kg, respectively and there is no significant variation for other depths. The radiological hazard indices such as radium equivalent activity, radiation external hazard index, absorbed dose rate, and annual effective dose were also estimated from the calculated values of activity concentrations.

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).

New Advanced Source Identification Algorithm (ASIA-NEW) for radiation monitors with plastic detectors

Energy Technology Data Exchange (ETDEWEB)

Stavrov, Andrei; Yamamoto, Eugene [Rapiscan Systems, Inc., 14000 Mead Street, Longmont, CO, 80504 (United States)

2015-07-01

Radiation Portal Monitors (RPM) with plastic detectors represent the main instruments used for primary border (customs) radiation control. RPM are widely used because they are simple, reliable, relatively inexpensive and have a high sensitivity. However, experience using the RPM in various countries has revealed the systems have some grave shortcomings. There is a dramatic decrease of the probability of detection of radioactive sources under high suppression of the natural gamma background (radiation control of heavy cargoes, containers and, especially, trains). NORM (Naturally Occurring Radioactive Material) existing in objects under control trigger the so-called 'nuisance alarms', requiring a secondary inspection for source verification. At a number of sites, the rate of such alarms is so high it significantly complicates the work of customs and border officers. This paper presents a brief description of new variant of algorithm ASIA-New (New Advanced Source Identification Algorithm), which was developed by the authors and based on some experimental test results. It also demonstrates results of different tests and the capability of a new system to overcome the shortcomings stated above. New electronics and ASIA-New enables RPM to detect radioactive sources under a high background suppression (tested at 15-30%) and to verify the detected NORM (KCl) and the artificial isotopes (Co-57, Ba-133 and other). New variant of ASIA is based on physical principles and does not require a lot of special tests to attain statistical data for its parameters. That is why this system can be easily installed into any RPM with plastic detectors. This algorithm was tested for 1,395 passages of different transports (cars, trucks and trailers) without radioactive sources. It also was tested for 4,015 passages of these transports with radioactive sources of different activity (Co-57, Ba-133, Cs-137, Co-60, Ra-226, Th-232) and these sources masked by NORM (K-40) as well

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.)

ttH multilepton: background estimation

CERN Document Server

Angelidakis, Stylianos; The ATLAS collaboration

2018-01-01

The slides present the background encountered in the ttH->Multilepton search and describe the data-driven techniques used for the determination of the dominant non-prompt-lepton contamination as well as the contribution of electron charge mis-identification.

A survey of the environmental radioactivity in the east sea related to the Russian ocean dumping of the radioactive waste

International Nuclear Information System (INIS)

Kim, Kyehoon; Kim, Changkyu; Lee, Mosung

1994-01-01

From October 24 - December 30, 1993 a joint survey by the Office of Fisheries, Korea Institute of Nuclear Safety, Korea Ocean Research and Development Institute, and several other governmental institutes which was supervised by Ministry of Science and Technology was carried out to investigate present marine environmental radioactivity of the East Sea where former USSR and Russia had dumped radioactive waste since 1957. Exposure rate was measured and the radioactivity of seawater, both surface and deep water, bottom sediment, fish, and planktonic organisms from the areas around the dumping sites and the East Sae were analyzed. Results showed that the radioactivities of Cs-137 in the sea water from dumping sites were less than 0.0038 Bq/L, which was similar to the background level of the East Sea. The radioactivity level of fish and bottom sediment from dumping sites also did not increased. A detailed Ocean Environmental Monitoring Plan, however, should be established and the monitoring must be carried out continuously to protect people from potential radioactive hazards

Radioactive waste management: An international perspective

International Nuclear Information System (INIS)

Chan, C.Y.

1992-01-01

Scientists, governments, and the general public have devoted considerable attention to the subject of radioactive waste over the past 35 years. The subject has gained even more attention of late, owing to heightened awareness of environmental protection. Potential transboundary effects have further added to this interest, which today extends beyond local domains to regional and global levels. Almost all of the IAEA's Member States generate some radioactive wastes. The type of waste they produce varies, however, as do the quantities, which range from a few grams to several hundred tonnes of wastes per year. This article will summarize the status of waste management and disposal activities in IAEA Member States as well as providing a brief background on what radioactive waste is, where it comes from, and how it is managed

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.

Natural occurring radioactive substances. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

Emara, A E [National Center for radiation Research and Technology Atomic Energy Authority, Cairo (Egypt)

1996-03-01

Naturally occurring radioactive substances produced by cosmic rays of those of terrestrial origin are surveyed. The different radioactive decay series are discussed. Special emphasis is given to the element radium as regards its properties and distribution in different environmental samples. The properties of naturally occurring k-40 and its distribution in different natural media are also outlined. Induced radionuclides which are formed as a result of the interaction of cosmic rays with the constituents of the atmosphere are mentioned. In this respect the intensity of natural background radiation and the dose at different locations and levels is surveyed. Some regions of exceptionally high radioactivity which result in high exposure rates are mentioned. Monazite deposits and water springs are mentioned in some detail. The Oklo phenomenon as a natural reactor is also discussed. 8 tabs.

Natural occurring radioactive substances. Vol. 1

International Nuclear Information System (INIS)

Emara, A.E.

1996-01-01

Naturally occurring radioactive substances produced by cosmic rays of those of terrestrial origin are surveyed. The different radioactive decay series are discussed. Special emphasis is given to the element radium as regards its properties and distribution in different environmental samples. The properties of naturally occurring k-40 and its distribution in different natural media are also outlined. Induced radionuclides which are formed as a result of the interaction of cosmic rays with the constituents of the atmosphere are mentioned. In this respect the intensity of natural background radiation and the dose at different locations and levels is surveyed. Some regions of exceptionally high radioactivity which result in high exposure rates are mentioned. Monazite deposits and water springs are mentioned in some detail. The Oklo phenomenon as a natural reactor is also discussed. 8 tabs

Thule-2007 - Investigation of radioactive pollution on land

International Nuclear Information System (INIS)

Nielsen, Sven Poul; Roos, P.

2011-10-01

A survey of radioactive pollution on land in the Thule area from an airplane accident in 1968 was carried out during 2007 and 2008. The results show levels of plutonium in soil at Narsaarsuk ranging from background values around 39 Bq m -2 up to levels of 1.7 MBq m -2 . Local sub-areas of sizes ranging from a few hundred to a few thousands of square metres show elevated levels above 10 kBq m -2 of plutonium. Based on geostatistical analysis, the total amount of plutonium in soil at Narsaarsuk is estimated at 270 GBq (100 g). Investigations were carried out at Narsaarsuk to determine the occurrence of radioactive particles in air. This involved collection of airborne particles with an air sampler, collection of airborne particles on sticky foils, collection of rain samples and collection of particles that could be resuspended by wind from the soil surface to the air. Small amounts of plutonium were found in air and rain samples, but the derived concentrations in air were very low corresponding to typical back-ground levels in Europe in the range 1-10 nBq m -3 . A few small particles were found on the soil surface with activities up to 1000 Bq plutonium but the air and rain samples showed no sign of resuspension of such particles from the soil. Local areas with elevated levels of radioactive pollution in soil were found at Kap Atholl and Groennedal 15-20 km south of Narsaarsuk. Here the levels were lower than those in the Narsaarsuk area but clearly above background. It was not possible within this project to carry out a systematic survey of the entire region. Hence, it cannot be excluded that there may be more local sub-areas than those identified with elevated levels of radioactive pollution in soil. Screening surveys were carried out at Thule Air Base, Moriusaq, Saunders Island and Wolstenholme Island. The results showed background levels in soil at these locations which means that no sign of radioactive pollution from the accident was found at these locations

Thule-2007 - Investigation of radioactive pollution on land

Energy Technology Data Exchange (ETDEWEB)

Nielsen, Sven Poul; Roos, P.

2011-10-15

A survey of radioactive pollution on land in the Thule area from an airplane accident in 1968 was carried out during 2007 and 2008. The results show levels of plutonium in soil at Narsaarsuk ranging from background values around 39 Bq m-2 up to levels of 1.7 MBq m-2. Local sub-areas of sizes ranging from a few hundred to a few thousands of square metres show elevated levels above 10 kBq m-2 of plutonium. Based on geostatistical analysis, the total amount of plutonium in soil at Narsaarsuk is estimated at 270 GBq (100 g). Investigations were carried out at Narsaarsuk to determine the occurrence of radioactive particles in air. This involved collection of airborne particles with an air sampler, collection of airborne particles on sticky foils, collection of rain samples and collection of particles that could be resuspended by wind from the soil surface to the air. Small amounts of plutonium were found in air and rain samples, but the derived concentrations in air were very low corresponding to typical back-ground levels in Europe in the range 1-10 nBq m-3. A few small particles were found on the soil surface with activities up to 1000 Bq plutonium but the air and rain samples showed no sign of resuspension of such particles from the soil. Local areas with elevated levels of radioactive pollution in soil were found at Kap Atholl and Groennedal 15-20 km south of Narsaarsuk. Here the levels were lower than those in the Narsaarsuk area but clearly above background. It was not possible within this project to carry out a systematic survey of the entire region. Hence, it cannot be excluded that there may be more local sub-areas than those identified with elevated levels of radioactive pollution in soil. Screening surveys were carried out at Thule Air Base, Moriusaq, Saunders Island and Wolstenholme Island. The results showed background levels in soil at these locations which means that no sign of radioactive pollution from the accident was found at these locations. (Author)

The problems and suggestions on supervision of the radioactive material transport

International Nuclear Information System (INIS)

Cao Fangfang; Que Ji; Zhang Min; Pan Yuting

2012-01-01

The developing background and importance of the rules on supervision of the radioactive material transport are discussed in the paper. Based on the existing problems found in the process of implementing the rule 'Regulations for the safe transport of Radioactive Material', some countermeasures are proposed. (authors)

Neutron- and muon-induced background in underground physics experiments

International Nuclear Information System (INIS)

Kudryavtsev, V.A.; Tomasello, V.; Pandola, L.

2008-01-01

Background induced by neutrons in deep underground laboratories is a critical issue for all experiments looking for rare events, such as dark matter interactions or neutrinoless ββ decay. Neutrons can be produced either by natural radioactivity, via spontaneous fission or (α, n) reactions, or by interactions initiated by high-energy cosmic rays. In all underground experiments, Monte Carlo simulations of neutron background play a crucial role for the evaluation of the total background rate and for the optimization of rejection strategies. The Monte Carlo methods that are commonly employed to evaluate neutron-induced background and to optimize the experimental setup, are reviewed and discussed. Focus is given to the issue of reliability of Monte Carlo background estimates. (orig.)

Neutron- and muon-induced background in underground physics experiments

Energy Technology Data Exchange (ETDEWEB)

Kudryavtsev, V.A.; Tomasello, V. [University of Sheffield, Department of Physics and Astronomy, Sheffield (United Kingdom); Pandola, L. [Laboratori Nazionali del Gran Sasso, INFN, Assergi (Italy)

2008-05-15

Background induced by neutrons in deep underground laboratories is a critical issue for all experiments looking for rare events, such as dark matter interactions or neutrinoless {beta}{beta} decay. Neutrons can be produced either by natural radioactivity, via spontaneous fission or ({alpha}, n) reactions, or by interactions initiated by high-energy cosmic rays. In all underground experiments, Monte Carlo simulations of neutron background play a crucial role for the evaluation of the total background rate and for the optimization of rejection strategies. The Monte Carlo methods that are commonly employed to evaluate neutron-induced background and to optimize the experimental setup, are reviewed and discussed. Focus is given to the issue of reliability of Monte Carlo background estimates. (orig.)

Overview of the solid radioactive waste management programme for Cernavoda NPP

International Nuclear Information System (INIS)

Raducea, D.

2001-01-01

The wastes generated from nuclear power plants have a very large diversity, and can be grouped into non-radioactive and radioactive wastes. These two types are manipulated completely different ways from each other. Among radioactive wastes, solid radioactive wastes are important, because of their diversity, their method of treatment and of their volume compared to the others types. The strategy for their treatment and characterisation has a dynamic character and allows modification after the identification of new solutions at the international level, or after the production of new waste types. The Radioactive Waste Management concept for Cernavoda NPP established the general approach required for the collection, handling, conditioning and storage of radioactive wastes, while maintaining acceptable levels of safety for workers, members of the public and the environment. The radioactive waste management programme has the following major characteristics: plant operation at all times ensures that radioactive wastes are minimised; procedures are established to ensure that radiation doses to operating staff and members of the public are in accordance with ALARA and contamination from collection, transportation and storage of wastes are eliminated; all staff is trained and qualified to carry out their responsibilities. This presentation does not address the management of spent fuel, contaminated heavy water and the disposal of the solid radioactive wastes.(author)

The identification and nature of bound exciton I-line PL systems in ZnO

Energy Technology Data Exchange (ETDEWEB)

Johnston, K. [PH Dept, CERN, 1211-Geneva (Switzerland); Cullen, J.; Henry, M. O.; McGlynn, Enda [School of Physics Sciences, Dublin City University, Dublin 9 (Ireland); Khawaga, Rehab I. [Department of Chemistry, College of Art and Science, American University of Sharjah (AUS) (United Arab Emirates)

2013-12-04

The chemical identification of donor bound excitons in ZnO has been studied using radioactive ions. Implantations of {sup 117}Ag - which decays to radioactive Cd and In - have enabled the identification of the I{sub 2} optical feature as being the ionized donor counterpart of I{sub 9}, one of the most prominent optical features in the photoluminescence spectrum of ZnO. Both of these lines are consistent with In occupying a Zn site.

Measurement of indoor background ionizing radiation in some ...

African Journals Online (AJOL)

Certain types of building materials are known to be radioactive. Exposure to indoor ionizing radiation like exposure to any other type of ionizing radiation results in critical health challenges. Measurement of the background ionizing radiation profile within the Chemistry Research Laboratory and Physics Laboratory III all of ...

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.)

Double beta radioactivity and physics of the neutrino. Study of the background noise at 3 MeV in the search of 100Mo beta beta decay

International Nuclear Information System (INIS)

Piquemal, F.

1994-05-01

Double beta decay without neutrino emission provides a test of the mass and nature of neutrinos (Majorana or Dirac). Experimental proof would be the observation of a peak at the transition energy in the spectrum of the two emitted electrons. The expected half-life of the process is extremely long (about 10 25 years for 100 Mo). So, being thus, it is very important to get a good knowledge of the origins and contributions of background noise in the region where the signal could occur. The main origins of the background noise in the region where the signal could occur. The main origins of the background noise are found to be e + - e - pairs induced by heavy energy gamma rays. These gamma rays follow the thermal neutron capture by the components of the detector. Another factor in the production of background noise is natural radio-activity. For example, the presence of Radon in the laboratory has been observed to produce deposits of 214 Bi on the sides of the detector. Data taken with the NEMO 2 prototype and an enriched molybdenum source foil indicates that the background limit reached is of the order of 1 event per year in the 3 MeV region. Results of this work have proven the necessity to have a magnetic field in NEMO 3 in order to reject e + - e - pairs. (author)

Savannah River Site Experiences in In Situ Field Measurements of Radioactive Materials

International Nuclear Information System (INIS)

Moore, F.S.

1999-01-01

This paper discusses some of the field gamma-ray measurements made at the Savannah River Site, the equipment used for the measurements, and lessons learned during in situ identification and characterization of radioactive materials

Investigation of natural radioactivity level of the waters in Inner Mongolia

International Nuclear Information System (INIS)

Du Xuelin; Li Wenyuan; Fu Su

1993-01-01

The authors reports the investigation results of natural radioactivity level in rivers, lakes, reservoirs, springs, wells and tap water in Inner Mongolia Autonomous Region. There were totally 326 samples collected from 178 measuring points. The results show that the radioactivity level of varied water bodies of the region was within normal natural background

Top soil radioactivity assessment in a high natural radiation background area: the case of Vinaninkarena, Antsirabe-Madagascar.

Science.gov (United States)

Rabesiranana, Naivo; Rasolonirina, Martin; Terina, Franck; Solonjara, Asivelo F; Andriambololona, Raoelina

2008-11-01

The village of Vinaninkarena, Antsirabe, Madagascar (47 degrees 02'40''E, 19 degrees 57'17''S) is located in a high natural radioactivity area. In order to evaluate the natural radionuclide content in soil, sampling was done on-site by the transect method (85 soil samples) and off-site through transects across and beyond the region (up to a range of 100 km), to determine the natural radioactivity variation within vs. outside the region, and to detect significant differences, taking into account spatial variability.

RADIOACTIVE MATERIALS SENSORS

International Nuclear Information System (INIS)

Mayo, Robert M.; Stephens, Daniel L.

2009-01-01

Providing technical means to detect, prevent, and reverse the threat of potential illicit use of radiological or nuclear materials is among the greatest challenges facing contemporary science and technology. In this short article, we provide brief description and overview of the state-of-the-art in sensor development for the detection of radioactive materials, as well as an identification of the technical needs and challenges faced by the detection community. We begin with a discussion of gamma-ray and neutron detectors and spectrometers, followed by a description of imaging sensors, active interrogation, and materials development, before closing with a brief discussion of the unique challenges posed in fielding sensor systems.

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

International Nuclear Information System (INIS)

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

2016-06-01

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

Radioactive ion beams and techniques for solid state research

International Nuclear Information System (INIS)

Correia, J.G.

1998-01-01

In this paper we review the most recent and new applications of solid state characterization techniques using radioactive ion beams. For such type ofresearch, high yields of chemically clean ion beams of radioactive isotopesare needed which are provided by the on-line coupling of high resolution isotope separators to particle accelerators, such as the isotope separator on-line (ISOLDE) facility at CERN. These new experiments are performed by an increasing number of solid state groups. They combine nuclear spectroscopic techniques such as Moessbauer, perturbed angular correlations (PAC) and emission channeling with the traditional non-radioactive techniques liked deep level transient spectroscopy (DLTS) and Hall effect measurements. Recently isotopes of elements, not available before, were successfully used in new PAC experiments, and the first photoluminescence (PL) measurements, where the element transmutation plays the essential role on the PL peak identification, have been performed. The scope of applications of radioactive ion beams for research in solid state physics will be enlarged in the near future, with the installation at ISOLDE of a post-accelerator device providing radioactive beams with energies ranging from a few keV up to a few MeV. (orig.)

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

System and Experiences in the Area of Radioactive Material Seizure Assurance

International Nuclear Information System (INIS)

Svoboda, K.; Podlaha, K.; Sir, D.

2005-01-01

In recent years, a number of radioactive seizures have been increased (i.e. the materials that contain one or more radionuclides and their activities from the point of view of radiation protection are not negligible). This is mainly due to newly installed technical equipment that monitors metal scrap resp. communal waste during its entry to metallurgical plants and iron works resp. incinerators or waste dumps. In the Nuclear research Institute Rez plc. (NRI Rez) was established a working group which provides, among other activities, full system of radioactive material seizure assurance. Part of this service contents also transport, storage, treatment, conditioning and disposal of the seizured radioactive source. This service was firstly established for communal waste dump, but other organizations can take advantage of this service not only for the seizures in communal waste dumps. The system of radioactive material seizure assurance is consisted of the following parts: (1) seizure on stationary detection system; (2) 24 hours emergency service of the working group; (3) event classification, detailed counting a tracking of radioactive source; (4) found radioactive source transport to NRI Rez for storage; (5) radioactive source characterization; (6) seizure evaluation and protocol providing; (7) State Office for Nuclear Safety (SONS) decree about next procedure. Stationary detection system ( detection gate ) is usually installed at the entry to dumps area, metallurgical plants, iron works etc. The detection gate traces changes of vehicle dose rate comparing to the average background by vehicle measurement. If the vehicle dose rate is significantly higher then the average background (usual alarm level is 10-30% above background), the vehicle is postponed by the gate operator and put aside on the determined place. Seizure is announced to the police of the Czech republic and to the SONS. Typical examples of the seizured radionuclide sources are: military, devices coated

International measures needed to protect metal recycling facilities from radioactive materials

International Nuclear Information System (INIS)

Mattia, M.; Wiener, R.

1999-01-01

In almost every major city and region of every country, there is a recycling facility that is designed to process or consume scrap metal. These same countries will probably have widespread applications of radioactive materials and radiation generating equipment. This material and equipment will have metal as a primary component of its housing or instrumentation. It is this metal that will cause these sources of radioactivity, when lost, stolen or mishandled, to be taken to a metal recycling facility to be sold for the value of the metal. This is the problem that has faced scrap recycling facilities for many years. The recycling industry has spent millions of dollars for installation of radiation monitors and training in identification of radioactive material. It has expended millions more for the disposal of radioactive material that has mistakenly entered these facilities. Action must be taken to prevent this material from entering the conventional recycling process. There are more than 2,300 known incidents of radioactive material found in recycled metal scrap. Worldwide, more than 50 smeltings of radioactive sources have been confirmed. Seven fatal accidents involving uncontrolled radioactive material have also been documented. Hazardous exposures to radioactive material have plagued not just the workers at metal recycling facilities. The families of these workers, including their children, have been exposed to potentially harmful levels of radioactivity. The threat from this material does not stop there. Radioactive material that is not caught at recycling facilities can be melted and the radioactivity has been found in construction materials used to build homes, as well as shovels, fencing material, and furniture offered for sale to the general public. The time has come for the international community to address the issue of the uncontrolled sources of radioactive material. The following are the key points that must be addressed. (i) Identification of sources

Are mushrooms radioactive?

International Nuclear Information System (INIS)

Randa, Z.; Benada, J.; Singert, M.; Horyna, J.

1988-01-01

Tabulated is the content of 137 Cs in dry matter of higher mushrooms collected in the years 1986 to 1987. The radioactive level of mushrooms collected in Czechoslovakia such as Boletus badius and B. chrysenteron reached 20 to 50 kBq/kg of dry matter. The individual dose at mean consumption of these mushrooms was estimated at 0.2 to 0.3 mSv/year which amounted to 20 to 30% of the dose from the natural background. (J.B.). 1 tab

Environmental pathways of radioactivity to man

International Nuclear Information System (INIS)

Johns, T.F.

1979-12-01

The report reviews and discusses the environmental pathways by which radioactive materials can lead to the irradiation of man, in a way that should be understood by non-specialists who have neither the time nor the knowledge to study all of the relevant literature on this subject. The role of these environmental pathways in the general structure of radiological protection is considered, and the various mechanisms which lead to the dispersion or re-concentration of radioactive materials are discussed at some length. Particular groups of radionuclides from the nuclear power industry are considered in some detail. Similarly the question of the corresponding pathways from naturally-occurring radioactive materials is covered. The doses to animals and plants resulting from the nuclear industry are examined, and it is concluded that there is no reason to expect that these doses will lead to significant harm. Finally a summary is presented, and it is noted that it has been possible to obtain a very extensive knowledge of the behaviour of radionuclides in the environment only because of the extreme sensitivity of the techniques available for their detection, identification and assay. As a result a fund of knowledge has been built up about the behaviour of radioactive materials in the environment which is far more extensive than our knowledge of the behaviour of many highly toxic chemicals which are also discharged into the environment. (UK)

Sampling airborne radioactivity

International Nuclear Information System (INIS)

Cohen, B.S.

1988-01-01

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

Research on near-surface disposal of very low level radioactive waste

International Nuclear Information System (INIS)

Wang Shaowei; Yue Huiguo; Hou Jie; Chen Haiying; Zuo Rui; Wang Jinsheng

2012-01-01

Radioactive waste disposal is one of the most sensitive environmental problems to control and solve. As the arriving of decommissioning of early period nuclear facilities in China, large amounts of very low level radioactive waste will be produced inevitably. The domestic and abroad definitions about very low level radioactive waste and its disposal were introduced, and then siting principles of near-surface disposal of very low level radioactive waste were discussed. The near- surface disposal siting methods of very low level radioactive waste were analyzed from natural and geographical conditions assessment, geological conditions analysis, hydrogeological conditions analysis, geological hazard assessment and radioactive background investigation; the near-surface disposal sites'natural barriers of very low level radioactive waste were analyzed from the crustal structure and physico-chemical characteristics, the dynamics characteristics of groundwater, the radionuclide adsorption characteristics of natural barriers and so on; the near-surface disposal sites' engineered barriers of very low level radioactive waste were analyzed from the repository design, the repository barrier materials selection and so on. Finally, the improving direction of very low level radioactive waste disposal was proposed. (authors)

Rain-Induced Increase in Background Radiation Detected by Radiation Portal Monitors

Energy Technology Data Exchange (ETDEWEB)

Hausladen, Paul [ORNL; Blessinger, Christopher S [ORNL; Guzzardo, Tyler [ORNL; Livesay, Jake [ORNL

2012-07-01

A complete understanding of both the steady state and transient background measured by Radiation Portal Monitors (RPMs) is essential to predictable system performance, as well as maximization of detection sensitivity. To facilitate this understanding, a test bed for the study of natural background in RPMs has been established at the Oak Ridge National Laboratory. This work was performed in support of the Second Line of Defense Program's mission to detect the illicit movement of nuclear material. In the present work, transient increases in gamma ray counting rates in RPMs due to rain are investigated. The increase in background activity associated with rain, which has been well documented in the field of environmental radioactivity, originates from the atmospheric deposition of two radioactive daughters of radon-222, namely lead-214 and bismuth-214 (henceforth {sup 222}Rn, {sup 214}Pb and {sup 214}Bi). In this study, rainfall rates recorded by a co-located weather station are compared with RPM count rates and High Purity Germanium spectra. The data verifies these radionuclides are responsible for the dominant transient natural background fluctuations in RPMs. Effects on system performance and potential mitigation strategies are discussed.

Marine sediments as a radioactive pollution repository in the world

International Nuclear Information System (INIS)

Navarrete, J.M.; Mueller, G.; Zuniga, M.A.; Camacho, M.; Espinosa, G.; Golzarri, J.I.

2014-01-01

During a time period little longer than 60 years, it has been created a radioactive pollution background over the natural one, which started in 1945 and it has been growing up since then, due to several nuclear tests, minor nuclear reactors failure and four major accidents: Wind Scale, Three Mile Island, Chernobyl and Fukushima. This radioactive polluting background can be easily detected through 137 Cs fission product, which by the effect of wind, river currents and rain has been accumulated in marine sediments, mainly because sea represents about 80 % of earth's surface. Since energy demand has been growing up with no interruption during last two centuries, and nuclear energy seems to be the largest available source, it is very likely a great expansion of nuclear energy during twenty-first century. So, this paper presents results obtained in strategic points of the two large littorals in Mexico: Gulf and Pacific Ocean, as an attempt to establish there some figure to evaluate the present radioactive pollution. An adequate figure to do it, seems to be the quotient of activity per gram of 137 Cs in marine sediments (Bq 137 Cs/g), divided by activity per gram of 40 K natural radioactivity (Bq 40 K/g). When this result is multiplied by 100 the percentage of polluting radioactivity ( 137 Cs) related to natural radioactivity ( 40 K) is obtained. This percentage seems to be useful to evaluate the importance of radioactive pollution from 4 points of view: a) calculate the extent of already radioactive pollution present in the seas of world; b) avoid the panic in case of nuclear accidents, c) what will be the growing up rate in the future; d) if it is possible to keep one decreasing rate at same decaying rate of 137 Cs (t 1/2 = 30.07 years), since from 1945, starting time of radioactive pollution, it has decayed only about 2.2 half lives. (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.)

Identification of simulated microcalcifications in white noise and mammographic backgrounds

International Nuclear Information System (INIS)

Reiser, Ingrid; Nishikawa, Robert M.

2006-01-01

This work investigates human performance in discriminating between differently shaped simulated microcalcifications embedded in white noise or mammographic backgrounds. Human performance was determined through two alternative forced-choice (2-AFC) experiments. The signals used were computer-generated simple shapes that were designed such that they had equal signal energy. This assured equal detectability. For experiments involving mammographic backgrounds, signals were blurred to account for the imaging system modulation transfer function (MTF). White noise backgrounds were computer generated; anatomic background patches were extracted from normal mammograms. We compared human performance levels as a function of signal energy in the expected difference template. In the discrimination task, the expected difference template is the difference between the two signals shown. In white noise backgrounds, human performance in the discrimination task was degraded compared to the detection task. In mammographic backgrounds, human performance in the discrimination task exceeded that of the detection task. This indicates that human observers do not follow the optimum decision strategy of correlating the expected signal template with the image. Human observer performance was qualitatively reproduced by non-prewhitening with eye filter (NPWE) model observer calculations, in which spatial uncertainty was explicitly included by shifting the locations of the expected difference templates. The results indicate that human strategy in the discrimination task may be to match individual signal templates with the image individually, rather than to perform template matching between the expected difference template and the image

Report to Congress: 1995 Annual report on low-level radioactive waste management progress

International Nuclear Information System (INIS)

1996-06-01

This report is prepared in response to the Low-Level Radioactive Waste Policy Act, Public Law 96-573, 1980, as amended by the Low-Level Radioactive Waste Policy Amendments Act of 1985, Public Law 99-240. The report summarizes the progress of states and compact regions during calendar year 1995 in establishing new disposal facilities for commercially-generated low-level radioactive waste. The report emphasizes significant issues and events that have affected progress, and also includes an introduction that provides background information and perspective on United States policy for low-level radioactive waste disposal

Krsko NPP radioactive waste characteristics

International Nuclear Information System (INIS)

Skanata, D.; Kroselj, V.; Jankovic, M.

2007-01-01

In May 2005 Krsko NPP initiated the Radioactive Waste Characterization Project and commissioned its realization to the consulting company Enconet International, Zagreb. The Agency for Radwaste Management was invited to participate on the Project. The Project was successfully closed out in August 2006. The main Project goal consisted of systematization the existing and gathering the missing radiological, chemical, physical, mechanical, thermal and biological information and data on radioactive waste. In a general perspective, the Project may also be considered as a part of broader scope of activities to support state efforts to find a disposal solution for radioactive waste in Slovenia. The operational low and intermediate level radioactive waste has been structured into 6 waste streams that contain evaporator concentrates and tank sludges, spent ion resins, spent filters, compressible and non-compressible waste as well as specific waste. For each of mentioned waste streams, process schemes have been developed including raw waste, treatment and conditioning technologies, waste forms, containers and waste packages. In the paper the main results of the Characterization Project will be briefly described. The results will indicate that there are 17 different types of raw waste that have been processed by applying 9 treatment/conditioning technologies. By this way 18 different waste forms have been produced and stored into 3 types of containers. Within each type of container several combinations should be distinguished. Considering all of this, there are 34 different types of waste packages altogether that are currently stored in the Solid Radwaste Storage Facility at the Krsko NPP site. Because of these findings a new identification system has been recommended and consequently the improvement of the existing database on radioactive waste has been proposed. The potential areas of further in depth characterization are indicated. In the paper a brief description on the

Identification and evaluation of alternative radioactive waste categorisation options

International Nuclear Information System (INIS)

Maul, P.R.; Smith, G.M.; Stenhouse, M.J.; Watkins, B.M.

1996-09-01

The purpose of the research described in this report was to consider the options for future UK radioactive waste categorisation, to evaluate the advantages and disadvantages of each option and, as a result, to identify any which might be viable practical alternatives to the current arrangements. The review process included meetings with large and small waste producers, a wider consultation exercise using a questionnaire, a presentation to RWMAC, and discussion with representatives of the UK regulators. These consultations provided the basis for the formulation and evaluation of a number of alternative waste categorisation schemes. (UK)

Background Model for the Majorana Demonstrator

Science.gov (United States)

Cuesta, C.; Abgrall, N.; Aguayo, E.; Avignone, F. T.; Barabash, A. S.; Bertrand, F. E.; Boswell, M.; Brudanin, V.; Busch, M.; Byram, D.; Caldwell, A. S.; Chan, Y.-D.; Christofferson, C. D.; Combs, D. C.; Detwiler, J. A.; Doe, P. J.; Efremenko, Yu.; Egorov, V.; Ejiri, H.; Elliott, S. R.; Fast, J. E.; Finnerty, P.; Fraenkle, F. M.; Galindo-Uribarri, A.; Giovanetti, G. K.; Goett, J.; Green, M. P.; Gruszko, J.; Guiseppe, V. E.; Gusev, K.; Hallin, A. L.; Hazama, R.; Hegai, A.; Henning, R.; Hoppe, E. W.; Howard, S.; Howe, M. A.; Keeter, K. J.; Kidd, M. F.; Kochetov, O.; Konovalov, S. I.; Kouzes, R. T.; LaFerriere, B. D.; Leon, J.; Leviner, L. E.; Loach, J. C.; MacMullin, J.; MacMullin, S.; Martin, R. D.; Meijer, S.; Mertens, S.; Nomachi, M.; Orrell, J. L.; O'Shaughnessy, C.; Overman, N. R.; Phillips, D. G.; Poon, A. W. P.; Pushkin, K.; Radford, D. C.; Rager, J.; Rielage, K.; Robertson, R. G. H.; Romero-Romero, E.; Ronquest, M. C.; Schubert, A. G.; Shanks, B.; Shima, T.; Shirchenko, M.; Snavely, K. J.; Snyder, N.; Suriano, A. M.; Thompson, J.; Timkin, V.; Tornow, W.; Trimble, J. E.; Varner, R. L.; Vasilyev, S.; Vetter, K.; Vorren, K.; White, B. R.; Wilkerson, J. F.; Wiseman, C.; Xu, W.; Yakushev, E.; Young, A. R.; Yu, C.-H.; Yumatov, V.

The Majorana Collaboration is constructing a system containing 40 kg of HPGe detectors to demonstrate the feasibility and potential of a future tonne-scale experiment capable of probing the neutrino mass scale in the inverted-hierarchy region. To realize this, a major goal of the Majorana Demonstrator is to demonstrate a path forward to achieving a background rate at or below 1 cnt/(ROI-t-y) in the 4 keV region of interest around the Q-value at 2039 keV. This goal is pursued through a combination of a significant reduction of radioactive impurities in construction materials with analytical methods for background rejection, for example using powerful pulse shape analysis techniques profiting from the p-type point contact HPGe detectors technology. The effectiveness of these methods is assessed using simulations of the different background components whose purity levels are constrained from radioassay measurements.

Environmental radioactivity in Canada, January-June 1978

International Nuclear Information System (INIS)

1979-05-01

The radiological surveillance program of the Department of National Health and Welfare is conducted for the purpose of determining levels of environmental radioactivity in Canada and assessing the resulting population exposures. In this report the results for the first half of 1978 from the analyses of air, precipitation, water vapour, drinking water, milk, biota and bone for critical radionuclides are presented. Radioactivity measurements are now given in in the SI unit, the becquerel (Bq). One becquerel is equivalent to about 27 picocuries. The graphical format used in previous reports has been retained with extensions of the trend-lines to enable identification of changes in the levels and assessment of their potential health significance. All the levels measured during this period are below the permissible limits recommended by the International Commission for Radiological Protection. (auth)

Properties of Natural Radiation and Radioactivity

International Nuclear Information System (INIS)

Strom, Daniel J.

2009-01-01

Ubiquitous natural sources of radiation and radioactive material (naturally occurring radioactive material, NORM) have exposed humans throughout history. To these natural sources have been added technologically-enhanced naturally occurring radioactive material (TENORM) sources and human-made (anthropogenic) sources. This chapter describes the ubiquitous radiation sources that we call background, including primordial radionuclides such as 40K, 87Rb, the 232Th series, the 238U series, and the 235U series; cosmogenic radionuclides such as 3H and 14C; anthropogenic radionuclides such as 3H, 14C, 137Cs, 90Sr, and 129I; radiation from space; and radiation from technologically-enhanced concentrations of natural radionuclides, particularly the short-lived decay products of 222Rn ('radon') and 220Rn ('thoron') in indoor air. These sources produce radiation doses to people principally via external irradiation or internal irradiation following intakes by inhalation or ingestion. The effective doses from each are given, with a total of 3.11 mSv y-1 (311 mrem y-1) to the average US resident. Over 2.5 million US residents receive over 20 mSv y-1 (2 rem y-1), primarily due to indoor radon. Exposure to radiation from NORM and TENORM produces the largest fraction of ubiquitous background exposure to US residents, on the order of 2.78 mSv (278 mrem) or about 89%. This is roughly 45% of the average annual effective dose to a US resident of 6.2 mSv y-1 (620 mrem y-1) that includes medical (48%), consumer products and air travel (2%), and occupational and industrial (0.1%). Much of this chapter is based on National Council on Radiation Protection and Measurements (NCRP) Report No. 160, 'Ionizing Radiation Exposure of the Population of the United States,' for which the author chaired the subcommittee that wrote Chapter 3 on 'Ubiquitous Background Radiation.'

Value of radioactive iodine uptake and thyroid imaging in diagnosis of painless thyroiditis

International Nuclear Information System (INIS)

Zhang Rusen; Feng Yong; Hu Yingjian; He Hongyuan

2010-01-01

Objective: To evaluate clinical value of radioactive iodine uptake and thyroid imaging in diagnosis of painless thyroiditis (PT). Methods: Seventy cases of PT patients, 50 cases of GD patients and 50 cases of healthy persons were retrospectively analyzed by using radioactive iodine uptake, thyroid imaging and serological examination. Results: PT group radioactive iodine uptake rate was significantly lower than the control group, GD group was significantly higher than the control group, PT group and the GD group difference was significant (F=64.88, P<0.01). Thyroid image of PT group is not clear, or no to be seen, thyroid image of GD group can be clearly visible. Conclusion: Radioactive iodine uptake and thyroid imaging play an irreplaceable role in the identification of PT and GD, and the method is simple and effective too. (authors)

Study of boletus edulis mushrooms in south- western Bulgaria for the presence of natural and technogenic radioactive substances

International Nuclear Information System (INIS)

Direkov, Lubomir; Gaberov, Vladimir; Vakova, Violeta

2015-01-01

Boletus includes in its composition natural and technogenic radioactive elements such as potassium - 40, carbon - 14, rubidium - 87 uranium - 238, thorium - 232, radium - 226, as well as anthropogenic radioactive substances: iodine - 131, cesium - 137, strontium - 90. Therefore, these fungi can be used as bio-indicators for the presence of radioactive substances in the wild species, the identification of areas with a higher content in the soils of natural radioactive substances, examination areas around uranium mines, and also in case of transboundary transport of anthropogenic radioactive substances as a result of accidents in nuclear power plants - Chernobyl - 1986 Fukushima - 2011 Zaporozhian NPP - 2014 and others.

Investigation of background radiation and associated anomalies in Rifle, Colorado

International Nuclear Information System (INIS)

Smuin, D.R.; Wilson, M.J.; Crutcher, J.W.

1988-02-01

In addition to examining anomalies and establishing the background gamma exposure rate range, the study presents a formula to convert thousand counts per minute (kcpm) from a gamma scintillator to microroentgen per hour (μRh) for the Rifle region. Also, a method is presented to identify contaminated areas containing excess 226 Ra, by using a GR-410 gamma spectrometer. This method is suggested to be applied to all property surveys in the Rifle area. The Wasatch Formation, which outcrops extensively in the Rifle area, was found to have a major influence on the background radiation. Varying potassium concentrations and naturally occurring uranium in this rock unit reveal varying gamma exposure rates. Examining RaTh ratios from laboratory analysis of soil samples or use of RaTh ratios from GR-410 gamma spectrometer readings on site allows discrimination between mill related contamination and naturally occuring radioactivity. Radioactive coal clinkers were found used as fill material throughout the Rifle region and have been determined to be a product of the mill and subject to remediation. Finally, windblown mill tailings contamination is addressed in some detail. Mill tailings redistributed from the Rifle uranium mill tailings piles by prevailing winds were detected extensively on vicinity properties in Rifle. Some radioactive components of the windblown tailings were found to have leached into the subsurface soil. The combination of Wasatch Formation, radioactive coal clinkers, and windblown tailings accounts for many of the anomalous gamma exposure rates observed by the radiological survey teams. 11 refs., 10 figs., 3 tabs

The role of national regulatory authority in monitoring of radioactivity and in case of seizure of radioactive or nuclear material

International Nuclear Information System (INIS)

Morkunas, G.

2002-01-01

Full text: The Radiation Protection Centre is a regulatory authority in radiation protection in Lithuania. Its main tasks are licensing of practices, supervision, control and enforcement of radiation protection requirements, dosimetric, radiometric and spectrometric measurements, evaluation of exposure and its sources, expertise and advice on optimization of radiation protection. Its activities may be divided into two main parts -- regulatory and analytical ones. Food, drinking water, environmental, wipe and other samples are monitored, the appropriate evaluation of doses is done. The data on concentrations of artificial radionuclides in different bodies are available. The laboratory is to be accredited according to the ISO 17025 standard in the framework of Phare Twinning Project. In case of seized radioactive or nuclear material the Radiation Protection Centre has to identify the necessary radiation protection means for members of public and emergency workers, perform measurements of dose rate and radioactive contamination, and, if necessary, evaluate doses received due to the seized radioactive or nuclear material. Since the Radiation Protection Centre has its departments in the largest cities of Lithuania the above mentioned measures can be taken very urgently, especially the ones connected with primary evaluation of situation and identification of optimized radiation protection measures. The Radiation Protection Centre has its own possibilities of identification of radionuclides in the seized material. Such installations as HpGe spectrometers (Oxford and Canberra), equipment for radiochemical separation of U, Pu and actinides, alpha spectrometer, liquid scintillation spectrometer and neutron rem counter are available. There were a few cases when seized material had to be analyzed also. Different sources were found in different places of Lithuania, and it was necessary to define the activity and isotopic content of these sources. The following scheme is used in

Radioactive waste management plan. Plan 82

International Nuclear Information System (INIS)

1982-06-01

The report is the first account of the nuclear power utilities of Sweden about the plans for the final disposal of the radioactive waste products of the nuclear power. Part 1 describes the general background, the plans for research and development, including the necessary facilities. The time schedule and the calculated costs of the operations are presented. (G.B.)

Radioactive sources in brachytherapy:

OpenAIRE

Burger, Janez

2003-01-01

Background. In modern brachytherapy, a greast step forward was made in the 1960s in France with the introduction of new radioactive isotopes and new techniques. These innovations spread rapidly across Europe, though no single dosimetry standard had been set by then. In the new millennium, the advances in brachytherapy are further stimulated by the introduction of 3-D imaging techniques and the latest after loading irradiation equipment that use point sources. The international organiyation IC...

Background radiation in two locations in Deaf Smith and Swisher Counties within the Palo Duro Basin

International Nuclear Information System (INIS)

1984-10-01

Data on external background radiation doses resulting from cosmic, terrestrial, and fallout sources and on concentrations of radioactivity in environmental media are presented and discussed. Doses to individuals located at the approximate centers of two locations in Texas, one in Deaf Smith County and the other in Swisher County, are given, as are the population doses to people residing within 50 miles of each of the approximate centers. No adjustments have been made for the effects of buildings on radiation doses - that is, the shielding from external radiation afforded by the buildings and radiation from building materials are not accounted for. Concentrations of radioactivity in air, water, and milk in the region are also given. Because of the lack of specific information on background radiation at the locations, the external-dose rates to people and the radioactivity levels in environmental media for the region have been taken from the literature. A background radiation survey will be conducted in the Palo Duro Basin to obtain additional data. 26 references, 3 figures, 15 tables

1996 annual report on low-level radioactive waste management progress. Report to Congress

International Nuclear Information System (INIS)

1997-11-01

This report is prepared in response to the Low-Level Radioactive Waste Policy Act (the Act), Public Law 96-573, 1980, as amended by the Low-Level Radioactive Waste Policy Amendments Act of 1985, Public Law 99-240. The report summarizes the activities during calendar year 1996 related to the establishment of new disposal facilities for commercially-generated low-level radioactive waste. The report emphasizes significant issues and events that have affected progress in developing new disposal facilities, and also includes an introduction that provides background information and perspective on US policy for low-level radioactive waste disposal

Investigation of natural radioactivity level of the waters in the tibet autonomous region

International Nuclear Information System (INIS)

Zhang Tianhua; Li Yankun; Yao Ke; Pan Chengchang

1995-01-01

The investigation results of natural radioactivity level in river, lake, spring, well and tap water in the Tibet Autonomous Region is reported. There were totally 46 samples collected from 53 measuring points. The results show that the radioactivity level of water bodies of the Tibet Autonomous region was within normal natural background

Investigation of natural radioactivity level of the waters in Guangxi Zhuangzu Autonomous Region

International Nuclear Information System (INIS)

Yang Mingshen; Ming Chuanbao; Dai Guozhi; Liang Runping; Chen Xiuyu; Yang Gang; Jin Mei

1993-01-01

This paper reports the investigation results of natural radioactivity level in river, lake reservoir, spring, well and tap water in Guangxi Zhuangzu Autonomous Region. There were totally 194 samples collected from 143 measuring points. The results show that the radioactivity level of varied water bodies of the region was within normal natural background

Rapid screening of radioactivity in food for emergency response.

Science.gov (United States)

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

2011-06-01

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

Rapid screening of radioactivity in food for emergency response

International Nuclear Information System (INIS)

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

2011-01-01

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

The BetaCage: Ultrasensitive Screener for Radioactive Backgrounds

Science.gov (United States)

Thompson, Michael; BetaCage Collaboration

2017-09-01

Rare event searches, such as dark matter detection and neutrinoless double beta decay, require screening of materials for backgrounds such as beta emission and alpha decaying isotopes. The BetaCage is a proposed ultra-sensitive time-projection chamber to screen for alpha-emitting and low energy beta-emitting (10-200 keV) contaminants. The expected sensitivity is 0.1 beta particles (perkeV -m2 - day) and 0.1 alpha particles (perm2 - day) , where the former will be limited by Compton scattering of external photons in the screening samples and the latter is expected to be signal-limited. The prototype BetaCage under commissioning at South Dakota School of Mines & Technology is filled with P10 gas (10% methane, 90% argon) in place of neon and is 40×40×20 cm in size. Details on design, construction and characterization will be presented.

Identification of radioisotopes in bulks with disused sealed sources using a high performance portable spectrometer

International Nuclear Information System (INIS)

Zapata, Luis; Mallaupoma, Mario

2013-01-01

Sealed radioactive sources are widely used in many industrial applications, and after completing its useful life must be managed as radioactive wastes. One of the most common problems of disused sealed radioactive sources is that many times they lack proper identification and their certificates of manufacture. In that context, it is necessary to identify them, prior to any other management step. There are a number of techniques which can be used; however they are sometimes complex. This technical paper shows a simple way for its identification using the InSpector 1000 monitor which allows to know their energy spectra. These modern instruments and detectors have been obtained thanks to the Project Global Threat Reduction Initiative (Programa de Reduccion de Amenazas) between IPEN and the US DOE. (authors).

Acceptance criteria for disposal of radioactive wastes in shallow ground and rock cavities

International Nuclear Information System (INIS)

1985-01-01

This document provides an overview of basic information related to waste acceptance criteria for disposal in shallow ground and rock cavity repositories, consisting of a discussion of acceptable waste types. The last item includes identification of those waste characteristics which may influence the performance of the disposal system and as such are areas of consideration for criteria development. The material is presented in a manner similar to a safety assessment. Waste acceptance criteria aimed at limiting the radiation exposure to acceptable levels are presented for each pathway. Radioactive wastes considered here are low-level radioactive wastes and intermediate-level radioactive wastes from nuclear fuel cycle operations and applications of radionuclides in research, medicine and industry

Technologies for remediation of radioactively contaminated sites

International Nuclear Information System (INIS)

1999-06-01

This report presents particulars on environmental restoration technologies (control and treatment) which can be applied to land based, radioactively contaminated sites. The media considered include soils, groundwater, surface water, sediments, air, and terrestrial and aquatic vegetation. The technologies addressed in this report can be categorized as follows: self-attenuation (natural restoration); in-situ treatment; removal of contamination; ex-situ treatment; and transportation and final disposal. The report provides also background information about and a general approach to remediation of radioactively contaminated sites as well as some guidance for the selection of a preferred remediation technology. Examples of remediation experience in Australia and Canada are given it annexes

Technologies for remediation of radioactively contaminated sites

Energy Technology Data Exchange (ETDEWEB)

1999-06-01

This report presents particulars on environmental restoration technologies (control and treatment) which can be applied to land based, radioactively contaminated sites. The media considered include soils, groundwater, surface water, sediments, air, and terrestrial and aquatic vegetation. The technologies addressed in this report can be categorized as follows: self-attenuation (natural restoration); in-situ treatment; removal of contamination; ex-situ treatment; and transportation and final disposal. The report provides also background information about and a general approach to remediation of radioactively contaminated sites as well as some guidance for the selection of a preferred remediation technology. Examples of remediation experience in Australia and Canada are given it annexes Refs, figs, tabs

Background as a residual radioactivity criterion for decommissioning: Appendix A to the Generic Environmental Impact Statement in support of rulemaking on radiological criteria for decommissioning of NRC-licensed nuclear facilities. Draft report

International Nuclear Information System (INIS)

Huffert, A.M.; Meck, R.A.; Miller, K.M.

1994-08-01

This report was originally published as an appendix to the draft U.S. Nuclear Regulatory Commission (NRC) document entitled, open-quotes Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for Decommissioning of NRC-Licensed Nuclear Facilities.close quotes Because of the great interest in this report by members of the public, citizen and environmental organizations, academicians, licensees, and regulators, the NRC staff is publishing this report separately, so that it can be readily available to a diverse audience. This report was created to assist both the NRC staff and interested members of the public in evaluating background radiation (background) as a decommissioning criterion, by serving as a primer on background and providing information on the existing applications of background in regulatory criteria and standards. This report also discusses some of the methods available to measure and distinguish between the very low radiation levels associated with background and man-made sources of radiation. Two approaches are considered for applying background as a decommissioning criterion; these are the use of background dose rates and background radionuclide concentrations. This report concludes that the temporal and spatial variability of background produces a wide range of doses to United States residents, which prevents the application of background dose rates as a decommissioning criterion. Instead, this report recommends that local background radionuclide concentrations serve as a benchmark for decommissioning criteria, while taking into account the concept of reducing residual radioactivity to a level as low as is reasonably achievable

Radioactivity distribution measurement of various natural material surfaces with imaging plate

International Nuclear Information System (INIS)

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

1996-01-01

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

Analysis of radioactive cobalt

International Nuclear Information System (INIS)

1977-01-01

This is a manual published by Science and Technology Agency, Japan, which prescribes on the analysis method for radioactive cobalt which is a typical indexing nuclide among the radioactive nuclides released from nuclear facilities. Since the released cobalt is mainly discharged to coastal region together with waste water, this manual is written for samples of sea water, sea bottom sediments and marine organisms. Radioactive cobalt includes the nuclides of 57 co, 58 Co, 60 Co, etc., the manual deals with them as a whole as 60 Co of long half life. Though 60 Co analysis has become feasible comparatively simply due to scintillation or semi-conductor spectrometry, trace 60 Co analysis is performed quantitatively by co-precipitation or collection into alumina and scintillation spectrometry. However, specific collecting operation and γ-γ coincidence measurement have been required so far. This manual employs 60 Co collection by means of ion-exchange method and measurement with low background GM counting system, to analyze quantitatively and rapidly low level 60 Co. It is primarily established as the standard analyzing method for the survey by local autonomous bodies. It is divided into 4 chapters including introduction sea water, marine organisms, and sea bottom sediments. List of required reagents is added in appendix. (Wakatsuki, Y.)

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)

Sponsored research on radioactive waste management. Progress report January 1981 - March 1982

Energy Technology Data Exchange (ETDEWEB)

1983-01-01

The report is in chapters entitled: introduction (background, responsibilities, options, structure of the programme); strategy development; disposal of accumulations; disposal of radioactive waste arisings; quality assurance for waste conditioning quality assurance related to radioactive waste disposal (effectiveness of different rock types as natural barriers to the movement of radioactivity, and non-site specific factors in the design of repositories; radiological assessment; environmental studies; research and development to meet requirements specific to UKAEA wastes; long term research (processes for the solidification of highly active liquid wastes); plutonium contamination waste minimisation.

Preparation of the National Radioactive Waste and Spent Fuel Management Programme in Slovenia

International Nuclear Information System (INIS)

Kralj, M.; Zeleznik, N.; Mele, I.; Veselic, M.

2006-01-01

The first separate National Radioactive Waste and Spent Fuel Management Programme (National Programme) was prepared in Slovenia in 2005, as a separate part of the National Environmental Action Programme that was adopted in June 2005. In the previous National Environmental Action Programme from the year 1999, the radioactive waste and spent fuel management was mentioned only briefly in the paragraph on radiation and nuclear safety with two main objectives: to provide an effective management of radioactive waste, and to keep the environmental ionising radiation under control. The new National Programme from 2005 includes all topics being relevant for the management of the radioactive waste and spent fuel, from the legislation and identification of different waste streams in Slovenia, to the management of radioactive waste and spent fuel, the decommissioning of nuclear facilities and management of (TE)NORM. It deals also with the relevant actors in the radioactive waste management, communication and information activities, and the financial aspects of the radioactive waste and spent fuel management. The National Programme was already adopted by the Slovenian Government in October 2005 and will go to Parliament proceedings. The Technical bases for the National Programme was prepared by ARAO and presented to the government in the beginning of 2005. The frames for this document were taken from relevant strategic documents: the Programme of decommissioning the nuclear power plant Krsko and the radioactive waste and spent fuel management, prepared in 2004 by Slovenian and Croatian experts (ARAO and APO), the Proposal of LILW Management Strategy (1999), the Strategy of Spent Fuel Management (1996), and the Resolution on the National Energy Programme (2004). ARAO made a detailed study on the amount and types of radioactive waste produced in Slovenia and future arising with emphasis on the minimization on radioactive waste production. It considered all producers of LILW and

Observation of radioactive background in the OSO-7 gamma ray monitor

International Nuclear Information System (INIS)

Dunphy, P.P.; Forrest, D.J.; Chupp, E.L.; Dyer, C.S.

1975-01-01

The counting rate, covering the energy range 0.3-10 MeV, during a sixteen month period (October 1971-December 1972) was considerably higher than expected from balloon data. Dyer et al. have shown the importance of activation in satellites for diffuse gamma flux measurements. The OSO-7 spectra exhibit strong, complex line structure, especially between 400 keV and 900 keV, and several identifications can be made consistent with the model of Dyer et al. We present here the spectral structure and time variations. (orig./WB) [de

ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS

International Nuclear Information System (INIS)

R.H. Little, P.R. Maul, J.S.S. Penfoldag

2003-01-01

This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of both the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible

Environmental radioactivity in Canada, 1980

International Nuclear Information System (INIS)

McGregor, R.G.; Meyerhof, D.P.; Quinn, J.M.; Tracy, B.L.

1983-01-01

The radiological surveillance program of the Department of National Health and Welfare is conducted to determine levels of environmental radioactivity in Canada and asessing the resulting population exposures. In this report, the results for 1980 from the analyses of air, precipitation, water vapour, drinking water, milk, biota and bone for critical radionuclides are presented. The graphical format is used with extensions of the trend-lines to enable identification of changes in the levels and assessment of their potential health significance. All the levels measured during this period are below the permissible limits recommended by the International Commission for Radiological Protection

Emergency response planning and preparedness for transport accidents involving radioactive material

International Nuclear Information System (INIS)

1988-01-01

The purpose of this Guide is to provide assistance to public authorities and others (including consignors and carriers of radioactive materials) who are responsible for ensuring safety in establishing and developing emergency response arrangements for responding effectively to transport accidents involving radioactive materials. This Guide is concerned mainly with the preparation of emergency response plans. It provides information which will assist those countries whose involvement with radioactive materials is just beginning and those which have already developed their industries involving radioactive materials and attendant emergency plans, but may need to review and improve these plans. The need for emergency response plans and the ways in which they are implemented vary from country to country. In each country, the responsible authorities must decide how best to apply this Guide, taking into account the actual shipments and associated hazards. In this Guide the emergency response planning and response philosophy are outlined, including identification of emergency response organizations and emergency services that would be required during a transport accident. General consequences which could prevail during an accident are described taking into account the IAEA Regulations for the Safe Transport of Radioactive Material. 43 refs, figs and tabs

Packaging requirements and procedures for the transport of radioactive materials

International Nuclear Information System (INIS)

White, M.C.

1980-01-01

Canadian regulations on the transportation of radioactive materials are based on those formulated by the IAEA. A synopsis of these regulations is presented, and the background to certain key provisions is explained. (LL)

An ultra-low-background detector for axion searches

International Nuclear Information System (INIS)

Aune, S; Ferrer Ribas, E; Giomataris, I; Mols, J P; Papaevangelou, T; Dafni, T; Lacarra, J Galan; Iguaz, F J; Irastorza, I G; Morales, J; Ruz, J; Tomas, A; Fanourakis, G; Geralis, T; Kousouris, K; Vafeiadis, T

2009-01-01

A low background Micromegas detector has been operating in the CAST experiment at CERN for the search of solar axions since the start of data taking in 2002. The detector, made out of low radioactivity materials, operated efficiently and achieved a very low level of background (5x10 -5 keV -1 -cm -2 -s -1 ) without any shielding. New manufacturing techniques (Bulk/Microbulk) have led to further improvement of the characteristics of the detector such as uniformity, stability and energy resolution. These characteristics, the implementation of passive shielding and the improvement of the analysis algorithms have dramatically reduced the background level (2x10 -7 keV -1 -cm -2 |s -1 ), improving thus the overall sensitivity of the experiment and opening new possibilities for future searches.

Radioactivity and United Kingdom estuaries: an overview identifying research priorities

International Nuclear Information System (INIS)

Hamilton, E.I.; Clifton, R.J.; Stevens, H.E.

1985-05-01

The report consists of the results of an evaluation of research priorities for the environmental radioactivity of estuaries, (and near shore waters) of the United Kingdom. The format of this report is:(i) general conclusions for the future requirements for research in the field of environmental radioactivity; (ii) an overview of some specific recommendations for research; and (iii) an appendix in which a comprehensive evaluation of the research priorities for specific areas of research are given. On the basis that man is the prime target for concern and protection, special attention has been given to the environment in the vicinity of the British Nuclear Fuels (BNFL) reprocessing plant at Sellafield, Cumbria, which is the source of major releases of a variety of radionuclides into the natural environment. Subjects covered in the Appendix are: site factors; pathways to man; source term; hot particles; terrestrial inputs; surveys and monitoring; analysis; organics; field versus laboratory data; biology; bioaccumulation factors; some bioaccumulators of radioactivity; bioturbation; bacteria; genetics; natural change; sediment; resuspension; surfaces; Ksub(d) factors; pore liquids; diagenesis and the ageing processes; airborne transport of radionuclides; models; natural radioactivity; public opinion; recreation; the ICRP; the ALARA principle; decommissioning of nuclear power stations; identification of research requirements; environmental radioactivity - the national effort. (U.K.)

Design and applications of an anticoincidence shielded low background gamma-ray spectrometer

Energy Technology Data Exchange (ETDEWEB)

Petri, H [Forschungszentrum Juelich GmbH (Germany). Zentralabteilung fuer Chemische Analysen

1997-03-01

A low background gamma-ray spectrometer has been constructed for measuring artificial and natural radioative isotopes. The design of the spectrometer, its properties and the application to the determination of natural radioactivity of dental ceramics are described. (orig.)

Spectrometry techniques for radioactivity measurements

International Nuclear Information System (INIS)

Anilkumar, S.

2016-01-01

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

Long term radioactive waste management

International Nuclear Information System (INIS)

Lavie, J.M.

1984-01-01

In France, waste management, a sensitive issue in term of public opinion, is developing quickly, and due to twenty years of experience, is now reaching maturity. With the launching of the French nuclear programme, the use of radioactive sources in radiotherapy and industry, waste management has become an industrial activity. Waste management is an integrated system dealing with the wastes from their production to the long term disposal, including their identification, sortage, treatment, packaging, collection and transport. This system aims at guaranteing the protection of present and future populations with an available technology. In regard to their long term management, and the design of disposals, radioactive wastes are divided in three categories. This classification takes into account the different radioisotopes contained, their half life and their total activity. Presently short-lived wastes are stored in the shallowland disposal of the ''Centre de la Manche''. Set up within the French Atomic Energy Commission (CEA), the National Agency for waste management (ANDRA) is responsible within the framework of legislative and regulatory provisions for long term waste management in France [fr

MONITORING OF RADIOACTIVITY AT DNURT CAMPUS

Directory of Open Access Journals (Sweden)

L. F. Dolina

2016-06-01

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

Detection of WIMPs in the Edelweiss experiment. Study of the radioactive background noise and measurements with bolometers; Recherche des wimp's du halo galactique dans l'experience edelweiss: etude du bas bruit radioactif et mesures a l'aide de bolometres a double detection ionisation/chaleur

Energy Technology Data Exchange (ETDEWEB)

Miramonti, L. [CEA/Saclay, Dept. d' Astrophysique, de la Physique des Particules, de la Physique Nucleaire et de l' Instrumentation Associee (DAPNIA), 91 - Gif-sur-Yvette (France)]|[Paris-11 Univ., 91 - Orsay (France)

1999-11-01

This thesis is dedicated to the detection of black matter in the form of WIMPs (weakly interacting massive particle). The characteristics of the interaction of WIMPs with matter are recalled. The very low number of expected events (<1 event/day.Kg) implies a radioactive background noise as weak as possible, furthermore the exponential decrease of the interacting rate with increasing energy calls for detectors with very low thresholds. Bolometers present advantages in WIMPs detection: i) very good resolution and very low thresholds, ii) very broad range of materials that can be used as absorber, the only requirements are: a crystal structure, to be a diamagnetic isolator and to have a convenient Debye temperature, iii) the possibility of detecting ionizing or non-ionizing particles, iv) the possibility of identifying the incident particle by measuring both temperature and another parameter such as ionization or scintillation, and v) the possibility of localizing the interaction inside the absorber by detecting ballistic phonons. The problematic of radioactive background noise is presented and the answers to the different sources (cosmic radiation,natural and artificial radioactivity) generating the background noise are examined. The materials used in the building of the detector and cryostat must be carefully chosen, they should be as little radioactive as possible. The test benches used to select materials for the Edelweiss experiment are described. The first measurements concerning the detectors Ge-4 and Ge-7 are presented. (A.C.)

Current situation and future plans in radioactive waste management in Mexico

International Nuclear Information System (INIS)

Lopez, H.; Jimenez, M.

1992-01-01

A brief introduction is offered in this document in order to explain the importance which is given in Mexico to the safe management of radioactive wastes. The Secretaria de Energia, Minas e Industria Paraestatal is the organization responsible for this issue. Also, a brief historical background is offered so as to understand the evolution of these activities since they were originated. This background allows us to describe the present situation, which consists in a substantial change in the volume of produced radioactive wastes; in other words, before the present situation only the, nuclear wastes from the application of radioisotopes were generated whereas currently, with the starting of commercial operation of the first unit of Laguna Verde Nuclear Power Plant (LVNPP), large volumes of industrial radioactive wastes are being generated. A mention is given as well of the acquired experience during more than 20 years of waste management and of the technologies which have been applied or practiced in the use and disposal of such wastes. Finally, some general trends in relation to the future planning are indicated, which essentially consist in the siting and characterization of a site so as to, design and construct a permanent disposal facility in order to dispose the operational radioactive wastes from LVNPP

Identification and characterization of Department of Energy special-case radioactive waste

International Nuclear Information System (INIS)

Williams, R.E.; Kudera, D.E.

1990-01-01

This paper identifies and characterizes Department of Energy (DOE) special-case radioactive wastes. Included in this paper are descriptions of the special-case waste categories and their volumes and curie contents, as well as discussions of potential methods for management of these special-case wastes. Work on extensive inventories of DOE-titled special-case waste are still in progress. 1 tab

Thule-2007 - Investigation of radioactive pollution on land

DEFF Research Database (Denmark)

Nielsen, Sven Poul; Roos, Per

the occurrence of radioactive particles in air. This involved col-lection of airborne particles with an air sampler, collection of airborne particles on sticky foils, collection of rain samples and collection of particles that could be resuspended by wind from the soil surface to the air. Small amounts...... of plutonium were found in air and rain samples, but the derived concentra-tions in air were very low corresponding to typical back-ground levels in Europe in the range 1-10 nBq m-3. A few small particles were found on the soil surface with activities up to 1000 Bq plutonium but the air and rain samples showed......A survey of radioactive pollution on land in the Thule area from an airplane accident in 1968 was carried out during 2007 and 2008. The results show levels of plutonium in soil at Narsaarsuk ranging from background values around 39 Bq m-2 up to levels of 1.7 MBq m-2. Local sub-areas of sizes...

Identification of backgrounds in the EDELWEISS-I dark matter search experiment

Energy Technology Data Exchange (ETDEWEB)

Fiorucci, S. [CEA, Centre d' Etudes Nucleaires de Saclay, DSM/DAPNIA, 91191 Gif-sur-Yvette Cedex (France); Benoit, A. [Centre de Recherche sur les Tres Basses Temperatures, SPM-CNRS, BP 166, 38042 Grenoble (France); Berge, L. [Centre de Spectroscopie Nucleaire et de Spectroscopie de Masse, UMR8609 IN2P3-CNRS, Univ. Paris Sud, bat 108, 91405 Orsay Campus (France)] (and others)

2007-05-15

This paper presents our interpretation and understanding of the different backgrounds in the EDELWEISS-I data sets. We analyze in detail the several populations observed, which include gammas, alphas, neutrons, thermal sensor events and surface events, and try to combine all data sets to provide a coherent picture of the nature and localization of the background sources. In light of this interpretation, we draw conclusions regarding the background suppression scheme for the EDELWEISS-II phase. (authors)

Identification of backgrounds in the EDELWEISS-I dark matter search experiment

Energy Technology Data Exchange (ETDEWEB)

Fiorucci, S. [CEA, Centre d' Etudes Nucleaires de Saclay, DSM/DAPNIA, 91191 Gif-sur-Yvette Cedex (France); Benoit, A. [Centre de Recherche sur les Tres Basses Temperatures, SPM-CNRS, BP 166, 38042 Grenoble (France); Berge, L. [Centre de Spectroscopie Nucleaire et de Spectroscopie de Masse, UMR 8609 IN2P3-CNRS, Univ. Paris Sud, bat 108, 91405 Orsay Campus (France)] (and others)

2006-10-15

This paper presents our interpretation and understanding of the different backgrounds in the EDELWEISS-I data sets. We analyze in detail the several populations observed, which include gammas, alphas, neutrons, thermal sensor events and surface events, and try to combine all data sets to provide a coherent picture of the nature and localisation of the background sources. In light of this interpretation, we draw conclusions regarding the background suppression scheme for the EDELWEISS-II phase. (authors)

International regulatory control of the transport of radioactive materials

International Nuclear Information System (INIS)

Swindell, G.E.

1979-01-01

The development of the IAEA regulations on the transport of radioactive materials and the background for the adoption of these regulations by the various international organizations responsible for regulating the different modes of international transport of hazardous materials is briefly discussed

Monte Carlo simulations of low background detectors

International Nuclear Information System (INIS)

Miley, H.S.; Brodzinski, R.L.; Hensley, W.K.; Reeves, J.H.

1995-01-01

An implementation of the Electron Gamma Shower 4 code (EGS4) has been developed to allow convenient simulation of typical gamma ray measurement systems. Coincidence gamma rays, beta spectra, and angular correlations have been added to adequately simulate a complete nuclear decay and provide corrections to experimentally determined detector efficiencies. This code has been used to strip certain low-background spectra for the purpose of extremely low-level assay. Monte Carlo calculations of this sort can be extremely successful since low background detectors are usually free of significant contributions from poorly localized radiation sources, such as cosmic muons, secondary cosmic neutrons, and radioactive construction or shielding materials. Previously, validation of this code has been obtained from a series of comparisons between measurements and blind calculations. An example of the application of this code to an exceedingly low background spectrum stripping will be presented. (author) 5 refs.; 3 figs.; 1 tab

Development of federal government policy on radioactive waste management

International Nuclear Information System (INIS)

Howieson, J.

1979-01-01

The federal government position on radioactive waste management has been defined in one area - that of spent fuel waste - where AECL is pursuing an R and D program under the 1978 Ontario-Federal agreement. This agreement has a term of two years. In considering its renewal and in other areas of radioactive waste management, the government is working towards establishing its policy position. A review is given of the reasons for the government's interest in this area and some of the background which affects the approach to be taken. (auth)

Import of metal scrap - risks associated with radioactivity

International Nuclear Information System (INIS)

Elert, M.

1992-11-01

There is a growing concern in Sweden for the possibility that imported metal scrap is radioactive. The recent political and economical changes in eastern Europe and the increased cooperation with the CEC has affected Swedens import. In the last years, the import of metal scrap from the former USSR has increased considerably. In view of recent incidents, when radioactive materials have been found, the Swedish Radiation Protection Institute has detected a need for identifying the potential risk sources and evaluating the magnitude of the risk associated with the import of metal scrap. The purpose of this report is to provide some background material concerning import statistics, use of metal scrap in Sweden and to identify potential sources of radioactive metal scrap. In addition, the radionuclides of most concern has been identified and the possibility of detecting them in metal scrap shipments is analyzed

Policy of radioactive waste disposal in the Netherlands

International Nuclear Information System (INIS)

Selling, H.A.

2002-01-01

Earlier this year the final report of the CORA Commission on retrievable disposal of radioactive waste was published. It confirmed the technical feasibility of retrievable repository concepts in the deep underground. Rock salt and sedimentary clay were considered as potential host rocks for such a repository. It is recommended, among other things, that subsequent research programmes should focus on stakeholder identification and involvement in a stepwise decision-making process of waste disposal. (author)

A device for identification of respective images in orthogonal localization roentgenograms

International Nuclear Information System (INIS)

Ganchev, M.

1977-01-01

Some problems which might be solved with the device, originally intended for localization of implanted radioactive wires, include: conjugation check-up of orthogonal localization roentgenograms; localization of partially screened radioactive sources in the patient body; localization of Fletcher's trapezium points in the pelvis; identification of the respective images of contrast filled lymph nodes and localization of some bone hallmarks, visible only on one of two localization roentgenograms. (author)

Very low background gamma spectrometer mounted in anti-Compton with NaI(Tl) for the study of glaciers and sediment samples; Spectrometrie gamma a tres bas niveau avec anti-Compton NaI(Tl), pour l`etude des glaciers et des sediments

Energy Technology Data Exchange (ETDEWEB)

Pinglot, J.F.; Pourchet, M. [Centre National de la Recherche Scientifique (CNRS), 38 - Grenoble (France). Lab. de Glaciologie

1994-05-01

The determination of natural and artificial radioactivities of snow (glaciers, polar ice-caps) or sediment samples (lakes, oceans), takes great benefit with the use of the superior resolution of high purity germanium detector, N type, in a broad energy range( 10 keV up to 1.6 MeV). This detector (relative efficiency: 20%), very low background specified, is mounted in anti-Compton with a 9`x 8` NaI(Tl) scintillator, also with low background. International standards, used with a quantitative software allows the determination of the efficiency curve and the isotopes identification and specific activity. The anti-Compton suppressed spectrometer exhibits a decrease of the background by a factor of ten, without any change in efficiencies. Applications of this spectrometer deal with samples from lake Titicaca and a glacier from Spitsbergen. (authors). 6 figs., 7 refs.

Environmental impact assessment on the radioactive of a REE separation project

International Nuclear Information System (INIS)

Li Nana; Zhu Yucheng; Cai Minqi

2011-01-01

Based on the investigation of field actual environment and analysis of radioactive sources, and industrial process techniques, environmental impact of the radioactive from a REE separation project has been analyzed, assessed and forecasted. The investigation and monitoring of actual radioactive in the environment indicated that value of assessment factors remained within the range of natural background level as a whole. The maximum annual individual effective dose for occupational worker and the public were forecasted and were found to be 1.622 mSv/a and 0.029 mSv/a respectively. Both of the values are lower than annual dose limit respectively. The radioactive impact of this project on the environment will comply with the standard limit of law and requirements after the reservation measures are carried out to REE. (authors)

Investigation of natural radioactivity level of the waters in the Ningxia Hui Autonomous Region

International Nuclear Information System (INIS)

Jing Yupei; Wang Li; Tian Yi; Ai Xianyuan; Liang Ningbu

1995-01-01

This paper reports the investigation results of natural radioactivity level in river, lake, reservoir, spring, well and tap water in the Ningxia Hui Autonomous Region. There were totally 117 samples collected from 84 measuring points. The results show that the radioactivity level of varied water bodies of the region was within normal natural background

Evaluation on radioactive level and quality of aquatic environment in Suzhou

International Nuclear Information System (INIS)

Yu Rongsheng; Tu Yu; Zhang Ruiju

2007-01-01

Objective: To assess the quality grade of water source in Suzhou in terms of the radioactive level. Methods: The levels of total α and total β activities in samples of water were detected by relative measurement with medium thickness using model BH 1216 low level α and β detector. 241 Am and pure potassium chloride were used as reference radioactive sources. Results: Among all samples collected, the measured levels varied from (2.62 ± 0.17) x 10 -2 to (8.48±2.80) x 10 -2 Bq/L for total α and (0.77 ± 0.47) x 10 -1 to (3.75 ± 0.26) x 10 -1 Bq/L for total β, the average levels of β/α were from 1.6 to 7.2. Conclusions: The radioactivity level of water source in Suzhou was within the natural background range, free from contamination of artificial radioactive nuclides, which was regarded as good in quality in terms of radioactive level. It is shown that the radioactivity of well water was highest among all investigated water sources. (authors)

International projects on radioactive waste management in the Northwest region of Russia

International Nuclear Information System (INIS)

Melnikov, Nikolay

1999-01-01

This presentation deals with a project of the EC within the TACIS (Technical Assistance to the CIS - Commonwealth of Independent States) Programme ''Improvement of Safety of Radioactive Waste Management in the Northwest of Russia''. The individual subtasks considered are (1) Detailed project organisation, (2) Conceptual repository design, (3) Identification of suitable sites, (4) Identification of necessary site surveys, (5) Identification of necessary in-situ experiments, (6) Preliminary safety assessment of conceptual repositories, (7) Evaluation of suitable sites, (8) Draft repository waste acceptance criteria, (9) Conceptual design of surface infrastructures, (10) Outline of the future programme, and (11) Final report. There is a table showing the proposed repository sites and their geological environments

Where, when, how: the place of radioactive wastes in France. Andra, 1998 activity report

International Nuclear Information System (INIS)

1998-01-01

The 1998 activity report of the French national agency of radioactive wastes (Andra) presents successively: the role and missions of the Andra (history, status of radioactive wastes in France, surface storage and know-how, underground research laboratories, site selection and public information); the aspects of safety (inventory, identification and labelling of wastes, environmental policy, public relation, safety rules and reports, information storage); the scientific programs (collaborations, financing, site studies, rock mechanics and reversibility of storage, design of storage facilities, services); financial report. (J.S.)

Background radiation levels and standards for protection from ionizing radiations

International Nuclear Information System (INIS)

Farai, I.

1999-01-01

Apart from the amount of radiation which a worker may receive while he performs his work, he is also exposed to radiation because of the nature of his environment. In other words, all individuals are subject to some irradiation even though they may not work with radioactive substances. This source of radiation exposure is often referred to as background radiation. In most environments, it is low-level and can be grouped into two natural and man-made. Background radiation provides the basis on which allowable exposure limits for workers are drawn

Disposal of radioactive waste: can long-term safety be evaluated

International Nuclear Information System (INIS)

1991-01-01

The long-term safety of any hazardous waste disposal system must be convincingly shown prior to its implementation. For radioactive wastes, safety assessments over timescales far beyond the normal horizon of social and technical planning have already been conducted in many countries. These assessments provide the principal means to investigate, quantify, and explain long-term safety of each selected disposal concept and site for the appropriate authorities and the public. Such assessments are based on four main elements: definition of the disposal system and its environment, identification of possible processes and events that may affect the integrity of the disposal system, quantification of the radiological impact by predictive modelling, and description of associated uncertainties. The NEA Radioactive Waste Management Committee and the IAEA International Radioactive Waste Management Advisory Committee have carefully examined the current scientific methods for safety assessments of radioactive waste disposal systems, as briefly summarized in this report. The Committees have also reviewed the experience now available from using safety assessment methods in many countries, for different disposal concepts and formations, and in the framework of both nationally and internationally conducted studies, as referenced in this report [fr

Radioactive environmental impact assessment for a production project of titanium dioxide by chlorination process

International Nuclear Information System (INIS)

Qiu Guohua

2010-01-01

Based on the analysis of shifting direction of radionuclide in production process and the environmental investigation and monitoring, the radioactive environmental impact from a production project of titanium dioxide by chlorination process has been analyzed and assessed. The result of radioactive environmental investigation shows that values of assessment factors are in the range of environmental radioactive background. The radioactive environmental sensitive spot has been delineated. The results of radioactive environmental prediction show that the additional doses to workers and residents are 0.59 mSv/a and 9.28 × 10-4 mSv/a respectively which are less than the annual dose limits of administration. The radioactive environmental impact of the production project of the titanium dioxide by chlorination process will meet the needs of national regulations and standards if radiation protection and environmental protection measures are implemented and radioactive environmental monitoring are strengthened. (author)

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)

An ultra-low-background detector for axion searches

Energy Technology Data Exchange (ETDEWEB)

Aune, S; Ferrer Ribas, E; Giomataris, I; Mols, J P; Papaevangelou, T [IRFU, Centre d' Etudes de Saclay, Gif sur Yvette CEDEX (France); Dafni, T; Lacarra, J Galan; Iguaz, F J; Irastorza, I G; Morales, J; Ruz, J; Tomas, A [Instituto de Fisica Nuclear y Altas EnergIas, Zaragoza (Spain); Fanourakis, G; Geralis, T; Kousouris, K [Institute of Nuclear Physics, NCSR Demokritos, Athens (Greece); Vafeiadis, T, E-mail: Thomas.Papaevangelou@cern.c [Physics Department, Aristotle University, Thessaloniki (Greece)

2009-07-01

A low background Micromegas detector has been operating in the CAST experiment at CERN for the search of solar axions since the start of data taking in 2002. The detector, made out of low radioactivity materials, operated efficiently and achieved a very low level of background (5x10{sup -5} keV{sup -1}-cm{sup -2}-s{sup -1}) without any shielding. New manufacturing techniques (Bulk/Microbulk) have led to further improvement of the characteristics of the detector such as uniformity, stability and energy resolution. These characteristics, the implementation of passive shielding and the improvement of the analysis algorithms have dramatically reduced the background level (2x10{sup -7} keV{sup -1}-cm{sup -2}|s{sup -1}), improving thus the overall sensitivity of the experiment and opening new possibilities for future searches.

Monitoring of Natural Soil Radioactivity with Portable Gamma-Ray Spectrometers

DEFF Research Database (Denmark)

Bøtter-Jensen, Lars; Løvborg, Leif; Kirkegaard, Peter

1979-01-01

Two portable NaI(Tl) spectrometers with four energy windows were used for the recording of gamma-ray counts over soil and rock of differing natural radioactivity. The exposure rates at the field sites were simultaneously measured with a high-pressure argon ionization chamber. Background measureme......Two portable NaI(Tl) spectrometers with four energy windows were used for the recording of gamma-ray counts over soil and rock of differing natural radioactivity. The exposure rates at the field sites were simultaneously measured with a high-pressure argon ionization chamber. Background...... measurements at sea were carried out in order to estimate the non-terrestrial contributions to the instrument readings. Counts recorded in the three high-energy windows of the spectrometers were converted into radiometrically equivalent concentrations of thorium, uranium, and potassium in the ground. Large....... The theoretical exposure rates deducible from the experimental radioelement concentrations at the field sites were in good agreement both with the ionization-chamber readings (corrected for cosmic-ray background) and with the exposure rates measured by total gamma-ray counting. From this and other results...

Monitoring radioactivity in the environment: context, objectives, challenges and prospects

International Nuclear Information System (INIS)

Collet, J.; Jaunet, P.

2010-01-01

The aims of environmental radioactivity monitoring are multiples: protection of human health and environment, knowledge of the radiological status of the environment, early detection of radiological events, public information. This monitoring is ensured by several stakeholders (licensees, IRSN, ASN, state and local authorities, associations...) and in all environment compartments (air, water, soil, fauna and flora...). Within a European regulatory context, the Nuclear Transparency and Security Act 2006-686 of 13 June 2006 (TSN Act) reinforces the importance attached to consideration of safety, radiation protection and the environment. Other developments in the scope of environmental radioactivity must be noted: new stakeholders, lower background radiation, deployment of the French National Network of Environmental Radioactivity Monitoring (RNM), evolution of the ICPR thoughts to take better account of environmental protection, post-accident management doctrine, new concerns about environmental behaviour of some radionuclides. In order to maintain a quality policy in the field of environmental radioactivity measurements and to ensure the transparency of information, ASN will make sure that the strategy of environmental radioactivity monitoring will take into account these concerns. (author)

Analysis of radioactive ruthenium

International Nuclear Information System (INIS)

1977-01-01

This manual explains the procedures of analysis of radioactive ruthenium in the drain water from atomic energy plants. The most important radioactive ruthenium is 106 Ru, and the method of measurement described in this manual is to measure the beta ray of the daughter nuclide 106 Rh. The samples to be measured are collected from seawater, marine living things, and sediment of sea bottom near atomic energy plants. In case of sea water, the ruthenium is separated by the co-precipitation with magnesium hydroxide and distillation or the extraction with carbon tetrachloride, reduction and precipitation. The beta ray of the obtained sample is measured by a gas-flow type low background β counting system. Alkali dissolution-distillation or nitric acid extraction-distillation, reduction and precipitation are applied for marine living things. The sediment of sea bottom is treated with nitric acid or strong phosphoric acid, and distilled then the ruthenium is reduced and precipitated, and the beta-counting of the precipitation is made. The method to fix radioactive ruthenium on polyethylene films after the co-precipitation is also described for reference. The detectable levels by the present methods are 0.05 pCi/l for sea water, 0.1 pCi/g for marine living things, and 20 pCi/kg for the sediment of sea bottom. (Kato, T.)

Isotopic and Radioactivity Fingerprinting of Groundwater in the United Arab Emirates (UAE)

Energy Technology Data Exchange (ETDEWEB)

Murad, A.; Hussein, S. [Department of Geology, United Arab Emirates University, Al Ain (United Arab Emirates); Aldahan, A. [Department of Geology, United Arab Emirates University, Al Ain (United Arab Emirates); Department of Earth Sciences, Uppsala University, Uppsala (Sweden); Hou, X. L. [Riso National Laboratory for Sustainable Energy, Technical University of Denmark, Roskilde (Denmark); Possnert, G. [Tandem Laboratory, Uppsala University, Uppsala (Sweden)

2013-07-15

A pilot investigation using radioactivity together with chemical features was conducted to characterize groundwater sampled from wells drilled in fractured Paleogen-Neogen carbonate rocks along the foothill of about 1200 m absl high mountain and wells drilled in Quaternary clastic sediments from a nearby alluvial plain in the southeastern part of the UAE. These two water modes are relatively easily separated by their chloride and EC (salt content) contents and provide an ideal case for testing radioactivity fingerprints. The groundwater of the alluvial plain, which is expected to reflect a short distance precipitation recharge source, indicates a concentration of {sup 222}Rn and {sup 226}Ra 2-3 orders of magnitude lower than the groundwater of the carbonate rocks. The range of variability for gross alpha is similar, but the gross beta activity indicates only 1 order of magnitude difference between the two water types. The radioactively richer groundwater of the carbonate aquifers compared to the alluvium plane may reflect the signature of deep basinal fluids. These marked differences in radioactivity of the two water modes clearly suggests that radioactive fingerprinting can provide a potential method for the identification groundwater sources in the UAE. (author)

MethodS of radioactive waste processing and disposal in the United Kingdom

International Nuclear Information System (INIS)

Tolstykh, V.D.

1983-01-01

The results of investigations into radioactive waste processing and disposal in the United Kingdom are discussed. Methods for solidification of metal and graphite radioactive wastes and radioactive slime of the Magnox reactors are described. Specifications of different installations used for radioactive waste disposal are given. Climatic and geological conditions in the United Kingdom are such that any deep storages of wastes will be lower than the underground water level. That is why dissolution and transport by underground waters will inevitably result in radionuclide mobility. In this connection an extended program of investigations into the main three aspects of disposal problem namely radionucleide release in storages, underground water transport and radionuclide migration is realized. The program is divided in two parts. The first part deals with retrival of hydrological and geochemical data on geological formations, development of specialized methods of investigations which are necessary for identification of places for waste final disposal. The second part represents theoretical and laboratory investigations into provesses of radionuclide transport in the system of ''sttorage-geological formation''. It is concluded that vitrification on the base of borosilicate glass is the most advanced method of radioactive waste solidification

Research programme on radioactive wastes - Synthesis report 2009

International Nuclear Information System (INIS)

Brander, S.

2010-02-01

This short synthesis report for the Swiss Federal Office of Energy (SFOE) issued by the head of the programme on radioactive wastes reports on activities during the year 2009. Background information on the definition of topics to be focussed on is briefly presented. In particular, topics such as communication with the general public, knowledge-saving and marking concepts for radioactive wastes are noted. Work done in these areas as well as on waste management in general are discussed. Conferences held and the transfer of know-how are noted, as is cooperation with foreign organisations active in the area of nuclear research and waste management. Finally, work planned for 2010 is noted

Use of Statistics for Data Evaluation in Environmental Radioactivity Measurements

International Nuclear Information System (INIS)

Sutarman

2001-01-01

Counting statistics will give a correction on environmental radioactivity measurement result. Statistics provides formulas to determine standard deviation (S B ) and minimum detectable concentration (MDC) according to the Poisson distribution. Both formulas depend on the background count rate, counting time, counting efficiency, gamma intensity, and sample size. A long time background counting results in relatively low S B and MDC that can present relatively accurate measurement results. (author)

Proposal for a questionnaire to assess risk perception concerning a radioactive waste repository

International Nuclear Information System (INIS)

Tanimoto, Katia Suemi

2011-01-01

One of the key features for public acceptance of nuclear energy is the belief that radioactive waste can be managed safely, in order to protect human beings from its possible harmful effects in present and future generations. In this sense, it is essential to understand how people perceive the risk associated with radioactive waste and which the main factors driving their attitudes toward its disposal are. One of the ways to achieve this understanding is through opinion polls. In this study, a questionnaire focused on the nuclear energy acceptability issue and its association with radioactive waste management was proposed, covering the following aspects: attitudes towards radioactive waste and nuclear power, credibility on institutions and sectors responsible by the nuclear safety, identification of perceived benefits, risk perception of specific technologies and activities, perception of real risk, emotional reaction comprehension and precautionary principle. Results obtained from a pilot questionnaire application are presented and discussed in this paper. (author)

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.)

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

Investigation on natural radioactive nuclide contents of rock products in Xi'an construction materials market

International Nuclear Information System (INIS)

Zhou Chunlin; Han Feng; Shang Aiguo; Li Tiantuo; Guo Huiping; Yie Lichao; Li Guifang

2001-01-01

The author reports the investigation results on natural radioactive nuclide contents of rock products from Xi'an construction materials market. The products were classified according to the national standard. The results show that natural radioactive nuclide contents in sampled rock products are in normal radioactive background levels. The radio-activity ranges of 238 U, 226 Ra, 232 Th and 40 K are 2.7 - 181.8, 0.92 - 271.0, 0.63 - 148.0, 1.8 - 1245 Bq·kg -1 , respectively. According to the national standard (JC 518-93), the application of some rock products must be limited

Long Term Behaviour Evaluation of Cement Conditioning Matrices Used for Management of Radioactive Wastes at IFIN-HH

International Nuclear Information System (INIS)

Dragolici, F.

2013-01-01

The mechanical and structural characterization of the radioactive waste conditioning matrix is very important during the final disposal stage in the radioactive waste management cycle. The conditioning products should be a monolith with acceptable mechanical, chemical and physical properties that are maintained over an appropriate time such that the release of radioactivity from the waste form in the environment is minimized. The aim of this work is the XRD application for the phase identification of matrix that simulates the conditioned radioactive waste and the correlation with mechanical performance. The selected matrices for the study are normal cement with iron precipitates (hydroxide and phosphate), mineral additives (bentonite and volcanic tuff) and complexing agents (tartaric, citric and oxalic acids). The results obtained by this analysis give information about the chemical reactions between the radioactive precipitates and the hydrates, hydrolysis products of the cement. (author)

Regulation of Transportation of Radioactive Material in Indonesia

International Nuclear Information System (INIS)

Nirwono, Muttaqin Margo; Choi, Kwang Sik

2011-01-01

1.1. Background Indonesia is a biggest archipelago country with 17,508 islands in 33 provinces. In transportation Indonesia has large number of airports, railways, roadways, waterways, and merchant marines. Since nuclear and radiation utilizations are expanding on whole country, the mobilization of these is usually placed outside of controlled facilities, in the public domain, and often entails movement between countries. The Indonesian Nuclear Energy Regulatory Agency (BAPETEN) is responsible for supervision and also authorization of the transport of radioactive material (TRM). TRM is the specific movement of a radioactive material consignment from origin to destination by public transportation (road or rail, water and air). This study aims to determine whether national regulation is harmonized with international practice in ensuring safety and security of TRM. The finding of this study will provide recommendation for enhancement of regulation on TRM. 1.2. Regulation of TRM in Indonesia Government Regulation (GR) No. 26, 2002 on the Safe Transport of Radioactive Material is implemented pursuant to Act 10, 1997 on Nuclear Energy. This GR was repealed GR 13, 1975 on TRM. The GR 26 consist of 16 chapters and 39 articles, included licensing: authority and responsibilities: packaging: radiation protection programme; training: quality assurance programme: type and activity limit of radioactive materials: radioactive materials with other dangerous properties: emergency preparedness: administrative sanction: and penal provisions. Principally, this GR adopted IAEA-TS-R-1, 'Regulations for the Safe Transport of Radioactive Material', 1996's Edition

Radionuclide identification using subtractive clustering method

International Nuclear Information System (INIS)

Farias, Marcos Santana; Mourelle, Luiza de Macedo

2011-01-01

Radionuclide identification is crucial to planning protective measures in emergency situations. This paper presents the application of a method for a classification system of radioactive elements with a fast and efficient response. To achieve this goal is proposed the application of subtractive clustering algorithm. The proposed application can be implemented in reconfigurable hardware, a flexible medium to implement digital hardware circuits. (author)

An EPIC Tale of the Quiescent Particle Background

Science.gov (United States)

Snowden, S.L.; Kuntz, K.D.

2017-01-01

Extended Source Analysis Software Use Based Empirical Investigation: (1) Builds quiescent particle background (QPB) spectra and images for observations of extended sources that fill (or mostly fill) the FOV i.e., annular background subtraction won't work. (2) Uses a combination of Filter Wheel Closed (FWC) and corner data to capture the spectral, spatial, and temporal variation of the quiescent particle background. New Work: (1) Improved understanding of the QPB (aided by adding a whole lot of data since 2008). (2) Significantly improved statistics (did I mention a LOT more data?). (3) Better characterization and identification of anomalous states. (4) Builds backgrounds for some anomalous state. (5) New efficient method for non-anomalous states.

Securing the Chernobyl exclusion zone against illegal movement of radioactive materials

International Nuclear Information System (INIS)

Bondarenko, O. O.; Proskura, M. I.; Duftschmid, K. E.; Kravchencko, N. E.

2004-01-01

. Within the framework of the IAEA Nuclear Security Program the technical cooperation project S trengthening Security of Nuclear Materials in Ukraine ( UKR/0/008) is aimed primarily to strengthen protection the entrance/exit checkpoints of the Chernobyl exclusion zone and adjacent State borders of Ukraine against illicit movement of radioactive materials (including nuclear materials). The particular situation of the exclusion zone presents a high risk of uncontrolled movement of radioactive materials from and into the exclusion zone. In view of the future construction of the S helter-2 a nd decommissioning of the three closed reactor blocks it is expected that the traffic through the exclusion zone will considerably increase in the next years and those large amounts of possibly contaminated metal scrap, construction material and equipment will leave the zone. There is also a risk of illegal movement of radioactive waste into the zone, possibly also through the international border, which could make the zone to an illegal dumping ground for radioactive waste. As practice shows theft of nuclear materials cannot be excluded. The general concept of the project is based on modernization of old and deployment of new vehicle (road and railway) and pedestrian monitoring equipment at all checkpoints of the exclusion zone including road checkpoints, train stations and river ports. A central station of data acquisition and management is to be located in Chernobyl. The equipment to be installed has to meet new technical requirements developed by IAEA. This includes, e.g. sensitivity of gamma and neutron detection, identification of innocent alarms caused by NORM materials or medical radioisotopes, accurate indication of the source position in the vehicle, and remote identification of license plate by advanced video systems. The implementation of the project and deployment of the equipment is expected to start in 2003 and should be completed in 2005. (Author)

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.)

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.)

Hazardous materials transportation. Part 2. Radioactive materials and wastes (citations from the NTIS Data Base). Final report for 1964--March 1978

International Nuclear Information System (INIS)

Reimherr, G.W.

1978-06-01

The bibliography cites studies on the hazards, risks, and uncertainty of transporting radioactive wastes and materials. The design of shipping containers and special labels for identification purposes for transporting fuels and wastes are also cited. Studies are included on legislation dealing with the safety and health of the population and the environmental problems associated with transporting radioactive materials

A perspective on the management of low-level radioactive waste

International Nuclear Information System (INIS)

Champ, D.R.; Charlesworth, D.H.

1994-01-01

In Canada, low-level radioactive waste (LLRW) is defined as all radioactive waste except spent fuel waste and tailings. At the time of the conference, the current practice was storage, but programs are underway to dispose of LLRW. AECL has applied for licensing of an intrusion-resistant underground structure. A comprehensive approach to LLRW management calls for: waste stream identification, waste characterization, waste segregation and characterization, waste processing, waste emplacement (storage or disposal); general principles are discussed under these headings. Performance assessment of disposal involves mathematical modelling. Progress has been slow, so if the Canadian nuclear industry does not eventually decide on a joint strategy for LLRW disposal, the federal government may have to impose a solution. 10 refs., 2 figs

The Utilization of Background Spectrum to Calibrate Gamma Spectrometry

International Nuclear Information System (INIS)

Mahrouka, M. M.; Mutawa, A. M.

2004-01-01

Many developed countries have very poor reference standards to calibrate their nuclear instrumentations or may find some difficulties to obtain a reference standard. In this work a simple way for Gamma spectrometry calibration was developed. The method depends on one reference point and additional points from the background. The two derived equations were applied to the analyses of radioactive nuclides in soil and liquid samples prepared by IAEA laboratories through AL MERA Project. The results showed the precision of the methodology used, as well as, the possibility of using some points in the background spectrum as a replacement for reference standards of Gamma spectrometry calibration. (authors)

Environmental effects associated with the transportation of radioactive material

International Nuclear Information System (INIS)

McClure, J.D.; Pope, R.B.; Yoshimura, H.R.

1979-01-01

The primary aim of this paper has been to describe some of the background information concerning nuclear materials transportation systems, accident statistics, accident severities, and test information - all of which when combined yield an environmental statement of the risks associated with the transportation of radioactive materials. The results of the ultimate risk analysis are expressed in terms of numbers of fatalities and, in that sense at least, tend to be an absolute measure of risk. When these risks are compared with other accepted societal risks, the relative risks associated with radioactive material transportation can be established. This information can be used to make decisions at the governmental level and to inform an interested public about these risks. It can be concluded that the risks associated with the transportation of radioactive material are low relative to the other risks that society has already accepted

Radioactive mineral occurences of Colorado and bibliography. [2500 citations in bibliography

Energy Technology Data Exchange (ETDEWEB)

Nelson-Moore, J.L.; Collins, D.B.; Hornbaker, A.L.

1978-01-01

This two-part report provides an essentially complete listing of radioactive occurrences in Colorado, with a comprehensive bibliography and bibliographic cross-indexes. Part 1 lists approximately 3000 known radioactive occurrences with their locations and brief accounts of the geology, mineralogy, radioactivity, host rock, production data, and source of data for each. The occurrences are classified by host rock and plotted on U.S. Geological Survey 1/sup 0/ x 2/sup 0/ topographic quadrangle maps with a special 1 : 100,000-scale base map for the Uravan mineral belt. Part 2 contains the bibliography of approximately 2500 citations on radioactive mineral occurrences in the state, with cross-indexes by county, host rock, and the special categories of ''Front Range,'' ''Colorado Plateau,'' and ''thorium.'' The term ''occurrence'' as used in this report is defined as any site where the concentration of uranium or thorium is at least 0.01% or where the range of radioactivity is greater than twice the background radioactivity. All citations and occurrence data are stored on computer diskettes for easy retrieval, correction, and updating.

A summary of the geotechnical and environmental investigations pertaining to the Vaalputs national radioactive waste disposal facility

International Nuclear Information System (INIS)

Hambleton-Jones, B.B.; Levin, M.; Camisani-Calzolari, F.A.G.M.

1986-08-01

This report describes the geological environmental surveys that lead to the choice and final evaluation of the Vaalputs national facility for the disposal of radioactive waste. This survey looked at the geography, demography, ecology, meteorology, geology, geohydrology and background radiological characteristics of the Vaalputs radioactive waste facility

The environmental impact of radioactive releases from accidents in nuclear power reactors

International Nuclear Information System (INIS)

Beattie, J.R.; Griffiths, R.F.; Kaiser, G.D.; Kinchin, G.H.

1978-01-01

A survey of accidental releases of radioactivity from thermal and fast reactors is presented. Following a general discussion on the hazards involved, the nature of the environmental impact of radioactive releases is examined. This includes a brief review of the natural radiation background, the effect on human health of various levels of radiation and radioactivity, permissible and reference levels, and the type of hazards from both passing clouds of airbourne radioactive material and from ground deposited material. The problem of atmospheric dispersion and methods of calculations of radioactive materials in the atmosphere are examined in order for the consequences of accidental release to be analysed. National accidents and their environmental consequences are then examined. Finally there is a review of the risks to which man is always exposed because of his environment. Common and collective risks are also considered. Conclusions are reached as to the acceptibility or otherwise of the environmental impact of reactor accidents. (U.K.)

Radioactive waste management

International Nuclear Information System (INIS)

2013-01-01

This eighth chapter presents the radioactive wastes and waste disposal; classification of radioactive wastes; basis requests of the radioactive waste management; conditions for a radioactive waste disposal; registers and inventories; transport of radioactive wastes from a facility to another and the radioactive waste management plan

Innovative concept for a major breakthrough in atmospheric radioactive xenon detection for nuclear explosion monitoring

International Nuclear Information System (INIS)

Le Petit, G.; Cagniant, A.; Gross, P.; Achim, P.; Douysset, G.; Taffary, T.; Moulin, C.; Morelle, M.

2013-01-01

The verification regime of the comprehensive test ban treaty (CTBT) is based on a network of three different waveform technologies together with global monitoring of aerosols and noble gas in order to detect, locate and identify a nuclear weapon explosion down to 1 kt TNT equivalent. In case of a low intensity underground or underwater nuclear explosion, it appears that only radioactive gases, especially the noble gas which are difficult to contain, will allow identification of weak yield nuclear tests. Four radioactive xenon isotopes, 131m Xe, 133m Xe, 133 Xe and 135 Xe, are sufficiently produced in fission reactions and exhibit suitable half-lives and radiation emissions to be detected in atmosphere at low level far away from the release site. Four different monitoring CTBT systems, ARIX, ARSA, SAUNA, and SPALAX TM have been developed in order to sample and to measure them with high sensitivity. The latest developed by the French Atomic Energy Commission (CEA) is likely to be drastically improved in detection sensitivity (especially for the metastable isotopes) through a higher sampling rate, when equipped with a new conversion electron (CE)/X-ray coincidence spectrometer. This new spectrometer is based on two combined detectors, both exhibiting very low radioactive background: a well-type NaI(Tl) detector for photon detection surrounding a gas cell equipped with two large passivated implanted planar silicon chips for electron detection. It is characterized by a low electron energy threshold and a much better energy resolution for the CE than those usually measured with the existing CTBT equipments. Furthermore, the compact geometry of the spectrometer provides high efficiency for X-ray and for CE associated to the decay modes of the four relevant radioxenons. The paper focus on the design of this new spectrometer and presents spectroscopic performances of a prototype based on recent results achieved from both radioactive xenon standards and air sample

Radioactive waste management in the former USSR

Energy Technology Data Exchange (ETDEWEB)

Bradley, D.J.

1992-06-01

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

Radioactive waste management in the former USSR

International Nuclear Information System (INIS)

Bradley, D.J.

1992-06-01

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes

Radioactive wastes in Oklo; Desechos radiactivos en Oklo

Energy Technology Data Exchange (ETDEWEB)

Balcazar, M.; Flores R, J.H.; Pena, P.; Lopez, A. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2006-07-01

The acceptance of the Nuclear Energy as electric power supply implies to give answer to the population on the two main challenges to conquer in the public opinion: the nuclear accidents and the radioactive wastes. Several of the questions that are made on the radioactive wastes, its are the mobility migration of them, the geologic stability of the place where its are deposited and the possible migration toward the aquifer mantels. Since the half lives of the radioactive waste of a Nuclear Reactor are of several hundred of thousands of years, the technical explanations to the previous questions little convince to the public in general. In this work summary the results of the radioactive waste generated in a natural reactor, denominated Oklo effect that took place in Gabon, Africa, it makes several thousands of millions of years, a lot before the man appeared in the Earth. The identification of at least 17 reactors in Oklo it was carried out thanks to the difference in the concentrations of Uranium 235 and 238 prospective, and to the analysis of the non-mobility of the radioactive waste in the site. It was able by this way to determine that the reactors with sizes of hardly some decimeter and powers of around 100 kilowatts were operating in intermittent and spontaneous form for space of 150,000 years, with operation cycles of around 30 minutes. Recent studies have contributed information valuable on the natural confinement of the radioactive waste of the Oklo reactors in matrixes of minerals of aluminum phosphate that caught and immobilized them for thousands of millions of years. This extracted information from the nature contributes guides and it allows 'to verify' the validity of the current proposals on the immobilization of radioactive wastes of a nuclear reactor. This work presents in clear and accessible form to the public in general on the secure 'design', operation, 'decommissioning' and 'storage' of the radioactive

Nuclear energy from radioactive waste

International Nuclear Information System (INIS)

Schwarzenberg, M.

1998-01-01

The global energy demand is increasing. Sound forecasts indicate that by the year 2020 almost eight thousand million people will be living on our planet, and generating their demand for energy will require conversion of about 20 thousand million tonnes of coal equivalents a year. Against this background scenario, a new concept for energy generation elaborated by nuclear scientists at CERN attracts particular interest. The concept describing a new nuclear energy source and technology intends to meet the following principal requirements: create a new energy source that can be exploited in compliance with extremely stringent safety requirements; reduce the amount of long-lived radioactive waste; substantially reduce the size of required radwaste repositories; use easily available natural fuels that will not need isotopic separation; prevent the risk of proliferation of radioactive materials; process and reduce unwanted actinides as are generated by the operation of current breeder reactors; achieve high efficiency both in terms of technology and economics. (orig./CB) [de

NATURAL RADIOACTIVITY LEVEL AND ELEMENTAL COMPOSITION OF SOIL SAMPLES FROM A HIGH BACKGROUND RADIATION AREA ON EASTERN COAST OF INDIA (ODISHA).

Science.gov (United States)

Sahoo, S K; Kierepko, R; Sorimachi, A; Omori, Y; Ishikawa, T; Tokonami, S; Prasad, G; Gusain, G S; Ramola, R C

2016-10-01

A comprehensive study was carried out to determine the radioactivity concentration of soil samples from different sites of a high background radiation area in the eastern coast of India, Odisha state. The dose rate measured in situ varied from 0.25 to 1.2 µSv h -1 The gamma spectrometry measurements indicated Th series elements as the main contributors to the enhanced level of radiation and allowed the authors to find the mean level of the activity concentration (±SD) for 226 Ra, 228 Th and 40 K as 130±97, 1110±890 and 360±140 Bq kg -1 , respectively. Human exposure from radionuclides occurring outdoor was estimated based on the effective dose rate, which ranged from 0.14±0.02 to 2.15±0.26 mSv and was higher than the UNSCEAR annual worldwide average value 0.07 mSv. Additionally, X-ray fluorescence analysis provided information about the content of major elements in samples and indicated the significant amount of Ti (7.4±4.9 %) in soils. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Back to the land: the sea-to-land transfer of radioactive pollution

International Nuclear Information System (INIS)

Deere-Jones, T.

1991-01-01

The British nuclear industry insists that its radioactive discharges into the sea are too small to affect human health. But this assertion is made against a background of basic ignorance about the behaviour of radioactivity in the seas and major uncertainties over the health effects of low-level radiation. The industry has ignored much evidence showing that the coastal population of the UK are exposed to significant doses of radiation originating from marine discharges from nuclear plant. (author)

High-level radioactive waste management in the United States. Background and status: 1996

International Nuclear Information System (INIS)

Dyer, J.R.

1996-01-01

The US high-level radioactive waste disposal program is investigating a site at Yucca Mountain, Nevada, to determine whether or not it is a suitable location for the development of a deep mined geologic repository. At this time, the US program is investigating a single site, although in the past, the program involved successive screening and comparison of alternate locations. The United States civilian reactor programs do not reprocess spent fuel; the high-level waste repository will be designed for the emplacement or spent fuel and a limited amount of vitrified high-level wastes from previous reprocessing in the US. The legislation enabling the US program also contains provisions for a Monitored Retrievable Storage facility, which could provide temporary storage of spent fuel accepted for disposal, and improve the flexibility of the repository development schedule

Purification of cerium, neodymium and gadolinium for low background experiments

Directory of Open Access Journals (Sweden)

Boiko R.S.

2014-01-01

Full Text Available Cerium, neodymium and gadolinium contain double beta active isotopes. The most interesting are 150Nd and 160Gd (promising for 0ν2β search, 136Ce (2β+ candidate with one of the highest Q2β. The main problem of compounds containing lanthanide elements is their high radioactive contamination by uranium, radium, actinium and thorium. The new generation 2β experiments require development of methods for a deep purification of lanthanides from the radioactive elements. A combination of physical and chemical methods was applied to purify cerium, neodymium and gadolinium. Liquid-liquid extraction technique was used to remove traces of Th and U from neodymium, gadolinium and for purification of cerium from Th, U, Ra and K. Co-precipitation and recrystallization methods were utilized for further reduction of the impurities. The radioactive contamination of the samples before and after the purification was tested by using ultra-low-background HPGe gamma spectrometry. As a result of the purification procedure the radioactive contamination of gadolinium oxide (a similar purification efficiency was reached also with cerium and neodymium oxides was decreased from 0.12 Bq/kg to 0.007 Bq/kg in 228Th, from 0.04 Bq/kg to <0.006 Bq/kg in 226Ra, and from 0.9 Bq/kg to 0.04 Bq/kg in 40K. The purification methods are much less efficient for chemically very similar radioactive elements like actinium, lanthanum and lutetium.

Environmental policy. Ambient radioactivity levels and radiation doses in 1998

International Nuclear Information System (INIS)

1999-11-01

The report contains information on the natural (background) radiation exposure (chapter II), the natural radiation exposure as influenced by anthropogenic effects (chapter III), the anthropogenic radiation exposure (chapter IV), and the radiation doses to the environment and the population emanating from the Chernobyl fallout (chapter V). The natural radiation exposure is specified referring to the contributions from cosmic and terrestrial background radiation and intake of natural radioactive substances. Changes of the natural environment resulting from anthropogenic effects (technology applications) inducing an increase in concentration of natural radioactive substances accordingly increase the anthropogenic radiation exposure. Indoor air radon concentration in buildings for instance is one typical example of anthropogenic increase of concentration of natural radioactivity, primarily caused by the mining industry or by various materials processing activities, which may cause an increase in the average radiation dose to the population. Measurements so far show that indoor air concentration of radon exceeds a level of 200 Bq/m 3 in less than 2% of the residential buildings; the EUropean Commission therefore recommends to use this concentration value as a maximum value for new residential buildings. Higher concentrations are primarily measured in areas with relevant geological conditions and abundance of radon, or eg. in mining areas. (orig./CB) [de

Background radioactivity in the monazite areas of Kerala, India

International Nuclear Information System (INIS)

Soman, S.D.

1982-07-01

External radiation exposure measurements were carried out with natural CaF 2 thermoluminescence dosimeters (TLD) in about 2500 dwellings and on about 10.000 persons living in monazite areas of south-west coast of India. Statistical analysis of the data indicate that the values are distributed lognormally. A systematic study was carried out a Manavalakurichi plant of Indian Rare Earths Ltd. and adjoining high background areas to obtain typical average radiation exposure to different categories of workers from both occupation and non-occupation. Results of thoron measurements from the exhaled breath of plant workers are presented from which the body burden of natural thorium deposited in lungs can be estimated. An important pathway of exposure, for which children are most susceptible, is non-specific ingestion of raw sand itself. Data obtained on the radonuclide content of urinary excretion of children belonging to two age groups are discussed. (orig.) [de

Rapid method of identification of β-ray emitters and of β-radioactive impurity dosage (1961)

International Nuclear Information System (INIS)

Le Gallic, Y.; Legrand, J.; Grinberg, B.

1961-01-01

We describe a simple method of radioactive analysis, which allows an accurate determination of maximal energies of β-emitters, and detection and titration of radioactive impurities in radionuclides as well. The method described, which uses a plastic scintillator, is based on the fact that the curve obtained by plotting the number of pulses measured against the threshold is a straight line, in the case of pure β-emitters. We then derive a simple relation between the data of this straight line and the maximal energy of the β-spectrum of the radionuclide under consideration. (authors) [fr

Using radioactivity

International Nuclear Information System (INIS)

1982-10-01

The leaflet discusses the following: radioactivity; radioisotopes; uses of ionising radiations; radioactivity from (a) naturally occurring radioactive elements, and (b) artificially produced radioisotopes; uses of radioactivity in medicine, (a) clinical diagnostic, (b) therapeutic (c) sterilization of medical equipment and materials; environmental uses as tracers; industrial applications, e.g. tracers and radiography; ensuring safety. (U.K.)

Radioactive labelling with 125 I of infectious pancreatic necrosis virus

International Nuclear Information System (INIS)

Soler Ch, M.; Farias O, G.; Kuznar H, J.

1993-01-01

In order to understand the interaction between a cellular receptor and a ligand the photochemical crosslinking method has been widely used. This method has been utilized as an approach to determine the presence or absence of virus receptors in susceptible cells. Successful detection of crosslinks is achieved if one of the components, in the crosslinked product, has been radioactively labeled. The incorporation of a radioactive isotope, in the virus-receptor complex, enables the identification of the receptor. To undertake this study in the future, in this communication the radioactive labeling of virus particles is presented. The infectious necrosis pancreatic virus (IPN virus) was the chosen moiety to be in vitro labeled with 125 I using a direct method. Three oxidizing agents were used in the iodination procedure for comparison: an enzyme, lactoperoxidase and two chemical reagents, N-Chloro-benceno-sulfonamide (Iodo-Beads) and 1,3,4,6-Tetra chloro-3a,6a-diphenyl glycouril (Iodo-Gen). The results are analysed to select the method which guarantee the incorporation of 125 I in the viral capsid protein, while preserving its full infectivity. (author)

Risk assessments for the disposal of high level radioactive wastes

International Nuclear Information System (INIS)

Smith, C.F.

1975-01-01

The risks associated with the disposal of high level wastes derive from the potential for release of radioactive materials into the environment. The assessment of these risks requires a methodology for risk analysis, an identification of the radioactive sources, and a method by which to express the relative hazard of the various radionuclides that comprise the high level waste. The development of a methodology for risk analysis is carried out after a review of previous work in the area of probabilistic risk assessment. The methodology suggested involves the probabilistic analysis of a general accident consequence distribution. In this analysis, the frequency aspect of the distribution is treated separately from the normalized probability function. At the final stage of the analysis, the frequency and probability characteristics of the distribution are recombined to provide an estimate of the risk. The characterization of the radioactive source term is accomplished using the ORIGEN computer code. Calculations are carried out for various reactor types and fuel cycles, and the overall waste hazard for a projected thirty-five year nuclear power program is determined

Radioactive battery

International Nuclear Information System (INIS)

Deaton, R.L.; Silver, G.L.

1975-01-01

A radioactive battery is described that is comprised of a container housing an electrolyte, two electrodes immersed in the electrolyte and insoluble radioactive material disposed adjacent one electrode. Insoluble radioactive material of different intensity of radioactivity may be disposed adjacent the second electrode. If hydrobromic acid is used as the electrolyte, Br 2 will be generated by the radioactivity and is reduced at the cathode: Br 2 + 2e = 2 Br - . At the anode Br - is oxidized: 2Br - = Br 2 + 2e. (U.S.)

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)

Transportation of radioactive materials: the legislative and regulatory information system

International Nuclear Information System (INIS)

Fore, C.S.

1982-03-01

The US Department of Energy is carrying out a national program to assure the safe shipment of radioactive materials. As part of this overall effort, the Hazardous Materials Information Center of Oak Ridge National Laboratory has developed the comprehensive Legislative and Regulatory Information System, which contains information on federal-, state-, and local-level legislative and regulatory actions pertaining primarily to the shipment of radioactive materials. Specific subject areas chosen to highlight particular transportation restrictions include: (1) identification of state agency responsible for regulating transportation, (2) type of escorts required, (3) areas requiring prior notification, (4) areas requiring permits or licenses, and (5) areas totally banning transportation of all radioactive materials. Other legislative information being categorized and of immediate relevance to the transportation issues is covered under the areas of disposal, storage, and management of radioactive materials; establishment of additional regulations; emergency response regulations; moratoriums on power plant construction and siting; radiation safety and control studies; and remedial action studies. The collected information is abstracted, indexed, and input into one of the two data bases developed under this information system - Current Legislation Data Base and Historical Legislation Data Base. An appendix is included which provides a summary of the state and local laws affecting the transportation of radioactive materials throughout the United States. The Legislative and Regulatory Information System is supported by the Transportation Technology Center located at Sandia National Laboratories, Albuquerque, New Mexico

Transportation of radioactive materials: the legislative and regulatory information system

Energy Technology Data Exchange (ETDEWEB)

Fore, C.S.

1982-03-01

The US Department of Energy is carrying out a national program to assure the safe shipment of radioactive materials. As part of this overall effort, the Hazardous Materials Information Center of Oak Ridge National Laboratory has developed the comprehensive Legislative and Regulatory Information System, which contains information on federal-, state-, and local-level legislative and regulatory actions pertaining primarily to the shipment of radioactive materials. Specific subject areas chosen to highlight particular transportation restrictions include: (1) identification of state agency responsible for regulating transportation, (2) type of escorts required, (3) areas requiring prior notification, (4) areas requiring permits or licenses, and (5) areas totally banning transportation of all radioactive materials. Other legislative information being categorized and of immediate relevance to the transportation issues is covered under the areas of disposal, storage, and management of radioactive materials; establishment of additional regulations; emergency response regulations; moratoriums on power plant construction and siting; radiation safety and control studies; and remedial action studies. The collected information is abstracted, indexed, and input into one of the two data bases developed under this information system - Current Legislation Data Base and Historical Legislation Data Base. An appendix is included which provides a summary of the state and local laws affecting the transportation of radioactive materials throughout the United States. The Legislative and Regulatory Information System is supported by the Transportation Technology Center located at Sandia National Laboratories, Albuquerque, New Mexico.

Characterization of the InSTEC's low-background gamma spectrometer for environmental radioactivity studies

International Nuclear Information System (INIS)

Diaz Rizo, O.; Lopez Pino, N.; D'Alessandro Rodriguez, K.; Reyes, H.; Padilla Cabal, F.; Arado Lopez, J.O.; Casanova Diaz, A.O.; Gelen Rudnikas, A.; Rodenas Palomino, C.; Gomez Arozamena, J.

2010-01-01

The capabilities of the Low-Background Gamma Spectrometer (LBGS) at InSTEC were studied for environmental purposes. Fifty three γ-lines were identified in the LBGS background spectrum. The Minimum Detectable Activity for 2 10 Pb, 2 38 U, 2 26 Ra, 1 37 Cs, 2 32 Th and 4 0K were calculated using the detector's volumetric efficiency simulated by the Monte Carlo method. Validation was performed by absolute and relative analysis of radionuclide activities present in a marine sediment certified material. (author)

Detection of radioactive material in public places: BARC's handheld tele radionuclide detector

International Nuclear Information System (INIS)

Bharade, S.K.; Sinha, Vineet; Vinod, M.; Ananthakrishnan, T.S.; Jindal, G.D.; Srivastava, Shikha; Sarade, Bhagyashree; Kamble, Ashok D.; Pithawa, C.K.; Subramanian, Venkat

2011-01-01

Electronics Division, BARC has developed a compact and portable system for detection of radioactive nuclides like 60 Co, 137 Cs etc. with high levels of radioactivity. These radioactive sources, because of their long life and relative ease of availability, have the potential of being used in radiological dispersion devices (dirty bombs) for panic creation in public places. The unit comprises of a compact CsI detector, photo diode and front-end electronics, micro-controller, a GPS module and Blue-tooth connectivity. The application software running on the mobile phone provides the interface as well as transmission of data to remote server. This is highly suitable for covert operations. The person, who carries this instrument, suitably camouflaged, also has a mobile phone in his pocket, which is connected to the system via blue tooth. On detection of activity above set limit, the system sends an alarm to the mobile phone. The mobile phone can be kept in vibration mode in order to avoid any undue attention. The graphical display on screen of mobile phone provides an indication of activity and the isotope identification. Simultaneously, the mobile phone sends information about the activity detected and source identification automatically along with the location of the instrument (longitude and latitude), provided by the GPS module in the instrument, to a remote server. The remote server provides radiation information on a map with position-coordinates. Based on this, necessary action can be initiated by the security personnel. (author)

Photon and electron identification with the ATLAS detector

CERN Document Server

AUTHOR|(INSPIRE)INSPIRE-00431162; The ATLAS collaboration

2016-01-01

The identification of prompt photons and the rejection of background, originating mostly from photons from hadron decays, relies on the high granularity of the ATLAS calorimeter. The electron identification is based on a likelihood discriminant to separate isolated electron from background electron originating from photon conversions, hadron misidentification and heavy flavour decays. Additionally, isolation variables provide further handles to separate signal and background. The measurements of the efficiencies of the electron and photon identification and isolation selections are performed with data. Tag and probe techniques are used with Z$\\rightarrow$ee, J/$\\psi$ $\\rightarrow$ee and Z$\\rightarrow$l l$\\gamma$ decays. Inclusive photon samples are also used to measure photon identification efficiency.\\\\ The results of these measurement with the pp collisions data recorded in 2015 at $\\sqrt {s}$ = 13 TeV, corresponding to an integrated luminosity of 3.2 fb$^{-1}$, are presented. as well as a first look at 201...

Recent Research Status on the Microbes in the Radioactive Waste Disposal and Identification of Aerobic Microbes in a Groundwater Sampled from the KAERI Underground Research Tunnel(KURT)

International Nuclear Information System (INIS)

Baik, Min Hoon; Lee, Seung Yeop; Cho, Won Jin

2006-11-01

In this report, a comprehensive review on the research results and status for the various effects of microbes in the radioactive waste disposal including definition and classification of microbes, and researches related with the waste containers, engineered barriers, natural barriers, natural analogue studies, and radionuclide migration and retardation. Cultivation, isolation, and classification of aerobic microbes found in a groundwater sampled from the KAERI Underground Research Tunnel (KURT) located in the KAERI site have carried out and over 20 microbes were found to be present in the groundwater. Microbial identification by a 16S rDNA genetic analysis of the selected major 10 aerobic microbes was performed and the identified microbes were characterized

Radioactive Contamination Estimation from micro-copters or helicopter Airborne survey: Simulation and real measurements

International Nuclear Information System (INIS)

Halevy, I.; Ghelman, M.; Yehuda-Zada, Y.; Manor, A.; Dadon, S.; Sharon, A.; Yaar, I.

2014-01-01

One of the main advantages of acquiring aero-radiometric measurements lies in the high collection rate of data over large areas and rough terrain. Typical aero-radiometric system records and saves gamma ray spectrum, correlated with the GPS derived location information in regular time intervals of one to two seconds. Such data can be used to locate radiation anomalies on the ground, map ground contamination or track a radioactive airborne plume. Acquiring spectral data of this type allows separation of natural radioactivity from that of man-made sources and identification of specific isotopes, natural or man-made

Radioactive Contamination Estimation from Micro-Copters or Helicopter Airborne Survey: Simulation and Real Measurements

International Nuclear Information System (INIS)

Halevy, I.; Ghelman, M.; Yehuda-Zada, Y.; Manor, A.; Sharon, A.; Yaar, I.

2014-01-01

One of the main advantages of acquiring aero-radiometric measurements lies in the high collection rate of data over large areas and rough terrain. Typical aero-radiometric system records and saves gamma ray spectrum, correlated with the GPS derived location information in regular time intervals of one to two seconds. Such data can be used to locate radiation anomalies on the ground, map ground contamination or track a radioactive airborne plume. Acquiring spectral data of this type allows separation of natural radioactivity from that of man-made sources and identification of specific isotopes, natural or man-made

Radioactivity measurements and control solutions

International Nuclear Information System (INIS)

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

2003-01-01

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

Introduction to naturally occurring radioactive material

Energy Technology Data Exchange (ETDEWEB)

Egidi, P.

1997-08-01

Naturally occurring radioactive material (NORM) is everywhere; we are exposed to it every day. It is found in our bodies, the food we eat, the places where we live and work, and in products we use. We are also bathed in a sea of natural radiation coming from the sun and deep space. Living systems have adapted to these levels of radiation and radioactivity. But some industrial practices involving natural resources concentrate these radionuclides to a degree that they may pose risk to humans and the environment if they are not controlled. Other activities, such as flying at high altitudes, expose us to elevated levels of NORM. This session will concentrate on diffuse sources of technologically-enhanced (TE) NORM, which are generally large-volume, low-activity waste streams produced by industries such as mineral mining, ore benefication, production of phosphate Fertilizers, water treatment and purification, and oil and gas production. The majority of radionuclides in TENORM are found in the uranium and thorium decay chains. Radium and its subsequent decay products (radon) are the principal radionuclides used in characterizing the redistribution of TENORM in the environment by human activity. We will briefly review other radionuclides occurring in nature (potassium and rubidium) that contribute primarily to background doses. TENORM is found in many waste streams; for example, scrap metal, sludges, slags, fluids, and is being discovered in industries traditionally not thought of as affected by radionuclide contamination. Not only the forms and volumes, but the levels of radioactivity in TENORM vary. Current discussions about the validity of the linear no dose threshold theory are central to the TENORM issue. TENORM is not regulated by the Atomic Energy Act or other Federal regulations. Control and regulation of TENORM is not consistent from industry to industry nor from state to state. Proposed regulations are moving from concentration-based standards to dose

Natural radiation background in the ancient city of Palmyra

International Nuclear Information System (INIS)

Shweikani, R.; Al-Masri, M.S.; Hushari, M.; Raja, G.; Aissa, M.; Al-Hent, R.

2012-01-01

Natural radiation background has been determined for the Ancient City of Palmyra and its surrounding areas. Car-borne gamma spectrometry, indoor radon gas concentration and natural radionuclides levels in environmental samples (soil, water and plants) have been determined. Two types of dwelling were involved in this study, one with cancer cases, and the others without. The results showed that indoor radon gas concentrations and radiation exposure rates are within reported mean background levels in Syria (45 Bq m −3 and less than 0.1 μSv h −1 , respectively); no differences were noticed between the dwelling groups. In addition, the results did not indicate any relation between recorded cancers and measured natural radioactivity.

Technical summary of Groundwater Quality Protection Program at Savannah River Plant. Volume II. Radioactive waste

International Nuclear Information System (INIS)

Stone, J.A.; Christensen, E.J.

1983-12-01

This report (Volume II) presents representative monitoring data for radioactivity in groundwater at SRP. Four major groups of radioactive waste disposal sites and three minor sites are described. Much of the geohydrological and and other background information given in Volume I is applicable to these sites and is incorporated by reference. Several of the sites that contain mixed chemical and radioactive wastes are discussed in both Volumes I and II. Bulk unirradiated uranium is considered primarily a chemical waste which is addressed in Volume I, but generally not in Volume II

Characterization of the InSTEC's low-background gamma spectrometer for environmental radioactivity studies

International Nuclear Information System (INIS)

Diaz Rizo, O.; Lopez Pino, N.; D'Alessandro Rodriguez, K.; Reyes, H.; Padilla Cabal, F.; Arado Lopez, J.O.; Casanova Diaz, A.O.; Gelen Rudnikas, A.; Rodenas Palomino, C.; Gomez Arozamena, J.

2009-01-01

The capabilities of the Low-Background Gamma Spectrometer (LBGS) at InSTEC were studied for environmental purposes. Fifty three ?-lines were fixed/identified? in the LBGS background spectrum. The Minimum Detectable Activity for 2 10 Pb, 2 38 U, 2 26 Ra, 1 37 Cs, 2 32 Th and 4 0K were calculated using the detector's volumetric efficiency simulated by the Monte Carlo method. The radionuclide activities in a marine sediment standard reference material? were determined by absolute and relative methods for validation./¿absolute and relative validation? (author)

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

International Nuclear Information System (INIS)

Wollel Tiruneh, Getachew; Wodaje Kebede, Worku

2008-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2008-11-15

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

Strategies and methodologies for applied marine radioactivity studies

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-04-01

The main objective of this document is to provide basic training in the theoretical background and practical applications of the methodologies for the measurement, monitoring and assessment of radioactivity in marine environment. This manual is a compilation of lectures and notes that have been presented at previous training courses. The document contains 16 individual papers, each of them was indexed separately.

Strategies and methodologies for applied marine radioactivity studies

International Nuclear Information System (INIS)

1997-01-01

The main objective of this document is to provide basic training in the theoretical background and practical applications of the methodologies for the measurement, monitoring and assessment of radioactivity in marine environment. This manual is a compilation of lectures and notes that have been presented at previous training courses. The document contains 16 individual papers, each of them was indexed separately

Henri Becquerel and the discovery of natural radioactivity

International Nuclear Information System (INIS)

Barquins, M.

2003-01-01

This article presents the life and achievements of Henri Becquerel particularly in the domain of natural radioactivity which he discovered. In 1903 H.Becquerel was awarded the Nobel prize of physics (jointly with the Curies). The author highlights the importance of his talent but also the influence of his family background: his grand-father and father were both renowned scientists

Radioactive waste - a select list of material

International Nuclear Information System (INIS)

Lambert, C.M.

1982-01-01

A chronological bibliography is presented of literature relating to radioactive waste management in the United Kingdom concentrating on material published since 1978. The main sections include Dept. of Environ. and Official publications, administrative and environmental concerns, technological and scientific considerations, including publications on geological aspects, deep-sea bed and ocean-dumping and salt domes, with general background material and further sources of information listed at the end. (U.K.)

The radioactive waste management policy and practice in the Czech Republic

International Nuclear Information System (INIS)

Kucerka, M.

1996-01-01

In recent period, the new Czech Atomic Law is in the final stage of preparation, and the author expects that Parliament of the Czech Republic will approve it in the first half of the year 1996. Partly the law deals with new distribution of responsibilities among bodies involved in utilization of nuclear energy and ionizing radiation, the state and local authorities. The new provisions include also radioactive waste management activities. These provisions clarify the relations between radioactive waste generators and state, and define explicitly duties of waste generators. One of the most important duties is to cover all expenses for radioactive waste management now and in the future, including radioactive waste disposal and decommissioning of nuclear facilities. The law establishes radioactive waste management and decommissioning funds and the new, on waste generators independent radioactive waste management organization, controlled by state, to ensure the safety of inhabitants and the environment, and a optimization of expenses. Parallel to the preparation of the law, the Ministry of Industry and Trade prepares drafts of a statute of the radioactive waste management organization and its control board, and of the methodology and rules of management the radioactive waste fund. First drafts of these documents are expected to be complete in January 1996. The paper will describe recent practice and policy of the radioactive waste management including uranium mining and milling tailings, amounts of waste and its activities, economical background, and safety. A special attention will be paid to description of expected changes in connection with the new Atomic Law and expected steps and time schedule of reorganization of the radioactive waste management structure in the Czech Republic

Radioactive situation in Kyrgyzstan: problems and perspectives

International Nuclear Information System (INIS)

Karimov, K.A.

2000-01-01

One of the major problems of the environment contamination in Kyrgyzstan is the development of radioactive and toxic pollution caused by nuclear tests, technogene accidents which took place in neighboring countries, and breach of safe storage and destruction of uranium and hazardous waste tailings. Long-term nuclear tests in various areas of the world and the accident at the NPP have caused the origin of stratospheric deposit of artificial radionuclides, the fallout of which have led to radioactive pollution of the biosphere. Maximum fallout have been observed in the latitudinal zone of 40-60 degrees and in the mountainous regions. As a result of many years of research the main sources of radioactive contamination have been established. It is shown that stratospheric or tropospheric and local fallout have permanently exposed the territory of Kyrgyzstan to the pollution by radionuclides. A brief description of radioactive contamination of the environment in Kyrgyzstan from remote external sources and atmospheric mechanisms of its transfer delineated on the basis of long-term observation of geophysical and atmospheric parameters and regular radiation monitoring have been presented. The investigated mechanisms can be used to interpret the sharp increase of the radioactive background and to estimate the risk to the environment and human health. Some methodological questions about the influence of geophysical conditions on the territorial distribution of contamination have bee considered. The tropospheric mechanism of contamination transfer for different seasons of year has been suggested. The uranium tailings located in mountain regions near densely populated areas and and groundwater basins are the internal sources of radioactive contamination in Kyrgyzstan. Waste products of uranium production present a real treat for the environment and public health. The problem of environment security in connection with destruction of uranium tailings has been discussed. Till now

Radioactive Decay

Science.gov (United States)

Radioactive decay is the emission of energy in the form of ionizing radiation. Example decay chains illustrate how radioactive atoms can go through many transformations as they become stable and no longer radioactive.

Radioactive waste management

International Nuclear Information System (INIS)

Kawakami, Yutaka

2008-01-01

Radioactive waste generated from utilization of radioisotopes and each step of the nuclear fuel cycle and decommissioning of nuclear facilities are presented. On the safe management of radioactive waste management, international safety standards are established such as ''The Principles of Radioactive Waste Management (IAEA)'' and T he Joint Convention on the Safety of Radioactive Waste Management . Basic steps of radioactive waste management consist of treatment, conditioning and disposal. Disposal is the final step of radioactive waste management and its safety is confirmed by safety assessment in the licensing process. Safety assessment means evaluation of radiation dose rate caused by radioactive materials contained in disposed radioactive waste. The results of the safety assessment are compared with dose limits. The key issues of radioactive waste disposal are establishment of long term national strategies and regulations for safe management of radioactive waste, siting of repository, continuity of management activities and financial bases for long term, and security of human resources. (Author)

Radioactive aerosols

International Nuclear Information System (INIS)

Chamberlain, A.C.

1991-01-01

Radon. Fission product aerosols. Radioiodine. Tritium. Plutonium. Mass transfer of radioactive vapours and aerosols. Studies with radioactive particles and human subjects. Index. This paper explores the environmental and health aspects of radioactive aerosols. Covers radioactive nuclides of potential concern to public health and applications to the study of boundary layer transport. Contains bibliographic references. Suitable for environmental chemistry collections in academic and research libraries

Radioactive source

International Nuclear Information System (INIS)

Drabkina, L.E.; Mazurek, V.; Myascedov, D.N.; Prokhorov, P.; Kachalov, V.A.; Ziv, D.M.

1976-01-01

A radioactive layer in a radioactive source is sealed by the application of a sealing layer on the radioactive layer. The sealing layer can consist of a film of oxide of titanium, tin, zirconium, aluminum, or chromium. Preferably, the sealing layer is pure titanium dioxide. The radioactive layer is embedded in a finish enamel which, in turn, is on a priming enamel which surrounds a substrate

Characteristics of radioactive waste streams generated in HTGR fuel reprocessing

International Nuclear Information System (INIS)

Lin, K.H.

1976-01-01

Results are presented of a study concerned with identification and characterization of radioactive waste streams from an HTGR fuel reprocessing plant. Approximate quantities of individual waste streams as well as pertinent characteristics of selected streams have been estimated. Most of the waste streams are unique to HTGR fuel reprocessing. However, waste streams from the solvent extraction system and from the plant facilities do not differ greatly from the corresponding LWR fuel reprocessing wastes

Shipment of radioactive materials by the US Department of Energy

International Nuclear Information System (INIS)

1986-01-01

This brochure provides notification of, and information on, the general types of radioactive material shipments being transported for or on behalf of DOE in commerce across state and other jurisdictional boundaries. This brochure addresses: packaging and material types, shipment identification, modes of transport/materials shipped, DOE policy for routing and oversize/overweight shipments, DOE policy for notification and cargo security, training, emergency assistance, compensation for nuclear accidents, safety record, and principal DOE contact

Disposal of radioactive wastes

International Nuclear Information System (INIS)

Dlouhy, Z.

1982-01-01

This book provides information on the origin, characteristics and methods of processing of radioactive wastes, as well as the philosophy and practice of their storage and disposal. Chapters are devoted to the following topics: radioactive wastes, characteristics of radioactive wastes, processing liquid and solid radioactive wastes, processing wastes from spent fuel reprocessing, processing gaseous radioactive wastes, fixation of radioactive concentrates, solidification of high-level radioactive wastes, use of radioactive wastes as raw material, radioactive waste disposal, transport of radioactive wastes and economic problems of radioactive wastes disposal. (C.F.)

Application of the permeation to the production of low radioactive calibrated gas flows. Low radioactive tritium measurement

International Nuclear Information System (INIS)

Pilot, Guy.

1979-12-01

The permeation of compounds (HT, HTO, 131 ICH 3 , and 129 ICH 3 ) through organic membranes in view of producing low radioactive calibrated gas flows has been studied. This process of which the diffusion is the main stage enables respecting certain conditions (choice of the membrane, temperature, partial pressure differential) our aims to be reached with a good accuracy. In order to measure radioactivity of tritiated standard gases, a detector was built. This detector is an Oeschger type proportional counter with a total volume of 17.4 dm 3 and an useful volume of 3.9 dm 3 . In the conditions of operation, the background is of 1.7.10 -6 I s -1 cm -3 . The counter coupled with a feed-rack enables various samples to be measured and it is possible in the best conditions to detect some 10 -11 μCi cm -3 NTP [fr

Lowering the radioactivity of the photomultiplier tubes for the XENON1T dark matter experiment

Energy Technology Data Exchange (ETDEWEB)

Aprile, E.; Contreras, H.; Goetzke, L.W.; Fernandez, A.J.M.; Messina, M.; Plante, G.; Rizzo, A. [Columbia University, Physics Department, New York, NY (United States); Agostini, F. [INFN-Laboratori Nazionali del Gran Sasso (Italy); Gran Sasso Science Institute, L' Aquila (Italy); Bologna Univ., Department of Physics and Astrophysics, Bologna (Italy); INFN, Bologna (Italy); Alfonsi, M. [Nikhef and the University of Amsterdam, Amsterdam (Netherlands); Johannes Gutenberg-Universitaet Mainz, Institut fuer Physik and Exzellenzcluster PRISMA, Mainz (Germany); Arazi, L.; Budnik, R.; Duchovni, E.; Gross, E.; Itay, R.; Landsman, H.; Lellouch, D.; Levinson, L.; Priel, N.; Vitells, O. [Weizmann Institute of Science, Department of Particle Physics and Astrophysics, Rehovot (Israel); Arisaka, K.; Lyashenko, A.; Meng, Y.; Pantic, E.; Teymourian, A.; Wang, H. [University of California, Physics and Astronomy Department, Los Angeles, CA (United States); Arneodo, F.; Di Giovanni, A. [New York University Abu Dhabi, Abu Dhabi (United Arab Emirates); Auger, M.; Barrow, P.; Baudis, L.; Behrens, A.; Galloway, M.; Kessler, G.; Kish, A.; Mayani, D.; Pakarha, P.; Piastra, F. [University of Zurich, Physik-Institut, Zurich (Switzerland); Balan, C.; Cardoso, J.M.R.; Lopes, J.A.M.; Santos, J.M.F. dos [University of Coimbra, Department of Physics, Coimbra (Portugal); Bauermeister, B.; Fattori, S.; Geis, C.; Grignon, C.; Oberlack, U.; Schindler, S. [Johannes Gutenberg-Universitaet Mainz, Institut fuer Physik and Exzellenzcluster PRISMA, Mainz (Germany); Beltrame, P. [Weizmann Institute of Science, Department of Particle Physics and Astrophysics, Rehovot (Israel); University of Edinburgh, Edinburgh (United Kingdom); Brown, A.; Lang, R.F.; Macmullin, S.; Pienaar, J.; Reichard, S.; Reuter, C. [Purdue University, Department of Physics and Astronomy, West Lafayette, IN (United States); Brown, E.; Levy, C. [Rensselaer Polytechnic Institute, Department of Physics, Applied Physics and Astronomy, Troy, NY (United States); Wilhelms-Universitaet Muenster, Institut fuer Kernphysik, Muenster (Germany); Bruenner, S.; Hampel, W.; Kaether, F.; Lindemann, S.; Lindner, M.; Undagoitia, T.M.; Rauch, L.; Schreiner, J.; Simgen, H.; Weber, M. [Max-Planck-Institut fuer Kernphysik, Heidelberg (Germany); Bruno, G. [INFN-Laboratori Nazionali del Gran Sasso and Gran Sasso Science Institute, L' Aquila (Italy); Wilhelms-Universitaet Muenster, Institut fuer Kernphysik, Muenster (Germany); Buetikofer, L.; Coderre, D.; Schumann, M. [University of Bern, Albert Einstein Center for Fundamental Physics, Bern (Switzerland); Colijn, A.P.; Decowski, M.P.; Tiseni, A.; Tunnell, C. [Nikhef and the University of Amsterdam, Amsterdam (Netherlands); Cussonneau, J.P.; Le Calloch, M.; Masbou, J.; Lavina, L.S.; Thers, D. [Universite de Nantes, Subatech, Ecole des Mines de Nantes, CNRS/In2p3, Nantes (France); Ferella, A.D.; Fulgione, W.; Laubenstein, M. [INFN-Laboratori Nazionali del Gran Sasso and Gran Sasso Science Institute, L' Aquila (Italy); Fieguth, A.; Murra, M.; Rosendahl, S.; Weinheimer, C. [Wilhelms-Universitaet Muenster, Institut fuer Kernphysik, Muenster (Germany); Garbini, M.; Massoli, F.V.; Sartorelli, G.; Selvi, M. [Bologna Univ., Department of Physics and Astrophysics, Bologna (Italy); INFN, Bologna (Italy); Miguez, B.; Molinario, A.; Trinchero, G. [INFN-Torino and Osservatorio Astrofisico di Torino, Turin (Italy); Naganoma, J.; Shagin, P.; Wall, R. [Rice University, Department of Physics and Astronomy, Houston, TX (United States); Orrigo, S.E.A. [University of Coimbra, Department of Physics, Coimbra (Portugal); IFIC, CSIC-Universidad de Valencia, Valencia (Spain); Persiani, R. [Universite de Nantes, Subatech, Ecole des Mines de Nantes, CNRS/In2p3, Nantes (FR); Bologna Univ., Department of Physics and Astrophysics, Bologna (IT); INFN, Bologna (IT); Collaboration: XENON Collaboration

2015-11-15

The low-background, VUV-sensitive 3-inch diameter photomultiplier tube R11410 has been developed by Hamamatsu for dark matter direct detection experiments using liquid xenon as the target material. We present the results from the joint effort between the XENON collaboration and the Hamamatsu company to produce a highly radio-pure photosensor (version R11410-21) for the XENON1T dark matter experiment. After introducing the photosensor and its components, we show the methods and results of the radioactive contamination measurements of the individual materials employed in the photomultiplier production. We then discuss the adopted strategies to reduce the radioactivity of the various PMT versions. Finally, we detail the results from screening 286 tubes with ultra-low background germanium detectors, as well as their implications for the expected electronic and nuclear recoil background of the XENON1T experiment. (orig.)

International recommendations[General radiation protection background to protective measures against foodstuffs contaminated with radioactive substances

Energy Technology Data Exchange (ETDEWEB)

Lindell, Bo [Swedish National Institute of Radiation Protection (Sweden)

1986-07-01

Full text: This short presentation will indicate the general radiation protection background to protective measures against foodstuffs contaminated with radioactive substances. A number of international organizations are involved in various aspects of radiation protection, for example, the International Atomic Energy Agency (IAEA), the United Nations Food and Agriculture Organization (FAO), the United Nations Environment Programme (UNEP), and the World Health Organization (WHO). Two international organizations, however, provide the basic background. These are the International Commission on Radiological Protection (ICRP) and the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). UNSCEAR provides the scientific information on radiation levels and effects. It consists of 21 member countries, with truly international coverage. It issues reports to the UN General Assembly, including comprehensive scientific annexes. Its latest comprehensive report was issued in 1982, the next is expected to be published in 1988. That report will include an assessment of the radiological consequences of the Chernobyl accident. The ICRP is a non-governmental organization. It has issued recommendations on radiation protection since 1928. The postulated biological basis for radiation protection recommendations involves two types of biological effects. The so-called non-stochastic effects, mainly due to cell death, appear only when the radiation doses exceed a certain threshold value. These effects, therefore, can only appear after high accidental exposures. After the Chernobyl accident, they only affected about 200 individuals involved in fire extinction and rescue work at the damaged nuclear power plant. Stochastic effects, with some simplification, may be seen as the result of initial changes in the genetic code of some surviving cells. If these cells are germ cells, this may lead to hereditary harm. If they are somatic cells, the result could be cancer

Development of site selection criteria for radioactive waste disposal in view of favourable geological settings in Germany

Energy Technology Data Exchange (ETDEWEB)

Baltes, B.; Brewitz, W. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Cologne (Germany)

2001-07-01

In Germany it is intended to dispose of all types of radioactive waste in deep geological formations. Since the government has doubts regarding the suitability of the Gorleben site, further sites in different host rock formations have to be investigated. This investigation process has to be carried out with respect to technical suitability and safety as well as to public acceptance. A Committee has been established whose mandate is to develop a comprehensible procedure for the selection of sites for radioactive waste disposal in Germany. The Committee developed an iterative procedure which provides, besides the increase of transparency, the necessary flexibility in dealing with assessment results. The method is governed by geo-scientific and social-scientific criteria that are presented in this paper. 7 steps have been identified in the procedure: 1) exclusion of areas with obviously unfavourable conditions, 2) identification of areas with favourable geological settings, 3) exclusion of areas for socio-scientific reasons, 4) identification of regions with favourable conditions and ranking of regions, 5) identification of sites for further identification, 6) above-ground site investigation and ranking of potentially suitable sites, and 7) identification of sites for suitability investigations. The first 3 steps give the remaining areas that meet the minimum requirements. The criteria of the first 3 steps are: extensive vertical movements, active disturbance zones, seismic activity and volcanic activity, as for the 4 last steps criteria are based on geo- and socio- scientific weighing, voluntariness and regional mediation. (A.C.)

Development of site selection criteria for radioactive waste disposal in view of favourable geological settings in Germany

International Nuclear Information System (INIS)

Baltes, B.; Brewitz, W.

2001-01-01

In Germany it is intended to dispose of all types of radioactive waste in deep geological formations. Since the government has doubts regarding the suitability of the Gorleben site, further sites in different host rock formations have to be investigated. This investigation process has to be carried out with respect to technical suitability and safety as well as to public acceptance. A Committee has been established whose mandate is to develop a comprehensible procedure for the selection of sites for radioactive waste disposal in Germany. The Committee developed an iterative procedure which provides, besides the increase of transparency, the necessary flexibility in dealing with assessment results. The method is governed by geo-scientific and social-scientific criteria that are presented in this paper. 7 steps have been identified in the procedure: 1) exclusion of areas with obviously unfavourable conditions, 2) identification of areas with favourable geological settings, 3) exclusion of areas for socio-scientific reasons, 4) identification of regions with favourable conditions and ranking of regions, 5) identification of sites for further identification, 6) above-ground site investigation and ranking of potentially suitable sites, and 7) identification of sites for suitability investigations. The first 3 steps give the remaining areas that meet the minimum requirements. The criteria of the first 3 steps are: extensive vertical movements, active disturbance zones, seismic activity and volcanic activity, as for the 4 last steps criteria are based on geo- and socio- scientific weighing, voluntariness and regional mediation. (A.C.)

Maintenance of records for radioactive waste disposal

International Nuclear Information System (INIS)

1999-07-01

The safety of the radioactive waste disposal concepts does not rely on long term institutional arrangements. However, future generations may need information related to repositories and the wastes confined in them. The potentially needed information therefore has to be identified and collected. A suitable system for the preservation of that information needs to be created as a part of the disposal concept beginning with the planning phase. The IAEA has prepared this technical report to respond to the needs of Member States having repositories or involved in or considering the development of repositories. In many countries policies and systems for record keeping and maintenance of information related to disposal are the subjects of current interest. This report describes the requirements for presenting information about repositories for radioactive waste including long lived and transuranic waste and spent fuel if it is declared as a waste. The report discussed topics of identification, transfer and long term retention of high level information pertaining to the repository in a records management system (RMS) for retrieval if it becomes necessary in the future

Assessment of Natural Exposure From Some kinds of Egyptian Gypsum Using Low Background Spectrometer

International Nuclear Information System (INIS)

Sroor, A.

2006-01-01

Radioactivity of natural gypsum and gypsum derived products are examined investigated due to their importance as element of building materials and agricultural gypsum. the natural gypsum and its product may constitute an additional source of radiation exposure to workers and members of public from radiation produced by radioactive decaying. thirty natural gypsum samples from different quarries and 32 fabricated gypsum samples from commercial companies were analyzed using low background HPGe detector. the natural concentration of Ra-226, 232 Th and 40 K activities in all samples were determined in Bq/Kg dry weight. it was found that radioactivity of natural gypsum is less than the fabricated gypsum, so it can be used as agricultural gypsum. fabricated gypsum is suitable for use as an element of building material in egypt

Analysis of background components in Ge-spectrometry and their influence on detection limits

Energy Technology Data Exchange (ETDEWEB)

Heusser, G [Max-Planck-Institut fuer Kernphysik, Heidelberg (Germany)

1997-03-01

In low radioactivity measurements the system own background of the spectrometer is, besides the counting efficiency, the limiting factor for the achievable sensitivity. Since the latter is mostly fixed, background reduction is the only way to gain sensitivity, although it is inversely proportional only to the square root of the background rate but directly proportional to the counting efficiency. A thorough understanding of the background sources and their quantitative contribution helps to choose the most adequate suppression method in order to reach a certain required level of detection limit. For Ge-spectrometry the background can be reduced by 5 to 6 orders of magnitude compared to the unshielded case applying state-of-the-art techniques. This reduction factor holds for the continuous background spectrum as well as for the line background as demonstrated for a Ge detector of the Heidelberg-Moscow double beta decay experiment. (orig./DG)

Contribution of low-frequency harmonics to Mandarin Chinese tone identification in quiet and six-talker babble background.

Science.gov (United States)

Liu, Chang; Azimi, Behnam; Bhandary, Moulesh; Hu, Yi

2014-01-01

The goal of this study was to investigate Mandarin Chinese tone identification in quiet and multi-talker babble conditions for normal-hearing listeners. Tone identification was measured with speech stimuli and stimuli with low and/or high harmonics that were embedded in three Mandarin vowels with two fundamental frequencies. There were six types of stimuli: all harmonics (All), low harmonics (Low), high harmonics (High), and the first (H1), second (H2), and third (H3) harmonic. Results showed that, for quiet conditions, individual harmonics carried frequency contour information well enough for tone identification with high accuracy; however, in noisy conditions, tone identification with individual low harmonics (e.g., H1, H2, and H3) was significantly lower than that with the Low, High, and All harmonics. Moreover, tone identification with individual harmonics in noise was lower for a low F0 than for a high F0, and was also dependent on vowel category. Tone identification with individual low-frequency harmonics was accounted for by local signal-to-noise ratios, indicating that audibility of harmonics in noise may play a primary role in tone identification.

Operation and technology development of the radioactive xenon and krypton detection equipment

International Nuclear Information System (INIS)

Lee, Wanno; Choi, Sangdo; Ji, Youngyong; Lim, Jong Myoung; Cho, Young Hyun; Kang, Han Beul; Lee, Hoon; Kang, Moon Ja; Choi, Kun Sik

2013-03-01

Operation and technology development of the radioactive xenon and krypton detection equipment - Advancement, independence of operation technology for BfS-IAR system(the simultaneous analysis of xenon and krypton) installed after North Korea nuclear tests in 2006 and establishment of background base-line for xenon and krypton radioactivity. - Enhanced detection and analysis capabilities for neighborhood nuclear activities through advanced research of noble gas detection technology. Results of the Project · The operation of xenon and krypton analysis system (BfS-IAR) · Operation of fixed adsorption system. · Operation of portable adsorption system · Exercise of emergency response and proficiency test with SAUNA. · Measurement of noble gas background at specific region in Korea. - Radioxenon levels at Dongdu Cheon is approximately 1.6 mBq/m 3 · Development of automation filling system for absorber cooling

Radioactive waste characterisation by neutron activation

International Nuclear Information System (INIS)

Nicol, Tangi

2016-01-01

Nuclear activities produce radioactive wastes classified following their radioactive level and decay time. an accurate characterization is necessary for efficient classification and management. Medium and high level wastes containing long lived radioactive isotopes will be stored in deep geological storage for hundreds of thousands years. at the end of this period, it is essential to ensure that the wastes do not represent any risk for humans and environment, not only from radioactive point of view, but also from stable toxic chemicals. This PhD thesis concerns the characterization of toxic chemicals and nuclear material in radioactive waste, by using neutron activation analysis, in the frame of collaboration between the Nuclear Measurement Laboratory of CEA Cadarache, France, and the Institute of Nuclear Waste Management and Reactor Safety of the research center, FZJ (Forschungszentrum Juelich GmbH), Germany. The first study is about the validation of the numerical model of the neutron activation cell MEDINA (FZJ), using MCNP Monte Carlo transport code. Simulations and measurements of prompt capture gamma rays from small samples measured in MEDINA have been compared for a number of elements of interest (beryllium, aluminum, chlorine, copper, selenium, strontium, and tantalum). The comparison was performed using different nuclear databases, resulting in satisfactory agreement and validating simulation in view of following studies. Then, the feasibility of fission delayed gamma-ray measurements of "2"3"9Pu and "2"3"5U in 225 L waste drums has been studied, considering bituminized or concrete matrixes representative of wastes produced in France and Germany. The delayed gamma emission yields were first determined from uranium and plutonium metallic samples measurements in REGAIN, the neutron activation cell of LMN, showing satisfactory consistency with published data. The useful delayed gamma signals of "2"3"9Pu and "2"3"5U, homogeneously distributed in the 225 L

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

Policies and strategies for radioactive waste management

International Nuclear Information System (INIS)

2009-01-01

A policy for spent fuel and radioactive waste management should include a set of goals or requirements to ensure the safe and efficient management of spent fuel and radioactive waste in the country. Policy is mainly established by the national government and may become codified in the national legislative system. The spent fuel and radioactive waste management strategy sets out the means for achieving the goals and requirements set out in the national policy. It is normally established by the relevant waste owner or nuclear facility operator, or by government (institutional waste). Thus, the national policy may be elaborated in several different strategy components. To ensure the safe, technically optimal and cost effective management of radioactive waste, countries are advised to formulate appropriate policies and strategies. A typical policy should include the following elements: defined safety and security objectives, arrangements for providing resources for spent fuel and radioactive waste management, identification of the main approaches for the management of the national spent fuel and radioactive waste categories, policy on export/import of radioactive waste, and provisions for public information and participation. In addition, the policy should define national roles and responsibilities for spent fuel and radioactive waste management. In order to formulate a meaningful policy, it is necessary to have sufficient information on the national situation, for example, on the existing national legal framework, institutional structures, relevant international obligations, other relevant national policies and strategies, indicative waste and spent fuel inventories, the availability of resources, the situation in other countries and the preferences of the major interested parties. The strategy reflects and elaborates the goals and requirements set out in the policy statement. For its formulation, detailed information is needed on the current situation in the country

Some peculiarities of radioactive elements metabolism in body according to the indices of activity of blood and urine in malignant neoplasms of different localization

International Nuclear Information System (INIS)

Gelashvili, K.D.

1988-01-01

Background beta-radioactivity of blood and day urine in 115 patients (36 healthy ones and 79 suffering from malignant tumor of different localization) taking into account age was determined. It is shown that changes in background radioactivity of blood and urine both in healthy and oncologic patients are mostly presented in old age. Increase of background radioactivity of blood and urine takes place mainly not due to 40 K, but other beta-active elements - in healthy persons. Activity of blood and day urine in patients with malignant tumors decreases due to other beta-emittor, but not 40 K. Some changes in metabolic processes of beta-active elements of an organism both with the growth increase and when developing malignant tumors are established. 1 tab

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

Radioactivity metrology

International Nuclear Information System (INIS)

Legrand, J.

1979-01-01

Some aspects of the radioactivity metrology are reviewed. Radioactivity primary references; absolute methods of radioactivity measurements used in the Laboratoire de Metrologie des Rayonnements Ionisants; relative measurement methods; traceability through international comparisons and interlaboratory tests; production and distribution of secondary standards [fr

Development of methodology for the characterization of radioactive sealed sources

International Nuclear Information System (INIS)

Ferreira, Robson de Jesus

2010-01-01

Sealed radioactive sources are widely used in many applications of nuclear technology in industry, medicine, research and others. The International Atomic Energy Agency (IAEA) estimates tens of millions sources in the world. In Brazil, the number is about 500 thousand sources, if the Americium-241 sources present in radioactive lightning rods and smoke detectors are included in the inventory. At the end of the useful life, most sources become disused, constitute a radioactive waste, and are then termed spent sealed radioactive sources (SSRS). In Brazil, this waste is collected by the research institutes of the Nuclear Commission of Nuclear Energy and kept under centralized storage, awaiting definition of the final disposal route. The Waste Management Laboratory (WML) at the Nuclear and Energy Research Institute is the main storage center, having received until July 2010 about 14.000 disused sources, not including the tens of thousands of lightning rod and smoke detector sources. A program is underway in the WML to replacing the original shielding by a standard disposal package and to determining the radioisotope content and activity of each one. The identification of the radionuclides and the measurement of activities will be carried out with a well type ionization chamber. This work aims to develop a methodology for measuring or to determine the activity SSRS stored in the WML accordance with its geometry and determine their uncertainties. (author)

Some Experience with Illicit Trafficking of Radioactive Materials in Tanzania

International Nuclear Information System (INIS)

Ngaile, J.E.; Banzi, F.P.; Kifanga, L.D.

2008-01-01

radiation sources; lack of radiation detection equipment; and also the lack of knowledge of radiation hazards as well as dangerous. In view of these deficiencies, there was an urgent need of improvement of radiation protection of the front line officers by providing them training and capability to deal with nuclear security, safety, illicit trafficking and emergencies of nuclear and radioactive materials by providing them with basic equipment for identification and detection in order to minimize accidental exposure resulting from lost of control and illicit trafficking of radioactive materials

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.)

NAIR: handbook on the national arrangements for incidents involving radioactivity

International Nuclear Information System (INIS)

1987-01-01

A revised handbook on the national arrangements for incidents involving radioactivity (NAIR) has been published. Following brief introductory sections on the administrative aspects and operational aspects, the main part of the handbook is devoted to operational and call-out lists including an index of police forces served by NAIR, an index of establishments providing assistance under NAIR, sources of stage 1 and stage 2 assistance for each police constabulary, hospitals prepared to accept contaminated casualties and to assist with decontamination of personnel, and hospitals prepared to advise on the treatment and admission of casualties exposed to large doses of radiation. Technical appendices are also given on radiological protection in NAIR incidents, instruments and equipment, radionuclide data and a guide to suitable detectors, package and source identification and disposal of radioactive materials involved in NAIR accidents. (U.K.)

Environmental 222Rn as a background source in the solar neutrino experiment GALLEX

International Nuclear Information System (INIS)

Wojcik, M.

1996-01-01

The radiochemical neutrino experiment GALLEX is described. Its aim is to measure the flux of low energy solar neutrinos. In this experiment it is essential to suppress strongly the background of environmental origin, like charged cosmic rays, neutrons and gamma rays. In low-level radioactivity measurements performed in deep underground laboratory where flux of charged comic rays is strongly reduced, radon (Rn) exhaled from rock or concrete walls forms a most important strong, time-dependent background component. In this work the impact of Rn on the GALLEX experiment has been discussed and attempts to recognize and minimize its influence on the counter background were described. 63 refs, 22 figs, 11 tabs

Development of a Low Background Environment for the Cryogenic Dark Matter Search

Energy Technology Data Exchange (ETDEWEB)

Da Silva, Angela Jane [British Columbia U.

1996-01-01

A major problem currently facing astrophysics and cosmology is the question of dark matter. Although there is little doubt about the existence of dark matter, there is considerable uncertainty about the abundance and nature of this matter. One possibility is that dark matter consists of weakly interacting massive particles (WIMPs), such as the lightest stable particle in supersymmetry models. Direct detection experiments look for nuclear recoils from WIMPs scattering in a detector. The first generation of direct detection experiments were ultimately limited by radioactive backgrounds. The Cryogenic Dark Matter Search (CDMS) is a direct detection experiment based on novel particle detectors operated at millikelvin temperatures that provide intrinsic background rejection. This capability, however, is not 100% effective. Therefore a low background environment is essential to the experiment. To create such an environment, all possible background sources have been extensively studied both by measuring the background contribution from muons, photons and neutrons and by performing detailed Monte Carlo simulations of the photon and neutron backgrounds. The results of this investigation, as discussed in this thesis, have influenced all aspects of the CDMS experiment. The initial site for the CDMS experiment is the Stanford Underground Facility. The relatively high muon flux at this site due to its shallow depth was balanced against the convenience of a local site with the unlimited access necessary for operating a complicated cryogenic system and developing new detector technology. The cryostat used to house the detectors was designed to accommodate the extensive shielding necessary to reduce the ambient backgrounds to acceptable levels and to minimize the amount of radioactive contamination near the detectors. Simulations and measurements of the local backgrounds led to a layered shield design that consists primarily of plastic scintillators to veto muons, lead and copper

Survey on non-nuclear radioactive waste; Kartlaeggning av radioaktivt avfall fraan icke kaernteknisk verksamhet

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-11-01

On request from the Swedish Radiation Protection Authority, the Swedish government has in May 2002 set up a non-standing committee for non-nuclear radioactive waste. The objective was to elaborate proposals for a national system for the management of all types of non-nuclear radioactive wastes with special consideration of inter alia the polluter pays principle and the responsibility of the producers. The committee will deliver its proposals to the government 1 December 2003. SSI has assisted the committee to the necessary extent to fulfill the investigation. This report is a summery of SSI's background material concerning non-nuclear radioactive waste in Sweden.

Radioactive waste from non-licensed activities - identification of waste, compilation of principles and guidance, and proposed system for final management

International Nuclear Information System (INIS)

Jones, C.; Pers, K.

2001-07-01

Presently national guidelines for the handling of radioactive waste from non-licensed activities are lacking in Sweden. Results and information presented in this report are intended to form a part of the basis for decisions on further work within the Swedish Radiation Protection Institute on regulations or other guidelines on final management and final disposal of this type of waste. An inventory of radioactive waste from non-licensed activities is presented in the report. In addition, existing rules and principles used in Sweden - and internationally - on the handling of radioactive and toxic waste and non-radioactive material are summarized. Based on these rules and principles a system is suggested for the final management of radioactive material from non-licensed activities. A model is shown for the estimation of dose as a consequence of leaching of radio-nuclides from different deposits. The model is applied on different types of waste, e.g. peat ashes, light concrete and low-level waste from a nuclear installation

Radioactivity in Trinitite six decades later

International Nuclear Information System (INIS)

Parekh, Pravin P.; Semkow, Thomas M.; Torres, Miguel A.; Haines, Douglas K.; Cooper, Joseph M.; Rosenberg, Peter M.; Kitto, Michael E.

2006-01-01

The first nuclear explosion test, named the Trinity test, was conducted on July 16, 1945 near Alamogordo, New Mexico. In the tremendous heat of the explosion, the radioactive debris fused with the local soil into a glassy material named Trinitite. Selected Trinitite samples from ground zero (GZ) of the test site were investigated in detail for radioactivity. The techniques used included α spectrometry, high-efficiency γ-ray spectrometry, and low-background β counting, following the radiochemistry for selected radionuclides. Specific activities were determined for fission products ( 9 Sr, 137 Cs), activation products ( 6 Co, 133 Ba, 152 Eu, 154 Eu, 238 Pu, 241 Pu), and the remnants of the nuclear fuel ( 239 Pu, 24 Pu). Additionally, specific activities of three natural radionuclides ( 4 K, 232 Th, 238 U) and their progeny were measured. The determined specific activities of radionuclides and their relationships are interpreted in the context of the fission process, chemical behavior of the elements, as well as the nuclear explosion phenomenology

Modern systems for environmental radioactivity measurements

International Nuclear Information System (INIS)

Cimpean, A.; Borodeanu, C.

1995-01-01

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

Global marine radioactivity database (GLOMARD)

International Nuclear Information System (INIS)

2000-06-01

The GLOMARD stores all available data on marine radioactivity in seawater, suspended matter, sediments and biota. The database provides critical input to the evaluation of the environmental radionuclide levels in regional seas and the world's oceans. It can be used as a basis for the assessment of the radiation doses to local, regional and global human populations and to marine biota. It also provides information on temporal trends of radionuclide levels in the marine environment and identifies gaps in available information. The database contains information on the sources of the data; the laboratories performing radionuclide analysis; the type of samples (seawater, sediment, biota) and associated details (such as volume and weight); the sample treatment, analytical methods, and measuring instruments; and the analysed results (such as radionuclide concentrations, uncertainties, temperature, salinity, etc.). The current version of the GLOMARD allows the input, maintenance and extraction of data for the production of various kinds of maps using external computer programs. Extracted data are processed by these programs to produce contour maps representing radionuclide distributions in studied areas. To date, development work has concentrated on the Barents and Kara Seas in the Arctic and the Sea of Japan in the northwest Pacific Ocean, in connection with the investigation of radioactive waste dumping sites, as well as on marine radioactivity assessment of the Mururoa and Fangataufa nuclear weapons tests sites in French Polynesia. Further data inputs and evaluations are being carried out for the Black and Mediterranean Seas. In the framework of the project on Worldwide Marine Radioactivity Studies, background levels of 3 H, 90 Sr, 137 Cs and 239,240 Pu in water, sediment and biota of the world's oceans and seas will be established

Import/Export Service of Radioactive Material and Radioactive Sources Service

CERN Multimedia

2004-01-01

Please note that the Import/Export Service of radioactive material (http://cern.ch/service-rp-shipping/ - e-mail : service-rp-shipping@cern.ch) and the Radioactive Sources Service (http://cern.ch/service-radioactive-sources - e-mail : service-radioactive-sources@cern.ch) at bldg. 24/E-024 will be closed on FRIDAY 10 SEPTEMBER 2004. Tel. 73171

Non radioactive precursor import into chloroplasts

International Nuclear Information System (INIS)

Lombardo, V.A.; Ottado, J.

2003-01-01

Full text: Eukaryotic cells have a subcellular organization based on organelles. Protein transport to these organelles is quantitatively important because the majority of cellular proteins are codified in nuclear genes and then delivered to their final destination. Most of the chloroplast proteins are translated on cytoplasmic ribosomes as larger precursors with an amino terminal transit peptide that is necessary and sufficient to direct the precursor to the chloroplast. Once inside the organelle the transit peptide is cleaved and the mature protein adopts its folded form. In this work we developed a system for the expression and purification of the pea ferredoxin-NADP + reductase precursor (preFNR) for its import into chloroplasts in non radioactive conditions. We constructed a preFNR fused in its carboxy terminus to a 6 histidines peptide (preFNR-6xHis) that allows its identification using a commercial specific antibody. The construction was expressed, purified, processed and precipitated, rendering a soluble and active preFNR-6xHis that was used in binding and import into chloroplasts experiments. The reisolated chloroplasts were analyzed by SDS-PAGE, electro-blotting and revealed by immuno-detection using either colorimetric or chemiluminescent reactive. We performed also import experiments labeling preFNR and preFNR-6xHis with radioactive methionine as controls. We conclude that preFNR-6xHis is bound and imported into chloroplasts as the wild type preFNR and that both colorimetric or chemiluminescent detection methods are useful to avoid the manipulation of radioactive material. (author)

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

International Nuclear Information System (INIS)

Winkelmann, I.; Kreiner, H.J.

1977-12-01

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

Radioactivity

International Nuclear Information System (INIS)

Chelet, Y.

2006-01-01

The beginning of this book explains the why and how of the radioactivity, with a presentation of the different modes of disintegration. Are tackled the reports between radioactivity and time before explaining how the mass-energy equivalence appears during disintegrations. Two chapters treat natural radioisotopes and artificial ones. This book makes an important part to the use of radioisotopes in medicine (scintigraphy, radiotherapy), in archaeology and earth sciences (dating) before giving an inventory of radioactive products that form in the nuclear power plants. (N.C.)

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)

Camouflage, detection and identification of moving targets.

Science.gov (United States)

Hall, Joanna R; Cuthill, Innes C; Baddeley, Roland; Shohet, Adam J; Scott-Samuel, Nicholas E

2013-05-07

Nearly all research on camouflage has investigated its effectiveness for concealing stationary objects. However, animals have to move, and patterns that only work when the subject is static will heavily constrain behaviour. We investigated the effects of different camouflages on the three stages of predation-detection, identification and capture-in a computer-based task with humans. An initial experiment tested seven camouflage strategies on static stimuli. In line with previous literature, background-matching and disruptive patterns were found to be most successful. Experiment 2 showed that if stimuli move, an isolated moving object on a stationary background cannot avoid detection or capture regardless of the type of camouflage. Experiment 3 used an identification task and showed that while camouflage is unable to slow detection or capture, camouflaged targets are harder to identify than uncamouflaged targets when similar background objects are present. The specific details of the camouflage patterns have little impact on this effect. If one has to move, camouflage cannot impede detection; but if one is surrounded by similar targets (e.g. other animals in a herd, or moving background distractors), then camouflage can slow identification. Despite previous assumptions, motion does not entirely 'break' camouflage.

Intake of natural radioactivity through dietary items: a prelude to preoperational environmental survey at Kudankulam

International Nuclear Information System (INIS)

Varughese, K.G.; Kumar, M.; George, Thomas; Sunder Rajan, P.; Vijay Kumar, B.; Rajan, M.P.

2008-01-01

High background radiation are found in nature at some parts of Australia, Brazil, China, Iran, India etc. Kanyakumari district in the southern peninsular India is such a NHBRA (Natural high background radiation area) having monazite placers along the coast. Although general radiation levels in this area has been investigated by many researchers in the past, the impact of this high background radioactivity on the flora and fauna is scarce. In the present investigations radiation survey has been done at high background areas with special attention to vegetables and crops grown in this area. The studies are centered at the 2x1000 MWe, Kudankulam Nuclear Power Project site which is about 25 km from Kanyakumari. Samples of soil, sand, vegetations and other food items are collected from the 30 km radial zone of KKNPP site and analysed for naturally occurring radionuclides such as 238 U, 232 Th and 40 K. The intake of natural radioactivity through food items produced in this area is found to be very small, and the internal dose to general population staying at this high natural background area is insignificant. (author)

Physical chemistry of portland-cement hydrate, radioactive-waste hosts: Final report, January 16, 1987--December 31, 1987

International Nuclear Information System (INIS)

Grutzeck, M.W.

1989-01-01

This is a final report summarizing the results of a study of the physical and crystal chemistry of potential hydroxylated radioactive waste hosts compatible with portland cement. Research has focussed on the identification and evaluation of hydrated host phases for four ions: cesium, strontium, iodine and boron. These ions were chosen because they are among the most long lived of the radioactive waste ions as well as the most difficult to immobilize with cement-based materials. Results show that such phases do indeed exist, and that they are excellent host phases for the above ions

Survey of the radioactive background of some specimens of the biota of Rio de Janeiro coastal waters

International Nuclear Information System (INIS)

Santos, P.L. dos; Santos Gouvea, R. de C. dos; Azevedo Gouvea, V. de.

The natural radioactivity of components known to be bioconcentrators of artificial radionuclides in the coast of Rio de Janeiro was determined by means of sistematical gross alpha and beta radiometry. These data constitute the pre-operational survey, determining the radioactivity levels of these organisms and permiting to establish basic values and their temporal variations, which will serve as a referencial for the detection of eventual increases in the radioactivity introduced in the marine environment during the operational phase of nuclear power plants. Uranium and Potassium were also measured in some samples. The maximum and minimum values obtained after six years of experiment, analysing 14 species of algae and 4 species of animals were: for gross alpha radiometry (0,454 + - 0,162)Bq/g in the ashes of the phaeophita Padina vickersiae and (0,473 + - 0,106)Bq/g in the cnidaria Bunodosoma caissarum, (0,067 + - 0,031)Bq/g in the clorophita Ulva Fasciata and (0,091 + - 0,060)Bq/g in the soft tissues of the bivalve Perna perna. The byssus of this animal presented the highest gross alpha concentration : (1,770 + - 0,708)Bq/g, probably due to its high Uranium concentration, which contributes with 71%, complexed with its main constituent, a scleroprotein. The gross beta concentrations were highest in the algae Chetomorpha antennina (6,63 + - 1,80)Bq/g and in the species Bunodosoma caissarum, with a mean value of (2,60 + - 0,74)Bq/g in the ashes. The lowest concentrations were obtained in the rodophita Plocamium brasiliense, (1,64 + - 0,36)Bq/g, and (1,04 + - 0,30)Bq/g in the byssus of Perna perna. By the theoretical concentration of 40 K, calculated from potassium, the strong contribution of that radionuclide in the gross beta activity of the organisms is stressed. Seven samples of ashes were submitted to analyses by three different laboratories and the intercomparison results showed a reasonable agreement. (Author) [pt

Background radiation map of Thailand

International Nuclear Information System (INIS)

Angsuwathana, P.; Chotikanatis, P.

1997-01-01

The radioelement concentration in the natural environment as well as the radiation exposure to man in day-to-day life is now the most interesting topic. The natural radiation is frequently referred as a standard for comparing additional sources of man-made radiation such as atomic weapon fallout, nuclear power generation, radioactive waste disposal, etc. The Department of Mineral Resources commenced a five-year project of nationwide airborne geophysical survey by awarding to Kenting Earth Sciences International Limited in 1984. The original purpose of survey was to support mineral exploration and geological mapping. Subsequently, the data quantity has been proved to be suitable for natural radiation information. In 1993 the Department of Mineral Resources, with the assistance of IAEA, published a Background Radiation Map of Thailand at the scale of 1:1,000,000 from the existing airborne radiometric digital data. The production of Background Radiation Map of Thailand is the result of data compilation and correction procedure developed over the Canadian Shield. This end product will be used as a base map in environmental application not only for Thailand but also Southeast Asia region. (author)

On the environmental pollution and radioactivity within the territory of Russia in October, 1992

International Nuclear Information System (INIS)

Ovanesyants, A.M.; Belova, N.A.; Ivanov, M.N.

1993-01-01

Points of Russia were indicated where the maximum permissible concentration limits of pollutants were found to be exceeded. Causes of the observed incidents were described. Pollution of the atmospheric air, soils and surface waters was presented for the october, 1992. Daily concentrations of the radioactive aerosols in the atmospheric air were equal to the background values as well as their fallout. High radioactivity in Chita and Rostov cities were explaned by natural origin factors (meteorological conditions)

Radioactivity Handbook

International Nuclear Information System (INIS)

Firestone, R.B.; Browne, E.

1985-01-01

The Radioactivity Handbook will be published in 1985. This handbook is intended primarily for applied users of nuclear data. It will contain recommended radiation data for all radioactive isotopes. Pages from the Radioactivity Handbook for A = 221 are shown as examples. These have been produced from the LBL Isotopes Project extended ENDSF data-base. The skeleton schemes have been manually updated from the Table of Isotopes and the tabular data are prepared using UNIX with a phototypesetter. Some of the features of the Radioactivity Handbook are discussed here

Measurement of background gamma radiation in the northern Marshall Islands

OpenAIRE

Bordner, Autumn S.; Crosswell, Danielle A.; Katz, Ainsley O.; Shah, Jill T.; Zhang, Catherine R.; Nikolic-Hughes, Ivana; Hughes, Emlyn W.; Ruderman, Malvin A.

2016-01-01

Sixty-seven nuclear tests were conducted on two atolls in the northern Marshall Islands between 1946 and 1958. These tests produced radioactive fallout, which even today gives rise to radiation measurable above naturally occurring background levels. Rather than obtain new data, recent estimates of contamination levels in the northern Marshall Islands use measurements made decades ago to calculate present radiation levels. In contrast, we report on timely measurements on three different atolls...

Assessment of Natural Radioactivity and its Radiological Impact in Ortum Region in Kenya

International Nuclear Information System (INIS)

Wanjala, F.O.; Otwoma, D.; Kitao, T.F.; Hashim, N.O.

2015-01-01

The earth contains natural background radiations originating from terrestrial and cosmic sources. This study aims at assessing the levels of background radiation in air, soil and water and its associated radiological impact and also determines the elemental concentration of the rocks and soils around Ortum hills and quarry. 100 points will be measured for radioactivity in the air and 40 soil and 10 water samples will be collected for laboratory analysis using both grid and purposive sampling methods. Radioactivity in the field will be determined using the hand held Red Eye and Radiagem radiation survey meters. The levels of naturally occurring radionuclide Uranium-238 ( 238 U), Thorium-232 ( 232 Th) and Potassium-40 ( 40 K) in the soil and rocks will be determined using High Pure Germanium (HPGe) detector; the Liquid Scintillation Counter (LSC) will be used for analysis of water samples while the Energy Dispersive X-Ray Fluorescence Spectrometer (EDXRF) will be used to determine the elemental composition in the rocks and soil. The Residual Radioactivity (RESRAD) program will be used to analyze and assess the doses and risks associated with radiation exposure in Ortum region. (author)

Development of threshold guidance: National Low-Level Radioactive Waste Management Program

International Nuclear Information System (INIS)

1986-09-01

The current study has been conducted to provide DOE with a technical basis for the development of threshold guidance. The objective of the study was to develop the necessary background information and recommendations to assist the DOE in implementing the threshold limit concept for the disposal of DOE wastes at DOE facilities. The nature of low-level radioactive waste (LLW) varies greatly in both form and radionuclide content. While some low-level waste streams can contain substantial quantities of radioactive constituents, a potentially significant fraction of low-level waste is contaminated either very slightly or not at all. There is a strong likelihood that managing wastes with extremely low levels of radioactivity as nonradioactive waste would pose no significant safety problems and could result in substantial cost savings relative to its handling as LLW. Since all materials, including waste products, contain some radioactivity, it is necessary to distinguish between those wastes that would require disposal as LLW and those that have sufficiently low levels of radiological content to be managed according to their nonradiological properties. 131 refs., 9 figs., 24 tabs

A low-background Micromegas detector for axion searches

CERN Document Server

Andriamonje, Samuel A; Dafni, T; Delagnes, E; Fanourakis, G K; Ferrer-Ribas, Esther; Geralis, T; Giomataris, Ioanis; Kousouris, K; Papaevangelou, T; Zachariadou, K

2004-01-01

A micropattern low-background detector based on the Micromegas technology has been designed and constructed for the CERN Axion Search experiment CAST. The detector is made of low natural radioactivity materials and has a two-dimensional readout with X-Y strip structure. It is operated with an Argon/Isobutane (95%/5%) mixture and is controlled by a VME data acquisition system. The detector is sensitive to photons in the energy range of 1-10 keV, it has a linear response, excellent stability and a very good energy resolution (14% FWHM at 5.9 keV). This device has been in stable operation since October 2002, taking data during the running periods of the CAST experiment. At the end of summer 2003, the detector was upgraded with a flash ADC readout of the grid signal to further improve its background rejection capability. The currently achieved background rate under normal operation is about 2.0 multiplied by 10 **-**5 events/keV/cm**2/s with better than 85% software efficiency.

High energy proton-induced radioactivity in HgI2 crystals

International Nuclear Information System (INIS)

Porras, E.; Ferrero, J.L.; Sanchez, F.; Ruiz, J.A.; Lei, F.

1995-01-01

Mercuric iodide (HgI 2 ) semiconductor crystals are generating a lot of interest as room temperature solid state detectors for hard X-ray astronomy observations. For these applications one of the most important background sources is the cosmic proton induced radioactivity in the detector material. In order to study this background noise contribution a 1x1x1 cm HgI 2 crystal was irradiated with high energy protons. The resulting long-lived unstable isotopes and their production rates have been identified and compared with Monte Carlo simulations. ((orig.))

Natural background gamma-ray spectrum. List of gamma-rays ordered in energy from natural radionuclides

International Nuclear Information System (INIS)

Ichimiya, Tsutomu; Narita, Tsutomu; Kitao, Kensuke.

1998-03-01

A quick index to γ-rays and X-rays from natural radionuclides is presented. In the list, γ-rays are arranged in order of increasing energy. The list also contains γ-rays from radioactive nuclides produced in a germanium detector and its surrounding materials by interaction with cosmic neutrons, as well as direct γ-rays from interaction with the neutrons. Artificial radioactive nuclides emitting γ-rays with same or near energy value as that of the natural γ-rays and X-rays are also listed. In appendix, γ-ray spectra from a rock, uranium ore, thorium, monazite and uraninite and also background spectra obtained with germanium detectors placed in iron or lead shield have been given. The list is designed for use in γ-ray spectroscopy under the conditions of highly natural background, such as in-situ environmental radiation monitoring or low-level activity measurements, with a germanium detector. (author)

Natural background gamma-ray spectrum. List of gamma-rays ordered in energy from natural radionuclides

Energy Technology Data Exchange (ETDEWEB)

Ichimiya, Tsutomu [Japan Radioisotope Association, Tokyo (Japan); Narita, Tsutomu; Kitao, Kensuke

1998-03-01

A quick index to {gamma}-rays and X-rays from natural radionuclides is presented. In the list, {gamma}-rays are arranged in order of increasing energy. The list also contains {gamma}-rays from radioactive nuclides produced in a germanium detector and its surrounding materials by interaction with cosmic neutrons, as well as direct {gamma}-rays from interaction with the neutrons. Artificial radioactive nuclides emitting {gamma}-rays with same or near energy value as that of the natural {gamma}-rays and X-rays are also listed. In appendix, {gamma}-ray spectra from a rock, uranium ore, thorium, monazite and uraninite and also background spectra obtained with germanium detectors placed in iron or lead shield have been given. The list is designed for use in {gamma}-ray spectroscopy under the conditions of highly natural background, such as in-situ environmental radiation monitoring or low-level activity measurements, with a germanium detector. (author)

Direct Reaction Experimental Studies with Beams of Radioactive Tin Ions

Energy Technology Data Exchange (ETDEWEB)

Jones, K. L. [University of Tennessee, Knoxville (UTK); Ahn, S.H. [University of Tennessee, Knoxville (UTK); Allmond, James M [ORNL; Ayres, A. [University of Tennessee, Knoxville (UTK); Bardayan, Daniel W [ORNL; Baugher, T. [Michigan State University, East Lansing; Bazin, D. [Michigan State University, National Superconducting Cyclotron Laboratory (NSCL); Beene, James R [ORNL; Berryman, J. S. [Michigan State University, East Lansing; Bey, A. [University of Tennessee, Knoxville (UTK); Bingham, C. R. [University of Tennessee, Knoxville (UTK); Cartegni, L. [University of Tennessee, Knoxville (UTK); Chae, K. Y. [University of Tennessee, Knoxville (UTK)/Sungkyunkwan University, Korea; Cizewski, J. A. [Rutgers University; Gade, A. [Michigan State University, National Superconducting Cyclotron Laboratory (NSCL); Galindo-Uribarri, Alfredo {nmn} [ORNL; Garcia-Ruiz, R.F. [Instituut voor Kernen Stralingsfysica, KU Leuven, B-3001, Leuven, Belgium; Grzywacz, Robert Kazimierz [ORNL; Howard, Meredith E [ORNL; Kozub, R. L. [Tennessee Technological University (TTU); Liang, J Felix [ORNL; Manning, Brett M [ORNL; Matos, M. [Louisiana State University; McDaniel, S. [Michigan State University, East Lansing; Miller, D. [University of Tennessee, Knoxville (UTK); Nesaraja, Caroline D [ORNL; O' Malley, Patrick [Rutgers University; Padgett, S [University of Tennessee, Knoxville (UTK); Padilla-Rodal, Elizabeth [Universidad Nacional Autonoma de Mexico (UNAM); Pain, Steven D [ORNL; Pittman, S. T. [University of Tennessee (UTK) and Oak Ridge National Laboratory (ORNL); Radford, David C [ORNL; Ratkiewicz, Andrew J [ORNL; Schmitt, Kyle [ORNL; Smith, Michael Scott [ORNL; Stracener, Daniel W [ORNL; Stroberg, S. [Michigan State University, East Lansing; Tostevin, Jeffrey A [ORNL; Varner Jr, Robert L [ORNL; Weisshaar, D. [Michigan State University, East Lansing; Wimmer, K. [Michigan State University, National Superconducting Cyclotron Laboratory (NSCL)/Central Michigan University; Winkler, R. [Michigan State University, East Lansing

2015-01-01

The tin chain of isotopes provides a unique region in which to investigate the evolution of single-particle structure, spreading from N = 50 at Sn-100, through 10 stable isotopes and the N = 82 shell closure at Sn-132 out into the r-process path. Direct reactions performed on radioactive ion beams are sensitive spectroscopic tools for studying exotic nuclei. Here we present one experiment knocking out neutrons from tin isotopes that are already neutron deficient and two reactions that add a neutron to neutron-rich Sn-130. Both techniques rely on selective particle identification and the measurement of gamma rays in coincidence with charged ions. We present the goals of the two experiments and the particle identification for the channels of interest. The final results will be presented in future publications.

Radioactive contamination in monitors received for calibration

International Nuclear Information System (INIS)

Dias, Paulo S.; Santos, Gilvan C. dos; Brunelo, Maria Antonieta G.; Paula, Tiago C. de; Pires, Marina A.; Borges, Jose C.

2013-01-01

The Calibration Laboratory - LABCAL, from the Research Center for Metrology and Testing - METROBRAS, MRA Comercio de Instrumentos Eletronicos Ltda., began activities in October 2008 and, in August 2009, decided to establish a procedure for monitoring tests, external and internal, of all packages received from customers, containing instruments for calibration. The aim was to investigate possible contamination radioactive on these instruments. On July 2011, this procedure was extended to packagings of personal thermoluminescent dosemeters - TLD, received by the newly created Laboratory Laboratorio de Dosimetria Pessoal - LDP . In the monitoring procedure were used monitors with external probe, type pancake, MRA brand, models GP - 500 and MIR 7028. During the 37 months in which this investigation was conducted, were detected 42 cases of radioactive contamination, with the following characteristics: 1) just one case was personal dosimeter, TLD type; 2) just one case was not from a packing from nuclear medicine service - was from a mining company; 3) contamination occurred on packs and instruments, located and/or widespread; 4) contamination values ranged from slightly above the level of background radiation to about a thousand fold. Although METROBRAS has facilities for decontamination, in most cases, especially those of higher contamination, the procedure followed was to store the contaminated material in a room used for storage of radioactive sources. Periodically, each package and/or instrument was monitored, being released when the radiation level matched the background radiation. Every contamination detected, the client and/or owner of the instrument was informed. The Brazilian National Energy Commission - CNEN, was informed, during your public consultation for reviewing the standard for nuclear medicine services, held in mid-2012, having received from METROBRAS the statistical data available at the time. The high frequency of contamination detected and the high

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

Validation of predictive models for geologic disposal of radioactive waste via natural analogs

International Nuclear Information System (INIS)

Cohen, J.J.; Smith, C.F.

1981-03-01

The incorporation of toxic or hazardous material in the earth's crust is a phenomenon not unique to radioactive waste burial. Useful insights on the environmental transport and effects of underground toxic or radioactive material can be derived from comparative analysis against natural (mineral) analogs. This paper includes a discussion of the background and rationale for the analog approach, a descripton of several variations of the approach, and some sample applications to illustrate the concept, focusing on Radium-226 and Iodine-129 as specific case studies

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

Uranium Glass: A Glowing Alternative to Conventional Sources of Radioactivity

Science.gov (United States)

Boot, Roeland

2017-01-01

There is a relatively simple way of using radioactive material in classroom experiments: uranium glass, which provides teachers with a suitable substance. By using the right computer software and a radiation sensor, it can be demonstrated that uranium glass emits radiation at a greater rate than the background radiation and with the aid of UV…

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

Managing low-level radioactive waste in Massachusetts. Final report

International Nuclear Information System (INIS)

Bander, S.R.; Goldstein, M.E.

1983-12-01

As one of the country's largest generators of low-level radioactive waste, Massachusetts has begun independently seeking solutions to the questions surrounding low-level waste management issues. The Massachusetts Department of Public Health, Radiation Control Program, obtained funding from the U.S. Department ofEnergy through EG and G, Idaho, Inc. to develop a low-level waste management strategy for the Commonwealth. The Working Group was made up of individuals from various waste generating industries, environmental and public interest groups, medical and academic institutions, and affected state agencies. This final report document contains the following staff project reports: Proposed Low-Level Radioactive Waste Management Plan for The Commonwealth of Massachusetts, February 1983 and Low-Level Radioactive Waste Management in Massachusetts - Actions to be Considered for Implementation in 1984-1986, December 1983. These two staff reports represent the completion of the Massachusetts Low-Level Radioactive Waste Management Project. The first report provides some of the background material to the issues and some of the alternative courses of action which can be considered by state policy-makers. The second report provides the next phase in the process by delineating specific steps which may be taken before 1986 in order to address the low-level waste problem, and the estimated amount of time needed to complete each step

Build up of Radioactive Krypton and Xenon Analysis System

International Nuclear Information System (INIS)

Lee, D. K.; Choi, C. S.; Chung, K. H.; Lee, W.; Cho, Y. H.; Lee, C. W.

2008-03-01

The objective of this project is to build up an analysis system to measure the activity of the atmospheric radioactive krypton and xenon in Korea. The work scopes of the project include the purchase and the installation of the analysis system to measure the activity of the radioactive krypton and xenon in air, and the establishment of the operation capability of the system through the training of the operator. The system consists of two air sampling systems, and one radioactivity analysis system, which incorporates the enrichment system, the gas chromatography to purify a mixture gas, and the gas proportional counter to count the activity of pure krypton and xenon gas. As planned originally, the establishment of the analysis system has been completed. At present, one air sampler is successfully being operated at a specific site of the South Korea to measure the background radioactivities of Kr-85 and Xe-133 in air. The other air sampler is being reserved at the KAERI in the Daejeon for a emergency like the second nuclear test of the North Korea. During the normal time, the reserved air sampler will be used to collect the air sample for the performance test of the analysis system and the cross analysis for the calibration of the system. The radioactivity analysis system has been installed at the KAERI, and is being used to measure the activity of Kr-85 and Xe-133 in the air sample from a domestic site

Deep-well injection of liquid radioactive waste in Russia. Present situation

International Nuclear Information System (INIS)

Rybalchenko, A.

1998-01-01

At present there are 3 facilities (polygons) for the deep-well injection of liquid radioactive waste in Russia, all of which were constructed in the mid60's. These facilities are operating successfully, and activities have started in preparation for decommissioning. Liquid radioactive waste is injected into deep porous horizons which act as 'collector-layers', isolated from the surface and from groundwaters by a relatively thick sequence of rock of low permeability. The collector-layers (also collector-horizons) contain salt waters or fresh waters of no practical application, lying beneath the main horizons containing potable waters. Construction of facilities for the deep-well injection of liquid radioactive waste was preceded by geological surveys and investigations which were able to substantiate the feasibility and safety of radioactive waste injection, and to obtain initial data for facility design. Operation of the facilities was accompanied by monitoring which confirmed that the main safety requirement was satisfied i.e. localisation of radioactive waste within specified boundaries of the geologic medium. The opinion of most specialists in the atomic power industry in Russia favours deep-well injection as a solution to the problem of liquid radioactive waste management; during the period of active operation of defence facilities (atomic power industry of the former U.S.S.R.), this disposal method prevented the impact of radioactive waste on man and the environment. The experience accumulated concerning the injection of liquid radioactive waste in Russia is of interest to scientists and engineers engaged in problems of protection and remediation of the environment in the vicinity of nuclear industry facilities; an example of the utilisation of the deep subsurface for solidified radioactive waste and the disposal of different types of nuclear materials. Information on the scientific principles and background for the development of facilities for the injection

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

International Nuclear Information System (INIS)

Wan Rongsheng

2004-01-01

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

Assessment and the levels of radioactivity of natural radionuclides in drinking waters in China

International Nuclear Information System (INIS)

Liu Yulan

1989-03-01

In order to assess the levels of radioactivity of natural radionuclides in drinking waters and to estimate the internal doses of the population of China from ingestion, 1650 samples of waters were collected from normal radiation background areas of 28 provinces or autonomous regions of China. Radioactivity levels of U, Th, 226 Ra and 40 K in drinking waters were determined. The levels and the characteristics of distribution of 4 radionuclides are given. The results show that radioactivity levels in the southeast China are lower than in the north and northwest China. The average radioactivity levles of the 4 radionuclides in China close to the average levels given in UNSCEAR 1986 report. The result of estimation of internal doses from ingestion in the population of China is below the corresponding results given in UNSCEAR 1986 report, but near the result given by ICRP

Natural occurring radioactivity materials (NORM) in Ecuadorian oil fields

International Nuclear Information System (INIS)

Vasquez, R.; Enriquez, F.; Reinoso, T.

2008-01-01

Full text: Many natural elements contain radioactive isotopes, and most of them are present in the soil. In the gas and oil industries the most important radio nuclides are Ra-226 from the decay series of U-238, and in lower grade Ra-228 from the decay series of Th-232. Water exit from the perforation and perforation mud in the Oil towers drowns the NORM materials. Changes in temperature and pressure, allows the presence of sulphates and carbonates in pipes and internal areas of equipment. A Ra and Ba similarity leads to the selective co-precipitation in mud and incrustations of radioisotopes. A measure made in the pipe lines show that these industries generate important doses overcoming the levels of exemption and even the limits of established doses. The research was done by finding a pipe at Shushufindi 52 B well of production near by Coca city in the Ecuadorian jungle. The 'Comision Ecuatoriana de Energia Atomica' (CEEA), supervises the pipe line and accessories that are used in PETROPRODUCION fields accomplishing the radiological characterization, identifying the useless pipes and separate them in order of take care the good ones. Meanwhile the identification of the radioactive isotopes the CEEA proceed with the isolation of the radioactive disposals. From 57.830 pipes and accessories there were 1.607 useless ones, 56.223 didn't show radioactivity. Those pipes were monitored from the PETRODUCCION'S warehouses in Coca, Lago Agrio and Guarumo from September 12 th 2005 to September 12 th 2006. The CEEA is interested in NORMS because inadvertent workers may get high levels of radioactivity exposition. The Oil industries should have a manual about the complete handling of these materials. (author)

OCRWM Backgrounder, January 1987

International Nuclear Information System (INIS)

1987-01-01

The Nuclear Waste Policy Act of 1982 (NWPA) assigns to the US Department of Energy (DOE) responsibility for developing a system to safely and economically transport spent nuclear fuel and high-level radioactive waste from various storage sites to geologic repositories or other facilities that constitute elements of the waste management program. This transportation system will evolve from technologies and capabilities already developed. Shipments of spent fuel to a monitored retrievable storage (MRS) facility could begin as early as 1996 if Congress authorizes its construction. Shipments of spent fuel to a geologic repository are scheduled to begin in 1998. The backgrounder provides an overview of DOE's cask development program. Transportation casks are a major element in the DOE nuclear waste transportation system because they are the primary protection against any potential radiation exposure to the public and transportation workers in the event an accident occurs

Introduction to naturally occurring radioactive material

International Nuclear Information System (INIS)

Egidi, P.

1997-01-01

Naturally occurring radioactive material (NORM) is everywhere; we are exposed to it every day. It is found in our bodies, the food we eat, the places where we live and work, and in products we use. Some industrial practices involving natural resources concentrate these radionuclides to a degree that they may pose risk to humans and the environment if they are not controlled. This session will concentrate on diffuse sources of technologically-enhanced (TE) NORM, which are generally large-volume, low-activity waste streams produced by industries such as mineral mining, ore benefication, production of phosphate Fertilizers, water treatment and purification, and oil and gas production. The majority of radionuclides in TENORM are found in the uranium and thorium decay chains. Radium and its subsequent decay products (radon) are the principal radionuclides used in characterizing the redistribution of TENORM in the environment by human activity. We will briefly review other radionuclides occurring in nature (potassium and rubidium) that contribute primarily to background doses. TENORM is found in many waste streams; for example, scrap metal, sludges, slags, fluids, and is being discovered in industries traditionally not thought of as affected by radionuclide contamination. Not only the forms and volumes, but the levels of radioactivity in TENORM vary. Current discussions about the validity of the linear no dose threshold theory are central to the TENORM issue. TENORM is not regulated by the Atomic Energy Act or other Federal regulations. Control and regulation of TENORM is not consistent from industry to industry nor from state to state. Proposed regulations are moving from concentration-based standards to dose-based standards. So when is TENORM a problem? Where is it a problem? That depends on when, where, and whom you talk to exclamation point We will start by reviewing background radioactivity, then we will proceed to the geology, mobility, and variability of these

Methodology for the technical evaluation of disposal systems for Greater-Than-Class C low-level radioactive waste

International Nuclear Information System (INIS)

Lamar, D.A.; Raymond, J.R.

1990-07-01

This paper presents the methodology that will be used for the evaluation of alternative disposal concepts for Greater-Than-Class C low-level radioactive waste. The primary focus will be on the technical evaluation of various disposal concepts leading toward the identification of technically feasible disposal systems

Noise Reduction with Microphone Arrays for Speaker Identification

Energy Technology Data Exchange (ETDEWEB)

Cohen, Z

2011-12-22

Reducing acoustic noise in audio recordings is an ongoing problem that plagues many applications. This noise is hard to reduce because of interfering sources and non-stationary behavior of the overall background noise. Many single channel noise reduction algorithms exist but are limited in that the more the noise is reduced; the more the signal of interest is distorted due to the fact that the signal and noise overlap in frequency. Specifically acoustic background noise causes problems in the area of speaker identification. Recording a speaker in the presence of acoustic noise ultimately limits the performance and confidence of speaker identification algorithms. In situations where it is impossible to control the environment where the speech sample is taken, noise reduction filtering algorithms need to be developed to clean the recorded speech of background noise. Because single channel noise reduction algorithms would distort the speech signal, the overall challenge of this project was to see if spatial information provided by microphone arrays could be exploited to aid in speaker identification. The goals are: (1) Test the feasibility of using microphone arrays to reduce background noise in speech recordings; (2) Characterize and compare different multichannel noise reduction algorithms; (3) Provide recommendations for using these multichannel algorithms; and (4) Ultimately answer the question - Can the use of microphone arrays aid in speaker identification?

Environmental {sup 222}Rn as a background source in the solar neutrino experiment GALLEX

Energy Technology Data Exchange (ETDEWEB)

Wojcik, M. [Uniwersytet Jagiellonski, Cracow (Poland). Inst. Fizyki; BOREXINO

1996-12-31

The radiochemical neutrino experiment GALLEX is described. Its aim is to measure the flux of low energy solar neutrinos. In this experiment it is essential to suppress strongly the background of environmental origin, like charged cosmic rays, neutrons and gamma rays. In low-level radioactivity measurements performed in deep underground laboratory where flux of charged comic rays is strongly reduced, radon (Rn) exhaled from rock or concrete walls forms a most important strong, time-dependent background component. In this work the impact of Rn on the GALLEX experiment has been discussed and attempts to recognize and minimize its influence on the counter background were described. 63 refs, 22 figs, 11 tabs.

Environmental {sup 222}Rn as a background source in the solar neutrino experiment GALLEX

Energy Technology Data Exchange (ETDEWEB)

Wojcik, M [Uniwersytet Jagiellonski, Cracow (Poland). Inst. Fizyki; BOREXINO,

1997-12-31

The radiochemical neutrino experiment GALLEX is described. Its aim is to measure the flux of low energy solar neutrinos. In this experiment it is essential to suppress strongly the background of environmental origin, like charged cosmic rays, neutrons and gamma rays. In low-level radioactivity measurements performed in deep underground laboratory where flux of charged comic rays is strongly reduced, radon (Rn) exhaled from rock or concrete walls forms a most important strong, time-dependent background component. In this work the impact of Rn on the GALLEX experiment has been discussed and attempts to recognize and minimize its influence on the counter background were described. 63 refs, 22 figs, 11 tabs.

Radioactive waste management in the former USSR. Volume 3

Energy Technology Data Exchange (ETDEWEB)

Bradley, D.J.

1992-06-01

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world`s largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

Environmental radioactivity. Measurement and monitoring

International Nuclear Information System (INIS)

2009-11-01

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

Safety of transport of radioactive material. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

Radioactive material has been transported for decades within and between countries as the use of radioactive material to benefit mankind has expanded. The transport can involve many types of materials (radionuclides and radiation sources for applications in agriculture, energy production, industry, and medicine) and all modes of transport (road, rail, sea and waterways, and air). Among the organizations in the United Nations system, the International Atomic Energy Agency (IAEA) has the statutory function to establish or adopt standards of safety for protection of health against exposure to ionizing radiation. Within its statutory mandate and pursuant to this request, in 1961, the IAEA issued Regulations for the Safe Transport of Radioactive Material (the IAEA Transport Regulations). The Transport Regulations were periodically reviewed and, as appropriate, have been amended or revised. The latest version of the Transport Regulations was issued in 2000 by the IAEA as Publication TS-R-1 (ST-1, Revised). In addition, the IAEA is entrusted by its Statute to provide for the application of its standards at the request of States. The objective of the Conference is to foster the exchange of information on issues related to the safety of transport of radioactive material by providing an opportunity for representatives from sponsoring international organizations and their Member States and from other co-operating and participating organizations to discuss critical issues relating to the safety of transport of radioactive material by all modes and to formulate recommendations, as appropriate, regarding further international co-operation in this area. The following topics have been identified by the Technical Programme Committee as the subjects to be covered in the background briefing sessions: History and Status of the IAEA Transport Regulation Development; Experience in adoption of the IAEA Transport Regulations at the international level; Implementation of the IAEA Transport

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}.

Radiological survey of the radioactive sands and residues at Lowman, Idaho

International Nuclear Information System (INIS)

Haywood, F.F.; Burden, J.E.; Ellis, B.S.; Loy, E.T.; Shinpaugh, W.H.

1980-08-01

No uranium ore milling was performed at the Lowman site, which is located approximately 0.8 km northeast of the town of Lowman, Idaho. Nevertheless, approximately 80,000 metric tons of radioactive sands and residues from upgrading of heavy minerals by physical processing methods remain on the site grounds. Measurements of external gamma radiation 1 m above the surface showed exposure rates up to 2.4 mR/hr on site, but the exposure rate off site quickly dropped to the background level in all directions. Analysis of surface soil and sediment samples for 226 Ra and 232 Th indicated a limited spread of radioactive material

Radioactive materials

International Nuclear Information System (INIS)

Sugiura, Yoshio; Shimizu, Makoto.

1975-01-01

The problems of radioactivity in the ocean with marine life are various. Activities in this field, especially the measurements of the radioactivity in sea water and marine life are described. The works first started in Japan concerning nuclear weapon tests. Then the port call to Japan by U.S. nuclear-powered naval ships began. On the other hand, nuclear power generation is advancing with its discharge of warm water. The radioactive pollution of sea water, and hence the contamination of marine life are now major problems. Surveys of the sea areas concerned and study of the radioactivity intake by fishes and others are carried out extensively in Japan. (Mori, K.)

Radioactive dust concentration around the Ranger uranium mine

International Nuclear Information System (INIS)

Kavasnicka, Jiri.

1988-07-01

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

Identification of gaps in the national research effort related to radioactive waste management

International Nuclear Information System (INIS)

Thorne, M.C.; Plews, M.; Kane, P.

1987-08-01

Based on papers submitted to the Government's Radioactivity Research and Environmental Monitoring Committee (RadREM), this report presents a consolidated summary of perceived research requirements for 1988/89 and a comparison with the research proposed for that period. On this basis, discussion is included of gaps in the national research effort to 1989, duplication of research plans and areas where better co-ordination or funding of research might be appropriate. (author)

Double Chooz sensitivity and backgrounds studies to search for θ13 leptonic mixing angle

International Nuclear Information System (INIS)

Mention, G.

2005-06-01

The Double Chooz experiment will study the oscillations of electron antineutrinos produced by the Chooz nuclear power station to measure θ 13 mixing angle. The current knowledge on this parameter, provided ny the Chooz experiment, can be improved by reducing statistical and systematic errors. A large data sample will be collected to improve the former one. Two identical detectors will be built to cancel most of experimental systematic uncertainties involved in production and detection processes. Special care will be dedicated to backgrounds generated by natural radioactivity and cosmic ray interactions. In the hereby thesis, we describe our simulation studies to compute θ 13 sensitivity and assess the discovery potential of the experiment. We concentrated particularly on quantifying the detector related systematic errors that would limit the θ 13 sensitivity. Background related systematic errors such as the accidental events produced by the radioactivity of the photomultiplier tubes, correlated events from neutrons as well as a hypothetical background (mimicking the oscillation pattern) were taken into account. After 3 years, Double Chooz will be able to disentangle an oscillation signal for sin 2 (2*θ 13 ) > 0.05 (at 3*σ) or, if no oscillations were observed, to put a limit of sin 2 (2θ 13 ) < 0.03 at 90% C.L. (author)

Influence of Task Difficulty and Background Music on Working Memory Activity: Developmental Considerations.

Science.gov (United States)

Kaniel, Shlomo; Aram, Dorit

1998-01-01

A study of 300 children in kindergarten, grade 2, and grade 6 found that background music improved visual discrimination task performance at the youngest and middle ages and had no effect on the oldest participants. On a square identification task, background music had no influence on easy and difficult tasks but lowered performance on…

Intrinsic neutron background of nuclear emulsions for directional Dark Matter searches

Science.gov (United States)

Alexandrov, A.; Asada, T.; Buonaura, A.; Consiglio, L.; D'Ambrosio, N.; De Lellis, G.; Di Crescenzo, A.; Di Marco, N.; Di Vacri, M. L.; Furuya, S.; Galati, G.; Gentile, V.; Katsuragawa, T.; Laubenstein, M.; Lauria, A.; Loverre, P. F.; Machii, S.; Monacelli, P.; Montesi, M. C.; Naka, T.; Pupilli, F.; Rosa, G.; Sato, O.; Strolin, P.; Tioukov, V.; Umemoto, A.; Yoshimoto, M.

2016-07-01

Recent developments of the nuclear emulsion technology led to the production of films with nanometric silver halide grains suitable to track low energy nuclear recoils with submicrometric length. This improvement opens the way to a directional Dark Matter detection, thus providing an innovative and complementary approach to the on-going WIMP searches. An important background source for these searches is represented by neutron-induced nuclear recoils that can mimic the WIMP signal. In this paper we provide an estimation of the contribution to this background from the intrinsic radioactive contamination of nuclear emulsions. We also report the neutron-induced background as a function of the read-out threshold, by using a GEANT4 simulation of the nuclear emulsion, showing that it amounts to about 0.06 per year per kilogram, fully compatible with the design of a 10 kg × year exposure.

Treating radioactive effluent

International Nuclear Information System (INIS)

Kirkham, I.A.

1981-01-01

In the treatment of radioactive effluent it is known to produce a floc being a suspension of precipitates carrying radioactive species in a mother liquor containing dissolved non-radioactive salts. It is also known and accepted practice to encapsulate the floc in a solid matrix by treatment with bitumen, cement and the like. In the present invention the floc is washed with water prior to encapsulation in the solid matrix whereby to displace the mother liquor containing the dissolved non-radioactive salts. This serves to reduce the final amount of solidified radioactive waste with consequent advantages in the storage and disposal thereof. (author)

Geometry of all supersymmetric four-dimensional N = 1 supergravity backgrounds

International Nuclear Information System (INIS)

Gran, U.; Gutowski, J.; Papadopoulos, G.

2008-01-01

We solve the Killing spinor equations of N = 1 supergravity, with four supercharges, coupled to any number of vector and scalar multiplets in all cases. We find that backgrounds with N = 1 supersymmetry admit a null, integrable, Killing vector field. There are two classes of N = 2 backgrounds. The spacetime in the first class admits a parallel null vector field and so it is a pp-wave. The spacetime of the other class admits three Killing vector fields, and a vector field that commutes with the three Killing directions. These backgrounds are of cohomogeneity one with homogenous sections either R 2,1 or AdS 3 and have an interpretation as domain walls. The N = 3 backgrounds are locally maximally supersymmetric. There are N = 3 backgrounds which arise as discrete identifications of maximally supersymmetric ones. The maximally supersymmetric backgrounds are locally isometric to either R 3,1 or AdS 4 .

Development of international standards for instrumentation used for detection of illicit trafficking of radioactive material

International Nuclear Information System (INIS)

Voytchev, M.; Chiaro, P.; Radev, R.

2006-01-01

Subcommittee 45 B 'Radiation Protection Instrumentation' of the International Electrotechnical Commission (I.E.C.) is charged with the development of international standards for instrumentation used for monitoring of illicit trafficking of radioactive material through international boarders and territories, as well as inside countries. Currently three I.E.C. standards are in advanced stages of development. They are expected to be approved and published in 2006-2007. The international participation and the main characteristics of the following three standards are discussed and presented: I.E.C. 62327 'Hand-held Instruments for the Detection and Identification of Radionuclides and Additionally for the Indication of Ambient Dose Equivalent Rate from Photon Radiation', I.E.C. 62401 'Alarming Personal Radiation Devices for Detection of Illicit Trafficking of Radioactive Material' and I.E.C. 62244 'Installed Radiation Monitors for the Detection of Radioactive and Special Nuclear Materials at National Borders'

Dossier: transport of radioactive materials; Dossier: le transport des matieres radioactives

Energy Technology Data Exchange (ETDEWEB)

Mignon, H. [CEA Centre d`Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Direction du Cycle du Combustible; Niel, J.Ch. [CEA Centre d`Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; Canton, H. [CEA Cesta, 33 - Bordeaux (France); Brachet, Y. [Transnucleaire, 75 - Paris (France); Turquet de Beauregard, G.; Mauny, G. [CIS bio international, France (France); Robine, F.; Plantet, F. [Prefecture de la Moselle (France); Pestel Lefevre, O. [Ministere de l`Equipement, des transports et du logement, (France); Hennenhofer, G. [BMU, Ministere de l`environnement, de la protection de la nature et de la surete des reacteurs (Germany); Bonnemains, J. [Association Robin des Bois (France)

1997-12-01

This dossier is entirely devoted to the transportation of radioactive and fissile materials of civil use. It comprises 9 papers dealing with: the organization of the control of the radioactive materials transport safety (safety and security aspects, safety regulations, safety analysis and inspection, emergency plans, public information), the technical aspects of the regulation concerning the transport of radioactive materials (elaboration of regulations and IAEA recommendations, risk assessments, defense in depth philosophy and containers, future IAEA recommendations, expertise-research interaction), the qualification of containers (regulations, test facilities), the Transnucleaire company (presentation, activity, containers for spent fuels), the packages of radioactive sources for medical use (flux, qualification, safety and transport), an example of accident during radioactive materials transportation: the Apach train derailment (February 4, 1997), the sea transport of radioactive materials (international maritime organization (OMI), international maritime dangerous goods (IMDG) code, irradiated nuclear fuel (INF) safety rules), the transport of radioactive materials in Germany, and the point of view from an external observer. (J.S.)

Mode shape and natural frequency identification for seismic analysis from background vibration

International Nuclear Information System (INIS)

Bhan, S.; Wozniak, Z.

1986-02-01

The feasibility of calculating natural frequencies and mode shapes of major equipment in a CANDU reactor from the measurements of their response to background excitation has been studied. A review of vibration data measured at various locations in CANDU plants shows that structures responded to a combination of random and harmonic background excitation. Amplitude of measured vibration is sufficient to allow meaningful data analysis. Frequency content in the 0 to 50-Hz range, which is of interest for earthquake response, is present in some of the vibration measurements studied. Spectral techniques have been developed for determining the response function of structures from measured vibration response to background excitation. The natural frequencies and mode shapes are then evaluated graphically from the frequency function plots. The methodology has been tested on a simple cantilever beam with known natural frequencies and mode shapes. The comparison between the theoretical and the computed natural frequencies and mode shapes is good for the lower modes. However, better curve-fitting techniques will be required in future, especially for higher modes. Readily available equipment necessary for the measurement of background vibration in a CANDU plant (which is commercially available) has been identified. An experimental program has been proposed to verify the methodology developed in this study. Recommendations are also made to study methods to improve the accuracy of the mode shape and natural frequency prediction

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

International Nuclear Information System (INIS)

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

2011-01-01

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

Automatized system of radioactive material analysis

International Nuclear Information System (INIS)

Pchelkin, V.A.; Sviderskij, M.F.; Litvinov, V.A.; Lavrikov, S.A.

1979-01-01

An automatized system has been developed for the identification of substance, element and isotope content of radioactive materials on the basis of data obtained for studying physical-chemical properties of substances (with the help of atomic-absorption spectrometers, infrared spectrometer, mass-spectrometer, derivatograph etc.). The system is based on the following principles: independent operation of each device; a possibility of increasing the number of physical instruments and devices; modular properties of engineering and computer means; modular properties and standardization of mathematical equipment, high reliability of the system; continuity of programming languages; a possibility of controlling the devices with the help of high-level language, typification of the system; simple and easy service; low cost. Block-diagram of the system is given

Working on an assured future: the control in Western-Europe of radioactive waste

International Nuclear Information System (INIS)

Boekschoten, H.

1989-01-01

This report presents background information with regard to the policy concerning the disposal and storage of radioactive waste. Also is outlined how this is being worked on by the various European countries which are joined in the UNIPEDE. (author). 60 figs.; 1 tab

Focus on radioactivity

Energy Technology Data Exchange (ETDEWEB)

Lambert, M

1989-01-01

Written for children, this book looks at the nature of radioactive materials, how they were discovered, what they are used for and how they affect the environment around us. The emphasis is on the benefits of radioactive materials, particularly in nuclear power stations, in medical diagnostics and radiotherapy, in industry and in agriculture. Nuclear fission and fusion are explained, how radioactive materials are handled and naturally occurring radioactivity are included. (UK).

Interpretation of low-level environmental radioactivity measurements

International Nuclear Information System (INIS)

Zeigler, C.C.

1982-01-01

Levels of radioactivity in the environment from worldwide fallout have decreased by about a factor of 10 since the early 1970's and many environmental concentrations are now less than the routine estimated lower limit of detection. To accurately represent these data and to assist in evaluating very low levels of radioactivity, each instrumental value with its statistical counting error should be reported. In some instances the background count of the instrument exceeds the sample count resulting in a value that is less than zero (a negative concentration). Evaluation of these negative numbers along with zero and positive concentrations over a suitable sample population can yield important information about concentrations that are less than routine minimum levels of detection. Actual instrumental values (negative, zero and positive) with associated statistical counting errors have been reported by the Environmental Monitoring Group at the Savannah River Plant since 1977. Methods for evaluating these data are discussed and empirical data presented to illustrate important points

Reduction of radioactive backgrounds in electroformed copper for ultra-sensitive radiation detectors

Energy Technology Data Exchange (ETDEWEB)

Hoppe, E.W., E-mail: eric.hoppe@pnnl.gov [Pacific Northwest National Laboratory, Richland, WA 99352 (United States); Aalseth, C.E.; Farmer, O.T.; Hossbach, T.W.; Liezers, M.; Miley, H.S.; Overman, N.R. [Pacific Northwest National Laboratory, Richland, WA 99352 (United States); Reeves, J.H. [Reeves and Son LLC, 10 Albert Ave., Richland, WA 99352 (United States)

2014-11-11

Ultra-pure construction materials are required for the next generation of neutrino physics, dark matter and environmental science applications. These materials are also important for use in high-purity germanium spectrometers used in screening materials for radiopurity. The next-generation science applications require materials with radiopurity levels at or below 1 μBq/kg {sup 232}Th and {sup 238}U. Yet radiometric analysis lacks sensitivity below ∼10 μBq/kg for the U and Th decay chains. This limits both the selection of clean materials and the validation of purification processes. Copper is an important high-purity material for low-background experiments due to the ease with which it can be purified by electrochemical methods. Electroplating for purification into near-final shapes, known as electroforming, is one such method. Continued refinement of the copper electroforming process is underway, for the first time guided by an ICP-MS based assay method that can measure {sup 232}Th and {sup 238}U near the desired purity levels. An assay of electroformed copper at a μBq/kg level has been achieved and is described. The implications of electroformed copper at or better than this purity on next-generation low-background experiments are discussed.

Study of the material photon and electron background and the liquid argon detector veto efficiency of the CDEX-10 experiment

International Nuclear Information System (INIS)

Su Jian; Zeng Zhi; Ma Hao

2015-01-01

The China Dark Matter Experiment (CDEX) is located at the China Jinping Underground Laboratory (CJPL) and aims to directly detect the weakly interacting massive particles (WIMP) flux with high sensitivity in the low mass region. Here we present a study of the predicted photon and electron backgrounds including the background contribution of the structure materials of the germanium detector, the passive shielding materials, and the intrinsic radioactivity of the liquid argon that serves as an anti-Compton active shielding detector. A detailed geometry is modeled and the background contribution has been simulated based on the measured radioactivities of all possible components within the GEANT4 program. Then the photon and electron background level in the energy region of interest (< 10 -2 events·kg 1 ·day -1 ·keV -1 (cpkkd)) is predicted based on Monte Carlo simulations. The simulated result is consistent with the design goal of the CDEX-10 experiment, 0.1cpkkd, which shows that the active and passive shield design of CDEX-10 is effective and feasible. (authors)

Determination of cosmic ray produced radionuclides by means of background radiation counting system, 3

International Nuclear Information System (INIS)

1976-01-01

This is the third report of the progress report series on studies of cosmic ray produced radionuclides by means of low background radiation counting system. In Part I some characteristics of a low beta-gamma coincidence spectrometer are described -- counter system, electronics, background spectra, counting efficiencies -- and studies on radioactive impurities in materials for scientific research are also described. In Part II, suitable solvents for a large scale liquid scintillation counter were examined and best combinations of solvents, solutes and naphthalene are shown. In Part III, miscellaneous topics are reported. (auth.)

Low background aspects of GERDA

International Nuclear Information System (INIS)

Simgen, Hardy

2011-01-01

The GERDA experiment operates bare Germanium diodes enriched in 76 Ge in an environment of pure liquid argon to search for neutrinoless double beta decay. A very low radioactive background is essential for the success of the experiment. We present here the research done in order to remove radio-impurities coming from the liquid argon, the stainless steel cryostat and the front-end electronics. We found that liquid argon can be purified efficiently from 222 Rn. The main source of 222 Rn in GERDA is the cryostat which emanates about 55 mBq. A thin copper shroud in the center of the cryostat was implemented to prevent radon from approaching the diodes. Gamma ray screening of radio-pure components for front-end electronics resulted in the development of a pre-amplifier with a total activity of less than 1 mBq 228 Th.

A study of hydrogen effects on fracture behavior of radioactive waste storage tanks

International Nuclear Information System (INIS)

Murty, K.L.; Elleman, T.S.

1993-01-01

Since the high-level radioactive waste at Savannah River and Hanford may have to occupy steel tanks for many years before processing, research was directed toward examination of hydrogen effects in carbon steels and identification of radiation-enhanced hydrogen uptake in steels. Results to date are too preliminary for any conclusions to be made; however, experimental methods for measuring hydrogen gradients appear to be satisfactory. 5 figs, 1 fig

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.

Romanian experience in a assessment of the risk and environmental consequences due to radioactive materials transportation

International Nuclear Information System (INIS)

Vieru, Gheorghe

2006-01-01

Full text: The transport of radioactive materials (RAM) is a very important problem taking into consideration its potential risks over the environment and the radiological consequences of this activity. Romania as a Member State of the International Atomic Energy Agency has implemented national regulations for a safe transport of RAM in complying with the Agency's recommendations as well as other international specialized organizations. The paper will present the main sources of radioactive materials in Romania, and their transportation routes with a particular focus on the radioactive wastes (very low level and mixed low-level radioactive materials), radioactive isotopes and sources, and natural uranium ore. Starting from the fact that the safety in the transport of radioactive materials is dependent on packaging appropriate for the contents being shipped, rather than operational and/or administrative actions required for the package, the paper presents, very briefly, the qualification tests for the main packages used for transport and storage of RAM in Romania. There are presented also specific problems related to the identification and evaluation of the environmental risks and impacts as well as the potential radiological consequences associated with the transport of radioactive materials, for all those three possible situations: routine transport (without incidents), normal transport (with minor incidents) and during potential accidents. As a conclusion, it is stated that the evaluated annual collective dose for the population due to RAM transport is less than those received by natural radiation sources. At the same time it is concluded that Romanian made packages are safe and prevent loss of its radioactive contents into environment. (author)

On risk assessment of high level radioactive waste disposal

International Nuclear Information System (INIS)

Smith, C.F.; Kastenberg, W.E.

1976-01-01

One of the major concerns with the continued growth of the nuclear power industry is the production of the high level radioactive wastes. The risks associated with the disposal of these wastes derives from the potential for release of radioactive materials into the environment. The development of a methodology for risk analysis is carried out. The methodology suggested involves the probabilistic analysis of a general accident consequence distribution. In this analysis, the frequency aspect of the distribution is treated separately from the normalized probability function. In the final stage of the analysis, the frequency and probability characteristics of the distribution are recombined to provide an estimate of the risk. The characterization of the radioactive source term is accomplished using the ORIGEN computer code. Calculations are carried out for various reactor types and fuel cycles, and the overall waste hazard for a projected 35 year nuclear power program is determined. An index of relative nuclide hazard appropriate to problems involving the management of high level radioactive wastes is developed. As an illustration of the methodology, risk analyses are made for two proposed methods for waste management: extraterrestrial disposal and interim surface storage. The results of these analyses indicate that, within the assumptions used, the risks of these management schemes are small compared with natural background radiation doses. (Auth.)

Management program on radioactive wastes in research

International Nuclear Information System (INIS)

Xavier, Ana Maria; Wieland, Patricia; Heilbron Filho, Paulo Fernando L.; Ferreira, Rubemar de Souza

1998-01-01

This document has the objective to orient and advise the researchers to practice a safety management of radioactive wastes in each research laboratory, based upon the technical norms of the Brazilian Nuclear Energy Commission and the recommendations of the International Atomic Energy Agency. Additionally, basic information on the main radioisotopes used in research are presented, including the processes used for production of radioisotopes, methods for radiation detection, range of alpha and beta particles, background radiation, as well as principles on radioprotection and biological effects of radiation

Radioactive and industrial waste water collection system study, Phase I

International Nuclear Information System (INIS)

1993-01-01

Phase I of the Radioactive Liquid Waste (RLW) Collection System Study has been completed, and the deliverables for this portion of the study are enclosed. The deliverables include: The Work Break-down Structure (WBS) for Phase II; The Annotated Outline for the Collection Study Report; The Process Flow Diagrams (PFD) of the RLW collection system based on current literature and knowledge; The Configuration database; The Reference Index, listing all currently held documents of the RLW collection system; The Reference Drawing Index listing all currently held, potentially applicable, drawings reviewed during the PFD development; The Regulation Identification Document for RCRA and CWA; The Regulation Database for RCRA and CWA; The Regulation Review Log, including statements justifying the non-applicability of certain regulations; Regulation Library, including the photocopied regulations with highlighted text for RCRA and CWA; The summary of RTG's waste water treatment plant design experience and associated regulations on which RTG based the design of these treatment facilities; TA-50 Influent Database; Radioactive Liquid Waste Stream Characterization Database

Revised Arrangements for the Management of Solid and Non-Aqueous Radioactive Waste - 12452

Energy Technology Data Exchange (ETDEWEB)

Fullbrook, Michael; Walker, Johann; Macnab, Alec [Atomic Weapons Establishment, Aldermaston (United Kingdom)

2012-07-01

In 2010, Atomic Weapons Establishment (AWE) identified a requirement to implement revised management arrangements for the generation, storage and disposal of radioactive waste. A thorough review of the current arrangements/processes was undertaken which included both legal compliance requirements and the identification of business improvement opportunities. On completion of this review a suitable project team was established and in 2011 an integrated Radioactive Waste Management process was implemented throughout the business. Initial results have shown measurable improvements within Radioactive Waste management compliance, operator understanding and increased business efficiency. Through the development and implementation of the revised working arrangements AWE has been able to continue to demonstrate both legal compliance to its regulators along with business efficiency and effectiveness improvements. Simple to follow process maps have improved employees understanding of Radioactive Waste management requirements, provided them with easily accessible information and ensured the business operates in a single coherent manner. The implementation of a modern electronic data management system has ensured all waste related information is easily retrievable and appropriately maintained. The additional functions that have been built into the system have reduced the potential for human error and increased the overall efficiency of the Waste Management department through the use of the automated report generation functionality. (authors)

Radioactive waste management solutions

International Nuclear Information System (INIS)

Siemann, Michael

2015-01-01

One of the more frequent questions that arise when discussing nuclear energy's potential contribution to mitigating climate change concerns that of how to manage radioactive waste. Radioactive waste is produced through nuclear power generation, but also - although to a significantly lesser extent - in a variety of other sectors including medicine, agriculture, research, industry and education. The amount, type and physical form of radioactive waste varies considerably. Some forms of radioactive waste, for example, need only be stored for a relatively short period while their radioactivity naturally decays to safe levels. Others remain radioactive for hundreds or even hundreds of thousands of years. Public concerns surrounding radioactive waste are largely related to long-lived high-level radioactive waste. Countries around the world with existing nuclear programmes are developing longer-term plans for final disposal of such waste, with an international consensus developing that the geological disposal of high-level waste (HLW) is the most technically feasible and safe solution. This article provides a brief overview of the different forms of radioactive waste, examines storage and disposal solutions, and briefly explores fuel recycling and stakeholder involvement in radioactive waste management decision making

Investigation of the radioactivity in the environment around the Blayais CNPE

International Nuclear Information System (INIS)

Barbey, P.; Boilley, D.; Josset, M.; Migeon, A.; Bernollin, A.; Dunand, E.

2012-01-01

This document reports the identification of potential sources of radioactive pollutions of the Blayais CNPE (nuclear power plant for the production of electricity) in France, recalls the results of a previous study, and indicates the geographic and radiologic perimeters of the investigation. It reports the radio-ecological investigation of the aqueous medium (sediments, aqueous plants, fish, water), of the ground medium (soil and plants), and the investigation of transfers of chemical species (hydrazine, morpholine, boron, lithium) by the power plant

Management and packaging of radioactive sources (90Sr) for their transport

International Nuclear Information System (INIS)

Morales C, M; Roas Z, N.

2000-09-01

This work describes the different activities that were carried out in relation to the identification of five sources of 90 Sr and the administrative administrations in the face of the regulatory authority of the country, Comision Nacional de Energia Atomica (CONEA), for the transfer of the sources toward its final destination. The preparation of the package and the documentation presented before the CONEA were in agreement to that settled down in the Regulation for the safe transport of radioactive materials (IAEA)

Idaho National Engineering Laboratory hazardous and radioactive mixed waste identification and characterization report for CY 1986

International Nuclear Information System (INIS)

Nishimoto, D.D.

1987-05-01

This report provides updated tabulations of the hazardous and radioactive mixed wastes generated and/or handled during CY 1986 at each INEL facility operated by EG and G, or any other operating contractor at the Site. These wastes are described in tabular form, providing information such as composition, generating process, contact person, EPA hazardous waste designation, quantity shipped off site (if applicable), and quantity in storage. Waste generation projections for the next ten years are also included for all INEL facilities. Finally, since many of EG and G's inactive disposal sites may prove to be significant sources of either hazardous or radioactive mixed wastes as remedial action activities under RCRA or CERCLA progress, information on these sites is provided. 2 refs., 1 fig., 8 tabs

Radioactive waste management

International Nuclear Information System (INIS)

Balek, V.

1994-01-01

This booklet is a publication by International Atomic Energy Agency for general awareness of citizens and policy-makers to clarify their concept of nuclear wastes. In a very simple way it tells what is radioactivity, radiations and radioactive wastes. It further hints on various medial and industrial uses of radiations. It discusses about different types of radioactive wastes and radioactive waste management. Status of nuclear power plants in Central and Eastern European countries are also discussed

Identification of High Confidence Nuclear Forensics Signatures. Results of a Coordinated Research Project and Related Research

International Nuclear Information System (INIS)

2017-08-01

The results of a Coordinated Research Project and related research on the identification of high confidence nuclear forensic isotopic, chemical and physical data characteristics, or signatures, provides information on signatures that can help identify the origin and history of nuclear and other radioactive material encountered out of regulatory control. This research report compiles findings from investigations of materials obtained from throughout the nuclear fuel cycle to include radioactive sources. The report further provides recent results used to identify, analyse in the laboratory, predict and interpret these signatures relative to the requirements of a nuclear forensics examination. The report describes some of the controls on the incorporation and persistence of these signatures in these materials as well as their potential use in a national system of identification to include a national nuclear forensics library.

Investigation of background processes in the KATRIN main spectrometer

Energy Technology Data Exchange (ETDEWEB)

Mueller, Axel [Karlsruhe Institute of Technology (KIT), Institut fuer Kernphysik (IKP) (Germany); Collaboration: KATRIN-Collaboration

2016-07-01

The KArlsruhe TRItium Neutrino experiment aims to probe the mass of the electron antineutrino in a model-independent way with an unsurpassed sensitivity of m{sub ν}=200 meV/c{sup 2} (90% C.L.). In order to determine the neutrino mass, the energy spectrum of electrons from the tritium β-decay is analyzed by a high-resolution electrostatic spectrometer which is based on the MAC-E filter principle. To keep the influence of the spectrometer background on the neutrino mass sensitivity small, KATRIN aims for a background level of 0.01 cps. For the investigation of different background components such as cosmic muons, external gamma radiation and the radioactive decay of isotopes in the volume of the spectrometer or on its surface, a series of dedicated measurements were performed with a combined system of main spectrometer and detector. This talk presents the results of measurements focusing on the secondary electron production at the inner surface of the spectrometer and compare them with electro-magnetic electron tracking simulations performed with the KATRIN developed simulation software KASSIOPEIA.

Cost benefit analysis, sustainability and long-lived radioactive waste management

International Nuclear Information System (INIS)

Berkhout, F.

1994-01-01

The objective of this paper is to examine how far the sustainability concept and the technique of cost-benefit analysis (CBA) can be applied to the problem of radioactive waste management. The paper begins with a slightly altered definition of the problem to the one carried in the Nea's background document (Nea 1994). A preliminary attempt is then be made to ascribe burdens to the various phases of long-lived radioactive waste management. The appropriateness of CBA and the sustainability concept for making decisions about long-term waste management policy is then discussed. The author ends with some conclusions about the appropriateness of systematic assessment approaches in the political process of constructing social consent for technological decisions. (O.L.). 12 refs., 1 tab

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

weapons in the 1950s and 1960s and releases from past nuclear accidents such as Chernobyl. Milk, because it is an important foodstuff for infants and children and is known to concentrate long lived radionuclides such as caesium-137 and strontium-90, is an important indicator of levels of artificial radioactivity in the terrestrial food chain. The estimated dose due to strontium-90 activity in milk was estimated to be 0.97 ?Sv for 2009. This was for the most exposed group, assessed to be infants, children under the age of one year. It is very small compared to the background radiation. Radioactivity measurements on other foodstuffs confirm the levels of artificial radioactivity in the Irish food-chain remain very low and that Irish foodstuffs are free from harmful levels of radioactivity. The RPII monitors radioactivity in drinking water supplies in rotation so that major supplies from each county are sampled at least once every four years. During 2009 supplies from Galway, Kerry, Kildare, Kilkenny, Leitrim, Longford, Limerick and Laois were tested. Drinking water samples are assessed for compliance with the radioactivity standards set out in the Drinking Water Directive. All drinking water samples tested during 2009 were found to be in compliance with the radioactivity standards set out in the Drinking Water Directive. The RPII programme also monitors airborne radioactivity through its network of on- and off-line samplers. External gamma dose rates are also monitored. No exceptional activity was detected in outdoor air during 2009. The levels were consistent with those recorded in previous years. For 2009 the average annual dose from inhalation of caesium-137 was estimated at 9.0 x 10?? ?Sv. The data presented in this report confirm that while the levels of artificial radioactivity in the Irish environment are detectable they are low and are continuing to decrease. They do not pose a significant risk to the human health of the Irish population. Activity concentrations of

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

weapons in the 1950s and 1960s and releases from past nuclear accidents such as Chernobyl. Milk, because it is an important foodstuff for infants and children and is known to concentrate long lived radionuclides such as caesium-137 and strontium-90, is an important indicator of levels of artificial radioactivity in the terrestrial food chain. The estimated dose due to strontium-90 activity in milk was estimated to be 0.55 ?Sv for 2008. This was for the most exposed group, assessed to be infants, children under the age of one year. It is very small compared to the background radiation. Radioactivity measurements on other foodstuffs confirm the levels of artificial radioactivity in the Irish food-chain remain very low and that Irish foodstuffs are free from harmful levels of radioactivity. The RPII monitors radioactivity in drinking water supplies in rotation so that major supplies from each county are sampled at least once every four years. During 2008 supplies from Carlow, Cavan, Clare, Cork, Donegal and Dublin were tested. Drinking water samples are assessed for compliance with the radioactivity standards set out in the Drinking Water Directive. All drinking water samples tested during 2008 were found to be in compliance with the radioactivity standards set out in the Drinking Water Directive. The RPII programme also monitors airborne radioactivity through its network of on- and off-line samplers. External gamma dose rates are also monitored. No exceptional activity was detected in outdoor air during 2008. The levels were consistent with those recorded in previous years. For 2008 the average annual dose from inhalation of caesium-137 was estimated at 8.0 x 10?? ?Sv. The data presented in this report confirm that while the levels of artificial radioactivity in the Irish environment are detectable they are low and are continuing to decrease. They do not pose a significant risk to the human health of the Irish population. Activity concentrations of radionuclides in airborne

Best available technology for the Los Alamos National Laboratory Radioactive Liquid Waste Treatment Facility

International Nuclear Information System (INIS)

Midkiff, W.S.; Romero, R.L.; Suazo, I.L.; Garcia, R.; Parsons, R.M.

1993-01-01

The existing Los Alamos National Laboratory TA-50 liquid radioactive waste treatment plant RLWP has been in service for over thirty years, during this period many technical, regulatory, and processing changes have occurred. The existing facility can no longer comply with the demands and requirements for continued operation, and would not be able to comply with anticipated stringent future contaminant discharge limitations. Either a major upgrading or replacement of the existing facility is required. In order to assess the most appropriate means of providing an adequate facility to comply with predicted requirements for Ta-50, this Best Available Technology (BAT) Study was conducted to compare feasible technical and economic alternatives in order to define the most favorable technology configuration. This report consists of eleven sections. Section 1 provides a general introduction and background of the TA-50 operations and the basis for this study. Section 2 provides a technical discussion of the unit processes at TA-50 and several other comparable operations at other DOE sites. Section 3 addresses the evaluation and selection of appropriate treatment processes. Section 4 provides an analysis of environmental issues and concerns. Section 5 presents the rationale for the selection of preferred process configurations. Section 6 is the evaluation of operational issues. Section 7 addresses energy and resource use topics. Section 8 provides an economic analysis, and Section 9 summarizes the evaluation and the identification of the BAT. These sections are augmented by appendices. The report identifies the construction of a new radioactive liquid waste treatment facility as the BAT. Based on the information analyzed for this study, this option appears to provide the best combination of environmental compliance, operability, and economic value

Transport of radioactive material in Romania -the assessment of the radiological consequences and the environmental impacts

International Nuclear Information System (INIS)

Vieru, Gheorghe

2008-01-01

The transport of radioactive materials (RAM) is a very important problem considering the potential risks and radiological consequences in carrying-out this activity. Romania as a Member State of the International Atomic Energy Agency has implemented national regulations for a safe transport of RAM in accordance with the Agency's recommendations as well as other international specialized organizations. Based on the IAEA's Safety Standard-TS-R-1 (ST-1), Romanian National Nuclear Regulatory Body - CNCAN adopted and implemented, by Act no. 357/December 21, 2005, the safety regulations for the transport of radioactive materials in Romania under the title: 'Regulations for the Transport of Radioactive Materials'. The paper will present the main sources of radioactive materials in Romania their transportation routes with a particular interest paid to the radioactive wastes (low level radioactive materials), isotopes and radioactive sources, uranium ore. Starting from the fact that the safety in the transport of radioactive materials is dependent on appropriate packaging for the contents being shipped, rather than operational and/or administrative actions required for the package, the paper presents, briefly the main packages used for transport and storage of such RAM in Romania. There are presented hypothetical scenarios for specific problems related to the identification and evaluation of the risks and potential radiological consequences associated with the transport of radioactive materials in Romania, for all these three situations: routine transport (without incidents), normal transport (with minor incidents) and during possible accidents. As a conclusion, it is ascertained that the evaluated annual collective dose for the population due to RAM transport is less than that received by natural radiation sources. At the same time it is concluded that Romanian made packages are safe and prevent loss of their radioactive contents into the environment. (author)

LUCIFER, a potentially background-free approach to the search for neutrinoless double beta decay

Energy Technology Data Exchange (ETDEWEB)

Nones, C. [Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, Bat. 108 Orsay Campus - Orsay (France)

2011-08-15

LUCIFER (Low-background Underground Cryogenic Installation For Elusive Rates) is a new project for the study of neutrinoless Double Beta Decay, based on the technology of scintillating bolometers. These devices promise a very efficient rejection of the alpha background, opening the way to a virtual background-free experiment if candidates with a transition energy higher than 2615 keV are investigated. The baseline candidate for LUCIFER is {sup 82}Se. This isotope will be embedded in ZnSe crystals grown with enriched selenium and operated as scintillating bolometers in a low-radioactivity underground dilution refrigerator. In this paper, the LUCIFER concept will be introduced. The sensitivity and the very promising prospects related to this project will be discussed.

Background study of absorbed dose in biological experiments at the Modane Underground Laboratory

Directory of Open Access Journals (Sweden)

Lampe Nathanael

2016-01-01

Full Text Available Aiming to explore how biological systems respond to ultra-low background environ-ments, we report here our background studies for biological experiments in the Modane Under-ground Laboratory. We find that the minimum radioactive background for biology experiments is limited by the potassium content of the biological sample itself, coming from its nutritive me-dium, which we find in our experimental set-up to be 26 nGy hr-1. Compared to our reference radiation environment in Clermont-Ferrand, biological experiments can be conducted in the Modane laboratory with a radiation background 8.2 times lower than the reference above-ground level. As the radiation background may be further reduced by using different nutritive media, we also provide measurements of the potassium concentration by gamma spectroscopy of yeast extract (63.3±1.2 mg g-1 and tryptone (2.5±0.2 mg g-1 in order to guide media selection in future experiments.

Reducing Uncontrolled Radioactive Sources through Tracking and Training: US Environmental Protection Agency Initiatives

Energy Technology Data Exchange (ETDEWEB)

Kopsick, D.A., E-mail: kopsick.deborah@epa.gov [US Environmental Protection Agency, Washington, DC (United States)

2011-07-15

The international metal processing industries are very concerned about the importation of scrap metal contaminated with radioactive materials. When radioactive sources fall out of regulatory control, improper handling can cause serious injury and death. There is no one way to address this problem and various US governmental and industry entities have developed radiation source control programmes that function within their authorities. The US Environmental Protection Agency's (EPA) mission is to protect public health and the environment. To ensure this protection, EPA's approach to orphan sources in scrap metal has focused on regaining control of lost sources and preventing future losses. EPA has accomplished this through a number of avenues including training development, product stewardship, identification of non-radiation source alternatives, physical tagging of sources, field testing of innovative radiation detection instrumentation and development of international best practices. In order to achieve its goal of enhanced control on contaminated scrap metal and orphaned radioactive sources, EPA has forged alliances with the metals industry, other Federal agencies, state governments and the IAEA. (author)

Radioactivity monitoring of the Irish marine environment 1991 and 1992

International Nuclear Information System (INIS)

McGarry, A.; Lyons, S.; McEnri, C.; Ryan, T.; O'Colmain, M.; Cunningham, J.D.

1994-05-01

This report presents the results of the Radiological Protection Institute's programme of monitoring of radioactivity in the seas around Ireland during 1991 and 1992. The principal objective of the monitoring programme is to review the risks to human health arising from the Sellafield discharges. Secondary objectives include studies of the distribution of the significant contaminating radionuclides in the marie environment and the identification of trends with a view to assessing possible future effects. Estimates of the radiation doses to the Irish public are also presented in this report. 23 refs. 24 tabs. 9 figs

Radioactive consumer products

International Nuclear Information System (INIS)

Sato, Otomaru

1981-01-01

Present situation of utilizing the radioactive consumer products and exposure dose were reviewed with published data. Practically, consumer products are divided into three categories, (1) radioactive nuclides intentionally incorporated into radioluminous dye, ionization chambers for smoke detector, eliminator of static electricity, and glow lamp (2) natural radioactive nuclides contained in false teeth, porcelain, glass, and gas mantle (3) natural radioactive nuclides accumulated as industrial waste at the consumption of coal, petroleum, and natural gas or in fertilizer and materials for construction. (Nakanishi, T.)

Safety of radiation sources and security of radioactive materials. Contributed papers