WorldWideScience

Sample records for water radioactivity measurements

  1. Measurement of radioactivity in water samples

    International Nuclear Information System (INIS)

    Richards, L.

    1990-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

  3. Measurement of liquid radioactive materials for monitoring radioactive emissions

    International Nuclear Information System (INIS)

    1977-10-01

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

  4. Validation of radioactivity measurements under the Safe Drinking Water Act

    International Nuclear Information System (INIS)

    Goldin, Abraham S.

    1978-01-01

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

  5. A critical review of measures to reduce radioactive doses from drinking water and consumption of freshwater foodstuffs

    International Nuclear Information System (INIS)

    Smith, J.T.; Voitsekhovitch, O.V.; Haakanson, L.; Hilton, J.

    2001-01-01

    Following a radioactive fallout event, there are a number of possible intervention measures to reduce radioactive doses to the public via the surface water pathway. We have critically reviewed the options available to decision-makers in the event of radioactive contamination of surface waters. We believe that the most effective and viable measures to reduce radioactivity in drinking water are those which operate at the water treatment and distribution stage. Intervention measures to reduce concentrations of radioactivity in rivers and reservoirs are expected to be much less viable and efficient at reducing doses via the drinking water pathway. Bans on consumption of freshwater fish can be effective, but there are few viable measures to reduce radioactivity in fish prior to the preparation stage. Lake liming and biomanipulation have been found to be ineffective for radiocaesium, although the addition of potassium to lakewaters appears promising in some situations. Lake liming may be effective in reducing radiostrontium in fish, though this has not, to our knowledge, been tested. De-boning fish contaminated by strontium is probably the most effective food preparation measure, but salting and freezing can also reduce radiocaesium concentrations in fish. The provision of accurate information to the public is highlighted as a key element of countermeasure implementation

  6. 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.)

  7. Influence of crosstalk phenomenon on the measurement of gross alpha and gross beta radioactivity in drinking water

    International Nuclear Information System (INIS)

    Gerilemandahu; Haribala; Xu Xiao; Shen Na; Sai Wenga; Bai Guilin; Wang Chengguo

    2014-01-01

    Objective: To study the influence of crosstalk phenomenon on the measurement of gross radioactivity in drinking water. Methods: The gross activity in different standard materials with different thickness and area was measured using national standard method. Results: There was no obvious change in crosstalk factor with the increase of "2"4"1Am powder amount in the measurement, whereas the larger amount of uranium used might lead to larger crosstalk factor. The different measurement channels resulted in different crosstalk factors. The influence of beta radioactivity on alpha radioactivity measurement was significant. On the contrary, the alpha-to-beta crosstalk factor was negligible. The area of sample plate imposed no significant influence on crosstalk factor. Conclusions: The gross beta activity can be corrected to decrease the influence of alpha radioactivity using powder standard samples, when simultaneous alpha and beta counting mode is applied in measurement grass radioactivity in drinking water. (authors)

  8. Radioactivity measurement in spring waters of Cantabria, Spain

    International Nuclear Information System (INIS)

    Soto Torres, J.; Gomez Arozamena, J.

    1999-01-01

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

  9. The control of water radioactivity

    International Nuclear Information System (INIS)

    Bovard, P.; Graubey, A.

    1962-01-01

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

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

    International Nuclear Information System (INIS)

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

    2007-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    1975-07-01

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

  12. Radioactive substances in tap water.

    Science.gov (United States)

    Atsuumi, Ryo; Endo, Yoshihiko; Suzuki, Akihiko; Kannotou, Yasumitu; Nakada, Masahiro; Yabuuchi, Reiko

    2014-01-01

    A 9.0 magnitude (M) earthquake with an epicenter off the Sanriku coast occurred at 14: 46 on March 11, 2011. TEPCO Fukushima Daiichi Nuclear Power Plant (F-1 NPP) was struck by the earthquake and its resulting tsunami. Consequently a critical nuclear disaster developed, as a large quantity of radioactive materials was released due to a hydrogen blast. On March 16(th), 2011, radioiodine and radioactive cesium were detected at levels of 177 Bq/kg and 58 Bq/kg, respectively, in tap water in Fukushima city (about 62km northwest of TEPCO F-1 NPP). On March 20th, radioiodine was detected in tap water at a level of 965 Bq/kg, which is over the value-index of restrictions on food and drink intake (radioiodine 300 Bq/kg (infant intake 100 Bq/kg)) designated by the Nuclear Safety Commission. Therefore, intake restriction measures were taken regarding drinking water. After that, although the all intake restrictions were lifted, in order to confirm the safety of tap water, an inspection system was established to monitor all tap water in the prefecture. This system has confirmed that there has been no detection of radioiodine or radioactive cesium in tap water in the prefecture since May 5(th), 2011. Furthermore, radioactive strontium ((89) Sr, (90)Sr) and plutonium ((238)Pu, (239)Pu+(240)Pu) in tap water and the raw water supply were measured. As a result, (89) Sr, (238)Pu, (239)Pu+(240)Pu were undetectable and although (90)Sr was detected, its committed effective dose of 0.00017 mSv was much lower than the yearly 0.1 mSv of the World Health Organization guidelines for drinking water quality. In addition, the results did not show any deviations from past inspection results.

  13. Handbook of radioactivity measurements procedures. Second edition

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

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

  14. Natural radioactivity in water supplies

    International Nuclear Information System (INIS)

    Horner, J.K.

    1985-01-01

    This book outlines the scientific aspects of the control of natural radioactivity in water supplies, as well as the labyrinthine uncertainties in water quality regulation concerning natural radiocontamination of water. The author provides an introduction to the theory of natural radioactivity; addresses risk assessment, sources of natural radiocontamination of water, radiobiology of natural radioactivity in water, and federal water law concerning natural radiocontamination. It presents an account of how one city dealt with the perplexes that mark the rapidly evolving area of water quality regulation. The contents include: radioactivity and risk; an introduction to the atomic theory; an introduction to natural radioactivity; risk assessment; uranium and radium contamination of water; radiobiology of uranium and radium in water. Determination of risk from exposure to uranium and radium in water; the legal milieu; one city's experience; and summary: the determinants of evolving regulation

  15. Environmental radioactivity measurement. Ispra 1990

    International Nuclear Information System (INIS)

    Dominici, G.; Risposi, L.

    1992-01-01

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

  16. Gross alpha radioactivity of drinking water in Venezuela

    International Nuclear Information System (INIS)

    Sajo-Bohus, L.; Gomez, J.; Greaves, E.D.; Herrera, O.; Salazar, V.; Smith, A.

    1997-01-01

    Bottled mineral water is consumed by a large population in Venezuela. The alpha emitters concentration was measured in samples of bottled water and water springs collected near the surface. Approximately 30% of the total mineral water suppliers was monitored. a database on natural and artificial radioactivity in drinking water was produced. Results indicate that 54% of the waters sampled contain a total alpha radioactivity of less than 0.185 Bql -1 and only 12% above 0.37 Bql -1 . Our results revealed a total annual dose of 2.3 mSv year -1 . (author)

  17. Radioactivity levels in surface water of lakes around Izmir / Turkey

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  18. An On-Line Water Monitor for Low Level {beta}-Radioactivity Measurements

    Energy Technology Data Exchange (ETDEWEB)

    Quirk, E J.M.

    1968-05-15

    A detection system is described for the continuous monitoring of {beta}-radioactivity in the secondary cooling water at the Studsvik R2 reactor. Radiation emanating from a water surface is measured by a large area gas proportional detector. To protect the detector from splash caused by bursting bubbles a protective film and heater assembly is interposed between the detector and the water surface. A special feature is the programmed 'exercise' sequence for the magnetic valves which eliminates a tendency for them to stick after prolonged periods of idleness. The extent to which contamination affects the background counting rate has been studied. It is shown that for the duration of the tests described the monitor remains free from the effects of contamination so long as the scaler live time is suitably chosen. Minimum measurable specific activities obtainable in practice extend from 4 x 10{sup -6} to 3.86 x 10{sup -8} Ci/m{sup 3} depending on the {beta} end-point energy in the range 167 keV - 2.26 MeV.

  19. Measurements on radioactive dusts over Calcutta

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-01-01

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

  20. Radioactivity in bottled waters sold in Mexico

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  1. Radioactivity monitoring of fallout, water and ground

    International Nuclear Information System (INIS)

    Radosavljevic, R.

    1961-01-01

    During 1961, the radioactivity monitoring of the Boris Kidric Institute site covered monitoring of the total β activity of the fallout and water on the site. Activity of the fallout was monitored by measuring the activity of the rain and collected sedimented dust form the atmosphere. Water monitored was the water from Danube and river Mlaka, technical and drinking water. Plants and soil activity were not measured although sample were taken and the total β activity will be measured and analysed later

  2. 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

  3. Measurement of environmental radioactivity. Ispra 1977

    International Nuclear Information System (INIS)

    Dominici, G.

    1979-01-01

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

  4. Measurements of environmental radioactivity, Ispra 1988

    International Nuclear Information System (INIS)

    Dominici, G.

    1989-01-01

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

  5. Measurement of environmental radioactivity. Ispra 1976

    International Nuclear Information System (INIS)

    Dominici, G.

    1977-01-01

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

  6. Development of solid water-equivalent radioactive certified reference materials

    International Nuclear Information System (INIS)

    Finke, E.; Greupner, H.; Groche, K.; Rittwag, R.; Geske, G.

    1991-01-01

    This paper presents a brief description of the development of solid water-equivalent beta volume radioactive certified reference materials. These certified reference materials were prepared for the beta fission nuclides 90 Sr/ 90 Y, 137 Cs, 147 Pm and 204 Tl. Comparative measurements of liquid and solid water-equivalent beta volume radioactive certified reference materials are discussed. (author)

  7. A device for fresh water sampling before radioactive measurements

    International Nuclear Information System (INIS)

    Maubert, Henri; Picat, Philippe.

    1982-06-01

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

  8. Distribution measurement of 60Co target radioactive specific activity

    International Nuclear Information System (INIS)

    Li Xingyan; Chen Zigen; Ren Min

    1994-01-01

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

  9. Development of solid water-equivalent radioactive certified reference materials

    Energy Technology Data Exchange (ETDEWEB)

    Finke, E.; Greupner, H.; Groche, K.; Rittwag, R. (Office for Standardization, Metrology and Quality Control (ASMW), Berlin (Germany, F.R.)); Geske, G. (Jena Univ. (Germany, F.R.))

    1991-01-01

    This paper presents a brief description of the development of solid water-equivalent beta volume radioactive certified reference materials. These certified reference materials were prepared for the beta fission nuclides {sup 90}Sr/{sup 90}Y, {sup 137}Cs, {sup 147}Pm and {sup 204}Tl. Comparative measurements of liquid and solid water-equivalent beta volume radioactive certified reference materials are discussed. (author).

  10. 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.)

  11. Radioactivity in drinking water: regulations, monitoring results and radiation protection issues

    Directory of Open Access Journals (Sweden)

    Cristina Nuccetelli

    2012-12-01

    Full Text Available INTRODUCTION: Drinking waters usually contain several natural radionuclides: tritium, radon, radium, uranium isotopes, etc. Their concentrations vary widely since they depend on the nature of the aquifer, namely, the prevailing lithology and whether there is air in it or not. AIMS: In this work a broad overview of the radioactivity in drinking water is presented: national and international regulations, for limiting the presence of radioactivity in waters intended for human consumption; results of extensive campaigns for monitoring radioactivity in drinking waters, including mineral bottled waters, carried out throughout the world in recent years; a draft of guidelines for the planning of campaigns to measure radioactivity in drinking water proposed by the Environmental Protection Agency (ARPA of Lombardia.

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

    International Nuclear Information System (INIS)

    Fallot, P.; Bugnard, L.

    1957-06-01

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

  13. Results of environmental radioactivity measurements in the Member States of the European Community for air - deposition - water - milk. 1981

    International Nuclear Information System (INIS)

    1983-01-01

    This is the 21st report on ambient radioactivity published by the Health and Safety Directorate of the Commission of the European Communities. It was drawn up using the data collected by stations responsible for environmental radioactivity monitoring in Member States. The results are extracts from the data sent to the Commission under Article 36 of the Treaty of Rome establishing the European Atomic Energy Community. The results presented in this report deal with radioactivity of the air, deposition, surface water and milk during 1981 in the ten Member States of the European Community, viz. Belgium, Denmark, Federal Republic of Germany, Greece, France, Ireland, Italy, Luxembourg, the Netherlands and the United Kingdom. The results are presented under four main headings: artificial radioactivity in the air at ground level; artificial radioactivity in deposition; radioactivity of water; radioactivity of milk. The report also contains the list of sampling stations and laboratories, together with a list of publications by Member States in this field. This report places special emphasis on the measurement results for specific radionuclides, but it also contains data on total beta activity so as to ensure continuity vis-a-vis previous and provide comparative values

  14. 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.

  15. Radioactivity of tap water in the Republic of Croatia

    International Nuclear Information System (INIS)

    Cesar, D.; Maracic, M.; Franic, Z.; Kovac, J.

    1994-01-01

    The purpose of the paper was to establish the difference between radioactivity level measured in tap water in relation to maximum permissible concentrations determined by law in the Republic of Croatia. Tables 1 and 2 give percentages of total beta activity in tap water of several cities in Croatia and Table 3 of 137 Cs, 3 H and 90 Sr specific activities, in relation to permissible levels. On basis of these data it could be concluded that total beta activity has exponentially decreased over the past 30 years and radioactivity in tape water of Croatia has never exceeded permissible levels. Taking in account possible hazards to human health that might be caused by the presence of radioactivity in water, this kind of investigation should be continued also in the future

  16. The protective role of ceramic filters against natural radioactivity of water

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  17. Monitoring of radioactivity in drinking water

    International Nuclear Information System (INIS)

    Legarda, F.; Herranz, M.; Letessier, P.

    2008-01-01

    Radioactivity is a physical phenomenon whose presence in water is monitored due to its potential capability to induce deleterious effects on human health. In this article the effects that can be caused by radioactivity as well as the way in which regulations establish how to perform a monitorization of water that enables us to ascertain that the radiological quality of water is in agreement with the accepted standard of quality of life are analyzed. Finally the means available to know the content of radioactivity in water together with some clues on how to remove it from water are described. (Author) 5 refs

  18. Estimation of potassium concentration in coconut water by beta radioactivity measurement

    International Nuclear Information System (INIS)

    Reddy, P.J.; Narayani, K.; Bhade, S.P.D.; Anilkumar, S.; Kolekar, R.V.; Singh, Rajvir; Pradeepkumar, K.S.

    2014-01-01

    Potassium is widely distributed in soil, in all vegetable, fruits and animal tissues. Approximately half the radioactivity found in humans comes from 40 K. Potassium is an essential element in our diet since it is required for proper nerve and muscle function, as well as for maintaining the fluid balance of cells and heart rhythm. Potassium can enter the body mainly consuming fruits, vegetables and food. Tender coconut water is consumed widely as natural refreshing drink which is rich in potassium. The simple way to determine 40 K activity is by gamma ray spectrometry. However, the low abundance of this gamma photon makes the technique less sensitive compared to gross beta measurement. Many analytical methods are reported for potassium estimation which is time consuming and destructive in nature. A unique way to estimate 40 K by beta activity is by Cerenkov Counting technique using Liquid Scintillation Analyzer. Also much lower detection limit is achieved, allowing for greater precision. In this work, we have compared two methods to arrive at the potassium concentration in tender and matured coconut water by measuring 40 K. One is non-scintillator method based on measurement of the Cerenkov radiation generated from the high-energy β of 40 K. The second method is based on beta activity measurement using low background Gas flow counter

  19. 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

  20. Proceedings of the technical meetings 'Water, radioactivity and environment'

    International Nuclear Information System (INIS)

    Perceval, Olivier; Foulquier, Luc; Canneva, Guillem; Jedor, Beatrice; Genthon, Benedicte; Vicaud, Alain; Skrzypczak, Julien; Gibeaux, Audrey; Phrommavanh, Vannapha; Descostes, Michael; Tognelli, Antoine; Calmet, Dominique; Leprieur, Fabrice; Pignol, David; Thybaud, Eric; Feray, Christine; Leclerc, Elisabeth; Maitre, Melanie; Calmon, Philippe; Marang, Laura; Beaugelin-Seiller, Karine; Garnier-Laplace, Jacqueline; Leprieur, Fabrice; Philippot, Benoit; Hemidy, Pierre-Yves; Devin, Patrick; Perrier, Gilles; CALVEZ, Marianne; Descamps, E.; Preveral, S.; Brutesco, C.; Ginet, N.; Escofier, C.; Garcia, D.; Pignol, D.; Ansaldi, M.; Rodrigue, A.; Bazin, I.; Cholat, P.; Bailly-Du-Bois, Pascal; Fievet, Bruno; Godinot, Claire; Eyrolle-Boyer, Frederique; Antonelli, Christelle; Tournieux, Damien; Augeray, Celine; Galliez, Kevin; Baconet, I.; Cavaliere, N.; Dias Varela, D.; Foulon, L.; Laconici, C.; Lorand, H.; Mouton, M.; Siscard, N.; Tarlette, L.; Loyen, Jeanne; Gleizes, Marc; Vidal, R.; Borgia, Cecile; Hemidy, Pierre-Yves; Fouchet, Loic; Gontier, G.; Grignard, G.; Drozdzak, Jegodz; Leermakers, Martine; Brun, Frederic; Ameon, Roselyne; Gleizes, Marc; Maulard, Alain; Moine, Jerome; Tchilian, Nathalie; Paillard, Herve; Gaid, Abdelkader; Wittmann, Erich; Boucherie, Christophe; Devin, Patrick

    2014-12-01

    These technical days were organized by the 'Environment section' of the French Society of Radiation Protection (SFRP). Their aim was to review the current state of water use, management and monitoring, in particular in the nuclear industry, both on the radiological and chemical aspects. This document brings together the available presentations (slides) together with their corresponding abstracts (in French) and dealing with: 1 - Environmental issues linked to water and aquatic ecosystems contamination by micropollutants (O. Perceval); 2 - 50 years of radioecology in aquatic environments (L. Foulquier); 3 - Regulation and organisation of the French administration for water and aquatic ecosystems management (G. Canneva); 4 -European and French regulations about the radiological quality of drinking water (B. Jedor); 5 - Water samplings and liquid effluents from nuclear facilities: regulation, authorisations, prescriptions (B. Genthon); 6 - Water needs of a NPP (A. Vicaud); 7 - Water management at old uranium mining sites (A. Gibeaux); 8 - Mobile system for liquid effluents treatment (J. Skrzypczak); 9 - Water: an essential vector for the transfer of radioactive and chemical compounds in the underground (A. Tognelli); 10 - Environmental guide values for aquatic ecosystems protection (E. Thybaud); 11 - Prioritisation work for radioactive and chemical compounds to be monitored in aquatic environments in the framework of the environment perennial lab (E. Leclerc); 12 - Liquid radioactive effluents in continental aquatic environments: why and how estimating the impact? (K. Beaugelin-Seiller); 13 - Sustainable water management: standards, a compulsory tool (D. Calmet); 14 - Water sampling: from theory to practice (F. Leprieur, B. Philippot); 15 - Prototype for the detection of toxic compounds in the environment (D. Pignol); 16 - Nuclear metrology and water: new available and developing techniques (C. Augeray, K. Galliez); 17 - Measurement of the uranium and radium bio

  1. 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;

  2. Water pollution by radioactive materials

    International Nuclear Information System (INIS)

    Bovard, P.

    1976-01-01

    Within the frame of the definition of a philosophy and politics of waste disposal and site selection, an analysis is made of the main elements of radioactive pollution of waters: sources of radioactivity, radionuclides classified according to their hazard, waste processing, disposal criteria and transfer processes in the compartments: water, suspended sediments, deposited sediments, biomass [fr

  3. Evaporation equipment for the rational measurement of the radioactivity of water

    International Nuclear Information System (INIS)

    Hasenjager, H.

    1960-01-01

    An apparatus is described whereby the water can be evaporated directly in the radioactive sample holder in which the sample is counted. Rapid evaporation is obtained by the heating of the dish combined with the application of a jet of hot air. Liquid is added to the dish and the heating stopped automatically at the end of evaporation. The speed of evaporation and the Losses in activity as a function of the degree of heating were studied for various substances and different qualities of water (permuted water, tap water, rainwater). Complexones are added to avoid losses of activity. (author) [fr

  4. Radioactivity in surface waters and its effects

    International Nuclear Information System (INIS)

    Stoeber, I.

    1987-01-01

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

  5. Nondestructive measurement of environmental radioactive strontium

    Directory of Open Access Journals (Sweden)

    Saiba Shuntaro

    2014-03-01

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

  6. 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)

  7. Natural and Artificial Radioactivity in Drinking Water in Malaga, Spain

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  8. 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.

  9. Radioactivity in French bottled waters

    Energy Technology Data Exchange (ETDEWEB)

    Loyen, J.; Brassac, A.; Augeray, C.; Fayolle, C.; Gleizes, M. [Institut de Radioprotection et de Surete Nucleaire - IRSN (France)

    2014-07-01

    As IRSN is considered as a reference laboratory for radioactivity measurements, French health ministry and French nuclear safety authority asked IRSN to carry out a study in order to get a fresh and complete status of radiological water quality of French bottled waters. The study was carried out during 12 months in 2012. A total of 142 bottled waters samples were analyzed (75 spring waters and 67 natural mineral waters). The laboratories of IRSN were in charge of: - systematic measurement of radioactivity following requirements of the French health ministry (Circulaire du 13/06/2007) regarding the monitoring and management of sanitary risk linked to the presence of radionuclides in drinking waters (natural mineral waters excepted). - systematic uranium mass concentration determination; - a few radon-222 gas measurements for waters in glass bottles. This study is a flash assessment of radiological characteristics of French bottled waters, at the analysis date for the sample received. It was done in informative way and was not done for regulatory control purposes.. This study has shown that: - all bottled waters analyzed have a tritium activity concentration lower than the quality reference value of 100 Bq/l of the French regulation; - More than 105 bottled waters analyzed (80% of the springs waters and 70% of natural mineral waters received) have a gross alpha activity concentration lower than the guideline value of 0,1 Bq/l of the French regulation; - All bottled waters analyzed have a residual gross beta activity concentration lower than the guideline value of 1 Bq/l of the French regulation; - All bottled waters analyzed have a uranium mass concentration lower than the provisory guideline value of 30 μg/l of the WHO for drinking waters; - radon-222 was only significantly measured once upon 6 glass bottled waters with a value far below the reference value of 100 Bq/l of the future European Directive on drinking waters. For 32 bottled waters with gross alpha

  10. 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

  11. 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

  12. Food and water radioactivity surveillance system in Romania

    International Nuclear Information System (INIS)

    Cucu, A.; Gheorghe, R.; May, C.; Barbu, R.

    2008-01-01

    Full text: Justification: Food and water radioactivity content are closely related both to natural radioactivity and also generated by contamination due to anthropic nuclear activities. Consequently, in accordance with the European Union acquis and World Health Organization recommendation, surveillance systems were operationalized in many European countries. According to the national Romanian derived legislation the public health authorities are responsible for organizing and coordination of the national surveillance system for water and food radioactivity and their health related effects. Objectives: Description of the levels and type of radioactivity of drinking water and main foodstuffs and their contribution to the Romanian population exposure in order to elaborate appropriate public health interventions. Method: The gross parameters, alpha and beta, have been used for screening surveillance of drinking water sources indeed for potable purposes in order to identify those that could exceed the total indicative dose of 0.1 mSv/year. The food surveillance was focused on the main foodstuffs including milk, meat, fish, eggs, bread, potatoes, root vegetables (mainly carrots), leafy vegetables (mainly cabbage), fruits, and canteen menu, controlled for presence and level of radioactivity for 137 Cs, 90 Sr, 226 Ra, 210 Po and 40 K. Nuclear facility related monitoring for areas as nuclear power plant Cernavoda (type HWR-CANDU) and for regions with activities of extraction and fabrication of uranium fuel includes monitoring of radioactivity for: environmental deposit levels, surface waters, spontaneous vegetation, drinking water and foodstuffs. Results: 1) The water radioactivity surveillance results, mapped by administrative borders of the national territory, reveal that parameters of drinking water complies both with Drinking Water Directive 98/83 EC and WHO recommandation/2004; 2) For food stuff radioactivity: a) Mean registered values fully comply with reference for

  13. Reduction of airborne radioactive dust by means of a charged water spray.

    Science.gov (United States)

    Bigu, J; Grenier, M G

    1989-07-01

    An electrostatic precipitator based on charged water spray technology has been used in an underground uranium mine to control long-lived radioactive dust and short-lived aerosol concentration in a mine gallery where dust from a rock breaking/ore transportation operation was discharged. Two main sampling stations were established: one upstream of the dust precipitator and one downstream. In addition, dust samplers were placed at different locations between the dust discharge and the end of the mine gallery. Long-lived radioactive dust was measured using cascade impactors and nylon cyclone dust samplers, and measurement of the radioactivity on the samples was carried out by conventional methods. Radon and thoron progeny were estimated using standard techniques. Experiments were conducted under a variety of airflow conditions. A maximum radioactive dust reduction of about 40% (approximately 20% caused by gravitational settling) at a ventilation rate of 0.61 m3/sec was obtained as a result of the combined action of water scrubbing and electrostatic precipitation by the charged water spray electrostatic precipitator. This represents the optimum efficiency attained within the range of ventilation rates investigated. The dust reduction efficiency of the charged water spray decreased with increasing ventilation rate, i.e., decreasing air residence time, and hence, reduced dust cloud/charged water droplets mixing time.

  14. Measurement methodology of natural radioactivity in the thermal establishments

    International Nuclear Information System (INIS)

    Ameon, R.; Robe, M.C.

    2004-11-01

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

  15. Determination of the radioactive concentration of 137Cs in water

    International Nuclear Information System (INIS)

    1986-01-01

    The recently accepted standard method to determine the radioactive concentration of 137 Cs in water is based on the selective retention of cesium ions on ammonium-phosphorous-molybdate followed by the dissolution of the sorbent and the selective precipitation of cesium-hexa-chloro-platinate. The radioactive concentration is determined by the measurement of β disintegration rate of the preparate. (V.N.)

  16. Radioactivity measurement

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  17. Heat of hydration measurements on cemented radioactive wastes. Part 1: cement-water pastes

    International Nuclear Information System (INIS)

    Lee, D.J.

    1983-12-01

    This report describes the hydration of cement pastes in terms of chemical and kinetic models. A calorimetric technique was used to measure the heat of hydration to develop these models. The effects of temperature, water/cement ratio and cement replacements, ground granulated blast furnace slag (BFS) and pulverised fuel ash (PFA) on the hydration of ordinary Portland cement (OPC) is reported. The incorporation of BFS or PFA has a marked effect on the hydration reaction. The effect of temperature is also important but changing the water/cement ratio has little effect. Results from cement pastes containing only water and cement yield total heats of reaction of 400, 200 and 100 kJ/kg for OPC, BFS and PFA respectively. Using the results from the models which have been developed, the effect of major salts present in radioactive waste streams can be assessed. Values of the total heat of reaction, the time to complete 50 percent reaction, and the energy of activation, can be compared for different waste systems. (U.K.)

  18. 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

  19. 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

  20. Water hyacinth : the suitable aquatic weed for radioactive nuclide absorption in water

    International Nuclear Information System (INIS)

    Chalermsuk, Somporn; Jungpattanawadee, Komgrid; Tongrong, Thanachai

    2003-06-01

    The experiment was set up to determine the quantities of radioactive nuclides which were absorbed by aquatic weeds in Khon Kaen Province. The best aquatic weed would be used to be sampled for study of radioactive nuclide quantities in natural water resources. Seven kinds of aquatic weeds in the same site were corrected and pretreated by ovening to be ash at 450 οC. Gamma-ray spectra of the samples were detected and analyzed for comparing the quantities of radioactive nuclides. Gamma-ray spectrometry with a HPGe detector was set up to detect radioactive nuclides and their quantities in ashes of aquatic weeds. According to this study, water hyacinth, from seven aquatic weeds, had the most quantities of radioactive nuclides. The water hyacinth with 30 cm leaves in length can absorb the most quantities of radioactive nuclides

  1. Radioactivity measurements of water, milk and dairy products, vegetables and grass from the surroundings of Cracow on the aftermath of Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Cywicka-Jakiel, T.; Grychowski, P.; Hajdas, I.; Jasinska, M.; Kolakowski, L.; Loskiewicz, L.; Mazgaj, Z.; Mikulski, J.; Ochab, E.

    2004-01-01

    The measurements of radioactive contamination of water and food products were carried out shortly after the Chernobyl nuclear reactor accident. Using the measured values, the committed effective dose equivalent for adult population of Cracow was estimated. (author)

  2. Radioactivity measurements

    International Nuclear Information System (INIS)

    Schwach, G.

    1986-01-01

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

  3. Method of treating radioactive waste waters from uranium industry

    International Nuclear Information System (INIS)

    Priban, V.; Novak, L.; Zubcek, L.; Hinterholzinger, O.

    1987-01-01

    radioactive mine waters with suspended solid particles and acid salinated solutions from the process of underground leaching of radioactive ores with sulfuric acid, are discharged in a specified ratio to a common sump. The acid salinated solutions are used as a coagulation agent for the treatment of radioactive mine waters. Both solutions are mixed at simultaneous addition of lime milk suspension. In a sedimentation tank, the precipitate thus produced is sedimented and the clarified water is carried from the tank to a public water flow. The advantages of the method include the treatment of an over-balance 3 m 3 /min of acid salinated solutions from the process of underground leaching of radioactive ores with sulfuric acid, and reduction in the cost of radioactive mine water treatment. (E.S.)

  4. Phytoremediation of water bodies contaminated with radioactive heavy metal

    International Nuclear Information System (INIS)

    Yan Zhen; Yuan Shichao; Ling Hui; Xie Shuibo

    2012-01-01

    The sources of the radioactive heavy metal in the water bodies were analyzed. The factors that affect phyto remediation of water contaminated with radioactive heavy metal were discussed. The plant species, mechanism and major technology of phyto remediation of water contaminated with radioactive heavy metal were particularly introduced. The prospective study was remarked. (authors)

  5. Radioactivity Monitoring System for TRIGA 2000 Reactor Water Tank with On-Line Gamma Spectrometer

    International Nuclear Information System (INIS)

    Prasetyo Basuki; Sudjatmi KA

    2009-01-01

    One of the requirements in radiological safety in the operating condition of research reactor are the absence of radionuclide from fission product released to reactor cooling water and environment. Early detection of fission product that released from fuel element can be done by monitoring radioactivity level on primary cooling water.Reactor cooling water can be used as an important indicator in detecting radioactivity level of material fission product, when the leakage occurs. Therefore, it needs to build a monitoring system for measuring radioactivity level of cooling water directly and simple. The idea of this system is counting radioactivity water flow from reactor tank to the marinelli cube that attached to the HPGe detector on gamma spectrometer. Cooling water from tank aimed on plastic pipe to the marinelli cube. Water flows in gravitational driven to the marinelli cube, with volume flow rate 5.1 liters/minute in the inlet and 2.2 liters/minute in output. (author)

  6. 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

  7. Distribution of radioactive constituents in river waters

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  8. Monitoring water for radioactive releases in the United States

    International Nuclear Information System (INIS)

    Porter, C.R.; Broadway, J.A.; Kahn, B.

    1990-01-01

    The major radiological environmental monitoring programs for water in the United States are described. The applications of these programs for monitoring radioactive fallout, routine discharges from nuclear facilities, and releases due to accidents at such facilities are discussed, and some examples of measurements are presented. The programs monitor rainfall, surface water, and water supplies. Samples are usually collected and analyzed on a monthly or quarterly schedule, but the frequency is increased in response to emergencies. (author)

  9. Radioactivity, radiation protection and monitoring during dismantling of light-water reactors

    International Nuclear Information System (INIS)

    Hummel, L.; Zech, J.B.

    2005-01-01

    Based on the radioactivity inventory in the systems and components of light-water reactors observed during operation, the impact of actions during plant emptying after the conclusion of power operation and possible subsequent long-term safe enclosure concerning the composition of the nuclide inventory of the plant to be dismantled will be described. Derived from this will be the effects on radioactivity monitoring in the plant, physical radiation protection monitoring, and the measured characterization of the residual materials resulting from the dismantling. The impact of long-term interim storage will also be addressed in the discussion. The talk should provide an overview of the interrelationships between source terms, decay times and the radioactivity monitoring requirements of the various dismantling concepts for commercial light-water reactors. (orig.)

  10. Radioactivity of household water in Finland

    International Nuclear Information System (INIS)

    Salonen, L.; Saxen, R.

    1991-01-01

    A nationwide study on artificial and natural radioactivity in household water has been under way in Finland since the 1960s. The occurrence of artificial radionuclides in the surface water of drainage basins has been monitored extensively. The proportion of household water derived from surface waters in Finland is currently 48 %, but its usage is decreasing whereas that of groundwater is increasing at an annual rate of 1 - 2 %. The natural radioactivity of household water has been studied in almost all of the waters distributed by public waterworks and in 5400 private ground water wells. The downward trend in 90 Sr, 137 Cs and 3 H concentrations in surface water continued from the middle 1960s until the Chernobyl accident. After the accident ten different radionuclides were detected in surface waters, but only 137 Cs made a minor contribution the radiation dose. The maximum effective dose via ingestion of water was about 0.001 mSv in 1986, and considerably lower in the following years

  11. Radioactivity and its measurement

    CERN Document Server

    Mann, W B; Garfinkel, S B

    1980-01-01

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

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

    International Nuclear Information System (INIS)

    Kobayashi, Yoshii

    1994-01-01

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

  13. The Quality Testing of Water from Microbiology and Radioactivity

    International Nuclear Information System (INIS)

    Zainul Kamal; Yazid, M.; Mulyaningsih; Iim lmroatin

    2002-01-01

    The quality testing of well water from microbiologic and radioactivity has been done. The samples were taken from Degolan and Lodadi village, Ngemplak, Sleman. The quality testing based from standard procedure of microbiologic and environmental radioactivity. From the experimentally results showed that E. Coli in well water = 5 - 920 JPT / 100 ml, Streptococcus in well water 0 - 4 JPT /100 ml, E. Coli and Streptococcus in PAM water 0 JPT / 100 ml, radioactivity β totally in well water 0.08-0.34 Bq/l and in PAM water 0.08 - 0.31 Bq/l. From the dates required could be concluded that in microbiologically aspects the value of E. Coli and Streptococcus in well water higher than the threshold value from Health Department Rl 416/Menkes/PER/IX/1990, in radioactivity aspect lower than the threshold value from Health Department RI 416/Menkes/PER/IX/1990. (author)

  14. Geomembranes as an interim measure to control water infiltration at a low-level radioactive waste disposal area

    International Nuclear Information System (INIS)

    Weishan, M.R.; Sonntag, T.L.; Shehane, W.D.

    1997-01-01

    Using an exposed geomembrane an interim measure to cover a closed, Low-Level Radioactive Waste Disposal Area requires unique design and construction considerations. In response to a Resource Conservation and Recovery Act Administrative Consent Order, the New York State Energy Research and Development Authority (NYSERDA) used very low-density polyethylene (VLDPE) geomembrane as an interim measure to cover two soil-capped, grass-covered waste trenches to address a rapid increase in water accumulation in the trenches. Two years later, NYSERDA covered the remaining grass-covered trench caps with a reinforced ethylene interpolymer alloy (EIA-R) geomembrane to reduce water accumulation in these trenches. This paper addresses the differences in geomembrane materials and discusses the lessons learned during design, construction, and operation since installation of the covers. Discussed are the successes and obstacles regarding the use of both geomembrane materials as an exposed cover, selecting the geomembrane materials, anchoring the geomembrane from wind uplift, and mitigating the increased surface water runoff from the geomembrane covered area

  15. Measurement of activity of radioactive gas

    International Nuclear Information System (INIS)

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

    2005-10-01

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

  16. Use of radioactive sources in measuring characteristics of snowpacks

    Science.gov (United States)

    Henry W. Anderson; Philip M. McDonald; Lloyd W. Gay

    1963-01-01

    Use of radioactive probes inserted in mountain snowpacks may make possible more accurate appraisal and prediction of snowmelt water. Commercially available gamma and neutron probes were tested for their ability to measure snow density, ice lenses, and the thermal quality of individual layers in the snowpack.

  17. Natural radioactivity measurements at the proposed nuclear power plant site

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  18. Influence of radioactive fallout on water supply and sewerage in Finland; Radioaktiivisen laskeuman vaikutukset vesihuoltoon

    Energy Technology Data Exchange (ETDEWEB)

    Rantavaara, A; Saxen, R; Puhakainen, M [Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland); Hatva, T; Ahosilta, P; Tenhunen, J [National Board of Waters and the Environment, Helsinki (Finland)

    1995-09-01

    The report reviews the practices and organization of water supply and sewerage in Finland and is related to their response to radioactive fallout situations. The contribution of drinking water to the internal radiation dose caused by radioactive fallout has earlier been small in Finland. However, in a wide-scale fallout situation, the decreasing of collective dose received from water may be justified, if the dose can be reduced at a reasonable cost, for instance by a temporary change of the raw water source. Efficient exchange of information between radiation protection and water supply experts is important for successful dose reduction measures. In Finland waterworks deliver tap water to 4.2 million people. Half of the water is ground water, and generally very well protected against fallout radioactivity. The other half is treated surface water. (6 figs., 5 tabs.).

  19. Preliminary study of radioactive concentration in treated sewage water

    Energy Technology Data Exchange (ETDEWEB)

    Elassaly, F M; Beal, A D.R. [Ministry of Health P.O. Box 1853 Dubai, (United Arab Emirates)

    1995-10-01

    Water from sewage treatment plant is used after processing for irrigation. Two water samples and one consolidated sludge (waste treatment products) were taken each day for period of months. Medical applications and research are the main sources of radioactivity such as Cr-51, Co-57, Ga-67, Se-75, Tc-99 m, In-111, Au-198 and Tl-201. Measurements were carried out using Hp Ge spectrometer with one liter Marinelli breaker. The maximum detected activity was 5.7 Bq.liter with a daily average of 2.4 Bq/liter for water. In the second period maximum activity was found to be 5 Bq/liter with an average daily activity 1.8 Bq/liter. The maximum activity recorded in the sludge during this period was 352 Bq/liter of which 343 Bq/liter was from I-131. The average daily activity was 162 Bq/liter. From these studies the levels of radioactivity concentration were 5 Bq/liter with an average 2 Bq/1 compared level 10 Bq/1 set for drinking water for Gcc countries. Although the sludge show higher activity of 353 Bq/liter it is kept for about year before being disposed. The maximum level for animal fodder is 300 Bq/kg for Gcc countries. These results indicate that radioactive concentration (2 Bq/liter) in the treated waste water present hazard to the public and environment. 6 figs., 4 tabs.

  20. Radioactivity monitoring in drinking water of Zahedan, Iran

    International Nuclear Information System (INIS)

    Hosseini, S. A.

    2007-01-01

    The present research has focused on the effect of radioactivity on drinking water from five sites in the region of Zahedan city. Materials and Methods: The measurement of water activity in wells, river and spring has been used as a screening method. The determination of gamma emitters was performed by use the application of gamma spectrometry. Results: The values of Radium concentration was between less than 2 mBq/l to 3±0.4 for water wells, 5±0.4 mBq/L for river, and less than 2 mBq/L for spring. Conclusion: All values of activity in the selected water samples were lower than the permissible limit for drinking water consumption. The water was safe for drinking, washing and agricultural use

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  3. Radioactivity measurement in soils, sediments and water from Salihli Basin, western Turkey

    International Nuclear Information System (INIS)

    Bakac, M.; Kumru, M.N.

    2001-01-01

    Full text: Salihli Basin (about 3500 km 2 ), which is located latitude 38 deg 25' - 38 deg 35' North and longitude 27 deg 58' - 28 deg 25' East, is found on the river of Gediz the second longest river in Aegean Sea. The Gediz river originates in the vicinity of Murat Mountain and flows into the Aegean Sea in western Turkey. Gediz river carries industry effluents and mine discharges frequently inundates its flood plains. Salihli Basin is also one of the flood plain basins which has these properties The bedrock structure of the basin is composed mainly of metamorphic and volcanic rocks of the Palaeozoic, Mesozoic and Neogene ages. Uranium deposits in the Koprubasi area (Salihli Basin) of western Turkey occur in fluvial sedimentary rocks, which Lire underlaid by high-grade metamorphic rocks of the Menderes Massif. In the present study, soil, sediment and water samples were collected from the basin, its environment and riverbank. Sediment and soil samples were analysed for uranium, thorium and potassium by gamma-spectroscopy method; for radium by collector chamber method. Water samples were analysed for radium by collector chamber method. Moreover, groundwaters and streams' soils, sediments and waters within the basin were analysed for above natural radioactive elements. The objective of this, study is to determine the level of natural radioactivity in Salihli Basin. Uranium, thorium, potassium und radium concentrations and their frequency distributions were plotted graphically

  4. Radioactivity measurements of the Danube area taken by the Federal Institute of Water Quality during 1975-1978

    International Nuclear Information System (INIS)

    Frantz, A.

    1980-01-01

    A review is given of the gross-β-, K- and gross-α-activity of the Austrian section of the river Danube, measured by the Federal Institute of Water Quality in Vienna during 1975 - 1978. The results of the tributaries to the Danube: Inn, March and Leitha are even discussed. Beside water samples the activity level in acquatic biota such as plankton, resp. seston, algae, fontinalis and fish as well as in grass and soil was studied. The investigations showed, that the radioactive burden of the Danube and her tributaries and especially the maxima of activity have slightly decreased from 1975 to 1978 corresponding to the decrease in number and force of the Chinese nuclear weapon tests. (author)

  5. The water role in a nuclear accident - Measures to be taken

    International Nuclear Information System (INIS)

    Ambroggi, R.

    1988-01-01

    In case of nuclear accidents or natural disasters, the contaminated water plays a large part in the environment contamination. This is illustrated by two examples: Agadir earthquake and Chernobyl accident. In Agadir earthquake, the contamination of the water was caused by the mutiple breaking down of the water pipes, and in Chernobyl accident it was derived from: -The reactor cooling water; -The radioactive fallout; -The radioactive clouds. The water concentrates incessantly the radioactivity proceeding by the hydrological cycle: Evaporation, precipitation, flowing. The radio-activity concentration by the water and the atmosphere contamination are explained in this paper. In USSR, the radioactive contamination has affected several Ukranian rivers and the artificial lake of Kiev. The measures that have been taken in USSR and in the next countries to prevent the radioactive contamination propagation by water have been discussed. The reparation of chernobyl accident damages is estimated to three milliard $. Theoretically, every nation, using nuclear energy, has a protection system for the accidental situations but none of them has a second protection system for the accidental situations occuring in the distance. The measures to be taken for the latter situations, particularly in Morocco, have been cited. The lessons learnt from the chernobyl accident have served to broaden the inter-national cooperation fields. 15 figs., 1 tab. (author)

  6. Measurement of gamma radioactivity in steel

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  7. Bioremediation system on-line for removal radionuclides in radioactive waters

    International Nuclear Information System (INIS)

    Belinchon, J. A.; Garcia, A. M.; Ruibal, C.; Moreno, D. A.

    2010-01-01

    In previous studies developed in Cofrentes Nuclear Power Plant (Valencia, Spain), has been observed that the microorganisms in the radioactive waters of the spent nuclear fuel pool are capable of colonizing the metallic surfaces of the walls and pipes and perform biofilm. These biofilm retain the nuclides contributing to decontaminate the water. In this project, carried out in Cofrentes Nuclear Power Plant, a pilot plant has been designed for the bio decontamination of the radioactive water. At present, the radioactive water coming from the spent nuclear fuel pools, pass through ionic exchange resins. After, these resins are managed as radioactive waste. In this project, the water passes through a bioreactor with stainless steel balls capable of being colonized by the microorganisms in the water. Inside the bioreactor the water gets in contact with the material of the balls, and a biofilm, which retains the nuclides in the water, is developed. The biofilm is easily removed by any conventional procedure of radiochemical decontamination of materials and the nuclides can be collected in a small volume for recovery final disposition or containment. Later, the material of the bioreactor could be managed as not radioactive material. (Author) 9 refs.

  8. Counting statistics in radioactivity measurements

    International Nuclear Information System (INIS)

    Martin, J.

    1975-01-01

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

  9. 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)

  10. Preparation of water-equivalent radioactive solid sources

    International Nuclear Information System (INIS)

    Yamazaki, Ione M.; Koskinas, Marina F.; Dias, Mauro S.

    2011-01-01

    The development of water-equivalent solid sources in two geometries, cylindrical and flat without the need of irradiation in a strong gamma radiation source to obtain polymerization is described. These sources should have density similar to water and good uniformity. Therefore, the density and uniformity of the distribution of radioactive material in the resins were measured. The variation of these parameters in the cylindrical geometry was better than 2.0% for the density and 2.3% for the uniformity and for the flat geometry the values obtained were better than 2.0 % and better than 1.3%, respectively. These values are in good agreement with the literature. (author)

  11. Pump station for radioactive waste water

    Science.gov (United States)

    Whitton, John P.; Klos, Dean M.; Carrara, Danny T.; Minno, John J.

    2003-11-18

    A pump station for transferring radioactive particle containing waste water, includes: (a.) an enclosed sump having a vertically elongated right frusto conical wall surface and a bottom surface and (b.) a submersible volute centrifugal pump having a horizontally rotating impeller and a volute exterior surface. The sump interior surface, the bottom surface and the volute exterior surface are made of stainless steel having a 30 Ra or finer surface finish. A 15 Ra finish has been found to be most cost effective. The pump station is used for transferring waste water, without accumulation of radioactive fines.

  12. The accumulation of radioactive contaminants in drinking water distribution systems.

    Science.gov (United States)

    Lytle, Darren A; Sorg, Thomas; Wang, Lili; Chen, Abe

    2014-03-01

    The accumulation of trace contaminants in drinking water distribution system sediment and scales has been documented, raising concerns that the subsequent release of the contaminants back to the water is a potential human exposure pathway. Radioactive contaminants are of concern because of their known health effects and because of their persistence within associated distribution system materials. The objective of this work was to measure the amount of a number of radioactive contaminants (radium, thorium, and uranium isotopes, and gross alpha and beta activity) in distribution solids collected from water systems in four states (Wisconsin, Illinois, Minnesota, and Texas). The water utilities chosen had measurable levels of radium in their source waters. In addition, 19 other elements in the solids were quantified. Water systems provided solids primarily collected during routine fire hydrant flushing. Iron was the dominant element in nearly all of the solids and was followed by calcium, phosphorus, magnesium, manganese, silicon, aluminum and barium in descending order. Gross alpha and beta radiation averaged 255 and 181 pCi/g, and were as high as 1602 and 1169 pCi/g, respectively. Total radium, thorium and uranium averaged 143, 40 and 6.4 pCi/g, respectively. Radium-226 and -228 averaged 74 and 69 pCi/g, and were as high as 250 and 351 pCi/g, respectively. Published by Elsevier Ltd.

  13. Natural radioactivity in bottled mineral water available in Australia

    International Nuclear Information System (INIS)

    Cooper, M.B.; Ralph, B.J.; Wilks, M.J.

    1981-08-01

    The levels of naturally-occurring radioactive elements in bottled mineral water, commercially available in Australia, have been assessed. The survey concentrated upon 226 Ra, 228 Ra and 210 Pb, radionuclides which have a high toxicity in drinking water. Detectable levels of 226 Ra were found to range from 0.02Bq/1 to 0.32Bq/1 in locally-bottled water and from 0.02Bq/1 to 0.44Bq/1 in imported brands. 210 Pb levels were found to be generally very low ( 228 Ra content of bottled water will have a similar distribution to that of 226 Ra. Concentrations of 228 Ra in excess of 0.7Bq/1 were measured in a number of samples. The radiological health implications of the consumption of bottled mineral water are discussed with reference to existing drinking water standards and also in terms of radiation exposure and the increased risk to health. It was concluded that, although some brands of water contain radioactivity in excess of the drinking-water limits recommended by Australian and overseas authorities, the annual radiation dose to an individual will be below the dose-equivalent limits recommended by the International Commission on Radiological Protection for life-long exposure. The increased risk of radiation-induced fatal disease due to the consumption of bottled mineral water is estimated to be less than 10 -5 and is therefore negligible

  14. Radiotoxic hazard measure for buried solid radioactive waste

    International Nuclear Information System (INIS)

    Hamstra, J.

    1975-01-01

    The radiotoxic hazards resulting from the disposal of highlevel reprocessing wastes into a deep geological formation are reviewed. The term radiotoxic hazard measure (RHM), used to measure the hazard from buried radioactive wastes, is based on the maximum radionuclide concentration permissible in water. Calculations are made of the RHM levels for the high-level reprocessing wastes of both light-water-reactor and fast breeder reactor fuels. In comparing these RHM levels with that for the natural activity of an equivalent amount of uranium ore and its mill tailings, it is concluded that an actual additional radiotoxic hazard for buried high-level reprocessing waste only exists for the first 300 to 500 years after burial. (U.S.)

  15. Dispersion of radioactive materials in air and water

    International Nuclear Information System (INIS)

    Tolksdorf, P.; Meurin, G.

    1976-01-01

    A review of current analytical methods for treating the dispersion of radioactive material in air and water is given. It is shown that suitable calculational models, based on experiments, exist for the dispersion in air. By contrast, the analysis of the dispersion of radioactive material in water still depends on the evaluation of experiments with site-specific models. (orig.) [de

  16. Natural radioactivity levels in different mineral waters from Bulgaria

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  17. Study of the radioactive contents in Barcelona's water supply during 1986

    International Nuclear Information System (INIS)

    Ortega, X.; Valles, I.

    1988-01-01

    Throughout 1986 several determinations were carried out of the contents in α and β radioactivity transmitters of different samples of the Barcelona water supply. It could be verified that beta radioactivity was ten times higher in the waters collected in the basin of Llobregat river than water from Ter river. Both rivers are the main sources of Barcelona supply. The reason for this unbalanced result is the high potassic content of the first river, coming from the mining exploitation of the basin. On the other hand, the contamination that could be measured in May, due to the Chernobyl nuclear accident, showed that the supply system from Llobregat river was more sensitive to the incorporation of contaminants carried down by the rain, whereas in the case of Ter river, owing to the presence of impounding regulation, a higher retention time of these waters was obtained. (author)

  18. 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.)

  19. Natural Radioactivity Pattern of Surabaya Water Environmental Samples

    International Nuclear Information System (INIS)

    Rosidi; Agus Taftazani

    2007-01-01

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

  20. Natural radioactivity of geothermal water in Beijing, China

    International Nuclear Information System (INIS)

    Shufang Wang; Chao Ye; Jiurong Liu; Pei Lin; Kai Liu; Pei Dong; Ying Sun; Yuanzhang Liu; Liya Wang; Guifang Wang

    2017-01-01

    In this work, we collected 101 geothermal water samples to investigate comprehensively the radioactivity of geothermal water in Beijing. The concentrations of gross beta, 226 Ra and 222 Rn were measured and the obtained values were in the range of 0.032-7.060, 0.023-0.363 and 0.470-29.700 Bq/L, respectively. The samples with higher concentration of 222 Rn were found to be located near large faults. The effective dose of 222 Rn in the air for three cases were calculated to be greater than radiation dose limit of 1 mSv/a. (author)

  1. Measurement of radioactivity in rain

    International Nuclear Information System (INIS)

    Eivindson, T.

    1985-01-01

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

  2. The Citizen Observatory of Radioactivity - Assessment of results for the second half-year 2008 - Measurement of gamma emitters and tritium in water

    International Nuclear Information System (INIS)

    2010-01-01

    This document proposes a set of tables containing different information and data regarding measurements of gamma radioactivity, of tritium level in different marine and water environments (algae, sands, sea water, molluscs, sediments, water mosses, vegetal) in different locations for the second half-year 2008: a bay close to the AREVA plant in La Hague, different locations on the Normandy coast, around the AREVA plant in La Hague, waterways in Normandy and near the Brennilis nuclear power station in Brittany. These tables contain information about the sampling (date, location, quantity, analysed fraction, and so on) and results of measurements of artificial (isotopes of cobalt, ruthenium-rhodium, silver, iodine, caesium, americium, europium) and natural (potassium, beryllium, lead, bismuth, etc.) radionuclides

  3. Radioactivity measurements of the HMI after the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Behrend, U.; Dulski, P.; Friedland, E.M.; Gawlik, D.; Kirschfeld, K.E.; Schubert, P.; Steinmetz, K.H.

    1987-01-01

    The report explains the methods applied and the data measured by the HMI campaign. The material is presented so as to be of interest also to readers who in general are not concerned with aspects of radiation protection. The data measured refer to the local dose rate and to radioactivity in the environment (air, rain, surface waters, soil, food, mother's milk. Also, results of measurements of samples from Eastern Europe are given. (orig./HP) [de

  4. Measurement of natural and anthropogenic radiation in surface waters

    International Nuclear Information System (INIS)

    Turcotte, Jacques

    1981-01-01

    The use of alumina gel in municipal water treatment plants is proving very promising for the measurement of radioactivity in watercourses. The amazing fixation power of aluminum hydroxide and the large volume of water treated daily in one plant permits alumina gel to concentrate traces of natural and artificial radioisotopes to a level at which it becomes possible to observe very small amounts of radioactive fallout from nuclear tests, or even to follow over hundreds of kilometers the wastes of nuclear stations, no matter how weak the radioactivity may be [fr

  5. The Citizen Observatory of Radioactivity - Assessment for 2010 of radioactivity survey in the environment at the scale of Normandy (coast and waterways) - Results of measurement of gamma emitters and of Tritium in water

    International Nuclear Information System (INIS)

    2012-01-01

    This document proposes a set of tables containing different information and data regarding measurements of gamma radioactivity and of the presence of tritium made during 2010 in different marine and water environments (algae, sands, sea water, molluscs, sediments, water mosses, vegetal) in different locations: a bay close to the AREVA plant in La Hague, different locations on the Normandy coast, around the AREVA plant in La Hague, and in waterways in Normandy. These tables contain information about the sampling (date, location, quantity, analysed fraction, and so on) and results of measurements of artificial (isotopes of cobalt, ruthenium-rhodium, silver, iodine, caesium, americium, europium) and natural (potassium, beryllium, lead, bismuth, etc.) radionuclides

  6. Measurement of Radioactivity in Some Croatian Regions

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  7. Measuring radioactivity in the body

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1961-09-15

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

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  9. Investigation to radioactive contamination of pool water in IMEF

    International Nuclear Information System (INIS)

    Song, Ung Sup; Jung, Yang Hong; Lee, J. H.; Lee, H. K.

    2003-06-01

    The pool (3x6x10) in irradiated materials examination facility is usually used for the purpose of taking the specimen out of cask loaded into the pool, and carrying in/out the specimen to/ from the hot cell. Always, it must be cared for the water into the pool to be fine condition because all operation are worked with the naked eye during taking an irradiated materials out of the cask and plunging them in the bucket-elevator. In the aspects of the radioactive remained substances in the water must be controlled so that the amount of substances to be lower than the standard amount prescribed by RCA Korea Activity in a part of radioactive contamination control. In consequence, an expertness of status and a practical use of skill make possible the prevention of radioactive material's diffusion or the radioactive contamination of pool water and safety work

  10. Thermoexoemission detectors for monitoring radioactive contamination of industrial waste waters

    International Nuclear Information System (INIS)

    Obukhov, V.T.; Sobolev, I.A.; Khomchik, L.M.

    1987-01-01

    Detectors on base of BeO(Na) monocrystals with thermoemission to be used for monitoring radioactive contamination of industrial waste waters are suggested. The detectors advantages are sensitivity to α and low-ehergy β radiations, high mechanical strength and wide range of measurements. The main disadvantage is the necessity of working in red light

  11. Natural radioactivity in ground water near the Savannah River Site

    International Nuclear Information System (INIS)

    Price, V. Jr.; Michel, J.

    1990-08-01

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

  12. Radioactivity measurements principles and practice

    CERN Document Server

    Mann, W B; Spernol, A

    2012-01-01

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

  13. Volume of baseline data on radioactivity in drinking water, ground water, waste water, sewage sludge, residues and wastes of the annual report 1988 'Environmental radioactivity and radiation exposure'

    International Nuclear Information System (INIS)

    Abelmann, S.; Buenger, T.; Fusban, H.U.; Ruehle, H.; Viertel, H.; Gans, I.

    1991-01-01

    This WaBoLu volume is a shortened version of the annual report by the Federal Ministry of the Environment, Nature Protection and Reactor Safety 'Environmental radioactivity and radiation exposure' and gives an overview of the data on radioactivity in drinking water, ground water, waste water, sewage sludge, residues and wastes, compiled for the area of the Federal Republic of Germany in 1988 by the Institute of Water, Soil and Air Hygiene (WaBoLu) of the Federal Health Office. (BBR) With 22 figs., 15 tabs [de

  14. Processing method for contaminated water containing radioactive waste

    International Nuclear Information System (INIS)

    Tahara, Toshiaki; Fukagawa, Ken-ichiro.

    1994-01-01

    For absorbing contaminated water containing radioactive substances, a sheet is prepared by covering water absorbing pulps carrying an organic water absorbent having an excellent water absorbability is semi-solidified upon absorption water with a water permeable cloth, such as a non-woven fabric having a shape stability. As the organic water absorbent, a hydrophilic polymer which retains adsorbed water as it is used. In particular, a starch-grafted copolymer having an excellent water absorbability also for reactor water containing boric acid is preferred. The organic water absorbent can be carried on the water absorbing pulps by scattering a granular organic water absorbent to the entire surface of the water absorbing cotton pulp extended thinly to carry it uniformly and putting them between thin absorbing paper sheets. If contaminated water containing radioactive materials are wiped off by using such a sheet, the entire sheet is semi-solidified along with the absorption with no leaching of the contaminated water, thereby enabling to move the wastes to a furnace for applying combustion treatment. (T.M.)

  15. Trench water chemistry at commercially operated low-level radioactive waste disposal sites

    International Nuclear Information System (INIS)

    Pietrzak, R.F.; Dayal, R.; Kinsley, M.T.; Clinton, J.; Czyscinski, K.S.; Weiss, A.J.

    1982-01-01

    Water samples from the disposal trenches of two low-level radioactive-waste-disposal sites were analyzed for their inorganic, organic, and radionuclide contents. Since oxidation of the trench waters can occur during their movement along the groundwater flow path, experiments were performed to measure the chemical and physical changes that occur in these waters upon oxidation. Low concentrations of chelating agents, shown to exist in trench waters, may be responsible for keeping radionuclides, particularly 60 Co, in solution. 4 figures, 5 tables

  16. Measurement of radioactivity in contaminated crops

    Energy Technology Data Exchange (ETDEWEB)

    Yamada, Y; Hasegawa, M; Kihara, T

    1956-01-01

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

  17. Use of microphytoalgae for purification of radioactive waste water

    International Nuclear Information System (INIS)

    Cecal, Al.; Palamaru, Ileana; Humelnicu, Doina; Popa, K.; Rudic, V.; Cepoi, Liliana; Gulea, A.

    1999-01-01

    This work deals with a study on the purification of some radioactive waters, simulating radioactive waste waters, by some microbial collectors. For a given ion the retaining degree varies as 134 Cs - > 60 Co 2- > 51 Cr 3- > 55-59 Fe 3- , but for same algae types, this parameter decreases as follows: Scenedesmus quadricauda > Cylindrospermum major > Nostoc microscopicum. Furthermore, using the radioactive 60 Co 2- ions, the biochemical mechanism of retaining for such cations by different separated components of living cells was established. More retention is observed in proteins, pigments and polysaccharides, but the glycides are not able to keep such cations. (authors)

  18. Spread of harmful radioactive materials into running water - Possible consequences on emergency protection measures: Results of the four work packages; Radiologische Schadstoffausbreitung in Fliessgewässer- Mögliche Auswirkungen auf den Notfallschutz: Ergebnisse der vier Arbeitspakete

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-07-15

    When an extreme event in a Swiss nuclear power plant occurs, the release of radioactive materials could contaminate the drinking water supply through ground water, the river Aare or the river Rhine. To avoid such an accident, protection measures have to be taken in time, in order to stop drinking water treatment facilities downstream from the source of radioactivity release. The Swiss Federal Nuclear Safety Inspectorate (ENSI) reviewed the current situation as far as their efficiency for emergency protection of drinking water supplies is concerned. Current legal requirements and measures provide protection for the population and the environment against an uncontrolled release of radioactive materials into ground water and flowing waters. However, some points have to be checked more deeply. The present report describes the results of this analysis. The release of radioactive material into ground water or flowing waters could occur as a result of earthquakes or flooding. Even for accidents exceeding design considerations with core meltdown, large contaminations of ground and flowing water are not to be expected thanks to the stability of the reactor buildings. Because of the varying ground water situations and the stability of the reactor buildings at Swiss nuclear power plants, a situation similar to the one that occurred during the Fukushima accident, where ground water continually entered into the reactor containment causing large contamination of the water, cannot take place. The examination of communication paths showed that the paths are established between the nuclear power plants, the participating federal offices and the cantons. The criteria for the setting off of alarms and immediate measures to be taken in cases where radioactive materials in the Aare or the Rhine are recorded were examined. Downstream of the nuclear power plants, five new sodium-iodide detectors were installed in order to continuously monitor the dose rate and the activity of gamma

  19. 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.

  20. Natural radioactivity levels in mineral, therapeutic and spring waters in Tunisia

    Energy Technology Data Exchange (ETDEWEB)

    Labidi, S., E-mail: labidisalam@yahoo.f [Institut Superieur des Technologies Medicales de Tunis (ISTMT), 9 Avenue du Docteur Z.Essafi, Tunis 1006 (Tunisia); Mahjoubi, H. [Institut Superieur des Technologies Medicales de Tunis (ISTMT), 9 Avenue du Docteur Z.Essafi, Tunis 1006 (Tunisia); Essafi, F. [Faculte de Medecine de Tunis. Section de Biophysique, Tunis (Tunisia); Ben Salah, R. [Faculte de Medecine de Sousse, 270, Sahloul II, 4054 Sousse (Tunisia)

    2010-12-15

    Radioactivity measurements were carried out in 26 groundwater samples from Tunisia. Activity concentrations of uranium were studied by radiochemical separation procedures followed by alpha spectrometry and that for radium isotopes by gamma-ray spectrometry. The results show that, the concentrations in water samples range from 1.2 to 69 mBq/L.1, 1.3 to 153.4 mBq/L, 2.0 to 1630.0 mBq/L and 2.0 to 1032.0 mBq/L for {sup 238}U, {sup 234}U, {sup 226}Ra and {sup 228}Ra, respectively. The U and Ra activity concentrations are low and similar to those published for other regions in the world. The natural radioactivity levels in the investigated samples are generally increased from mineral waters through therapeutic to the spring waters. The results show that a correlation between total dissolved solids (TDS) values and the {sup 226}Ra concentrations was found to be high indicating that {sup 266}Ra has a high affinity towards the majority of mineral elements dissolved in these waters. High correlation coefficients were also observed between {sup 226}Ra content and chloride ions for Cl{sup -}Na{sup +} water types. This can be explained by the fact that radium forms a complex with chloride and in this form is more soluble. The isotopic ratio of {sup 234}U/{sup 238}U and {sup 226}Ra/{sup 234}U varies in the range from 0.8 to 2.6 and 0.6 to 360.8, respectively, in all investigated waters, which means that there is no radioactive equilibrium between the two members of the {sup 238}U series. The fractionation of isotopes of a given element may occur because of preferential leaching of one, or by the direct action of recoil during radioactive decay. The annual effective doses due to ingestion of the mineral waters have been estimated to be well below the 0.1 mSv/y reference dose level.

  1. Results of environmental radioactivity measurements in the Member States of the European Community for air - deposition - water - milk - 1977

    International Nuclear Information System (INIS)

    1979-01-01

    The present document is the seventeenth report published by the Health and Safety Directorate of the Commission of the European Communities concerning ambient radioactivity. It was drawn up using the data collected by the stations responsible for environmental radioactivity monitoring in the Member States. The results are extracts from the data sent to the Commission in application of Article 36 of the Treaty of Rome establishing the European Atomic Energy Community. The results presented in this report deal with radioactive contamination of the air, precipitation and fallout, surface water and milk during 1977 in the nine Member States of the European Community, viz. Belgium, Denmark, the Federal Republic of Germany, France, Italy, Ireland, Luxembourg, the Netherlands and the United Kingdom. The report also contains supplementary data on short-lived radioelements detected during the fourth quarter of 1977, the list of sampling stations and laboratories together With a list of publications by Member States in this field. This report places special emphasis on the measurement results for specific radionuclides, but it also contains data on total beta activity so as to ensure continuity vis-a-vis previous reports and provide comparative values

  2. 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.

  3. Chapter 4. Radioactivity of waters and factors influencing its value

    International Nuclear Information System (INIS)

    Toelgyessy, J.; Harangozo, M.

    2000-01-01

    This is a chapter of textbook of radioecology for university students. In this chapter authors deal with radioactivity of waters and factors influencing its value. Chapter consists of next parts: (1) Natural radioactivity of hydrosphere; (2) Radioactive contamination of hydrosphere

  4. The measurement theory of radioactivity in building materials

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  5. Disposal of liquid radioactive waste - discharge of radioactive waste waters from hospitals

    International Nuclear Information System (INIS)

    Ludwieg, F.

    1976-01-01

    A survey is given about legal prescriptions in the FRG concerning composition and amount of the liquid waste substances and waste water disposal by emitting into the sewerage, waste water decay systems and collecting and storage of patients excretions. The radiation exposure of the population due to drainage of radioactive waste water from hospitals lower by more than two orders than the mean exposure due to nuclear-medical use. (HP) [de

  6. Treatment of radioactive contaminated water in nuclear power plants

    International Nuclear Information System (INIS)

    1978-12-01

    This rule is to be applied to the design, construction, and operation of facilities for treatment of water contaminated with radioactive material in stationary nuclear power plants with LWRs and HTRs. According to the requirements of the rule these facilities are to be designed, constructed, and operated in such a way that a) uncontrolled discharge of water contaminated with radioactive material is avoided, b) the activity discharged with water is as low as possible, c) water contaminated with radioactive material will not reach the ground, d) the radiation exposure as a consequence of direct radiation, contamination, and inhalation of the persons occupied in the facilities is as low as possible and as a maximum corresponds to the values laid down in the radiation protection regulation or to the values of the operating license. This rule is not to be applied to facilities for coolant and storage pit clean-up as well as facilities for the treatment of concentrates produced during the contamination of the water. (orig./HP) [de

  7. Environmental radioactivity measurements at BNL following the Chernobyl accident

    International Nuclear Information System (INIS)

    Hancock, R.; Woollam, P.B.

    1986-06-01

    Measurements are reported of the concentrations at Berkeley in Gloucestershire of radioactivity in the air, rainwater, tap water, soil, herbage and fresh vegetables for the period 29 April 1986 to 15 May 1986, following the Chernobyl Power Station accident. Data for up to 18 gamma emitting isotopes are reported, together with some limited actinide-in-air measurements. Deposition velocities are calculated and an assessment is presented of the sensitivity of the techniques employed. Some data are also included on the gaseous composition of the cloud and the isotope dependent dose rate from deposition. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-11-15

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

  9. Quality Assurance In Radioactivity Measurements

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  10. Radioactivity of well water around the site of Tricastin-Pierrelatte

    International Nuclear Information System (INIS)

    2008-01-01

    This study has for principal objective the measurement of radioactivity of private well waters around the site of Pierrelatte-Tricastin, because there is no data available at this day concerning the radiological situation of this source of water supply in the local population. A campaign of sampling has been made between september and october 2007 on the cities of Bollene, Lapalud and Pierrelatte. At the laboratory, I.R.S.N. analysed more particularly uranium and its daughters, as well as some artificial radioisotopes (plutonium and americium) in order to identify an eventual influence of the nuclear site of Tricastin-Pierrelatte. This report presents successively the campaign of sampling, the results of measurements and compares them with the measurements of uranium concentration made by Areva NC in the field of the regulatory surveillance of waters in the surrounding of the site of Tricastin-Pierrelatte. (N.C.)

  11. Transit time measurement of Juqueri river waters

    International Nuclear Information System (INIS)

    Plata Bedmar, E.; Garcia A, E.; Albuquerque, A.M. de; Sanchez, W.

    1975-01-01

    The time of travel of the Juqueri River water through the east branch of the Pirapora Reservoir was measured using radioactive tracers (6 Ci 131 I in Kl Solution). The changes in Juqueri River flow rate were also measured during the run. The center of mass of the radioactive cloud was used for the time of travel calculations. Six measurements of the Juqueri River flow rate were perfomed in different days, using the total count method. Fifty, millicuries of 131 I were used in each run. The results of time travel obtained under non-steady conditions, and their correction for steady state are also discussed

  12. Water, vapour and heat transport in concrete cells for storing radioactive waste

    Science.gov (United States)

    Carme Chaparro, M.; W. Saaltink, Maarten

    2016-08-01

    Water is collected from a drain situated at the centre of a concrete cell that stores radioactive waste at 'El Cabril', which is the low and intermediate level radioactive waste disposal facility of Spain. This indicates flow of water within the cell. 2D numerical models have been made in order to reproduce and understand the processes that take place inside the cell. Temperature and relative humidity measured by sensors in the cells and thermo-hydraulic parameters from laboratory test have been used. Results show that this phenomenon is caused by capillary rise from the phreatic level, evaporation and condensation within the cell produced by temperature gradients caused by seasonal temperature fluctuations outside. At the centre of the cell, flow of gas and convection also play a role. Three remedial actions have been studied that may avoid the leakage of water from the drain.

  13. innovation in radioactive waste water-stream management

    International Nuclear Information System (INIS)

    Shaaban, D.A.E.F.

    2010-01-01

    treatment of radioactive waste dtreams is receiving considereble attention in most countries. the present work is for the radioactive wastewater stream management, by volume reduction by a mutual heating and humidificaction of a compressed dry air introduced through the wastewater. in the present work, a mathematical model describing the volume reduction by at the optimum operating condition is determined. a set of coupled first order differential equations, obtained through the mass and energy conservations laws, are used to obtain the humidity ratio, water diffused to the air stream, water temperature, and humid air stream temperature distributions through the bubbling column. these coupled differential equations are simulataneously solved numerically by the developed computer program using fourth order rung-kutta method. the results obtained, according to the present mathematical model, revealed that the air bubble state variables such as mass transfer coefficient (K G ) and interfacial area (a) have a strong effect on the process. therefore, the behavior of the air bubble state variables with coulmn height can be predicted and optimized. moreover, the design curves of the volumetric reduction of the wastewater streams are obtained and assessed at the different operating conditions. an experimental setup was constructed to verify the suggested model. comperhensive comparison between suggested model results, recent experimental measurements and the results of previous work was carried out

  14. Investigation of radiation safety management at nuclear medicine facilities in Japan. Contamination of radioactivity in the draining-water system

    International Nuclear Information System (INIS)

    Endo, Keigo; Koizumi, Mitsuru; Kinoshita, Fujimi; Nakazawa, Keiji

    1999-01-01

    Radiation-safety management condition in Japanese nuclear medicine facilities were investigated by the questionnaire method. The first questionnaire was asked in all Japanese 1,401 Nuclear Medicine facilities. Answers from 624 institutes (44.5%) were received and analyzed. The radiation-safety management in nuclear medicine institutes was considered to be very well performed everyday. Opinion for the present legal control of nuclear medicine institutes was that the regulation in Japan was too strict for the clinical use of radionuclides. The current regulation is based on the assumption that 1% of all radioactivity used in nuclear medicine institutes contaminates into the draining-water system. The second questionnaire detailing the contamination of radioactivity in the draining-water system was sent to 128 institutes, and 64 answers were received. Of them, 42 institutes were considered to be enough to evaluate the contamination of radioactivity in the draining-water system. There was no difference between 624 institutes answered to the first questionnaire and 42 institutes, where the radioactivity in the draining-water system measured, in the distribution of the institute size, draining-water system equipment and the radioactivity measuring method, and these 42 institutes seemed to be representative of Japanese nuclear medicine institutes. Contamination rate of radioactivity into the draining system was calculated by the value of radioactivity in the collecting tank divided by the amount of radionuclides used daily in each institute. The institutes were divided into two categories on the basis of nuclear medicine practice pattern; type A: in-vivo use only and type B: both in-vivo and in-vitro use. The contamination rate in 27 type A institutes did not exceed 0.01%, whereas in 15 type B institutes the contamination rate distributed widely from undetectable to above 1%. These results indicated that the present regulation for the draining-water system, which assumed

  15. Measurement of lung water with SPECT

    International Nuclear Information System (INIS)

    Chu, R.Y.L.; Ficken, V.J.; Ekeh, S.U.; Ryals, C.J.; Allen, E.W.; Basmadjian, G.

    1990-01-01

    This paper investigates the use of iodoantipyrine (IAP) labeled with radioactive iodine (I-123) and single photon emission tomography (SPECT) to measure lung water. I-123 IAP was injected intravenously to six New Zealand White rabbits under anesthesia. After 1 hour, Tc-99m macroaggregates of albumin (MAA) were injected. SPECT imaging was performed in dual-energy mode. After a blood sample was drawn, the animals were sacrificed, and the lungs were removed. Blood samples were assayed for radioactivity. The lungs were weighed, dried, and weighted again to determine water content. The product of area defined by MAA in a tomogram and IAP count rate of central pixels of that region in the corresponding tomogram was taken as the relative amount of IAP in each lung

  16. Safety of drinking water supplies to suburban Paris: analysis and control of radioactivity at Choisy-le-Roi

    International Nuclear Information System (INIS)

    Rapinat, M.; Philipot, J.M.; Cadet, J.L.

    1990-01-01

    The Syndicat des Eaux d'Ile de France and the Compagnie des Eaux have undertaken several stringent actions, to analyse and control radioactivity at Cholsy-le-Roi, 150 KM downstream from Nogent/s/Seine:- founding in 1985 a new laboratory branch for radioactivity measurement. - adding new elements to the existing alarm network (automatic analysis of the raw water quality). - studies for the treatability of radioelements. - using protected resources (ground water). -set up of a second treated water feeder between the river Seine and the river Marne areas. Others projects are under study, such as the creation of a raw water reservoir and increasing the capacity of treated water stockage. (author)

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

    International Nuclear Information System (INIS)

    Kobayashi, Katsutoshi; Hoizumi, Kiyoshi

    1985-03-01

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

  18. Mineral water and radioactivity. Technical report n. 15

    International Nuclear Information System (INIS)

    2000-07-01

    This technical report aims at giving to people taking charge of mineral water analysis, information needed to the interpretation of radioactivity monitoring results. It provides bulk notions on the radioactivity (biological and environmental effects), regulations and reference texts of the WHO (World Health Organization). Examples of activities and absorbed doses calculation are also provided. (A.L.B.)

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

    International Nuclear Information System (INIS)

    1984-01-01

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

  20. Factors affecting the release of radioactivity to the biosphere during deep geologic disposal of radioactive solids through underground water

    International Nuclear Information System (INIS)

    Solomah, A.G.

    1984-01-01

    The chemical alteration formed by ground water on the solidified radioactive waste during deep geologic disposal represents the most likely mechanism by which dangerous radioactive species could be reintroduced into the biosphere. Knowing the geologic history of the repository, the chemistry of the ground water and the mechanisms involved in the corrosion of the radioactive solids can provide help to predict the long-term stability of these materials. The factors that must be considered in order to assess the safety and the risk associated with such a disposal strategy are presented. The leaching behavior of a solidified radioactive waste form called SYNROC-B (SYNthetic ROCks) is discussed. Different simulated ground water brines similar to those of the repository sites were prepared and used as the leaching media in leaching experiments

  1. Environmental radioactivity monitoring in Republic of Serbia

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  2. Estimation of annual committed effective dose due to radioactivity of curative drinking thermal spring waters in Turkey

    International Nuclear Information System (INIS)

    Dirican, A.; Shahin, M.; Serefinoglu, M.; Erden, P.E.; Shahin, N.K.

    2014-01-01

    Full text : Spa customers protection against natural radioactivity in curative drinking thermal water is not regulated in Europe and Turkey. For this reason, a technical cooperation project was conducted to provide a report containing radioactivity measurement results, dosimetric calculations and analysis of the radiation protection regulations to be applied in spas

  3. Method of detecting water leakage in radioactive waste containing vessel

    International Nuclear Information System (INIS)

    Ishioka, Hitoshi; Takao, Yoshiaki; Hayakawa, Kiyoshige.

    1989-01-01

    Lower level radioactive wastes formed upon operation of nuclear facilities are processed by underground storage. In this case, a plurality of drum cans packed with radioactive wastes are contained in a vessel and a water soluble dye material is placed at the inside of the vessel. The method of placing the water soluble dye material at the inside of the vessel includes a method of coating the material on the inner surface of the vessel and a method of mixing the material in sands to be filled between each of the drum cans. Then, leakage of water soluble dye material is detected when water intruding from the outside into the vessel is again leached out of the vessel, to detect the water leakage from the inside of the vessel. In this way, it is possible to find a water-invaded vessel before corrosion of the drum can by water intruded into the vessel and leakage of nuclides in the drum can. Accordingly, it is possible to apply treatment such as repair before occurrence of accident and can maintain the safety of radioactive water processing facilities. (I.S.)

  4. Measurements of radioactive and xenobiotic substances in the biological environment in the Netherlands 1986

    International Nuclear Information System (INIS)

    1988-01-01

    A brief survey of the results of detailed radioactivity measurements performed in the Netherlands during the period immediately after the Chernobylsk accident, and the risk analyses made on the basis of these results, are presented. The increase of the airborne radioactivity and the activity concentrations in surface water during the first week of May 1986 is demonstrated graphically. The radiation dose in 1986 due to artificial radioactivity has been calculated to be about 60 μSv for adults, 70 μSv for ten-year-old children and 110 μSv for one-year-old children. 54 figs.; 32 tabs

  5. Radioactivity of the Cooling Water

    Science.gov (United States)

    Wigner, E. P.

    1943-03-01

    The most important source of radioactivity at the exit manifold of the pile will be due to O{sup 19}, formed by neutron absorption of O{sup 18}. A recent measurement of Fermi and Weil permits to estimate that it will be safe to stay about 80 minutes daily close to the exit manifolds without any shield. Estimates are given for the radioactivities from other sources both in the neighborhood and farther away from the pile.

  6. Radioactivity of drinking water in Finland - basis for quality requirements; Talousveden radioaktiivisuus - perusteita laatuvaatimuksille

    Energy Technology Data Exchange (ETDEWEB)

    Maekelaeinen, I.; Huikuri, P.; Salonen, L.; Markkanen, M.; Arvela, H

    2001-07-01

    the radon concentration in drinking water, commonly used in Finland: liquid scintillation method and Mini-Assay measurement used by local foodstuff and environmental laboratories. The concentration of uranium and radium-226 can be assessed using alpha-activity measured by liquid scintillation method. Concentrations of all radionuclides can be accurately determined using radiochemical analysis. The guidelines proposed in this report are based on radioactivity only. In respect of chemical toxicity of uranium, lower limits than those based on radiological effects have been set. Approximately 15% of Finns use drinking water with uranium concentration exceeding the guideline value of 2 micrograms per litre recommended by WHO. (orig.)

  7. Measurement of flow and direction of ground water by radioactive tracers: hydrological evaluation of a waste disposal site at 'Instituto de Pesquisas Energeticas e Nucleares (IPEN)'

    International Nuclear Information System (INIS)

    Chandra, U.; Aoki, P.E.; Ramos e Silva, J.A.; Castagnet, A.C.G.

    1981-05-01

    The method of determining flow and drection of ground water by using radioactive tracers in ground water borings is described. Various parameters controlling the measurements are discussed in detail. Application of the method in studying a variety of geohydrological problems, in view of the hydrological evaluation of the waste disposal site at IPEN, is indicated. Comparison of the method with conventional pumping tests is made. (I.C.R.) [pt

  8. Radioactive contamination of some important fish species in fish ponds and natural waters with special attention to 90Sr radioisotope accumulation Pt. 1

    International Nuclear Information System (INIS)

    Kantor, D.; Szentjobi, O.

    1977-01-01

    The radioactive contamination accumulated in the organs and bones of fishes, a major protein source for mankind, depends on the radioactive contamination of waters and aquatic vegetation. In addition to the activity per gram of water, K, Ca, and chloride contents of waters and oxygen consumption were studied, since radioactivity and radioactive material enrichment in natural waters are the consequence of complex geological and physico-chemical processes. The origin of the differences in radioactivity of rivers, lakes and fish ponds is tentatively explained from the results of analytical and radiometric measurements of waters. Results of similar investigations on aquatic and coastal vegetation of these waters cannot be explained in a simple way because the answer is uncertain due to the compositional differences of plant specimens and the sampling in changing seasons. Therefore, additional investigations are proposed. (P.J.)

  9. Radon and radium measurement in well water at Curitiba (PR), Brazil

    International Nuclear Information System (INIS)

    Correa, Janine N.; Paschuk, Sergei A.; Perna, Allan F.N.; Kappke, Jaqueline; Claro, Flavio del; Denyak, Valeriy; Schelin, Hugo R.; Rocha, Zildete

    2011-01-01

    This study presents the results of 226 Ra and 222 Rn activity concentration measurements in well water in the city of Curitiba - Parana State of Brazil. Water samples were collected from 31 wells and submitted to the radioactivity measurements in the Laboratory of Applied Nuclear Physics of the Federal University of Technology (UTFPR) in cooperation with CDTN-CNEN. Each water sample was submitted to 4 measurements of radon concentration with interval of three days. After two months the same samples were submitted once again to 222 Rn concentration measurements with an objective to evaluate indirectly the amount of 226 Ra contained in water samples. The 222 Rn concentration measurements were performed using AlphaGUARD radon monitor (Genitron Instruments) and 226 Ra concentration was evaluated using the decay curves of 222 Rn. Within few hours after extraction about 70% of water samples from monitored wells presented 222 Rn concentration values above the limit of 11.1 Bq/L recommended by the USEPA. Obtained activity values varied between 1.57 Bq/L - 215.16 Bq/L for radon concentration, and radium concentrations deviated within an interval of 0.61 Bq/L - 6.76 Bq/L. Obtained results showed that the biggest part of 222 Rn found in water samples was not originated from the 226 Ra compounds soluble in water but from gas exhalation by the soil adjacent to the well. The results of present research show the requirement of radioactivity monitoring of water extracted from artesian wells at Curitiba region and indicate the necessity of mitigation procedure development for better control of global alpha radioactivity in drinking water. (author)

  10. Characterization of trench water at the Maxey Flats low-level radioactive waste disposal site

    International Nuclear Information System (INIS)

    Weiss, A.J.; Francis, A.J.; Colombo, P.

    1977-01-01

    Currently the United States Geological Survey is conducting a study of the hydrogeological and geochemical behavior of commercially operated low-level radioactive waste disposal sites. The data collected from this study will be used to establish criteria for selection of new sites for disposal of radioactive wastes. As part of this study, water samples from trenches at the Maxey Flats, Kentucky site were analyzed at Brookhaven National Laboratory to determine the source terms of the radionuclides and other components in solution in the trenches. Procedures for collection and filtration of the samples under anoxic conditions are described. The samples were analyzed for inorganic, radiochemical and organic constituents. The inorganic analysis includes the measurements of pH, specific conductance, alkalinity, and various cations and anions. The radionuclides were measured by the gross alpha, gross beta, tritium, and gamma activities, followed by specific measurements of strontium-90 and plutonium isotopes. The organics were extracted, concentrated, and identified by gas chromatography/mass spectrometry. Considerable quantities of organics were detected in all of the trench waters sampled. Specific organics were found in most of the trenches, however, the organic composition of the trench waters vary. The presence of a variety of organic compounds in trench waters suggest that they may play an important role in the transport of radionuclides

  11. Fukushima overflowed by radioactive waters

    International Nuclear Information System (INIS)

    Mulot, Rachel

    2013-01-01

    As Tepco admitted, after two years of denial, that it was unable to stop radioactive water leakages from the Fukushima plant towards the ocean, this article briefly describes the problems faced regarding this issue. Pumping, storage and decontamination systems are not large enough to cope with waters which are oozing from the underground. Storage means are insufficient. The article evokes the various undertaken actions and works, as well as some more or less realistic projects (a costly and not sure creation of an underground cryogenic barrier). Another worrying issue is finally outlined: the quantity of released caesium 137 has not been published

  12. The measurement of radioactivity in foodstuffs

    International Nuclear Information System (INIS)

    Maushart, R.

    1988-01-01

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

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  14. Results of radioactivity measurements on foodstuffs in Romania

    International Nuclear Information System (INIS)

    Ferdes, O.; Cojocariu, T.

    1996-01-01

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

  15. System for measuring radioactivity of labelled biopolymers

    International Nuclear Information System (INIS)

    Gross, V.

    1980-01-01

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

  16. Radioactivity concentration measuring device for radiation waste containing vessel

    International Nuclear Information System (INIS)

    Goto, Tetsuo.

    1994-01-01

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

  17. Measurement of the gross α radioactivity in a river near a sewerage of a uranium mine

    International Nuclear Information System (INIS)

    Xu Congxue; Li Tianduo; Zhou Chunlin; Han Feng; Ma Wenyan

    2003-01-01

    This paper introduced the measurement of the gross α radioactivity in a river near a sewerage of a uranium mine. By using the drip infusion set, the water was transfused into the sample trays and evaporated directly. This method makes it possible batch the water samples

  18. Measurements of natural radioactivity concentration in drinking water samples of Shiraz city and springs of the Fars province, Iran, and dose estimation

    International Nuclear Information System (INIS)

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

    2013-01-01

    The Fars province is located in the south-west region of Iran where different nuclear sites has been established, such as Bushehr Nuclear Power Plant. In this research, 92 water samples from the water supplies of Shiraz city and springs of the Fars province were investigated with regard to the concentrations of natural radioactive elements, total uranium, 226 Ra, gross alpha and gross beta. 226 Ra concentration was determined by the 222 Rn emanation method. To measure the total uranium concentration, a laser fluorimetry analyzer (UA-3) was used. The mean concentration of 226 Ra in Shiraz's water resources was 23.9 mBq l -1 , while 93% of spring waters have a concentration 2 mBq l -1 . The results of uranium concentration measurements show the mean concentrations of 7.6 and 6 mg l -1 in the water of Shiraz and springs of Fars, respectively. The gross alpha and beta concentrations measured by the evaporation method were lower than the limit of detection of the measuring instruments used in this survey. The mean annual effective doses of infants, children and adults from 238 U and 226 Ra content of Shiraz's water and spring waters were estimated. According to the results of this study, the activity concentration in water samples were below the maximum permissible concentrations determined by the World Health Organization and the US Environmental Protection Agency. Finally, the correlation between 226 Ra and total U activity concentrations and geochemical properties of water samples, i.e. pH, total dissolve solids and SO 4 2- , were estimated. (authors)

  19. Radioactivity in the Rhine - the LWA controls North-Rhine-Westphalian surface waters

    International Nuclear Information System (INIS)

    Kloes, H.

    1985-01-01

    The State Authority for Water and Waste Management has been testing the Rhine and the most important surface waters of North-Rhine Westphalia for radioactivity ever since it was founded in 1969. Radiation exposure of human beings who use Rhine water is far below the permitted maximum values of the 'radiation protection ordinance'. Pollution of the Rhine and its tributaries in North-Rhine Westphalia with artificial radioactive substances has even slightly decreased over the past ten years; pollution of the River Emscher with natural radioactive material remained high, the Lippe River now contains less radium than before. (orig./PW) [de

  20. Natural radioactivity in hot and mineral waters in Syria

    International Nuclear Information System (INIS)

    Othman, I.; Abbass, M.; Kattan, Z.

    1994-08-01

    A study of water chemistry and radioactivity of hot and mineral ground waters was conducted in Syria in order to determine the natural radioactivity levels as well as the mobility process of major radionuclides in the studied systems. The water samples were collected generally from carbonate and basaltic aquifer systems. The chemistry of groundwaters was a reflection of the rock type, while no relationship was found between the radionuclide activities and water temperatures. The increase of 222 Rn concentration in hot and mineral waters was accompanied by a similar increase of the concentration of its patent radionuclides (U t ot and 226 Ra). In parallel, the relative increase of 222 Rn concentration was correlated significantly with the presence of the large faults systems prevailing in the studied areas (Palmyrides and Great African Faults Systems). In all the cases, the radionuclide activity levels were below the maximum contaminant levels given for drinking water and health effects. (author). 11 refs., 7 figs., 8 tabs

  1. Valuating report on radioactivity concentrations in surface waters in 1988

    International Nuclear Information System (INIS)

    Henrich, E.; Weisz, J.; Zapletal, M.; Friedrich, M.; Haider, W.

    1989-02-01

    Sample preparation- and measuring methods and results on river and lake water samples for 1988 are presented. This is part of the Austrian Environment Radioactivity Monitoring Network. 22 sampling sites and 9 nuclides - natural, atomic weapons tests and Chernobyl fallout - were assessed. Emphasis was on the Chernobyl fallout; iodine 131, chromium 51 and cobalt 60. Hypotheses on the origin of the radionuclides are presented. The radiation burden to the population is marginal. 15 refs., 19 figs., 15 tabs. (qui)

  2. Results of radioactivity measurements on foodstuffs in Romania

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-12-31

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

  3. 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

  4. Characterization of radioactive contaminants and water treatment trials for the Taiwan Research Reactor's spent fuel pool

    International Nuclear Information System (INIS)

    Huang, Chun-Ping; Lin, Tzung-Yi; Chiao, Ling-Huan; Chen, Hong-Bin

    2012-01-01

    Highlights: ► Deal with a practical radioactive contamination in Taiwan Research Reactor spent fuel pool water. ► Identify the properties of radioactive contaminants and performance test for water treatment materials. ► The radioactive solids were primary attributed by ruptured spent fuels, spent resins, and metal debris. ► The radioactive ions were major composed by uranium and fission products. ► Diatomite-based ceramic depth filter can simultaneously removal radioactive solids and ions. - Abstract: There were approximately 926 m 3 of water contaminated by fission products and actinides in the Taiwan Research Reactor's spent fuel pool (TRR SFP). The solid and ionic contaminants were thoroughly characterized using radiochemical analyses, scanning electron microscopy equipped with an energy dispersive spectrometer (SEM-EDS), and inductively coupled plasma optical emission spectrometry (ICP-OES) in this study. The sludge was made up of agglomerates contaminated by spent fuel particles. Suspended solids from spent ion-exchange resins interfered with the clarity of the water. In addition, the ionic radionuclides such as 137 Cs, 90 Sr, U, and α-emitters, present in the water were measured. Various filters and cation-exchange resins were employed for water treatment trials, and the results indicated that the solid and ionic contaminants could be effectively removed through the use of <0.9 μm filters and cation exchange resins, respectively. Interestingly, the removal of U was obviously efficient by cation exchange resin, and the ceramic depth filter composed of diatomite exhibited the properties of both filtration and adsorption. It was found that the ceramic depth filter could adsorb β-emitters, α-emitters, and uranium ions. The diatomite-based ceramic depth filter was able to simultaneously eliminate particles and adsorb ionic radionuclides from water.

  5. Radioactivity monitoring in Ireland of air, deposition and water 1982-1987

    International Nuclear Information System (INIS)

    Sequeira, S.; McRandall, M.; Hayden, E.; Cunningham, J.D.

    1989-02-01

    The Nuclear Energy Board in conjunction with the Meteorological Service undertakes an environmental radioactivity monitoring programme with the objective of determining levels of artificially produced radioactivity in the Irish environment. The levels of radioactivity in airbourne dust, total fallout samples, precipitation and drinking water are presented for 1982, 1983, 1984, 1985, 1986 and 1987

  6. Treatment techniques for the removal of radioactive contaminants from drinking water

    International Nuclear Information System (INIS)

    Logsdon, Gary S.

    1978-01-01

    Maximum contaminant levels have been set for radioactive contaminants, as required by the Safe Drinking Water Act (PL 93-523). Treatment techniques are available for removing radium and beta-gamma emitters. Presently-used methods of removing radium-226 are precipitative lime softening (80-90% removal) ion exchange softening (95% removal) and reverse osmosis (95% removal). The 5 p Ci/l limit for radium can be met with conventional technology for raw waters in the 5-100 p Ci/l concentration range. Treatment for removal of beta or gamma emitters must be based upon chemical rather than radioactive characteristics of the contaminant. Reverse osmosis can remove a broad spectrum of ions and molecules from water, so it is the process most likely to be used. The maximum contaminant level for beta and gamma radioactivity is an annual dose equivalent to the total body or any organ not to exceed 4 m rem/year. The fate of radionuclides after removal from drinking water should be considered. Presently radium is disposed with other process wastes at softening plants removing radium. Confinement and disposal as a radioactive waste would be very expensive. (author)

  7. Radioactivity of water and air in Misasa Spa, Japan

    International Nuclear Information System (INIS)

    Morinaga, H.; Mifune, M.; Furuno, K.

    1984-01-01

    Misasa Spa is one of the most highly radioactive hot springs in Japan, the waters of which contain mainly 222 Rn (437 +- 132 Bq.litre -1 ). Radon contents of indoor air of private houses and health resort hotels (built of wood) at Misasa Spa range from 18.5 to 55.5 mBq.litre -1 and 22.2 to 129.5 mBq.litre -1 , respectively. Radon contents in the air of facilities using spring waters at Misasa Branch Hospital of Okayama University were measured to be: bathroom 807 +- 78 mBq.1 -1 , Hubbard-tank bathroom, 5306 +- 2568 mBq.litre -1 ; the drinking hall, 1491 +- 178 mBq.litre -1 . The environmental and dose rate inside private houses has been measured to be 14.0 +- 1.8 μR.h -1 . Chromosome abberations (dicentrics) in the peripheral blood lymphocytes of residents of Misasa Spa were investigated in 14 persons; the mean value of aberration frequencies were 0.21%. (author)

  8. Radium and uranium in phosphate fertilizers and their impact on the radioactivity of waters

    International Nuclear Information System (INIS)

    Barisic, D.; Lulic, S.; Miletic, P.

    1992-01-01

    The study of radioactivity in the phosphate fertilizers and water ways of the Kanovci area was performed in order to determine the influence of the application of phosphate fertilizers on the radioactive pollution of these waters. The activity of 226 Ra, 228 Ra, 235 U and 238 U was measured in different types of phosphate fertilizers and waters by means of γ-ray spectrometry. Surface water, water from drainage channels, shallow groundwater and deep groundwater samples were collected from the Kanovci agricultural and well field area in Eastern Slavonia, where phosphate fertilizers have been used for the past 15 years. 137 Cs was also measured in water samples. The typical phosphate fertilizer used in the Kanovci area contains 75 Bq kg -1 of 226 Ra, 9 Bq kg -1 of 228 Ra, 52 Bq kg -1 of 235 U and 1120 Bq kg -1 of 238 U. The estimated annual deposition of uranium and radium in soils of the agricultural and well field area in Kanovci is: 4.5 Bq m -2 for 226 Ra, 0.5 Bq m -2 for 228 Ra, 3.1 Bq m -2 for 235 U and 67 Bq m -2 for 238 U. The greatest concentrations of both uranium isotopes are measured in water from drainage channels with a mean value of 120 Bq m -3 for 238 U and 5.5 Bq m -3 for 235 U. The concentrations of both radium isotopes generally increase with depth of water as distinct from uranium, whose concentrations in deep groundwater are much lower. The highest concentrations of 137 Cs were measured in water from drainage channels; it was not detected in deep groundwater. The 238 U/ 226 Ra activity ratio (AR) is the highest in water from drainage channels and the Bosut River, while in deep groundwater the ratio is only 1.6. Results indicate that high uranium concentrations in surface water, shallow groundwater and water from drainage channels are caused by phosphate fertilizer application in agriculture on the Kanovci area. (author)

  9. Radioactive contents in water Galleries Tenerife, Canary Islands

    International Nuclear Information System (INIS)

    Lopez Perez, M.; Duarte Rodriguez, X.; Triguero Perez, M.; Hernandez Armas, J.; Catalan Acosta, A.

    2011-01-01

    Water consumption by humans leads to the possible incorporation into the body of existing radionuclides in it and can cause undesirable effects on human health. To avoid or reduce them, various agencies have established limits for the concentration of radioactive substances in the water so that it can be used for human consumption. (Author)

  10. 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...

  11. Elevated levels of radioactivity in water wells in Los Angeles and Orange Counties, California

    International Nuclear Information System (INIS)

    Weigand, J.; Yamamoto, G.; Gaston, W.

    1987-01-01

    Levels of gross alpha particle radioactivity nearly three times the maximum contamination levels (MCL) have been detected for several years in well waters and related surface waters in Los Angeles and Orange Counties, California. A few elevated levels of uranium have also been recorded. The affected wells and related surface waters represent only a minor fraction of the water sampled and tested in this area. None of the excessive radioactivity is believed to persist in the municipal waters sold to the public, due to the customary blending of waters from several wells or sources which water purveyors practice. This papers is a preliminary survey of the occurrence, possible sources, fate, and implications of these elevated radioactivity levels

  12. 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

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

    International Nuclear Information System (INIS)

    Mao Yong; Li Aiwu

    1997-01-01

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

  14. Set up and application of an underwater Α-ray spectrometer for radioactivity measurements

    Directory of Open Access Journals (Sweden)

    C. TSABARIS

    2005-06-01

    Full Text Available The set up and control of an underwater measuring instrument for radioactivity pollution in the marine environment is described. The detection system is based on a NaI scintillator (RADAM III with modifications for use in the marine environment with on-line measurements. The system is simple, has low power consumption and is stable for long-term monitoring (10 months. Before its deployment, the sensor was calibrated in the laboratory in a tank full of water to reproduce the marine environment. The calibrations were performed, by detecting the 661keV and 1461 keV gamma rays of known activity liquid sources 137 Cs and 40 K, respectively. The measured spectra in the laboratory were compared with spectra from a similar detector as acquired in the field. The analysis of the parallel measurement gave satisfactory agreement for the concentration of the potassium (40 K, as calculated from the salinity in the seawater, thus enabling the system for quantitative measurement of the seawater radioactivity.

  15. An overview on measurements of natural radioactivity in Malaysia

    Directory of Open Access Journals (Sweden)

    Nisar Ahmad

    2015-01-01

    Full Text Available Humans are always exposed during their lives to ionizing radiation arising outside and within the earth. The exposure to these radiation occurs from natural sources such as radioactive elements in rocks and soil, internal exposure form radioactive elements through water, food and air and cosmic rays entering from outer space to earth's atmosphere. About 87% of the radiation dose received by human beings is due to natural radiation, it is essential to assess the radiation doses in order to control possible health effects from such natural sources. In this regard, a number of articles have been appeared for Malaysia in international research journals, which have been reviewed and complied in this article. Most of these articles are about the measurement of activity concentrations of primordial (238U, 232Th, 226Ra and 40K and anthropogenic (137Cs radionuclide's and gamma dose rate in environmental samples using HPGe and NaI (Tl survey meter.

  16. Measurements of distribution coefficient for U and Th on sand stone in synthesized sea water and distilled water

    International Nuclear Information System (INIS)

    Nakazawa, Toshiyuki; Okada, Kenichi; Saito, Yoshihiko; Shibata, Masahiro; Sasamoto, Hiroshi

    2005-01-01

    Japan Nuclear Cycle Development Institute (JNC) has developed the sorption database for bentonite and rocks in order to assess the retardation property of important radioactive elements in natural and engineered barriers in the H12 report. However, there are not enough distribution coefficient data for radioactive elements in saline type groundwater in the database. Thus the batch sorption tests were performed for uranium (U) and thorium (Th) in saline type groundwater. For these elements, there are little registration numbers in the JNC's sorption database, and also these elements are important to evaluate the safety of disposal system. The experiments for each radioactive element were performed on the following conditions; U: Kd measurements using the solutions (synthesized sea water and distilled water) reacted with sand stone as a function of carbonate concentration, under reducing conditions. Th: Kd measurements using the solutions (synthesized sea water and distilled water) reacted with sand stone. The results of the experiments are summarized below; In the case of U, Kd was approximately 6.5E-01 - 9.2E-01 m 3 /kg in synthesized sea water. On the other hand, Kd was 2.2E-02 - 2.4E-02 m 3 /kg in the high carbonate solution. And also, Kd was 6.5E-02 - 7.2E-02 m 3 /kg in synthesized sea water adjusted pH 10 and 3.4E-02 - 4.1E-02 m 3 /kg in distilled water adjusted pH 10, respectively. In the case of Th, Kd was measured in synthesized sea water adjusted to pH 10 and in distilled water adjusted to pH 10. At the sorption measurements of Th, precipitation might be occurred by very low solubility of Th. (author)

  17. Mass measurement of radioactive isotopes

    CERN Document Server

    Kluge, H J; Scheidenberger, C

    2004-01-01

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

  18. The French National Network for the Measurement of Environmental Radioactivity

    International Nuclear Information System (INIS)

    Jaunet, P.

    2010-01-01

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

  19. Apparatus for measuring radioactive emissions

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  20. Submersible purification system for radioactive water

    Science.gov (United States)

    Abbott, Michael L.; Lewis, Donald R.

    1989-01-01

    A portable, submersible water purification system for use in a pool of water containing radioactive contamination includes a prefilter for filtering particulates from the water. A resin bed is then provided for removal of remaining dissolved, particulate, organic, and colloidal impurities from the prefiltered water. A sterilizer then sterilizes the water. The prefilter and resin bed are suitably contained and are submerged in the pool. The sterilizer is water tight and located at the surface of the pool. The water is circulated from the pool through the prefilter, resin bed, and sterilizer by suitable pump or the like. In the preferred embodiment, the resin bed is contained within a tank which stands on the bottom of the pool and to which a base mounting the prefilter and pump is attached. An inlet for the pump is provided adjacent the bottom of the pool, while the sterilizer and outlet for the system is located adjacent the top of the pool.

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

    International Nuclear Information System (INIS)

    Siswanti; Munandar, A. Aris

    2013-01-01

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

  2. Vessel for solidifying water-impermeable radioactive waste

    International Nuclear Information System (INIS)

    Kiuchi, Yoshimasa; Tamada, Shin; Suzuki, Yasushi.

    1993-01-01

    A blend prepared by admixing silica sand, alumina powder or glass fiber, as aggregates, to epoxy resin elastic adhesives is coated on an inner surface of a steel drum can or an inner surface of a concrete vessel at a thickness of greater than 1mm followed by hardening. The addition amount of the silica sand, alumina powder or glass fiber is determined as 20 to 40% by weight, 30 to 60% by weight or 5 to 15% by weight respectively. A lid having a hole for injecting fillers is previously bonded to a container for use in solidifying radioactive materials. The strength of the coating layer is increased and a coating performance and an adhesion force are improved by admixing the aggregates, to provide a satisfactory water-impermeability. The container for use in solidifying radioactive wastes having a coating layer with an advantage of the elastic resin adhesives, strong strength and adhesion and being excellent in the water-impermeability can be obtained relatively economically. (N.H.)

  3. International conventions for measuring radioactivity of building materials

    International Nuclear Information System (INIS)

    Tan Chenglong

    2004-01-01

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

  4. Processing method for discharged radioactive laundry water waste

    International Nuclear Information System (INIS)

    Izumida, Tatsuo; Kitsukawa, Ryozo; Tsuchiya, Hiroyuki; Kiuchi, Yoshimasa; Hattori, Yasuo.

    1995-01-01

    In order to process discharged radioactive laundry water wastes safely and decrease radioactive wastes, bubbling of a surface active agent in a detergent which causes a problem upon its condensation is suppressed, so that the liquid condensate are continuously and easily dried into a powder. A nonionic surface active agent is used against the bubbling of the surface active agent. In addition, the bubbling in an the evaporation can is reduced, and the powderization is facilitated by adding an appropriate inorganic builder. (T.M.)

  5. Device for monitoring radioactivity of cooling water in a nuclear reactor

    International Nuclear Information System (INIS)

    Osawa, Yasuo.

    1975-01-01

    Object: To provide means for monitoring the peak channel of γ-ray spectrum in cooling water and the time-wise attenuation value of the counts of the peak channels and capable of early detecting abnormal phenomenon with a constant reference. Structure: It is provided with a γ-ray detector, a multi-channel γ-ray spectrometer, peak determining means for determining the peak position of the spectrum from the count value of each channel of the γ-ray spectrum, a peak channel memory for memorizing the channel number of the peak channels, attenuation measurement means for measuring the attenuation value by repeatedly measuring the count value of the peak channel, an attenuation memory for memorizing the attenuation value and a variation detector for detecting the variation in radioactivity of the reactor cooling water from the count value of the peak channel and peak channel attenuation value. When a difference is detected by the variation detector, the measurement value is provided as defective value. (Kamimura, M.)

  6. Investigation of the environmental radioactivity around the mooring port

    International Nuclear Information System (INIS)

    Tanigawa, Yoshio

    1976-01-01

    Here are the main data for radioactivity examination performed in 1975 at Mutsu port, the mooring port of atomic energy vessel ''Mutsu''. No abnormality were observed in space γ ray dose ratio, and integrated doses measured by the thermofluorescence dosimeter at three monitoring posts in the port (G M tube) and three monitoring station in Mutsu City. A serial measurement of radioactivity concentration in sea water did not show any abnormality, either. Samples were taken from the surface soil of the ground, the bottom of the rivers, river water, drinking water, and milk and measured the total radioactivity by a gas flow counter. The measurement of the total β-radioactivity and radio nuclides analysis were carried out in sea water, the soil from the bottom of the sea and sea products. Abnormality considered to be caused by ''Mutsu'' did not observed at all. (Kobatake, H.)

  7. A process for treating radioactive water-reactive wastes

    International Nuclear Information System (INIS)

    Dziewinski, J.; Lussiez, G.; Munger, D.

    1995-01-01

    Los Alamos National Laboratory and other locations in the complex of experimental and production facilities operated by the United States Department of Energy (DOE) have generated an appreciable quantity of hazardous and radioactive wastes. The Resource Conservation and Recovery Act (RCRA) enacted by the United States Congress in 1976 and subsequently amended in 1984, 1986, and 1988 requires that every hazardous waste must be rendered nonhazardous before disposal. Many of the wastes generated by the DOE complex are both hazardous and radioactive. These wastes, called mixed wastes, require applying appropriate regulations for radioactive waste disposal and the regulations under RCRA. Mixed wastes must be treated to remove the hazardous waste component before they are disposed as radioactive waste. This paper discusses the development of a treatment process for mixed wastes that exhibit the reactive hazardous characteristic. Specifically, these wastes react readily and violently with water. Wastes such as lithium hydride (LiH), sodium metal, and potassium metal are the primary wastes in this category

  8. Minimization of radioactive material deposition in water-cooled nuclear reactors

    International Nuclear Information System (INIS)

    Ruiz, C.P.; Blaies, D.M.

    1988-01-01

    This patent describes the method for inhibiting the deposition of radioactive cobalt in a water-bearing vessel of a water-cooled nuclear reactor which comprises adding zinc ion to water entering the water-bearing vessel. The improvement contains a substantially lower proportion of the /sup 64/Zn isotope than naturally occurring zinc

  9. A research on the environmental impact on nearby waters range at low-level radioactive waste water drain from the Dayawan nuclear power station

    International Nuclear Information System (INIS)

    Zhang Chunling; Xu Zitu; Xiao Zhang.

    1987-01-01

    The possible influence of the low-level radioactive waste water drain from the Dayawan nuclear power station upon nearby waters range is discussed. The contents of the article contains the numerical simulation on tidal currents and pollutant diffusion, the calculation of concentration distribution of radioactive contaminants in the water area and of polluted field, and the criterion on radioactive contaminant influence on nearby residents and aquatic biologicals. The result shows that when the Dayawan nuclear power station is on normal operation and after the low-level radioactive waste water has been drained off into the sea, the radioactive concentration is even lower than the natural background radiation just out-side the area of about 4 km 2 round the water outlet. As a result, it won't cause any danger to the water environment. Due to the fact that the concentration of the low-level radioactive waste water from the nuclear power station fully accords with the national standard GB4792-84 and the sea water quality sandard GBH2, 3-82. It is no harm to either residents and aquatic biologicals or ecological balance

  10. Quantitative autoradiography - a method of radioactivity measurement

    International Nuclear Information System (INIS)

    Treutler, H.C.; Freyer, K.

    1988-01-01

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

  11. Measurements of natural radioactivity in phosphate fertilizers

    International Nuclear Information System (INIS)

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

    1997-01-01

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

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

    International Nuclear Information System (INIS)

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

    2009-10-01

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

  13. Environmental radioactivity and water supply. Pt. 3. The contamination of surface waters in Germany after the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Haberer, K.

    1988-03-01

    After the reactor accident, german surface waters have been monitored in numerous positions over a long period of time. The highest concentrations of iodine 131 occurred in the lower german region of the Danube river with more than 200 Bg/l whereas the Rhine river had the lowest concentrations. The sudden rise of the radioactivity of the river water have been followed by a slower decrease but nevertheless much faster than the radioactive decay. Probably this is caused by the interaction with river sediments. For the german lakes and reservoirs it was very important whether the water masses have been stratified or not when the radioactive cloud arrived. Where this was the case, the radioactive contaminants remained predominantly in the upper layer, the epilimnion for a long period of time [fr

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

    International Nuclear Information System (INIS)

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

    1970-01-01

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

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

    International Nuclear Information System (INIS)

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

    1970-01-01

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

  16. Measurements of natural radioactivity in historical glasses

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  17. 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

  18. The radioactivity of the sea

    International Nuclear Information System (INIS)

    Walker, M.I.; Rose, K.S.B.

    1990-01-01

    The radioactivity in the world's surface sea water averages 13.6 Bq/kg of water. Over 88% of this activity arises from a single natural radionuclide, 40 K, and 7% of the remainder results from nuclear weapon test fallout. Variations in the radioactivity occur due to changes in salinity, weapon test fallout and discharges of artificial radionuclides, and are examined here on the basis of published measurements. The most radioactive sea identified by these measurements is the Dead Sea, which averages 178 Bq/kg due to its high salinity. Other enclosed, highly saline waters can be expected to have similar levels. The radioactivity in open seas varies within a much narrower range, generally within 20% of the world average. The highest averages are found in the Persian Gulf (22 Bq/kg), the Red Sea (15 Bq/kg) and the Eastern Mediterranean (14.6 Bq/kg). The Irish Sea averaged 13.7 Bq/kg in 1987, with the effect of the Sellafield discharges being partly offset by lower than average salinity. Although higher levels occurred in the Irish Sea during the 1970s when the Sellafield discharges were higher, the average level has always been much less than that in the Dead Sea, so that the Irish Sea has never been the most radioactive sea in the world. Exceptionally low levels of radioactivity (4 Bq/kg) occur in the Baltic Sea due to dilution by fresh water. (author)

  19. Radioactive pollution of the Chernobyl cooling pond bottom sediments. I. Water-physical properties, chemical compound and radioactive pollution of pore water

    Directory of Open Access Journals (Sweden)

    L. S. Pirnach

    2011-03-01

    Full Text Available First results of complex research of the Chernobyl cooling pond bottom sediments are presented. The general problematic is considered. Information about vertical distribution of bottom sediments water-physical properties, and also ionic compound and radioactive pollution 137Cs and 90Sr of pore water is received. The inventory of bottom sediments pore water activity is calculated. Strong correlations between concentration in pore water 137Cs, K +, NH4 + within the selected sediments columns are found out. Results of researches are intended for the forecast of radioecological situation change in the cooling pond water-soil complex during drying-up.

  20. 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)

  1. Reduction of releases of radioactive effluents from light-water-power-reactors in Japan

    International Nuclear Information System (INIS)

    Yoshida, Y.; Itakura, T.; Kanai, T.

    1977-01-01

    Japan Atomic Energy Commission established the dose objectives to the population around the light-water-reactors in May, 1975, based on the ''ALAP'' concept. These values are respectively, 5 mrems per year for total body and 15 mrems per year for thyroid of an individual in the critical group in the environs, due to both gaseous and liquid effluents from LWRs in one site. The present paper describes the implications of the dose objective values, control measures which have been adopted to reduce releases of radioactive materials and related technical developments in Japan. The main control measures for reduction of radioactive gaseous effluents are an installation of a charcoal gas holdup system for decay of noble gases and a supply of clean steam for the gland seal of a turbine in BWR, and a storage tank system allowing decay of noble gases in PWR. For liquid effluents are taken measures to re-use them as the primary coolant. Consequently, the amounts of radioactivity released to the environment from any LWR during normal operation have been maintained under the level to meet the above dose objective values. For research reactors, reduction of release of effluents has also been carried out in a similar way to LWRs. In order to establish the techniques applicable for further reduction, studies are being made on the control measures to reduce leakage of radioiodine, an apparatus for removal of krypton, the treatment of laundry waste and measures to remove the crud in the primary coolant. Presentation is also made on the energy-integrated gas monitor for gaseous effluent and systems of measuring γ dose from radioactive cloud descriminating from natural background, which have been developed for effective monitoring thus reduced environmental dose

  2. Radioactive waste management practices with KWU-boiling water reactors

    International Nuclear Information System (INIS)

    Queiser, H.

    1976-01-01

    A Kraftwerk Union boiling water reactor is used to demonstrate the reactor auxiliary systems which are applied to minimize the radioactive discharge. Based on the most important design criteria the philosophy and function of the various systems for handling the off-gas, ventilation air, waste water and concentrated waste are described. (orig.) [de

  3. Absolute radioactivity measurements

    International Nuclear Information System (INIS)

    Weiss, H.M.

    1983-01-01

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

  4. Crosslinked plastic scintillators: A new detection system for radioactivity measurement in organic and aggressive media

    International Nuclear Information System (INIS)

    Bagán, Héctor; Tarancón, Alex; Ye, Lei; García, José F.

    2014-01-01

    Highlights: • A crosslinked plastic scintillatior for radioactivity measurement was developed. • The effect of C-PS composition in the detection efficiency was evaluated. • C-PS permits the measurement of radioactivity in organic and aggressive media. • C-PS exhibits high detection efficiency in water and even higher in organic media. • C-PS exhibits good reproducibility under different polymerisations with elevated yield. - Abstract: The measurement of radioactive solutions containing organic or aggressive media may cause stability problems in liquid and plastic scintillation (PS) techniques. In the case of PS, this can be overcome by adding a crosslinker to the polymer structure. The objectives of this study are to synthesise a suitable crosslinked plastic scintillator (C-PS) for radioactivity determination in organic and aggressive media. The results indicated that an increase in the crosslinker content reduces the detection efficiency and a more flexible crosslinker yields higher detection efficiency. For the polymer composition studied, 2,5-diphenyloxazole (PPO) is the most adequate fluorescent solute and an increase in its concentration causes little change in the detection efficiency. The inclusion of a secondary fluorescent solute 1,4-bis-2-(5-phenyloxazolyl) benzene (POPOP) improves the C-PS radiometrical characteristics. For the final composition chosen, the synthesis of the C-PS exhibits good reproducibility with elevated yield. The obtained C-PS also displays high stability in different organic (toluene, hydrotreated vegetable oil (HVO) and methanol) and aggressive media (hydrochloric acid, nitric acid and hydrogen peroxide). Finally, the C-PS exhibits high detection efficiency both in water and in aggressive media and can also be applied in organic media showing similar or even higher detection efficiency values

  5. Characterization of radioactive contaminants and water treatment trials for the Taiwan Research Reactor's spent fuel pool

    Energy Technology Data Exchange (ETDEWEB)

    Huang, Chun-Ping, E-mail: chunping@iner.gov.tw [Institute of Nuclear Energy Research, 1000, Wenhua Road, Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan, ROC (China); Lin, Tzung-Yi; Chiao, Ling-Huan; Chen, Hong-Bin [Institute of Nuclear Energy Research, 1000, Wenhua Road, Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan, ROC (China)

    2012-09-30

    Highlights: Black-Right-Pointing-Pointer Deal with a practical radioactive contamination in Taiwan Research Reactor spent fuel pool water. Black-Right-Pointing-Pointer Identify the properties of radioactive contaminants and performance test for water treatment materials. Black-Right-Pointing-Pointer The radioactive solids were primary attributed by ruptured spent fuels, spent resins, and metal debris. Black-Right-Pointing-Pointer The radioactive ions were major composed by uranium and fission products. Black-Right-Pointing-Pointer Diatomite-based ceramic depth filter can simultaneously removal radioactive solids and ions. - Abstract: There were approximately 926 m{sup 3} of water contaminated by fission products and actinides in the Taiwan Research Reactor's spent fuel pool (TRR SFP). The solid and ionic contaminants were thoroughly characterized using radiochemical analyses, scanning electron microscopy equipped with an energy dispersive spectrometer (SEM-EDS), and inductively coupled plasma optical emission spectrometry (ICP-OES) in this study. The sludge was made up of agglomerates contaminated by spent fuel particles. Suspended solids from spent ion-exchange resins interfered with the clarity of the water. In addition, the ionic radionuclides such as {sup 137}Cs, {sup 90}Sr, U, and {alpha}-emitters, present in the water were measured. Various filters and cation-exchange resins were employed for water treatment trials, and the results indicated that the solid and ionic contaminants could be effectively removed through the use of <0.9 {mu}m filters and cation exchange resins, respectively. Interestingly, the removal of U was obviously efficient by cation exchange resin, and the ceramic depth filter composed of diatomite exhibited the properties of both filtration and adsorption. It was found that the ceramic depth filter could adsorb {beta}-emitters, {alpha}-emitters, and uranium ions. The diatomite-based ceramic depth filter was able to simultaneously

  6. A survey of radioactivity in drinking water in Upper Austria

    International Nuclear Information System (INIS)

    Gruber, V.; Maringer, F.J.; Maringer, F.J.; Kaineder, H.; Sperker, S.; Brettner-Messler, R.

    2006-01-01

    The University of Natural Resources and Applied Life Science Vienna, in co-operation with the environmental department of the government of Upper Austria, realizes a 3 year program (2004-2006) to investigate the radioactivity in drinking water in Upper Austria. The superior purpose of the project is to protect the population from radiation exposure by drinking water. Therefore the measurements should yield basic data for further processing (guidelines, regulations [O.N. S.5251]) and their realisation (precaution, mitigation). To get an overview of the situation water samples are taken from water supplies and consumers houses(population radiation exposure) as well as directly from springs and fountains to obtain hydrogeological-radiological basic data. The first 230 water samples (to get a general idea, distributed among the area of Upper Austria) are analyzed for different radionuclides (Rn-222, Ra-226, H-3, U-238) and alpha-beta total activity concentration by liquid scintillation technologies. On the basis of these results more samples are taken in regions with elevated activity concentrations and besides in regions of particular geological interest (e.g. Bohemian Massif granite rocks; along geological disturbances; in regions with elevated Uranium and Thorium-values in the rocks). These samples are analyzed for Radon on-site by a mobile liquid scintillation instrument (Triathler, by Hidex) and additionally in the laboratory for Ra-228, Po-210, Pb-210. So far, 145 samples have been taken in this way in about 23 communities. First results indicate that the Radon activity concentrations in some springs and fountains range to 1000 Bq/l, but after preparation of the water in the supplies the activity concentrations are usually much lower. To determine this behaviour (e.g. for different preparation facilities), samples are taken at several places within the run of the water from the spring to the consumer. Besides special attention is given to U-238, because little

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

    Science.gov (United States)

    Gorur, F Korkmaz; Camgoz, H

    2014-10-01

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

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

    International Nuclear Information System (INIS)

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

    2018-01-01

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

  9. The radioactivity of bottled mineral waters

    International Nuclear Information System (INIS)

    Vrakova, M.; Babarikova, F.; Belanova, A.

    2005-01-01

    Mineral waters with increased contents of minerals (total mineralization ranging from 1000 to 4000 mg.dm -3 ) can also contain increased concentrations of natural radionuclides. For this reason it is necessary to monitor radioactivity of mineral and thermal springs. Hundreds of springs which are used for drinking purposes are spread in many regions all over Slovakia. In our laboratory we determined these radionuclides in mineral waters: total alpha, total beta, volume activity 222 Rn, concentration of U nat , volume 226 Ra, 228 Ra and 210 Po. From values of determined volume activities of radionuclides we calculated total effective dose from reception mineral waters. By calculation of effective dose we supposed consumption of mineral water 150 dm 3 .year -1 (0.4 dm 3 .day -1 ) for adults (according to UNSCEAR). Conversion factors are initiated in the regulation of Ministry of Health of Slovak Republic (MZ SR No.12/2001). (authors)

  10. Statistical aspects in radioactivity measurements

    International Nuclear Information System (INIS)

    Hoetzl, H.

    1979-10-01

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

  11. Contribution to the study of radioactivity of drinking water in Madagascar. Case study of the locality of Alasora

    International Nuclear Information System (INIS)

    RAVOSON, Heritiana N.

    2007-01-01

    Among the radioactive parameters which pollute water, the radon is a radioactive gas of natural origin. It comes from the desintegration of radium-226, which itself is coming from uranium-238 present in the earth crust. It infiltrates in underground water and generates solid daughters. The ingestion of radon and its daughters results in a medical risk to the exposed people. The interest of this study is to detect the presence of the short half-life radionuclides, radon and radium in drinking water of the Alasora rural district Antananarivo, Madagascar. For measurement, portable Triathler LSC, model 425-034 was used. Results obtained from 11 sites confirm the presence of the short half life radionuclides such as the Po-218, Po-214, Bi-214 and the Pb-214 in the samples. So, the gross alpha at first measurement varies from 13700± 100 Bq -1 to 85500±300 Bq.l -1 . Results also confirm the presence of radon in excess or not supported, by the fact that radium in the samples is lower than the detection limit. To confirm the presence of radium and the origin of the radionuclides in the water, more studies are needed. Compared to the legal limit, the studied zone does not show high radioactivity level. However, it is necessary to reduce any risk of exposure. For this purpose, it is not advised to drink the water immediately after collection. [fr

  12. (238)U and total radioactivity in drinking waters in Van province, Turkey.

    Science.gov (United States)

    Selçuk Zorer, Özlem; Dağ, Beşir

    2014-06-01

    As part of the national survey to evaluate natural radioactivity in the environment, concentration levels of total radioactivity and natural uranium have been analysed in drinking water samples. A survey to study natural radioactivity in drinking waters was carried out in the Van province, East Turkey. Twenty-three samples of drinking water were collected in the Van province and analysed for total α, total β and (238)U activity. The total α and total β activities were counted by using the α/β counter of the multi-detector low background system (PIC MPC-9604), and the (238)U concentrations were determined by inductively coupled plasma-mass spectrometry (Thermo Scientific Element 2). The samples were categorised according to origin: tap, spring or mineral supply. The activity concentrations for total α were found to range from 0.002 to 0.030 Bq L(-1) and for total β from 0.023 to 1.351 Bq L(-1). Uranium concentrations ranging from 0.562 to 14.710 μg L(-1) were observed in drinking waters. Following the World Health Organisation rules, all investigated waters can be used as drinking water.

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  14. Validation of an advanced analytical procedure applied to the measurement of environmental radioactivity.

    Science.gov (United States)

    Thanh, Tran Thien; Vuong, Le Quang; Ho, Phan Long; Chuong, Huynh Dinh; Nguyen, Vo Hoang; Tao, Chau Van

    2018-04-01

    In this work, an advanced analytical procedure was applied to calculate radioactivity in spiked water samples in a close geometry gamma spectroscopy. It included MCNP-CP code in order to calculate the coincidence summing correction factor (CSF). The CSF results were validated by a deterministic method using ETNA code for both p-type HPGe detectors. It showed that a good agreement for both codes. Finally, the validity of the developed procedure was confirmed by a proficiency test to calculate the activities of various radionuclides. The results of the radioactivity measurement with both detectors using the advanced analytical procedure were received the ''Accepted'' statuses following the proficiency test. Copyright © 2018 Elsevier Ltd. All rights reserved.

  15. Environmental radioactivity survey in Suwon

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-12-15

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

  16. Practice and experience in traceability of radioactivity measurements of environmental samples

    International Nuclear Information System (INIS)

    Huang Zhijian

    1990-01-01

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

  17. NPL support for environmental radioactivity measurements in the United Kingdom

    International Nuclear Information System (INIS)

    Jerome, Simon

    2009-01-01

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

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

    International Nuclear Information System (INIS)

    Sutjipto; Muryono; Sumining

    2000-01-01

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

  19. Radioactivity measurements on live Bewick's Swans

    International Nuclear Information System (INIS)

    Hancock, R.; Wollam, P.B.

    1987-01-01

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

  20. Development of a water purifier for radioactive cesium removal from contaminated natural water by radiation-induced graft polymerization

    Science.gov (United States)

    Seko, Noriaki; Hoshina, Hiroyuki; Kasai, Noboru; Shibata, Takuya; Saiki, Seiichi; Ueki, Yuji

    2018-02-01

    Six years after the Fukushima-nuclear accident, the dissolved radioactive cesium (Cs) is now hardly detected in environmental natural waters. These natural waters are directly used as source of drinking and domestic waters in disaster-stricken areas in Fukushima. However, the possibility that some radioactive Cs adsorbed on soil or leaves will contaminate these natural waters during heavy rains or typhoon is always present. In order for the returning residents to live with peace of mind, it is important to demonstrate the safety of the domestic waters that they will use for their daily life. For this purpose, we have synthesized a material for selective removal of radioactive Cs by introducing ammonium 12-molybdophosphate (AMP) onto polyethylene nonwoven fabric through radiation-induced emulsion graft polymerization technique. Water purifiers filled with the grafted Cs adsorbent were installed in selected houses in Fukushima. The capability of the grafted adsorbent to remove Cs from domestic waters was evaluated for a whole year. The results showed that the tap water filtered through the developed water purifier contained no radioactive Cs, signifying the very effective adsorption performance of the developed grafted adsorbent. From several demonstrations, we have commercialized the water purifier named "KranCsair®". Furthermore, we have also developed a method for the mass production of the grafted nonwoven fabric. Using a 30 L grafting reactor, it was possible to produce the grafted nonwoven fabric with a suitable range of degree of grafting. When an irradiated roll of nonwoven trunk fabric with a length of 10 m and a width of 30 cm was set in the reactor filled with glycidyl methacrylate (GMA), AMP, Tween 80 monomer emulsion solution at 40 °C for 1 h, the difference of Dgs in the length and the width on roll of fabrics was negligible.

  1. The Citizen Observatory of Radioactivity - Assessment of results - Measurement of gamma emitters. Year 2009

    International Nuclear Information System (INIS)

    2010-01-01

    This document proposes a set of tables containing different information and data regarding measurements of gamma radioactivity made during the first and second half-year of 2009 in different marine and water environments (algae, sands, sea water, molluscs, sediments, water mosses, vegetal) in different locations: a bay close to the AREVA plant in La Hague, different locations on the Normandy coast, around the AREVA plant in La Hague, waterways in Normandy and in other river near the Chinon and Civaux nuclear power stations. These tables contain information about the sampling (date, location, quantity, analysed fraction, and so on) and results of measurements of artificial (isotopes of cobalt, ruthenium-rhodium, silver, iodine, caesium, americium, europium) and natural (potassium, beryllium, lead, bismuth, etc.) radionuclides

  2. Radioactivity in waste water samples from COGEMA supplied by Greenpeace

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  3. Radioactivity of fission products in cistern waters along the Croatian coast of the Adriatic Sea

    International Nuclear Information System (INIS)

    Franic, Z.; Marovic, G.

    1997-01-01

    Measurements of radioactive contamination of water samples from cisterns collecting rainwater from roofs etc. with fission products have been carried out along the Croatian coast of the Adriatic Sea since 1968. An exponential decline of radioactivity followed the nuclear moratorium.After the nuclear accident at Chernobyl, higher levels of 137 Cs and 90 Sr were detected again, cistern waters being the only environmental samples in Croatia in which elevated 90 Sr activities persisted for several years. For the pre-Chernobyl period, the mean residence time of 90 Sr in cistern waters being order of magnitude several years was similar to that calculated for fallout.Contrary, for the post-Chernobyl time, S r mean residence time was calculated to be considerably shorter, reflecting the tropospheric mean residence time.Therefore, the pre-Chernobyl) and the post-Chernobyl mean residence times of 90 Sr in cistern waters reflect the mechanism by which strontium was released to the atmosphere. The annual dose for the critical adult population received from 90 Sr, 137 Cs and 90 Cs by drinking cistern water was estimated to be a few per cent of the dose from natural background radiation. (authors)

  4. Monitoring of radioactivity in drinking water; Control de la radiactividad en las aguas de consumo humano

    Energy Technology Data Exchange (ETDEWEB)

    Legarda, F.; Herranz, M.; Letessier, P.

    2008-07-01

    Radioactivity is a physical phenomenon whose presence in water is monitored due to its potential capability to induce deleterious effects on human health. In this article the effects that can be caused by radioactivity as well as the way in which regulations establish how to perform a monitorization of water that enables us to ascertain that the radiological quality of water is in agreement with the accepted standard of quality of life are analyzed. Finally the means available to know the content of radioactivity in water together with some clues on how to remove it from water are described. (Author) 5 refs.

  5. Boiling water reactor liquid radioactive waste processing system

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    The standard sets forth minimum design, construction and performance requirements with due consideration for operation of the liquid radioactive waste processing system for boiling water reactor plants for routine operation including design basis fuel leakage and design basis occurrences. For the purpose of this standard, the liquid radioactive waste processing system begins at the interfaces with the reactor coolant pressure boundary, at the interface valve(s) in lines from other systems and at those sumps and floor drains provided for liquid waste with the potential of containing radioactive material. The system terminates at the point of controlled discharge to the environment, at the point of interface with the waste solidification system and at the point of recycle back to storage for reuse. The standard does not include the reactor coolant clean-up system, fuel pool clean-up system, sanitary waste system, any nonaqueous liquid system or controlled area storm drains

  6. 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

  7. Apparatus for measuring a concentration of radioactivity

    International Nuclear Information System (INIS)

    Tabuchi, H.; Ogushi, A.

    1978-01-01

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

  8. Measurement of water flow rate in unsaturated soil by thermistor type sensor

    International Nuclear Information System (INIS)

    Takebe, Shinichi; Yamamoto, Tadatoshi; Wadachi, Yoshiki

    1981-09-01

    As a part of radiological safety studies for ground disposal of radioactive wastes, a measuring apparatus of water flow rate with thermistor type sensor was made as preliminary one and the measurement of water flow rate in the soil was carried out, in order to evalute by comparison of the migration rate of water with that of radionuclide in an unsaturated soil. The water flow rate can be determined by measuring the change of the thermal conductivity (temperature) of soil around the several thermistor type sensors set in a soil. Particularly at the region of low water content in the soil, the water flow rate was able to measure successfully by this apparatus. (author)

  9. Measurements of radioactive dust in high altitude air

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  10. 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.

  11. Development of methods to measure virus inactivation in fresh waters.

    OpenAIRE

    Ward, R L; Winston, P E

    1985-01-01

    This study concerns the identification and correction of deficiencies in methods used to measure inactivation rates of enteric viruses seeded into environmental waters. It was found that viable microorganisms in an environmental water sample increased greatly after addition of small amounts of nutrients normally present in the unpurified seed virus preparation. This burst of microbial growth was not observed after seeding the water with purified virus. The use of radioactively labeled poliovi...

  12. Multi-criteria analysis for evaluating the radiological and ecological safety measures in radioactive waste management

    International Nuclear Information System (INIS)

    Sazykina, T.G.; Kryshev, I.I.

    2006-01-01

    A methodological approach is presented for multicriterial evaluating the effectiveness of radiation ecological safety measures during radioactive waste management. The approach is based on multicriterial analysis with consideration of radiological, ecological, social, economical consequences of various safety measures. The application of the multicriterial approach is demonstrated taking as an example of decision-making on the most effective actions for rehabilitation of a water subject, contaminated with radionuclides [ru

  13. Results of environmental radioactivity measurements in the member states of the European Community for air, deposition, water, milk, 1975-1976

    International Nuclear Information System (INIS)

    1978-01-01

    The present document is the sixteenth report published by the Health and Safety Directorate of the Commission of the European Communities concerning ambient radioactivity. It was drawn up using the data collected by the stations in charge of the surveillance of environmental radioactivity in the Member States. The results are extracts from the data sent to the Commission in application of Article 36 of the Treaty of Rome instituting the European Atomic Energy Community. This is the second document which includes data from the enlarged community-viz. Belgium, the Federal Republic of Germany, France, Italy, Luxembourg, the Netherlands, plus Denmark, Ireland and the United Kingdom, who joined the Community on 1 January 1973. The results presented in this report deal with radioactive contamination of the air, precipitaton and fallout, surface water and milk during 1975 and 1976

  14. Environmental radioactivity measurement intercomparison exercise 1990

    International Nuclear Information System (INIS)

    Jerome, S.M.

    1991-05-01

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

  15. Surveillance of the radioactivity in the environment of the Loire basin

    International Nuclear Information System (INIS)

    2008-12-01

    The surveillance of the radioactivity in environment in the Loire catchment basin rests on the measurement of radioactivity in atmosphere, in the rain waters and continental waters as well as the follow up of radioactivity in food chain. Concerning the air radiation monitoring, that is the dose rate measurement of ambient gamma radiation, the radon measurement and the measurement of particulates and radioactive aerosols. Concerning the food chain, the follow up is made on drinking water, milk, fishes and the special case of strontium 90. The actors of this campaign are the institute of radiation protection and nuclear safety (I.R.S.N.), Electricite de France (E.D.F.) Areva NC, the associations qualified for the surveillance of air quality (A.A.S.Q.A.) and the government services. (N.C.)

  16. Measurement and analysis of radioactive substances

    International Nuclear Information System (INIS)

    2001-01-01

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

  17. Radioactivity measurement for emergency or post-accident situations

    International Nuclear Information System (INIS)

    Champion, D.

    2010-01-01

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

  18. Radioactivity measurements by liquid scintillation spectroscopy

    International Nuclear Information System (INIS)

    Cassette, Ph.

    2004-01-01

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

  19. Facilities for treatment of radioactive contaminated water in nuclear power plants

    International Nuclear Information System (INIS)

    1981-02-01

    The standard applies to processes applied in facilities for treatment of radioactive contaminated water in nuclear power plants with LWR- and HTR-type reactors. It does not apply to the treatment of concentrates obtained in the decontamination of water. (orig.) [de

  20. 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)

  1. 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.)

  2. Liquid radioactive waste processing system for pressurized water reactor plants

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    This Standard sets forth design, construction, and performance requirements, with due consideration for operation, of the Liquid Radioactive Waste Processing System for pressurized water reactor plants for design basis inputs. For the purpose of this Standard, the Liquid Radioactive Waste Processing System begins at the interfaces with the reactor coolant pressure boundary and the interface valve(s) in lines from other systems, or at those sumps and floor drains provided for liquid waste with the potential of containing radioactive material; and it terminates at the point of controlled discharge to the environment, at the point of interface with the waste solidification system, and at the point of recycle back to storage for reuse

  3. Measurement and evaluation of alpha radioactivity using ionized air transport technology

    International Nuclear Information System (INIS)

    Maekawa, Tatsuyuki; Yamaguchi, Hiromi

    2009-01-01

    A novel alpha radioactivity monitor using ionized air transport technology has been developed for future constitution of 'clearance level' for uranium and TRU radioactive waste. This technology will bring paradigm shift on alpha-ray measurement, such as converting 'closely contacting and scanning measurement' to 'remotely contacting measurement in the block', and drastically improve the efficiency of measurement operation. In this article, the origin and chronicle of this technology were simply explained and our newest accomplishment was described. Furthermore, using measurement data obtained in our development process, measurement and evaluation examples of alpha radioactivity were shown for practical operations as informative guides. We hope that this technology will be widely endorsed as a practical method for alpha clearance measurement in the near future. (author)

  4. Applicability of portable spectrometer for activity measurement of contaminated water and soil samples

    International Nuclear Information System (INIS)

    Krishnan, Narayani; Rekha, A.K.; Anilkumar, S.; Sharma, D.N.

    2011-01-01

    The absolute activity measurement is often necessary to assess the impact of radioactivity contamination due to various incidents. Commercially available portable spectrometer cum dose rate meter is used for the identification of radionuclides involved and associated dose rates. In this paper the authors discusses the study carried out on the applicability of portable spectrometer for absolute radioactivity measurements in water and soil matrices. The portable spectrometer and the methodology developed for activity estimation has been used in many insitu applications. (author)

  5. The use of tracer techniques to measure water flow rates in steam turbines

    International Nuclear Information System (INIS)

    Whitfield, O.J.; Blaylock, G.; Gale, R.W.

    1979-01-01

    Radioactive and chemical tracers offer some unique advantages in detailed flow measurement on steam turbine plant. A series of experiments on a nuclear power station are reported where tracers successfully measured water flow rates and the initial steam moisture with an accuracy suitable for performance and commissioning tests. Both radioactive and chemical tracer methods produced identical results. Straightforward practical procedures were evolved that ensured repeatable accuracy and in addition a quantitative method of detecting heater leaks on load was established. (author)

  6. Radioactivity levels in well water supplies within the greater Chicago area

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  7. Survey monitoring of environmental radioactivity in Gangneung area

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-12-15

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

  8. Survey monitoring of environmental radioactivity in Gangneung area

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-12-15

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

  9. Survey monitoring of environmental radioactivity in Gangneung area

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-12-15

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

  10. 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

  11. Improvement of the safety regulations in the management of radioactive waste accumulated in the liquid radioactive waste water basins of the PO 'Majak' (Ozersk), the Siberian Chemical Plant (Seversk) and the Mining-Chemical Plant (Zheleznogorsk)

    International Nuclear Information System (INIS)

    Vishnevski, Y.G.; Kislov, A.I.; Irushkin, V.M.

    2002-01-01

    One of the most important problems of radiation safety in Russia is the decommissioning of the liquid radioactive waste water basins of the PO 'Majak' (Ozersk), Siberian Chemical Plant (Seversk) and Mining-Chemical Plant (Zheleznogorsk). The liquid radioactive waste water basins were constructed in 1950-1960 for the collection and storage of liquid waste from the radiochemical plants. The potential hazards of the liquid in the radioactive waste water basins are: migration of radionuclides into the soil of the liquid radioactive waste water basin floors; wind-induced carry-over of radionuclides from the liquid radioactive waste water basins; hazards (radiation included) to the environment and population arising in case physical barriers and hydraulic structures are damaged; and criticality hazards. The classification of the liquid radioactive waste water basins were developed based on the collection and analyzes of the information on liquid radioactive waste water basin characteristics and the method of multicriterion expert assessment of potential hazards. Three main directions for the improvement of safety regulation in the management of radioactive waste accumulated in the liquid radioactive waste water basins were defined: 1. Common directions for the improvement of safety regulation in the area of rehabilitation of the territories contaminated with radioactive substances. 2. Common directions for the improvement of safety regulation in the area of rehabilitation of the territories, such as the liquid radioactive waste water basins. 3. Special directions for the regulatory activities in the area of operation and decommissioning of the liquid radioactive waste water basins of the PO 'Majak' (Ozersk), Siberian Chemical Plant (Seversk) and Mining-Chemical Plant (Zheleznogorsk). As a result, concrete recommendations on safety regulation for the management of radioactive waste accumulated in the water basins were developed. (author)

  12. Development of measuring and control systems for underwater cutting of radioactive components

    International Nuclear Information System (INIS)

    Drews, P.; Fuchs, K.

    1990-01-01

    Shutdown and dismantling of nuclear power plants requires special techniques to decommission the radioactive components involved. For reasons of safety, decommissioning of components under water can be advantageous because of the radioactive shielding effect of water. In this project, research activities and developmental works focused on the realization of different sensor systems and their adaptation to cutting tasks. A new image-processing system has been developed in addition to the use of a modified underwater TV camera for optical cutting process control (plasma and abrasive wheel cutting). For control of process parameters, different inductive, ultrasonic and optical sensors have been modified and tested. The investigations performed are aimed at assuring high-quality underwater cutting with the help of sensor systems specially adapted to cutting tasks, with special signal procession and evaluation through microcomputer control. It is important that special attention be paid to the reduction of interferences in image pick-up and procession. The measuring system has been designed and realized according to the consideration of the demands for underwater cutting processes. The reliability of the system was tested in conjunction with a four-axes handling system

  13. Decommissioning the Romanian Water-Cooled Water-Moderated Research Reactor: New Environmental Perspective on the Management of Radioactive Waste

    International Nuclear Information System (INIS)

    Barariu, G.; Giumanca, R.

    2006-01-01

    Pre-feasibility and feasibility studies were performed for decommissioning of the water-cooled water-moderated research reactor (WWER) located in Bucharest - Magurele, Romania. Using these studies as a starting point, the preferred safe management strategy for radioactive wastes produced by reactor decommissioning is outlined. The strategy must account for reactor decommissioning, as well as for the rehabilitation of the existing Radioactive Waste Treatment Plant and for the upgrade of the Radioactive Waste Disposal Facility at Baita-Bihor. Furthermore, the final rehabilitation of the laboratories and ecological reconstruction of the grounds need to be provided for, in accordance with national and international regulations. In accordance with IAEA recommendations at the time, the pre-feasibility study proposed three stages of decommissioning. However, since then new ideas have surfaced with regard to decommissioning. Thus, taking into account the current IAEA ideology, the feasibility study proposes that decommissioning of the WWER be done in one stage to an unrestricted clearance level of the reactor building in an Immediate Dismantling option. Different options and the corresponding derived preferred option for waste management are discussed taking into account safety measures, but also considering technical, logistical and economic factors. For this purpose, possible types of waste created during each decommissioning stage are reviewed. An approximate inventory of each type of radioactive waste is presented. The proposed waste management strategy is selected in accordance with the recommended international basic safety standards identified in the previous phase of the project. The existing Radioactive Waste Treatment Plant (RWTP) from the Horia Hulubei Institute for Nuclear Physics and Engineering (IFIN-HH), which has been in service with no significant upgrade since 1974, will need refurbishing due to deterioration, as well as upgrading in order to ensure the

  14. Evaluation of isotope migration: land burial. Water chemistry at commercially operated low-level radioactive waste disposal sites. Progress report No. 6, July--September 1977. [Maxey Flats, Kentucky

    Energy Technology Data Exchange (ETDEWEB)

    Colombo, P.; Weiss, A. J.; Francis, A. J.

    1978-04-01

    A survey of the Maxey Flats, Kentucky, low-level radioactive waste disposal site was conducted to obtain an overview of the radioactivity in the trench waters for the purpose of selecting specific trenches for comprehensive study. Water samples collected from trenches and wells were analyzed for specific conductance, pH, temperature, dissolved organic carbon, tritium, gross alpha, gross beta, and gamma radioactivities. The results indicate that there are large differences in the composition of trench waters at the site. Several trenches, that represent extreme and average values of the major parameters measured, have been tentatively selected for further study. 10 fig, 6 tables.

  15. Radioactivity standards for drinking water

    International Nuclear Information System (INIS)

    Sastry, V.N.; Mahadevan, T.N.; Nair, R.N.; Krishnamoorthy, T.M.; Nambi, K.S.V.

    1995-01-01

    The Bureau of Indian Standards (BIS) had issued drinking water specifications for radioactivity in 1991 as 0.1 Bq/L for gross α and 1 pCi/L for gross β. The specification for gross β should have been 1 Bq/L, however the basis for arriving at these standards were not clearly stated. The radiological basis for fixing the Drinking Water Standards (DWS) has, therefore, been reviewed in the present work. The values derived now for gross α (0.01 Bq/L) and gross β (0.34 Bq/L) are different from the values given above. In addition, the DWS for some important radionuclides using the ingestion dose factors applicable to members of the general public (adult as well as children) are given here. It is hoped that the presently suggested values will be accepted by the Atomic Energy Regulatory Board and adopted by the BIS in the near future. (author). 14 refs., 2 tabs., 2 ills

  16. Development of equipment for migration control of radioactive cesium absorbed in suspended solid in the river water

    International Nuclear Information System (INIS)

    Ohyama, Takuya; Ishikawa, Hiroyasu

    2015-01-01

    To prevent inflow of radiocesium with suspended solids (SS) into farmland and increase in dose rate of the river bank in the midstream and downstream, it is important to reduce SS in the river water; therefore we newly developed the test equipment using non-woven fabrics as a trapping material to capture and reduce the SS in running small river water. Authors installed this equipment into the small river which is located in mountainous area surrounded by forests where radionuclides released from the Fukushima Daiichi Nuclear Power Plant were deposited. Two turbidity gauges are installed in inflow and outflow point of this equipment and the turbidity has been continuously measured. From the result of a comparison of turbidity between inflow point and outflow point, a turbidity of inflow point is always higher than outflow point during ordinary water-level; this equipment can capture and reduce the SS in the river water. Through the analysis of particle size distribution, identification of minerals and measurement of concentration of radioactive Cs of the captured SS in the non-woven fabric should be carried out, to clarify the effectiveness of this equipment and non-woven fabrics for reducing the radioactive Cs in small rivers in the future. (author)

  17. Radioactivity leakage monitoring system

    International Nuclear Information System (INIS)

    Nakajima, Takuichiro; Noguchi, Noboru.

    1982-01-01

    Purpose: To obtain a device for detecting the leakage ratio of a primary coolant by utilizing the variation in the radioactivity concentration in a reactor container when the coolant is leaked. Constitution: A measurement signal is produced from a radioactivity measuring instrument, and is continuously input to a malfunction discriminator. The discriminator inputs a measurement signal to a concentration variation discriminator when the malfunction is recognized and simultaneously inputs a measurement starting time from the inputting time to a concentration measuring instrument. On the other hand, reactor water radioactivity concentration data obtained by sampling the primary coolant is input to a concentration variation computing device. A comparator obtains the ratio of the measurement signal from the measuring instrument and the computed data signal from the computing device at the same time and hence the leakage rate, indicates the average leakage rate by averaging the leakage rate signals and also indicates the total leakage amount. (Yoshihara, H.)

  18. Probabilistic Prognosis of Environmental Radioactivity Concentrations due to Radioisotopes Discharged to Water Bodies from Nuclear Power Plants.

    Science.gov (United States)

    Tomás Zerquera, Juan; Mora, Juan C; Robles, Beatriz

    2017-11-15

    Due to their very low values, the complexity of comparing the contribution of nuclear power plants (NPPs) to environmental radioactivity with modeled values is recognized. In order to compare probabilistic prognosis of radioactivity concentrations with environmental measurement values, an exercise was performed using public data of radioactive routine discharges from three representative Spanish nuclear power plants. Specifically, data on liquid discharges from three Spanish NPPs: Almaraz, Vandellós II, and Ascó to three different aquatic bodies (river, lake, and coast) were used. Results modelled using generic conservative models together with Monte Carlo techniques used for uncertainties propagation were compared with values of radioactivity concentrations in the environment measured in the surroundings of these NPPs. Probability distribution functions were inferred for the source term, used as an input to the model to estimate the radioactivity concentrations in the environment due to discharges to the water bodies. Radioactivity concentrations measured in bottom sediments were used in the exercise due to their accumulation properties. Of all the radioisotopes measured in the environmental monitoring programs around the NPPs, only Cs-137, Sr-90, and Co-60 had positive values greater than their respective detection limits. Of those, Sr-90 and Cs-137 are easily measured in the environment, but significant contribution from the radioactive fall-out due to nuclear explosions in the atmosphere exists, and therefore their values cannot be attributed to the NPPs. On the contrary, Co-60 is especially useful as an indicator of the radioactive discharges from NPPs because its presence in the environment can solely be attributed to the impact of the closer nuclear facilities. All the modelled values for Co-60 showed a reasonable correspondence with measured environmental data in all cases, being conservative in two of them. The more conservative predictions obtained with

  19. Environmental radioactivity Ispra 1987

    International Nuclear Information System (INIS)

    Dominici, G.

    1988-01-01

    In this report there are briefly described the measurements of environmental radioactivity performed during 1987 by the site survey group of the Radioprotection Division at the Joint Research Centre Ispra Establishment. Data are given on the concentrations of Sr-90, Cs-137, and other radionuclides in precipitation, air, waters, herbage, milk and radioactive effluents. The environmental contamination is mainly a consequence of the nuclear accident of Chernobyl

  20. Environmental radioactivity Ispra 1989

    International Nuclear Information System (INIS)

    Dominici, G.

    1990-01-01

    In this report there are briefly described the measurements of environmental radioactivity performed during 1989 by the site survey group of the Radioprotection Division at the Joint Research Centre Ispra Establishment. Data are given on the concentrations of Sr-90, Cs-137, and other radionuclides in precipitation, air, waters, herbage, milk and radioactive effluents. The environmental contamination is mainly a consequence of the nuclear accident of Chernobyl

  1. Radioactivity in north European waters: report of Working Group 2 of CEC project MARINA

    International Nuclear Information System (INIS)

    Camplin, W.C.; Aarkrog, A.

    1989-01-01

    The primary objective of Working Group 2 of Project MARINA was to consider recent measurements of environmental radioactivity in north European waters and to use this, and other information, to report likely magnitude of doses to the critical group from marine pathways. The monitoring data were supplemented, where appropriate, with predictions from simple models. The major sources of radioactivity studied were as follows: (i) liquid wastes from nuclear fuel reprocessing plants, (Sellafield, Dounreay, Cap de la Hague); (ii) liquid wastes from nuclear power plants and other major nuclear industry sites, (including Belgium, Denmark, France, Finland, GDR, FDR, Netherlands, Sweden, UK, USSR); (iii) solid waste disposal in the deep north-east Atlantic; (iv) fallout from Chernobyl; and (v) naturally-occurring radionuclides. (author)

  2. 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

  3. National network of radioactivity measurement in environment

    International Nuclear Information System (INIS)

    2006-01-01

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

  4. 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%

  5. Survey monitoring of environmental radioactivity in Daegu area

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-01-15

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

  6. The role of 210Po and 210Pb in low radioactivity experiments and ultrapure water

    International Nuclear Information System (INIS)

    Giammarch, Marco G.

    2013-01-01

    210 Po and 210 Pb isotopes constitute a major background for low background nuclear physics experiments searching for rare events. Searches for solar neutrinos, double beta decay, dark matter and other rare phenomena need to control and monitor radioactivity from Po and Pb through measurements and purification processes. Ultrapure water is often used in these experiments; therefore the issue of minimizing Po and Pb content in water will also be discussed. Finally, the role of 214 Po and 212 Po in low background experiments will be briefly recalled. (author)

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

    International Nuclear Information System (INIS)

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

    1981-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

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

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

    International Nuclear Information System (INIS)

    2008-01-01

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

  10. Krypton-85 and other airborne radioactivity measurements throughout Ireland

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  11. Measurement of radioactivity in Norway

    International Nuclear Information System (INIS)

    Berg, T.C.

    1989-10-01

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

  12. Measurement of radioactivity in Norway

    International Nuclear Information System (INIS)

    Berg, T.C.

    1990-08-01

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

  13. Establishment and application of standard devices for radioactivity measurement

    International Nuclear Information System (INIS)

    Zhou Changgui; Li Xingyuan; Chen Zigen

    1991-03-01

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

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  15. Residual radioactivity guidelines for the heavy water components test reactor at the Savannah River Site

    International Nuclear Information System (INIS)

    Owen, M.B. Smith, R.; McNeil, J.

    1997-04-01

    Guidelines were developed for acceptable levels of residual radioactivity in the Heavy Water Components Test Reactor (HWCTR) facility at the conclusion of its decommissioning. Using source terms developed from data generated in a detailed characterization study, the RESRAD and RASRAD-BUILD computer codes were used to calculate derived concentration guideline levels (DCGLs) for the radionuclides that will remain in the facility. The calculated DCGLs, when compared to existing concentrations of radionuclides measured during a 1996 characterization program, indicate that no decontamination of concrete surfaces will be necessary. Also, based on the results of the calculations, activated concrete in the reactor biological shield does not have to be removed, and imbedded radioactive piping in the facility can remain in place. Viewed in another way, the results of the calculations showed that the present inventory of residual radioactivity in the facility (not including that associated with the reactor vessel and steam generators) would produce less than one millirem per year above background to a hypothetical individual on the property. The residual radioactivity is estimated to be approximately 0.04 percent of the total inventory in the facility as of March, 1997. According to the results, the only radionuclides that would produce greater than 0.0.1-millirem per year are Am-241 (0.013 mrem/yr at 300 years), C-14 (0.022 mrem/yr at 1000 years) and U-238 (0.034 mrem/yr at 6000 years). Human exposure would occur only through the groundwater pathways, that is, from water drawn from, a well on the property. The maximum exposure would be approximately one percent of the 4 millirem per year ground water exposure limit established by the U.S. Environmental Protection Agency. 11 refs., 13 figs., 15 tabs

  16. Radioactivity of drinking-water in the vicinity of nuclear power plants in China based on a large-scale monitoring study.

    Science.gov (United States)

    Miao, Xiao-Xiang; Ji, Yan-Qin; Shao, Xian-Zhang; Wang, Huan; Sun, Quan-Fu; Su, Xu

    2013-12-06

    The public concern for radioactivity of drinking-water has been increasing in recent years after the rapid development of nuclear power plants, and especially after the Fukushima nuclear accident. In this study, the radioactivity of water samples collected in the vicinity of nuclear facilities from seven provinces in China was measured and an average annual equivalent effective dose derived from drinking-water ingestion was calculated. The results showed that, in winter and spring, the activities of gross α and β ranged from 0.009 Bq/L to 0.200 Bq/L and from 0.067 Bq/L to 0.320 Bq/L, respectively. While, in summer and autumn, the activities of gross a and β varied from 0.002 Bq/L to 0.175 Bq/L and from 0.060 Bq/L to 0.334 Bq/L. Our results indicated that the gross a and β activities in these measured water samples were below the WHO recommended values (0.5 Bq/L for gross α and 1.0 Bq/L for gross β) and the annual equivalent effective dose derived from drinking-water ingestion was at a safe level.

  17. Analysis on Radioactive Waste Transmutation in Light Water cooled Hyb-WT

    International Nuclear Information System (INIS)

    Hong, Seonghee; Kim, Myung Hyun

    2014-01-01

    A feasibility of realization is much higher in FFHR compared with pure fusion. A combination of plasma fusion source for neutrons with a subcritical reactor at the blanket side has much higher capability in transmutation of waste as well as reactor safety compared with fission reactor options. Fusion-Fission Hybrid Reactor (FFHR) uses various coolants depending on the purpose. It is important that coolant being used should be suitable to reactor purpose, because reactor performance and the design constraints may change depending on the coolant. There are basically two major groups of coolants for FFHR. One group of coolant does not contain Li. They are Na, Pb-Bi, H 2 O and D 2 O. The other group contains Li for tritium breeding. They are Li, LiPb, LiSN, FLIBE and FLiNaBe. Currently, the issue in FFHR is its implication for radioactive waste transmutation (FFHR for WT). Because radioactive wastes of spent nuclear fuel (SNF) are transmuted using fusion neutron source. Therefore a suitable coolant should be used for effective waste transmutation. . In FFHR for WT, LiPb coolant is being used mainly because of tritium production in Li and high neutron economic through reaction in Pb. However different coolants use such as Na, Pb-Bi are used in fast reactors and accelerator driven systems (ADS) having same purpose. In this study, radioactive waste transmutation performance of various coolants mentioned above will be compared and analyzed. Through this study, the coolants are judged primarily for their support to waste transmutation disregarding their limitation to reactor design and tritium breeding capability. First, performance of the light water coolant regarding radioactive waste transmutation was analyzed among various coolants mentioned above. In this paper, performance of radioactive waste transmutation can be known depending on different volume fractions (54.53, 60.27, 97.94vol.%) of the light water. Light water dose required fusion power lower than LiPb due to

  18. Method to decontaminate radioactive water in the presence of impurity substances

    Energy Technology Data Exchange (ETDEWEB)

    Krause, H; Hepp, H; Kluger, W; Geisel, R

    1978-08-24

    The method ensures the removal of radioactive substances from hard-to-decontaminate water. Before decontamination proper, ozone or chlorine is added to the water for demasking. The daughter products (oxidized radionuclides) of ozone are gaseous while the decay products of the chlorine remain in the water in the form of salts. In both cases, complex or chelate formation during the subsequent decontamination process is avoided.

  19. Method to decontaminate radioactive water in the presence of impurity substances

    International Nuclear Information System (INIS)

    Krause, H.; Hepp, H.; Kluger, W.; Geisel, R.

    1978-01-01

    The method ensures the removal of radioactive substances from hard-to-decontaminate water. Before decontamination proper, ozone or chlorine is added to the water for demasking. The daughter products (oxidized radionuclides) of ozone are gaseous while the decay products of the chlorine remain in the water in the form of salts. In both cases, complex or chelate formation during the subsequent decontamination process is avoided. (DG) [de

  20. Natural radioactivity in mineral and spa water: the current regulatory approach in Italy

    International Nuclear Information System (INIS)

    Nuccetelli, C.; Bochicchio, F.; Ruocco, G.

    2004-01-01

    Mineral and thermal waters can contain radioactivity of natural origin which, in some cases, can lead to radiation-protection problems for both workers and consumers. In Italy, as in many other countries, the consumption of bottled mineral water is rather high and the practice of spending short stays in spas is also popular. Consumer protection against natural radioactivity in mineral water is not regulated at all and exposure from thermal waters is not treated in detail, in either the European Union or Italy. For this reason, the Italian Ministry of Health - which has the duty to authorize spa activities and the sale of mineral water on the basis of water characteristics - asked the Istituto Superiore di Sanita (the Italian National Institute of Health) to provide ad-hoc reports containing both dosimetric calculations and analysis of the radiation-protection regulations to be applied in these situations. On the basis of these reports, the Ministry of Health decided, in two statements for spa and mineral waters respectively, to indicate upper levels for natural radioactivity content. Since 2002, spa water parameters have been in force for authorization of their use and sale, and are to be promulgated by specific and more comprehensive regulations. For mineral waters used for infant feeding and drinking, levels lower than those for general public uses have been proposed, in order to take into account the higher ingestion dose coefficients for infants. At the moment, mineral water levels are not enforced as law. This paper presents the dosimetric calculation results and the Ministry of Health statements. (Author) 17 refs

  1. Radioactivity in waters in SR Slovenia

    International Nuclear Information System (INIS)

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

    1977-12-01

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

  2. New Applications of Cosmogenic Radioactive Isotopes to Study Water Travel Times

    Science.gov (United States)

    Visser, A.; Thaw, M.; Deinhart, A.; Bibby, R. K.; Esser, B.

    2017-12-01

    The travel time of water moving through a landscape influences nutrient dynamics and biogeochemical cycles. Constraining water travel times helps to understand the functioning of the critical zone. Water travel times cannot be observed directly but can be constrained by measurements of cosmogenic radioactive isotopes. We studied a small (4.6 km2) subalpine (1660-2117 m) catchment in a Mediterranean climate (8 °C, 1200 mm/yr) in the California Sierra Nevada to assess subsurface water storage dynamics and investigate flow paths and flow velocities. We analyzed a combination of three cosmogenic radioactive isotopes with half-lives varying from 87 days (sulfur-35), 2.6 years (sodium-22) to 12.3 years (tritium) in precipitation and stream samples. Water stable isotopes and solute chemistry aided the interpretation of the cosmogenic isotopes. Tritium samples (1L) are analyzed by noble gas mass spectrometry after helium-3 accumulation. Samples for sulfur-35 and sodium-22 are collected by processing 20-1000 L of water through an anion and cation exchange column in-situ. Sulfur-35 is analyzed by liquid scintillation counting after chemical purification and precipitation. Sodium-22 is analyzed by gamma counting after eluting the cations into a 4L Marinelli beaker. Monthly collected precipitation samples show variability of deposition rate for tritium and sulfur-35. Sodium-22 levels in cumulative yearly precipitation samples are consistent with recent studies in the US and Japan. The observed variability of deposition rates complicates direct use as decaying age tracers. The level and variability of tritium in monthly stream samples indicate a mean residence time on the order of 10 years and only small contributions of younger water during high flow conditions. Sulfur-35 and sodium-22 concentrations were critically interpreted considering possible uptake by vegetation and cation exchange. Detections of sodium-22 confirm a small fraction of younger (water. Low concentrations

  3. 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

  4. 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}.

  5. Survey monitoring of environmental radioactivity in Jeju area

    Energy Technology Data Exchange (ETDEWEB)

    U, Zang Kual; Kang, Tae Woo; Park, Won Pyo [Jeju National Univ., Jeju (Korea, Republic of)

    2003-12-15

    The project is carried out to monitor the change of environmental radioactivity in Jeju, and to provide a systematic data for radiation monitoring and counter measurement at a radiological emergency situation. Also the survey of natural environmental radioactivities in the samples was conducted to make the reliable data base for evaluation of internal exposure and environmental contamination of radiation. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Jeju Regional Monitoring Station in 2002. Also it contains the data of natural radioactivity levels of food stuff such as agricultural and marine products, including drinking waters.

  6. Survey monitoring of environmental radioactivity in Jeju area

    Energy Technology Data Exchange (ETDEWEB)

    U, Z. K.; Oh, S. H. [Jeju National Univ., Jeju (Korea, Republic of)

    1998-01-15

    The project is carried out to monitor the change of environmental radioactivity in Jeju, and to provide a systematic data for radiation monitoring and counter measurement at a radiological emergency situation. Also the survey of natural environmental radioactivities in the samples was conducted to make the reliable data base for evaluation of internal exposure and environmental contamination of radiation. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Jeju Regional Monitoring Station in 1997. Also it contains the data of natural radioactivity levels of food stuff such as agricultural and marine products, including drinking waters.

  7. Survey monitoring of environmental radioactivity in Jeju area

    Energy Technology Data Exchange (ETDEWEB)

    U, Zang Kual; Kang, Tae Woo; Park, Won Pyo [Jeju National Univ., Jeju (Korea, Republic of)

    2002-12-15

    The project is carried out to monitor the change of environmental radioactivity in Jeju, and to provide a systematic data for radiation monitoring and counter measurement at a radiological emergency situation. Also the survey of natural environmental radioactivities in the samples was conducted to make the reliable data base for evaluation of internal exposure and environmental contamination of radiation. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Jeju Regional Monitoring Station in 2001. Also it contains the data of natural radioactivity levels of food stuff such as agricultural and marine products, including drinking waters.

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  9. Measurement of artificial radioactivity in the atmosphere at Ottawa, Canada

    Energy Technology Data Exchange (ETDEWEB)

    Terentiuk, F

    1958-01-01

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

  10. 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.)

  11. Survey monitoring of environmental radioactivity in Jeju area

    Energy Technology Data Exchange (ETDEWEB)

    U, Zang Kual; Kang, Tae Woo [Jeju National Univ., Jeju (Korea, Republic of)

    2000-12-15

    The project is carried out to monitor the change of environmental radioactivity in Jeju, and to provide a systematic data for radiation monitoring and counter measurement at a radiological emergency situation. Also the survey of natural environmental radioactivities in the samples was conducted to make the reliable data base for evaluation of internal exposure and environmental contamination of radiation. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Jeju Regional Monitoring Station in 2000. Also it contains the data of natural radioactivity levels of food stuff such as agricultural and marine products, including drinking waters. There was no significant difference in environmental radioactivities between 1999 and 2000.

  12. Method and apparatus for the treatment of radioactive or toxic waste waters

    Energy Technology Data Exchange (ETDEWEB)

    Hofstaetter, K; Glock, J; Jakusch, H

    1976-05-26

    A method is described which proposes to store radioactive or toxic waste water in a binder, e.g. bitumen, for disposal. First of all, the liquid contained in the waste water is evaporated so that the radioactive or toxic part remains in solid form. This solid, whose specific gravity must be higher than that of the binder, is put on the surface of the binder, e.g. bitumen. Due to gravity it is embedded by sedimentation and completely covered by the binder. An apparatus with two variants to carry out the process is described, with particular emphasis on the advantages as compared to conventional methods.

  13. Radioactive Beam Measurements to Probe Stellar Explosions

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Michael Scott [ORNL

    2010-01-01

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

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

    International Nuclear Information System (INIS)

    1970-01-01

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

  15. Measurements of astrophysical reaction rates for radioactive samples

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  16. The ''invisible'' radioactive scale

    International Nuclear Information System (INIS)

    Bjoernstad, T.; Ramsoey, T.

    1999-04-01

    Production and up-concentration of naturally occurring radioactive material (NORM) in the petroleum industry has attracted steadily increasing attention during the last 15 years. Most production engineers today associate this radioactivity with precipitates (scales) and sludges in production tubing, pumps, valves, separators, settling tanks etc., wherever water is being transported or treated. 226 Ra and 228 Ra are the most well known radioactive constituents in scale. Surprisingly little known is the radioactive contamination by 210 Pb and progeny 210 Bi and 210 Po. These are found in combination with 226 Ra in ordinary scale, often in layer of non-radioactive metallic lead in water transportation systems, but also in pure gas and condensate handling systems ''unsupported'' by 226 Ra, but due to transportation and decay of the noble gas 222 Rn in NG/LNG. This latter contamination may be rather thin, in some cases virtually invisible. When, in addition, the radiation energies are low enough for not being detectable on the equipment outer surface, its existence has for most people in the industry been a secret. The report discusses transportation and deposition mechanisms, detection methods and provides some examples of measured results from the North Sea on equipment sent for maintenance. It is concluded that a regular measurement program for this type of contamination should be mandatory under all dismantling processes of transportation and fluid handling equipment for fluids and gases offshore and onshore

  17. Use of aquatic bryophytes as bio monitors for radioactive studies

    International Nuclear Information System (INIS)

    Damianova, A.; Penev, I.; Drenska, M.

    2006-01-01

    As a widespread water moss Fontinalis antipyretics is frequently used as a biomonitor for trace elements pollution in lakes and running waters. The purpose of this study is to use Fontinalis antipyretics as a tool for monitoring of radioactivity in waters from different rivers (Musalenska Bistriza, Iskar, Maritza, etc.) in Rila Mountain. The radioactivity of aquatic moss, water samples and sediments were measured using HPG detector with the parameters FWHM 2 kev at 6 0Co efficiency 35% with low background. The dose rate measurements (μR/h) show different values according to the place of sampling and reflect the present ecological status of the river ecosystems. The ongoing measurements will allowed the absolute value of 1 37Cs in bryophytes to be determined and eventually some seasonal variations to be observed. A special interest is whether the measured activity is accidental or is as a consequence of a long time accumulation in the bryophytes. In this case they could probably be used for water purification. On that basis the bryophytes could be used for controlling radioactivity of river ecosystems even in high-mountain difficult accessible places replacing the transportation of large volumes of water

  18. Measurement of radioactivity in Norway

    International Nuclear Information System (INIS)

    Berg, T.C.

    1988-05-01

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

  19. Modeling ground water flow and radioactive transport in a fractured aquifer

    International Nuclear Information System (INIS)

    Pohll, G.; Hassan, A.E.; Chapman, J.B.; Papelis, C.; Andricevic, R.

    1999-01-01

    Three-dimensional numerical modeling is used to characterize ground water flow and contaminant transport at the Shoal nuclear test site in north-central Nevada. The fractured rock aquifer at the site is modeled using an equivalent porous medium approach. Field data are used to characterize the fracture system into classes: large, medium, and no/small fracture zones. Hydraulic conductivities are assigned based on discrete interval measurements. Contaminants from the Shoal test are assumed to all be located within the cavity. Several challenging issues are addressed in this study. Radionuclides are apportioned between surface deposits and volume deposits in nuclear melt glass, based on their volatility and previous observations. Surface-deposited radionuclides are released hydraulically after equilibration of the cavity with the surrounding ground water system, and as a function of ground water flow through the higher-porosity cavity into the low-porosity surrounding aquifer. Processes that are modeled include the release functions, retardation, radioactive decay, prompt injection, and in growth of daughter products. Prompt injection of radionuclides away from the cavity is found to increase the arrival of mass at the control plane but is not found to significantly impact calculated concentrations due to increased spreading. Behavior of the other radionuclides is affected by the slow chemical release and retardation behavior. The transport calculations are sensitive to many flow and transport parameters. Most important are the heterogeneity of the flow field and effective porosity. The effect of porosity in radioactive decay is crucial and has not been adequately addressed in the literature. For reactive solutes, retardation and the glass dissolution rate are also critical

  20. Environmental radioactivity. Ispra 1973-1974

    International Nuclear Information System (INIS)

    Dominici, G.

    1976-01-01

    In this report there are briefly described the measurements of environmental radioactivity performed during 1973-1974 by the site survey group of the Protection Division of the Euratom Joint Research Centre - Ispra Establishment. Data are given on the concentrations of 90 Sr, 137 Cs and other radionuclides in precipitation, air, waters, herbage, milk and radioactive effluents. The environmental contamination is mainly world-wide fall out

  1. Storage of solid and liquid radioactive material

    International Nuclear Information System (INIS)

    Matijasic, A.; Gacinovic, O.

    1961-01-01

    Solid radioactive waste collected during 1961 from the laboratories of the Institute amounted to 22.5 m 3 . This report contains data about activity of the waste collected from january to November 1961. About 70% of the waste are short lived radioactive material. Material was packed in metal barrels and stored in the radioactive storage in the Institute. There was no contamination of the personnel involved in these actions. Liquid radioactive wastes come from the Isotope production laboratory, laboratories using tracer techniques, reactor cooling; decontamination of the equipment. Liquid wastes from isotope production were collected in plastic bottles and stored. Waste water from the RA reactor were collected in special containers. After activity measurements this water was released into the sewage system since no activity was found. Table containing data on quantities and activity of radioactive effluents is included in this report

  2. Evaluation of uncertainty and detection limits in radioactivity measurements

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-10-01

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

  3. Evaluation of uncertainty and detection limits in radioactivity measurements

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  4. The support for a purification of water contaminated with radioactivity, and problems of the radioactivity standard in an emergency situation at the stricken area 2011 Great East Japan Earthquake

    International Nuclear Information System (INIS)

    Maeda, Yoshiaki

    2011-01-01

    The accident of the Fukushima Daiichi Nuclear Station of Tokyo Electric Power Company associated with the Great East Japan Earthquake incurred severe situation, where lifeline was cut off due to the discharge of a large amount of radioactive substances. In particular, the supply of safe foods and drinking water in radiation-polluted areas is urgently required. The authors have been developing up to now Crystal Valley water purifier and CV-Rescue water purifier that can purify well-water unsuitable for drinking due to contamination with toxic substances and produce drinkable water with safety without anxiety. This paper introduces the processes, in which verification test was performed to confirm that the above purifiers can be used for the removal of radioactivity discharged from the Great East Japan Earthquake this time, the validity of these purifiers was clarified, and these purifiers have actually been used for supporting water supply. This paper especially points out that a problem exists in the various standards on radioactivity that were temporarily determined in face of emergency of radiation pollution due to the nuclear power station accident this time. In these standards, the temporary standard on radioactive iodine 131 in drinking water is too high compared with the standards of WHO and those of advanced countries like U.S.A. It also points out the problem that radioactive substances in drinking water have not been removed yet. (O.A.)

  5. Radioactivity Monitoring of the Irish Environment 2003-2005

    International Nuclear Information System (INIS)

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

    2007-05-01

    This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) between 2003 and 2005. This programme aims to assess the exposure of the Irish population to anthropogenic radioactivity in the environment, to review the temporal and geographical distribution of contaminating radionuclides and to maintain systems and procedures which would allow a rapid assessment of environmental contamination to be made in the event of a radiological emergency. Radioactivity is present in the environment due to natural processes, the testing of nuclear weapons in the atmosphere, past nuclear accidents such as that at Chernobyl and the routine licensed 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 anthropogenic radioactivity in the Irish marine environment. The key elements of the monitoring programme implemented by the RPII during the reporting period include; assessment of ambient radioactivity based on measurements of radioactivity in air and 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 miscellaneous ingredients; assessment of levels of radioactivity in the marine environment based on sampling and measurements of seawater, sediment, seaweed, fish and shellfish. The RPII monitored airborne radioactivity at eleven stations located throughout the country. One station is equipped with a high volume sampler, which allows global fallout concentrations to be measured, and one is equipped to detect the presence of the gas krypton-85. Krypton-85 is released into the environment primarily as a result of the reprocessing of nuclear

  6. Internal radiation doses from radioactivity of drinking water in Finland

    International Nuclear Information System (INIS)

    Kahlos, H.; Asikainen, M.

    1980-01-01

    A study of the radioactivity of drinking water in Finland was carried out from 1974 to 1978. Samples were collected from nearly all water supply plants with more than 200 users and from privately dug or drilled wells. This paper considers drinking water as a factor in increasing the natural radiation exposure of the population and estimates the collective and per capita dose rates caused by the 222 Rn present in water. Instead of performing dose calculations, the significance of 226 Ra and uranium is assessed by means of daily intake. The assessment is made for both the whole population and three subgroups using the water from water supply plants and privately dug or drilled wells. (author)

  7. Radioactivity Monitoring of the Irish Environment 2006

    International Nuclear Information System (INIS)

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

    2007-10-01

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

  8. Studies on the behaviour of some radioactive pollutants into soil-fresh water environment

    International Nuclear Information System (INIS)

    Sayed, M.S.

    1989-01-01

    The overwhelming increase in the use of nuclear power plants comes to cover many purposes, such as generating of electricity, desalination of sea water, and producing radioactive isotopes in large quantities. There is no doubt that the continuous increase in the production of radioisotope, presents an outstanding potential health hazard to man and its environment. Many radio-nuclide wastes, may be released to the environment from nuclear research reactors, hospitals, universities etc in large quantities and low radioactive level which can contaminate drinking and underground water, plants, animals and air. The present work includes introduction which is a literature survey of uses of natural minerals and clays in the treatment of low level radioactive wastes and the different chemical methods used for their treatment e.g. co-participation, adsorption chromatography, ion exchange , solvent extraction, coagulation and flocculation etc

  9. Use of naturally occurring helium to estimate ground-water velocities for studies of geologic storage of radioactive waste

    International Nuclear Information System (INIS)

    Marine, I.W.

    1977-01-01

    In a study of the potential for storing radioactive waste in metamorphic rock at the Savannah River Plant near Aiken, South Carolina, the rate of water movement was determined to be about 0.06 m/y by analyzing gas dissolved in the water. The gas contained up to 6 percent helium, which originated from the radioactive decay of natural uranium and thorium in the crystalline rock. The residence time of the water in the rock was calculated to be 840,000 years from the quantity of uranium and thorium in the rock, their rates of radioactive decay, and the quantity of helium dissolved in the water. The estimation of ground-water velocities by the helium method is more applicable to the assessment of a geologic site for storage of radioactive waste than are velocities estimated from packer tests, pumping tests, or artificial tracer tests, all of which require extensive time and space extrapolations

  10. Radioactivity in environmental samples

    International Nuclear Information System (INIS)

    Fornaro, Laura

    2001-01-01

    The objective of this practical work is to familiarize the student with radioactivity measures in environmental samples. For that were chosen samples a salt of natural potassium, a salt of uranium or torio and a sample of drinkable water

  11. Study of the radioactivity of drinking water in the city of Antsirabe using the method of liquid scintillation counting

    International Nuclear Information System (INIS)

    RAKOTOMANGA, H.

    2003-01-01

    The objective of this work is to determine the radioactivity by liquid scintillation counting (LSC) and to study the distribution of radionuclides in drinking water from the Antsirabe region. Optiphase Hisafe 3TM is used to measure gross alpha-beta radioactivity. Radium, radon and the excess of short half-life radionuclides are obtained from MaxilightTM cocktail. Results of measurement of drinking water samples show that : gross alpha-beta activities are between (120±27) Bq.l -1 and (426±47) Bq.l -1 , the radium activities are from (14±2)Bq.l -1 to (78±5) Bq.l -1 , radon activities are from (0.6±0.2)Bq.l -1 to (60±6) Bq.l -1 , short half-life radionuclides activities are between 25±8 Bq.l -1 and 270±27 Bq.l -1 .Annual dose exposure from ingestion of radium-226 is between (2.09 ± 0.32)mSv and (11.03 ± 0.73)mSv. These values are close to the Malagasy standard (5 mSv). The results show that drinking waters from the Antsirabe region contain natural radionuclides. Dose exposure increases if the water is directly ingested after collection. [fr

  12. Measurement of nuclear cross sections using radioactive beams

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  13. Development of radioactive seawater monitors, 1

    International Nuclear Information System (INIS)

    Fukushima, Masanori

    1989-01-01

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

  14. Development of In-situation radioactivity Inspection system

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  15. Development of In-situation radioactivity Inspection system

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-05-15

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

  16. Determination of potassium concentration in salt water for residual beta radioactivity measurements

    International Nuclear Information System (INIS)

    Suarez-Navarro, J.A.; Pujol, Ll.

    2004-01-01

    High interferences may arise in the determination of potassium concentration in salt water. Several analytical methods were studied to determine which method provided the most accurate measurements of potassium concentration. This study is relevant for radiation protection because the exact amount of potassium in water samples must be known for determinations of residual beta activity concentration. The fitting algorithm of the calibration curve and estimation of uncertainty in potassium determinations were also studied. The reproducibility of the proposed analytical method was tested by internal and external validation. Furthermore, the residual beta activity concentration of several Spanish seawater and brackish river water samples was determined using the proposed method

  17. A real-time tritium-in-water monitor for measurement of heavy water leak to the secondary coolant

    International Nuclear Information System (INIS)

    Rathnakaran, M.; Ravetkar, R.M.; Samant, R.K.; Abani, M.C.

    2000-01-01

    The paper describes the development and evaluation of on-line, real-time tritium in water monitor for detection and measurement of heavy water leak to the secondary coolant in a Pressurised Heavy Water Reactor. The detector used for this is a plastic scintillator film, made in the form of sponge and housed in a flow cell which is used for measurement of tritium activity present in heavy water. Two photomultiplier tubes are optically coupled on either face of the flow cell detector and measurement is done in coincidence mode. The sample water is continuously passed through the flow cell detector and a continuous measurement of tritium activity is carried out. It is observed that the impurities in the process water sample are gradually trapped in the flow cell, which affects the transparency of the detector with use. This reduces the sensitivity of the system. In addition, chlorine, which is added in the sample water, to arrest the fungus formation, creates chemiluminescence which interfere the measurement. To improve the sample quality as well as to eliminate the chemiluminescence created by chlorine, sample conditioner consisting of polypropylene candle, activated charcoal and glass fibre filter paper is developed. Polypropylene candle traps particulates above 5 μm pore size, activated charcoal absorbs organic compounds, free chlorine, fungus and turbidity and glass fibre filter paper stops submicron size particles. The measurement is also affected by the interference of dissolved argon-41 in the sample water. A bubbler system developed at BARC is used to strip the dissolved Ar-41 present in the sample which enables the system to measure tritium in presence of this interfering radioactive gas. The microprocessor based electronic system, used in the monitor provides the facility for selection of counting time and thereby improving the counting statistics. Alarm circuit is provided to give timely alarm when the tritium activity concentration exceeds the preset level

  18. Volume reduction and encapsulation process for water containing low level radioactive waste

    International Nuclear Information System (INIS)

    Miller, G.P.; Fox, D.W.; Weech, M.E.

    1982-01-01

    In encapsulating solutions or slurries of radio-active waste within polymeric material for disposal, the water is removed therefrom by adding a water insoluble liquid forming a low boiling azeotrope and evaporating the azeotrope, and then a polymerisable composition is dispersed throughout the dewatered waste and allowed to set. (author)

  19. Radioactive polyethyleneglycol: an intestinal water marker in birds

    International Nuclear Information System (INIS)

    Mongin, P.

    1976-01-01

    Polyethyleneglycol (MW=4000) labeled with 14 C remains in the liquid phase whatever the physical conditions are: dilution-alkalinity or acidity. It does not enter the food particles and is not adsorbed by them. When the animals are in state conditions, a four-day balance study in four laying hens shows, that ingested radioactivity is totally recovered in the feces. PEG- 14 C is a valuable water marker in the bird intestine

  20. Environmental radioactivity in Greenland 1977

    International Nuclear Information System (INIS)

    Aarkrog, A.; Lippert, J.

    1978-07-01

    Measurements of fallout radioactivity in Greenland in 1977 are reported. Strontium-90 (and Cesium-137 in most cases) was determined in samples of precipitation, sea water, vegetation, animals, and drinking water. Estimates are given of the mean contents of 90 Sr and 137 Cs in the human diet in Greenland in 1977. (author)

  1. Error calculations statistics in radioactive measurements

    International Nuclear Information System (INIS)

    Verdera, Silvia

    1994-01-01

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

  2. Environmental radioactivity in Greenland in 1974

    International Nuclear Information System (INIS)

    Aarkrog, A.; Lippert, J.

    1975-07-01

    Measurements of fall-out radioactivity in Greenland in 1974 are reported. Strontium 90 (and Caesium-137 in most cases) was determined in samples of precipitation, sea water, vegetation, animals, and drinking water. Estimates are given of the mean contents of 90 Sr and 137 Cs in the human diet in Greenland in 1974. Three Greenlanders were measured by wholebody counting. (author)

  3. The investigation of enviromental radioactivity background around a pulsed reactor

    International Nuclear Information System (INIS)

    Xiao Tenghui; Zhao Zhongli

    1990-01-01

    The radioactivity background level of enviromental medium around a pulsed reactor for 5 km and external penetrating radioactivity dose level for 10 km are given. mediums measured include air, water, soil, organisms, fallout, etc

  4. The investigation of enviromental radioactivity background around a pulsed reactor

    Energy Technology Data Exchange (ETDEWEB)

    Tenghui, Xiao; Zhongli, Zhao [Southwest Inst. of Nuclear Reactor Engineering, Sichuan, SC (China)

    1990-06-01

    The radioactivity background level of enviromental medium around a pulsed reactor for 5 km and external penetrating radioactivity dose level for 10 km are given. mediums measured include air, water, soil, organisms, fallout, etc.

  5. Measurement of Gross Alpha and Gross Beta Radioactivity of River Yobe, North Eastern Nigeria

    International Nuclear Information System (INIS)

    Abba, H. T.; Sadiq, U.; Adeyemo, D. J.

    2013-01-01

    Measurement of the gross alpha and gross beta radioactivity of River Yobe has been carried out. Fifteen samples of the river water were collected from the farming, fishing, domestic/livestock and control areas along the river and were analyzed using desktop alpha/beta (MPC 2000- DP) counting system. The count results show the average alpha activities in farming, fishing, domestic/livestock and control areas are 0.207±0.082, 0.257±0.13, 0.437±0.315 and 0.237±0.10 Bq L -1 , respectively. The average beta activities in the four areas are 0.813±0.122, 0.308±0.0145, 0.563±0.230 and 0.225±0.0096 Bq L -1 , respectively. The overall results show that the alpha and beta activities in the four areas are far below the practical screening level of radioactivity in drinking water of 0.5 Bq L -1 for alpha and 1 Bq L -1 for beta recommended by CEC-FAO and WHO and therefore may not pose any serious detrimental health side-effects to the public users of the river.

  6. Volume reduction and encapsulation process for water containing low-level radioactive waste

    International Nuclear Information System (INIS)

    Fox, D.W.; Miller, G.P.; Weech, M.E.

    1984-01-01

    Solutions or slurries of waste material in water are dewatered and encapsulated within a polymer for disposal, comprising the operations of removing water therefrom with azeotropic mixture evaporation and encasing the dewatered waste residue in an organic polymer. The method and system disclosed are especially useful for the safe disposal of radioactive waste

  7. Aerial mapping of radioactive contamination in the vicinity of water streams

    International Nuclear Information System (INIS)

    Dedacek, K.

    1993-01-01

    The results of aerial measurement of the natural radioactivity of K, U, and Th and the radioactivity of 137 Cs in some rivers are reported. A 256-channel gamma spectrometer equipped with an NaI(Tl) scintillation crystal 33.6 litres in volume was used. The apparatus has been installed in an AN-2 airplane. The measurement is accomplished at 80 m heights and airplane velocities of 120 to 140 km/h. (Z.S.)

  8. Environmental radioactivity surveillance programme 1988-89

    International Nuclear Information System (INIS)

    Sequeira, S.; Pollard, D.; Hayden, E.; Dunne, B.; Colgan, P.A.; Cunningham, J.D.

    1990-06-01

    The Nuclear Energy Board measures radionuclides in air, rainwater, total fallout, drinking water supplies and milk as part of its programme to monitor radioactivity in the Irish environment. The report presents the results of measurements made during 1988 and 1989

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

    African Journals Online (AJOL)

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

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  11. Natural radioactivity in private water supplies in Devon

    International Nuclear Information System (INIS)

    Talbot, D.; Davis, J.; Rainey, M.

    2000-01-01

    This report details a study of the occurrence of natural radioactivity in private water Supplies in West Devon. Supplies sourced from wells, springs boreholes and a small number surface supplies were sampled. The findings of a laboratory simulation of the radon content in drinks such as tea, coffee and squash are also presented. Of supplies sampled in phase one of the work approximately 8% of tap water and 9% of samples directly from the supply contained radon at concentrations exceeding the draft European Union Commission Recommendation action level of 1000 Bq/I for individual and public water supplies. In a small number of supplies 238 U is present at levels exceeding 2 μg/I, the World Health Organisation (WHO) provisional guideline value for uranium in drinking water. The final aspect of the study looked at seasonal variation in the radon content of selected supplies. This showed considerable variability in radon concentration over the course of a week and between studies carried out several months apart. (author)

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

    International Nuclear Information System (INIS)

    1983-01-01

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

  13. Development of alpha radioactivity measurement using ionized air transportation technology

    International Nuclear Information System (INIS)

    Kanemoto, Shigeru; Naito, Susumu; Sano, Akira; Sato, Mitsuyoshi; Fukumoto, Masahiko; Miyamoto, Yasuaki; Nanbu, Kenichi; Takahashi, Hiroyuki

    2005-01-01

    Alpha radioactivity Measurement using ionized Air Transportation technology (AMAT) is developed to measure alpha contaminated wastes with large and complex surfaces. An outline of this project was described in this text. A major problem of AMAT technology is that the theoretical relation between alpha radioactivity and observed ion current is unclear because of the complicated behavior of ionized air molecules. An ion current prediction model covering from ionization of air molecules to ion detection was developed based on atmospheric electrodynamics. This model was described in this text, too. (author)

  14. The Procedures for Transit of Ships Carrying Radioactive Materials in Regional Waters and Sea Ports of Egypt

    International Nuclear Information System (INIS)

    Rahman, F.A.; Riad, N.

    2005-01-01

    According to the Egyptian Legislation related to the safe transport of radioactive materials, a license is required for transit of ships carrying radioactive materials in the Egyptian territorial water and sea harbors of Egypt including Suez Canal. The License is granted, upon a written application to NCNSRC-AEA. All the procedures and conditions for granting the license have been developed according to the International and Egyptian Legislation. The procedures for transit of ships carrying radioactive material in Suez Canal are also constructed. The NCNSRC-AEA experts are entitled to accept or refuse the transit of ships carrying radioactive material in the Egyptian territorial water and its sea harbors including Suez Canal according to the national and international regulations

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

    International Nuclear Information System (INIS)

    Bambang-Purwanto

    2000-01-01

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

  16. 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.

  17. Naturally occurring radioactive elements, arsenic and other metals in drinking water from private wells

    International Nuclear Information System (INIS)

    Ek, Britt-Marie; Thunholm, Bo; Oestergren, Inger; Falk, Rolf; Mjoenes, Lars

    2008-04-01

    Approximately 50 % of all drinking water is extracted from groundwater. For private supply of drinking water almost 100 % emanates from groundwater. For approximately 1.2 of the 9 million Swedish citizens, private wells are the primary water source where 700 000 get their water from wells drilled in the bedrock. Radioactive elements and metals that occur naturally in the bedrock can be found in the well water. The radioactive elements include radon-222 ( 222 Rn), uranium (U), radium-226 ( 226 Ra) as well as polonium-210 ( 210 Po) and lead-210 ( 210 Pb), which are long-lived progeny of radon. In 2001 SGU and SSI initiated a collaboration to investigate the occurrence of radioactive elements and metals in water from private wells. Data sampling and analysis was completed in 2006. The aim of the project was to map the occurrence of radioactive elements in drinking water from private wells and to estimate their respective dose contribution. Another aim was to map metals and other elements in the water, to study temporal variations and possible co-variations between analysed elements. Sampling was conducted in a random fashion throughout the country. However, in regions where bedrock and soils are known to show enhanced concentrations of radioactive elements and arsenic the sampling density was increased. The analyses comprises: total beta activity, total alpha activity, radium-226, radon-222, uranium, aluminium, chloride, calcium, vanadium, chromium, iron, manganese, cobalt, nickel, copper, zink, arsenic, strontium, molybdenum, cadmium, barium, lead, thorium, boron, sodium, manganese, potassium, silica, alkalinity, sulfate, fluoride, phosphate, nitrate, pH and electric conductivity. In a few cases chemistry analyses of polonium-210 and lead-210 have been done. It was observed that the south-western part of Sweden, with exception for granite areas in the county of Bohuslaen, has relatively low concentrations of natural radioactive elements in the drinking water. The

  18. Standard criteria for disposal of liquid radioactive wastes from nuclear power plants into surface waters (river systems)

    International Nuclear Information System (INIS)

    Pisarev, V.V.; Tsybizov, I.S.

    1976-01-01

    Radioactive products discharge into natural water streams results in the necessity to regulate nuclear power plant discharges to ensure radiation safety (RS) for population using a river and surrounding river territory. To ensure RS it is necessary to set scientific-founded standards of permissible discharge level of liquid radioactive wastes (LRW) from nuclear power plant assuring observance of hygienic requirements for surface water puring. Volume of permissible LRW discharge into river systems must be set both with provision for concrete physical-geographycal conditions, specficity of utilizing the river and river valley and social-economical peculiarities of crtical population groups. The value of permissible LRW discharge into river systems is determined by three criterion groups: radiological, ecological and hydrological ones. By means of radiological group the internal and external irradiation doses for the whole body and its separate organs are set and RS of population is determined. Ecological criteria include a number of parameters (coefficients of accumulation, distribution and transition) determining quantitative ratios between radioactive element contents in water and separate links of biological chains: soil/water, fish/water, vegetables/water and others. Hydrological criteria determine the degree of waste dilution in rivers, control radioactive contamination of flood-lands areas and in common with ecological criteria determine radionuclide contents in soil and food products. A method of determining average annual values of LRW dilution in river waters is presented [ru

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  20. Alpha radioactivity measurement technology with ionized air type measurement. Applicability evaluation to verification of the clearance level

    International Nuclear Information System (INIS)

    Mita, Yutaka; Matsumura, Toshihiro; Yokoyama, Kaoru; Sugitsue, Noritake

    2008-10-01

    The purpose of this test is to evaluate the applicability of the clearance level measuring system by Ionized Air Type Measurement after decontaminated by sulfuric acid sample. In Ningyo-toge Environmental Engineering Center. The equipment and radioactive waste which were contaminated with uranium are generated so much in future dismantling stage. In our plan, some of equipments and radioactive waste are contaminated to a clearance level, and cut down on decommission and disposal expense. This plan needs the alpha-rays measurement technology of the very low level. We think that ionized Air transfer measurement technology is promising as of clearance verification technology. The ionized Air transfer measurement technology applied to the Ionized Air Type Measurement can measure plan radioactivity of a very low level. Moreover, as compared with a direct survey, there is the merit which can be measured in a short time. However ionized Air transfer measurement technology is new technology. Therefore, there is almost no measurement track record. Furthermore, the date about the influence of a background, a detection limit, measurement performance, and reliability is insufficient. So, this measurement test estimated applicability as clearance level verification of an Ionized Air Type Measurement. (author)

  1. Radioactive Aerosol Size Distribution Measured in Nuclear Workplaces

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  2. 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).

  3. 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).

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

    International Nuclear Information System (INIS)

    2007-01-01

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

  5. Methods of measuring radioactivity in the environment

    Science.gov (United States)

    Isaksson, Mats

    In this thesis a variety of sampling methods have been utilised to assess the amount of deposited activity, mainly of 137Cs, from the Chernobyl accident and from the nuclear weapons tests. Starting with the Chernobyl accident in 1986 sampling of air and rain was used to determine the composition and amount of radioactive debris from this accident, brought to southern Sweden by the weather systems. The resulting deposition and its removal from urban areas was than studied through measurements on sewage sludge and water. The main part of the thesis considers methods of determining the amount of radiocaesium in the ground through soil sampling. In connection with soil sampling a method of optimising the sampling procedure has been developed and tested in the areas of Sweden which have a comparatively high amount of 137Cs from the Chernobyl accident. This method was then used in a survey of the activity in soil in Lund and Skane, divided between nuclear weapons fallout and fallout from the Chernobyl accident. By comparing the results from this survey with deposition calculated from precipitation measurements it was found possible to predict the deposition pattern over Skane for both nuclear weapons fallout and fallout from the Chernobyl accident. In addition, the vertical distribution of 137Cs has been modelled and the temporal variation of the depth distribution has been described.

  6. In-situ gamma spectroscopic measurement of natural waters in Bulgaria

    International Nuclear Information System (INIS)

    Manushev, B.; Mandzhukov, I.; Tsankov, L.; Boshkova, T.; Gurev, V.; Mandzhukova, B.; Kozhukharov, I.; Grozev, G.

    1983-01-01

    In-situ gamma spectrometric measurements are carried out to record differences higher than the errors of measurement in the gamma-field spectra in various basins in Bulgaria - two high mountain lakes, dam and the Black sea. A standard scintillation gamma spectrometer, consisting of a scintillation detector ND-424 type, a channel analyzer NP-424 and a 128 channel Al-128 type analyzer, has been used. The sensitivity of the procedure used is sufficient to detect the transfer of nuclides by dissolution from rocks, forming the bottom and the water-collecting region of the water basin. The advancement of the experimental techniques defines the future use of the procedure. In-situ gamma spectrometric determination may be used in cases of continuous and automated control of the radiation purity of the cooling water in atomic power plants or the water basins located close to such plants and of radioactive contamination of the sea and ocean water

  7. Uranium and radium geochemistry. Radioactive disequilibrium in natural waters

    International Nuclear Information System (INIS)

    Beaucaire, C.

    1987-09-01

    Rock-water interactions play a primary part in uranium-series disequilibrium either by different chemical behavior or by recoiling alpha emitting nuclei in solution. Three series of thermal water containing CO 2 (Vichy, Vals and Cezallier) and one from Lodeve uranium deposit are studied to define parameters (pH, Eh, pCO 2 , T,...) controlling studied nuclei. For U complexation by carbonates is in competition with redox conditions. Ra is coprecipitated by barium. For thermal waters keeping their deep characteristics there is a low disequilibriums 234 U- 238 U between 1 and 2. On the contrary important disequilibrium (up to 12) in Vichy Saint Yorre water are due to secondary remobilization. In the same way for these waters 234 U and 226 Ra are correlated. Then leaching is essential for the radioactive disequilibrium but alpha recoil of 234 Th is of secondary importance in this case [fr

  8. Measuring and modeling water imbibition into tuff

    International Nuclear Information System (INIS)

    Peters, R.R.; Klavetter, E.A.; George, J.T.; Gauthier, J.H.

    1986-01-01

    Yucca Mountain (Nevada) is being investigated as a potential site for a high-level-radioactive-waste repository. The site combines a partially saturated hydrologic system and a stratigraphy of fractured, welded and nonwelded tuffs. The long time scale for site hydrologic phenomena makes their direct measurement prohibitive. Also, modeling is difficult because the tuffs exhibit widely varying, and often highly nonlinear hydrologic properties. To increase a basic understanding of both the hydrologic properties of tuffs and the modeling of flow in partially saturated regimes, the following tasks were performed, and the results are reported: (1) Laboratory Experiment: Water imbibition into a cylinder of tuff (taken from Yucca Mountain drill core) was measured by immersing one end of a dry sample in water and noting its weight at various times. The flow of water was approximately one-dimensional, filling the sample from bottom to top. (2) Computer Simulation: The experiment was modeled using TOSPAC (a one-dimensional, finite-difference computer program for simulating water flow in partially saturated, fractured, layered media) with data currently considered for use in site-scale modeling of a repository in Yucca Mountain. The measurements and the results of the modeling are compared. Conclusions are drawn with respect to the accuracy of modeling transient flow in a partially saturated, porous medium using a one-dimensional model and currently available hydrologic-property data

  9. A survey of natural radioactivity in drinking water; Kartlaeggning av naturligt radioaktiva aemnen i dricksvatten

    Energy Technology Data Exchange (ETDEWEB)

    Falk, Rolf; Mjoenes, Lars [Swedish Radiation Protection Authority, Stockholm (Sweden); Ek, Britt-Marie [SGU, Uppsala (Sweden); Appelblad, Petra [Swedish Defence Research Agency, Stockholm (Sweden); Erlandsson, Bitte; Svensson, Kettil [National Food Administration, Uppsala (Sweden); Hedenberg, Gullvy [Svenskt Vatten AB, Stockholm (Sweden)

    2004-11-01

    A survey of uranium and other radioactive material in drinking water from municipal water works has been conducted. Water samples from water works with ground water from 256 communities were analysed. In EUs Drinking Water Directive (98/83/EG) a reference level of 0.1 mSv/year is set for Total Indicative Dose (TID). Levels above 0.1 mSv/year is judged as 'fit for consumption with reservations' in the Swedish drinking water regulations. The radiation dose from uranium and other radionuclides in tap water is low. An estimated dose exceeding 0.1 mSv/year was found in only two samples. Half the amount of all tap water from municipal water work plants use surface water, which has low levels of radioactivity. Nine water works show a uranium concentration above 15 microgram per litre ({mu}g/l). There is no reference level for uranium in drinking water neither in the EU nor in Sweden but the WHO recommend a reference level of 15 ({mu}g/l)

  10. Distribution of radioactive "1"3"7Cs and "1"3"4Cs in river water and bottom sand for major rivers at Minami-Soma City in Fukushima

    International Nuclear Information System (INIS)

    Kajimoto, Tsuyoshi; Endo, Satoru; Shizuma, Kiyoshi; Naganuma, Takeshi

    2013-01-01

    A nuclear power plant accident, which occurred on March 11, 2011, caused severe radioactive contamination in Fukushima. We initiated an environmental radioactive survey in Minami-Soma City the following October. The city is located approximately 10-40 km north of the TEPCO's Fukushima Daiichi Nuclear Power Plant. The study reported here involves an environmental radioactive survey conducted along three rivers and their tributary streams. Water and bottom sands were collected from four to six sampling locations along each river. Water samples (1 L) were dried on thin Teflon sheets, and gamma-ray measurements were performed with a well-type Ge detector. Sand samples were homogenized after drying, and approximately 50 g were measured for gamma-rays with a low-background coaxial-type Ge detector. The Cs concentrations ("1"3"7Cs+"1"3"4Cs) were determined to be 10,000-20,000 Bq/kg in the bottom sand collected from the upper reaches of the rivers, whereas the concentrations measured from samples collected near coastal down reaches were measured at about 200 Bq/kg. The Cs concentrations measured in river water were about 0.8 Bq/L in the upper reaches of the rivers and 0.3 Bq/L in the lower reaches, indicating that the Cs concentration in water is quite low. It is necessary to study the behavior of the contaminants in the upper reaches of the river system, and determine if they will move to the down stream area hereafter. (author)

  11. Distribution of radioactive "1"3"7Cs and "1"3"4Cs in river water and bottom sand for major rivers at Minami-Soma City in Fukushima

    International Nuclear Information System (INIS)

    Kajimoto, Tsuyoshi; Endo, Satoru; Shizuma, Kiyoshi; Naganuma, Takeshi

    2012-01-01

    A nuclear power plant accident, which occurred on March 11, 2011, caused severe radioactive contamination in Fukushima. We initiated an environmental radioactive survey in Minami-Soma City the following October. The city is located approximately 10-40 km north of the TEPCO's Fukushima Daiichi Nuclear Power Plant. The study reported here involves an environmental radioactive survey conducted along three rivers and their tributary streams.Water and bottom sands were collected from four to six sampling locations along each river. Water samples (1 L) were dried on thin Teflon sheets, and gamma-ray measurements were performed with a well-type Ge detector. Sand samples were homogenized after drying, and approximately 50 g were measured for gamma-rays with a low-background coaxial-type Ge detector. The Cs concentrations ("1"3"7Cs+"1"3"4Cs) were determined to be 10,000-20,000 Bq/kg in the bottom sand collected from the upper reaches of the rivers, whereas the concentrations measured from samples collected near coastal down reaches were measured at about 200 Bq/kg. The Cs concentrations measured in river water were about 0.8 Bq/L in the upper reaches of the rivers and 0.3 Bq/L in the lower reaches, indicating that the Cs concentration in water is quite low. It is necessary to study the behavior of the contaminants in the upper reaches of the river system, and determine if they will move to the down stream area hereafter. (author)

  12. Radioactivity Monitoring of the Irish Environment 2009

    International Nuclear Information System (INIS)

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

    2010-12-01

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

  13. Radioactivity Monitoring of the Irish Environment 2008

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  14. Processing method for radioactive liquid waste

    International Nuclear Information System (INIS)

    Yasumura, Keijiro

    1991-01-01

    Drainages, such as water after used for washing operators' clothes and water used for washing hands and for showers have such features that the radioactive concentration is extremely low and detergent ingredients and insoluble ingredients such as waste threads, hairs and dirts are contained. At present, waste threads are removed by a strainer. Then, after measuring the radioactivity and determining that the radioactivity is less than a predetermined concentration, they are released to circumstances. However, various organic ingredients such as detergents and dirts in the liquid wastes are released as they are and it is not preferred in respect of environmental protection. Then, in the present invention, activated carbon is filled in a container orderly so that the diameter of the particles of the activated carbon is increased in the upper layer and decreased in the lower layer, and radioactive liquid wastes are passed through the container. With such a constitution. Both of soluble substances and insoluble substances can be removed efficiently without causing cloggings. (T.M.)

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

    Directory of Open Access Journals (Sweden)

    O. A. Bezshyyko

    2011-12-01

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

  16. Monitoring radioactive contamination in food, water sediments and other environmental samples in Egypt. Final report for the period 1 October 1992 - 31 July 1996

    International Nuclear Information System (INIS)

    Farouk, M.

    1996-09-01

    A detailed survey for radioactivity content was carried out in the following materials: 1) Raw (from quarries) and finished (e.g., bricks, cement, ceramic tiles) building materials originating in central Egypt; 2) soils and plants (particularly cattle fodder) in upper Egypt, including soil to plant transfer factors; 3) water, bottom sediments and shore sediments from Lake Nasser and its immediate surroundings; 4) water, fish, bottom and shore sediments from the Lake Quaran region; 5) soil, plant, drinking water, bottom and shore sediments from the Sinai Peninsula. The concentrations of the following radionuclides were measured: K-40, Cs-137, Ra-226, Th-232 and U-238. Samples were sealed in Marinelli beakers for 4 weeks to allow complete ingrowth of Rn-222 and daughters. High resolution gamma-ray spectrometry was used to measure K-40 and Cs-137 directly and Ra-226, Th-232 and U-238 indirectly by means of daughter radioactivities. In addition, uranium measurements were also made after chemical decomposition of selected samples by laser fluorimetry and by alpha spectrometry techniques. The results were used for establishing a database of baseline radioactivity levels, for evaluating average doses to the population, for comparison with similar materials from other countries and for determining soil to plant transfer factors which can be used to estimate internal doses to the population. (author). Refs, figs, tabs

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-10-01

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

  18. Environmental radioactivity in Greenland in 1978

    International Nuclear Information System (INIS)

    Aarkrog, A.; Hansen, H.; Lippert, J.

    1979-07-01

    Measurements of fallout radioactivity in Greenland in 1978 are reported. Strontium-90 (and Cesium-137 in most cases) was determined in samples of precipitation, sea water, vegetation, animals, and drinking water. Tritium was determined in samples of drinking water. Estimates are given of the mean contents of 90 Sr and 137 Cs in the human diet in Greenland in 1978. (author)

  19. Simple method of measuring pulmonary extravascular water using heavy water

    Energy Technology Data Exchange (ETDEWEB)

    Basset, G; Moreau, F; Scaringella, M; Tistchenko, S; Botter, F; Marsac, J

    1975-11-20

    The field of application of the multiple indicators dilution method in human pathology, already used to study pulmonary edema, can be extended to cover the identification and testing of all conditions leading to increase lung water. To be really practical it must be simple, fast, sensitive, inexpensive and subject to repetition; the use of non-radioactive tracers is implied. Indocyanine Green and heavy water were chosen respectively as vascular and diffusible indicators. Original methods have been developed for the treatment and isotopic analysis of blood: mass spectrometric analysis of aqueous blood extracts after deproteinisation by zinc sulphate then rapid distillation of the supernatant under helium; infrared analysis either of acetone extracts from small blood samples (100..mu..litre) or of blood itself in a continuous measurement. The infrared technique adopted has been used on rats and on men in normal and pathological situations. The results show that the method proposed for the determination of pulmonary extravascular water meets the requirements of clinicians while respecting the patients' safety, and could be generalized to other organs.

  20. Latest movements on waste recycling measures. Dynamic state and risk assessment of radioactive cesium in disaster waste

    International Nuclear Information System (INIS)

    Fujikawa, Yoko

    2012-01-01

    A large amount of radioactive substances were discharge by the catastrophe of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company. From the analysis of the dynamic state of radioactive substances in the environment, the radioactive cesium in the land and freshwater environment is distributed much in soil and freshwater sediment (solid phase) rather than in aqueous phase, even though the distribution depends on the composition of liquid phase water and adsorption objects. From this fact, the problem of radioactive cesium in the living environment can be summarized in the problem of solid system disaster waste in the end, such as soil, sediment, sludge, and waste. As for the current situation of disaster waste, this paper introduces the present state of disaster waste, in which treatment operations are not smoothly proceeding due to the large amount of waste, and difficulty in the classification work of waste and incineration treatment work. Regarding the wide-area treatment measures, there are various problems such that some municipalities are cooperative and some municipalities are hesitant about the acceptance of waste with radioactive contamination. As an example, this paper introduces the reviewing process and reference information in Osaka Prefecture regarding the acceptance of waste. (O.A.)

  1. Investigation of environmental radioactivity around the mooring port of the atomic power ship 'Mutsu'

    International Nuclear Information System (INIS)

    Tanigawa, Yoshiro

    1977-01-01

    The environmental radio activity around the mooring port of the atomic power ship ''Mutsu'' has been investigated as the continuation of work in the last year. On the continuous measurements at the three monitoring posts in the port premises and at the three monitoring stations in Mutsu City, and on the measurements by monitoring cars and ships, no abnormality has been observed on the spatial radioactive dose-rate also in this year. No abnormality has also been detected on the radioactivity in sea water measured by the sea-water monitor. On the measurements of β-radioactivity of surface soil, river-bed soil, river water, drinking water and milk, there was no difference from that in the last year. The total β-radioactivity measurement by the low background 2 π gas flow counter and the nuclide analysis by the γ-spectrometer with a Ge (Li) semiconductor detector showed no abnormality. Although 137 Cs was detected in almost all samples, this isotope seemed to be the fallout from nuclear explosion experiments, and the activity was almost same as the values in various districts in Japan. (Kobatake, H.)

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

    International Nuclear Information System (INIS)

    Grabowski, D.; Kurowski, W.

    1990-01-01

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

  3. First measurements of the radioactivity in atmospheric precipitations

    Energy Technology Data Exchange (ETDEWEB)

    Santomauro, L; Cigna, A

    1953-01-01

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

  4. National audit of radioactivity measurements in Nuclear Medicine Centres

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  5. Radioactive Sources in Medicine: Impact of Additional Security Measures

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  6. Activities of Hydrometeorologic Institute of Serbia - Belgrade, during the case of radioactive pollution of environment caused by the accident of nuclear power plant 'Chernobyl' in 1986

    International Nuclear Information System (INIS)

    Jovanovic, Dj.

    2002-01-01

    The programme of 'Systematic testing of water quality' performed by Hydrometeorologic Institute of Serbia - Belgrade includes the measurement of total beta radioactivity on 33 sampling points. The measurement of total beta radioactivity is performed with instrument 'Lola - 4' produced by 'Institute for Nuclear Science - Vinca'. During the accident of Nuclear Power Plant 'Chernobyl' in 1986 arose the need to investigate the influence of this case on the environment of Belgrade and Serbia. In that respect a series of measurement of total beta radioactivity of rain water, surface waters, tap water and air were performed. Those measurements showed an increase of radioactivity of river waters. River Sava had radioactivity of 3,4 Bq/l (0,08 Bq/l in 1 9850 and river Danube 3-5 Bq/l (0,09 Bq/l in 1 985). High values of radioactivity were measured in the waters of highland accumulation lakes over 30 Bq/l. Rain water showed it's maximum of 52 Bq/l on 1 st and 2nd May l986 and it drooped to 0,3 Bq/l until 5th of June. Tap water showed it's maximum of 35,2 Bq/l on 12th May and it was reduced to 1 ,0 Bq/l on 2nd of June. Radioactivity of air showed it's maximum of 2,64 Bq/m 3 in the period 1 -3 May and in the period 5-8 May, 1 . - 1 ,57 Bq/m 3 . Measurement of river water radioactivity on 33 regular sampling points at the end of the year 1 986 showed that was no increase in comparison with the same measurements in 1 985. All mentioned results of the radioactivity of river waters and the waters of highland accumulations used to fall into ranges predicted by the model of the radioactive pollution distribution developed on the Imperial College -London. (author)

  7. Radioactivity of drinking waters from regions exposed to depleted uranium ammunition bombing in 2003 end 2004

    International Nuclear Information System (INIS)

    Tanaskovic, I.; Pantelic, G.; Vuletic, V.; Eremic Savkovic, M.; Javorina, L.J.

    2006-01-01

    Due to the military application of the depleted uranium in our country, the problem of its radioactivity and hemo toxicity is actualized. The locations verified to be contaminated by depleted uranium ammunition were at the South part of Serbia (Pljackovica, Bratoselce, Borovac and Reljan). The soluble forms of uranium could translocated and dispersed from soils and sediments into surface waters and groundwater. The environmental presence of depleted uranium is considered as potential threat to human health. The study presents the results of radiological safety analysis of drinking water in 2003 and 2004. All samples were analyzed by gamma spectrometry and measurements of alpha and beta activity. (authors)

  8. Natural radioactivity in some drinking water sources of coastal, northern, eastern and AlJazera regions in Syria

    International Nuclear Information System (INIS)

    Al-Masri, M. S.; Byrakdar, E.; Amin, Y.; Abu Baker, S.

    2003-01-01

    Naturally occurring radionuclides in drinking water sources of coastal, northern, eastern and AlJazera regions in Syria have been determined. Samples were collected during the year of 2000 at two periods from the main water sources, from which water being transported for drinking or from houses. Results have shown that most concentrations of the measured naturally occurring radionuclides ( 222 Rn, 222 Ra, 210 Po, 234 U, 238 U) were within the natural levels and below the higher permissible limits of International Organizations. In addition, variations in concentrations from region to another have been observed; these variations may be due to differences in geological formations and water sources (well, spring, surface water). Moreover, the obtained data in this study and other published data for other regions can be used for establishing the radiation map for natural radioactivity in drinking water in Syria. (author)

  9. Analysis of radioactive strontium

    International Nuclear Information System (INIS)

    1977-01-01

    In environmental radiation survey, radioactive strontium has been analyzed in compliance with the manual ''Analyzing methods for radioactive strontium'' published in 1960 by the Science and Technology Agency, Japan, and revised in 1963. However, in a past decade, progress and development in analyzing methods and measuring equipments have been significant, therefore the manual was revised in 1974. Major revisions are as follows. (1) Analysis of 90 Sr with long half life was changed to the main theme and that of 89 Sr with short half life became a subordinate one. (2) Measuring criteria and sampling volume were revised. (3) Sample collection method was unified. (4) Analyzing method for soil was improved to NaOH-HCl method which has good recovery rate. (5) 90 Y separation method of simple operation was added for sea water analysis besides EDTA and fuming nitric acid methods. (6) Flame spectrometry for quantitative analysis of stable strontium was revised to atomic absorption spectrometry. The contents of the manual comprises 11 chapters describing introduction, measuring criteria for 90 Sr ( 89 Sr), rain and dust, land water, sea water, soil, sea bottom and river bottom sediments (changed from human urine and human bones), crops, milk (the previous one chapter was divided into two), marine organisms, and everyday foods, respectively. (Wakatsuki, Y.)

  10. Weak Interaction Measurements with Optically Trapped Radioactive Atoms

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  11. 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

  12. Natural radioactivity product from coal burning in PLTU Pacitan

    International Nuclear Information System (INIS)

    Sukirno; Sri Murniasih; Rosidi; Sutanto WW

    2016-01-01

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

  13. Modelling of Transport of Radioactive Substances in the Primary Circuit of Water Cooled Reactors

    International Nuclear Information System (INIS)

    2012-03-01

    Since the beginning of the development of water cooled nuclear power reactors, it has been known that the materials in contact with the water release some of their corrosion products into the water. As a consequence, some of the corrosion products are neutron-activated while in the reactor core and then create a gamma radiation field when deposited outside the core. These radiation fields are hazardous to the inspection, maintenance and operating staff in the power plant and therefore must be minimized. Many methods have been developed to control these radiation fields, such as the proper selection of materials and surface finishing technologies at the design stage, operating and shutdown water chemistry optimization, and the application of different decontamination methods. The need to understand the causes of this radioactivity transport has resulted in many mathematical models to describe the transport, irradiation and deposition of the radioactive corrosion products out of the core. Early models were empirical descriptions of the transport, irradiation and deposition steps, and these models allowed analytical solution of the resulting differential equations. As the mechanisms responsible for radioactivity transport gradually became better understood, more precise models of the mechanisms were made. Computer codes to solve the equations describing these models are necessary. Accurate codes are invaluable design tools for carrying out cost-benefit analysis during materials selection, for estimating shielding thicknesses and for evaluating water chemistry specifications, for example. Such codes are also useful in operating plants to predict radiation fields at specific locations where shielding may be required during a maintenance shutdown, for example, when control of radiation dose to staff is essential. To complement the previous work of the International Atomic Energy Agency (IAEA) to improve the mechanistic understanding of radioactivity transport, a

  14. International measures needed to protect metal recycling facilities from radioactive materials

    International Nuclear Information System (INIS)

    Mattia, M.; Wiener, R.

    1999-01-01

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

  15. Quality assurance for radioactive measurement in nuclear medicine

    International Nuclear Information System (INIS)

    2006-01-01

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

  16. Efficient Removal of Cationic and Anionic Radioactive Pollutants from Water Using Hydrotalcite-Based Getters.

    Science.gov (United States)

    Bo, Arixin; Sarina, Sarina; Liu, Hongwei; Zheng, Zhanfeng; Xiao, Qi; Gu, Yuantong; Ayoko, Godwin A; Zhu, Huaiyong

    2016-06-29

    Hydrotalcite (HT)-based materials are usually applied to capture anionic pollutants in aqueous solutions. Generally considered anion exchangers, their ability to capture radioactive cations is rarely exploited. In the present work, we explored the ability of pristine and calcined HT getters to effectively capture radioactive cations (Sr(2+) and Ba(2+)) which can be securely stabilized at the getter surface. It is found that calcined HT outperforms its pristine counterpart in cation removal ability. Meanwhile, a novel anion removal mechanism targeting radioactive I(-) is demonstrated. This approach involves HT surface modification with silver species, namely, Ag2CO3 nanoparticles, which can attach firmly on HT surface by forming coherent interface. This HT-based anion getter can be further used to capture I(-) in aqueous solution. The observed I(-) uptake mechanism is distinctly different from the widely reported ion exchange mechanism of HT and much more efficient. As a result of the high local concentrations of precipitants on the getters, radioactive ions in water can be readily immobilized onto the getter surface by forming precipitates. The secured ionic pollutants can be subsequently removed from water by filtration or sedimentation for safe disposal. Overall, these stable, inexpensive getters are the materials of choice for removal of trace ionic pollutants from bulk radioactive liquids, especially during episodic environmental crisis.

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

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  18. Current state of the technology measures of accident from contamination by the radioactive substance. 2. Overall management of radioactive material contaminated waste in the off-site

    International Nuclear Information System (INIS)

    Endo, Kazuto

    2015-01-01

    This paper focuses on the disposal standards of the Act on Special Measures Concerning the Handling of Environmental Pollution by Radioactive Materials by the NPS Accident Associated with the Tohoku District - off the Pacific Ocean Earthquake that Occurred on March 11, 2011, which was promulgated on August 30, 2011 as a framework for the management of radioactively contaminated waste and removed soil. It stipulated that the byproducts of water/sewage treatment, major ash, and fly ash up to the radiation of 8,000 Bq/kg can be reclaimed in land. However, fly ash has a limit in landfill conditions, due to very high leaching rate of radioactive cesium. Later, incineration ash with between 8,000 Bq/kg and 100,000 Bq/kg became possible to be buried at disposal sites corresponding to leachate-controlled type. The specified waste with 100,000 Bq/kg or above is reclaimed in land with specified method at a site provided with outer peripheral partition facilities and cut off from the public water and groundwater. In Fukushima Prefecture, the specified waste with 100,000 Bq/kg or above is to be stored in provisional storage facilities, and later sent to final disposal sites outside the prefecture after the volume has been reduced. The decontaminated waste composed of vegetation is covered totally with a breathable waterproof sheet, and stored at a provisional yard. According to the characteristics of each provisional storage yard, there are needs for patrol and management. (A.O.)

  19. Analysis of water content in salt deposits: its application to radioactive waste storage

    International Nuclear Information System (INIS)

    Cuevas Muller, C. de la.

    1993-01-01

    The salt deposits as radioactive storage medium are analyzed. This report studies the physical-chemical characteristics of water into salts deposits, its implications for the safety of the repository, and the transport water release mechanism. The last part analyzes the geochemical numerical data of correlation analysis, geostatistics analysis and interpretation of statistical data

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

    International Nuclear Information System (INIS)

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

    1999-01-01

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

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

    International Nuclear Information System (INIS)

    Oktay Baykara; Mahmut Dogru; Firat University, Elazig

    2010-01-01

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

  2. Environmental radioactivity in Greenland in 1976

    International Nuclear Information System (INIS)

    Aarkrog, A.; Lippert, J.

    1977-07-01

    Measurements of fall-out radioactivity in Greenland in 1976 are reported. Strontium-90 (and Caesium-137 in most cases) was determined in samples of precipitation, sea water, vegetation, animals, and drinking water. Estimates are given of the mean contents of 90 Sr and 137 Cs in the human diet in Greenland in 1976. (author)

  3. Radioactive survey of the environment of the nuclear sites of French Nuclear Board: an overview

    International Nuclear Information System (INIS)

    Robeau, D.; Montjoie, M.; Sauve, A.M.; Laporte, J.; Rahaplen, A.; Alphonse, L.; Huc, C.; Bensimon, C.; Cissoko, G.

    1992-01-01

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

  4. Solid radioactive waste processing system for light water cooled reactor plants

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    Design, construction and performance requirements are given for the operation of the solid radioactive waste processing system for light water-cooled reactor plants. All radioactive or contaminated materials, including spent air and liquid filter elements, spent bead resins, filter sludge, spent powdered resins, evaporator and reverse osmosis concentrates, and dry radioactive wastes are to be processed in appropriate portions of the system. Sections of the standard cover: overall system requirements; equipment requirement; controls and instrumentation; physical arrangement; system capacity and redundancy; operation and maintenance; and system construction and testing. Provisions contained in this standard are to take precedence over ANS-51.1-1973(N18.2-1973) and its revision, ANS-51.8-1975(N18.2a-1975), Sections 2.2 and 2.3. The product resulting from the solid radioactive waste processing system must meet criteria imposed by standards and regulations for transportation and burial (Title 10, Code of Federal Regulations, Part 71, Title 49, Code of Federal Regulations, Parts 100 to 199). As a special feature, all statements in this standard which are related to nuclear safety are set off in boxes

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

    Science.gov (United States)

    Seiler, Ralph L.

    2007-01-01

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

  6. Ultra sensitive sea water radioactivity monitoring system. Autonomous low power consumption equipped with wireless data communication

    International Nuclear Information System (INIS)

    Bonet, H.; Debauche, A.; Lellis, C. de; Adam, V.; Lacroix, J.P.; Put, P. van

    2003-01-01

    Following the recognition of their usefulness by the States and the scientific community, the automatic water monitoring networks were developed again to be able to measure sea water. For that purpose they had to be fully autonomous, have low power consumption (solar panels power supply), use wireless communicating (satellite, GSM, Radio) and be very sensitive (few Bq/m 3 ). It is important to note that radioactivity detection in sea has many constraints: The detection system sensitivity must be very high because of the dilution factor of the ocean. The analysis method has to be adapted: the detection of very low levels of artificial contamination is made difficult due to the natural radioactivity in seawater (i.e., more than 10 kBq of 40 K/m 3 ). The system has to be completely autonomous, 'wireless'. Additional conventional measuring probes must be connected to the system to increase its interest (pH, t deg, salinity, position, meteorology). The system maintenance must be very limited (1/year). Wind and corrosion resistance must be high. The probe must be installed on a buoy. Moreover, some improvements are needed to allow: Amplification Gain drifts due to NaI sensitivity to t deg to be compensated. Net peak area computation in a specific energy range. Interference correction to prevent false alarms due to natural radiation. Very long counting time. (author)

  7. The Safe Transportation of Radioactive Materials

    International Nuclear Information System (INIS)

    Megrahi, Abdulhafeed; Abu-Ali, Giuma; Enhaba; Ahmed

    2008-01-01

    In this paper, we present the essential conditions that should be required for transporting the radioactive materials. We demonstrate the procedure for transporting the radioactive iodine-131 from the Centre of Renewable Energies and Desalination of Water in Tajoura, Libya to Tripoli Medical Center. The safe measures were taken during the process of the transportation of the isotope produced in the centre including dosimetry analysis and the thickness of the container. (author)

  8. Environmental radioactive intercomparison program and radioactive standards program

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-12-31

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

  9. Biological effects of water reservoir radioactive contamination

    International Nuclear Information System (INIS)

    Mashneva, N.I.

    1983-01-01

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

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

    International Nuclear Information System (INIS)

    Kawano, Takao; Nomura, Kiyoshi

    2008-01-01

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

  11. 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

  12. Environmental radioactivity in Hungary

    International Nuclear Information System (INIS)

    Kovacs, J.; Predmerszky, T.

    1979-01-01

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

  13. Radioactivity measurements for some ophthalmic glasses

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  14. Study on radioactive material management plan and environmental analysis of water (I) study of radioactive substance in water management and analyse to eat of the US environmental protection agency (environmental protection agency)

    Energy Technology Data Exchange (ETDEWEB)

    Her, Jae; Min, Hye Lim; Han, Seong Gyu; Lim, Hyun Jong; Jo, Han Byeol; Noh, Young Hoon; Lee, Ho Sun [Dept. of Bio-convergence Engineering, Graduate School of Korea University, Seoul (Korea, Republic of); Kim, Jung Min [Dept. of Radiological Science, Korea University, Seoul (Korea, Republic of); Park, Min Suk [Korea Institute of Radiological and Medical Sciences, Seoul (Korea, Republic of)

    2015-06-15

    The interest of the people in the radioactive contamination of the water has increased significantly and the study about analysis and management of radioactive materials are being actively conducted. And monitoring spots have been expanded to the range of public water as well as drinking water by publishing the rule of drinking water quality standards and examination in the Environmental Enforcement Ordinance No. 553 of Korea. In this study, US EPA was investigated as the foreign advanced cases and the way that is appropriate for the Korea was sought by analyzing investigate radionuclide, interval and management. As a result, in the selection part of investigate radionuclide, geological survey, status of nuclear power plants and the presence of the use of artificial radionuclides of the Korea should be investigated and additionally after the selection of a few radionuclides, the systems should be extended to cover all possible radionuclides by considering radioactive pollution levels in humans may be exposed due to the annual drinking water. In the part of the investigate interval, the concept(MCL, DL) should be set up for preventing concentration detection of above MCL and it needs to the maintenance and management. For example, when the concentration is more than MCL, it should be investigated on a quarterly and when the concentration is lower than MCL, it should be investigated to each different interval and management. And the US EPA divided the management area and make the road map for managing drinking water. The each classified area has been organized to match the state budget and labor force and the individual data have been managed effectively by HPGe, the NaI, TLD and so on.

  15. Investigation of counter-measures in the case of radioactive materials penetration in soils and ground water

    International Nuclear Information System (INIS)

    Sachse, G.; Anders, G.; Puehrer, H.; Stohn, W.

    1975-03-01

    Proceeding from the methods known from hydraulic engineering for the protection of ground waters from penetrating noxious substances, suitable measures for preventing the contamination of ground waters and soils are discussed. Since preventive measures are always of priority, a facility using concrete containers with double walls is considered to be an appropriate method for temporary storage of low and medium activity waste waters. (author)

  16. General radioactive contamination of the biosphere in the Netherlands

    International Nuclear Information System (INIS)

    1980-01-01

    The Coordinating Committee for the Monitoring of Radioactive and Xenobiotic Substances (C.C.R.X.) reports the results of the radioactivity measurements in 1979. These are divided into measurements for the National Measuring Programme and Additional Measurements. The former include the analyses considered essential for an efficacious control of the radioactivity of the biosphere and are performed in air, soil, surface water, milk and in deposition on the surface of the earth. Samples of milk and grass from the surroundings of nuclear reactors have also been analysed. Additional measurements comprises orientating research for specific radionuclides which may be present in some samples, and other investigations which may procure useful information. Results of determinations of radionuclides in some fishery-products from the Dutch waters are given in view of the potential which some marine organisms have to concentrate fission products and especially activated corrosion products from nuclear installations. After a discussion of the results for the National Measuring Programme, a calculation is given of the total artificial radioactivity in the average Dutch diet in 1979 and of the total mean annual radiation dose the Dutch population received as a result of the presence of artificial radionuclides. Different methods studied to calculate the bone dose due to Sr-90 in the diet are outlined as an appendix. (Auth.)

  17. Method for reduction in volume and encapsulation of water-containing weakly radioactive waste

    International Nuclear Information System (INIS)

    Fox, D.W.; Miller, G.P.; Weech, M.E.

    1982-01-01

    Solutions and slurries of waste material in water are dehydrated and enclosed in a polymerizate for final storage. The water is removed as an azeotropic mixture and the dehydrated waste residue is then enclosed in an organic polymerizate. The method and system disclosed in this patent claim are particularly suitable for safe removal of radioactive waste. (orig.) [de

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

    Energy Technology Data Exchange (ETDEWEB)

    Perot, B

    1997-12-31

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

  19. Disposal of radioactive waste arising from water treatment: Recommendations for the EC. Final report of the WP 8 of the TENAWA project

    International Nuclear Information System (INIS)

    Annanmaeki, M.; Turtiainen, T.; Jungclas, H.; Rausse, Ch.

    2000-04-01

    Ground water, especially bedrock water, may contain high amounts of natural radioactivity. Elevated levels of natural radionuclides in ground water are mainly associated with uranium and thorium rich soil and rocks. Various processes based on different principles can be applied to the removal of radioactivity from water. Aeration and granular activated carbon (GAC) filtration are used to remove radon from household water. Ion exchangers are applied to the removal of uranium and radium. Lead and polonium may sometimes be removed by ion exchange technology as well. Membrane techniques are applied to the removal of uranium, radium, lead and polonium. Radionuclide removal can also be carried out using adsorptive materials. When different kinds of treatment methods are used to remove natural radioactivity from drinking water, wastes containing natural radioactivity will be produced. The wastes are in liquid or solid form. Liquid wastes are produced when materials used to accumulate radioactivity are regenerated or backwashed. Solid wastes are formed in cases where regeneration or backwashing are not used or cannot be used, and when the materials are taken out of service. GAC filters emit gamma radiation when they are in service. To gather information on existing national regulations and guidelines on the treatment and disposal of radioactive wastes produced by various water treatment methods, a questionnaire was sent to all the Member Countries of the European Union. (orig.)

  20. 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)

  1. Environmental radioactivity in northern parts of Iran and Teheran

    International Nuclear Information System (INIS)

    Khademi, B.; Hanjani, M.A.

    1974-01-01

    This article deals with the measurement of the amount of 226Ra by ''radium emanation method'' in water and food products of the North, North-West and North-East of Iran. A total of 126 water samples, 249 food-stuffs and 22 air samples have been examined. The concentration of 226Ra in water was about 0.01 to 1x10 4 pci/1, and in food products was about 0.01 to 20.00 pci/gr. The measured radioactivity in the air for the city of Tehran and Tehran University reactor's environment has been about 0.003 to 0.227 pci/m 3 . The results of these measurements for Iran's atmosphere are given in various tables which indicated that in some part of Iran the rate of the radioactivity is higher than the normal rate

  2. 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)

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

    International Nuclear Information System (INIS)

    Geryes, Tony

    2009-01-01

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

  4. Radioactivity of spent TRIGA fuel

    International Nuclear Information System (INIS)

    Usang, M. D.; Nabil, A. R. A.; Alfred, S. L.; Hamzah, N. S.; Abi, M. J. B.; Rawi, M. Z. M.; Abu, M. P.

    2015-01-01

    Some of the oldest TRIGA fuel in the Malaysian Reaktor TRIGA PUSPATI (RTP) is approaching the limit of its end of life with burn-up of around 20%. Hence it is prudent for us to start planning on the replacement of the fuel in the reactor and other derivative activities associated with it. In this regard, we need to understand all of the risk associated with such operation and one of them is to predict the radioactivity of the fuel, so as to estimate the safety of our working conditions. The radioactivity of several fuels are measured and compared with simulation results to confirm the burnup levels of the selected fuels. The radioactivity measurement are conducted inside the water tank to reduce the risk of exposure and in this case the detector wrapped in plastics are lowered under water. In nuclear power plant, the general practice was to continuously burn the fuel. In research reactor, most operations are based on the immediate needs of the reactor and our RTP for example operate periodically. By integrating the burnup contribution for each core configuration, we simplify the simulation of burn up for each core configuration. Our results for two (2) fuel however indicates that the dose from simulation underestimate the actual dose from our measurements. Several postulates are investigated but the underlying reason remain inconclusive

  5. Radioactivity of spent TRIGA fuel

    Energy Technology Data Exchange (ETDEWEB)

    Usang, M. D., E-mail: mark-dennis@nuclearmalaysia.gov.my; Nabil, A. R. A.; Alfred, S. L.; Hamzah, N. S.; Abi, M. J. B.; Rawi, M. Z. M.; Abu, M. P. [Reactor Department, Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor (Malaysia)

    2015-04-29

    Some of the oldest TRIGA fuel in the Malaysian Reaktor TRIGA PUSPATI (RTP) is approaching the limit of its end of life with burn-up of around 20%. Hence it is prudent for us to start planning on the replacement of the fuel in the reactor and other derivative activities associated with it. In this regard, we need to understand all of the risk associated with such operation and one of them is to predict the radioactivity of the fuel, so as to estimate the safety of our working conditions. The radioactivity of several fuels are measured and compared with simulation results to confirm the burnup levels of the selected fuels. The radioactivity measurement are conducted inside the water tank to reduce the risk of exposure and in this case the detector wrapped in plastics are lowered under water. In nuclear power plant, the general practice was to continuously burn the fuel. In research reactor, most operations are based on the immediate needs of the reactor and our RTP for example operate periodically. By integrating the burnup contribution for each core configuration, we simplify the simulation of burn up for each core configuration. Our results for two (2) fuel however indicates that the dose from simulation underestimate the actual dose from our measurements. Several postulates are investigated but the underlying reason remain inconclusive.

  6. Water hyacinth for phytoremediation of radioactive waste simulate contaminated with cesium and cobalt radionuclides

    International Nuclear Information System (INIS)

    Saleh, H.M.

    2012-01-01

    Highlights: ► Phytoremediation of radioactive wastes containing 137 Cs and 60 Co radionuclides. ► Using water hyacinth for radioactive waste treatment. ► Bioaccumulation of radionuclides from radioactive waste streams. ► Factors affecting bioaccumulation of 137 Cs and 60 Co using floating plants. - Abstract: Phytoremediation is based on the capability of plants to remove hazardous contaminants present in the environment. This study aimed to demonstrate some factors controlling the phytoremediation efficiency of live floating plant, water hyacinth (Eichhornia crassipes), towards the effluents contaminated with 137 Cs and/or 60 Co. Cesium has unknown vital biological role for plant while cobalt is one of the essential trace elements required for plant. The main idea of this work i.e. using undesirable species, water hyacinth, in purification of radiocontaminated aqueous solutions has been receiving much attention. The controlling factors such as radioactivity concentration, pH values, the amount of biomass and the light were studied. The uptake rate of radiocesium from the simulated waste solution is inversely proportional to the initial activity content and directly proportional to the increase in mass of plant and sunlight exposure. A spiked solution of pH ≈ 4.9 was found to be the suitable medium for the treatment process. The uptake efficiency of 137 Cs present with 60 Co in mixed solution was higher than if it was present separately. On the contrary, uptake of 60 Co is affected negatively by the presence of 137 Cs in their mixed solution. Sunlight is the most required factor for the plant vitality and radiation resistance. The results of the present study indicated that water hyacinth may be a potential candidate plant of high concentration ratios (CR) for phytoremediation of radionuclides such as 137 Cs and 60 Co.

  7. Water balance at a low-level radioactive-waste disposal site

    Science.gov (United States)

    Healy, R.W.; Gray, J.R.; De Vries, G. M.; Mills, P.C.

    1989-01-01

    The water balance at a low-level radioactive-waste disposal site in northwestern Illinois was studied from July 1982 through June 1984. Continuous data collection allowed estimates to be made for each component of the water-balance equation independent of other components. The average annual precipitation was 948 millimeters. Average annual evapotranspiration was estimated at 637 millimeters, runoff was 160 millimeters, change in water storage in a waste-trench cover was 24 millimeters, and deep percolation was 208 millimeters. The magnitude of the difference between precipitation and all other components (81 millimeters per year) indicates that, in a similar environment, the water-budget method would be useful in estimating evapotranspiration, but questionable for estimation of other components. Precipitation depth and temporal distribution had a very strong effect on all other components of the water-balance equation. Due to the variability of precipitation from year to year, it appears that two years of data are inadequate for characterization of the long-term average water balance at the site.

  8. Water balance at a low-level radioactive-waste disposal site

    International Nuclear Information System (INIS)

    Healy, R.W.; Gray, J.R.; de Vries, M.P.; Mills, P.C.

    1989-01-01

    The water balance at a low-level radioactive-waste disposal site in northwestern Illinois was studied from July 1982 through June 1984. Continuous data collection allowed estimates to be made for each component of the water-balance equation independent of other components. The average annual precipitation was 948 millimeters. Average annual evapotranspiration was estimated at 637 millimeters, runoff was 160 millimeters, change in water storage in a waste-trench cover was 24 millimeters, and deep percolation was 208 millimeters. The magnitude of the difference between precipitation and all other components indicates that, in a similar environment, the water-budget method would be useful in estimating evapotranspiration, but questionable for estimation of other components. Precipitation depth and temporal distribution had a very strong effect on all other components of the water-balance equation. Due to the variability of precipitation from year to year, it appears that two years of data are inadequate for characterization of the long-term average water balance at the site

  9. Investigation of produced waters radioactivity of oil and gas deposits in the Dnieper-Donets province

    Directory of Open Access Journals (Sweden)

    Plyatsuk L. D.

    2017-12-01

    Full Text Available The process of radioactive pollution of produced waters, oilfield equipment, oil-contaminated soils and sludge is widely spread and differs within the various oil and gas regions. Formation waters contained radioactive element isotopes become the significant source and cause of elevated level of equivalent dose power and as a consequence, an increase in the incidence among the population. The author's idea is formulation of specific recommendations on the decontamination of the investigated objects by conducting the necessary appropriate experimental studies. The purpose of the article is to determine the content of radionuclides, γ- and α-emitters in technogenic objects of Bugruvate oil and gas fields, and to reveal the relationship with the features of mineralogical composition, geological structure and technological process. The γ-spectrometric analysis was used to determine the radionuclide composition of the natural radiators of the 238U (226Ra, 214Pо, 214Bi and 232Th (228Ac, 212Pb, 212Вi series in samples of technological sludge, oil, individual soil samples and water. The content of radionuclides of α-emitters was determined using separate radiochemical techniques. It was investigated that the radioactivity of the formation water is mainly determined by 226Ra and 228Ra and the products of their decay.

  10. Artificial and natural radioactivity measurements in the vicinity of Ghana nuclear research reactor (GHARR-1)

    International Nuclear Information System (INIS)

    Faanu, A.; Awudua, A.R.; Darko, E.O.; Emi-Reynolds, G.; Inkooma, S.; Adukpo, O.; Kpeglo, D.O.; Lawluva, H.; Obeng, M.K; Titiati, J.; Agyeman, B.; Kpodzro, R.; Ibrahim, A.; Gloverb, E.T.

    2010-01-01

    Radioactivity concentrations of 226Ra, 232Th, 40K and 137Cs in soil and water samples around the Ghana Research Reactor-1 (GHARR-1) and the immediate surroundings have been investigated using gamma spectrometry. The primary aim of this study was to establish baseline radioactivity levels in the environs of GHARR-1. The average activity concentration in soil for 226Ra, 232Th, 40K and 137Cs were 19.8 Bqkg-1, 40.4 Bqkg-1, 95.3 Bqkg-1 and 1.5 Bqkg-1 respectively. For the water samples the average activity concentration of 226Ra was 2.15 Bql-1, 232Th was 0.61 Bql-1, 40K was 10.75Bql-1 and 137Cs was 0.47 Bql-1. The 226Ra and 232Th concentrations compare quite well with world averages, whilst the 40K concentration was lower than the world average. The activity concentrations of 137Cs observed in the samples are within the range of background. concentrations. The estimated average annual effective dose from external exposure to soil and ingestion of water samples was calculated to be 0.64 mSv. The estimated outdoor external gamma dose rate measured in air ranged from 10-430 nGyh-1 with an average value of 41 nGyh-1 which is lower than the worldwide average value of 60 nGyh-1. In the case of the water samples, the average annual effective value was higher than the WHO guideline value of 0.1 mSvy-1 (author)

  11. Contamination of foods by radioactive rains

    Energy Technology Data Exchange (ETDEWEB)

    Obo, F; Wakamatsu, C; Nakae, Y; Higasayama, S

    1955-01-01

    The radioactivities of various vegetable foods contaminated by radioactive rains in May, 1954, in the Kagoshima Area were detected. Tea showed especially high radioactivities which could be extracted with hot water. Radioactive Nb, Zr, Hf, Ce, Y, Pr, and La were detected in the hot water extractions of tea by ion-exchange chromatography. The partial contribution of /sup 40/K in these radioactive vegetables was critically examined.

  12. Environmental radioactivity in Greenland in 1979

    International Nuclear Information System (INIS)

    Aarkrog, A.; Dahlgaard, H.; Lippert, J.; Nilsson, K.; Holm, E.

    1980-07-01

    Measurements of fallout radioactivity in Greenland in 1979 are reported. Strontium-90 (and Cesium-137 in most cases) was determined in samples of precipitation, sea water, vegetation, animals, and drinking water. Estimates are given of the mean contents of 90 Sr and 137 Cs in the human diet in Greenland in 1979. Provisional results of the 239 , 240 Pu and 241 Am measurements on samples from the expedition to Thule in August 1979 are presented. (author)

  13. Bioremediation system on-line for removal radionuclides in radioactive waters; Sistema de biorremediation on-line pra la eliminacion de radionuclidos en aguas radiactivas

    Energy Technology Data Exchange (ETDEWEB)

    Belinchon, J. A.; Garcia, A. M.; Ruibal, C.; Moreno, D. A.

    2010-07-01

    In previous studies developed in Cofrentes Nuclear Power Plant (Valencia, Spain), has been observed that the microorganisms in the radioactive waters of the spent nuclear fuel pool are capable of colonizing the metallic surfaces of the walls and pipes and perform biofilm. These biofilm retain the nuclides contributing to decontaminate the water. In this project, carried out in Cofrentes Nuclear Power Plant, a pilot plant has been designed for the bio decontamination of the radioactive water. At present, the radioactive water coming from the spent nuclear fuel pools, pass through ionic exchange resins. After, these resins are managed as radioactive waste. In this project, the water passes through a bioreactor with stainless steel balls capable of being colonized by the microorganisms in the water. Inside the bioreactor the water gets in contact with the material of the balls, and a biofilm, which retains the nuclides in the water, is developed. The biofilm is easily removed by any conventional procedure of radiochemical decontamination of materials and the nuclides can be collected in a small volume for recovery final disposition or containment. Later, the material of the bioreactor could be managed as not radioactive material. (Author) 9 refs.

  14. Natural radioactivity levels of geothermal waters and their influence on soil and agricultural activities.

    Science.gov (United States)

    Murat Saç, Müslim; Aydemir, Sercan; Içhedef, Mutlu; Kumru, Mehmet N; Bolca, Mustafa; Ozen, Fulsen

    2014-01-01

    All over the world geothermal sources are used for different purposes. The contents of these waters are important to understand positive/negative effects on human life. In this study, natural radioactivity concentrations of geothermal waters were investigated to evaluate the effect on soils and agricultural activities. Geothermal water samples were collected from the Seferihisar Geothermal Region, and the radon and radium concentrations of these waters were analysed using a collector chamber method. Also soil samples, which are irrigated with geothermal waters, were collected from the surroundings of geothermal areas, and natural radioactivity concentrations of collected samples (U, Th and K) were determined using an NaI(Tl) detector system. The activity concentrations of radon and radium were found to be 0.6-6.0 and 0.1-1.0 Bq l(-1), respectively. Generally, the obtained results are not higher compared with the geothermal waters of the world. The activity concentrations in soils were found to be in the range of 3.3-120.3 Bq kg(-1) for (226)Ra (eU), 0.3-108.5 Bq kg(-1) for (232)Th (eTh), 116.0-850.0 Bq kg(-1) for (40)K (% K).

  15. VVER operational experience - effect of preconditioning and primary water chemistry on radioactivity build-up

    International Nuclear Information System (INIS)

    Zmitko, M.; Kysela, J.; Dudjakova, K.; Martykan, M.; Janesik, J.; Hanus, V.; Marcinsky, P.

    2004-01-01

    The primary coolant technology approaches currently used in VVER units are reviewed and compared with those used in PWR units. Standard and modified water chemistries differing in boron-potassium control are discussed. Preparation of the VVER Primary Water Chemistry Guidelines in the Czech Republic is noted. Operational experience of some VVER units, operated in the Czech Republic and Slovakia, in the field of the primary water chemistry, and radioactivity transport and build-up are presented. In Mochovce and Temelin units, a surface preconditioning (passivation) procedure has been applied during hot functional tests. The main principles of the controlled primary water chemistry applied during the hot functional tests are reviewed and importance of the water chemistry, technological and other relevant parameters is stressed regarding to the quality of the passive layer formed on the primary system surfaces. The first operational experience obtained in the course of beginning of these units operation is presented mainly with respect to the corrosion products coolant and surface activities. Effect of the initial passivation performed during hot functional tests and the primary water chemistry on corrosion products radioactivity level and radiation situation is discussed. (author)

  16. National network of environment radioactivity measurements. Press kit

    International Nuclear Information System (INIS)

    2010-01-01

    This document first presents the objectives, challenges, context, operation and actors of the French national network of environment radioactivity measurements. It discusses the reasons for these measurements, the way they are performed, who perform them and how they are transmitted to the national network. It describes the quality policy for these measurements, and how this network is at the service of authorities, experts and population. It outlines the originality of the French approach within the European Union, and how this network takes the population expectations and their evolution into account

  17. A method for prevention of radioactive material release

    International Nuclear Information System (INIS)

    Uchida, Shunsuke; Sato, Chikara; Kitamura, Masao.

    1975-01-01

    Object: To provide a method for preventing an underwater radioactive material from being released in a simple and highly reliable manner, which can decrease an amount of radioactive materials discharged into open air from reactor water containing a large amount of radioactive materials such as a reactor core pool. Structure: Pure warm water higher in temperature than that of reactor water is poured from the top of a water surface of a water tank which stores reactor water containing radioactive materials such as radioactive iodine, and water is drawn through an outlet located downwardly of the pure warm water inlet to form a layer of pure warm water at the upper part of the water tank while preventing diffusion of the reactor water into the pure warm water by the difference in density between the reactor water and the pure warm water and downward movement of the pure warm water, thereby preventing contact of the reactor water with the atmosphere and diffusion of the radioactive material into the atmosphere. (Kamimura, M.)

  18. Application of two-barrier model of radioactive agent transport in sea water for analyzing artificial radionuclide release from containers with radioactive waste dumped in Kara Sea

    Energy Technology Data Exchange (ETDEWEB)

    Grishin, Denis S.; Laykin, Andrey I.; Kuchin, Nickolay L.; Platovskikh, Yuri A. [Krylov State Research Center, Saint Petersburg, 44 Moskovskoe shosse, 196158 (Russian Federation)

    2014-07-01

    Modeling of artificial radionuclide transport in sea water is crucial for prognosis of radioecological situation in regions where dumping of radioactive waste had been made and/or accidents with nuclear submarines had taken place. Distribution of artificial radionuclides in bottom sediments can be a detector of radionuclide release from dumped or sunk objects to marine environment. Proper model can determine the dependence between radionuclide distribution in sediments and radionuclide release. Following report describes two-barrier model of radioactive agent transport in sea water. It was tested on data from 1994 - 2013 expeditions to Novaya Zemlya bays, where regular dumping of solid radioactive waste was practiced by the former USSR from the early 1960's until 1990. Two-barrier model agrees with experimental data and allows more accurate determination of time and intensity of artificial radionuclide release from dumped containers. (authors)

  19. Environmental radioactivity in Canada, 1981

    International Nuclear Information System (INIS)

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

    1983-01-01

    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. Special investigations were carried out during 1981 on bottled mineral waters and in conjunction with unusual occurences at nuclear reactor sites and a uranium refinery. Dose commitments have been estimated for the ongoing natural radioactivity, fallout and reactor studies. All measurements made during the year are below the limits recommended by the International Commission on Radiological Protection

  20. Radioactivity in the hydrologic environment

    International Nuclear Information System (INIS)

    Werner, L.B.

    1969-01-01

    Certain proposed uses of nuclear explosives for peaceful purposes will introduce radioactive debris into the natural hydrologic environment. Consideration must therefore be given in each situation to the extent and significance to man of resulting radioactively contaminated water. For contained underground detonations, space-time - concentration predictions of radioactive materials in ground water are dependent on several factors: radionuclide production and initial distribution, radioactive decay, sorption on geologic materials, and dispersion during hydrologic transport. For uncontained (cratering) detonations, other aspects of the hydrologic cycle, particularly rainfall, and watershed characteristics must be considered. Programs sponsored principally by the U.S. Atomic Energy Commission have investigated these factors. Examination of their net effects on radioactivity concentration in water shows that areas if any, underlain by water exceeding permissible concentrations tend first to increase in size, then decrease, and finally disappear. Hydrologic processes at the surface remove or redistribute radioactive debris deposited on a watershed to other locations. Where sufficient information is available, predictions of location and concentration of radionuclides in natural waters can be made. Any potentially hazardous conditions arising from a particular detonation can then be evaluated. (author)

  1. Radioactivity in the hydrologic environment

    Energy Technology Data Exchange (ETDEWEB)

    Werner, L B [Isotopes, Inc., Palo Alto, CA (United States)

    1969-07-01

    Certain proposed uses of nuclear explosives for peaceful purposes will introduce radioactive debris into the natural hydrologic environment. Consideration must therefore be given in each situation to the extent and significance to man of resulting radioactively contaminated water. For contained underground detonations, space-time - concentration predictions of radioactive materials in ground water are dependent on several factors: radionuclide production and initial distribution, radioactive decay, sorption on geologic materials, and dispersion during hydrologic transport. For uncontained (cratering) detonations, other aspects of the hydrologic cycle, particularly rainfall, and watershed characteristics must be considered. Programs sponsored principally by the U.S. Atomic Energy Commission have investigated these factors. Examination of their net effects on radioactivity concentration in water shows that areas if any, underlain by water exceeding permissible concentrations tend first to increase in size, then decrease, and finally disappear. Hydrologic processes at the surface remove or redistribute radioactive debris deposited on a watershed to other locations. Where sufficient information is available, predictions of location and concentration of radionuclides in natural waters can be made. Any potentially hazardous conditions arising from a particular detonation can then be evaluated. (author)

  2. Development of Radioactive Inventory Evaluation System using 3D Shape and Multiple Radiation Measurement

    International Nuclear Information System (INIS)

    Lee, Sang Chul; Kim, Won Seok; Han, Byong Su; Moon, Joo Hyun

    2013-01-01

    The increase of the operating NPPs and the superannuation of the equipment in NPPs cause a large amount of the metal radioactive waste. Presently the metal radioactive wastes are stored in the temporary storage facility in NPPs because of the delay of the construction of the final disposal facility. The radioactive level of general metal radioactive wastes is low, and the radioactive level can be lowered by the simple decontamination process. If the radioactive wastes are disposed as the industry waste, the disposal cost is diminished largely. For the disposal of the radioactive wastes as the industrial wastes, the radioactive level of the target wastes are evaluated. It is difficult to know the position of the source term for most of the metal radioactive and the source term is distributed non-homogeneously. And the self-shielding effect of the metal material makes the evaluation more difficult. In this study, the radioactive inventory evaluation system for the metal radioactive waste is developed. For the correction of the uncertainty of the position and the non-homogeneity of the source term, the 3D shape and multiple radiation measurement are used. The existing gamma-ray measurement system for the metal radioactive waste cannot reflect the position and the distribution of the source term and the effect of self-shielding. This evaluation system suggested in this system can calculate the reasonable value regarding to the position and the distribution of the source term and the effect of self-shielding. By the calculation of the partial inventory of the target metal waste, the advantage in the application of the clearance criteria can be obtained

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

    Science.gov (United States)

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

    2010-01-01

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

  4. Direct gamma-ray measurement of different radionuclides in the surface water of Suez Canal

    International Nuclear Information System (INIS)

    Lasheen, Y.F.; El-Zakla, T.; Seliman, A.F.; Abdel-Rassoul, A.A.

    2008-01-01

    The radioactivity levels of naturally-occurring 238 U, 232 Th, 226 Ra and 40 K and anthropogenic 137 Cs in surface water from eight locations in the Suez Canal have been assessed by gamma-ray spectrometry. The samples were further characterized by determination of the common cations and anions using ion chromatography. A comparison of 137 Cs radioactivity levels in surface water from the Suez Canal with those of other sea waters is presented. The radioactivity levels of 238 U, 232 Th, 226 Ra and 40 K from sea water are also reported. The effect of total dissolved solids (T.D.S.), chloride, sulphate ion concentrations on the radioactivity levels of 238 U, 232 Th and 226 Ra is discussed. (authors)

  5. Dose in a recreational water park with thermal water

    International Nuclear Information System (INIS)

    Thomassin, A.

    2006-01-01

    This paper assesses the annual effective dose received by the public due to baths in thermal water of a recreational water park in Royat (France) with significant levels of natural radionuclides. After the context be specified and the measurements of radioactivity presented, an assessment of radiological consequences is performed, based on an hypothetical scenario for persons of the public. Context The french commune of Royat in the Massif Central (centre of France) intends to build a recreational water park, using thermal water from a local source, out of the public water supply network. With this aim in view, the operator builds up a technical file to get a prefectorial authorization. Considering that many waters and thermal waters in this area have significant levels of natural radionuclides (granitic subsoil) on the one hand, and that the operator of establishments receiving public is requested by L 1333-10 article of the Public Health Code to supervise the exposure if an impact on health is possible on the other hand, the operator asked I.R.S.N. to measure the level of radioactivity in the water. Considering the level of radioactivity measured, the competent authority then asks I.R.S.N. if this level is compatible with its use in a recreational water park. After calculations it appears that in the particular case of the commune of Royat, the level of activity of natural radionuclides of the thermal water (22 Bq.L -1 for 222 Rn) is compatible with its use in a recreational water park, the annual effective dose being about 40 μSv with a conservative approach. For other thermal waters in France winch could have much higher levels of natural radioactivity, it is recommended to pay attention to their use in recreational water park. (N.C.)

  6. Fuel element replacement and cooling water radioactivity at the Musashi reactor

    International Nuclear Information System (INIS)

    Nozaki, T.; Honda, T.; Horiuchi, N.; Aizawa, O.; Sato, T.

    1988-01-01

    The Musashi reactor (TRIGA-II, 100kW) has been operated without any serious troubles since 1963. In 1985 the old Al-cladded fuel elements were replaced with new stainless cladded ones in order to insure a long and safe operation. By using a semi-automatic equipment the old fuel elements have been transferred into the bulk-shielding experimental pool, which was remodelled for the spent-fuel storage. In order to reduce the exposure during the transfer work, the old fuel elements were cooled in the core tank for 3 months. After the replacement, the radioactivities in the cooling water have been drastically changed. The activity of Na-24 decreased about one decade, and the activities of Cr-51, Mn-54, Mn-56, Co-58 and Co-60 increased about two decades. At this conference we will report on the following points: (1) semi-automatic equipment for the transportation of the Al-cladded spent fuel, (2) structure of spent-fuel storage pool, and (3) radioactivity change in the cooling water. (author)

  7. Treatment of radioactive waste water by flocculation method, (1)

    International Nuclear Information System (INIS)

    Kimura, Syojiro; Tsutsui, Tenson.

    1976-01-01

    Coagulation property of particle on the treatment of radioactive waste water by floculation method is varied with its electrical potential and mixing condition. The surface state of the particle is influenced by contents of coexistent materials in the waste water and added materials at the treatment process. In the case of using ferric hydroxide as coagulant, assuming the ions which decide the potential of the particle surface are Fe(OH) 2 + and Fe(OH) 4 - , calculated values of the potential agree with zeta-potential of ferric hydroxide particle which is formed from FeCl 4 and NaOH in demineralized water. When Na 2 CO 3 is in the waste water as coexistent materials, anion HCO 3 - adsorbs on the particle surface in connection with pH variation and thus the surface charge is being minus. If Ca 2+ ion is present in the waste water, the surface charge plus. ABS acts as single molecule anion at low concentration, but it forms micell at high concentration and influences zeta-potential of the particle. The potential of the particle is correlated to the coprecipitation rate of 90 Sr in the waste water. (auth.)

  8. Results of environmental radioactivity measurements in the Member States of European Community for air-deposition-water 1973-1974, milk 1972-1973-1974

    International Nuclear Information System (INIS)

    1977-01-01

    The present document is the fifteenth report published by the Health and Safety Directorate of the Commission of the European Communities concerning ambient radioactivity and using the data collected by the stations in charge of the surveillance of the environmental radioactivity in Member States. The results are compiled and extracted from the data sent to the Commission in application of Article 36 of the Treaty of Rome instituting the European Atomic Energy Community. It is the first document in which data from Denmark, Ireland and the United Kingdom which joined the European Community on 1 January 1973 are included in addition to data from Belgium, the Federal Republic of Germany, France, Italy, Luxembourg and the Netherlands. The results presented in this report cover the years 1973 and 1974 for air deposition and surface water and the years 1972, 1973 and 1974 for milk

  9. Development of temporal trends of radioactivity in benthic organisms and in water from the deep sea (Atlantic)

    International Nuclear Information System (INIS)

    Kanisch, G.; Kellermann, H.-J.; Vobach, M.; Krueger, A.

    2003-01-01

    Since 20 years the Federal Research Centre for Fisheries is performing radioecological studies in the deep sea of the Northeast Atlantic, especially in the area north-west of Spain used for dumping of radioactive waste until 1982. Until 1998/2000, in Benthos some decrease was observed for 137 Cs, however, almost not for 238 Pu, 239,240 Pu and 241 Am. In the dumpsite area the ratio 238 Pu/ 239,240 Pu, about 0.072, showed higher values than in comparison sites, about 0,044. Alpha spectrometric measurements of the atom based ratio 240 Pu/ 239 Pu in Benthos, due to slight deviations from the global fallout value of 0.18, indicated a special impact of the ''Nevada Test Site'' fallout. In rat-tailed fish (Macrouridae) from the deep sea 137Cs decreased since 1989 with an effective half-live of 14.5 years, comparable to that of 16.2 years in the surface water. Related to the concentration in the surface water a 137 Cs concentration factor of 83 was obtained. It is concluded that the dominant source for 137 Cs in deep sea fish is the global fallout. For plutonium isotopes measured in sea water samples from the deep the values of 238 Pu/ 239,240 Pu and 238 Pu, being higher for the dumpsite area, were interpreted as impact of leaking radioactive drums. For this leakage acting as a plutonium source a 238 Pu/ 239,240 Pu ratio of 0.17 was estimated. However, the total plutonium inventory in the deep sea thereby increased by only about 20 %. (orig.)

  10. On-line monitoring of water amount in fresh concrete by radioactive-wave method

    International Nuclear Information System (INIS)

    Kemi, T.; Arai, M.; Enomoto, S.; Suzki, K.; Kumahara, Y.

    2003-01-01

    The committee on nondestructive inspection for steel reinforced concrete structures in the Federation of Construction Materials Industries, Japan has published a proposed standard for on-line monitoring of water amount in fresh concrete by the radioactive wave method. By applying a neutron technique, water amount in fresh concrete is estimated continuously from the energy consumption of neutron due to hydrogen. A standard is discussed along with results of verification tests. Thus, on-line monitoring for water amount is proposed

  11. Risk of a large amount of high-radioactive contaminated water leaking into the reactor building basement of Fukushima Daiichi nuclear power station

    International Nuclear Information System (INIS)

    Ebisawa, Toru; Sawai, Masako

    2013-01-01

    In November 2012 about one and half year after the accident at units 1, 2 and 3 of Fukushima Daiichi nuclear power station, some 405 m 3 /day cooling water was being injected into the melt damaged core and leaked as highly-radioactive contaminated water from damaged lower part of containment into the basement of turbine hall. To treat a large amount of contaminated water in the basement, waste processing plant to remove cesium was installed in June 2011 with desalination plant, which produced clean water for circulating coolant system of damaged nuclear fuel while the rest went to storage. Radioactivity of contaminated water in the basement accumulated at initial almost 80 days of the accident was evaluated about 20% for Cs-137 of core inventory of units 1, 2 and 3 and 2.3% for Sr-90 of core inventory of units 2 and 3. Sr-90 from unit 1 was not released into the basement and almost remained at suppression chamber. By November 2012, Cs-137 released into the basement was evaluated to total about 40% of core inventory and stored contaminated water amounted to about 360 kilotons, while Cs-137 released into the atmosphere was estimated about 3.6% of core inventory with its one third contributed for land contamination. Sr-90 released into the basement was estimated as 6.3% or 4.4% of core inventory based on Sr-90 measured activity of treated water in December or September 2011 with stored contaminated water of 300 kilotons. Cs-137 and Sr-90 contaminated water kept continuously releasing into the basement as long as melt damaged core existed and cooling water washed out Cs-137 and Sr-90 attached on containment walls. Safe store of released radioactivity was highly important and acquired important data was recommended to publish for check and review. (T. Tanaka)

  12. Radioactivity in north European waters: report of Working Group 2 of CEC project MARINA

    Energy Technology Data Exchange (ETDEWEB)

    Camplin, W C [Ministry of Agriculture, Fisheries and Food, Lowestoft (UK). Directorate of Fisheries Research; Aarkrog, A [Risoe National Lab., Roskilde (Denmark)

    1989-01-01

    The primary objective of Working Group 2 of Project MARINA was to consider recent measurements of environmental radioactivity in north European waters and to use this, and other information, to report the likely magnitude of doses to the critical group from marine pathways. The monitoring data were supplemented, where appropriate, with predictions from simple models. The major sources of radioactivity studied were as follows: (i) liquid wastes from nuclear fuel reprocessing plants; (ii) liquid wastes from nuclear power plants and other major nuclear industry sites; (iii) solid waste disposal in the deep north-east Atlantic; (iv) fallout from Chernobyl; and (v) naturally-occurring radionuclides. Some of the largest doses from marine pathways are predicted for naturally-occurring radionuclides. In this case, the dominant radionuclide is polonium-210 and the dominant pathway is via consumption of molluscan species. The highest doses from the nuclear industry were due to the operation of the reprocessing plant at Sellafield. Discharges from this site have been decreasing substantially in recent years and, as a consequence, doses have also been reducing. (author).

  13. Study of the source-detector system geometry using the MCNP-X code in the flowrate measurement with radioactive tracers

    Energy Technology Data Exchange (ETDEWEB)

    Avilan Puertas, Eddie, E-mail: epuertas@nuclear.ufrj.br [Universidad Central de Venezuela (UCV), Facultad de Ingenieria, Departamento de Fisica Aplicada, Caracas (Venezuela, Bolivarian Republic of); Braz, Delson, E-mail: delson@lin.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear; Brandao, Luis E.; Salgado, Cesar M., E-mail: brandao@ien.gov.br, E-mail: otero@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    The use radioactive tracers for flow rate measurement is applied to a great variety of situations, however the accuracy of the technique is highly dependent of the adequate choice of the experimental measurement conditions. To measure flow rate of fluids in ducts partially filled, is necessary to measure the fluid flow velocity and the fluid height. The flow velocity can be measured with the cross correlation function and the fluid level, with a fluid level meter system. One of the error factors when measuring flow rate, is on the correct setting of the source-detector of the fluid level meter system. The goal of the present work is to establish by mean of MCNP-X code simulations the experimental parameters to measure the fluid level. The experimental tests will be realized in a flow rate system of 10 mm of diameter of acrylic tube for water and oil as fluids. The radioactive tracer to be used is the {sup 82}Br and for the detection will be employed two 1″ NaI(Tl) scintillator detectors, shielded with collimators of 0.5 cm and 1 cm of circular aperture diameter. (author)

  14. 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)

  15. ROKO-Database of the environmental radioactivity measurements in Slovenia

    International Nuclear Information System (INIS)

    Stritar, A.; Mitic, D.

    2005-01-01

    ROKO is the acronym of the Environmental Radioactivity in Slovenian language R adioaktivnost v OKOlju . Computer database ROKO contains data of all measurements of the radioactivity in the environment in Slovenia. Data about radioactivity in the environment have been collected in Slovenia more or less regularly since 1961 on. Most results are gathered in the form of paper reports. Slovenian Nuclear Safety Administration (SNSA) has initiated the project of transfer of all those data into the electronic form and making it available for easy research. The database is designed so, that it contains all records, relevant for any kind of analyses and for the transfer to the international data systems. By the end of the summer 2005 a major part of data from previous years have already been transferred into the database and the user interface software is under development. It will allow the users to examine individual data records, to plot time history graphs or geographical contour plots. (author)

  16. Radioactive waste processing field

    International Nuclear Information System (INIS)

    Ito, Minoru.

    1993-01-01

    Storing space for radioactive wastes (storage tunnels) are formed underground of the sea bottom along coast. A plurality of boreholes through which sea water flows are pored vertically in a direction intersecting underground streams of brine in the ground between the tunnels and seaside. Sea water introduction pipes are joined to the upper side walls of the boreholes. The sea water introduction pipes have introduction ports protruded under the sea level of the coastal sea area region. Since sea water flows from the introduction ports to the boreholes passing through the sea water introduction pipes, sea water is always filled in the boreholes. Therefore, brine is sufficiently supplied toward the land by sea water from the boreholes, the underground stream of brine is negligibly small. This can prevent radioactive contamination due to flow of the underground water when radioactive wastes are buried in the underground near coast. (I.N.)

  17. Method of inhibiting concentration of radioactive corrosion products in cooling water or nuclear power plants

    International Nuclear Information System (INIS)

    Takabayashi, Jun-ichi; Hishida, Mamoru; Ishikura, Takeshi.

    1979-01-01

    Purpose: To suppress the increase in the concentration of the radioactive corrosion products in cooling water, which increase is accompanied by the transference of the corrosion products activated and accumulated in the core due to dissolution and exfoliation into the core water, and inhibit the flowing of said products out of the core and the diffusion thereof into the cooling system, thereby to prevent the accumulation of said products in the cooling system and prevent radioactive contaminations. Method: In a nuclear power plant of a BWR type light water reactor, when the temperature of the pile water is t 0 C, hydrogen is injected in cooling water in a period of time from immediately before starting of the drive stopping operation of the nuclear power plant to immediately after the termination of restarting operation, whereby the concentration of hydrogen in the reactor water through said period is maintained at a value more than 2exp (0.013 t) cm 3 N.T.P./kg H 2 O. (Aizawa, K.)

  18. Uptake of radioactive strontium by fishes in relation to the calcium content of the water

    International Nuclear Information System (INIS)

    Chiosila, J.

    1975-01-01

    The study attempts to compare experimental results obtained with pseudorasbora parava with regard to 85 Sr uptake at various Ca concentrations of the water (4.20 and 50 mg/l Ca) and also to compare these results with natural conditions. The water was contaminated with 500 pCi/ml 85 SrCl 2 only at the onset of the experiments. Radiostrontium uptake is much higher with a very low calcium content of the water; maximum values are reached in about 10 days. - With low or optimum calcium contents of the water, the values are 3-5 times lower and are not reached until 30 days after radioactive contamination. The fish in this Danube water experiment took up somewhat less radioactivity than in an experiment with the same amounts of Ca and Mg in a control medium. The uptake of 85 Sr in fish in dependence of the Ca content of the water varies according to the formula F.C = 2.505 x Casup(-0.909), with Ca given in Mg/l. (orig.) [de

  19. Environmental radioactivity measurements at BNL during the year following the Chernobyl accident

    International Nuclear Information System (INIS)

    Hancock, R.; Woollam, P.B.

    1987-07-01

    The accident which destroyed Unit 4 of the Chernobyl Nuclear Power Station on 26 April 1986 provided the world's scientists with an opportunity, unique in recent years, to study many of the processes which follow the release of large quantities of radioactivity into the atmosphere. BNL undertook a wide ranging programme of environmental measurements after the accident, the immediate aim being to supply HM Government with data to help assess the radiological consequences to the UK population. As it became clear that the UK dose commitment was relatively low, the thrust of the measurements began to be concentrated on airborne radioactivity and the movement of nuclides in the grass-soil system. The aim of these studies was to assess dispersion and diffusion of radioactivity in these particular compartments of the environment. The measurements have continued over the twelve month period since the Chernobyl accident. This report aims to disseminate the year's data and to offer some initial interpretations of the trends. (U.K.)

  20. A new method for measuring aerosol nebulizers output using radioactive tracers

    International Nuclear Information System (INIS)

    Gatnash, A.A.; Connolly, C.K.; Chandler, S.T.

    1998-01-01

    Reproducibility and comparability of bronchial challenge tests depends critically on accurate assessment of nebulizers output. Evaporation during nebulization means that simple weighing is inaccurate, overestimating the delivered dose of active ingredient. We wanted to quantify this effect in the context of intermittent nebulization, using a dosimeter as used in bronchial provocation tests. Output of three types of nebulizers, from the MEFAR dosimeter, was measured by radioactive tracer, using a standard solution of technetium-99m-pertechnetate (1.5 kBq x mL -1 ) in 4 mL of normal saline. The aerosol was impacted by suction onto a micro filter, and the radioactivity measured. Nebulizers were weighed before and after nebulization. Ratio of nebulized volume calculated from the radioactivity on the filter, to the total volume loss by weight, was expressed as nebulized ratio. The effect on output of two concentrations of methacholine, two tracers of different weights, and change in temperature, were assessed. Nebulized ratio varied between 44.1-71.6%. Results were more consistent within the same type of nebulizer than between different makes. Neither changes in molar concentration nor molecular weight affected nebulizer output or nebulized ratio. Mean nebulized ratio was 58.5%, showing that calibration by weighing, overestimates the delivered dose by a factor of approximately two. Measuring radioactivity eluted from a micro filter, onto which nebulized output had been impacted proved to be a satisfactory method of calibration. (au)

  1. Removal of high-level radioactive substances contained with water from the Fukushima No. 1 Nuclear Power Stations. Some technical problems in waste treatment

    International Nuclear Information System (INIS)

    Amano, Osamu; Mimura, Hitoshi; Sato, Nobuaki; Kirishima, Akira; Hattori, Toshio

    2011-01-01

    The Japanese government and plant operator Tokyo Electric Power Co. announced to process the highly radioactive water amounting to about 250,000 cubic meters by the end of fiscal year 2011. Radiation-contaminated water will be moved to the waste facility to remove oil and radioactive cesium using zeolite. The process using Prussian Blue is expected for the effectiveness. Other radioactive substances will be removed through precipitation using special chemicals and radioactivity in the water will be reduced to 10 -6 of its original level. The water will be then be returned to the reactors and used to cool them after going through a desalination process. The facility can process about 1,200 tons of contaminated water a day. TEPCO will store radioactive materials and other waste from the cleansing process at the Fukushima plant. They need to decide how the waste will finally be disposed of and to figure out what to do with the highly radioactive waste produced in the above process. Kurion Inc., Areva SA, and some domestic firms provide equipment and technology, but all the Japanese facilities and institutions should join to settle the problems. (S. Ohno)

  2. Treatment of radioactive waste water originating from the laundries of contaminated clothing

    International Nuclear Information System (INIS)

    Pavlik, O.; Friedrich, V.; Reti, Gy.

    1980-01-01

    The technology of purification of low radioactivity, high detergent content waste water from the laundries and shower stalls of the Paks Nuclear Power Station was developed. The technology consists of chemical treatment, clarification, filtration of clarified water, compaction and dehydratation of the slurry. During chemical treatment the concentration of radioactive isotopes is significantly lowered by separating a precipitate containing Cu 2 Fe(CN) 6 , Ca 3 (PO 4 ) 2 and Fe(OH) 3 . The precipitate is compacted into a slurry of 30-40% extract content by continuous operation of countercurrent suspension, sedimentation and a centrifuge, then dehydrated by hot air which serves as a transport medium of the steam, too. After having been filled the container is closed and transported to the burial site. The energy balance of the dryer-evaporator, the decontamination factor of evaporation for 90 Sr, 137 Cs and 131 I and the effect of the parameters of circulating air on the steam capacity were studied. (author)

  3. Removal of bulk contaminants from radioactive waste water at Bruce A using a clay based flocculent system

    International Nuclear Information System (INIS)

    Davloor, R.; Harper, B.

    2011-01-01

    Bruce Power's Bruce Nuclear Generating Station 'A', located on Lake Huron, has a treatment system that processes all aqueous radioactive waste water originating from the station. This Active Liquid Waste Treatment System (ALWTS) consists of collection tanks for the collection of radioactive waste water, a Pre-Treatment System (PTS) for the removal of bulk contaminants and suspended solids, a Reverse Osmosis System (ROS) to remove dissolved solids, an Evaporation and Solidification System (ESS) to concentrate and immobilize solids contained in concentrated waste streams from the ROS, and discharge tanks for the dispersal of the treated water. The ALWTS has been in continuous service since 1999 and is used to treat approximately 100,000 litres of Active Liquid Waste (ALW) each day. With the exception of tritium, it discharges waste water containing near zero concentrations of radioactive and conventional contaminants to the lake. The original design of the Bruce A ALWTS used a Backwashable Filtration System (BFS) to provide solids free water to the ROS, as measured by the Silt Density Index (SDI). During commissioning, the BFS was not successful in backwashing the solids from the filter elements. For approximately one year, a temporary solution was implemented using a Disposable Filtration System (DFS). A cationic polymer was added upstream of the DFS to agglomerate the solids. The system proved to be highly unreliable. It was difficult to agglomerate solids in the waste stream containing high amounts of detergent. As a result, DFS consumption was high and very costly. The SDI specification for the RO membrane was not always met, resulting in a quick decline of performance of the first stage ROS membranes in the treatment process. In addition, the excess cationic polymer in the RO feed caused the membranes to become fouled. In-house station staff, together with personnel from Colloid Environmental Technologies (CETCO) Company, worked to develop and

  4. Removal of bulk contaminants from radioactive waste water at Bruce A using a clay based flocculent system

    Energy Technology Data Exchange (ETDEWEB)

    Davloor, R.; Harper, B. [Bruce Power, Tiverton, ON (Canada)

    2011-07-01

    Bruce Power's Bruce Nuclear Generating Station 'A', located on Lake Huron, has a treatment system that processes all aqueous radioactive waste water originating from the station. This Active Liquid Waste Treatment System (ALWTS) consists of collection tanks for the collection of radioactive waste water, a Pre-Treatment System (PTS) for the removal of bulk contaminants and suspended solids, a Reverse Osmosis System (ROS) to remove dissolved solids, an Evaporation and Solidification System (ESS) to concentrate and immobilize solids contained in concentrated waste streams from the ROS, and discharge tanks for the dispersal of the treated water. The ALWTS has been in continuous service since 1999 and is used to treat approximately 100,000 litres of Active Liquid Waste (ALW) each day. With the exception of tritium, it discharges waste water containing near zero concentrations of radioactive and conventional contaminants to the lake. The original design of the Bruce A ALWTS used a Backwashable Filtration System (BFS) to provide solids free water to the ROS, as measured by the Silt Density Index (SDI). During commissioning, the BFS was not successful in backwashing the solids from the filter elements. For approximately one year, a temporary solution was implemented using a Disposable Filtration System (DFS). A cationic polymer was added upstream of the DFS to agglomerate the solids. The system proved to be highly unreliable. It was difficult to agglomerate solids in the waste stream containing high amounts of detergent. As a result, DFS consumption was high and very costly. The SDI specification for the RO membrane was not always met, resulting in a quick decline of performance of the first stage ROS membranes in the treatment process. In addition, the excess cationic polymer in the RO feed caused the membranes to become fouled. In-house station staff, together with personnel from Colloid Environmental Technologies (CETCO) Company, worked to develop and

  5. 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

  6. IAEA-MEL's AQCS programme for marine radioactivity measurements

    International Nuclear Information System (INIS)

    Povinec, P.P.; Gastaud, J.; Pham, M.K.

    1999-01-01

    The main objectives of the IAEA-MEL's Analytical Quality Control Services (AQCS) for marine radioactivity measurements are discussed and future plans for the organization of intercomparison exercises and the production of certified reference materials are presented. The new developments should also include implementation of quality assurance programmes in Member States' laboratories, training in quality management and accreditation programmes. (author)

  7. Radioactivity measurement in Austria 1992 and 1993. Data and evaluation

    International Nuclear Information System (INIS)

    Bobek, E.

    1995-01-01

    The Federal Ministry of Health and Consumer Protection is responsible for the large scale surveillance of radioactive contaminations of the Austrian territory. For this purpose on one hand an on-line measurement system has been set up, using gamma dose rate measuring devices situated in 336 locations. On the other hand, various media e.g. aerosols, precipitation, surface water and foodstuffs are being collected. Their radionuclide content is analysed in several laboratories. Additional special projects have been set up to improve the knowledge of the time dependence respectively of regional aspects of the contamination situation. The report covers the results of this surveillance for the years 1992 and 1993. The evaluation of these measurements and of other data concerning the average exposure of the Austrian population for the year 1993 is summarized in the following figure. It can be seen that the main contributions to the radiation dose are due to natural exposure pathways, among which the inhalation of indoor radon is of main importance. (Compared to the data in earlier reports due to a new evaluation of the radon risk by ICRP this dose contribution is significantly lower.) In comparison, the component due to the consequences of the Chernobyl reactor accident in 1986 onto Austrian territory during 1992 and 1993 was marginal. (author)

  8. Charging and coagulation of water aerosols with negligible addition of high-radioactive droplets

    International Nuclear Information System (INIS)

    Vasil'eva, N.L.; Sedova, G.L.; Chernyj, L.T.

    1994-01-01

    The mechanics of electrocoagulation of water aerosols with negligible admixture of high-radioactive droplets is considered. A corresponding mathematical model has been worked out which describes the processes of ionization, electrification and coagulation of radioactive aerosols. Numerical studies are carried out for a series of typical aerosols on the time dependence of ion concentrations, charge and pure droplet concentrations, as well as the charge and radius of radioactive droplets. It is shown that coagulation can give rise to the growth of droplet radius from 5-10 μm up to 30-40 μm for a 10 4 s period f time, and therefore it can play a considerable role in the development of aerosols with droplet radius up to 20 μm when gravitational coagulation is insignificant

  9. Remote measurements of radioactivity distribution with BROKK robotic system - 16147

    International Nuclear Information System (INIS)

    Ivanov, Oleg; Danilovich, Alexey; Stepanov, Vyacheslav; Smirnov, Sergey; Potapov, Victor

    2009-01-01

    Robotic system for the remote measurement of radioactivity in the reactor areas was developed. The BROKK robotic system replaces hand-held radiation measuring tools. The system consists of a collimated gamma detector, a standard gamma detector, color CCD video camera and searchlights, all mounted on a robotic platform (BROKK). The signals from the detectors are coupled with the video signals and are transferred to an operator's console via a radio channel or a cable. Operator works at a safe position. The video image of the object with imposed exposure dose rate from the detectors generates an image on the monitor screen, and the images are recorded for subsequent analysis. Preliminary work has started for the decommissioning of a research reactor at the RRC 'Kurchatov Institute'. Results of the remote radioactivity measurements with new system during radiation inspection waste storage of this reactor are presented and discussed. (authors)

  10. Role of electromagnetic filter in limitating radioactivity in the primary circuits of light water reactors

    International Nuclear Information System (INIS)

    Dolle, L.

    1978-01-01

    High temperature electromagnetic filtration of particulate corrosion products can be carried out with discharges up to 5% of the cooling flow rate. It allows efficient extraction of particulate matter which rate constants required for considerable reduction of activable crud deposition in the core. The paper holds a review of the preventing operation in the primary circuit of a PWR, and reports experimental results of efficiency measurments with an electromagnetic filter set in out-of-pile and in-pile pressurized water loops. The notable efficiencies towards radioactive fine grain and colloidal matter justify more extensive reactor scale application experiments. (author)

  11. Role of electromagnetic filter in limitating radioactivity in the primary circuits of light water reactors

    International Nuclear Information System (INIS)

    Dolle, L.

    1978-01-01

    High temperature electromagnetic filtration of particulate corrosion products can be carried out with discharges up to 5% of the cooling flow rate. It allows efficient extraction of particulate matter with rate constants required for considerable reduction of activable crud deposition in the core. The paper holds a review of the preventing operation in the primary circuit of a PWR, and reports experimental results of efficiency measurements with an electromagnetic filter set in out-of-pile and in-pile pressurized water loops. The notable efficiencies towards radioactive fine grain and colloidal matter justify more extensive reactor scale application experiments

  12. Radioactive liquid containing vessel

    International Nuclear Information System (INIS)

    Sakurada, Tetsuo; Kawamura, Hironobu.

    1993-01-01

    Cooling jackets are coiled around the outer circumference of a container vessel, and the outer circumference thereof is covered with a surrounding plate. A liquid of good conductivity (for example, water) is filled between the cooling jackets and the surrounding plate. A radioactive liquid is supplied to the container vessel passing through a supply pipe and discharged passing through a discharge pipe. Cooling water at high pressure is passed through the cooling water jackets in order to remove the heat generated from the radioactive liquid. Since cooling water at high pressure is thus passed through the coiled pipes, the wall thickness of the container vessel and the cooling water jackets can be reduced, thereby enabling to reduce the cost. Further, even if the radioactive liquid is leaked, there is no worry of contaminating cooling water, to prevent contamination. (I.N.)

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  15. Measurents of natural radioactivity in an underground hydroelectric power plant

    International Nuclear Information System (INIS)

    Malvicini, Andrea; Esposito, PierLuigi; Depiesse, Danielle

    2008-01-01

    In underground working places, especially when ventilation is not properly regulated, large amounts of natural radioactivity can be found. This can give rise to potential exposures of non-negligible magnitude. Direct measurements of gamma radiation and radon were carried out during excavation works for the construction of an hydroelectric plant in the north of Italy. After the construction of the plant, in order to reduce radon concentrations and to improve ventilation effectiveness, the main entry gate was motorized and automated. Then, in order to find the optimal speed for the fans located in the galleries and in the power plant, radon and airflow velocity were measured. Correlation data between airflow and radon concentrations were found. An automatic regulation system has been set up using air velocity detectors and slightly modifying the software for the control and regulation of the power plant. Measurements must be made in order to identify radon sources and evaluate quantitative contributions as a function of ventilation. Underground hydroelectric plants are provided with entry galleries as well as secondary galleries from which radon coming out from the soil and the walls can exhale in quantities that depend on the contents of 226 Ra in the rocks and in the building materials. Other radon sources are the water coming out from the walls of the galleries and the water in the deep well located at the bottom of the power plant. Geological studies and mathematical models are useful means for the analysis of the relative contributions of the main sources as well as for the prediction of the effects deriving from modifications of the hydroelectric plant ventilation system or resulting from other important structural changes. (author)

  16. Natural radioactivity in groundwater--a review.

    Science.gov (United States)

    Dinh Chau, Nguyen; Dulinski, Marek; Jodlowski, Pawel; Nowak, Jakub; Rozanski, Kazimierz; Sleziak, Monika; Wachniew, Przemyslaw

    2011-12-01

    The issue of natural radioactivity in groundwater is reviewed, with emphasis on those radioisotopes which contribute in a significant way to the overall effective dose received by members of the public due to the intake of drinking water originating from groundwater systems. The term 'natural radioactivity' is used in this context to cover all radioactivity present in the environment, including man-made (anthropogenic) radioactivity. Comprehensive discussion of radiological aspects of the presence of natural radionuclides in groundwater, including an overview of current regulations dealing with radioactivity in drinking water, is provided. The presented data indicate that thorough assessments of the committed doses resulting from the presence of natural radioactivity in groundwater are needed, particularly when such water is envisaged for regular intake by infants. They should be based on a precise determination of radioactivity concentration levels of the whole suite of radionuclides, including characterisation of their temporal variability. Equally important is a realistic assessment of water intake values for specific age groups. Only such an evaluation may provide the basis for possible remedial actions.

  17. Supplementary radiological measurements at the Maxey Flats radioactive waste burial site, 1976--1977

    International Nuclear Information System (INIS)

    Blanchard, R.L.; Montgomery, D.M.; Kolde, H.E.; Gels, G.L.

    1978-09-01

    Evaporator effluents were investigated further to better define quantities of radionuclides discharged to the atmosphere and improve decontamination factors assigned to the principal radionuclides observed in the evaporator feed: 3 H, 14 C, 60 Co, 137 Cs, 238 Pu, and 239 Pu. On-site measurements included soil sample profiles taken to a maximum depth of 3.5 m from the trench area and from within the main washes east and south of the site. These measurements provided additional information on the near-surface lateral movement of radioactivity. Radiochemical analysis of a test-well sample showed that all measurable radioactivity was associated with the sediment in the well and the highest specific radioactivity was associated with the smaller particles (< 5 μm). Milk and vegetables were again sampled from a number of nearby farms. As previously reported, tritium was the only radionuclide measured in these foods above ambient levels, although concentrations were less than in similar samples collected during the earlier study. 4 figures, 17 tables

  18. Cementification for radioactive waste including high-concentration sodium sulfate and high-concentration radioactive nuclide

    International Nuclear Information System (INIS)

    Miyamoto, Shinya; Sato, Tatsuaki; Sasoh, Michitaka; Sakurai, Jiro; Takada, Takao

    2005-01-01

    For the cementification of radioactive waste that has large concentrations of sodium sulfate and radioactive nuclide, a way of fixation for sulfate ion was studied comprising the pH control of water in contact with the cement solid, and the removal of the excess water from the cement matrix to prevent hydrogen gas generation with radiolysis. It was confirmed that the sulfate ion concentration in the contacted water with the cement solid is decreased with the formation of ettringite or barium sulfate before solidification, the pH value of the pore water in the cement solid can control less than 12.5 by the application of zeolite and a low-alkali cement such as alumina cement or fly ash mixed cement, and removal of the excess water from the cement matrix by heating is possible with aggregate addition. Consequently, radioactive waste including high-concentration sodium sulfate and high-concentration radioactive nuclide can be solidified with cementitious materials. (author)

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

    International Nuclear Information System (INIS)

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

    1982-05-01

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

  20. Method of solidifying radioactive wastes

    International Nuclear Information System (INIS)

    Fukazawa, Tetsuo; Ootsuka, Masaharu; Uetake, Naoto; Ozawa, Yoshihiro.

    1984-01-01

    Purpose: To prepare radioactive solidified wastes excellent in strength, heat resistance, weather-proof, water resistance, dampproof and low-leaching property. Method: A hardening material reactive with alkali silicates to form less soluble salts is used as a hardener for alkali silicates which are solidification filler for the radioactive wastes, and mixed with cement as a water absorbent and water to solidify the radioactive wastes. The hardening agent includes, for example, CaCO 3 , Ca(ClO 4 ) 2 , CaSiF 6 and CaSiO 3 . Further, in order to reduce the water content in the wastes and reduce the gap ratio in the solidification products, the hardener adding rate, cement adding rate and water content are selected adequately. As the result, solidification products can be prepared with no deposition of easily soluble salts to the surface thereof, with extremely low leaching of radioactive nucleides. (Kamimura, M.)

  1. Evaluation Of Radioactivity Concentration In The Primary Cooling Water System Of The RSG-GAS During Operation With 30% Silicide Fuels

    International Nuclear Information System (INIS)

    Hartoyo, Unggul; Udiyani, P.M.; Setiawanto, Anto

    2001-01-01

    The evaluating radioactivity concentration in the primary cooling water of the RSG-GAS during operation with 30% silicide fuels has been performed. The method of the research is sampling of primary cooling water during operation of the reactor and calculation of its radioactivity concentration. Based on the data obtained from calculation, the identified nuclides in the water are, Mn-56, Sb-124, Sb-122 and Na-24, under the limit of safety value

  2. Results of special radiation measurements resulting from the Chernobyl accident and regional analysis of environmental radioactivity

    International Nuclear Information System (INIS)

    1986-07-01

    This report of the SCPRI exposes an interpretation of the results concerning the monitoring of the environmental radioactivity in France following Chernobyl accident. Atmospheric dusts, milk and milk products, vegetables, water and various beverages are analyzed. More than 1500 additional food samples are presented. Regional analysis of radioactivity and human gamma-spectrometric investigations are included [fr

  3. Survey monitoring of environmental radioactivity in Chuncheon area

    Energy Technology Data Exchange (ETDEWEB)

    Cha, Moon Hoe.; Hwang, Sang Gyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

    2002-12-15

    Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2002 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137}Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs etc. concentrations in the 19 foodstuffs(peanut, chestnut, walnut, pine nut acorn, oak mushroom, western mushroom, winter mushroom, oyster mushroom, coffee, green tea, ginseng tea, soils, cereals, vegetable, indicator plant) and 5 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except {sup 40}K nuclide. All the concentrations of {sup 137}Cs nuclides in the water are less than the MDA values.

  4. Survey monitoring of environmental radioactivity in Chuncheon area

    Energy Technology Data Exchange (ETDEWEB)

    Cha, Moon Hoe.; Hwang, Sang Gyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

    2003-12-15

    Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2003 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137} Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs etc. concentrations in the 22 foodstuffs(peanut, chestnut, walnut, pine nut acorn, oak mushroom, western mushroom, winter mushroom, oyster mushroom, coffee, green tea, ginseng tea, soils, cereals, vegetable, indicator plant) and 10 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except {sup 40}K nuclide. All the concentrations of {sup 137}Cs nuclides in the water are less than the MDA values.

  5. Survey monitoring of environmental radioactivity in Chuncheon area

    International Nuclear Information System (INIS)

    Lee, Byung Ki.; Hwang, Sang Kyu

    2001-12-01

    Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2001 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of 7 Be and 137 Cs on airborne dust, and 7 Be, 40 K and 137 Cs on fallout, precipitation have been analyzed monthly. The 7 Be, 40 K, 137 Cs and 226 Ra etc. concentrations in the 23 foodstuffs(potato, sweet potato, bean sprout, onion, pumpkin, spinach, welsh onion, radish leaves, red pepper, garlic, lettuce, apple, persimmon, orange, pear, grape, mackerel, Alaska pollack, hairtail, squid oyster, baby clam, mussel) and 5 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of 7 Be, 40 K, and 137 Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except 40 K nuclide. All the concentrations of 137 Cs and 226 Ra nuclides in the water are less than the MDA values

  6. Radioactive contamination monitoring device for off-gas in ventilation system

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  7. Environmental radioactivity surveillance programme 1994-1996

    International Nuclear Information System (INIS)

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

    1997-12-01

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

  8. 129I, 60Co, and 106Ru measurements on water samples from the Hanford project environs

    International Nuclear Information System (INIS)

    Brauer, F.P.; Rieck, H.G. Jr.

    1973-01-01

    Groundwater flow and contamination patterns beneath the Hanford project reservation have been studied since the early days of the project. The measurement of radioactive materials at concentrations much below those required for radiation protection are useful for tracing groundwater movement and detection of potential contamination problems before they are apt to occur. Groundwater samples from a number of wells on or near the Hanford reservation have been analyzed for 129 I by neutron activation analysis and for gamma radioactivity by low-level coincidence gamma-ray spectrometry. The major radionuclides in addition to natural radioactivity detected in the underground waters by gamma-ray spectrometry were 106 Ru and 60 Co. Local river and rain water samples were also analyzed for 129 I and long-lived radionuclides. Special sample collection methods were developed to prevent contamination of the water samples during collection. Anions travel farther than cations in underground water systems since soils are primarily cation exchangers and retain the cations. Anion exchange techniques were used in the field and the laboratory to recover the desired radionuclides. Sample sizes ranged up to several thousand liters. This paper discusses the sample collection methods,analysis methods, and results obtained. The methods used were found to provide high sensitivity for groundwater studies. (auth)

  9. The use of radioactive and other tracers in oil and gas measurement

    International Nuclear Information System (INIS)

    Edmonds, E.A.

    1985-01-01

    A description and critical discussion of the use of tracer techniques of flowrate measurement in the oil and gas industries. Radioactive tracers are discussed in particular, with emphasis on the practical aspects of their use. Radiotracers suitable for use in industrial environments are described and discussed. The advantages of radiotracers over conventional chemical tracers are reviewed and the logistical problems associated with the use of radioactive materials are considered. The results of measurements conducted using radiotracers on operating plant and on calibration facilities are presented with a discussion of the accuracy of measurement of flowrate which is achievable: potentially, in ideal circumstances, and in practical situations. The modification of tracer techniques of flow measurement to enable residence time distributions to be evaluated and leaks to be located and quantified on operating process plant is illustrated and discussed. The use of specially synthesized radiochemicals for tracing complex petrochemical processes involving chemical reactions and multiproduct streams is described. The use of novel non-radioactive tracers and specialized detection systems is also described, again with practical illustrations of experience in the field. The benefits offered by the use of these tracers and the limitations encountered are discussed. (author)

  10. Water hyacinth for phytoremediation of radioactive waste simulate contaminated with cesium and cobalt radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Saleh, H.M., E-mail: hosamsaleh70@yahoo.com [Radioisotope Department, Nuclear Research Center, Atomic Energy Authority, Dokki 12311, Giza (Egypt)

    2012-01-15

    Highlights: Black-Right-Pointing-Pointer Phytoremediation of radioactive wastes containing {sup 137}Cs and {sup 60}Co radionuclides. Black-Right-Pointing-Pointer Using water hyacinth for radioactive waste treatment. Black-Right-Pointing-Pointer Bioaccumulation of radionuclides from radioactive waste streams. Black-Right-Pointing-Pointer Factors affecting bioaccumulation of {sup 137}Cs and {sup 60}Co using floating plants. - Abstract: Phytoremediation is based on the capability of plants to remove hazardous contaminants present in the environment. This study aimed to demonstrate some factors controlling the phytoremediation efficiency of live floating plant, water hyacinth (Eichhornia crassipes), towards the effluents contaminated with {sup 137}Cs and/or {sup 60}Co. Cesium has unknown vital biological role for plant while cobalt is one of the essential trace elements required for plant. The main idea of this work i.e. using undesirable species, water hyacinth, in purification of radiocontaminated aqueous solutions has been receiving much attention. The controlling factors such as radioactivity concentration, pH values, the amount of biomass and the light were studied. The uptake rate of radiocesium from the simulated waste solution is inversely proportional to the initial activity content and directly proportional to the increase in mass of plant and sunlight exposure. A spiked solution of pH Almost-Equal-To 4.9 was found to be the suitable medium for the treatment process. The uptake efficiency of {sup 137}Cs present with {sup 60}Co in mixed solution was higher than if it was present separately. On the contrary, uptake of {sup 60}Co is affected negatively by the presence of {sup 137}Cs in their mixed solution. Sunlight is the most required factor for the plant vitality and radiation resistance. The results of the present study indicated that water hyacinth may be a potential candidate plant of high concentration ratios (CR) for phytoremediation of radionuclides

  11. Measurement of radioactivity in the atmosphere and pollution nearby an atomic centre

    International Nuclear Information System (INIS)

    Labeyrie, J.; Weill, J.

    1955-01-01

    The French Atomic Energy Commission (CEA) is particularly interested in studies on atmospheric radioactivity by reason of the necessity to control the atmosphere nearby nuclear plants as uranium mines, nuclear reactors and hot laboratories or radioactive materials treatment plants. Thus, the CEA developed different apparatus to control and monitor the atmosphere nearby its sites. These air monitors are essentially of two types: the first one, called 'Babar', monitors smokes, fogs and dusts, the second type is an ionization chamber and measures the concentration of radioactive gas in the air. The functioning and sensitivity of these two systems are discussed. (M.P.)

  12. Radioactivity in surface and coastal waters of the British Isles, 1988

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1989-01-01

    This report presents the results of the aquatic environmental monitoring programme performed during 1988 by the Ministry of Agriculture, Fisheries and Food's (MAFF's) Directorate of Fisheries Research (DFR). Radioactivity measurements are made in aquatic organisms and environmental materials in the vicinity of nuclear establishments including BNFL, UKAEA, nuclear power stations operated by the electricity boards, defence establishments and Amersham International. A summary of estimated public radiation exposures in 1988, relating to liquid radioactive waste discharges from nuclear establishments is presented. (UK)

  13. GEMS: Underwater spectrometer for long-term radioactivity measurements

    Energy Technology Data Exchange (ETDEWEB)

    Sartini, Ludovica, E-mail: ludovica.sartini@ingv.i [Istituto Nazionale di Geofisica e Vulcanologia (INGV), Sect.Roma 2, Roma (Italy); Genoa University, Genoa (Italy); Simeone, Francesco; Pani, Priscilla [' Sapienza' University and Istituto Nazionale di Fisica Nucleare (INFN), Sect.Roma, Roma (Italy); Lo Bue, Nadia; Marinaro, Giuditta [Istituto Nazionale di Geofisica e Vulcanologia (INGV), Sect.Roma 2, Roma (Italy); Grubich, Andry; Lobko, Alexander [Institute for Nuclear Problems (INP), Belarus State University, Minsk (Belarus); Etiope, Giuseppe [Istituto Nazionale di Geofisica e Vulcanologia (INGV), Sect.Roma 2, Roma (Italy); Capone, Antonio [' Sapienza' University and Istituto Nazionale di Fisica Nucleare (INFN), Sect.Roma, Roma (Italy); Favali, Paolo [Istituto Nazionale di Geofisica e Vulcanologia (INGV), Sect.Roma 2, Roma (Italy); Gasparoni, Francesco; Bruni, Federico [Tecnomare S.p.A., Venice (Italy)

    2011-01-21

    GEMS (Gamma Energy Marine Spectrometer) is a prototype of an autonomous radioactivity sensor for underwater measurements, developed in the framework for a development of a submarine telescope for neutrino detection (KM3NeT Design Study Project). The spectrometer is highly sensitive to gamma rays produced by {sup 40}K decays but it can detect other natural (e.g., {sup 238}U,{sup 232}Th) and anthropogenic radio-nuclides (e.g., {sup 137}Cs). GEMS was firstly tested and calibrated in the laboratory using known sources and it was successfully deployed for a long-term (6 months) monitoring at a depth of 3200 m in the Ionian Sea (Capo Passero, offshore Eastern Sicily). The instrument recorded data for the whole deployment period within the expected specifications. This monitoring provided, for the first time, a continuous time-series of radioactivity in deep-sea.

  14. Surface temperature measurement with radioactive kryptonates

    International Nuclear Information System (INIS)

    Pruzinec, J.; Piatrik, M.

    1976-01-01

    The preparation and use of radioactive kryptonates is described for measuring surface temperatures within the region of 45 to 70 degC. Two samples each were prepared of kryptonated beechwood and hydroquinone on a paper carrier. One sample served as the standard which during the experiment was placed in a thermostat at a constant temperature of 45 degC. The second sample was placed in another thermostat where the temperature changed from 45 to 70 degC. Both samples were in the thermostat for 30 mins. The temperature was raised in steps of 2.5 degC and the time of measurement was constant in both samples. The dependences are given of the drop in activity on temperature for both types of samples. The difference was determined of the drop in activity between the standard and the second sample and the relation for measuring the temperature of the sample was determined therefrom. (J.B.)

  15. Declassification of radioactive water from a pool type reactor after nuclear facility dismantling

    Science.gov (United States)

    Arnal, J. M.; Sancho, M.; García-Fayos, B.; Verdú, G.; Serrano, C.; Ruiz-Martínez, J. T.

    2017-09-01

    This work is aimed to the treatment of the radioactive water from a dismantled nuclear facility with an experimental pool type reactor. The main objective of the treatment is to declassify the maximum volume of water and thus decrease the volume of radioactive liquid waste to be managed. In a preliminary stage, simulation of treatment by the combination of reverse osmosis (RO) and evaporation have been performed. Predicted results showed that the combination of membrane and evaporation technologies would result in a volume reduction factor higher than 600. The estimated time to complete the treatment was around 650 h (25-30 days). For different economical and organizational reasons which are explained in this paper, the final treatment of the real waste had to be reduced and only evaporation was applied. The volume reduction factor achieved in the real treatment was around 170, and the time spent for treatment was 194 days.

  16. Ecological transport and radiation doses from ground water borne radioactive matters

    International Nuclear Information System (INIS)

    Bergman, R.; Bergstroem, U.; Evans, S.

    1978-12-01

    Turnover of radioactive matter entering the biosphere with ground water has been studied with regard to exposure and dose to critical groups and populations. The main alternatives considered for outflow of radioactive effluents to the biosphere are: outflow in a valley containing wells, outflow to a fresh-water lake, and outflow in a coastal region of the Baltic Sea. Mathematical models of a set of coupled ecosystems on local, regional- intermediate- and global levels have been used for calculations of doses. The intermediate system refers to the Baltic Sea. The mathematical analysis, based on first order kinetics for the exchange of matter in a system according to compartment principles, also includes products in decay chains, i.e. daughter nuclides generated by decay of nuclides under ecological cycling. The time dependent exposures have been studied for certain long-lived nuclides of radiological interest in waste from reprosessed fuel. Dose and dose commitment have been calculted for different release patterns comprising idealised episodes for outflow to the biosphere during short periods and outflow governed by constant leakage from a source on the border between geosphere and biosphere. (author)

  17. Positron emission medical measurements with accelerated radioactive ion beams

    International Nuclear Information System (INIS)

    Llacer, J.

    1988-01-01

    This paper reviews in some detail the process by which a heavy ion accelerator can be used to inject positron emitting radioactive particles into a human body for a range of possible medical measurements. The process of radioactive beam generation and injection is described, followed by a study of the relationship between activity that can be injected versus dose to the patient as a function of which of the positron emitting ions is used. It is found that 6 C 10 and 10 Ne 19 are the two isotopes that appear more promising for injection into humans. The design considerations for a non-tomographic instrument to obtain images from beam injections are outlined and the results of 10 Ne 19 preliminary measurements with human phantoms and actual patients for the determination of end-of-range of cancer therapy ion beams is reported. Accuracies in the order of ±1 mm in the measurements of stopping point of a therapy beam with safe doses to the patient are reported. The paper concludes with a simple analysis of requirements to extend the technique to on-line verification of cancer treatment and to nuclear medicine research and diagnostics measurements. 17 refs.; 16 figs.; 3 tabs

  18. The behavior of radioactive iodine at the time of reactor accident and its counterplan

    International Nuclear Information System (INIS)

    Murata, Toshifumi

    1974-01-01

    When an accident occurs in a reactor, very volatile radioactive iodine is most dangerous among fission products. Among the isotopes of radioactive iodine, 131 I which has longer half-life is harmful. Supposing one-tenth of the radioactivity of 10 8 Ci in a reactor of 10 6 Kw heat output is due to 131 I, it weights about 100g. The behavior of the radioactive iodine is greatly subjected to the influence of inside temperature and other conditions. Therefore, very prudent policies are adopted by installing emergency core cooling system, containment vessels, and activated carbon filters. For the emergency core cooling system, water spraying, flooding with low pressure water, and maintaining of water level by high pressure water injection are adopted, while in the containment vessels, measures are taken so as to lower the inside pressure and minimize leakage. (Kobatake, H.)

  19. Quality assurance in nuclear medicine radioactivity measurements

    International Nuclear Information System (INIS)

    Sahagia, Maria; Razdolescu Anamaria Cristina

    2007-01-01

    The paper presents some recent results of the Radionuclide Metrology Laboratory (RML) from IFIN-HH, in the assurance of quality in radioactivity measurements for nuclear medicine. Three aspects are treated: (i) Participation of the RML in the frame of the IAEA Coordinated Research Program (CRP), E 2.10.05; (ii) Improvement of the secondary standard, based on a CENTRONIC IG12/20A ionization chamber; (iii) Implementation of the quality management, according to the SR EN ISO/IEC 17025:2005. (authors)

  20. Annual effective dose due to natural radioactivity in drinking water

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  1. Radioactive contamination in the environs of the Hanford Works for the period October, November, December 1949

    Energy Technology Data Exchange (ETDEWEB)

    Paas, H.J.; Singlevich, W.

    1950-03-02

    This report summarizes the measurements made for radioactive contamination in the environs of the Hanford Works. The principal sources of the radioactivity originating as a result of operations at Hanford which affect the environment in this area are the two waste stacks in the separations area and the cooling water from the four pile areas. Measurements are also made on samples taken from the Hanford waste systems which are primarily confined within the project proper. Although monthly summaries of these data are reported in Health Instrument Divisions Environs reports, a somewhat more detailed discussion of these data is covered in the quarterly report. In this manner, a better evaluation of possible trends can be detected as a result of the increased number of measurements made available by combining the data for a three month period. The following areas are discussed: meteorology, radioactive contamination of vegetation, airborne contamination and air radiation levels, radioactive contamination in Hanford wastes, radioactive contamination in the Columbia and Yakima rivers; beta activity in rain and snow, and radioactive contamination in drinking water and test wells.

  2. Environmental radioactivity in Greenland in 1981

    International Nuclear Information System (INIS)

    Aarkrog, A.; Dahlgaard, H.; Hansen, H.; Lippert, J.; Nilsson, K.; Holm, E.

    1982-07-01

    Measurements of fallout radioactivity in Greenland in 1981 are reported. Strontium-90 (and Cesium-137 in most cases) was determined in samples of precipitation, sea water, vegetation, animals, and drinking water. Estimates are given of the mean contents of 90 Sr and 137 Cs in the human diet in Greenland in 1981. Further results of the 239 , 240 Pu and 241 Am measurements on samples from the expedition to Thule in August 1979 are prsented. Brown algae collected in East Greenland in 1969 were analysed for Pu and Am. (author)

  3. Radioactivity in groundwater along the borders of Oman and UAE

    International Nuclear Information System (INIS)

    Murad, A.; Alshamsi, D.; Al Shidi, F.; Al Kendi, R.; Aldahan, A.; Uppsala University, Uppsala

    2014-01-01

    Characterizing the quality and radioactivity of groundwater is vital as it represents valuable resource in arid regions. Here we present radioactivity level in groundwater collected from wells in a region along the border between Sultanate of Oman and United Arab Emirates (UAE). The aquifers are alluvium deposits (silt, sand and gravel) and the measured groundwater radioactivity (including 232 Th, 238 U, 235 U, 226 Ra, 222 Rn, gross-α and gross-β) indicates values below the WHO permissible limits for drinking water. The results also show large difference in radioactivity fingerprints, in particular for 226 Ra and 222 Rn within the investigated aquifers. The data further indicate lower radioactivity in groundwater of the alluviums compared to the carbonate aquifers in the region. This feature makes the alluvium aquifers valuable reservoirs that should be carefully exploited as a source of groundwater. As this is the first investigation on the radioactivity of groundwater in alluvial aquifers in the region, it suggests that other alluvial deposits, particularly those inland and far from the marine water intrusion or seepage from carbonate rocks would have low radioactivity fingerprints. (author)

  4. Measurements of radon and radium activity in bottled mineral water

    Energy Technology Data Exchange (ETDEWEB)

    Kappke, Jaqueline; Paschuk, Sergei A.; Correa, Janine N.; Reque, Marilson; Tabuchi, Camila Garcia; Del Claro, Flavia; Perna, Allan Felipe, E-mail: jaquelinekappke@gmail.com [Universidade Tecnologica Federal do Parana (UTFPR), Curitiba, PR (Brazil); Deniak, Valeriy [Instituto de Pesquisa Pele Pequeno Principe, Curitiba, PR (Brazil)

    2013-07-01

    Current work presents the results of further development of optimized experimental protocol for RAD7 instant radon detector (Durridge Company Inc.) usage in low level radon in water measurements and the results concerning Ra-226 activity evaluation in bottled mineral water samples purchased at Brazilian market. With the purpose to achieve the statistically consistent results for the activity levels of 0.1Bq/L for radon (radium) activity in water, present study used modified experimental protocol which consists of: 1) water samples were stored in hermetically sealed glass vials of 250mL during 30 days to guarantee that Rn-222 will reach the secular equilibrium; 2) the measurements were performed using WAT250 protocol of RAD7 detector; 3) with an aim to decrease the background, the cleaning (activated carbon filter) and drying (DRIERITE desiccant) vessels, which have a function to retain the radioactive decay product of Rn-222 and humidity, were connected to a closed air loop of RAD7 permanently by means of valves and taps, which gave a possibility to repeat all sequence of measurements (including background evaluation) three or four times without to open the air loop and disconnect the sample vial with water. Each water sample was submitted to such measurements two or three times. Obtained results presented the level of Ra-226 activity in studied samples of bottled mineral water that varied from 0.007 ± 0.061 Bq/L to 0.145 ± 0.049 Bq/L, which is below the limit of 0,5 Bq/L established by the World Health Organization (WHO) in 2011 for drinking water. (author)

  5. Measurements of radon and radium activity in bottled mineral water

    International Nuclear Information System (INIS)

    Kappke, Jaqueline; Paschuk, Sergei A.; Correa, Janine N.; Reque, Marilson; Tabuchi, Camila Garcia; Del Claro, Flavia; Perna, Allan Felipe; Deniak, Valeriy

    2013-01-01

    Current work presents the results of further development of optimized experimental protocol for RAD7 instant radon detector (Durridge Company Inc.) usage in low level radon in water measurements and the results concerning Ra-226 activity evaluation in bottled mineral water samples purchased at Brazilian market. With the purpose to achieve the statistically consistent results for the activity levels of 0.1Bq/L for radon (radium) activity in water, present study used modified experimental protocol which consists of: 1) water samples were stored in hermetically sealed glass vials of 250mL during 30 days to guarantee that Rn-222 will reach the secular equilibrium; 2) the measurements were performed using WAT250 protocol of RAD7 detector; 3) with an aim to decrease the background, the cleaning (activated carbon filter) and drying (DRIERITE desiccant) vessels, which have a function to retain the radioactive decay product of Rn-222 and humidity, were connected to a closed air loop of RAD7 permanently by means of valves and taps, which gave a possibility to repeat all sequence of measurements (including background evaluation) three or four times without to open the air loop and disconnect the sample vial with water. Each water sample was submitted to such measurements two or three times. Obtained results presented the level of Ra-226 activity in studied samples of bottled mineral water that varied from 0.007 ± 0.061 Bq/L to 0.145 ± 0.049 Bq/L, which is below the limit of 0,5 Bq/L established by the World Health Organization (WHO) in 2011 for drinking water. (author)

  6. Environmental radioactivity measurements in greece following the Fukushima Daichi nuclear accident

    International Nuclear Information System (INIS)

    Potiriadis, C.; Kolovou, M.; Clouvas, A.; Xanthos, S.

    2008-01-01

    Since the double disaster of the 9.0 magnitude earthquake and tsunami that affected hundreds of thousands of people and seriously damaged the Fukushima Daichi power plant in Japan on 11 March 2011, traces of radioactive emissions from Fukushima have spread across the entire northern hemisphere. The radioactive isotope of iodine 131 I that was generated by the nuclear accident in Fukushima arrived in Greece on 24 March 2011. Radioactive iodine is present in the air either as gas or bound to particles (aerosols). The maximum 131 I concentrations were measured between 3 and 5 April 2011. In aerosols the maximum 131 I values measured in Southern Greece (Athens) and Northern Greece (Thessaloniki) were 585±70 and 408±61 μBq m -3 , respectively 131 I concentrations in gas were about 3.5 times higher than in aerosols. Since 29 April 2011, the 131 I concentration has been below detection limits. Traces of 137 Cs and 134 Cs were also measured in the air filters with an activity ratio of 137 Cs/ 134 Cs equal to 1 and 131 I/ 137 Cs activity ratio of about 3. Since 16 May 2011, the 137 Cs concentration in air has been determined to be about the same as before the Fukushima accident. Traces of 131 I were also measured in grass and milk. The maximum measured activity of 131 I in sheep milk was about 2 Bq l -1 which is 5000 times less than that measured in Greece immediately after the Chernobyl accident. The measured activity concentrations of artificial radionuclides in Greece due to the Fukushima release, have been very low, with no impact on human health. (authors)

  7. Water old and new

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1964-12-15

    Part of a collection of rain-water samples obtained for the IAEA/World Meteorological Organization global project for the determination of the concentration of hydrogen and oxygen isotopes in rain-water. Samples are collected monthly at about 100 stations all over the world, and are analyzed for tritium (radioactive hydrogen) concentration at the Agency 's laboratory and some other advanced laboratories. The purpose is to study the circulation pattern of water vapour and to measure the tritium concentration of rain-water in different parts of the world. This knowledge is needed for solving local, regional and global problems of water supply. Containers labelled 'dead water' contain no tritium. This water is used to check the counting equipment in order to ensure consistent measurement, and to assess background radiation. Tritium is produced in the atmosphere in nature and by nuclear testing, and is brought down by rainfall. In a particular water body, absence of tritium or a lower-than-normal concentration, indicates the radioactive decay (loss of radioactivity) of the original tritium without fresh injection of tritium from rain - i.e., the water would be old. As the rate of decay of tritium is known, the measurement of tritium can solve problems of hydrological chronology.

  8. 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

  9. The estimation of uncertainty of radioactivity measurement on gamma counters in radiopharmacy

    International Nuclear Information System (INIS)

    Jovanovic, M.S.; Orlic, M.; Vranjes, S.; Stamenkovic, Lj. . E-mail address of corresponding author: nikijov@vin.bg.ac.yu; Jovanovic, M.S.)

    2005-01-01

    In this paper the estimation of uncertainty of measurement of radioactivity on gamma counter in Laboratory for radioisotopes is presented. The uncertainty components, which are important for these measurements, are identified and taken into account while estimating the uncertainty of measurement.(author)

  10. 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

  11. [Assessment of cyto- and genotoxicity of natural waters in the vicinity of radioactive waste storage facility using Allium-test].

    Science.gov (United States)

    Udalova, A A; Geras'kin, S A; Dikarev, V G; Dikareva, N S

    2014-01-01

    Efficacy of bioassays of "aberrant cells frequency" and "proliferative activity" in root meristem of Allium cepa L. is studied in the present work for a cyto- and genotoxicity assessment of natural waters contaminated with 90Sr and heavy metals in the vicinity of the radioactive waste storage facility in Obninsk, Kaluga region. The Allium-test is shown to be applicable for the diagnostics of environmental media at their combined pollution with chemical and radioactive substances. The analysis of aberration spectrum shows an important role of chemical toxicants in the mutagenic potential of waters collected in the vicinity of the radioactive waste storage facility. Biological effects are not always possible to explain from the knowledge on water contamination levels, which shows limitations of physical-chemical monitoring in providing the adequate risk assessment for human and biota from multicomponent environmental impacts.

  12. Routine surveillance of environmental radioactivity in the influence area of the institute during 1996

    International Nuclear Information System (INIS)

    Breban, Domnica; Breban Ioana

    1997-01-01

    The radioactivity measurements were performed according to the Monitoring Plan for nuclear units in NIPNE-HH, which provides the type, locations and sampling frequency of the environmental factors which were analyzed. Samples of water, sediment, soil, and vegetation were analyzed for both gross beta and gamma activity, as follows: - 1010 samples of potential radioactive water (surface, drinking and underground water); - 35 sediment and 98 soil samples; - 48 samples of spontaneous vegetation and 16 samples of milk, salad, potatoes, cabbage and maize. Radiochemical analysis of Sr-90 in surface, sewage water and milk was performed. Gamma spectrometric measurements were also carried out in water and sediment samples. We analyzed for gross beta and gamma activity 238 samples of radioactive liquid effluents from the two nuclear units of the Institute, Radioisotope Production Centre and Station for Radioactive Waste Treatment. No significant difference between the gross activity of soil and vegetation samples collected from the area of influence and those from the reference site (Bucharest) were observed. The variation of the gross beta activity in the surface water, sampled upstream and downstream to the site where the wastes effluents are discharged is presented. The activity of the downstream river water has always been situated below the maximum admissible level (MAL = 1.80 Bq/l), hence we can conclude that the nuclear activity developed on Magurele Platform did not lead to the river contamination. (authors)

  13. 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

  14. Hair radioactivity as a measure of exposure to radioisotopes

    Science.gov (United States)

    Strain, W. H.; Pories, W. J.; Fratianne, R. B.; Flynn, A.

    1972-01-01

    Since many radioisotopes accumulate in hair, this tropism was investigated by comparing the radioactivity of shaved with plucked hair collected from rats at various time intervals up to 24 hrs after intravenous injection of the ecologically important radioisotopes, iodine-131, manganese-54, strontium-85, and zinc-65. The plucked hair includes the hair follicles where biochemical transformations are taking place. The data indicate a slight surge of each radioisotpe into the hair immediately after injection, a variation of content of each radionuclide in the hair, and a greater accumulation of radioactivity in plucked than in shaved hair. These results have application not only to hair as a measure of exposure to radioisotopes, but also to tissue damage and repair at the hair follicle.

  15. Radioactive waste storage facility and underground disposal method for radioactive wastes using the facility

    International Nuclear Information System (INIS)

    Endo, Yoshihiro.

    1997-01-01

    A sealed container storage chamber is formed in underground rocks. A container storage pool is formed on the inner bottom of the sealed vessel storage chamber. A heat exchanger for cooling water and a recycling pump are disposed on an operation floor of the sealed vessel storage chamber. Radioactive wastes sealed vessels in which radioactive wastes are sealed are transferred from the ground to the sealed vessel storage chamber through a sealed vessel transferring shaft, and immersed in cooling water stored in the vessel storage pool. When after heat of the radioactive wastes is removed by the cooling water, the cooling water in the vessel storage pool is sucked up to the ground surface. After dismantling equipments, bentonite-type fillers are filled in the inside of the sealed vessel storage chamber, sealed vessel transferring shaft, air supplying shaft and air exhaustion shaft, and the radioactive waste-sealed vessels can be subjected stably to into underground disposal. (I.N.)

  16. Small zeolite column tests for removal of cesium from high radioactive contaminated water in Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

    Hijikata, Takatoshi; Uozumi, Koichi; Tukada, Takeshi; Koyama, Tadafumi; Ishikawa, Keiji; Ono, Shoichi; Suzuki, Shunichi; Denton, Mark; Raymont, John

    2011-01-01

    After the earthquake on March 11th 2011, a large amount (more than 0.12 million m 3 ) of highly radioactive contaminated water had pooled in Fukushima Daiichi nuclear power station. As an urgent issue, highly radioactive nuclides should be removed from this contaminated water to reduce radioactivity in the turbine buildings and nuclear reactor buildings. Removal of Cs from this contaminated water is a key issue, because 134 Cs and 137 Cs are highly radioactive γ-emitting nuclides. The zeolite column system was used for Cs and Sr removal from the radioactive water of Three-Mile Island Unit 2, and modified columns were then developed as a Cs removal method for high-level radioactive water in US national laboratories (WRSC, ORNL, PNNL, Hanford, etc.). In order to treat Fukushima's highly contaminated water with a similar system, it was necessary to understand the properties of zeolite to remove Cs from sea salt as well as the applicability of the column system to a high throughput of around 1200 m 3 /d. The kinetic characteristics of the column were another property to be understood before actual operation. Hence, a functional small-scale zeolite column system was installed in CRIEPI for conducting the experiments to understand decontamination behaviors. Each column has a 2- or 3-cm inner diameter and a 12-cm height, and 12 g of zeolite-type media was packed into the column. The column experiments were carried out with Kurion-zeolite, Herschelite, at different feed rates of simulated water with different concentrations of Cs and sea salt. As for the water with 4 ppm Cs and 0 ppm sea salt, only a 10% Cs concentration was observed in the effluent after 20,000 bed volumes were fed at a rate of 33 cm/min, which corresponds to the actual system. On the other hand, a 40% Cs concentration was observed in the effluent after only 50 bed volumes were passed for water with 2 ppm Cs and 3.4 wt.% sea salt at a feed rate of 34 cm/min. As the absorption of Cs is hampered by the

  17. 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)

  18. Comparison between ex situ and in situ measurement methods for the assessment of radioactively contaminated land. Comparison between measurement methods for the characterisation of radioactively contaminated land

    International Nuclear Information System (INIS)

    Rostron, Peter D.; Ramsey, Michael H.; Heathcote, John A.

    2012-01-01

    In the UK, it is estimated that there may be 20,000,000 cubic metres of contaminated land at Sellafield alone. Harwell and Dounreay are known to have significant amounts of radioactive or nonradioactive contaminated land (NDA, 2006). It is therefore important to devise optimal methods for the characterisation of areas of land for radionuclide content, in order to enable cost-effective decommissioning. With chemical contaminants, ex situ measurements are made on a larger volume of soil than are in situ measurements, such as PXRF. However, the opposite is often true for the characterisation of radioactive contamination, when this involves the detection of penetrating radiation from γ-emitting radionuclides. This means that when investigating for hotspots of radioactive contamination at or near the ground surface, better coverage can be obtained using in situ methods. This leads to the question, what is the optimal strategy (e.g. percentage coverage, counting time) for in situ characterisation of radioactively contaminated land' Surveys on light-moderate contaminated areas of ground were conducted at Dounreay in order to compare the relative effectiveness of in situ and ex situ methods, both for the detection of radioactive hotspots and also for estimating the average radionuclide content of an area of ground. These surveys suggest that continuous coverage by in situ devices is more effective at hotspot detection, with ex situ laboratory measurements being less effective, although in one case elevated activity below 10 cm depth that was identified by ex situ measurement was not located by in situ measurement. The surveys also highlighted that careful choice of an appropriate spatial model is critical to the estimation of activity concentrations over averaging areas. Whereas continuous coverage may be considered necessary for hotspot identification, in the particular case of the detection of hot particles (where the particle is very small compared to the sampling

  19. International guidance on the establishment of quality assurance programmes for radioactivity measurement in nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Zimmerman, B.E. [Dosimetry and Medical Radiation Physics Section, Division of Human Health, International Atomic Energy Agency, Wagramer Strasse 5, P.O. Box 200, A-1400 Vienna (Austria)]. E-mail: b.zimmerman@iaea.org; Herbst, C. [Department of Medical Physics, University of the Free State, Geneeskundige Fisika G 68, Bloemfontein 9300 (South Africa); Norenberg, J.P. [College of Pharmacy, 2502 Marble, NE MSC09 5360, University of New Mexico, Albuquerque 87131 (United States); Woods, M.J. [Ionizing Radiation Consultants, Ltd., 152 Broom Road, Teddington, Middlesex TW11 9PQ (United Kingdom)

    2006-10-15

    A new guidance document for the implementation of quality assurance (QA) programmes for nuclear medicine radioactivity measurement, produced by the International Atomic Energy Agency, is described. The proposed programme is based on the principles of ISO 17025 and will enable laboratories, particularly in developing countries, to provide consistent, safe and effective radioactivity measurement services to the nuclear medicine community.

  20. International guidance on the establishment of quality assurance programmes for radioactivity measurement in nuclear medicine

    International Nuclear Information System (INIS)

    Zimmerman, B.E.; Herbst, C.; Norenberg, J.P.; Woods, M.J.

    2006-01-01

    A new guidance document for the implementation of quality assurance (QA) programmes for nuclear medicine radioactivity measurement, produced by the International Atomic Energy Agency, is described. The proposed programme is based on the principles of ISO 17025 and will enable laboratories, particularly in developing countries, to provide consistent, safe and effective radioactivity measurement services to the nuclear medicine community