WorldWideScience

Sample records for determining radioactive substances

  1. Process and device for determining the spatial distribution of a radioactive substance

    International Nuclear Information System (INIS)

    1977-01-01

    This invention describes a process for determining the spatial distribution of a radioactive substance consisting in determining the positions and energy losses associated to the interactions of the Compton effect and the photoelectric interactions that occur owing to the emission of gamma photons by the radioactive material and in deducing an information on the spatial distribution of the radioactive substance, depending on the positions and energy losses associated to the interactions of the Compton effect of these gamma photons and the positions and energy losses associated to the subsequent photoelectric interactions of these same photons. The invention also concerns a processing system for identifying, among the signals representing the positions and energy losses of the interactions of the Compton effect and the photoelectric interactions of the gamma photons emitted by a radioactive source, those signals that are in keeping with the gamma photons that have been subjected to an initial interaction of the Compton effect and a second and last photoelectric interaction. It further concerns a system for determining, among the identified signals, the positions of the sources of several gamma photons. This detector of Compton interaction can be used with conventional Auger-type imaging system (gamma camera) for detecting photoelectric interactions [fr

  2. Comparative animal studies for the determination of the extracellular space with several radioactively labelled substances

    International Nuclear Information System (INIS)

    Pippart, S.

    1973-01-01

    The volume of the total extracellular space and of the extracellular space of the organs (liver, lungs, heart, spleen, brain) was determined with the aid of 5 radioactively labelled substances, each in 10 rats. The test substances (inulin- 3 H, 51 Cr-EDTA, thiosulfate- 35 S, NH 4 - 82 Br, 60 Co-vitamin B 12 ) are described in the relevant literature as substances for the determination of the extracellular space and as clearance substances. (BSC/AK) [de

  3. Comparative animal studies for the determination of the extracellular space with several radioactively labelled substances

    Energy Technology Data Exchange (ETDEWEB)

    Pippart, S

    1973-01-01

    The volume of the total extracellular space and of the extracellular space of the organs (liver, lungs, heart, spleen, brain) was determined with the aid of 5 radioactively labelled substances, each in 10 rats. The test substances (inulin-/sup 3/H, /sup 51/Cr-EDTA, thiosulfate-/sup 35/S, NH/sub 4/-/sup 82/Br, /sup 60/Co-vitamin B/sub 12/) are described in the relevant literature as substances for the determination of the extracellular space and as clearance substances.

  4. Transport of radioactive substances

    International Nuclear Information System (INIS)

    2014-12-01

    The report on the transport of radioactive substances covers the following topics: facts on radioactive materials transport, safety of the transport of radioactive substances, legal regulations and guidelines: a multiform but consistent system, transport of nuclear fuels, safety during the transport of nuclear fuel, future transport of spent fuel elements and high-level radioactive wastes in Germany.

  5. Determination of substances by radiothermometric titration

    International Nuclear Information System (INIS)

    Tolgyessy, J.; Lesny, J.

    1976-01-01

    For determination, nitrogen is bubbled through a solution containing radioactive Kr, Xe, Rn or another aerogen in addition to the substance determined. A continuous or intermittent addition of the titrating solution results in the release of reaction heat, thus increasing the temperature of the reaction mixture, which releases a radioactive gas. Upon reaching the equivalence point, the cold titrating reagent cools the reaction mixture, thus reducing the radioactive substance release. The equivalence point lies at the point of intersection of the extended linear parts of the curve of the dependence of released radioactivity on the volume of the titrating solution added. (M.K.)

  6. Analysis of determination modalities concerning the exposure and emission limits values of chemical and radioactive substances

    International Nuclear Information System (INIS)

    Schieber, C.; Schneider, T.

    2002-08-01

    This document presents the generic approach adopted by various organizations for the determination of the public exposure limits values to chemical and radioactive substances and for the determination of limits values of chemical products emissions by some installations. (A.L.B.)

  7. A method and apparatus for preparing the storage of noxious substances, in particular radioactive substances

    International Nuclear Information System (INIS)

    1974-01-01

    The invention relates to the storage of radioactive substances. It deals with a method for storing a substance, in particular a noxious or radioactive substance, comprising trapping said substance in a solid substance by bombarding said solid substance with ions of the above substance, so that the latter reaches a certain concentration level in the solid substance. This is applicable to the storage of radioactive wastes [fr

  8. A container for containing and protecting a radioactive substance

    International Nuclear Information System (INIS)

    1974-01-01

    The invention relates to a container adapted to contain and protect a radio-active substance. That container comprises a heat sensitive device for automatically (and, preferably, sealingly) enclosing and protecting the radio-active substance, should room temperature reach a predetermined level. Thus, the radio-active substance cannot escape in case of fire. Preferably, a bolt is also provided, capable of being actuated at a temperature slightly above the temperature actuating the protective device so as to maintain the radioactive substance protected. This can be applied to containers containing a radio-active substance such as polonium 210 [fr

  9. Radioactive Substances Act 1948

    International Nuclear Information System (INIS)

    1948-01-01

    This Act regulates the use of radioactive substances and radiation producing devices in the United Kingdom. It provides for the control of import, export, sale, supply etc. of such substances and devices and lays down the safety regulations to be complied with when dealing with them. (NEA) [fr

  10. Device for ray diagnosis for determining the distribution of radioactive substances

    International Nuclear Information System (INIS)

    Heinz, L.

    1976-01-01

    A ray diagnosing device for determining the distribution of radioactive substances in a body has a measuring head containing the ray probe, means for moving the head for a scanning line by line of the part to be examined, a setting device for the line distance and a printer actuated by the ray probe for inscribing an image corresponding to the activity distribution upon a writing sheet. The invention is particularly characterized in that the printer has a number of printing keys each of which is made to correspond to a specific line spacing and that there is an adjusting device for selectively switching on and off each one of the keys

  11. Transport of radioactive substances; Der Transport radioaktiver Stoffe

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-12-15

    The report on the transport of radioactive substances covers the following topics: facts on radioactive materials transport, safety of the transport of radioactive substances, legal regulations and guidelines: a multiform but consistent system, transport of nuclear fuels, safety during the transport of nuclear fuel, future transport of spent fuel elements and high-level radioactive wastes in Germany.

  12. Analysis of determination modalities concerning the exposure and emission limits values of chemical and radioactive substances; Analyse des modalites de fixation des valeurs limites d'exposition et d'emission pour les substances chimiques et radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Schieber, C.; Schneider, T

    2002-08-01

    This document presents the generic approach adopted by various organizations for the determination of the public exposure limits values to chemical and radioactive substances and for the determination of limits values of chemical products emissions by some installations. (A.L.B.)

  13. The existing state of sewage sludge containing radioactive substances

    International Nuclear Information System (INIS)

    Shirasaki, Makoto; Hisaoka, Natsuki

    2012-01-01

    Radioactive substances were discharged over a wide range from the accident of the Fukushima Daiichi Nuclear Station of Tokyo Electric Power Company. As a result, in sewer system, especially in the combined sewer system that jointly collects rainwater and sewage, radioactive substances accumulated on the surface of urban areas were transferred together with rainwater to sewage plants and accumulated there. In the process of further treatment, radioactive substances were transferred to and concentrated in sewage sludge, and a high concentration of radioactive substances were detected in incineration ash. For this reason, some sewage plants still continuously store dewatered sludge, incinerator ash, etc. This paper introduces the current state of waste treatment from the published data from each local government in Tohoku and Kanto districts. As for the sewer, which is essential as a lifeline, the Ministry of Land, Infrastructure, Transport and Tourism, together with the Japan Sewage Works Association, established 'Investigative Commission on Radioactive Substance Countermeasures in Sewerage System.' This group grasped the damage situation due to radioactive substances, and summarized the measures to be taken by sewage managers, such as the storage method for sewage sludge containing radioactive substances as well as the method for the volume reduction of sewage sludge. (O.A.)

  14. An action plan for radioactive substances regulation

    International Nuclear Information System (INIS)

    1998-01-01

    This document sets out an action plan for the Agency's Radioactive Substances Regulation function. Our vision is to secure continuous improvement in the protection of the public and the environment from the harmful effects of radioactive substances. Radioactive Substances Regulation will work with others to realise this vision and contribute to the Agency's role in achieving sustainable development. We will also work to ensure that the Agency achieves its objectives in an efficient, consistent and integrated way. The main elements of our Action Plan are as follows: establishing indicators of sustainability and the means and methods of monitoring them; establishing performance indicators and a programme of targets and objectives to be achieved; establishing a database of all premises subject to RSA93 and to use it for work planning, resource targeting, and improvement to radioactive waste management; provision of systems of procedures and technical guidance to ensure nationally consistent and cost- effective regulation; establishing systems to audit the implementation of the procedures and guidance; ensuring quality of regulation by defining technical competencies of inspectors and the training programmes to secure them; an R and D programme targeted on improving radioactive waste management and radioactive substances regulation; and full and effective participation in development of national policy

  15. Charging scheme for Radioactive Substances Act regulation 1998-1999

    International Nuclear Information System (INIS)

    1998-03-01

    The Environment Act 1995 provides for the Environment Agency ('the Agency') to recover the costs and expenses incurred by the Agency and by the Minister of Agriculture, Fisheries and Food (MAFF) in carrying out their functions in relation to the Radioactive Substances Act 1993 ('the Act'). The Act deals with the keeping and use of radioactive substances, and with the accumulation and disposal of radioactive waste

  16. The administration of radioactive substances

    International Nuclear Information System (INIS)

    Bourdillon, P.J.; Godfrey, B.E.; O'Brien, R.

    1983-01-01

    A brief history is given of the evolution of a system to approve the licensing of doctors and dentists to use radioactive medicinal products in man. Currently, the Administration of Radioactive Substances Advisory Committee (ARSAC) is appointed by UK Health Ministers to advise them on the granting, renewal, suspension, revocation and variation of certificates. The type of information requested on the application form for a certificate is outlined. (UK)

  17. Implementation vigenere algorithm using microcontroller for sending SMS in monitoring radioactive substances transport system

    International Nuclear Information System (INIS)

    Adi Abimanyu; Nurhidayat; Jumari

    2013-01-01

    Aspects of safety and security of radioactive substances from the sender to the receiver is to be secured for not to harm humans. In general, monitoring the transport of radioactive materials is done by communication with a telephone conversation to determine the location and rate of exposure radioactive substances. From the aspect of safety, communication through telephone conversations easily interpreted by others, in addition the possibility of human-error is quite high. SMS service is known for its ease in terms of use so that SMS can be used as a substitute for communication through telephone conversations to monitor the rate of radiation exposure and the position of radioactive substances in the transport of radioactive substances. The system monitors the transport of radioactive materials developed by implement vigenere algorithms using a microcontroller for sending SMS (Short Message Service) to communicate. Tests was conducted to testing encryption and description and computation time required. From the test results obtained they have been successfully implemented vigenere algorithm to encrypt and decrypt the messages on the transport of radioactive monitoring system and the computational time required to encrypt and decrypt the data is 13.05 ms for 36 characters and 13.61 for 37 characters. So for every single character require computing time 0.56 ms. (author)

  18. Radioactive preparations. Determination of radiochemical purity by thin-layer chromatography

    International Nuclear Information System (INIS)

    1986-01-01

    The standard sets the data which must be attached to every sample, and the equipment, chemicals and auxiliary substances used in the determination of radiochemical purity of substances by chromatography. Described are preparation of the sample, the procedure of sample deposition, the development, drying and detection of the radioactive preparation. The qualitative and quantitative assessment of the radiochromatogram is described as are the calculation of radiochemical purity and the determination of the reproducibility of measurement of radiochemical purity of radioactive preparations. (E.S.)

  19. Longitudinal dispersion of radioactive substances in Federal waterways

    Energy Technology Data Exchange (ETDEWEB)

    Krause, W.J. [Bundesanstalt fuer Gewaesserkunde (BfG), Koblenz (Germany); Speer, W.; Luellwitz, T.; Cremer, M.; Tolksdorf, W.

    2007-08-15

    In the context of radioactivity monitoring in German Federal Waterways (BWStr) by the Federal Institute of Hydrology (BfG) according to the Precautionary Radiation Protection Act (StrVG), the prediction of the dispersion of radioactive substances in water is one of the key tasks. The aim is the forecasting of the longitudinal dispersion of concentrations of soluble hazardous substances in flowing water. These predictions are based on the so-called dispersion tests with tritium as a tracer that the BfG has performed since 1980. Characteristic parameters like discharge-dependent flow velocities, dispersion and elimination constants related to emission sources or selected river sections are determined. They will serve as basis for a mathematical model to forecast discharge-dependent flow velocities, expected impact times, concentration maxima, and the duration of critical increases in concentrations. In the following, the results obtained till now from three investigation campaigns on the River Weser and its source rivers Werra and Fulda are described. (orig.)

  20. Specific activity isolation and determination of radioactive Estrogenic Substances in White Clover

    International Nuclear Information System (INIS)

    Pupiales T, G.; Mejia M, G.

    1986-01-01

    Due to high number of leguminous that exhibit estrogenic activity, subterranean clover between others, which causes infertility in sheep that eat it. It has been considered that white clover (Trifolium repens, variety Ladino, is an specie of low estrogenic activity, however at Bogota City (Colombia) it has high estrogenic activity and may cause reduction in the dairy cattle fertility. Research done in the IAN (today Ingeominas) over this clover variety, showed that the radioactivity substances presents in the white clover have high activity for stradiol, affecting organs from mouse females; Isoflavonoids from vegetables have an anabolism and utero tropic action; estrogenic activity of clover leaves, was exponentially proportional to the amount of ultraviolet radioactivity, falling upon plants during leaves development stage

  1. Upper parameters of toxicity (LDsub(50/30)) of some radioactive and chemical substances

    International Nuclear Information System (INIS)

    Rodionova, L.F.; Kupriyanova, V.M.; Zasedatelev, A.A.

    1978-01-01

    The toxicities of radioactive ( 90 Sr, 210 Po) and chemical (lead nitrate, mercuric chloride) substances were compared using equivalent procedures. Ninety six doses of toxic substances in various concentrations were tested on mice to which these substances were administered by intragastric intubation. The material was processed and analyzed by conventional methods used in toxicology. The upper limits of toxicity for the tested substances were determined from their LDsub(50/30) values by various methods of calculation

  2. The draft Radioactive Substances (Natural Gas) Exemption Order (Northern Ireland) 2002. Consultation paper

    International Nuclear Information System (INIS)

    2002-01-01

    Natural gas, and products made from it such as liquefied petroleum gas, may contain small amounts of naturally occurring radioactive substances. The use, accumulation and disposal of radioactive substances by organisations is regulated by the Radioactive Substances Act 1993 (RSA 93) and in Northern Ireland the regulatory authority is the Chief Radiochemical Inspector in the Environment and Heritage Service, which is part of the Department of the Environment (the Department). RSA 93 ensures the control of radioactive wastes by requiring registration of use of radioactive substances and authorisation of disposal of radioactive waste. It sets out the levels at which certain naturally occurring radioelements eg. uranium in gases, liquids and solids, and radon in gases, should be regarded as radioactive

  3. Radiological consequences of radioactive substances in building materials

    International Nuclear Information System (INIS)

    Tschurlovits, M.

    1982-01-01

    A review of radiological consequences of radioactive substances in building materials is given. Where the other contributing papers are dealing with technical problems and measuring techniques, this paper is going beyond the term dose and is considering the risk by radioactive substances in building materials in relation to conventional risks. The present state of international standards is also discussed. If a limit of 1 mSv is adopted, it is shown that this limit is just met at present conditions. (Author) [de

  4. Radioactive Substances Act 1960. Keeping and use of radioactive materials; list of registrations in England and Wales issued under the Radioactive Substances Act 1960 for the keeping and use of radioactive materials and mobile

    International Nuclear Information System (INIS)

    1989-05-01

    Through the Radioactive Substances Act 1960 (RSA 60), Her Majesty's Inspectorate of Pollution (Radioactive Substances) (HMIP) exercises control, on behalf of the Secretary of State for the Environment, over the keeping and use of radioactive material and the accumulation and disposal of radioactive waste in England. HMIP also provides technical advice to the Secretary of State for Wales in connection with the enforcement of RSA 60 in Wales. Registrations under RSA 60 for the keeping and use of radioactive materials in England and Wales are issued respectively by the Secretaries of State for the Environment and Wales, following careful assessment of the radiological consequences for members of the public. Registrations impose strict limits and conditions and premises and apparatus are subject to scrutiny by HMIP Inspectors to ensure compliance. A list contains names and addresses of those registered in England and Wales for the keeping and use of radioactive materials and mobile apparatus

  5. Radioactive substances detection at solid waste incinerators entrance

    International Nuclear Information System (INIS)

    Bourjat, V.; Carre, J.; Perrier-Rosset, A.

    2001-01-01

    SYCTOM'S incinerators, operated by TIRU will soon be fitted out with radioactivity control systems to prevent entrance of radioactive waste. Such implementation aims at reducing health risks due to exposition of operators working in incinerators or in sites receiving incineration residues. Radioactive wastes are supposed to be well managed: in the case where the radioactive elements period is short, they have to be stored for a precise time; in all the other cases, a statutory organism dealing with radioactive waste (ANDRA) has to take charge of them. Meanwhile they may arrived in incinerators by mistake. It's difficult to regulate radioactivity control systems for technical reasons; the measured values can be really different from these in the truck because of radiation decreasing; moreover it can't be correlated to an activity, hence it can't be compared to exemption values or to the limits that characterise a radioactive substance. It can explain why regulated documents don't indicate the way to fix alarm threshold. Implementing such a system is not sufficient: when the alarm sound, the following steps can be applied: checking the missing of interference, potential truck return to sender, putting the truck in quarantine, information of authorities and main actors, calling on a specialize company to locate, extract and package the radiation source, storage of this source and spectrometric analysis to identify and quantify the radioactive elements in order to determinate its way of elimination. (authors)

  6. 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.)

  7. Determination of the potential radiation exposure of the population close to the Asse II mine caused by deduction of radioactive substances with the discharge air in the normal operation using the ''Atmospheric Radionuclide-Transport-Model'' (ARTM)

    International Nuclear Information System (INIS)

    Esch, D.; Wittwer, C.

    2014-01-01

    Between 1967 and 1978 125.787 packages filled with low-level and intermediate-level radioactive waste were emplaced in the mining plant Asse II. Volatile radioactive substances like H-3, C-14 and Rn-222 are released from the emplaced waste. These substances reach the ventilated parts of the mine and are released with the discharge air. The potential radiation exposure of the population caused by deduction of radioactive substances with the discharge air in the normal operation is determined by the ''Atmospheric Radionuclide-Transport-Model'' (ARTM). As result the maximal deductions of volatile radioactive substances with the discharge air in the normal operation of the Asse II mine lead to radiation exposure of the population, which is considerably lower than the permissible values of application rate.

  8. Radioactive substance solidifying device

    International Nuclear Information System (INIS)

    Sakoda, Kotaro.

    1979-01-01

    Purpose: To easily solidify radioactive substances adhering to the surfaces of solid wastes without scattering in the circumference by paints, and further to reduce surface contamination concentrations. Constitution: Solid wastes are placed on a hanging plate, and dipped in paints within a paint dipping treatment tank installed at the lower part of a treatment tank by means of a monorail hoist, and the surfaces of said solid wastes are coated with paints, thereby to solidify the radioactivity on the surfaces of the solid wastes. After dipping, the solid wastes are suspended up to a paint spraying tank to dry the paints. After drying, non-contaminated paints are atomized to apply through an atomizing tube onto the solid wastes. After drying the atomized paints, the solid wastes are carried outside the treatment tank by means of the monorail hoist. (Yoshino, Y.)

  9. Environments with elevated radiation levels from natural radioactive substances

    International Nuclear Information System (INIS)

    Sohrabi, M.

    2000-01-01

    Some areas in the world have elevated levels of radioactive substances in the environment forming elevated radiation areas (ERAs) where public potential annual effective doses can exceed even the dose limit of radiation workers. Such radioactive substances are either terrestrial natural radioactivity added naturally in the soil or natural and/or man-made radioactivity from human activities added into the environment. If radioactivity is added naturally, elevated natural radiation areas (ENRAs) are formed. Based on the classification criteria introduced by the author, such regions are divided into static and dynamic areas. They are also classified in accordance with their level of potential effective dose to the public. Some main ENRAs are classified. Highlights are presented of the results of activity studies carried out in selected areas. The concepts discussed can also be applied to areas formed by human activities. The author suggests some guidelines for future studies, regulatory control and decision making, bearing in mind the need for harmonization of policies for regulatory control and remedial actions at sites to protect the public from environmental chronic exposures. (author)

  10. Natural occurring radioactive substances. Vol. 1

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-03-01

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

  11. Natural occurring radioactive substances. Vol. 1

    International Nuclear Information System (INIS)

    Emara, A.E.

    1996-01-01

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

  12. Summary of the law relating to atomic energy and radioactive substances

    International Nuclear Information System (INIS)

    Sim, D.F.; Ritchie, K.J.S.

    1982-04-01

    The law relating to atomic energy and radioactive substances in the United Kingdom is summarized under the following headings: the Common Law; legislation (Atomic Energy Act 1946; Radioactive Substances Acts 1948 and 1960; Electricity (Amendment) Act 1961; Nuclear Installations Act 1965 and 1969 (and subordinate legislation); Secretary of State for Trade and Industry Order 1970; Radiological Protection Act 1970 (as amended); Air Navigation (Restriction of Flying)(Atomic Energy Establishments) Regulations 1981; Nuclear Safeguards and Electricity (Finance) Act 1978; legislation relating to the UK Atomic Energy Authority); Regulations under the Factories Act 1961; Regulations relating to educational establishments; Regulations and Orders relating to food and medicines; Regulations, etc., affecting the transport of radioactive materials; Regulations under the Social Security Act 1975; control of import and export; the Euratom Treaty; important non-statutory Codes of Practice, etc.; international conventions, etc., relating to the peaceful use of atomic energy and radioactive substances, in which the United Kingdom is interested; foreign legislation. (U.K.)

  13. 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)

  14. Summary of the law relating to atomic energy and radioactive substances

    International Nuclear Information System (INIS)

    Sim, D.F.; Ritchie, K.J.S.

    1982-01-01

    This Summary is an updated version of a previous revision of the Summary of the United Kingdom's legislation on atomic energy and reviews the main texts in that field. Reference is made to the regulations on atomic energy, nuclear installations, radioactive substances, transport of such substances, radiation protection etc. It is intended to be a signpost to the relevant law, but does not cover any aspect in detail. The Summary also refers to international agreements in the nuclear field: conventions and regulations on the transport of radioactive substances and nuclear material, nuclear third party liability, radiation protection and environmental protection. (NEA) [fr

  15. Vessel used in radiation counting to determine radioactivity levels

    International Nuclear Information System (INIS)

    Charlton, J.C.; Glover, J.S.; Shephard, B.P.

    1977-01-01

    This invention concerns the vessels used in radiation counting to determine radioactivity levels. These vessels prove to be particularly useful in analyses of the kind where a radioactive element or compound is separated into two phases and the radioactivity of one phase is determined. Such a vessel used in the counting of radiation includes an organic plastic substance tube appreciably cylindrical in shape whose upper end is open whilst the lower end is closed and integral with it, and an anti-radiation shield in metal or in metal reinforced plastic located at the lower end of the tube and extending along the wall of the tube up to a given height. The vessel contains a reaction area of 1 to 10 ml for holding fluid reagents [fr

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

    International Nuclear Information System (INIS)

    Hesty Rimadianny

    2015-01-01

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

  17. [The main directions of improving the system of state accounting and control of radioactive substances and radioactive waste products].

    Science.gov (United States)

    2012-01-01

    This paper describes a modification of the basic directions of state accounting and control of radioactive substances and radioactive waste products, whose implementation will significantly improve the efficiency of its operation at the regional level. Selected areas are designed to improve accounting and control system for the submission of the enterprises established by the reporting forms, the quality of the information contained in them, as well as structures of information and process for collecting, analyzing and data processing concerning radioactive substances and waste products.

  18. Approaches to assign security levels for radioactive substances and radiation sources

    International Nuclear Information System (INIS)

    Ivanov, M.V.; Petrovskij, N.P.; Pinchuk, G.N.; Telkov, S.N.; Kuzin, V.V.

    2011-01-01

    The article contains analyzed provisions on categorization of radioactive substances and radiation sources according to the extent of their potential danger. Above provisions are used in the IAEA documents and in Russian regulatory documents for differentiation of regulatory requirements to physical security. It is demonstrated that with the account of possible threats of violators, rules of physical protection of radiation sources and radioactive substances should be amended as regards the approaches to assign their categories and security levels [ru

  19. Handling of radioactive substances containing ionization smoke detectors found in debris

    International Nuclear Information System (INIS)

    Kratz, M.; Lorenz, F.

    1992-01-01

    In many commercial buildings, ionization smoke detectors are installed which contain radioactive substances such as Ra-226 or Am-241 and are subject to regularoty control. The obligations of plant owners having installed such devices are laid down in Annex III of the Radiation Protection Ordinance of June 30, 1989. In the event of a fire, the public trade inspection offices are the competent authorities for examining the radioactivity level of the debris to be managed after a fire. The radioactivity level is determined in accordance with Annex IV of the Radiation Protection Ordinance, defining the MPA data for every nuclide. If the specific activity measured per gramme of debris is in excess of the 10 -4 -fold maximum permissible activity, waste management requires a permit according to section 3 of the Radiation Protection Ordinance. (orig.) [de

  20. Radiation environmental impact assessment of radioactive substances of an airport transit storage construction projects

    International Nuclear Information System (INIS)

    Zhang Baozeng; Xia Zitong; Zou Zhaozhuang

    2014-01-01

    Radioactive substances belong to dangerous goods transport aviation. Radioactive substances impoundments construction purpose is to ensure that the radioactive material during transport to transport and the public to achieve full or isolation, the effects of radiation on the human body, property and the environment caused by the control to an acceptable level. According to the relevant national standards and norms, for radiation protection evaluation of project construction of an airport radioactive impoundments, feasibility of the construction project radiation environment. (authors)

  1. Summary of the law relating to atomic energy and radioactive substances

    International Nuclear Information System (INIS)

    Sim, D.F.; Ritchie, K.J.S.

    1981-04-01

    A summary is given of the law relating to atomic energy and radioactive substances revised as at 31 March 1981 under the following headings: (1) The common law. (2) The legislation. (3) Regulations under the factories act 1961. (4) Regulations relating to educational establishments. (5) Regulations and orders relating to food and medicines. (6) Regulations, rules, etc. affecting the transport of radioactive materials. (7) Regulations under the social security act 1975. (8) Control of import and export. (9) The Euratom treaty. (10) Important nonstatutory codes of practice, etc.. (11) International conventions, regulations, etc. relating to the peaceful use of atomic energy and radioactive substances, in which the United Kingdom is interested. (12) Foreign legislation. (U.K.)

  2. Artificial neural network models' application for radioactive substances' migration forecasting in soil

    International Nuclear Information System (INIS)

    Kovalenko, V.I.; Khil'ko, O.S.; Kundas, S.P.

    2009-01-01

    The work is indicated to the use of artificial neural network (ANN) models in program complex SPS for radioactive substances' migration forecasting in soil. For the problem solution two ANN models are used. One of them forecasts radioactive substances' migration, another carries out forecasting of physical and chemical soil properties. Program complex SPS allows to achieve a low error of forecasting (no more than 5 %) and high training speed. (authors)

  3. Radiation consequences of combatant radioactive substances tests on the Semipalatinsk Test Site

    International Nuclear Information System (INIS)

    Strilchuk, Yu.G.; Osintsev, A.Yu.; Kuzin, D.E.; Bryantseva, N.V.; Bozhko, V.V.; Tonevitskaya, O.V.; Panitskaya, D.S.; Lukashenko, S.N.; Georgievskij, V.; Murley, R.; Wells, D.

    2008-01-01

    Nuclear explosions were not the only type of tests carried out on the STS territory. In 1953 - 1957 the STS territory was the area of testing of combatant radioactive substances (CRS). Combatant radioactive substances were liquid or powder-like combatment radioactive mixtures manufactured either from the wastes of radiochemical industry or by neutron irradiation of specally selected substances in nuclear reactor. Their specific activity ranged from tenths of Curie to several Curie per liter. CRS tests were made on testing grounds ''4'' and ''4A'' situated near northern outpost beyond the Opytnoye Pole (Experimental field). Dispersion of CRS was achieved by blasting of individual shells, bombardment of the area by mortar shells, bombardment from aircraft bombers or dispersion of CRS from airplanes. Investigations carried out in the past years on the territory of the testing grounds discovered fragments of metal products used in the CRS tests and over 30 areas of local radioactive contamination. 90 Sr was the main radioactive pollutant, whose specific activity in upper soil is as high as 5*10 8 Bq/kg; other radionuclides are presented by isotopes: 239+240 Pu, 152 Eu, 154 Eu, 137 Cs, 241 Am, 60 Co. The areas of radioactively-contaminated soil range from hundreds to hundreds of thousands of square meters with some of them expanding to distances of several kilometers. Concentration of radionuclides in soil and vegetation may be compared with that of radioactive waste

  4. SI 1985 No. 1048 - The Radioactive Substances (Luminous Articles) Exemption Order 1985

    International Nuclear Information System (INIS)

    1985-01-01

    This Order, which came into force on 17 September 1985, is concerned with exemptions and exclusions under the Radioactive Substances Act 1960 in respect of radioactive luminous instruments and indicators. (NEA) [fr

  5. 29 CFR 570.57 - Exposure to radioactive substances and to ionizing radiations (Order 6).

    Science.gov (United States)

    2010-07-01

    ... to Their Health or Well-Being § 570.57 Exposure to radioactive substances and to ionizing radiations... radioactive substances and to ionizing radiations are particularly hazardous and detrimental to health for... involves exposure to ionizing radiations in excess of 0.5 rem per year. (b) Definitions. As used in this...

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

    International Nuclear Information System (INIS)

    Direkov, Lubomir; Gaberov, Vladimir; Vakova, Violeta

    2015-01-01

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

  7. Code of practice for the design of laboratories using radioactive substances for medical purposes

    International Nuclear Information System (INIS)

    1981-01-01

    This Code has been prepared to supplement the radioactive substances acts and regulations implemented in Australia. It is intended as a guide to safe practices but is not legislation. Areas covered include siting, layout, surface finishes, laboratory furniture and fittings, ventilation, containment and release of airborne effluent and storage of radioactive substances

  8. Radioactive substances monitoring programme. Report for 1995

    International Nuclear Information System (INIS)

    1995-01-01

    The Radioactive Substances Act 1993 provides for controls to be exercised over the use and keeping of radioactive materials and the accumulation and disposal of radioactive wastes. The Environment Agency (the Agency) has been responsible for administration and enforcement of the Act in England and Wales since its formation on 1 April 1996. Prior to this date the work was undertaken by Her Majesty's Inspectorate of Pollution (HMIP). In support of its regulatory functions HMIP commissioned independent monitoring. This report presents the results from monitoring undertaken in 1995. The 1995 HMIP programme required operators of certain sites to provide samples of their liquid effluents for independent radiochemical analysis. The results provide checks on site operators' returns and insights into their quality assurance (QA) procedures and analytical techniques. The analyses were undertaken by the Laboratory of the Government Chemist (LGC) at its laboratories in Teddington, Middlesex. The programme also included checks on solid low level radioactive waste destined for land disposal at the site operated by British Nuclear Fuels plc (BNFL) at Drigg in Cumbria. (author)

  9. Criteria of acceptability relating to the approval of consumer goods containing radioactive substances

    International Nuclear Information System (INIS)

    Paynter, R.A.

    1992-01-01

    The criteria are described which the Board intends to use when considering goods containing radioactive substances for approval under the regulations that the Government intends to make with respect to such goods. Some products are deemed unacceptable in principle because there would appear to be no justification for the use of radioactive substances in them. Examples of such products are given. Other products may be approved for supply to the public depending on the doses likely to be received by individuals, principally those who use the products. A lower dose is considered acceptable from products that do not contribute to safety than from products that do. In the interim, before the regulations are made, the criteria will be used as the basis of the Board's advice to suppliers and manufacturers of goods containing radioactive substances. (Author)

  10. 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.)

  11. Countermeasure technology for environmental pollution due to radioactive substances

    International Nuclear Information System (INIS)

    Shimizu, Hideki

    2014-01-01

    This paper introduces the progress of challenges by Maeda Corporation toward the countermeasures for the environmental pollution caused by radioactive substances that covers the whole areas of Naraha Town in Fukushima Prefecture. It also introduces in full detail the environmental pollution countermeasure technologies against radioactive substances challenged by the said company. These technologies are as follows; (1) porous block kneaded with zeolite, (2) Aqua-filter System (technique to automatically and continuously purify construction work water to the level of tap water), (3) super vacuum press (dehydration unit to realize the dehydration, volume reduction and solidification, and insolubilization at the same time), (4) mist blender (technique to manufacture bentonite-mixed soil), (5) wet-type classification washing technique for contaminated soil, (6) soil sorting technique (continuous discrimination technique to sort soil depending on radiation level), and (7) speedy construction technique for dam body using CSG (cemented sand and gravel). (A.O.)

  12. The monitoring of radioactive substances in biological food chains by the veterinary service in Czechoslovakia

    Energy Technology Data Exchange (ETDEWEB)

    Pawel, O [Central State Veterinary Institute, Prague, Czechoslovakia (Czech Republic)

    1986-07-01

    Czechoslovakia has established an environmental monitoring system to protect the hygienic conditions of the environment from the radiation hazard. The control authorities of the Ministry of Agriculture and Food take part in this system in order to collect information on the contamination with radioactive substances of soil, plants, game, food animals, foodstuffs and raw materials, i.e. information on all links of the food chain which extends from animals to man. A radioactive substances detection programme has been launched by the appropriate authorities in agriculture, animal husbandry and veterinary service. The programme includes a two-stage laboratory analysis of radioactive substances. The majority of laboratories covering the programme are already in operation.

  13. The monitoring of radioactive substances in biological food chains by the veterinary service in Czechoslovakia

    International Nuclear Information System (INIS)

    Pawel, O.

    1986-01-01

    Czechoslovakia has established an environmental monitoring system to protect the hygienic conditions of the environment from the radiation hazard. The control authorities of the Ministry of Agriculture and Food take part in this system in order to collect information on the contamination with radioactive substances of soil, plants, game, food animals, foodstuffs and raw materials, i.e. information on all links of the food chain which extends from animals to man. A radioactive substances detection programme has been launched by the appropriate authorities in agriculture, animal husbandry and veterinary service. The programme includes a two-stage laboratory analysis of radioactive substances. The majority of laboratories covering the programme are already in operation

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

    Science.gov (United States)

    Sasaki, S.; Yamada, T.

    2013-05-01

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

  15. Abstract of the law relating to the nuclear industry and radioactive substances

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    This summary of the law relating to Atomic Energy and Radioactive substances as at March 1980 is divided into sections headed: (1) The common law. (2) Legislation. (3) Regulations under the Factories Act 1961. (4) Regulations, rules etc. affecting the transport of radioactive materials. (5) The Euratom treaty. (U.K.)

  16. Hazardous and radioactive substances in Danish marine waters. Status and temporal trends

    Energy Technology Data Exchange (ETDEWEB)

    Dahlloef, I; Andersen, Jesper H

    2009-07-15

    This book fulfils the Danish reporting obligations in relation to the OSPAR Trend Assessment on Dangerous Substances, and describes the degree of contamination from hazardous and radioactive substances and their temporal trends, as well as the effects of some of these hazardous substances, in the Danish marine environment. The assessment is based on existing information, primarily data collected via national and regional Danish monitoring activities until 2004. (author)

  17. Hazardous and radioactive substances in Danish marine waters. Status and temporal trends

    International Nuclear Information System (INIS)

    Dahlloef, I.; Andersen, Jesper H.

    2009-07-01

    This book fulfils the Danish reporting obligations in relation to the OSPAR Trend Assessment on Dangerous Substances, and describes the degree of contamination from hazardous and radioactive substances and their temporal trends, as well as the effects of some of these hazardous substances, in the Danish marine environment. The assessment is based on existing information, primarily data collected via national and regional Danish monitoring activities until 2004. (author)

  18. S.I. No 249 of 1972, Factories Ionising Radiations (Unsealed Radioactive Substances) Regulations, 1972

    International Nuclear Information System (INIS)

    1972-12-01

    The Regulations which entered into force on 1 December 1972 apply to factories in which a process involving the use of unsealed radioactive substances is carried on and where the total activity of the unsealed radioactive substances exceeds specified levels, or where there are objects contaminated in excess of certain levels. The Schedules specify the maximum radiation doses and the maximum permissible levels of contamination and provide for a classification of radionuclides [fr

  19. Monitoring programme. Radioactive substances - report for 1994

    International Nuclear Information System (INIS)

    1995-09-01

    The monitoring of radioactive substances in the vicinity of nuclear sites in the United Kingdom by Her Majesty's Inspectorate of Pollution, acts as an independent check on the operator's returns, on the environmental impact of radioactive waste disposal at authorised sites and on radiation doses to critical groups of the public. In 1994 the programme included the analysis of 160 effluent samples, the analysis of low-level solid radioactive waste destined for the British Nuclear Fuels site at Drigg, and the analysis of a total of 290 environmental samples and direct monitoring at over 150 locations. The materials monitored are those that might result in exposure of the public to radiation by non-food pathways and complements monitoring by the Ministry of Agriculture, Food and Fisheries. Radiation exposures by these pathways which may have been incurred in 1994 are similar to those in previous years and, in all cases, fall substantially below the International Commission on Radiological Protection's recommended principal dose limit of 1mSv per year. (UK)

  20. Original jurisdiction in matters relating to transport of radioactive substances

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    Decisions on actions for avoidance of government supervision in matters of transport of radioactive substances are placed under the original jurisdiction of administrative courts. (Kassel Administrative Court, decision of 20 December 1988 - 8 A 699/88). (orig.) [de

  1. Methodological guide: management of industrial sites potentially contaminated by radioactive substances; Guide methodologique: gestion des sites industriels potentiellement contamines par des substances radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    At the request of the Ministries of Health and the Environment, IPSN is preparing and publishing the first version of the methodological guide devoted to managing industrial sites potentially contaminated by radioactive substances. This guide describes a procedure for defining and choosing strategies for rehabilitating such industrial sites. (author)

  2. The Medicines (Radioactive Substances) Order 1978 (S.I. no.1004)

    International Nuclear Information System (INIS)

    1978-01-01

    This Order extends the application of specified provisions of the Medicines Act 1968 to certain articles and substances that are, contain or generate radioactive substances. These provisions include section 60 of that Act which enables regulations to be made prohibiting the sale, supply or administration of medicinal products specified in the regulations except by practitioners holding a certificate issued for the purposes of section 60. The Order also modifies the definition of 'administer' for the purposes of the Order [fr

  3. Radioactive Substances and Irradiating Apparatus Regulations 1962-1979 (South Australia)

    International Nuclear Information System (INIS)

    1980-01-01

    These regulations are a consolidation of regulations made under the Health Act 1935-1978, which cover such topics as licensing, registration and record-keeping procedures, prevention of injury by radiation and methods of storage, labelling, transport and packaging of radioactive substances. (NEA) [fr

  4. HMIP Monitoring Programme radioactive substances report for 1990

    International Nuclear Information System (INIS)

    1992-03-01

    The programme of environmental monitoring of radioactive substances in England and Wales during 1990, was completed satisfactorily under the auspices of Her Majesty's Inspectorate of Pollution. The programme concentrates on monitoring activity levels in environmental materials which might result in radiation exposure of the public from non-food pathways. The programme acts as a check on site operator's returns and provides independent data on the environmental impact of authorised disposals of radioactive wastes and on radiation doses to critical groups of the public. This report presents the data from this continuing monitoring programme. The monitoring was carried out at installations controlled by British Nuclear Fuels PLC, Nuclear Electric the United Kingdom Atomic Energy Authority, Amersham International PLC, the Ministry of Defence, at two non-nuclear sites which use tritium, the works of Capper Pass Ltd who carry out lead smelting and at several landfill sites where controlled buried of low-level radioactive wastes is carried out. (Author)

  5. Working rules for medical application of radioactive substances

    International Nuclear Information System (INIS)

    Gloebel, B.

    1982-01-01

    After incorporation of radioactive substances radiation exposure is detectable only in case of iodine 125 and iodine 131. Organizational measures should improve the protection of personnel. According to the experience gained decontamination successes are possible between 1 and 99%, however they evade forecasting. With iodine 131 it is necessary to make for accelerated discharge resp. prevent further penetration from the extrathydroidal space into the thyroid gland. (DG) [de

  6. Access device for transferring toxic or radioactive substances between a flanged flask and a containment

    International Nuclear Information System (INIS)

    Winnett, G.F.

    1980-01-01

    This invention concerns the transfer of toxic or radioactive substances between a containment and a flask in which such substances are transported. When toxic or radioactive substances are being transferred, it is important to ensure that such substances cannot excape into the surrounding atmosphere and, preferably, the appliance utilized has to be capable of making a misuse impossible, whether accidental or calculated. The flask to which this invention applies is of the type comprising lugs, near its open ends, which act in combination with a groove made around an access opening to hold and maintain the flask in position against the wall of the containment, so that its open end is aligned with an access opening provided in the containment wall [fr

  7. Radioactive substances found on the contaminated fish

    Energy Technology Data Exchange (ETDEWEB)

    Kiba, T; Ohashi, S; Shibata, M; Mizube, T

    1954-01-01

    Radiochemical investigation of the substance collected from the surface of tuna fish which were brought back by the No. 5 Fukuryu Maru was performed. Most of the radioactivity was found on the scales which could not be decontaminated by treating with H/sub 2/O; 80% of the activity was removed by washing the dried scales with 3N HCl. Paper chromatographic separation of the HCl fraction showed the presence of /sup 140/Ba, /sup 89/Sr, /sup 132/Te, and probably /sup 95/Zr, /sup 140/La, and rare earths.

  8. Environmental safety of the disposal system for radioactive substance-contaminated wastes

    International Nuclear Information System (INIS)

    Oosako, Masahiro

    2012-01-01

    In accordance with the full-scale enforcement of 'The Act on Special Measures concerning the Handling of Radioactive Pollution' in 2012, the collective efforts of entire Japan for dealing with radioactive pollutants began. The most important item for dealing with radioactive pollution is to control radioactive substances that polluted the global environment and establish a contaminated waste treatment system for risk reduction. On the incineration system and landfill disposal system of radioactive waste, this paper arranges the scientific information up to now, and discusses the safety of the treatment / disposal systems of contaminated waste. As for 'The Act on Special Measures concerning the Handling of Radioactive Pollution,' this paper discusses the points of the Act and basic policy, roadmap for the installation of interim storage facilities, and enforcement regulations (Ordinance of the Ministry of the Environment). About the safety of waste treatment system, it discusses the safety level of technical standards at waste treatment facilities, safety of incineration facilities, and safety of landfill disposal sites. (O.A.)

  9. A guide for controlling consumer products containing radioactive substances

    International Nuclear Information System (INIS)

    1985-01-01

    Consumer products are considered regardless of the purpose for which the radionuclide is added. For example, the purpose may be to make use of the ionising radiation emitted by the substance in the product itself (e.g. radioluminescent devices antistatic devices and ionisation chamber smoke detectors), or to make use of some other property of the material where the presence of radiation in the final product is merely adventitious (e.g. thorium gas mantles, ceramics with uranium glazes, and products containing radioactive tracers added to facilitate manufacturing and inspection processes). The Guide does not cover some products containing natural radioactive substances which have not been intentionally added, such as building materials. The Guide does not cover medicinal products and pharmaceuticals, nuclear powered cardiac pacemakers, or electronic equipment, such as television receivers, that emit X-rays. Unlike the 1970 Guide, this Guide does not consider those products, such as EXIT signs, containing gaseous tritium light sources, that would not be supplied directly to members of the public. The Guide is concerned mainly with the exposure arising from consumer products of those persons who are not subject to any regulatory controls for purposes of radiation protection in normal circumstances. Members of the public come under this heading, but not workers involved in the manufacture of consumer products. These workers will normally be subject to separate control. Radiological protection concepts and policy for the control of radioactive consumer products and licensing and post-licensing surveillance are developed

  10. Summary of the law relating to atomic energy and radioactive substances

    International Nuclear Information System (INIS)

    Sim, D.F.; Ritchie, K.J.S.

    1983-01-01

    This summary is an updated version of a previous revision of the summary of the United Kingdom's legislation on atomic energy and reviews the main texts in that field. Reference is made to the regulations on atomic energy, nuclear installations, radioactive substances, transport of such substances, radiation protection etc. The Energy Act 1983 amends the third party liability provisions of the nuclear installations Act 1965 in particular by raising the limits of compensation for nuclear damage. (NEA) [fr

  11. Summary of the law relating to atomic energy and radioactive substances as at March 1979

    International Nuclear Information System (INIS)

    Sim, D.F.; Ritchie, K.J.S.

    1979-01-01

    This summary is intended to be a 'signpost' to the relevant law in the United Kingdom, but does not cover any aspect in detail. It falls under the following headings: common law; legislation (Atomic Energy Act 1946 and subordinate legislation; Radioactive Substances Act 1948 and subordinate legislation; Radioactive Substances Act 1960; Electricity (Amendment) Act 1961; Nuclear Installations Acts 1965 and 1969 and subordinate legislation; the Secretary of State for Trade and Industry Order 1970; Radiological Protection Act 1970 as amended by the Health and Safety at Work etc. Act 1974; Air Navigation (Restriction of Flying)(Atomic Energy Establishments) Regulations 1976; Nuclear Safeguards and Electricity (Finance) Act 1978; legislation relating to the United Kingdom Atomic Energy Authority); regulations under the Factories Act 1961; regulations relating to educational establishments; regulations and orders relating to food and medicines; regulations, rules etc. affecting the transport of radioactive materials; regulations under the Social Security Act 1975; control of import and export; the Euratom Treaty; important non-statutory codes of practice etc.; international conventions, regulations etc. relating to the peaceful use of atomic energy and radioactive substances, in which the United Kingdom is interested; foreign legislation. (U.K.)

  12. Collection of ministerial circulars on the transport of radioactive substances

    International Nuclear Information System (INIS)

    1977-10-01

    This publication by the CNEN reproduces the full texts of Ministerial Circulars on the transport by road, rail, air and sea of radioactive substances, made in implementation of Act No. 1860 on the peaceful uses of nuclear energy of 1962, as amended by Decree No. 1704 of 1965, laying down that regulatory standards should be elaborated for such transport in accordance with the Euratom basic radiation protection standards and the IAEA Regulations on the Safe Transport of Radioactive Materials. These Circulars are set out in chronological order with reference to the national and international provisions under which they were made. (NEA) [fr

  13. Various possible ways to express the toxicity of radioactive substances in relation with the involved practical problems; Diverses expressions possibles de la toxicite des substances radioactives en fonction des problemes pratiques poses

    Energy Technology Data Exchange (ETDEWEB)

    Jammet, H; Vacca, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1959-07-01

    Radioelements have at the same time physico-chemical and radioactive properties. It is then possible to establish two types of toxicological classifications: one in function of the weight of the radioelement, another in function of its activity. More often, the maximum permissible amounts (MPA) in the human body and the maximum permissible concentrations (MPC) in air and water are expressed in microcuries by millilitre ({mu}c/ml), less frequently in micrograms by millilitre ({mu}g/ml). The comparison of these tables of MPA and MPC shows important differences in the classification of radioactive substances by order of decreasing toxicity. Plutonium and radium, being among the most toxic products when the activity is considered are far from being the most dangerous when the weight is considered. On the other hand, {sup 131}I and {sup 56}Mn, for instance appear to be among the most hazardous substances in this eventuality. This twofold consideration corresponds to two aspects of the problems of the toxicity of radioisotopes. The classification by activity is almost exclusively utilised because the toxicological measurements are based on the radioactive properties of the radioisotopes. In general, only these measurements allow to detect the very small amounts of substance usually involved. On the other hand, the toxicity related to internal contamination by radioisotopes depends mostly from their metabolism which is exclusively a function of their physico-chemical properties. Therefore the classification by weight gives the best representation of the hazards encountered when radioactive substances are inhaled or ingested. As a result, the relative toxicity of radioisotopes cannot be based on the classification by activity only. The present division of radioisotopes into different classes: very hazardous, moderately hazardous, slightly hazardous must be revised. (author) [French] Les radioelements presentent a la fois des proprietes physico-chimiques banales et des

  14. Method and apparatus for the purification of a liquid contaminated with radioactive substances

    International Nuclear Information System (INIS)

    Mende, H.

    1976-01-01

    A method of and apparatus for the purification of a liquid contaminated with radioactive substances is described, wherein the liquid is infed to an evaporator in or with which there is connected a column having a multiplicity of superposed plates or floors. The vapor generated in the evaporator is guided through a washing or scrubbing liquid uniformly distributed at the floors and flowing in crosswise counterflow with regard to the vapor. The washing liquid at the floors is deflected a number of times in such a manner that the washing liquid itself together with the droplets entrained by the vapor are uniformly admixed and the washing liquid subjected to a constant intake of the radioactive substance

  15. The safety of consumer goods containing radioactive substances

    International Nuclear Information System (INIS)

    Wrixon, A.D.

    1980-01-01

    Consideration is given to the arguments used in the formulation of proposals which have been incorporated into a consultative document published by the National Radiological Protection Board (Criteria Relating to the Approval of Consumer Goods Containing Radioactive Substances: A Consultative Document, HMSO, London). The proposals are summarized. They were based on the classification of these consumer goods into different categories, and details are given of the suggested dose limits for these categories. Comments on the proposals are invited. (U.K.)

  16. Road surface washing system for decontaminating radioactive substances. Experiment of radioactive decontamination

    International Nuclear Information System (INIS)

    Endo, Mitsuru; Endo, Mai; Kakizaki, Takao

    2015-01-01

    The Great East Japan Earthquake that occurred on March 11, 2011 resulted in the explosion of the TEPCO Fukushima 1st Nuclear Power Plant and the global dispersion of a large quantity of radioactive substances. A high radiation dose was particularly recorded in Fukushima prefecture several weeks after the accident, although the level is presently sufficiently low. However, considering that the adverse effects of low but extended exposure to radiation are yet to be negated, there is the urgent need for further decontamination. In our study, we focused on the efficient decontamination of radioactive substances in residential areas, for which we propose a high-pressure water jet system for washing road surfaces. The system differs from conventional systems of its type that were initially designed for use in the immediate environment of the nuclear reactors of the TEPCO Fukushima 1st Nuclear Power Plant. The proposed system consists of multiple washing, transporter, and server robots. The washing robots decontaminate the road surface using high-pressure water jets and are transported between washed and unwashed areas by the transporter robots. The server robots supply the water used for washing and absorb the polluted water together with ground dust. In this paper, we describe the concept of the system and present the results of decontamination experiments. Particular attention is given to the washing robot and its mechanism and control method. The results of the integration of the washing robot in an experimental system confirmed the feasibility of the proposed system. (author)

  17. Methodological guide: management of industrial sites potentially contaminated by radioactive substances

    International Nuclear Information System (INIS)

    2001-01-01

    At the request of the Ministries of Health and the Environment, IPSN is preparing and publishing the first version of the methodological guide devoted to managing industrial sites potentially contaminated by radioactive substances. This guide describes a procedure for defining and choosing strategies for rehabilitating such industrial sites. (author)

  18. Licence template for mobile handling and storage of radioactive substances for the nondestructive testing of materials

    International Nuclear Information System (INIS)

    Lange, A.; Schumann, J.; Huhn, W.

    2016-01-01

    The Technical Committee ''Radiation Protection'' (Fachausschuss ''Strahlenschutz'') and the Laender Committee ''X-ray ordinance'' (Laenderausschuss ''Roentgenverordnung'') have appointed a working group for the formulation of licence templates for the nationwide use of X-ray equipment or handling of radioactive substances. To date, the following licence templates have been adopted: - Mobile operation of X-ray equipment under technical radiography to the coarse structural analysis in material testing; - Mobile operation of a handheld X-ray fluorescence system; - Mobile operation of a flash X-ray system; - Operation of an X-ray system for teleradiology The licence template ''Mobile handling and storage of radioactive substances for the nondestructive testing of materials'' is scheduled for publication. The licence template ''Practices in external facilities and installations'' is currently being revised. The licence template ''Mobile handling and storage of radioactive substances for the nondestructive testing of materials'' is used as an example to demonstrate the legal framework and the results of the working group.

  19. A method for purifying air containing radioactive substances resulting from the disintegration of radon

    International Nuclear Information System (INIS)

    Stringer, C.W.

    1974-01-01

    The invention relates to the extraction of radioactive isotopes from air. It refers to a method for withdrawing the radioactive substances resulting from the disintegration of radon from air, said method of the type comprising filtrating the air contaminated by the radon daughter products in a filter wetted with water in order to trap said substances in water. It is characterized in that it comprises the steps of causing the water contaminated by the radon daughter products to flow through a filtrating substance containing a non hydrosoluble granular substrate, the outer surface of which has been dried then wetted by a normally-liquid hydrocarbon, and of returning then wetted by a normally-liquid hydrocarbon, and of returning the thus filtrated water so that it wets again the air filter and entraps further radon daughter products. This can be applied to the purification of the air in uranium mines [fr

  20. Experiences from the exercise ''MERLIN'' for the detection of radioactive substances with the participation of special-purpose vehicles

    International Nuclear Information System (INIS)

    Griesbach, M.

    2009-01-01

    Experiences of an exercise with hazardous goods, in particular with radioactive substances (measurements and taking environmental samples) are described. Several special-purpose vehicles with equipment and specially trained crews were used together with radiation protection experts according to the concept of Hesse. It has been the greatest exercise in Hesse with regard to hazardous goods and in particular with regard to ''incidents with radioactive substances''. (orig.)

  1. Proposals for the Radioactive Substances (Basic Safety Standards) (England and Wales) Regulations 2000 and the Radioactive Substances (Basic Safety Standards) (England and Wales) Direction 2000. Consultative document

    International Nuclear Information System (INIS)

    2000-01-01

    This document contains proposals for changes to the Radioactive Substances Act 1993 (RSA 93) and proposals for a Direction to be given to the Environment Agency in order to implement aspects of the European Directive 96/29/Euratom concerned with the control of radioactive waste. The Directive lays down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionising radiation. With the Government pledged to making government more accessible and responsive, an important feature of this approach is effective consultation with all interested organisations. This leads to more realistic and robust proposals, which is particularly important when dealing with proposed legislation. In March this year, the Government published a consultation paper 'The Radioactive Substances Act 1993: Implementing the Revised Basic Safety Standards Directive Euratom 96/29.' This sought comments on the basic principles for change - including the setting of levels of radioactivity below which radioactive material should be considered outside the framework of regulatory control. This document forms the second stage of the consultation process with the aim of gathering views on the proposed legal instruments to implement the Directive. This document: explains the background to the proposed regulations (paragraphs 8-13); summarises the results of the consultation on principles (paragraphs 14-24); describes the proposed changes (paragraphs 25-36); includes draft Regulations (paragraphs 27-29); includes a draft Direction to the Environment Agency (paragraphs 30-36); describes the next steps (paragraphs 37-39); includes a draft Regulatory Impact Assessment (paragraphs 40-41). In general, the devolved administrations in Scotland, Wales and Northern Ireland have assumed responsibility for environmental issues and hence management of radioactive waste policies and legislation affecting their respective countries. However, this

  2. Sample taking device for toxic and/or radioactive substances

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  3. Determination of standards for transportation of radioactive material by aircrafts

    International Nuclear Information System (INIS)

    1978-01-01

    These provisions are established on the basis of the Enforcement Regulation for the Law on Aviation. Terms are explained, such as exclusive loading and containers. Spontaneously ignitable liquid radioactive materials and the radioactive substances required to be contained in special vessels and others particularly operated during the transport, are excluded from the radioactive materials permissible for transport. The radioactive substances required to be transported as radioactive loadings don't include empty vessels used to contain radioactive materials and other things contaminated by such materials, when they conform to the prescriptions. The technical standards on radioactive loadings are defined, such as maximum radiation dose rate of 0.5 millirem per hour on the surface of L type loadings, 200 millirem per hour for A, and 1000 millirem per hour at the distance of 1 m for BM and BU types, respectively. Confirmation of the safeness of radioactive loadings may be made through the written documents prepared by the competent persons acknowledged by the Minister of Transport. The requisite of fissile loadings is that such loadings shall not reach critical state during the transport in the specified cases. Radioactive loadings or the containers with such loadings shall be loaded so that the safeness of such loadings is not injured by movement, overturn and fall during the transport. The maximum radiation dose rate of the containers with radioactive loadings shall not be more than 200 millirem per hour on the surface. The written documents describing the handling method and other matters for attention and the measures to be taken on accidents shall be carried with for the transport of radioactive loadings. (Okada, K.)

  4. National plan for achieving the objectives of the OSPAR strategy with regard to radioactive substances

    International Nuclear Information System (INIS)

    2002-06-01

    This report describes the Swedish plans for implementation of the OSPAR strategy with regard to radioactive substances. Revised release regulations for nuclear facilities are the primary tool in the work for achieving the objectives of the OSPAR strategy. The limitation of releases of radioactive substances shall be based on optimisation of radiation protection (ALARA) and the use of best available technique (BAT). Technical improvements to reduce discharges from the nuclear facilities include changes of daily routines in the waste management. Plans for the future include the introduction of new purification techniques and modernisation of waste facilities. The implementation of the new regulations, and in particular the introduction of BAT in terms of reference and target values for nuclear power reactors indicates the foreseen reductions of releases for the forthcoming five years. After that time, new reference and target values will be established. The regulations stipulate that monitoring of releases of radioactive substances shall be reported to the authorities. These reports will fulfil the demand for following-up of the progress of implementing the strategy. In particular, in yearly reports the progress towards reaching the target values will be monitored

  5. The gas-filled counting tube of the PTB - a device for the activity determination of radioactive gases

    International Nuclear Information System (INIS)

    Guenther, E.W.

    1993-08-01

    A measuring device for the activity determination of gaseous radioactive materials (H-3, Kr-85, C-14 O 2 ) has been set up as a PTB primary standard. Samples measured in it or their initial substances are the basis for activity standards. The gaseous samples are introduced directly into the vacuum device. The amount of gas filled can be determined by measuring pressure, volume and temperature. After the gas has been mixed with a counting gas (methane, argon/methane or propane), the count-rates are measured and the activity of the gas calculated. The activity of solid or liquid radioactive substances can also be determined with the device described, if they can be converted into a suitable gas. For this purpose there are additional devices (e.g. for producing hydrogen from water or C-14 O 2 from carbonate). The first models of these devices have been developed and are described. (orig.) [de

  6. Method for removal of decay heat of radioactive substances

    International Nuclear Information System (INIS)

    Hesky, H.; Wunderer, A.

    1981-01-01

    In this process, the decay heat from radioactive substances is removed by means of a liquid carried in the coolant loop. The liquid is partially evaporated by the decay heat. The steam is used to drive the liquid through the loop. When a static pressure level equivalent to the pressure drop in the loop is exceeded, the steam is separated from the liquid, condensed, and the condensate is reunited with the return flow of liquid for partial evaporation. (orig.) [de

  7. Nuclear power plant providing a function of suppressing the deposition of radioactive substance

    International Nuclear Information System (INIS)

    Honda, T.; Kawakami, T.; Izumiya, M.; Minato, A.; Ohsumi, K.

    1988-01-01

    In a nuclear power plant having a cooling system and radioactive coolant in the cooling system, the cooling system is described including ferrous structural material in contact with the radioactive coolant, wherein the ferrous structural material has a preliminary oxide film formed thereon, by oxidation of the bare surface portion thereof, by contacting bare surfaces of the structural material with flowing water containing an oxidizing agent and no metallic ions. The preliminary oxide film is formed at those portions of the ferrous structural material to be in contact with the radioactive coolant. The preliminary oxide film is formed prior to the structural material contacting the radioactive coolant. The preliminary oxide film consists essentially of Fe/sub 2/O/sub 3/ and having a thickness of at least 300 A, whereby later formation of new oxide film while the structural material is in contact with the radioactive coolant is suppressed to thereby suppress deposition of the radioactive substances on the ferrous structural material

  8. Method of determining paper-deposited materials, eg. lead, by their reaction with radioactive krypton

    International Nuclear Information System (INIS)

    Tolgyessy, J.; Pruzinec, J.

    1976-01-01

    The invention claims a method of determining substances on a paper carrier based on the substance reaction with 85 Kr gas and the measurement of radioactivity of the kryptonate formed. Lead is shown as an example. Different amounts of lead acetate were deposited on Whatman 2 chromatographic paper as was an unknown sample of Pb salt. The paper was exposed to a 2.5 mCi 85 Kr atmosphere for 48 hours. The activity of the individual spots was then measured, a calibration curve established and the amount of lead in the analyzed sample read-out. (Ha)

  9. Flask for highly radioactive substances

    International Nuclear Information System (INIS)

    1980-01-01

    The flask for highly radioactive substances described in this invention comprises a thick steel cylinder with leak proof closures at both ends and made up of several coaxial rings in rolled sheet steel, fitted into each other and welded to each other along their edges. The inner ring is preferably in sheet steel with a lining on its internal side, for instance a stainless steel lining. Likewise the outer ring is preferably in sheet steel with a covering on its outer side. The cylindrical body of the flask is welded by its lower end to a forged steel bottom and by its upper end to a forged steel ring. The bottom can also be made with several partitions. This forged steel ring has an inside peripheral shoulder and the upper end of the flask is closed in a leak proof manner by an initial forged steel plus resting on this shoulder and bolted to it and by a second plug bolted to the free end of this ring [fr

  10. Express control of migration processes of radioactive substances during drilling works in 'Ukryttya' object local zone

    International Nuclear Information System (INIS)

    Pravdivyj, A.A.

    2003-01-01

    Technical proposals are prepared to create a procedure for operative control of drilling works. Such a procedure will permit detecting the displacement of radioactively contaminated ground along borehole bore and correcting the drilling work procedure, which would prevent radioactive substance spreading, in boreholes of 'Ukryttya' object local zone and those of Exclusion Zone

  11. Study of casks shielded with heavy metal to transport highly radioactive substances

    International Nuclear Information System (INIS)

    Lucchesi, R.F.; Hara, D.H.S.; Martinez, L.G.; Mucsi, C.S.; Rossi, J.L.

    2014-01-01

    Nowadays, Brazil relies on casks produced abroad for transportation in its territory of substances that are sources of high radioactivity, especially the Mo-99. The product of the radioactive decay of the Mo-99 is the Tc-99m, which is used in nuclear medicine for administration to humans in the form of injectable radioactive drugs for the image diagnosis of numerous pathologies. This paper aims to study the existing casks in order to propose materials for the construction of the core part as shielding against gamma radiation. To this purpose, the existing literature on the subject was studied, as well as evaluation of existing and available casks. The study was focused on the core of which is made of heavy metals, especially depleted uranium for shielding the emitted radiation. (author)

  12. Code of Practice for the safe transport of radioactive substances 1990

    International Nuclear Information System (INIS)

    1990-01-01

    This Federal Code revises an earlier Code on the same subject issued in 1982 and was formulated under the Environment Protection (Nuclear Codes) Act 1978. The purpose of the Code is to establish uniform safety standards, applicable throughout the Commonwealth of Australia, to provide for the protection of persons and the environment, against any dangers associated with the transport of radioactive substances. The Code uses as a basis the IAEA Regulations for the Safe Transport of Radioactive Materials. This new edition takes into account the 1985 Edition of the Regulations incorporating the 1988 Supplement and provides, furthermore, that radiation protection standards will also be subject to recommendations of the Australian National Health and Medical Research Council [fr

  13. 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.

  14. 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

  15. An Act to regulate the keeping and use of radioactive substances, irradiating apparatus and certain electronic products, and for matters incidental thereto (No. 440 of 1975)

    International Nuclear Information System (INIS)

    1975-01-01

    This Radiation Safety Act 1975 which applies to radioactive substances and irradiating apparatus is a framework Act governing activities involving their possession and applications including their disposal. It makes provision for the duties and powers of the authorities responsible for administering the Act (the Radiological Council), licensing requirements and exemptions therefrom, registration of such substances and apparatus, inspection procedures and liability under the Act. The Radioactive Substances Act 1954, the Radioactive Substances Act Amendment Acts 1960 and 1964 are repealed. (NEA) [fr

  16. Safety in transports of civil radioactive substances on the French territory. Lessons learned by the IRSN from the analysis of significant events declared in 2012 and 2013. Safety of transports of civil radioactive substances in France

    International Nuclear Information System (INIS)

    2016-11-01

    After a presentation of some general elements regarding transports of radioactive substances in France, this report proposes a synthetic overview of the main lessons learned by the IRSN from the analysis of transport-related events in 2012 and 2013. Then, the body of this report presents the context of transports of radioactive substances: legal framework, main safety elements, nature and flows of these transports in France, transports per activity sector. It proposes a global analysis of significant events, with a comparison with previous years. The four main significant events are described. Some transverse issues are finally addressed: return on experience on crisis management in relationship with transport events, IRSN study on the behaviour of packagings during long duration fire

  17. Applicability of Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) to releases of radioactive substances

    International Nuclear Information System (INIS)

    Miller, S.R.

    1987-01-01

    The Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA), commonly called Superfund, provided a $1.6 billion fund (financed by a tax on petrochemical feedstocks and crude oil and by general revenues) for the cleanup of releases of hazardous substances, including source, special nuclear or byproduct material, and other radioactive substances, from mostly inactive facilities. The US Environmental Protection Agency (EPA) is authorized to require private responsible parties to clean up releases of hazardous substances, or EPA, at its option, may undertake the cleanup with monies from the Fund and recover the monies through civil actions brought against responsible parties. CERCLA imposes criminal penalties for noncompliance with its reporting requirements. This paper will overview the key provisions of CERCLA which apply to the cleanup of radioactive materials

  18. Criteria relating to the approval of consumer goods containing radioactive substances: a consultative document

    International Nuclear Information System (INIS)

    1980-05-01

    The National Radiological Protection Board currently provides manufacturers and suppliers of consumer goods containing radioactive substances with advice on the acceptability of their products. Examples of such goods available to the public include radioluminous devices such as clocks, watches and compasses, products containing gaseous tritium light sources, ionisation chamber smoke detectors and thorium gas mantles. In the present document, detailed proposals are put forward for criteria which the Board may use when considering applications for the approval of goods containing radioactive substances to ensure that they are safe. The proposals relate to the radiation doses to consumers and others who may be exposed as a consequence of their activities, and also consider the benefits to consumers. They are concerned with doses arising during normal use, through accidents and misuse, and as a consequence of uncontrolled disposal. (U.K.)

  19. Method of treating the waste liquid of a washing containing a radioactive substance

    International Nuclear Information System (INIS)

    Sawaguchi, Yusuke; Tsuyuki, Takashi; Kaneko, Masato; Sato, Yasuhiko; Yamaguchi, Takashi.

    1975-01-01

    Object: To separate waste liquid resulting from washing and which contains a radioactive substance and surface active agent into high purity water and a solid waste substance containing a small quantity of surface active agent. Structure: To waste liquid from a waste liquid tank is added a pH adjusting agent for adjusting the pH to 5.5, and the resultant liquid is sent to an agglomeration reaction tank, in which an inorganic agglomerating agent is added to the waste liquid to cause a major proportion of the radioactive substance and surface active agent to form flocks produced through agglomeration. Then, the waste liquid is sent from the agglomeration reaction tank to a froth separation tank, to which air is supplied through a perforated plate to cause frothing. The over-flowing liquid is de-frothed, and then the insoluble matter is separated as sludge, followed by hydroextraction and drying for solidification. The treated liquid extracted from a froth separation tank is sent to an agglomerating agent recovery tank for separation of the agglomeration agent, and then the residual surface active agent is removed by adsorption in an active carbon adsorption tower, followed by concentration by evaporation in an evaporating can. The concentrated liquid is extracted and then solidified with cement or asphalt. (Kamimura, M.)

  20. Summary of the law relating to atomic energy and radioactive substances

    International Nuclear Information System (INIS)

    Sim, D.F.; Ritchie, K.J.S.

    1983-04-01

    Intended as a signpost to the relevant law no aspect is covered in detail but a full summary is given. For further details reference has to be made to Acts or regulations themselves. The summary covers the Common Law, the laws in force, regulations under the Factories Act 1961, regulations and orders relating to food and medicines, those concerned with the transport of radioactive materials, regulations under the Social Security Act 1975, Control of Import and Export, the Euratom treaty, important non-statutory codes of practice etc., international conventions, regulations etc. relating to the peaceful use of atomic energy and radioactive substances in which the UK is interested and finally, foreign legislation. The details have been revised as at 31 March 1983. (U.K.)

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

    International Nuclear Information System (INIS)

    2008-03-01

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

  2. The Belgian approach and status on the radiological surveillance of radioactive substances in metal scrap and non-radioactive waste and the financing of orphan sources

    International Nuclear Information System (INIS)

    Braeckeveldt, Marnix; Preter, Peter De; Michiels, Jan; Pepin, Stephane; Schrauben, Manfred; Wertelaers, An

    2007-01-01

    Numerous facilities in the non-nuclear sector in Belgium (e.g. in the non-radioactive waste processing and management sector and in the metal recycling sector) have been equipped with measuring ports for detecting radioactive substances. These measuring ports prevent radioactive sources or radioactive contamination from ending up in the material fluxes treated by the sectors concerned. They thus play an important part in the protection of the workers and the people living in the neighbourhood of the facilities, as well as in the protection of the population and the environment in general. In 2006, Belgium's federal nuclear control agency (FANC/AFCN) drew up guidelines for the operators of non-nuclear facilities with a measuring port for detecting radioactive substances. These guidelines describe the steps to be followed by the operators when the port's alarm goes off. Following the publication of the European guideline 2003/122/EURATOM of 22 December 2003 on the control of high-activity sealed radioactive sources and orphan sources, a procedure has been drawn up by FANC/AFCN and ONDRAF/NIRAS, the Belgian National Agency for Radioactive Waste and Enriched Fissile Materials, to identify the responsible to cover the costs relating to the further management of detected sealed sources and if not found to declare the sealed source as an orphan source. In this latter case and from mid-2006 the insolvency fund managed by ONDRAF/NIRAS covers the cost of radioactive waste management. At the request of the Belgian government, a financing proposal for the management of unsealed orphan sources as radioactive waste was also established by FANC/AFCN and ONDRAF/NIRAS. This proposal applies the same approach as for sealed sources and thus the financing of unsealed orphan sources will also be covered by the insolvency fund. (authors)

  3. Regulatory requirements for the use of consumer products containing radioactive substances

    International Nuclear Information System (INIS)

    Mason, G.C.; Paynter, R.A.; Schmitt-Hannig, A.; Sztanyik, L.B.

    1996-01-01

    In almost 100 years since the discovery of radioactivity, the properties of radioactive materials have been exploited in products such as clocks and watches incorporating luminous paint which are freely available to members of the public. Over time, regulatory authorities have felt it necessary to apply some degree of control to the supply and use of such products in order to protect public health. In many areas of radiation protection, national authorities take note of international recommendations when developing national standards, but the existing detailed guidance of the International Atomic Energy Agency (IAEA) for consumer products is incomplete and out of date. Recently, a thorough revision of the International Basic Safety Standards (BSS) has occurred, which has prompted a review and revision of the related guidance published by the IAEA. A draft Guide on Regulatory Requirements for the Use of Consumer Products Containing Radioactive Substances has now been completed and is currently under review within the IAEA's system for development of documents in its Safety Series of publications. (author)

  4. Sim and Ritchie's summary of the law relating to atomic energy and radioactive substances

    International Nuclear Information System (INIS)

    Grazebrook, D.; Turner, M.

    1984-12-01

    The law is summarised under the headings: the Common Law; the Legislation; Regulations under the Factories Act 1961; Regulations relating to educational establishments; Regulations and Orders relating to food and medicines; Regulations, Rules, etc. affecting the transport of radioactive materials; Regulations under the Social Security Act 1975; control of import and export; the Euratom Treaty; important non-statutory Codes of Practice, etc.; international Conventions, Regulations, etc. relating to the peaceful use of atomic energy and radioactive substances, in which the United Kingdom is interested; foreign legislation. (U.K.)

  5. Inconsistency... or why differentiate, where prevention is concerned, between radioactive substances and carcinogenic chemicals

    International Nuclear Information System (INIS)

    Choquet, R.; Vinit, J.

    1982-01-01

    Radiotracers, low-activity unsealed radioactive sources, and certain chemical products belong to the list of substances and agents known to promote cancers in humans. The dangers of radiotracers and carcinogenic chemicals being very similar, or even identical, it is inadmissible that preventive measures have not been equally developed and are not viewed in the same way in our country. It should be noted that the International Labour Bureau has long since included radioactive products in the list of carcinogenic substances and agents and treated preventive measures as a whole by proceeding in this way it would be easier to account for the possible combined effects of ionising radiations and chemical molecules. After a review of some facts about cancer the present situation is examined with regard to statutory measures applied on the one hand to radioelements and on the other to chemicals recognised as carcinogenic by international organisations. Proposals are made to remedy this illogical situation [fr

  6. Levels of surface contamination with radioactive materials at workplaces of nuclear research centre at Rez

    International Nuclear Information System (INIS)

    Hoelgye, Z.; Nemcova, I.; Kasikova, M.; Popper, J.; Chysky, J.

    1983-01-01

    A hygiene supervision unit at workplaces of the nuclear Research Institute in Rez monitored on a long-term basis surface contamination with radioactive substances. Surface contamination was found at workplaces with open sources. Of the 4343 monitored places action levels were only exceeded in 13 cases. The obtained data were used for typifying workplaces with the highest level of surface contamination, to determine in certain instances the mechanism of the escape of radioactive substances from insulating facilities and to determine the rate of the spread of the radioactive substance into adjacent non-active workplaces. (author)

  7. The Application and Regulation of Non-Medical radioactive Substances in Taiwan, China

    International Nuclear Information System (INIS)

    Chang, Chihchien; Chou, Keiden; Wang, Songfeng

    1998-01-01

    Based on the Atomic Energy Law of Taiwan and regulations regarding radiation protection, an operating system has been established for the approval and regulation of import (production), installation, licensing, safety inspection, record keeping, storage, transfer, transportation and abandonment of nonmedical radioactive materials and equipment capable of producing ionizing radiation. In order to ensure that all equipment capable of producing ionizing radiation can meet the respective standard of radiation protection in accordance with the ALARA principle, nonmedical equipment capable of producing ionizing radiation is divided into six categories depending on its inherent shielding ability, operation limit, characteristics of the radiation and the required degree of surveillance for achieving the purpose of radiation protection. The six categories are: 1. Protective equipment, 2. Immobile closed equipment, 3. Automatic operating equipment, 4. Mobile equipment, 5. Unsealed radioactive substances, 6. Consumer products and other radioactive sources with different properties. Each category has its specific requirements in radiation protection. (author)

  8. Development of Radioactive Substance Contamination Diffusion Preventive Equipment for a Hot cell

    International Nuclear Information System (INIS)

    Choo, Yong Sun; Kim, Do Sik; Baik, Seung Je; Yoo, Byung Ok; Kim, Ki Ha; Lee, Eun Pyo; Ahn, Sang Bok; Ryu, Woo Seok

    2009-01-01

    The hot cell of irradiated materials examination facility (IMEF), which has been operating since 1996, is generally contaminated by the radioactive nuclides of irradiated nuclear fuels and structural steels like Cs-137, Co-60, Co-134 and Ru-106. Especially Cs-137 is a main contaminated radioactive isotope which is easily moved here and there due to air flow in the hot cell, water-soluble, extremely toxic, and has a half-life of 30.23 years. To repair or fix the abnormal function of test apparatus installed in the hot cell, the maintenance door, so called a rear door and located at an intervention area, is opened to enter the hot cell inside. In a moment of opening the maintenance door, dirty air diffusion from the hot cell to an intervention area could be occurred in spite of increasing the rpm of exhaust fan to maintain much low under pressure, but an adjacent area to a maintenance door, i.e. intervention area, is very severely contaminated due to the unpredictable air flow. In this paper, the development of the radioactive substance contamination diffusion preventive equipment for a hot cell is studied to prevent dirty and toxic gaseous radioactive nuclides diffusion from a hot cell and installed at an intervention area of IMEF

  9. Radioactive substance removing device

    International Nuclear Information System (INIS)

    Takeuchi, Jun; Tayama, Ryuichi; Teruyama, Hidehiko; Hikichi, Takayoshi.

    1992-01-01

    If inert gases are jetted from a jetting device to liquid metals in a capturing vessel, the inert gases are impinged on the inner wall surface of the capturing vessel, to reduce the thickness of a boundary layer as a diffusion region of radioactive materials formed between the inner wall surface of the capturing vessel and the liquid metals. Further, a portion of the boundary layer is peeled off to increase the adsorption amount of radioactive materials by the capturing vessel. When the inert gases are jetted on the inner or outer circumference of the capturing vessel to rotate the capturing vessel, the flow of the liquid metals is formed along with the rotation, and the thickness of the boundary layer is reduced or the boundary layer is peeled off to increase the absorption amount of the radioactive materials. If gas bubbles are formed in the liquid metals by the inert gases, the liquid metals are stirred by the gas bubbles to reduce the thickness of the boundary layer or peel it off, thereby enabling to increase the adsorption amount of the radioactive materials. Since it is not necessary to pass through the rotational member to the wall surface of the vessel, safety and reliability can be improved. (N.H.)

  10. Ministerial Order appointing the Customs Offices through which radioactive substances or devices containing such substances subject to licensing must be imported

    International Nuclear Information System (INIS)

    1977-01-01

    Under the royal Order of 28 February 1963 regulating protection of the population and workers against the hazards of ionizing radiation, this Order by the Minister of Public Health and the Family designates the Customs Offices through which radioactive substances and devices containing them may be imported. It lists for each type of transport (land, sea etc) the authorised points of access into Belgium. (NEA) [fr

  11. Determination of the potential radiation exposure of the population close to the Asse II mine caused by deduction of radioactive substances with the discharge air in the normal operation using the ''Atmospheric Radionuclide-Transport-Model'' (ARTM); Ermittlung der potenziellen Strahlenexposition der Bevoelkerung in der Umgebung der Schachtanlage Asse II infolge Ableitung radioaktiver Stoffe mit den abwettern im bestimmungsgemaessen Betrieb mittels des ''atmospaerischen Radionuklid-Transport-Modells'' ARTM

    Energy Technology Data Exchange (ETDEWEB)

    Esch, D.; Wittwer, C. [Bundesamt fuer Strahlenschutz, Salzgitter (Germany)

    2014-01-20

    Between 1967 and 1978 125.787 packages filled with low-level and intermediate-level radioactive waste were emplaced in the mining plant Asse II. Volatile radioactive substances like H-3, C-14 and Rn-222 are released from the emplaced waste. These substances reach the ventilated parts of the mine and are released with the discharge air. The potential radiation exposure of the population caused by deduction of radioactive substances with the discharge air in the normal operation is determined by the ''Atmospheric Radionuclide-Transport-Model'' (ARTM). As result the maximal deductions of volatile radioactive substances with the discharge air in the normal operation of the Asse II mine lead to radiation exposure of the population, which is considerably lower than the permissible values of application rate.

  12. Requirements for a long-term safety certification for chemotoxic substances stored in a final storage facility for high radioactive and heat-generating radioactive waste in rock salt formations

    International Nuclear Information System (INIS)

    Tholen, M.; Hippler, J.; Herzog, C.

    2007-01-01

    Within the scope of a project funded by the German Federal Ministry of Economics and Technology (Bundesministerium fuer Wirtschaft und Technologie, BMWi), a safety certification concept for a future permanent final storage for high radioactive and heat-generating radioactive waste (HAW disposal facility) in rock salt formations is being prepared. For a reference concept, compliance with safety requirements in regard to operational safety as well as radiological and non-radiological protection objectives related to long-term safety, including ground water protection, will be evaluated. This paper deals with the requirements for a long-term safety certification for the purpose of protecting ground water from chemotoxic substances. In particular, longterm safety certifications for the permanent disposal of radioactive waste in a HAW disposal facility in rock salt formations and for the dumping of hazardous waste in underground storage facilities in rock salt formations are first discussed, followed by an evaluation as to whether these methods can be applied to the long-term safety certification for chemotoxic substances. The authors find it advisable to apply the long-term safety certification for underground storage facilities to the long-term safety certification for chemotoxic substances stored in a HAW disposal facility in rock salt formations. In conclusion, a corresponding certification concept is introduced. (orig.)

  13. Radioactive Substances Act 1960

    International Nuclear Information System (INIS)

    1960-01-01

    This Act regulates the keeping and use of radioactive material and makes provision for the disposal and storage of radioactive waste in the United Kingdom. It provides for a licensing system for such activities and for exemptions therefrom, in particular as concerns the United Kingdom Atomic Energy Authority. The Act repeals Section 4(5) of the Atomic Energy Authority Act, 1954 which made temporary provision for discharge of waste on or from premises occupied by the Authority. (NEA) [fr

  14. Radioactivity and food

    International Nuclear Information System (INIS)

    Olszyna-Marzys, A.E.

    1990-01-01

    Two topics relating to radioactivity and food are discussed: food irradiation for preservation purposes, and food contamination from radioactive substances. Food irradiation involves the use of electromagnetic energy (x and gamma rays) emitted by radioactive substances or produced by machine in order to destroy the insects and microorganisms present and prevent germination. The sanitary and economic advantages of treating food in this way are discussed. Numerous studies have confirmed that under strictly controlled conditions no undesirable changes take place in food that has been irradiated nor is radioactivity induced. Reference is made to the accident at the Chernobyl nuclear power station, which aroused public concern about irradiated food. The events surrounding the accident are reviewed, and its consequences with regard to contamination of different foods with radioactive substances, particularly iodine-131 and cesium-137, are described. Also discussed are the steps that have been taken by different international organizations to set limits on acceptable radioactivity in food.15 references

  15. Determination of hepatic blood flow through radioactive colloidal gold in congestive heart foilure

    International Nuclear Information System (INIS)

    Papaleo Netto, M.; Carvalho, N.; Carvalho Filho, E.T.; Forti, N.A.; Giannini, S.D.; Diament, J.; Decourt, L.V.; Chiaverini, R.

    1974-01-01

    Hepatic blood flow as derermined by radioactive colloidal gold and its correlation with total blood valume are studied in 13 patients with predominantly right-side congestive heart failure. During the phase of cardiac compensation, the following events occur: 1) significant decrease of the half-life of the clearance of radioactive colloidal gold and of the total blood volume; 2) increase of the clearance constant of the radioactive substance and of hepatic blood flow; 3) significantion correlation between the clearance constant and the total blood volume [pt

  16. Radioactive substances

    International Nuclear Information System (INIS)

    Butler, G.C.; Hyslop, C.

    1980-01-01

    The purpose of this chapter is to show how to assess the detriment resulting from the release of radioactive materials to the environment. The minimum information required for the assessments is given for seven radionuclides of interest from the point of view of environmental contamination. The seven radionuclides are tritium, krypton-85, strontium-90, iodine-131, cesium-137, radium-226 and plutonium-239. Information is given on the radiation doses and the radiation effects on man due to these radioisotopes. (AN)

  17. Determination of detailed regulations concerning transportation of radioactive materials by vehicles

    International Nuclear Information System (INIS)

    1978-01-01

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

  18. Determination of detailed standards for transportation of radioactive materials by ships

    International Nuclear Information System (INIS)

    1978-01-01

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

  19. Guideline for the assessment of radioactive substances in drinking water in the frame of the implementation of the drinking water regulation. Recommendation by BMUB, BfS, UBA and the responsible state authorities and DVGW and BDFW; Leitfaden zur Untersuchung und Bewertung von radioaktiven Stoffen im Trinkwasser bei der Umsetzung der Trinkwasserverordnung. Empfehlung von BMUB, BMG, BfS, UBA und den zustaendigen Landesbehoerden sowie DVGW und BDEW

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-01-15

    The guidelines on the assessment of radioactive substances in drinking water cover the following issues: terms, symbols and units concerning radioactivity, radioactivity in the drinking water and radiation exposure, requirements for drinking water with respect to radioactive substances, fundamentals of the assessment concept according to the drinking water regulation, practical application of the assessment concept, analytical determination of radioactivity related parameters.

  20. 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.)

  1. Radioactive Substances Regulations, 1959 under the Radioactive Substances Act 1957

    International Nuclear Information System (INIS)

    1983-01-01

    These Regulations as amended lay down maximum permissible concentrations and doses and prescribe radiation protection measures for personnel. They provide for the licensing procedures for radioactive materials and irradiating apparatus and the conditions to be complied with for their handling, packaging, transport and disposal. The Schedules to the Regulations contain tables of maximum permissible radionuclide concentrations, models of licence application forms and labels. (NEA) [fr

  2. 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

  3. Determination of radioactivity in meat samples

    International Nuclear Information System (INIS)

    Malik, G.M.; Atta, M.A.; Shafiq, M.; Zafar, M.S.

    1993-01-01

    The presence of radionuclides in edibles can create harmful effects in the human body. It is, therefore, essential that the radioactivity must be searched in the food stuff specially in those items which are available near the nuclear installations. The radioactivity in the meat samples obtained from the surroundings of PINSTECH (Pakistan Institute of Nuclear Science and Technology), PINSTECH Complex has been determined using high resolution Ge(Li) gamma ray spectrometer and a low level beta counting system. The results show that the measured values of the radioactivity are below the maximum permissible levels. (author)

  4. Conducting the personal subsidiary plot at the territory, contaminated with radioactive substances

    International Nuclear Information System (INIS)

    Borovikov, A.N.; Kulazhenko, V.G.; Kovalev, S.D.; Milyuta, B.I.; Basalaeva, Z.N.

    1993-01-01

    As a result of Chernobyl NPP accident large amount of radioactive substances fell at agricultural areas and its production became the source of additional irradiation of population. One of the task is to get food with the content of radionuclides not exceeding the fixed norms. The rules of working hygiene which provide safe living of population at the territories with different level of contamination are described. Recommendations for processing the fruit and market gardens are given, suitable from the point of view of accumulation of radionuclides vegetables and fruits, kinds and sorts cultures are presented. The rules of keeping and feeding the animals, bees and fur-bearing animals are developed. The rules for primary processing of products of plant-growing and stock-breeding, which permit to decrease radioactive contamination 2-10 and more times are presented. Methods of using the products of forest - material and fuel wood, meet of wild animals, mushrooms and berries - are proposed. 5 tabs

  5. Illustrative assessment of human health issues arising from the potential release of chemotoxic substances from a generic geological disposal facility for radioactive waste.

    Science.gov (United States)

    Wilson, James C; Thorne, Michael C; Towler, George; Norris, Simon

    2011-12-01

    Many countries have a programme for developing an underground geological disposal facility for radioactive waste. A case study is provided herein on the illustrative assessment of human health issues arising from the potential release of chemotoxic and radioactive substances from a generic geological disposal facility (GDF) for radioactive waste. The illustrative assessment uses a source-pathway-receptor methodology and considers a number of human exposure pathways. Estimated exposures are compared with authoritative toxicological assessment criteria. The possibility of additive and synergistic effects resulting from exposures to mixtures of chemical contaminants or a combination of radiotoxic and chemotoxic substances is considered. The case study provides an illustration of how to assess human health issues arising from chemotoxic species released from a GDF for radioactive waste and highlights potential difficulties associated with a lack of data being available with which to assess synergistic effects. It also highlights how such difficulties can be addressed.

  6. Illustrative assessment of human health issues arising from the potential release of chemotoxic substances from a generic geological disposal facility for radioactive waste

    International Nuclear Information System (INIS)

    Wilson, James C; Towler, George; Thorne, Michael C; Norris, Simon

    2011-01-01

    Many countries have a programme for developing an underground geological disposal facility for radioactive waste. A case study is provided herein on the illustrative assessment of human health issues arising from the potential release of chemotoxic and radioactive substances from a generic geological disposal facility (GDF) for radioactive waste. The illustrative assessment uses a source–pathway–receptor methodology and considers a number of human exposure pathways. Estimated exposures are compared with authoritative toxicological assessment criteria. The possibility of additive and synergistic effects resulting from exposures to mixtures of chemical contaminants or a combination of radiotoxic and chemotoxic substances is considered. The case study provides an illustration of how to assess human health issues arising from chemotoxic species released from a GDF for radioactive waste and highlights potential difficulties associated with a lack of data being available with which to assess synergistic effects. It also highlights how such difficulties can be addressed.

  7. Radiological testing of products containing radioactivity

    International Nuclear Information System (INIS)

    Dixon, D.W.; Knight, A.

    1980-01-01

    Consumer products containing radioactive substances are tested by NRPB to determine how much radioactive material is likely to be released from a product if it is misused or accidentally damaged. Such testing is briefly described with particular reference to ionisation chamber smoke detectors, liquid crystal display watches illuminated with gaseous tritium light sources and anti-static brushes containing polonium-210 in the form of ceramic microspheres. (U.K.)

  8. Influence of humic acids on the migration behavior of radioactive and non-radioactive substances under conditions close to nature. Synthesis, radiometric determination of functional groups, complexation

    International Nuclear Information System (INIS)

    Pompe, S.; Bubner, M.; Schmeide, K.; Heise, K.H.; Bernhard, G.; Nitsche, H.

    2000-04-01

    The interaction behavior of humic acids with uranium(VI) and the influence of humic substances on the migration behavior of uranium was investigated. A main focus of this work was the synthesis of four different humic acid model substances and their characterization and comparison to the natural humic acid from Aldrich. A radiometric method for the determination of humic acid functional groups was applied in addition to conventional methods for the determination of the functionality of humic acids. The humic acid model substances show functional and structural properties comparable to natural humic acids. Modified humic acids with blocked phenolic OH were synthesized to determine the influence of phenolic OH groups on the complexation behavior of humic acids. A synthesis method for 14 C-labeled humic acids with high specific activity was developed. The complexation behavior of synthetic and natural humic acids with uranium(VI) was investigated by X-ray absorption spectroscopy, laser-induced fluorescence spectroscopy and FTIR spectroscopy. The synthetic model substances show an interaction behavior with uranium(VI) that is comparable to natural humic acids. This points to the fact that the synthetic humic acids simulate the functionality of their natural analogues very well. For the first time the influence of phenolic OH groups on the complexation behavior of humic acids was investigated by applying a modified humic acid with blocked phenolic OH groups. The formation of a uranyl hydroxy humate complex was identified by laserspectroscopic investigations of the complexation of Aldrich humic acid with uranium(VI) at pH7. The migration behavior of uranium in a sandy aquifer system rich in humic substances was investigated in column experiments. A part of uranium migrates non-retarded through the sediment, bound to humic colloids. The uranium migration behavior is strongly influenced by the kinetically controlled interaction processes of uranium with the humic colloids

  9. Structural models of public risk perception of radioactive substances in food. An analysis of the data from internet survey

    International Nuclear Information System (INIS)

    Kito, Yayoi; Niiyama, Yoko

    2012-01-01

    In risk communication of food contamination by radioactive substances derived from the accident at Fukushima Daiichi nuclear power plant, it is required that experts, government and the public exchange information and opinions and establish a mutual understanding. To meet these requirements, it is necessary to investigate public risk perception and the structure of perception. We conducted a series of internet surveys in 2011-2012, two times in Kanto- and Kansai-area on men and women aged from 30 to 49 who have children, and once in all parts of Japan on women aged from 20 to 59. From the data analysis, we identified the feature of risk perception of radioactive substances and buying behavior, and moreover, we analyzed the relationship among the perceived risks and other factors using Structural Equation Modeling. (author)

  10. An interpretation of schedule 1 of the Radioactive Substances Act 1993 and related issues

    International Nuclear Information System (INIS)

    Hill, M.; Wakerley, M.W.

    2000-09-01

    Schedule 1 of the UK's Radioactive Substances Act 1993 was originally Schedule 3 of the 1960 Act of the same name. It is possible that different methods are currently being employed to interpret how Schedule 1 should be used. This report provides an interpretation and guidance on this and related issues. It is primarily for technical specialists already familiar with the workings of the Act. This report covers the period 1999/2000

  11. Management of sites potentially polluted by radioactive substances - Methodological guidebook; Gestion des sites potentiellement pollues par des substances radioactives - Guide methodologique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-12-15

    This document is the update of the 'methodological guidelines for the management of industrial areas potentially contaminated by radioactive substances', published in 2001 by IRSN. Revisions intended to bring coherence between management of areas polluted by radioactive substances and the general policy applied to polluted sites described in a document published in Feb. 2007 by the French Ministry in charge of Environment. Requirements introduced both by the law relative to waste management of June 28, 2006 and the ministerial order of 17 November 2008 were introduced. The involvement of all stakeholders during the process was stressed. The updating mainly lead to introduce a clear distinction between polluted areas where uses are established and those without use or at redevelopment stage. When the uses are established, an 'Interpretation of the condition of environment' is conducted. Alternatively, the remediation process follows a 'management plan'. The revision also led to the disappearance of the 'doubt removal' phase which has been incorporated as an entire part in the site characterisation. Among other significant changes, it may be noted the evolution of the 'risk assessment' tools from simplified risk assessment and detailed risk assessment to a single tool allowing the quantitative assessment of exposure (EQER). Finally, the guidelines highlight stakeholder involvement in identifying the different participants and in reminding the benefits of a consultative approach. Whatever the remediation process: interpretation of the condition of environment or management plan; site characterisation is required as soon as a pollution is suspected. It includes literature reviews and field investigations primarily to confirm or deny the presence of pollution and, where appropriate, to determine its location, nature and level. The effort accorded to site characterisation must be proportionate to identified issues. The

  12. Factories Act 1961, Ionizing Radiations (Unsealed Radioactive Substances) Regulations 1968, Certificate of Approval No.1 (General)

    International Nuclear Information System (INIS)

    1969-01-01

    Under the Ionising Radiations (Unsealed Radioactive Substances) Regulations No. 780 of 1968, the Chief Inspector of Factories has wide powers to ensure the protection of workers. By this Certificate he approved, for the purpose of measuring radiation doses, any radiation dosemeter, based on the phenomenon of radiation-induced thermoluminescence, supplied by an approved laboratory. (NEA) [fr

  13. Workshop meeting on State accounting and control system for radioactive substances and waste

    International Nuclear Information System (INIS)

    Evseev, V.F.

    2012-01-01

    On 2-6 July 2012, the fifth All-Russian workshop meeting of State Accounting and Control System for Radiation Substances (RS) and Radioactive Wastes (RAW) was conducted. The objective of the workshop was to discuss development of the State Accounting and Control System for RS and RAW in the Russian Federation, current changes to legal acts and regulations that pertain to management of RS and RAW, as well as other issues related to organisation of RS and RAW management activities and promotion of international cooperation [ru

  14. Models for environmental impact assessments of releases of radioactive substances from CERN facilities

    CERN Document Server

    Vojtyla, P

    2005-01-01

    The document describes generic models for environmental impact assessments of releases of radioactive substances from CERN facilities. Except for few models developed in the Safety Commission, the models are based on the 1997 Swiss directive HSK-R-41 and on the 2001 IAEA Safety Report No. 19. The writing style is descriptive, facilitating the practical implementation of the models at CERN. There are four scenarios assumed for airborne releases: (1) short-term releases for release limit calculations, (2) actual short-term releases, (3) short-term releases during incidents/accidents, and (4) chronic long-term releases during the normal operation of a facility. For water releases, two scenarios are considered: (1) a release into a river, and (2) a release into a water treatment plant. The document shall be understood as a reference for specific environmental studies involving radioactive releases and as a recommendation of the Safety Commission.

  15. Using radioactive tracer technique in municipal hygiene

    International Nuclear Information System (INIS)

    Yurasova, O.I.

    1974-01-01

    Work of the A. N. Syrsin Institute of General and Municiapl Hygiene using raidoactive tracers is reviewed. The studies include research on protein metabolism in the living organism following action of unfavorable factors of the environment; determination of the paths of introduction into the organism of substances with an alien composition; and study of the rate of resorption of subcutaneous papuli. Results are shown of radioactive-tracer studies on the mechanism of action of poisonous substances on the living organism and of migration of alien chemical compounds in the organism and in objects in the environment. It is concluded that the radioactive tracer method has wide application in municipal hygiene and sanitary microbiology. The absence of laborious operations, economy of time, precision of the experiments, and the possibility of obtaining additional information on the mechanism of action of poisonous substances on the organism and the low cost of such studies compared with other methods makes the radioactive tracer method economically attractive. The studies made show the various types of use of the method in municipal hygiene and sanitary microbiology

  16. Using radioactive tracer technique in municipal hygiene

    Energy Technology Data Exchange (ETDEWEB)

    Yurasova, O I [Institut Obshchej i Kommunal' noj Gigieny, Moscow (USSR)

    1974-01-01

    Work of the A. N. Syrsin Institute of General and Municiapl Hygiene using raidoactive tracers is reviewed. The studies include research on protein metabolism in the living organism following action of unfavorable factors of the environment; determination of the paths of introduction into the organism of substances with an alien composition; and study of the rate of resorption of subcutaneous papuli. Results are shown of radioactive-tracer studies on the mechanism of action of poisonous substances on the living organism and of migration of alien chemical compounds in the organism and in objects in the environment. It is concluded that the radioactive tracer method has wide application in municipal hygiene and sanitary microbiology. The absence of laborious operations, economy of time, precision of the experiments, and the possibility of obtaining additional information on the mechanism of action of poisonous substances on the organism and the low cost of such studies compared with other methods makes the radioactive tracer method economically attractive. The studies made show the various types of use of the method in municipal hygiene and sanitary microbiology.

  17. Best Available Technique (BAT) as an Instrument for the Limitation of Radioactive Substances from Nuclear Power Reactors in Sweden

    International Nuclear Information System (INIS)

    Moberg, L.; Sundell-Bergman, S.; Sandwall, J.

    2004-01-01

    Traditionally, the concept of ALARA has been the basis for limitation and optimisation of releases of radioactive substances from nuclear power reactors in order to protect human health. In recent years, it has been discussed whether the ALARA principle can be applied also to protect the environment. For the protection of the environment, in particular for non-nuclear pollutants, the precautionary principle and the concept of Best Available Technique (BAT) have been applied. New Swedish regulations concerning the protection of human health and the environment from radioactive discharges from certain nuclear installations entered into force January 1st, 2002. The prime purpose of the regulations is to limit the radioactive releases. This limitation shall be based on the optimisation of radiation protection and shall be achieved by using BAT. In order to show compliance with the regulation and BAT, the concepts of reference values and target values have been introduced for nuclear power reactors. The reference value should be the release that is representative for optimum use and full functioning of systems of importance to the occurrence and limitation of radioactive releases from nuclear power reactors. The target value should show the level to which radioactive releases from nuclear power reactors can be reduced during a certain given period of time. Reference and target values have been determined for each nuclear power reactor in Sweden. Each year, the reactor licensees shall report to the Swedish Radiation Protection Authority (SSI) the measures that have been adopted or that are planned to be adopted to limit radioactive releases with the aim of achieving the target values. The first report has been submitted to the SSI in 2003. (Author) 8 refs

  18. Deposition of high-level radioactive waste products in bore-holes with buffer substance

    International Nuclear Information System (INIS)

    Jacobsson, A.; Pusch, R.

    1977-05-01

    The present investigation comprised a compilation of available literature data concerning the possible use of clayey masses as buffer substances in bore-holes (in rock) with canisters containing radioactive waste products. The aim was to find a suitable composition of the buffer mass and to recommend a suitable storing technique. The criteria concerning the function of the buffer substance were: Sufficient mechanical supporting power, suitable mechanical properties, prevention of free circulation of ground water, ion-adsorption ability, sufficiently good heat conduction properties. These criteria suggest that a buffer substance containing Na-montmorillonite would be suitable. Literature studies and own experience show that montmorillonite is permanently stable at 100 degrees C temperature and 5 MPa pressure when pH is within the range of 6.5-10 while quartz is stable at pH <9. The authors conclude that the suggested principle of storing the canisters in sealed bore-holes filled with a 10 percent bentonite/90 percent quartz (silt, sand) mass is suitable provided that the tunnel system, from which the holes are bored, is sealed with a dense buffer mass consisting of quartz (silt, sand) and 20-50 percent bentonite powder. (author)

  19. Method for the radioactive determination of the foliates

    International Nuclear Information System (INIS)

    Rosen, H.

    1976-01-01

    A method is described for the radioactive determination of the foliates, in which a determination is made of the uptake on a protein fraction of the milk taking up the foliates by competition between the foliate(s) to be determined and a folic acid by-product labelled with a radioactive isotope. The characteristics of this method is that it consists in using tyramide of iodinated folic acid 125 [fr

  20. Determination of radioactivity in Cisadane River

    International Nuclear Information System (INIS)

    Tarigan, C.; Lubis, E.

    1993-01-01

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

  1. Radioactive substance separation systems

    International Nuclear Information System (INIS)

    Sakai, Takuhiko.

    1981-01-01

    Purpose: To enable separation of fission products, radioactive corrosion products and the likes in primary coolants with no requirement for the replacement of separation system during plant service life, by providing protruded magnetic pole plates in a liquid metal flow channel to thereby form slopes magnetic fields. Constitution: A plurality of magnetic pole plates are disposed vertically in a comb-like arrangement so as not to contact with each other along the direction of flow in a rectangular primary coolant pipeway at the exit of the reactor core in an LMFBR type reactor. Large magnetic poles are provided to the upper and lower sides of the pipeway and coils are wound on the side opposed to the pipeway. When electrical current is supplied to the coils, the magnetic pole is magnetized intensely and thus the magnetic pole plates are also magnetized intensely and thus the magnetic pole plates are also magnetized intensely to form large gradient in the magnetic fields between the upper and lower magnetic plates, whereby ferromagnetic and ferrimagnetic fission products and radioactive corrosion products in the coolants are intensely adsorbed and not detached by the flow of the coolants. Accordingly, the fission products and the radioactive corrosion products can surely be removed with no requirement for the exchange of separation system during plant service life. (Horiuchi, T.)

  2. Analysis gives the penal treatment in Cuba to the tied infractions to the use and conservation gives radioactive substances

    International Nuclear Information System (INIS)

    Perez Gonzalez, F.; Perez Velazquez, R.S.; Fornet, R.O.; Reyes Fajardo, E.

    1998-01-01

    The work refers the realized analysis to the Law 62 the Cuban penal code that with establishing to the treatment of the infractions referred standard's to the uses and conservation the radioactive substances and other ionizing radiations sources

  3. Determination of detailed standards for transportation of radioactive materials by ships

    International Nuclear Information System (INIS)

    1979-01-01

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

  4. Labelled radioactive adenosinphosphates for the determination of toxic action

    International Nuclear Information System (INIS)

    Tahbaz, Z.

    1983-01-01

    Normal house-flies had been fed with carrier free radiophosphate (phosphorus). Many phosphorous containing substances in the tissue of the housefly are labelled with radiophosphorus by this procedure. Radiophosphorus is also found in the nucleotides of the housefly after applying radioactive phosphate. Suitable methods for processing and separation had been selected and worked out to isolate 32 P-adenosin-triphosphate 32 P-adenosin-diphosphate, 32 P-adenosin-monophosphate and 32 P-phosphate. Working at low temperature prevents chemical changes of the nucleotides. Extraction and thin layer chromatorgraphy turned out to be effective separation procedures for preparing samples for radioactivity measurement of the nucleotides. Autoradiographic techniques, scanning and liquid scitillation counting had been used for radioactivity measurements of the radioactive zones at the chromatograms. The results of these measurements provide information concerning the normal composition of adenosin-phosphates in the tissues of the housefly. If the animals are exposed to toxic chemicals, to insecticides, the composition of the phosphate containing compounds is changing. The concentration of adenosin-triphosphate is decreasing and the concentration of phosphate is increasing. This can be very easily shown by scanning the chromatograms of the extracts of the muscles of houseflies after feeding the animals with radioactive phosphate. Using this method, it is possible to show the toxic action of insecticides upon the metabolism of adenosin-phosphates. The decrease of the radioactivity at the zone of the adenosin-triphosphate and the increase of the radioactivity at the phosphate zone corresponds to the toxic action of foreign chemicals like insecticides. By using this tracer technique, it may be possible to investigate the toxic action of several toxic chemicals, if they are applied at the same time, thus investigating synergetic actions of environmental poisons. (Author)

  5. Radioactive substances in the Danish building materials

    International Nuclear Information System (INIS)

    Ulbak, K.

    1986-01-01

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

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

    International Nuclear Information System (INIS)

    2012-03-01

    coordinated research project (CRP) was proposed to determine the accuracy of existing computer codes and to identify how they could be improved through application of this body of work. Specifically, the CRP was expected to: - Build a database for selected pressurized water reactor (PWR) plants that would contain the design information suitable for their description within a computer code, as well as give the operating history of the plant, which would include the water chemistry data over several refuelling cycles; - Show the contamination of selected out-of-core surfaces such as circulating loops and steam generator channel heads versus operating history and compare the prediction of surface contamination versus time from modern radioactivity transport codes with actual plant data in a blind benchmarking exercise; - Determine how current codes, as well as new ones, could be improved and encourage the development of accurate new codes in Member States using the recommendations from the present work. This report uses as its basis the results of this CRP on 'Modelling of Transport of Radioactive Substances in the Primary Circuit of Water Cooled Reactors', which was conducted over the period 1996-2001 for PWR type reactors. The report also describes the significant progress demonstrated in this field in the period that followed.

  7. Possibilities for action in the case of radioactive pollution, problems and perspectives

    International Nuclear Information System (INIS)

    Mutaf, V.

    2009-01-01

    This article describes basic threats with the use of radioactive substances typical for Republic of Moldova. The main tasks of the network of observation and laboratory control in the case of radioactive pollution are listed. Prospects of development of radiological protection units in the country are determined.

  8. Proposed new regulations for the limitation of releases of radioactive substances from nuclear power stations with light water reactors

    International Nuclear Information System (INIS)

    1975-07-01

    In this publication the Swedish National Institute of Radiation Protection presents a proposed version of new regulations concerning the way in which the release of radioactive substances from nuclear power stations is to be limited. The regulations come into force on 1st January 1976. (Auth.)

  9. Method for electrolytic decontamination of radioactive contaminated metals

    International Nuclear Information System (INIS)

    Tanaka, Akio; Horita, Masami; Onuma, Tsutomu; Kato, Koji

    1991-01-01

    The invention relates to an electrolytic decontamination method for radioactive contaminated metals. The contaminated sections are eluted by electrolysis after the surface of a piece of equipment used with radioactive substances has been immersed in an electrolyte. Metal contaminated by radioactive substances acts as the anode

  10. Radioactive kryptonates in the analysis of environmental samples

    International Nuclear Information System (INIS)

    Tolgyessy, J.

    1986-01-01

    The term ''radioactive Kryptonates'' is used for substances into which atoms or ions of the radioactive nuclide 85 Kr are incorporated. The basis of the use of radioactive Kryptonates in analytical chemistry is that during a chemical reaction the crystalline lattice of the kryptonated carrier is destroyed, the carrier consumed, and the radioactive krypton released (radio-release method). Analysis can be made with a calibration curve or by comparison with a standard. Radio-release methods with the aid of radioactive Kryptonates as analytical reagents are very useful for the analysis of environmental samples, e.g. for the determination of air pollutants (ozone, sulphur dioxide, fluorine, hydrogen fluoride, mercury); and water pollutants (oxygen, dichromate, vanadium, hydrochloric acid, sulphur dioxide). (author)

  11. 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.

  12. Remediation of sites with mixed contamination of radioactive and other hazardous substances

    International Nuclear Information System (INIS)

    2006-01-01

    The IAEA attaches great importance to the dissemination of information that can assist Member States with the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support the management of the legacies of past practices and accidents. In response to this, the IAEA has initiated a comprehensive programme of work covering all aspects of environmental remediation. Mixed radioactive and hazardous substances contamination poses a particular challenge because of the combination of types of hazards and potential exposures. While radionuclides and toxic (heavy) metals pose similar and mostly compatible challenges, organic contaminants often require different approaches that may not be compatible with the former. Additional complexity is introduced into the problem by a different and sometimes conflicting regulatory framework for radiological and non-radiological contamination, including the prescribed waste management routes. In consideration of the added complexities of remediating (mixed) contamination, the IAEA has determined that this subject sufficiently warrants the development of a specialized report for assisting Member States. Topics discussed are types of sites, hazards and contaminant behaviour; regulatory implications; implications for worker health and safety; implications for sampling and analysis; elements of the remediation process; technology evaluation and selection; monitored non-intervention; blocking of pathways; removal of the source term; ex-situ treatment followed by case studies and a glossary

  13. Design of position monitor module in radioactive material transport monitoring system

    International Nuclear Information System (INIS)

    Adi Abimanyu; Dwi Yuliansari N

    2013-01-01

    Aspects of safety and security of radioactive substances from the sender to the receiver is to be secured so as not to harm humans. In general, monitoring is done through conversation by telephone to determine the location and rate of exposure of radioactive substances. Through the development of science and technology makes it possible to develop a system of monitoring the transport of radioactive substances in real time by combining radiation monitor module, position monitors module and sending information nir-cable. Position monitor module developed using GPS-receiver and a micro controller ATMega8 based serial interrupts communication. Testing is done by testing communication between micro controller and GPS and also testing reading position by GPS receiver. From the test results concluded that the developed modules is good in serial communication is based on serial interrupts, good position measurement to be used outdoors and is not good enough for measurements indoors because the GPS receiver used is not using an outdoor antenna. (author)

  14. Radioactive Substances Act, 1957, No 5

    International Nuclear Information System (INIS)

    1982-01-01

    This Act as amended regulates the possession, sale and use of radioactive materials and irradiating apparatus. It sets up a Radiological Advisory Council to advise the competent authorities on questions within the scope of the Act, also with a view to radiation protection. The Council's rules of procedure are laid down. The Act also provides that, subject to prescribed exemptions, no person may hold, use or sell radioactive materials without a licence. (NEA) [fr

  15. Immunological methods for gentamicin determination

    International Nuclear Information System (INIS)

    Krugers Dagneauz, P.G.L.C.; Olthuis, F.M.F.G.

    1979-01-01

    For immunoassay, an antibody against the substance to the determined, the pure substance itself, and a labelled form or derivative of the substance are required. The principles and problems of the preparation of antibodies are discussed, some methods for the preparation of derivatives labelled with radioactive tracers or enzymes are reviewed, and homologous enzyme-immunological determination of gentamicin is discussed in detail. A comparison is mae of three radio-immunological determination methods, and the most suitable radio-immunological method is compared with two microbiological techniques. The results are found to be comparable. (Auth.)

  16. Determination of beta and gamma radioactivity on the coal

    International Nuclear Information System (INIS)

    Suhardi; Mulyono; Sutanto WW; Rosidi

    2013-01-01

    Radioactivity in coal, botton ash and fly ash. This determination was carried out to know each the radioactivity of β gross, γ gross on the coal, botton ash and fly ash, which accommodation of environment data the present in PLTU Paiton Probolinggo. Samples taken preparation and analysis based on the procedures of environmental radioactivity analysis. The radioactivity on the PLTU Paiton Probolinggo detected by beta gross Spectrometer with Geiger Muller (GM) and gamma Spectrometer with Ge(Li) detector. The result indicates that radioactivity concentration of beta and gamma gross are (95,57-308,26) Bq/kg and (1,374 - 31,677) Bq/kg respectively. (author)

  17. Approval of radioactive consumer goods

    International Nuclear Information System (INIS)

    Paynter, R.A.

    1992-01-01

    The 1980 Euratom Directive obliges the UK to draw up a system of prior authorization for the use of radioactive substances in a range of consumer products, and the Government intends to make regulations to fulfil the requirements of the Directive. These regulations will empower NRPB to approve such products prior to their supply to the public. In this brief article, the NRPB reviews the criteria against which to consider any proposed use of radioactive substances, considers radiological production standards for products and discusses the questions of the labelling of radioactive consumer goods. (UK)

  18. Advance in radioactive decontamination

    International Nuclear Information System (INIS)

    Basteris M, J. A.; Farrera V, R.

    2010-09-01

    The objective of the present work was to determine if the application of the Na hypochlorite has some utility in the radioactive decontamination, in comparison with the water, detergent and alcohol. Several methods were compared for decontaminate the iodine 131 and technetium 99, the work table and the skin it was carried out an initial count with the Geiger Muller. Later on, in a single occasion, the areas were washed with abundant water, alcohol, clothes detergent and sodium hypochlorite (used commercially as domestic bleacher) without diluting. Observing that the percentage in the decrease of the counted radioactivity by the Geiger Muller, decreased in the following way: It was demonstrated that the Na hypochlorite presents the highest index of radioactive decontamination with 100% of effectiveness. The Na hypochlorite is an excellent substance that can be used with effectiveness and efficiency like decontamination element in the accident cases of radioactive contamination in the clinical laboratories of nuclear medicine. (Author)

  19. Age-dependent dose factors and dose limits of annual radioactivity uptake with unsealed radioactive substances by occupationally exposed persons

    International Nuclear Information System (INIS)

    Kaul, A.; Nosske, D; Elsasser, U; Roedler, H.D.; Henrichs, K.

    1986-01-01

    The dose factors have been calculated on the basis of the ICRP models for dosimetric and metabolistic assessment, and are laid open in accordance with Annex XI ( to sec. 45 sub-section (2)) of the amended version of the Radiation Protection Ordinance. The contribution in hand explains the scientific fundamentals and results of the calculations of dose factors relating to inhalation and ingestion of unsealed radioactive substances by adult reference man, and age-dependent factors calculated for children and adolescents. Further, annual limits of uptake by occupationally exposed persons, as calculated on the basis of primary dose limits pursunant to the draft amendment presented by the Federal Interior Minister, are compared with relevant data given by the ICRP and EC institutions. (orig./DG) [de

  20. Management of sites potentially polluted by radioactive substances - Methodological guidebook

    International Nuclear Information System (INIS)

    2011-12-01

    This document is the update of the 'methodological guidelines for the management of industrial areas potentially contaminated by radioactive substances', published in 2001 by IRSN. Revisions intended to bring coherence between management of areas polluted by radioactive substances and the general policy applied to polluted sites described in a document published in February 2007 by the French Ministry in charge of Environment. Requirements introduced both by the law relative to waste management of June 28, 2006 and the ministerial order of 17 November 2008 were introduced. The involvement of all stakeholders during the process was stressed. The updating, mainly lead to introduce a clear distinction between polluted areas where uses are established and those without use or at redevelopment stage. When the uses are established, an 'Interpretation of the condition of environment' is conducted. Alternatively, the remediation process follows a 'management plan'. The revision also led to the disappearance of the 'doubt removal' phase which has been incorporated as an entire part in the site characterisation. Among other significant changes, it may be noted the evolution of the 'risk assessment' tools from simplified risk assessment and detailed risk assessment to a single tool allowing the quantitative assessment of exposure (EQER). Finally, the guidelines highlight stakeholder involvement in identifying the different participants and in reminding the benefits of a consultative approach. Whatever the remediation process: interpretation of the condition of environment or management plan; site characterisation is required as soon as a pollution is suspected. It includes literature reviews and field investigations primarily to confirm or deny the presence of pollution and, where appropriate, to determine its location, nature and level. The effort accorded to site characterisation must be proportionate to identified issues. The first step consists in comparing the

  1. Application of radioactive substances in research in nuclear medicine: current trends and radiation exposure to the study subjects

    International Nuclear Information System (INIS)

    Minkov, V.; Schwarz, E.R.; Bauer, B.; Nosske, D.; Erzberger, A.; Brix, G.

    2001-01-01

    Aim: Analysis of the application of radioactive substances in research in the field of nuclear medicine in human beings and of the resulting radiation exposure to study subjects. Methods: Assessment of applications for approval submitted in accordance with Paragraph 41 of the Radiation Protection Ordinance, evaluated by the Federal office for Radiation Protection together with the Federal Institute for Pharmaceuticals and Medical Products, within the period from 1997 to 1999. Results: The focus of the studies on the diagnostic application of radioactive substances in medicine evaluated has, since 1998, shifted from oncological to neurological and psychological aspects, while, at the same time, the number of PET studies increased constantly The proportion of healthy study subjects included in the diagnostic studies increased from 7 to 22%. The number of therapeutic applications of radioactive substances has, since 1997, undergone a three-fold increase, and in the process of this, the focus of attention lay within the area of radioimmuno-therapy and endovascular brachytherapy. The effective dose was, among up to 49% of the investigated healthy study subjects higher than 5 mSv, and among up to 6% of these subjects was at levels of over 20 mSv. Up to 22% of the patients received, within the scope of diagnostic studies, an effective dose of between 20 and 50 mSv. An exceeding of the 50 mSv limit occurred among up to 3% of the patients. Conclusions: In spite of the increasing numbers of PET applications, conventional nuclear medicine has maintained its importance in the field of medical research. Further developments in the areas of radiochemistry and molecular biology led to an increase in the importance of radio-immuno therapy. The evaluation of new radiopharmaceuticals and the extension of basic biomedical research, resulted in an increase in the proportion of healthy study subjects included in the studies. The radiation exposure among subjects resulting directly from

  2. A radioactive tracer dilution method to determine the mass of molten salt

    International Nuclear Information System (INIS)

    Lei Cao; Jarrell, Josh; Hardtmayer, D.E.; White, Susan; Herminghuysen, Kevin; Kauffman, Andrew; Sanders, Jeff; Li, Shelly

    2017-01-01

    A new technique for molten salt mass determination, termed radioactive tracer dilution, that uses 22 Na as a tracer was validated at bench scale. It has been a challenging problem to determine the mass of molten salt in irregularly shaped containers, where a highly radioactive, high-temperature molten salt was used to process nuclear spent/used fuel during electrochemical recycling (pyro-processing) or for coolant/fuel salt from molten salt reactors. A radioactive source with known activity is dissolved into the salt. After a complete mixture, a small amount of the salt is sampled and measured in terms of its mass and radioactivity. By finding the ratio of the mass to radioactivity, the unknown salt mass in the original container can be precisely determined. (author)

  3. Radioactive substances in foodstuffs and drinking water in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Vaaramaa, K.; Vesterbacka, P.; Solatie, D. [STUK - Radiation and Nuclear Safety Authority (Finland)

    2014-07-01

    The concentrations of radioactive substances in the environment and foodstuffs are continuously monitored in Finland. Radiation and Nuclear Safety Authority (STUK) publishes the annual report of Surveillance of Environmental Radiation which shows the activity levels of artificial radionuclides in Finland. Based on the results the radiation dose to Finnish people is estimated. Natural radioactive elements will be included in the surveillance program in future years. The aim of the foodstuffs monitoring program is to obtain information from the intake of radionuclides through ingestion. The radioactivity in foodstuffs is monitored by collecting foodstuffs on market, drinking water and daily meals offered at hospitals over one week. The sampling sites are located in southern, central and northern Finland, representing the main population centres and areal differences in the consumption of foodstuffs. One of these sampling sites is located in the highest {sup 137}Cs deposition area in Finland originating from the Chernobyl accident. The foodstuff samples on market are, for example, wild game, wild berries, wild mushrooms and fish. {sup 137}Cs and {sup 90}Sr are analysed from mixed diet samples and {sup 137}Cs from foodstuffs samples on market. The concentrations of {sup 137}Cs and {sup 90}Sr in daily meals are low because the agricultural products used as raw material are almost free of artificial radionuclides. The small variation in the results is caused by the differences in the types of meals that were prepared on the sampling dates and in the areal origins of raw materials. {sup 137}Cs concentration is remarkably higher in such food which contains a lot of natural products like wild berries, freshwater fish, wild mushrooms and game. As an example, the concentrations of {sup 137}Cs in the solid food in 2012 ranged from 0.06 - 1.0 Bq/kg, and in the drinks from 0.27 - 0.40 Bq/l, respectively. The radiation dose to Finnish people is estimated based on an analysis of

  4. A comparative study of changes in immunological reactivity during prolonged introduction of radioactive and chemical substances into the organism with drinking water

    International Nuclear Information System (INIS)

    Shubik, V.M.; Nevstrueva, M.A.; Kalnitskij, S.A.; Livshits, R.E.; Merkushev, G.N.; Pilshchik, E.M.; Ponomareva, T.V.

    1978-01-01

    A comparative study was conducted into the factors of non-specific protection and specific immunity, allergic and autoallergic reactivities during prolonged exposure of experimental animals to 6 different radioactive and 7 harmful chemical substances. Qualitative and quantitative peculiarities were found in the changes in immunological reactivity during the exposure of the organism to radionuclides and stable chemical compounds. Impairment of immunity plays an essential role in the course and the outcome of effects induced by chronic action of the substances examined. (author)

  5. 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.)

  6. Disposal of radioactive wastes. Chapter 11

    International Nuclear Information System (INIS)

    Skitt, J.

    1979-01-01

    An account is given of the history and present position of legislation in the United Kingdom on the disposal of radioactive wastes. The sections are headed: introduction and definitions; history; the Radioactive Substances Act 1960; disposal of solid radioactive wastes through Local Authority services; function of Local Authorities; exemptions; national radioactive waste disposal service; incidents involving radioactivity. (U.K.)

  7. Commentary on guidelines for radiation measurement and treatment of substances including naturally occurring radioactive materials

    International Nuclear Information System (INIS)

    Sakurai, Naoyuki; Ishiguro, Hideharu

    2007-01-01

    Study group on safety regulation on research reactors in Ministry of Education, Culture, Sports, Science and Technology (MEXT) reported the guidelines of 'Guidelines on radiation measurement and treatment of naturally occurring radioactive materials (NORM)' on 6 February 2006. RANDEC made the website contents 'Study on use and safety of the substances including uranium or thorium', based on the contract with MEXT to make theirs contents. This paper describes the outline of the website in MEXT homepage, background and contents of NORM guidelines in order to understand easily and visually the NORM guidelines, adding in some flowcharts and figures. (author)

  8. Financial consequences of illicit movements of metallic substances contaminated by radioactivity

    International Nuclear Information System (INIS)

    Montmayeul, J.-P.

    1999-01-01

    It is increasingly frequent for States to have to deal with illicit movements of metallic substances contaminated by radioactivity. Steps taken in the areas of safety and health protection necessarily have financial implications . Except in cases of special urgency, a financial evaluation is vital before such decisions are taken. Specific actions must be initiated. Aside from action by the industries directly involved in self-regulation procedures, checks must be imposed in cases of fraudulent trafficking which has no connection with fair commercial activity. Customs administrations may take specific steps to restore order to legitimate markets. International organizations have a special role to play in disseminating information and promoting international cooperation. The paper outlines the financial impact of fraudulent trafficking, and methods of ensuring that those responsible for such activities bear the financial costs incurred. It underlines the roles that can be played by those involved in the traffic in contaminated products. (author)

  9. Radioactive waste: show time? - 16309

    International Nuclear Information System (INIS)

    Codee, Hans; Verhoef, Ewoud

    2009-01-01

    Time will render radioactive waste harmless. How can we manage the time radioactive substances remain harmful? Just 'wait and see' or 'marking time' is not an option. We need to isolate the waste from our living environment and control it as long as necessary. For the situation in the Netherlands, it is obvious that a period of long term storage is needed. Both the small volume of waste and the limited financial possibilities are determining factors. Time is needed to let the volume of waste grow and to let the money, needed for disposal, grow in a capital growth fund. An organisation such as COVRA - the radioactive waste organisation in the Netherlands - can only function when it has good, open and transparent relationship with the public and particularly with the local population. If we tell people that we safely store radioactive waste for 100 years, they often ask: 'That long?' How can we explain the long-term aspect of radioactive waste management in a way people can relate to? In this paper, an overview is given of the activities of COVRA on the communication of radioactive waste management. (authors)

  10. Safety of transport of radioactive substances for civil use on the French territory. Lessons learned by the IRSN from the analysis of significant events reported in 2012 and 2013

    International Nuclear Information System (INIS)

    2014-01-01

    The first part of this report proposes an overview of significant aspects and events related to the transport of radioactive substances in France, and a comment on lessons learned by the IRSN. The second and main part first presents some aspects of this specific transport: regulatory framework, main safety issues, nature and flow of these transports, transports of radioactive substances per sector. The second part proposes an analysis of significant events: elements related to the reporting of an event, assessment of events and analysis of main trends noticed in 2012 and 2013 with respect to previous years, analysis of the main types of events which occurred in 2013 and 2013 with respect with those which occurred during the previous years. The next chapter describes significant events: damage of a parcel during its handling, a non conformal content, loss of a parcel on a public road, derailment of a car in Le Bourget. Some transverse topics are finally addressed: return on experience of crisis management in relationship with events in radioactive substance transport, IRSN study on the behaviour of packaging during long duration fires

  11. Radioactive Substances Act 1993. Explanatory document and draft authorisation prepared by the Environment Agency to Assist public consultation on application by Devonport Royal Dockyard Limited to dispose of radioactive wastes from Devonport Royal Dockyard Plymouth Devon

    International Nuclear Information System (INIS)

    2000-01-01

    The Environment Agency (the Agency) is the independent public body responsible for regulating the use of radioactive substances and accumulation and disposal of radioactive wastes in order to ensure protection of people and the environment. Anyone who is proposing activities involving the use of radioactive substances or disposal of radioactive waste must apply for permission from the Agency. In 1993, the Government decided to locate all nuclear submarine refit work at Devonport. This will lead to increased amounts of radioactive waste arisings at Devonport and a decreased amount of waste arisings at Rosyth, where refit work was also previously carried out. In May 2000 Devonport Royal Dockyard Limited (DML) applied to the Agency for a variation to its authorisations under the Radioactive Substances Act 1993 to dispose of gaseous, liquid, and solid radioactive wastes from its site at Devonport in Plymouth. Once the application was received, the Agency made the information publicly available and held a well attended public meeting in Plymouth to highlight the issues. Since then the Agency has required DML to provide additional information in support of its application. Six rounds of questions were asked and responded to, and these responses have also been made publicly available. The application and responses from the company have been made publicly available. The Agency is now consulting widely on this information to assist its decision making. This Explanatory Document and the accompanying draft authorisation has been prepared by the Agency to assist the consultation process. They are intended to help members of the public and other consultees to understand the application and the Agency's considerations so far. The consultation is being carried out to enable the public and other consultees to draw the Agency's attention to any matters they would wish it to consider when reaching its decisions on this application. The Agency has not made any decisions on the DML

  12. Safety in the management of radioactive substances

    International Nuclear Information System (INIS)

    Balter, Henia; Rey, Ana; Leon, Alba; Jelen, Miguel

    1994-01-01

    A brief explanation of radiation protection,external irradiation,internal contamination,risk factors, active laboratory design,localization,ventilation,working surfaces,area distribution,classification of active laboratory.Radiopharmacy laboratory,shielding, area monitoring,personal dosimetry,rules for management of open sources,maximum admitted limits for radionuclides currently used in radiopharmacy.Decontamination of active areas and materials,surfaces,equipment s.Decontamination of hands.Waste disposal.Radioactive materials transportation.Reception of radioactive materials.Bibliography

  13. Radioactive wastes and discharges

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The guide sets out the radiation safety requirements and limits for the treatment of radioactive waste. They shall be observed when discharging radioactive substances into the atmosphere or sewer system, or when delivering solid, low-activity waste to a landfill site without a separate waste treatment plan. The guide does not apply to the radioactive waste resulting from the utilisation of nuclear energy or natural resources.

  14. Radioactive wastes and discharges

    International Nuclear Information System (INIS)

    2000-01-01

    The guide sets out the radiation safety requirements and limits for the treatment of radioactive waste. They shall be observed when discharging radioactive substances into the atmosphere or sewer system, or when delivering solid, low-activity waste to a landfill site without a separate waste treatment plan. The guide does not apply to the radioactive waste resulting from the utilisation of nuclear energy or natural resources

  15. Control of trafficking of radioactive sources/substances on European Community eastern border

    International Nuclear Information System (INIS)

    Lovjagina, Irina; Graveris, Visvaldis

    2008-01-01

    . Conclusions: Applied qualitative containment and surveillance procedures on transported goods in general strengthen system for control of radioactive sources and substances within European Community Member States, and shall have systematically approach. Hence we may conclude that the total amount of orphaned sources decreases accordingly. (author)

  16. New method for the radioactive determination of vitamin B12

    International Nuclear Information System (INIS)

    Lewin, Nathan; Fries, J.E.; Richards, C.S.

    1975-01-01

    A description is given of a method for the radioactive determination of vitamin B12 in a sample solution of serum in which a radioactive tracer of vitamin B12 and the vitamin B12 of the serum compete with respect to an intrinsic factor of limited linking capacity. The free radioactive vitamin B12 and the free vitamin B12 of the serum are separated from the intrinsic factor and from the radioactive vitamin B12 and from the serum vitamin B12 linked to this factor, before the radioactivity is measured against standard values. The method consists in separating the free radioactive vitamin B12 and the free serum vitamin B12 of the intrinsic factor and portions of radioactive and serum vitamin B12 linked to this factor, by adding an adequate quantity of bentonite to adsorb the free radioactive vitamin B12 and free serum vitamin B12 so that the intrinsic factor surface floating solution in association with the linked radioactive vitamin B12 and the linked serum vitamin B12 may be physically isolated from the solid bentonite that has adsorbed the free radioactive vitamin B12 and the free serum vitamin B12 [fr

  17. Determination of Substances Content of Soil Surface Using Fast Neutron Activation Analysis

    International Nuclear Information System (INIS)

    Elin Nuraini; Elisabeth; Sunardi

    2002-01-01

    Determination of substances content of soil surface using neutron activation analysis has been performed. The aim of this research is to determine whether there are any dangerous, hazardous and toxic substances that released from The Research and Development Center for Advanced Technology (RDCAT) as a government institution has possibility in releasing that substances to the environment by surface water, sewage or rain water that give any dangerous the environmental. The fast neutron activation analysis was used to analyze the type and concentration of substances qualitative and quantitatively. The quantitative analysis was performed using relative method. Samples were counted using NaI(TI) detector. The result showed that there are several substances such as Mn-55, Fe-56, P-31, Al-27. Zn,65 and Mg-24. And there are found any hazardous, dangerous and toxic substances in the samples that causing any danger to human and environment. (author)

  18. Radioactivity in coal, ashes and selected wastewaters from Canadian coal-fired steam electric generating stations

    International Nuclear Information System (INIS)

    1985-09-01

    Coal is known to contain naturally occurring radioactive elements and there has been speculation that as a results, coal-fuelled power generation stations may be significant emitters of these substances. In this report, the subject of radioactivity is introduced. The kinds of radioactive substances which occur naturally in coal formations, the nature of their emissions and the existing information on their behaviour and their effects on environmental organisms are also reviewed. The results of an examination of levels of alpha, beta and gamma radiaton levels, and the substances which produce them in coals, fly ashes, bottom ashes and related wastewaters at six Canadian coal-fuelled power stations are presented. Difficulties in studies of this nature and the potential effects of these releases on organisms in the adjacent aquatic environment are discussed. Existing and potential technologies for the removal of these substances from wastewaters are examined. In general the releases in wastewaters from the six stations were found to be lower than those known to cause short-term or acute biological effects. The potential for long-term effects from such low-level releases could not be accurately assessed because of the paucity of information. A number of recommendations for: improvements in further studies of this nature; the further examination of the fate of naturally occurring radionuclides in the environment; and the determination of the long-term effects of low levels of naturally occurring radioactive substances on aquatic organisms, are made

  19. Licence template for mobile handling and storage of radioactive substances for the nondestructive testing of materials; Mustergenehmigung zur ortsveraenderlichen Verwendung und Lagerung radioaktiver Stoffe im Rahmen der zerstoerungsfreien Materialpruefung

    Energy Technology Data Exchange (ETDEWEB)

    Lange, A. [Niedersaechsisches Ministerium fuer Umwelt, Energie und Klimaschutz (Germany); Schumann, J. [Landesamt fuer Arbeitsschutz, Gesundheitsschutz und technische Sicherheit, Berlin (Germany); Huhn, W.

    2016-07-01

    The Technical Committee ''Radiation Protection'' (Fachausschuss ''Strahlenschutz'') and the Laender Committee ''X-ray ordinance'' (Laenderausschuss ''Roentgenverordnung'') have appointed a working group for the formulation of licence templates for the nationwide use of X-ray equipment or handling of radioactive substances. To date, the following licence templates have been adopted: - Mobile operation of X-ray equipment under technical radiography to the coarse structural analysis in material testing; - Mobile operation of a handheld X-ray fluorescence system; - Mobile operation of a flash X-ray system; - Operation of an X-ray system for teleradiology The licence template ''Mobile handling and storage of radioactive substances for the nondestructive testing of materials'' is scheduled for publication. The licence template ''Practices in external facilities and installations'' is currently being revised. The licence template ''Mobile handling and storage of radioactive substances for the nondestructive testing of materials'' is used as an example to demonstrate the legal framework and the results of the working group.

  20. Method for determining immunochemical substances

    International Nuclear Information System (INIS)

    O'connor, J.

    1980-01-01

    Drawing a method for detecting and measuring a predetermined specifically-bindable immunochemical substance in a liquid sample in a cuvette, comprising the steps of: (A) providing, in an immunoassay technique for the liquid sample in said cuvette, a component comprising a suspension of particles which may be agglutinated or insolubilized in relationship to the presence and concentration of the immunochemical substance in the sample; and (B) determining the presence and concentration of the immunochemical substance by measuring the electromagnetic radiation transmission properties of the sample using a calibrated radiation-measuring apparatus, said apparatus comprising: (1) a suitable electromagnetic radiation source capable of providing radiation at wavelengths equal to or less than the mean diameter of said particles; (2) means for concentrating and collimating radiation from the electromagnetic radiation source to form a beam; (3) means for filtering the beam to (I) eliminate radiation having wavelengths greater than the means diameter of the particles and (II) transmit radiation, which radiation has a range, whereby the upper wavelength is equal to or below the mean diameter of the particles, and the range is of at least about 100nm; (4) means for (I) positioning a sample-containing cuvette and for (II) allowing the filtered beam incident on the cuvette to be transmitted through the cuvette and sample, and for (III) receiving a portion of the filtered beam transmitted through the sample at two or more predetermined angles with respect to the beam; and (5) means for detecting and measuring the portion of the beam transmitted at a predetermined angle

  1. Limitation of releases of radioactive effluents for nuclear power plants in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Tolksdorf, P.; Buehling, A.

    1981-01-01

    Empirical values relating to the effluents of nuclear power plants in the Federal Republic of Germany are now available. These values cover a period of several years of operation. The measured emissions of radioactive substances are often very much below the maximum permissible values, based on the dose limits for the environment stipulated in the legal regulations. Extensive technical and administrative measures contribute to the reduction of radioactive effluents. Furthermore, additional possibilities for improvement are mentioned which may lead to a further reduction of radioactive effluents. These are derived from investigations into the release of radioactive substances in nuclear power plants. The licensing procedure in the Federal Republic of Germany in fixing discharge limits is outlined. Proposals are made concerning licence values which may be determined for the radioactive effluents in modern standardized nuclear power plants with light-water reactors. The resulting radiation exposures are quoted for a typical nuclear power plant site. (author)

  2. Method of solidifying radioactive wastes

    International Nuclear Information System (INIS)

    Tomita, Toshihide; Minami, Yuji; Matsuura, Hiroyuki

    1984-01-01

    Purpose: To enable complete curing even when radioactive wastes contain those materials hindering the curing reaction, for example, copper hydroxide. Method: After admixing an alkaline substance to radioactive concentrated liquid wastes containing copper hydroxide or other amphoteric substances, they are dried, powderized and then cured with thermosetting resins. The thermosetting resins usable herein include, for example, those prepared by mixing an unsaturated polyester with a monomer such as styrene. When a polymerization initiator such as methyl ethyl ketone peroxide and a polymerization promotor are added to the mixture, it takes places curing reaction at normal temperature. Suitable alkaline substances usable herein are those which are insoluble to the liquid wastes and do not change the chemical form under heating and drying. (Yoshihara, H.)

  3. 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.)

  4. ELECTRONIC ANALOG COMPUTER FOR DETERMINING RADIOACTIVE DISINTEGRATION

    Science.gov (United States)

    Robinson, H.P.

    1959-07-14

    A computer is presented for determining growth and decay curves for elements in a radioactive disintegration series wherein one unstable element decays to form a second unstable element or isotope, which in turn forms a third element, etc. The growth and decay curves of radioactive elements are simulated by the charge and discharge curves of a resistance-capacitance network. Several such networks having readily adjustable values are connected in series with an amplifier between each successive pair. The time constant of each of the various networks is set proportional to the half-life of a corresponding element in the series represented and the charge and discharge curves of each of the networks simulates the element growth and decay curve.

  5. Determination of Anti-nutrients and Toxic Substances of Selected ...

    African Journals Online (AJOL)

    USER

    ABSTRACT: Determination of antinutrients and toxic substances in leafy vegetables is an imperative facet in nutritional studies as it establishes the baseline concentrations index for phytotoxins in the vegetables. Concentrations of cyanide, nitrate, soluble and total oxalates were quantitatively determined in the common ...

  6. On-line radioactivity detector for HPLC

    International Nuclear Information System (INIS)

    Kessler, M.J.

    1986-01-01

    Over the last ten years the technique of high performance liquid chromotography (HPLC) has become extensively employed for the separation and quantitation of various biological, organic, and inorganic substances. The use of HPLC for the separation of various metabolic compounds has become routine. The major problem of analyzing the metabolism process is that the quantitation is accomplished by the use of radioactive substrates. Until recently the only method to quantitate these radioactive compounds eluting from the HPLC was by collecting fractions at preset times, removing aliquots and quantitating in a liquid scintillation counter. Once the radioactivity present in each fraction was determined, the results were plotted on a graph and the area of each of the radioactive peaks was determined. This entire process required from 3-20 hours. The introduction of the flow through radioactivity detector enable the investigator to directly quantitate the radioactive peaks as they elute from the HPLC in real time and at about one-tenth the original cost of the previous methods. The detection limits of this technique are dependent on the residence time of the sample in the flow cell and the type of flow cell used for the analysis. Using a 2.5 ml liquid flow cell, (mixing with liquid scintillation solution), base line resolution can be obtained for peaks 1.5 minutes apart, and a sensitivity of 70 dpm for tritium and 30 dpm for carbon-14 can be achieved

  7. Geological storage of radioactive waste

    International Nuclear Information System (INIS)

    Barthoux, A.

    1983-01-01

    Certain radioactive waste contains substances which present, although they disappear naturally in a progressive manner, a potential risk which can last for very long periods, of over thousands of years. To ensure a safe long-term handling, provision has been made to bury it deep in stable geological structures which will secure its confinement. Radioactive waste is treated and conditioned to make it insoluble and is then encased in matrices which are to immobilize them. The most radioactive waste is thus incorporated in a matrix of glass which will ensure the insulation of the radioactive substances during the first thousands of years. Beyond that time, the safety will be ensured by the properties of the storage site which must be selected from now on. Various hydrogeological configurations have been identified. They must undergo detailed investigations, including even the creation of an underground laboratory. This document also presents examples of underground storage installations which are due to be built [fr

  8. 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)

  9. Contamination and decontamination of vehicles driven in radioactive areas

    International Nuclear Information System (INIS)

    Ulvsand, T.; Nygren, U.

    1999-03-01

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

  10. Transport of proximity nuclear radioactive materials

    International Nuclear Information System (INIS)

    2010-01-01

    This brief publication gives an overview of the international and national regulatory framework for the transport of radioactive substances, outlines progress orientations identified by the French Nuclear Safety Authority (ASN), indicates the parcel classification and shipment radiological criteria, and how to declare events occurring during the transport of radioactive substances, which number to phone in case of a radiological incident. Finally, the role of the ASN and its field of activity in matters of control are briefly presented with a table of its office addresses in France

  11. Determination of pharmacokinetic processes in body organs on the basis of the box model and, by analogy, of laws of radioactive disintegration of naturally occurring and artificially activated isotope families

    International Nuclear Information System (INIS)

    Rauser, P.

    1992-01-01

    The research work described is based on the simple law of degradation and disintegration for pharmaceutical substances. The transport, storage and, possibly, accumulation of beneficial and harmful pharmaceuticals in the organs of the human body are analysed using the box model. The studies are not restricted to asymptotic conditions occurring after continuous treatment with a particular drug but also investigate into the so-called stabilisation phase immediately after the beginning of medication, which is described mathematically. This phase is shown to be subject to a set of rules that are much more complex than those responsible for asymptotic substance levels. The analytical procedures used here are described on the basis of typical cases drawn from medical practice. The laws derived from these observations can, by analogy, also be applied to the radioactive disintegration of isotope families. They also permit formulas to be determined for the activity of multiple-link chain members. The report proceeds by discussing cases, where the baseline substance is the result of nuclear chain reacting. The last issue to be treated within the scope of this study is the radioactive disintegration and simultaneous activation of isotope families. (orig./MG) [de

  12. Radioactivity and environment

    Energy Technology Data Exchange (ETDEWEB)

    Trivedi, R N [Fertilizer Association of India, New Delhi

    1977-12-01

    Power generation from radioisotopes is one of the major applications of nuclear energy for peaceful purposes and is in practice in over twenty countries including India. Other well-known applications of radioactive substances are in medicine, industry, scientific and industrial research programs, and nuclear weapons. The only serious disadvantage with the radioisotopes and their waste products is the constant release of radiation energy which contaminates the environment and endangers the life. An attempt has been made to identify the major sources of radioactivity in the environment and assess its potential impact on the environment. Recent developments in safety measures for prevention of contamination and control of radioactivity and in radioactive wastes management are also discussed.

  13. Transporting radioactive rock

    International Nuclear Information System (INIS)

    Pearce, G.

    1990-01-01

    The case is made for exempting geological specimens from the IAEA Regulations for Safer Transport of Radioactive Materials. It is pointed out that many mineral collectors in Devon and Cornwall may be unwittingly infringing these regulations by taking naturally radioactive rocks and specimens containing uranium ores. Even if these collectors are aware that these rocks are radioactive, and many are not, few have the necessary equipment to monitor the activity levels. If the transport regulations were to be enforced alarm could be generated and the regulations devalued in case of an accident. The danger from a spill of rock specimens is negligible compared with an accident involving industrial or medical radioactive substances yet would require similar special treatment. (UK)

  14. Coal combustion ashes: A radioactive Waste?

    International Nuclear Information System (INIS)

    Michetti, F.P.; Tocci, M.

    1992-01-01

    The radioactive substances naturally hold in fossil fuels, such as Uranium and Thorium, after the combustion, are subjected to an increase of concentration in the residual combustion products as flying ashes or as firebox ashes. A significant percentage of the waste should be classified as radioactive waste, while the political strategies seems to be setted to declassify it as non-radioactive waste. (Author)

  15. Radioactivity survey data in Japan, part 1

    International Nuclear Information System (INIS)

    1988-04-01

    The report presents data on radioactive substances in environmental materials. Samples collected are rain and dry fallout (monthly for domestic program and monthly for WHO program), airborne dust (quarterly), service water and freshwater (semiyearly for source water, semiyearly for tap water, yearly in fishing season for freshwater), soil (yearly at 1.0 - 5 cm and 5 - 20 cm), sea water (yearly) and sea sediments (yearly). The samples collected are treated appropriately to provide solutions for analysis. Their analysis is carried out as follows. Each sample solution prepared is first neutralized with sodium hydroxide. After sodium carbonate is added, the precipitate of strontium and calcium carbonates is separated and the supernatant solution is used for cesium-137 determination. The carbonates are converted into oxalates, which are then dissolved in nitric acid. Strontium is separated by successive fuming nitric acid separation. The supernatant is acidified and cesium is absorbed on ammonium molybdophosphate added. Stable strontium, calcium and potassium are also determined. After the radiochemical separation, counting of radioactivity is performed using low background beta counters normally for 60 to 90 min. From the results, the concentrations of the nuclides in the original samples are calculated. The contents of the substances in the samples are tabulated. (Nogami, K.)

  16. Laser fluorescence determination of radioactive waste cotton fabric in the exploration of uranium content

    International Nuclear Information System (INIS)

    Wang Jiangong

    2010-01-01

    In order to meet the dosage test the operational needs of the laser fluorescence determination of trace radioactive waste cotton fabric uranium research and exploration, to determine the sample ashing time, measured dosage of acidity and digestion and other technical parameters, gives the laser fluorescence determination of radioactive abandoned cotton fabric of trace uranium method. Method of high sensitivity, strong anti-interference, the detection limit of 0.025μg/g(Burning down dregs), relative standard deviation was 3.96%, the mean recovery 93.3%-103% for masks, gloves and other radioactive waste to the determination of trace uranium. (authors)

  17. Solid and liquid radioactive wastes

    International Nuclear Information System (INIS)

    Cluchet, J.; Desroches, J.

    1977-01-01

    The problems raised by the solid and liquid radioactive wastes from the CEA nuclear centres are briefly exposed. The processing methods developed at the Saclay centre are described together with the methods for the wastes from nuclear power plants and reprocessing plants. The different storage techniques used at the La Hague centre are presented. The production of radioactive wastes by laboratories, hospitals and private industry is studied for the sealed sources and the various radioactive substances used in these plants. The cost of the radioactive wastes is analysed: processing, transport, long term storage [fr

  18. Summary of the Law relating to Atomic Energy and Radioactive Subtances as at March 1979

    International Nuclear Information System (INIS)

    Sim, D.F.; Ritchie, K.J.S.

    1979-01-01

    This Note contains summaries of new laws and regulations on atomic energy and radioactive substances and amendments made to previous ones in the United Kingdom as at March 1979, including international regulations and agreements. New materials referred to includes the Nuclear Installations (Excepted Matter) Regulations 1978, the Medicines (Radioactive Substances) Order 1978, the Medicines (Committee on Radiation from Radioactive Medicinal Products) Order 1978 and the Medicines (Administration of Radioactive Substances) Regulations 1978. The Note also reproduces other amendments in nuclear legislation, already referred to in a previous Note dated March 1978. (NEA) [fr

  19. Contamination and decontamination of vehicles when driven in radioactive areas

    International Nuclear Information System (INIS)

    Ulvsand, T.; Nygren, U.

    1999-10-01

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

  20. Small WEEE: determining recyclables and hazardous substances in plastics.

    Science.gov (United States)

    Dimitrakakis, Emmanouil; Janz, Alexander; Bilitewski, Bernd; Gidarakos, Evangelos

    2009-01-30

    An examination regarding the determination of recyclables and hazardous substances in small waste electrical and electronic equipment (WEEE) found in the residual household waste stream of the city of Dresden, Germany, is described. Firstly, attitudes towards the disposal of small WEEE in the latter are assessed, and product types and categories which mostly contribute to its composition are identified. Physical parameters which could be used as mechanical sorting criteria are measured, and the material composition of the small WEEE found is determined. The hazardous substances' "base" charge in the residual waste is established by means of atomic absorption spectrometry and ionic chromatography, as a first step in estimating the contribution of small WEEE to its pollutant load. Consequently, the content of small WEEE plastics in key heavy metals and halogens is determined. Key conclusions are drawn concerning the future strategic development and practical implementation of the 2002/96/EC Directive, in relation to small WEEE management and recycling.

  1. Small WEEE: Determining recyclables and hazardous substances in plastics

    International Nuclear Information System (INIS)

    Dimitrakakis, Emmanouil; Janz, Alexander; Bilitewski, Bernd; Gidarakos, Evangelos

    2009-01-01

    An examination regarding the determination of recyclables and hazardous substances in small waste electrical and electronic equipment (WEEE) found in the residual household waste stream of the city of Dresden, Germany, is described. Firstly, attitudes towards the disposal of small WEEE in the latter are assessed, and product types and categories which mostly contribute to its composition are identified. Physical parameters which could be used as mechanical sorting criteria are measured, and the material composition of the small WEEE found is determined. The hazardous substances' 'base' charge in the residual waste is established by means of atomic absorption spectrometry and ionic chromatography, as a first step in estimating the contribution of small WEEE to its pollutant load. Consequently, the content of small WEEE plastics in key heavy metals and halogens is determined. Key conclusions are drawn concerning the future strategic development and practical implementation of the 2002/96/EC Directive, in relation to small WEEE management and recycling

  2. Advance in radioactive decontamination; Avances en descontaminacion radiactiva

    Energy Technology Data Exchange (ETDEWEB)

    Basteris M, J. A. [Universidad Autonoma de Yucatan, Facultad de Medicina, Departamento de Diagnostico por Laboratorio y Gabinete, Av. Cupules No. 232, Col. Garcia Gineres, 97070 Merida, Yucatan (Mexico); Farrera V, R., E-mail: basteris@prodigy.net.m [Hospital de Especialidades de la UMAE, Centro Medico Nacional Ignacio Garcia Tellez, Departamento de Medicina Nuclear, Calle 34 x 41, Exterrenos el Fenix s/n, Col. Industrial, 91750 Merida, Yucatan (Mexico)

    2010-09-15

    The objective of the present work was to determine if the application of the Na hypochlorite has some utility in the radioactive decontamination, in comparison with the water, detergent and alcohol. Several methods were compared for decontaminate the iodine 131 and technetium 99, the work table and the skin it was carried out an initial count with the Geiger Muller. Later on, in a single occasion, the areas were washed with abundant water, alcohol, clothes detergent and sodium hypochlorite (used commercially as domestic bleacher) without diluting. Observing that the percentage in the decrease of the counted radioactivity by the Geiger Muller, decreased in the following way: It was demonstrated that the Na hypochlorite presents the highest index of radioactive decontamination with 100% of effectiveness. The Na hypochlorite is an excellent substance that can be used with effectiveness and efficiency like decontamination element in the accident cases of radioactive contamination in the clinical laboratories of nuclear medicine. (Author)

  3. Radioactive waste disposal

    International Nuclear Information System (INIS)

    Bohm, H.; Closs, K.D.; Kuhn, K.

    1981-01-01

    The solutions to the technical problem of the disposal of radioactive waste are limited by a) the state of knowledge of reprocessing possibilites, b) public acceptance of the use of those techniques which are known, c) legislative procedures linking licensing of new nuclear power plants to the solution of waste problems, and d) other political constraints. Wastes are generated in the mining and enriching of radioactive elements, and in the operation of nuclear power plants as well as in all fields where radioactive substances may be used. Waste management will depend on the stability and concentration of radioactive materials which must be stored, and a resolution of the tension between numerous small storage sites and a few large ones, which again face problems of public acceptability

  4. Experiences from the exercise ''MERLIN'' for the detection of radioactive substances with the participation of special-purpose vehicles; Erfahrungen aus der Uebung ''MERLIN'' zur Detektion radioaktiver Stoffe unter Beteiligung verschiedenen Einsatzfahrzeuge

    Energy Technology Data Exchange (ETDEWEB)

    Griesbach, M. [Hessisches Ministerium des Innern und fuer Sport, Wiesbaden (Germany)

    2009-08-15

    Experiences of an exercise with hazardous goods, in particular with radioactive substances (measurements and taking environmental samples) are described. Several special-purpose vehicles with equipment and specially trained crews were used together with radiation protection experts according to the concept of Hesse. It has been the greatest exercise in Hesse with regard to hazardous goods and in particular with regard to ''incidents with radioactive substances''. (orig.)

  5. Background radioactivity in environmental materials

    International Nuclear Information System (INIS)

    Maul, P.R.; O'Hara, J.P.

    1989-01-01

    This paper presents the results of a literature search to identify information on concentrations of 'background' radioactivity in foodstuffs and other commonly available environmental materials. The review has concentrated on naturally occurring radioactivity in foods and on UK data, although results from other countries have also been considered where appropriate. The data are compared with established definitions of a 'radioactive' substance and radionuclides which do not appear to be adequately covered in the literature are noted. (author)

  6. Radiation protection of the public in respect of consumer goods containing radioactive substances

    International Nuclear Information System (INIS)

    1984-01-01

    The use of consumer goods containing radioactive substances makes a contribution to the total exposure of man to ionizing radiation. This contribution is explicitly recognized in Section II of the Basic Safety Standards established pursuant to Article 30 of the Euratom Treaty for the health protection of the general public and workers against the dangers of ionizing radiation, first published in 1959 and most recently revised 15 July 1980. Nevertheless, the Standards are of a general nature and need to be expanded on to be of practical application in this field. National authorities must have additional information in order to attain in full the objectives stated in them. This guide has been prepared with these considerations in mind. The guide is not a set of regulations but is better described as a code of practice, drawn up by specialists and approved by the scientific experts in the field of radiological protection and public health appointed under Article 31 of the Euratom Treaty

  7. An improved analytical method for iodine-129 determination in low-level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Hsieh, Yi-Kong; Wang, TsingHai; Jian, Li-Wei; Chen, Wei-Han; Wang, Chu-Fang [National Tsing Hua Univ., Hsinchu, Taiwan (China). Dept. of Biomedical Engineering and Environmental Sciences; Tsai, Tsuey-Lin [Atomic Energy Council, Taiwan (China). Chemical Analysis Div.

    2014-07-01

    In this study, an alkaline-digestion pretreatment and a subsequent ICP-MS measurement were conducted for iodine-129 (I-129) determination in low-level radioactive waste. A TMAH + H{sub 2}O{sub 2} + Triton X-100 mixed alkaline digestion was the most effective mixture for I-129 determination. Using this alkaline reagent, a high level of I-129 recovery (101 ± 6%) was achieved for the analysis of the I-129-spiked standard reference materials NIST 2709 and 2711. Importantly, the I-129 concentrations determined for ten real samples provided by the Lan-Yu radioactive waste temporary storage site were found to be below the detection limit (0.011 mg/kg). This value was only approximately 30-70% of the values determined using the I-129/Cs-137 scaling factor. This means that using the I-129/Cs-137 scaling factor severely overestimates the I-129 concentration in these low-level radioactive wastes. We therefore suggest that a detailed re-inspection of the I-129/Cs-137 scaling factor should be performed to appropriately categorize these low-level radioactive wastes.

  8. Objectives for remediation of areas polluted by radioactive substances in France - 59300

    International Nuclear Information System (INIS)

    Cazala, Charlotte; Gay, Didier; Chabanis, Olivier; Guillevic, Jerome; Palut Laurent, Odile; Dandrieux, Geraldine; Thomassin, Alain; Chapalain, Estelle; Roy, Laurence

    2012-01-01

    Document available in abstract form only. Full text of publication follows: In the 90's, the French administration has developed several tools in order to inventory potentially polluted sites and to identify those requiring an immediate action. Concerns and needs have gradually moved on and a methodology for the management of selected areas was established. A general framework was then published by the Ministry of Ecology in 2007. The Ministry of Ecology jointly with the Nuclear Safety Authority (ASN) asked the Institute for Radiological Protection and Nuclear Safety (IRSN) to establish guidelines for the management of radioactive polluted areas. Requirements were: i) to fit with the published general framework while highlighting specificities of radioactive pollutants management; ii) to take benefit of radioactive polluted areas remediation; iii) to precise remediation objectives and iv) to develop stakeholders involvement issues. Within this general framework, two situations were identified: i) the polluted area is already used for domestic, public or industrial purposes; ii) the polluted area is an industrial site under dismantling or a polluted wasteland where a redevelopment project is under consideration. Management of a polluted site with ongoing use is based on the pollution level determination

  9. Contents of management plans for incidents and accidents involving the transport of radioactive substances. Guide no. 17, Version of 22/12/2014

    International Nuclear Information System (INIS)

    2014-01-01

    This guide presents the essential topics to be developed in a management plan for incidents and accidents involving the transport of radioactive substances for civil use. It does not aim to be exhaustive and could be added to by each party involved in the transport, who can make the necessary adaptations and additions, taking account of the particularities of its shipments and its organisation, as well as those of the company or group to which it belongs. The radioactive substances transport incident and accident management plan is a document comprising a descriptive part and an operational part. It presents the overall response of the party involved in the transport operation to an incident or accident situation concerning one of its shipments and the steps it intends to make in order to support the authorities in charge of this situation, in the best possible conditions. This response is designed to cover the cases of incidents or accidents whether or not they lead to a radiological emergency situation. The guide exclusively concerns: - road transport; - rail transport; - the 'road' and 'rail' parts of multimodal transport operations. The case of an incident or an accident occurring during a particular stop such as a transit site, in a transhipment area (port, airport, railway station, etc.), or in a transport infrastructure, is also covered by the radioactive substances transport incident and accident management plan, which then supports the entities in charge of managing this situation (operator of the transhipment area or the transport infrastructure and - as applicable - their supervisory authorities). The level of risk associated with transport incidents and accidents varies widely, according to the nature and quantities of the materials being carried, the number of shipments made and the package model used. The incident and accident management plan must therefore be tailored to the specific nature of the shipments by the party concerned. The radioactive

  10. Monitoring programme. Radioactive substances report for 1994

    International Nuclear Information System (INIS)

    1995-09-01

    In the United Kingdom, Her Majesty's Inspectorate of Pollution commissions independent monitoring of radioactive discharges to the environment. This report presents the results of such monitoring for 1994. It covers nuclear sites, two non-nuclear sites which use large amounts of tritium and several landfill sites which receive low-level radioactive waste for controlled burial. The monitoring programme concentrates on activity levels in environmental materials that might result in exposure of the public to radiation from non-food pathways. The results show that exposures from these pathways in 1994 remain similar to those in previous years and in all cases are estimated to have been substantially lower than the International Commission on Radiological Protection's recommended dose limit of 1mSv per year. (6 figures; 20 tables; 29 references) (UK)

  11. Monitoring of covering model of the National radioactive waste repository

    International Nuclear Information System (INIS)

    Jezikova, M.

    2009-01-01

    The subject of this rigorous report is justification of cover model building at radioactive waste repository in Mochovce as a very important engineering barrier preventing significant release of radioactive substances into the environment and providing protection against ionizing radiation. This rigorous report includes a theoretical part, which describes radioactive waste characterization, radioactive waste management and summary of the preliminary activities prior to the building cover model, particularly involving the selection of appropriate variables and parameters and creation of monitoring plan during the long term monitoring for evaluation of this barrier in order to ensure minimization of any leak of radioactive substances from RAW. The next part includes evaluation of the values of parameters and variables to build cover model of RAW in Mochovce during 2006-2008 (author)

  12. Determination of microscopic interactions between actinides and humic substances

    International Nuclear Information System (INIS)

    Brunel, Benoit

    2015-01-01

    Large amount of plutonium has been introduced into the environment as a result of nuclear weapons testing, and nuclear power-plant accidents. Contaminated areas, which need a particular survey, have become a very interesting place to study and understand the plutonium behaviour in the environment. Until few years ago, it was admitted that plutonium introduced into subsurface environment is relatively immobile, owing to its low solubility in ground water and strong sorption onto rocks. However, studies of contaminated areas show that humic substances, which are ubiquitous in environment, can alter the speciation of metal ion, e.g. plutonium, and thus their migration. These humic substances are major components of the natural organic matter in soil and water as well as in geological organic deposits such as lake sediments, peats and brown coals. They are complex heterogeneous mixtures of polydisperse supra-molecules formed by biochemical and chemical reactions during the decay and transformation of plant and microbial remains. The knowledge of the impact of humic substances on the plutonium migration is required to assess their transport in natural systems. However, due to the complex and heterogeneous nature of humic substances, there are a lot of difficulties in the description of microscopic interactions. The aim of this PhD thesis is to evaluate as precisely as possible interactions between actinides and humic substances. This work is divided in two parts: on the one hand humic substances will be separated to identify each component, on the other hand the speciation of actinides with characterized humic substances will be studied. In the first part of this study, new methods are developed to study the speciation of actinides with humic substances using two kinds of mass spectrometers: an ICP-MS and a high resolution mass spectrometer using various ionization devices (ESI, APCI, DART, APPI) in order to determine all active molecules for the complexation. In the

  13. An experimental interactive risk communication on the effect of radioactive substance on health through food

    International Nuclear Information System (INIS)

    Niiyama, Yoko; Kito, Yayoi; Kudo, Haruyo

    2011-01-01

    Risk communication, an interactive process of exchange of information and opinion on risk among stakeholders is the important element in Risk Analysis. However, we haven't effective model yet. We have tried experimental Interactive risk communication on the effect of radioactive substance on health through food related the accident of Fukushima Daiichi nuclear power plant. The model is consist of some process for making scientific information and discussion among consumer groups on the information; making and providing first step scientific information by scientists and communicator for consumers, first step group discussions on the information by consumers, making second step scientific information based critical questions in the first step group discussions, and second step group discussions on the second step information by consumers. We had organized 8 discussion groups, 50 subjects in Tokyo and Kyoto. (author)

  14. 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

  15. Treatment of Radioactive Gaseous Waste

    International Nuclear Information System (INIS)

    2014-07-01

    Radioactive waste, with widely varying characteristics, is generated from the operation and maintenance of nuclear power plants, nuclear fuel cycle facilities, research laboratories and medical facilities. The waste needs to be treated and conditioned as necessary to provide waste forms acceptable for safe storage and disposal. Although radioactive gaseous radioactive waste does not constitute the main waste flow stream at nuclear fuel cycle and radioactive waste processing facilities, it represents a major source for potential direct environmental impact. Effective control and management of gaseous waste in both normal and accidental conditions is therefore one of the main issues of nuclear fuel cycle and waste processing facility design and operation. One of the duties of an operator is to take measures to avoid or to optimize the generation and management of radioactive waste to minimize the overall environmental impact. This includes ensuring that gaseous and liquid radioactive releases to the environment are within authorized limits, and that doses to the public and the effects on the environment are reduced to levels that are as low as reasonably achievable. Responsibilities of the regulatory body include the removal of radioactive materials within authorized practices from any further regulatory control — known as clearance — and the control of discharges — releases of gaseous radioactive material that originate from regulated nuclear facilities during normal operation to the environment within authorized limits. These issues, and others, are addressed in IAEA Safety Standards Series Nos RS-G-1.7, WS-G-2.3 and NS-G-3.2. Special systems should be designed and constructed to ensure proper isolation of areas within nuclear facilities that contain gaseous radioactive substances. Such systems consist of two basic subsystems. The first subsystem is for the supply of clean air to the facility, and the second subsystem is for the collection, cleanup and

  16. Chemical decontamination method for radioactive metal waste

    International Nuclear Information System (INIS)

    Onuma, Tsutomu; Akimoto, Hidetoshi

    1991-01-01

    The invention relates to a decontamination method for radioactive metal waste products derived from equipment that handles radioactive materials whose surfaces have been contaminated; in particular it concerns a decontamination method that reduces the amount of radioactive waste by decontaminating radioactive waste substances to a level of radioactivity in line with normal waste products. In order to apply chemical decontamination to metal waste products whose surfaces are divided into carbon steel waste and stainless steel waste; the carbon steel waste is treated using only a primary process in which the waste is immersed in a sulfuric acid solution, while the stainless steel waste must be treated with both the primary process and then electrolytically reduces it for a specific length of time and a secondary process that uses a solution of sulfuric acid mixed with oxidizing metal salts. The method used to categorize metal waste into carbon steel waste and stainless steel waste involves determining the presence, or absence, of magnetism. Voltage is applied for a fixed duration; once that has stopped, electrolytic reduction repeats the operative cycle of applying, then stopping voltage until the potential of the radioactive metal waste is retained in the active region. 1 fig. 2 tabs

  17. Morsleben repository for radioactive waste (ERAM). Operational safety, radiation protection and environmental monitoring. Release: December 2009

    International Nuclear Information System (INIS)

    2010-01-01

    The report overviews the monitoring activities of the Federal Office for Radiation Protection at the Morsleben repository for radioactive waste (ERAM), focussing the ERAM inventory of radioactive waste and the measures and results of geomechanical and hydrogeological monitoring, operational radiation protection, the monitoring of discharges of radioactive substances, environmental monitoring, and the dose levels expected from discharges of radioactive substances. (orig.)

  18. The 'new' Radiation Protection Ordinance - marking the difference between application of 'radioactive substances in medical research' (Section 41 StrlschV) and 'radioactive substances or ionizing radiation in medicine and dental medicine' (Section 42 StrlschV)

    International Nuclear Information System (INIS)

    Roedern, P.

    1983-01-01

    The main differences in the provisions are to be found under the following aspects: - Observation of dose limits; - Necessity of physical radiation protection surveillance; - Obligation to apply for approval in individual cases; - Selection of test persons/patients; - Scope of conditions governing approval; - Obligation to inform about hazards. The unambiguous definition of procedures and purposes allowed in the field of medical research, and of those in the field of medical therapy (including dental medicine) is of crucial importance, due to its significance with regard to radiation protection, civil law and penal law. Marking the limits between these two fields subject to supervision is a precondition allowing the proper application of relevant laws in the field of use and handling of radioactive substances or ionizing radiation for medical purposes. (orig./HSCH) [de

  19. Determination of natural radioactivity in beach sediments collected from Kovalam, Chennai

    International Nuclear Information System (INIS)

    Rajalakshmi, A.; Jananee, B.; Thangam, V.; Chandrasekaran, A.

    2018-01-01

    Long lived radioactive elements such as uranium, thorium, potassium and their decay products such as radium and radon are examples of naturally occurring radioactive materials abbreviated as NORM. All living things are exposed to ionizing radiation from NORM contributing to about 90% of human radiation exposure. The interaction of ionizing radiation with human body leads to several biological damages like leukemia, cancer etc due to damage and modification of cells and tissues in the body. Hence, the present work is carried out to determine the natural radioactivity of beach sediments along Kovalam Beach, Chennai. Associated parameters are also calculated

  20. Regulations under the Radioactive Substances Act of 1958, No. 115, 1961

    International Nuclear Information System (INIS)

    1961-01-01

    These very detailed regulations lay down the licensing system for the use of radioactive materials. They provide for monitoring and control of radiation and radiation contamination, storage, labelling and transport of radioactive materials and also for the disposal of radioactive waste. (NEA) [fr

  1. EG type radioactive calibration standards

    International Nuclear Information System (INIS)

    1980-01-01

    EG standards are standards with a radioactive substance deposited as a solution on filtration paper and after drying sealed into a plastic disc or cylinder shaped casing. They serve the official testing of X-ray and gamma spectrometers and as test sources. The table shows the types of used radionuclides, nominal values of activity and total error of determination not exceeding +-4%. Activity of standards is calculated from the charge and the specific activity of standard solution used for the preparation of the standard. Tightness and surface contamination is measured for each standard. The manufacturer, UVVVR Praha, gives a guarantee for the given values of activity and total error of determination. (M.D.)

  2. Guidance on accidents involving radioactivity

    International Nuclear Information System (INIS)

    1989-01-01

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

  3. Bases for safety of shipping radioactive materials

    International Nuclear Information System (INIS)

    Frejman, Eh.S.; Shchupanovskij, V.D.; Kaloshin, V.M.

    1986-01-01

    Classification is presented and design of packaging containers for radioactive substance shipment is described. Standard documents and the main activities related to the shipment radiation safety provision are considered. Practical recommendations on environment and personnel protection during radioactive cargo shipment by all types of vehicles are presented

  4. Study on hazardous substances contained in radioactive waste

    International Nuclear Information System (INIS)

    Kuroki, Ryoichiro; Takahashi, Kuniaki

    2008-01-01

    It is necessary that the technical criteria is established concerning waste package for disposal of the TRU waste generated in Japan Atomic Energy Agency. And it is important to consider the criteria not only in terms of radioactivity but also in terms of chemical hazard and criticality. Therefore the environmental impact of hazardous materials and possibility of criticality were investigated to decide on technical specification of radioactive waste packages. The contents and results are as following. (1) Concerning hazardous materials included in TRU waste, regulations on disposal of industrial wastes and on environmental preservation were investigated. (2) The assessment methods for environmental impact of hazardous materials included in radioactive waste in U.K, U.S.A. and France were investigated. (3) The parameters for mass transport assessment about migration of hazardous materials in waste packages around disposal facilities were compiled. And the upper limits of amounts of hazardous materials in waste packages to satisfy the environmental standard were calculated with mass transport assessment for some disposal concepts. (4) It was suggested from criticality analysis for waste packages in disposal facility that the occurrence of criticality was almost impossible under the realistic conditions. (author)

  5. Methods and apparatus for determining the spatial distribution of a radioactive material

    International Nuclear Information System (INIS)

    Todd, R.W.

    1975-01-01

    The spatial distribution of a radioactive material is determined by locating the positions of and energy losses resulting from Compton interactions which occur in a detector as a result of gamma photons emitted by the radioactive material, which may, for example, have been administered to a patient for medical diagnostic investigation. (auth)

  6. Radioactive contamination of natural and artificial materials

    International Nuclear Information System (INIS)

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

    1980-01-01

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

  7. Determining Original Inventory Amount of Radioactive Substances from Unmonitored Radionuclide Emissions

    International Nuclear Information System (INIS)

    Hamilton, J.T.; Blunt, B.C.

    1999-01-01

    The purpose of this document is to determine the air emissions inventory of the Savannah River Site. To satisfy regulatory requirements, a new equation has been developed to determine original inventory amounts from unmonitored radionuclide emissions

  8. Determination of geochemical and natural radioactivity characteristics in Bilecik Marble, Turkey

    Science.gov (United States)

    Yerel Kandemir, Suheyla; Ozbay, Nurgul

    2014-05-01

    Natural stones are one of the oldest known building materials. There are more than 400 natural stone in Turkey. Recently, the demand for the natural stone types in markets has been increasing rapidly. For this reason, the geochemical and natural radioactivity characteristics of natural stone are very important. Bilecik province is located at the northwest part of Turkey and it is surrounded by Sakarya, Bursa, Eskisehir and Kutahya city. Bilecik is one of the important marble industry regions of Turkey. Thus, the geochemical and natural radioactivity characteristics of Bilecik marble are very important. In this study, Bilecik marble was collected to determine the geochemistry and natural radioactivity. Then, analyses of geochemical and natural radioactivity in the marble samples are interpreted. ACKNOWLEDGMENT This study is supported by Bilecik Seyh Edebali University scientific project (Project Number =2011-02-BIL.03-04).

  9. Visualization of the thymus by substance P receptor scintigraphy in man

    Energy Technology Data Exchange (ETDEWEB)

    Hagen, P.M. van [Department of Immunology, Erasmus University, Rotterdam (Netherlands)]|[Department of Internal Medicine III, Erasmus University, Rotterdam (Netherlands); Breeman, W.A.P. [Department of Nuclear Medicine, Erasmus University, Rotterdam (Netherlands); Reubi, J.C. [Department of Pathology, University of Berne (Switzerland); Postema, P.T.E. [Department of Internal Medicine III, Erasmus University, Rotterdam (Netherlands); Anker-Lugtenburg, P.J. van den [Department of Hematology, Erasmus University, Rotterdam (Netherlands); Kwekkeboom, D.J. [Department of Nuclear Medicine, Erasmus University, Rotterdam (Netherlands); Laissue, J. [Department of Pathology, University of Berne (Switzerland); Waser, B. [Department of Pathology, University of Berne (Switzerland); Lamberts, S.W.J. [Department of Internal Medicine III, Erasmus University, Rotterdam (Netherlands); Visser, T.J. [Department of Internal Medicine III, Erasmus University, Rotterdam (Netherlands); Krenning, E.P. [Department of Internal Medicine III, Erasmus University, Rotterdam (Netherlands)]|[Department of Nuclear Medicine, Erasmus University, Rotterdam (Netherlands)

    1996-11-01

    In this study we present the results concerning the metabolism of the substance P analogue [{sup 111}In-DTPA-Arg{sup 1}]-substance P in man, as well as the visualization of the thymus in patients with immune-mediated diseases. Twelve selected patients were investigated, comprising five with inflammatory bowel disease, one with ophthalmic Graves` disease, one with sclerosing cholangitis, one with Sjoegren`s syndrome, one with rheumatoid arthritis, one with systemic lupus erythematosus and two with myasthenia gravis. After intravenous administration of 150-250 MBq (2.5-5.0 {mu}g) [{sup 111}In-DTPA-Arg{sup 1}]-substance P, radioactivity was measured in blood, urine and faeces for 48 h. Planar and single-photon emission tomographic images were obtained 4 and 24 h after injection. After administration of [{sup 111}In-DTPA-Arg{sup 1}]-substance P, a transient flush was observed in all patients. Degradation of [{sup 111}In-DTPA-Arg{sup 1}]-substance P started in the first minutes after administration, resulting in a half-life of 10 min for the total plasma radioactivity, and of 4 min for the intact radiopharmaceutical. Urinary excretion accounted for >95% of the radioactivity within 24 h post injection, and up to 0.05% was found in the faeces up to 60 h. In all patients uptake of radioactivity was found in the areolae mammae (in women), liver, spleen, kidneys and urinary bladder. In eight patients a high uptake of [{sup 111}In-DTPA-Arg{sup 1}]-substance P was observed in the thymus. We conclude that, despite its short half-life, [{sup 111}In-DTPA-Arg{sup 1}]-substance P can be used to visualize the thymus. This may contribute to the investigation of the role of thymus in immune-mediated diseases. In addition, inflammatory sites in various diseases could be visualized. (orig.). With 6 figs., 1 tab.

  10. Visualization of the thymus by substance P receptor scintigraphy in man

    International Nuclear Information System (INIS)

    Hagen, P.M. van; Breeman, W.A.P.; Reubi, J.C.; Postema, P.T.E.; Anker-Lugtenburg, P.J. van den; Kwekkeboom, D.J.; Laissue, J.; Waser, B.; Lamberts, S.W.J.; Visser, T.J.; Krenning, E.P.

    1996-01-01

    In this study we present the results concerning the metabolism of the substance P analogue [ 111 In-DTPA-Arg 1 ]-substance P in man, as well as the visualization of the thymus in patients with immune-mediated diseases. Twelve selected patients were investigated, comprising five with inflammatory bowel disease, one with ophthalmic Graves' disease, one with sclerosing cholangitis, one with Sjoegren's syndrome, one with rheumatoid arthritis, one with systemic lupus erythematosus and two with myasthenia gravis. After intravenous administration of 150-250 MBq (2.5-5.0 μg) [ 111 In-DTPA-Arg 1 ]-substance P, radioactivity was measured in blood, urine and faeces for 48 h. Planar and single-photon emission tomographic images were obtained 4 and 24 h after injection. After administration of [ 111 In-DTPA-Arg 1 ]-substance P, a transient flush was observed in all patients. Degradation of [ 111 In-DTPA-Arg 1 ]-substance P started in the first minutes after administration, resulting in a half-life of 10 min for the total plasma radioactivity, and of 4 min for the intact radiopharmaceutical. Urinary excretion accounted for >95% of the radioactivity within 24 h post injection, and up to 0.05% was found in the faeces up to 60 h. In all patients uptake of radioactivity was found in the areolae mammae (in women), liver, spleen, kidneys and urinary bladder. In eight patients a high uptake of [ 111 In-DTPA-Arg 1 ]-substance P was observed in the thymus. We conclude that, despite its short half-life, [ 111 In-DTPA-Arg 1 ]-substance P can be used to visualize the thymus. This may contribute to the investigation of the role of thymus in immune-mediated diseases. In addition, inflammatory sites in various diseases could be visualized. (orig.). With 6 figs., 1 tab

  11. Diagnostic agent for radioimmunological determinations

    International Nuclear Information System (INIS)

    Updike, S.J.

    1978-01-01

    The invention concerns a diagnostic agent for radioimmunological determinations. According to the invention, a binding protein (protein globulins, antibodies) of an aqueous solution specific for the substance to be determined is incorporated in gel particles of a strongly hydrophilic insoluble gel of controlled pore size. After subsequent drying of the system, a radioactively labelled form of the substance to be determined from a non-aqueous medium is included. The mixture is dried again. The diagnostic agent forred can be well stored and is very stable. There is no loss of activity of the specific bonding protein when drying according to the invented method. The described reagent can be effectively applied to the determination of many antigens and haptens: The gel is rehydrated by the sample to be investigated; as a result of this, the non-bonded tracer is set free and competes with the non-labelled substance for the bonding position. (VJ) [de

  12. Study of casks shielded with heavy metal to transport highly radioactive substances; Estudo de embalados com blindagem em metal pesado para transporte de substancias altamente radioativas

    Energy Technology Data Exchange (ETDEWEB)

    Lucchesi, R.F.; Hara, D.H.S.; Martinez, L.G.; Mucsi, C.S.; Rossi, J.L., E-mail: rflguimaraes@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2014-07-01

    Nowadays, Brazil relies on casks produced abroad for transportation in its territory of substances that are sources of high radioactivity, especially the Mo-99. The product of the radioactive decay of the Mo-99 is the Tc-99m, which is used in nuclear medicine for administration to humans in the form of injectable radioactive drugs for the image diagnosis of numerous pathologies. This paper aims to study the existing casks in order to propose materials for the construction of the core part as shielding against gamma radiation. To this purpose, the existing literature on the subject was studied, as well as evaluation of existing and available casks. The study was focused on the core of which is made of heavy metals, especially depleted uranium for shielding the emitted radiation. (author)

  13. Determination of lead and radioactivity in cosmetics products: Hazard assessment

    Directory of Open Access Journals (Sweden)

    Medhat Moustafa E.

    2015-01-01

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

  14. Activity determination of the Am-241 radioactive lightning rods

    International Nuclear Information System (INIS)

    Dellamano, Jose C.; Minematsu, Denise; Potiens Jr, Ademar J.

    2008-01-01

    Full text: The radioactive lightning rods had been manufactured in Brazil up to 1989, when the Comissao Nacional de Energia Nuclear (CNEN) lifted the license for manufacture, commerce and installation of these devices. Since this date, the radioactive lightning rods have been replaced for conventional protection systems against electric discharges and have been sent to the institutes subordinated to the CNEN, amongst them the Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP). The radioactive lightning rods are constituted in its majority for a central metallic rod where the plates are mounted. Am-241 radioactive sources are fixed in these plates. The treatment of these devices is made in a glove box, where mechanically the sources are separate of the plates and connecting rods, placed in a metallic package and stored for posterior characterization, final packaging, intermediate storage and final disposal. In accordance with manufacturers information had been installed in Brazil, approximately 75,000 units with activities varying between 25 and 92 MBq. Preliminary studies were carried out in some of the 16,000 lightning rods received by the Laboratorio de Rejeitos Radioativos (LRR) of the IPEN-CNEN/SP, and demonstrated that the variation of the values of activity is very bigger. The implantation of a methodology for the radioisotope characterization of the Am-241 removed sources of the radioactive lightning rods is important because the isotope inventory is necessary for the certification of the processes considered for packaging and storage, besides being indispensable data for the final disposal. It is convenient mentioning that one is not about the determination of activity of a radioactive source with geometry and defined characteristics, but the implantation of a measure protocol for groups of sources that will be used in the routine tasks of the LRR. The current work presents the methodology developed for the radioisotope characterization of the Am

  15. Smuggling of radioactive substances. Swedish capacity to detect and analyze; Smuggling av radioaktivt material. Sveriges foermaaga till detektion och analys

    Energy Technology Data Exchange (ETDEWEB)

    Ringbom, A.; Spjuth, L. [Swedish Defence Research Agency (FOI), Stockholm (Sweden)

    2001-04-01

    This report is the result of a survey of the existing Swedish national capability to detect an attempt to smuggle nuclear material or other radioactive substances. The capacity to perform a more thorough analysis of a seized sample has also been investigated. The study shows that Sweden today has a small capacity to disclose a smuggling attempt of such materials. The limited detection capacity that exists is not sensitive enough for this purpose, and is not used in an optimal way. Furthermore, relevant education of the custom officers is needed. Today, a national capability for an initial analysis of seized material exists, but action plans describing the handling of the material should be resolved. The high number of seizures of radioactive material in countries having a better detection capability indicates that illicit trafficking of radioactive materials is still a problem. In Sweden, we so far do not have many reported incidents of illicit trafficking - partly due to our limited capacity to detect radioactive material - however, we do not know how many incidents that really have occurred. Fixed installations for detection at the border controls are the most efficient way to improve our capacity for detecting nuclear material. An initial pilot study is suggested to be able to estimate the need. Increased education of the custom officers, establishment of formal routines for handling and analysis of seized materials, and to formalise the contacts with international analysis laboratories are also identified as important factors to be improved.

  16. Radioactivity analysis of food and accuracy control

    International Nuclear Information System (INIS)

    Ota, Tomoko

    2013-01-01

    From the fact that radioactive substances have been detected from the foods such as agricultural and livestock products and marine products due to the accident of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company, the Ministry of Health, Labour and Welfare stipulated new standards geared to general foods on radioactive cesium by replacing the interim standards up to now. Various institutions began to measure radioactivity on the basis of this instruction, but as a new challenge, a problem of the reliability of the data occurred. Therefore, accuracy control to indicate the proof that the quality of the data can be retained at an appropriate level judging from an objective manner is important. In order to consecutively implement quality management activities, it is necessary for each inspection agency to build an accuracy control system. This paper introduces support service, as a new attempt, for establishing the accuracy control system. This service is offered jointly by three organizations, such as TUV Rheinland Japan Ltd., Japan Frozen Foods Inspection Corporation, and Japan Chemical Analysis Center. This service consists of the training of radioactivity measurement practitioners, proficiency test for radioactive substance measurement, and personal authentication. (O.A.)

  17. Bio indicator organisms available to use for determination of radioactive elements in Turkey's seas

    International Nuclear Information System (INIS)

    Kocbas, F.; Guener, H.

    2006-01-01

    In determination of radioactive concentration and monitoring alive and lifeless environmental samples possess a significant place. Thus, intense study is carried out related to natural and artificial radionuclides sediment. Bio indicator living organisms inhabiting in sea ecosystems; are being evaluated in researches such as determinations of environmental pollution, natural and artificial radioactive elements. Turkey's seas are rich related to diversification of various types. In determining and monitoring radioactivity concentration widespread implementation of some sorts appeal attention and on the other hand inadequate usage of many types is observed. In the present study, providing information about the bio indicator organisms keep living in seas and plays important role in food supply chain and increasing the numbers of the types of organisms used are aimed

  18. Decontamination of radioactively contaminated surfaces

    International Nuclear Information System (INIS)

    1986-10-01

    By this standard objective conditions to evaluate and test the ease of decontamination of surfaces under laboratory conditions are to be laid down. Ease of decontamination in this context denotes the summed-up effect of two material properties: a) the capacity of the material for retaining radioactive substances at its surface; b) the ease with which these substances are given off again in the course of cleaning processes. (orig./HP) [de

  19. Radioactive elements and earthworms in contaminated soils

    International Nuclear Information System (INIS)

    Suleymanova, A.S.; Abdullayev, A.S.; Ahmadov, G.S.; Naghiyev, J.A.; Samadov, P.A.

    2010-11-01

    Earthworms are one of the indispensable soil animals which treat soil with letting it through their gut and help increasing soil fertility. The effect of radioactive elements and comparative effect of heavy metals to the vital functions of earthworms were determined in laboratory conditions. Experiments were continued for a month, and first of all, each soil type, grey-brown soil from Ramana iodine plant territory of Baku city, brown soil from Aluminum plant territory of Ganja city, aborigine grey-brown soil of Absheron peninsula, treated with Ra and U salts as model variants and brown soil of Ganja city was analyzed by gamma-spectrometer for radionuclide determining at the beginning and at the end of the experiment. Earthworms (Nicodrilus Caliginosus Sav.trapezoides) aboriginal for Absheron peninsula and plant residues were added to the soil. At the end of the month the biomass, survival value, coprolite allocation value, food activity and catalase value in earthworms and in soil were determined. The gamma-spectrometric analysis results gave interesting values in coprolites, soils which had been treated through the earthworms' gut. In comparison with the initial variants in experimental results more percent of radioactivity was gathered in coprolites. By this way earthworms absorbed most of radioactive elements and allocated them as coprogenous substances on the upper layer of soil. During absorbing, some percents of radioactive elements were also gathered in gut cells of the earthworms. Thereby determination of some vital functions of earthworms was expedient. Thus, by the instrumentality of these experiments we can use earthworms for biodiagnosis and for bioremediation of contaminated soils with radionuclides and heavy metals.

  20. Assessment of people exposure to contamination with radioactive substances removed to the atmosphere from nuclear objects of Swierk Centre, Poland, in the period of 1987-1992

    International Nuclear Information System (INIS)

    Filipiak, B.; Nowicki, K.

    1995-01-01

    The exposure of particular persons, living in the near surroundings of Nuclear Centre - Swierk near Warsaw, Poland, to radioactive substances removed to the atmosphere during the period 1987-1992 has been assessed. The effective dose equivalent for statistically critical groups of persons has been estimated. The results have been compared with maximum permitted dose limits. 17 refs, 12 tabs

  1. Method to determine the activity concentration and total activity of radioactive waste

    International Nuclear Information System (INIS)

    Angeles C, A.

    2001-02-01

    A characteristic system of radioactive waste is described to determine the concentration of radionuclides activity and the total activity of bundles of radioactive waste. The system this integrated by three subsystems: - Elevator of drums. - Electromechanics. - Gamma spectroscopy. In the system it is analyzed waste of issuing gamma specifically, and this designed for materials of relative low density and it analyzes materials of cylindrical recipients

  2. The use of fast and thermal neutron detectors based on oxide scintillators in inspection systems for prevention of illegal transportation of radioactive substances

    International Nuclear Information System (INIS)

    Ryzhikov, V. D.; Grinyov, B. V.; Piven, L. A.; Pochet, T.; Onyshchenko, G. M.; Lysetska, O. K.; Nagornaya, L. L.

    2009-01-01

    We present results of our studies aimed at practical application of an efficient method for detection of fast and thermal neutrons, which uses the process of inelastic scattering on atom nuclei present in inorganic scintillators. Due to energy transformation in inelastic scattering, the main fraction of gamma-radiation energy falls into the low-energy range (below 0.3 MeV). Detection in this range ensures efficiency that reaches up to 70% (as compared with 1% using conventional LiI(E)-techniques) and depends on the effective atomic number of the scintillator. The most evident practical application field for this method is inspection systems for prevention of illegal transportation of radioactive substances. Especially promising is the creation of a small-sized neutron detector for portable radioactive materials detection systems using the 'scintillator-avalanche photodiode' technology

  3. Entrapment process of radioactive gaseous wastes

    International Nuclear Information System (INIS)

    Gagneraud, Francis; Gagneraud, Michel.

    1981-01-01

    Process for collecting chemically inert gaseous radioactive waste in melted substances, whereby the gaseous waste is injected under pressure in a molten substance to its saturation point followed by fast cooling. This substance is constituted of glass, ceramics, metallurgical drosses and slag masses in fusion. Its cooling is carried out by quenching by means of running water or a gas fluid, or by casting into vessels with great thermal inertia such as cast iron or similar, before recovery and confinement in receptacles for storage [fr

  4. Measuring arrangement for simultaneous and continuous determination of the total and radioactive amounts of reactive matters in flowing inert gases. Pt. 1

    International Nuclear Information System (INIS)

    Figge, K.; Martinen, H.; Schulz, W.

    1976-01-01

    In order to investigate the metabolism behaviour of radiocarbon-labelled substances, a special apparatus has been designed which enables a fully automatic as well as continuous and simultaneous determination of the total and the 14 C-labelled carbon dioxide (CO 2 ) in the respiratory air of small animals. The CO 2 which is exhaled by the experimental animals is absorbed quantitatively in a novel absorber-scintillator cocktail. The quantity of combined total CO 2 is then determined by measuring the specific conductivity whereas the amount of radioactive CO 2 is assessed via scintillation measurement. The measuring accuracy achieved is around 10 N cm 3 or about 5 nCi, whereas the CO 2 recovery is above 98%. In addition to the recording in a linear recorder, the data are transferred to punching tapes and can be evaluated in an EDP unit. (orig.) [de

  5. Use of a radioactive substance, the depleted uranium, for the fabrication of enamels and usual things and jewels decoration

    International Nuclear Information System (INIS)

    1999-01-01

    This open letter to the ministers and State Secretaries of the public health, the environment and the consumers protection, deals with a complaint against X, lodged by the CRII-RAD. This complaint concerns the use of depleted uranium for the fabrication of enamels and the decoration of usual things and jewels. This utilization constitutes a breach of the decree 66-450, which forbids since 1966 the addition of radioactive substances in food, cosmetic and domestic products. The letter takes into account the hazards for the workers and the consumers, the uranium powder origin and discusses the guaranties forecast under the legislation eye. (A.L.B.)

  6. The environmental radioactivity data analysis at the inr platform in the post-chernobyl period

    International Nuclear Information System (INIS)

    Tudor, G.; Valeca, M.; Iordache, R.

    2016-01-01

    As a result of the Chernobyl accident, large quantities of radioactive substances were released into the atmosphere and were transported long distances, covering virtually the whole Europe, including Romania. This paper presents the analysis of the environment radioactivity data around the INR site, in the post-Chernobyl period in different types of samples. The purpose of this study was to evaluate the evolution of Chernobyl originated radionuclides concentration in Mioveni-Pitesti area. The selected indicator was Cs-137, which was monitored on a regular basis. From the post-Chernobyl annual reports, were collected the average values for Cs-137 activity in environmental samples. The concentration was determined for eleven sampling locations (soil and vegetation samples) distributed on 10 km distance around INR site, and the determination was made using gamma spectrometry. The data reveals significant variations of the Cs-137 activity. These variations may be generated by various disturbances that detach material from the soil and air, therefore allowing the substance to travel long distances from its origin. (authors)

  7. 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

  8. Determination of radioactivity in petroleum products and wastes

    International Nuclear Information System (INIS)

    Hrichi, Hajer

    2009-01-01

    At this end engineering study, we determined the activities of gamma- emitting radionuclides belonging to the families of 238 U, 235 U, 232 Th and 40K in the petroleum products and wastes of the refinery S.T.I.R. The activities of radionuclides which exceed that of crude oil prove that it's a technologically enhanced natural radioactivity since several chemical products were injected during the refining process. (Author)

  9. Authorization procedure for containers and modalities of transport of radioactive substances within the EC Member States

    International Nuclear Information System (INIS)

    Amaducci, S.

    1977-02-01

    In all EC Member States, the transport of radioactive substances, the activity of which is higher than a specific level, is subject to regulatory requirements. Most of these requirements demand an administrative authorization before starting transport. In Belgium, authorization may take the form of a general, particular or special authorization, and in Luxembourg of a general or particular authorization. The latter applies in France and Italy but in these countries specific provisions also exist depending on the means of transport used. The latter specific provisions also exist in Germany and in the Netherlands. On the contrary in the United Kingdom, no administrative authorization is needed for such transport, except for special consignments. Finally, it is to be noted that neither in Denmark nor in Ireland have regulatory requirements been laid down with respect to such authorization procedure

  10. Regulations for the disposal of radioactive waste in the Konrad repository - 59105

    International Nuclear Information System (INIS)

    Jung, Hagen G.; Bandt, Gabriele

    2012-01-01

    In Germany low / medium level waste, which is classified here as radioactive waste with negligible heat generation, will be disposed of in the Konrad underground repository. The construction and the operation of this nuclear facility required authorization by different fields of law, i.e., by nuclear law, mining law and water law. Whereas the nuclear law considers solely radiological aspects, the relevant permit issued according to the water law considers the impact of radioactive as well as non-radioactive harmful substances. The Federal Office for Radiation Protection (BfS) as operator of the repository and permit holder has (a) to record the disposed of radioactive and non-radioactive harmful substances and (b) to balance them. To meet these requirements BfS has developed a concept, which led to a site specific solution. Threshold values were defined for recording and for balancing the harmful substances. It had to be verified that by disposal of radioactive waste packages according to these values an adverse effect on the near-surface groundwater can be excluded. The Lower Saxony Water Management, Coastal Protection and Nature Conservation Agency (NLWKN) as the responsible water law regulatory authority approved the operator's concept as appropriate to comply with the requirements of the Water Law Permit. Nonetheless, collateral clauses were imposed to assure this. (authors)

  11. Tomogram forming process and apparatus using radioactive isotopes

    International Nuclear Information System (INIS)

    Stoddart, H.F.

    1980-01-01

    This invention relates to nuclear medicine and particularly to a tomogram forming apparatus which permits, with great efficiency, the very sensitive quantitative determination and the accurate spatial localization of the radioactivity of a body section of a patient to whom a substance labelled with radioactive isotopes has been administered. This scanner is characterized in that it includes several highly focused collimators placed one after the other, according to an arrangement which surrounds a scanning field. Each collimator is mobile with respect to the adjacent one and a system enables the arrangement to be rotated about the scanning field from one scanning position to another. Another device enables the collimators to be moved so that, for each scanning position, the focus of each collimator uniformly samples at least half the scanning field [fr

  12. Sensitive non-radioactive determination of aminotransferase stereospecificity for C-4' hydrogen transfer on the coenzyme.

    Science.gov (United States)

    Jomrit, Juntratip; Summpunn, Pijug; Meevootisom, Vithaya; Wiyakrutta, Suthep

    2011-02-25

    A sensitive non-radioactive method for determination of the stereospecificity of the C-4' hydrogen transfer on the coenzymes (pyridoxal phosphate, PLP; and pyridoxamine phosphate, PMP) of aminotransferases has been developed. Aminotransferase of unknown stereospecificity in its PLP form was incubated in (2)H(2)O with a substrate amino acid resulted in PMP labeled with deuterium at C-4' in the pro-S or pro-R configuration according to the stereospecificity of the aminotransferase tested. The [4'-(2)H]PMP was isolated from the enzyme protein and divided into two portions. The first portion was incubated in aqueous buffer with apo-aspartate aminotransferase (a reference si-face specific enzyme), and the other was incubated with apo-branched-chain amino acid aminotransferase (a reference re-face specific enzyme) in the presence of a substrate 2-oxo acid. The (2)H at C-4' is retained with the PLP if the aminotransferase in question transfers C-4' hydrogen on the opposite face of the coenzyme compared with the reference aminotransferase, but the (2)H is removed if the test and reference aminotransferases catalyze hydrogen transfer on the same face. PLP formed in the final reactions was analyzed by LC-MS/MS for the presence or absence of (2)H. The method was highly sensitive that for the aminotransferase with ca. 50 kDa subunit molecular weight, only 2mg of the enzyme was sufficient for the whole test. With this method, the use of radioactive substances could be avoided without compromising the sensitivity of the assay. Copyright © 2011 Elsevier Inc. All rights reserved.

  13. Can the same principles be used for the management of radioactive and non-radioactive waste?

    International Nuclear Information System (INIS)

    Bengtsson, Gunnar.

    1989-01-01

    Non-radioactive waste has a much more complex composition than radioactive waste and appears in much larger quantities. The two types of waste have, however, some properties in common when it comes to their longterm impact on health and the environment. The occurrence in both of substances that may exist for generations and may cause cancer provides one example. Both types of waste also always occur together. It is therefore proposed that the same basic principles could be applied for the management of radioactive and non-radioactive waste. By doing so one may increase the efficiency of policy development, research and practical management. This is particurlarly importand for the very costly restoration of old disposal sites which have earlier been poorly managed. (author)

  14. Anatomic-physiological schema of the gastrointestinal tract, to be taken in account in determining the levels of radioactive contamination; Schema anatomo-physiologique du tractus gastro-intestinal a prendre en consideration pour le calcul des niveaux de contamination Radioactive

    Energy Technology Data Exchange (ETDEWEB)

    Fabry, C [Commissariat a l' Energie Atomique, Cadarache, Association EURATOM-CEA, Niveaux de Contamination (France). Centre d' Etudes Nucleaires

    1964-07-01

    Anatomical and physiological data of the gastrointestinal tract of adults and children were summarized in a standard schema, to be used in calculating the levels of radioactive contamination, in the food chain. (author) [French] Cette note a pour objet de rassembler les donnees anatomiques et physiologiques du tractus gastrointestinal, chez l'adulte et chez l'enfant, et d'en deduire un schema standard qui puisse servir de base au calcul des niveaux de contamination de la chaine alimentaire par les substances radioactives. (auteur)

  15. Determination of natural Radioactivity in Groundwater in Tanke ...

    African Journals Online (AJOL)

    A study of the radioactivity in groundwater from Tanke-Ilorin, Nigeria, has been carried out. Ten water samples were analyzed by ϒ-ray spectroscopy to determine the 226Ra and 228Ra concentrations. The activity concentration values range from 0.81 ± 0.08 to 7.4 ± 2.2 Bq/l for 226Ra and from 1.8 ± 0.3 to 5.6 ± 2.6 Bq/l for ...

  16. Determination of environmental radioactivity, 8

    International Nuclear Information System (INIS)

    Takagi, Shinji; Nakaoka, Akira; Fukushima, Masanori; Tsukamoto, Masaki

    1984-01-01

    According to the fundamental design proposed for the purpose of dose assessment of the general public around a nuclear facility corresponding to the guideline issued by the Atomic Energy Commission of Japan, 5 mrem/yr, the authors developed a rapid and simple determination method of radioactivity in food and related environmental samples by pretreating with a modified microwave dehydration apparatus followed by radiation counting. Equation to estimate heating condition by the apparatus was derived, and estimation by the equation was in good agreement with experimental data. It took less than 4.5 hours to dehydrate by the proposed method. This value was much smaller in comparison with the value of more than 10 hours by a conventional hot-air drying method, and radiation counting was able to be started in the same day of sampling and dehydration procedure. It was cralified that lower limits of detection for each radionuclide by the proposed method by using a Ge(Li) detector of 20 % relative efficiency was lower than half level of needed detection limits to determine and evaluate the 5 mrem/yr level. Radionuclide levels in food samples such as vegetables and crustaceans was determined by the proposed method and it was found that they were below the lower detection limit of the method except natural radionuclide 40 K and fallout originated 137 Cs. (author)

  17. Thermal Neutron Die-Way-Time Studies for P and DGNAA of Radioactive Waste Drums at the MEDINA Facility

    Energy Technology Data Exchange (ETDEWEB)

    Mildenberger, Frank; Mauerhofer, Eric [Institute of Energy and Climate Research - Nuclear Waste Management and Reactor Safety, Forschungszentrum Juelich GmbH, 52425 Juelich (Germany)

    2015-07-01

    In Germany, radioactive waste with negligible heat production has to pass through a process of quality checking in order to check its conformance with national regulations prior to its transport, intermediate storage and final disposal. Additionally to its radioactive components, the waste may contain non-radioactive chemically toxic substances that can adversely affect human health and pollute the environment, especially the ground water. After an adequate decay time, the waste radioactivity will become harmless but the non-radioactive substances will persist over time. In principle, these hazardous substances may be quantified from traceability and quality controls performed during the production of the waste packages. As a consequence, a research and development program was initiated in 2007 with the aim to develop a nondestructive analytical technique for radioactive waste packages based on prompt and delayed gamma neutron activation analysis (P and DGNAA) employing a DT-neutron generator in pulsed mode. In a preliminary study it was experimentally demonstrated that P and DGNAA is suitable to determine the chemical composition of large samples. In 2010 a facility called MEDINA (Multi Element Detection based on Instrumental Neutron Activation) was developed for the qualitative and quantitative determination of nonradioactive, toxic elements and substances in 200-l steel drums. The determination of hazardous substances and elements is generally achieved measuring the prompt gamma-rays induced by thermal neutrons. Additional information about the composition of the waste matrix could be derived measuring the delayed gamma-rays from short life activation products. However a sensitive detection of these delayed gamma-rays requires that thermal neutrons have almost vanished. Therefore, the thermal neutron die-away-time has to be known in order to achieve an optimal discrimination between prompt and delayed gamma-ray spectra acquisition. Measurements Thermal neutron

  18. Compilation of data on the release of radioactive substances in the vent air of nuclear power plants in the Federal Republic of Germany in 1975

    International Nuclear Information System (INIS)

    Winkelmann, I.; Endrulat, H.J.; Haubelt, R.; Westpfahl, U.

    1976-04-01

    The present compilation of data on the release of radioactive substances in the vent air of nuclear power plants in the FRG is a continuation of a report series on aerosol filter and iodine filter samples from the exhaust air control systems of the nuclear power plants Gundremmingen, Obrigheim, Wuergassen, Stade, Lingen and Biblis A. The reports have been issued by the Federal public health office since 1972. This report is supplemented by annual release values on radioactive noble gases, on short- and long-lived aerosols, and on gaseous 131 I, supplied by the individual nuclear power plants as in previous years on uniform questionnaires. Data on the release of tritium are also available from some nuclear power plants. (orig.) [de

  19. Method of solidifying radioactive wastes

    International Nuclear Information System (INIS)

    Tomita, Toshihide; Minami, Yuji; Matsuura, Hiroyuki; Kageyama, Hisashi; Kobori, Junzo.

    1984-01-01

    Purpose: To perform the curing sufficiently even when copper hydroxide that interferes the curing reaction is contained in radioactive wastes. Method: Solidification of radioactive wastes containing copper hydroxide using thermoset resins is carried out under the presence of an alkaline material. The thermoset resin used herein is an polyester resin comprising unsaturated polyester and a polymerizable monomer. The alkaline substance usable herein can include powder or an aqueous solution of hydroxides or oxides of sodium, magnesium, calcium or the like. (Yoshino, Y.)

  20. Anatomic-physiological schema of the gastrointestinal tract, to be taken in account in determining the levels of radioactive contamination; Schema anatomo-physiologique du tractus gastro-intestinal a prendre en consideration pour le calcul des niveaux de contamination Radioactive

    Energy Technology Data Exchange (ETDEWEB)

    Fabry, C. [Commissariat a l' Energie Atomique, Cadarache, Association EURATOM-CEA, Niveaux de Contamination (France). Centre d' Etudes Nucleaires

    1964-07-01

    Anatomical and physiological data of the gastrointestinal tract of adults and children were summarized in a standard schema, to be used in calculating the levels of radioactive contamination, in the food chain. (author) [French] Cette note a pour objet de rassembler les donnees anatomiques et physiologiques du tractus gastrointestinal, chez l'adulte et chez l'enfant, et d'en deduire un schema standard qui puisse servir de base au calcul des niveaux de contamination de la chaine alimentaire par les substances radioactives. (auteur)

  1. X rays and radioactivity: a complete surprise

    International Nuclear Information System (INIS)

    Radvanyi, P.; Bordry, M.

    1995-01-01

    The discoveries of X rays and of radioactivity came as complete experimental surprises; the physicists, at that time, had no previous hint of a possible structure of atoms. It is difficult now, knowing what we know, to replace ourselves in the spirit, astonishment and questioning of these years, between 1895 and 1903. The nature of X rays was soon hypothesized, but the nature of the rays emitted by uranium, polonium and radium was much more difficult to disentangle, as they were a mixture of different types of radiations. The origin of the energy continuously released in radioactivity remained a complete mystery for a few years. The multiplicity of the radioactive substances became soon a difficult matter: what was real and what was induced ? Isotopy was still far ahead. It appeared that some radioactive substances had ''half-lifes'': were they genuine radioactive elements or was it just a transitory phenomenon ? Henri Becquerel (in 1900) and Pierre and Marie Curie (in 1902) hesitated on the correct answer. Only after Ernest Rutherford and Frederick Soddy established that radioactivity was the transmutation of one element into another, could one understand that a solid element transformed into a gaseous element, which in turn transformed itself into a succession of solid radioactive elements. It was only in 1913 - after the discovery of the atomic nucleus -, through precise measurements of X ray spectra, that Henry Moseley showed that the number of electrons of a given atom - and the charge of its nucleus - was equal to its atomic number in the periodic table. (authors)

  2. X rays and radioactivity: a complete surprise

    Energy Technology Data Exchange (ETDEWEB)

    Radvanyi, P. [Laboratoire National Saturne, Centre d`Etudes de Saclay, 91 - Gif-sur-Yvette (France); Bordry, M. [Institut du Radium, 75 - Paris (France)

    1995-12-31

    The discoveries of X rays and of radioactivity came as complete experimental surprises; the physicists, at that time, had no previous hint of a possible structure of atoms. It is difficult now, knowing what we know, to replace ourselves in the spirit, astonishment and questioning of these years, between 1895 and 1903. The nature of X rays was soon hypothesized, but the nature of the rays emitted by uranium, polonium and radium was much more difficult to disentangle, as they were a mixture of different types of radiations. The origin of the energy continuously released in radioactivity remained a complete mystery for a few years. The multiplicity of the radioactive substances became soon a difficult matter: what was real and what was induced ? Isotopy was still far ahead. It appeared that some radioactive substances had ``half-lifes``: were they genuine radioactive elements or was it just a transitory phenomenon ? Henri Becquerel (in 1900) and Pierre and Marie Curie (in 1902) hesitated on the correct answer. Only after Ernest Rutherford and Frederick Soddy established that radioactivity was the transmutation of one element into another, could one understand that a solid element transformed into a gaseous element, which in turn transformed itself into a succession of solid radioactive elements. It was only in 1913 - after the discovery of the atomic nucleus -, through precise measurements of X ray spectra, that Henry Moseley showed that the number of electrons of a given atom - and the charge of its nucleus - was equal to its atomic number in the periodic table. (authors).

  3. Hazard of radioactive releases resulted from coal burning

    International Nuclear Information System (INIS)

    Gabbard, V.

    1995-01-01

    Consideration is given to the data, pointing to the fact, that coal-burning power plants release of radioactive substances, contained in gaseous wastes, is not less, than the same one of nuclear power plants. The necessity of regulating emission of these substance in atmosphere by analogy with nuclear power industry is shown. 1 fig

  4. Determination and evaluation of the radiation dose to the population due to incorporation of natural radioactivity. Ermittlung und Bewertung der Strahlenexposition der Bevoelkerung, die durch Inkorporation natuerlicher radioaktiver Stoffe verursacht wird

    Energy Technology Data Exchange (ETDEWEB)

    Gloebel, B; Berlich, J; Keller, K D; Bauer, U; Andres, C; Zaeh, I; Malter, G; Fehrenz, K; Lehnen, H; Fehringer, F

    1989-03-01

    Of all natural radioactivity the uranium-radium and thorium decay chain each contribute essentially to the internal radiation exposure of human populations. The objective of the investigations carried out during the past years was on the one hand to determine the contents of the radionuclides {sup 3}H/uranium, radium, lead, polonium and thorium in the human body and furthermore to determine the relevant ingestion pathways as regards type and activity of the natural radioactive substances incorporated in foodstuffs and drinking water. For this purpose both human organ samples and environmental samples including foodstuffs and drinking water, essentially from the Saarland, but also from other regions of the FRG, were taken and analyzed. The methods used, as far as deviating from standard methods, are described. The measuring results are given and discussed. A concluding evaluation assigns the natural internal radiation exposure within the other risks of everyday life. The concentrations determined and the ingestion of the essential natural radionuclides are presented in tables. The radiation dose is estimated from the respective tissue concentration. (orig./HP).

  5. Investigation of the use of thermometric titrimetry for the determination of acidic substances in wine.

    Science.gov (United States)

    Godinho, O E; Coelho, J A; Chagas, A P; Aleixo, L M

    1984-03-01

    The use of thermometric titrimetry in the determination of acidic substances in red wine is described. The titration curve obtained in the thermometric titration of red wine with strong base presents two inflections. The stoichiometry corresponding to the first inflection presents good agreement with the so-called "total acidity" of wine, and is proposed for its determination. The second inflection is related to the content of phenolic substances in red wine.

  6. Techniques of Water-Resources Investigations of the United States Geological Survey. Book 5, Laboratory Analysis. Chapter A5, Methods for Determination of Radioactive Substances in Water and Fluvial Sediments.

    Science.gov (United States)

    Thatcher, L. L.; And Others

    Analytical methods for determining important components of fission and natural radioactivity found in water are reported. The discussion of each method includes conditions for application of the method, a summary of the method, interferences, required apparatus, procedures, calculations and estimation of precision. Isotopes considered are…

  7. Trasmar: automated vehicle for transport of radioactive materials

    International Nuclear Information System (INIS)

    Segovia R, J.A.; Martinez J, L.

    2001-01-01

    Traditionally robots have been used for industrial applications, even though area in which these devices had a deep impact is in the nuclear industry. The ININ is an Institute that must to manage and to work with radioactive substances. The ININ is also responsible of the storage and supervision of radioactive wastes in the country, therefore the applications of the automated systems in the Institute have as the main objective to reduce the exposure and the contact of personnel with the radioactive material. Here to, it has been proposed the project called Assisted Transportation of Radioactive Material (TRASMAR). (Author)

  8. On - Site Assessment Methods For Environmental Radioactivity

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  9. Determining the Knowledge Level of Pre-Service Teachers' on Radioactivity and Radiation

    Science.gov (United States)

    Ergul, N. Remziye

    2012-01-01

    This study investigated the basic knowledge levels of teacher candidates' from different branches regarding the subjects of radiation and radioactivity. 42 variables were determined in relation to the specified titles. In the preparation stage of determining the variables, all the related programs were examined, and attention was paid to include…

  10. 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

  11. Identification and determination of natural radioactive impurities in rare earth chlorides

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  12. 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

    Several natural radioactive substances occur in drinking water in Finland, among which radon-222 is the most harmful from radiation protection viewpoint. Also long-lived alpha-active substances like uranium-238, uranium-234, polonium-210 and radium-226, as well as beta-active lead-210 and radium-228 occur in drinking water. Elevated concentrations are found only in ground water, those originating from bedrock being clearly higher than those from soil. Assessments based on dosimetry indicate that radioactivity in drinking water causes annually 20 fatal cancers. About 40% of cases is due to inhaled waterborn radon, 40% is due to ingested radon and 20% is due to other natural radioactive substances than radon. This report gives motivation for a proposition to restrict and monitor the radiation exposure from radioactive substances in drinking water, delivered by STUK to the Ministry of Social Affairs and Health in March 1999. The proposition introduces an action level of 300 Bq/l for radon concerning the waterworks. For other radionuclides except radon the action level proposed is 0.1 millisieverts per year (mSv/a), collectively. This new proposition does not bring in notable changes in the monitoring practice, although the calculated doses will change slightly. The proposed guideline for radon in private wells is 1000 Bq/l. According to the present monitoring data, less than 200 Finns served by waterworks use drinking water with radon concentration exceeding 300 Bq/l. Approximately 1000 waterworks consumers receive an annual dose that exceeds 0.1 mSv from other radionuclides than radon. About 20 000 Finns served by private wells use drinking water with radon concentration exceeding the STUK guideline 1 000 Bq/l. Radon can be removed from drinking water using aeration or granular activated carbon filtration (GAC), whereas uranium and radium can be effectively removed by ion exchange resins and lead and polonium using reverse osmosis. There are two methods to determine

  13. Rapid determination of radioactive general β in the rain and snow

    International Nuclear Information System (INIS)

    Li Shuqing; Jiao Shufeng

    1992-01-01

    Deposit filtration has been successfully applied to the determination of radioactive general β in the rain and snow. This method is more direct and rapid than evaporation, and more efficient. The method has been widely used in the emergency monitoring of nuclear pollution

  14. Report of radioactivity survey research in fiscal year 1989

    International Nuclear Information System (INIS)

    1990-12-01

    In the National Institute of Radiological Sciences, as a part of the radioactivity survey and research of Science and Technology Agency, the survey of environmental radioactivity level due to the radioactive fallout accompanying nuclear explosion experiments and the radioactive substances released from nuclear facilities and others and the safety analysis of these have been carried out. The radioactivity and dose survey for environment, foods and human bodies, the survey of the level around nuclear facilities, the business of radioactivity data center, the basic investigation for the evaluation of the results of radioactivity survey, the training of environmental radiation monitoring technicians and the investigation and research of the measurement of emergency radiation exposure and countermeasures were carried out. Those results are summarized. (K.I.)

  15. Determination of radioactive scales in oil industry using naturally occurring radioactive materials

    International Nuclear Information System (INIS)

    Al-Masri, M. S.

    2006-06-01

    In the present study, naturally occurring radioactive materials (Radium isotopes) present in produced water and radiation measurements have been used to study the formation of scales, evaluate their age, determination of geological formations and between wells interactions. Produced water samples were collected and analyzed monthly for 5 months from 11 oil wells in three Syrian oil fields. Analysis includes radium isotopes and anions and cations concentrations in addition to radiation measurements at the well heads. The highest mean values of radium 226, Radium 228 and Radium 224 concentration in produced were 41 Bq/1, 57.1 Bq/1 and 1.1 Bq/1, respectively. The values obtained for Radium 226, Radium 228 and the activity ratio were statistically evaluated and the results were presented using the box plot method. The mean value of the activity ration of Radium 226 and Radium 228 was used to determine the age of scales accumulated inside tubulars. (author)

  16. Terms and definitions in the field of radiological technique. Radioactivity. Draft. Begriffe und Benennungen in der radiologischen Technik. Radioaktivitaet. Entwurf

    Energy Technology Data Exchange (ETDEWEB)

    1978-04-01

    Nuclides and their symbols: Nuclide, symbol for nuclides; Nuclear processes: Nuclear transformation, isomeric transition; Radioactive substances; Radiation of radioactive substances: Alpha radiation, beta radiation, k radiation, gamma radiation, conversion electrons, annihilation radiation, neutron radiation; Activity, specific activity, and activity concentration; Characteristic constants of radio nuclides: Decay constant, lifetime, half-life, specific gamma-ray constant, conversion coefficient; Decay series: Radioactive decay series, radioactive equilibrium; Nuclides with special names and symbols: Hydrogen isotopes, nuclides of the natural decay series.

  17. On safety of radioactive waste carrier

    International Nuclear Information System (INIS)

    Kondo, Toshikazu

    1995-01-01

    The waste generated by reprocessing the spent fuel from Japanese nuclear power stations in France and U.K. is to be returned to Japan. The first return transport was carried out from February to April when the waste management facility in Rokkasho, Aomori Prefecture, was completed. Most of this return transport was the sea transport using the exclusively used carrier, Pacific Pintail, from Cherbourg, France, to Mutsu Ogawara, Japan. Ministry of Transport carried out the examination on the safety of this method of transport including the safety of the carrier based on the rule for the sea transport and storage of dangerous substances. The international rule on the sea transport of high level radioactive waste, the course of adopting the INF code and its outline, and the Japanese safety standard for the carriers exclusively used for high level radioactive waste are explained. The Pacific Pintail is the ship of 5087 GT, which was built in 1987 as the carrier exclusively used for radioactive substances, owned by Pacific Nuclear Transport Ltd. of U.K. The main features related to the safety of the Pacific Pintail are explained, and the sufficient countermeasures are taken. (K.I.)

  18. Simulation of the dispersion of radioactive substances, for the case of Chernobyl as an example

    International Nuclear Information System (INIS)

    Memmesheimer, M.; Hass, H.; Jakobs, H.J.; Geiss, H.; Laube, M.

    1989-01-01

    On April 25, 1989, an accident with the so far most serious consequences occurred in the nuclear power plant at Chernobyl. As a result during the period April 25 to May 6, 1986, about 4% of the core inventory of radionuclides was released. The large scale atmospheric circulation dispersed the emitted radioactive material during and after this period over the complete northern hemisphere whereby the European area was affected in particular. The distribution and deposition of the radioactive air admixtures in the European region provides an interesting possibility to test the EURAD model. The transport and deposition of the radioactive material can then, within the frame of the model, be treated as a dispersal problem with consideration of the deposition processes. Simulating the reactor accident provides the possibility to test the role of emission heights of point sources. The calculations accomplished so far indicate among others that a determination as exact as possible of the meteorologic fields is decisive. Improvements appear to be possible with a nudging version of MM4, with which presently first simulation tests for the Chernobyl case are conducted. (orig./KW) [de

  19. Statutory Instruments - 1984 No. 863 and 1985 No. 708. Public Health, England and Wales - Public Health Scotland. The Control of Pollution (Radioactive Waste) Regulations 1984, The Control of Pollution (Radioactive Waste) Regulations 1985

    International Nuclear Information System (INIS)

    1985-01-01

    The Regulations provide that radioactive waste is to be treated as any other waste for pollution control purposes as opposed to special radioactive control purposes. In the former respect, radioactive waste is subject to Part II of the Control of Pollution Act 1974, but in the latter, it remains subject to the Radioactive Substances Act 1960. (NEA) [fr

  20. The role of chemistry in the history of radioactivity (1897-1939)

    International Nuclear Information System (INIS)

    Adloff, J.P.

    1997-01-01

    Chemical research on radioactivity started in 1898. That year, Pierre and Marie Curie discovered in pitchblende polonium and radium. Rutherford and Soddy showed that radioactivity is an atomic phenomenon accompanied by transmutation of elements and established the basic laws of radioactive changes. The existence of isotopes was postulated after the discovery of many radioactive substances. Major discoveries in nuclear science, i.e. the atomic nucleus, the neutron and artificial radioactivity, were made with radiation sources elaborated bu chemists. Finally, in 1939, radiochemists on the search for transuranium elements, discovered nuclear fission. (authors)

  1. Natural and artificial radioactivity determination of some medicinal plants

    International Nuclear Information System (INIS)

    Desideri, Donatella; Meli, Maria Assunta; Roselli, Carla

    2010-01-01

    Several medicinal plants used in Italy were analysed to determine natural and artificial radioactivity in those parts (leaves, fruits, seeds, roots, peduncles, flowers, barks, berries, thallus) used generally as remedies. The radionuclides were determined by alpha ( 238 U, 210 Po) and gamma ( 214 Pb-Bi, 210 Pb, 40 K and 137 Cs) spectrometry. 238 U ranged between dry -1 ; 210 Po between dry -1 ; 214 Pb- 214 Bi between dry -1 ; 210 Pb between dry -1 ; 40 K between 66.2 and 3582.0 Bq kg dry -1 ; 137 Cs between dry -1 . The percentage of 210 Po extraction in infusion and decoction was also determined; the arithmetical mean value of percentage of 210 Po extraction resulted 20.7 ± 7.5.

  2. Determination of 90Sr, 129I and gross beta radioactivity concentration in some teas

    International Nuclear Information System (INIS)

    Sultan Sahin; Mahmut Dogru

    2011-01-01

    In this study, 90 Sr (540 keVβ - ), 129 I (150 keVβ - ) and the gross beta radioactivity concentrations were determined for the samples of tea as the most leading consumed hot drink in the markets (processed and packaged for sale) in our country. Furthermore, the obtained data were statistically analyzed. For determination of 129 I (150 keVβ - ), 90 Sr (540 keVβ - ) and gross radioactivity concentrations in tea samples, a sensor system consisting of scintillation detector with BP4 probe sensitive to beta radiation and a radiation meter (ST7) configurable for windows at desired power was used. (author)

  3. Kinetic assays for determining in vitro APS reductase activity in plants without the use of radioactive substances.

    Science.gov (United States)

    Brychkova, Galina; Yarmolinsky, Dmitry; Sagi, Moshe

    2012-09-01

    Adenosine 5'-phosphosulfate (APS) reductase (APR; EC 1.8.4.9) catalyzes the two-electron reduction of APS to sulfite and AMP, a key step in the sulfate assimilation pathway in higher plants. In spite of the importance of this enzyme, methods currently available for detection of APR activity rely on radioactive labeling and can only be performed in a very few specially equipped laboratories. Here we present two novel kinetic assays for detecting in vitro APR activity that do not require radioactive labeling. In the first assay, APS is used as substrate and reduced glutathione (GSH) as electron donor, while in the second assay APS is replaced by an APS-regenerating system in which ATP sulfurylase catalyzes APS in the reaction medium, which employs sulfate and ATP as substrates. Both kinetic assays rely on fuchsin colorimetric detection of sulfite, the final product of APR activity. Incubation of the desalted protein extract, prior to assay initiation, with tungstate that inhibits the oxidation of sulfite by sulfite oxidase activity, resulted in enhancement of the actual APR activity. The reliability of the two methods was confirmed by assaying leaf extract from Arabidopsis wild-type and APR mutants with impaired or overexpressed APR2 protein, the former lacking APR activity and the latter exhibiting much higher activity than the wild type. The assays were further tested on tomato leaves, which revealed a higher APR activity than Arabidopsis. The proposed APR assays are highly specific, technically simple and readily performed in any laboratory.

  4. Teaching concepts in the field of radioactivity and nuclear energy

    International Nuclear Information System (INIS)

    Bleichroth, W.

    1982-01-01

    This issue of 'Naturwissenschaften im Unterricht', dealing with the subjects of physics and chemistry, gives an account of the fundamentals of radioactivity, nuclear fission, controlled nuclear fission, nuclear power plants, dosimetry, safety engineering, shielding measures to prevent the release of radioactive substances, pressure engineering, emergency core cooling systems, waste disposal and natural and artificial environmental radioactivity. Teachers will find helpful hints as to the method of instruction and the explanation of problems. (DG) [de

  5. Transport of radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-04-15

    The increasing use of radioactive substances, not only in reactor operations but also in medicine, industry and other fields, is making the movement of these materials progressively wider, more frequent and larger in volume. Although regulations for the safe transport of radioactive materials have been in existence for many years, it has now become necessary to modify or supplement the existing provisions on an international basis. It is essential that the regulations should be applied uniformly by all countries. It is also desirable that the basic regulations should be uniform for all modes of transport so as to simplify the procedures to be complied with by shippers and carriers

  6. Determinants of psychoactive substance use among incarcerated ...

    African Journals Online (AJOL)

    The average age of first use was 12.6 ± 5.9 years. The prevalence of lifetime and current use of any substance was 88.0% and 64.3% respectively. Prior arrest, being sexually active and family drug use significantly (p<0.05) predicted lifetime use of any substance while being raised in a monogamous family was protective.

  7. The efficacy of surface active substances to decontaminate radioactive pollution of animals

    International Nuclear Information System (INIS)

    Kossakowski, S.

    1975-01-01

    The purpose of the work was to determine the efficacy of native surface-active substances in the decontamination of pig pollution with 90 Sr, 131 J, 144 Ce and 137 Cs. The appraisal was performed on the basis of indices of final activity. It was found that an Ixi solution was the most efficient against 137 Cs, E powder and Kokosal against 144 Ce and 90 Sr respectively, and also E powder against 137 J. The most universal proved to be enzymatic powders E and R, and then the detergens Ixi, Bis, FF and Kokosal. (author)

  8. Concentration of radioactive cobalt by seaweeds in the food chain

    International Nuclear Information System (INIS)

    Nakahara, Motokazu; Koyanagi, Taku; Saiki, Masamichi

    1976-01-01

    On the pathway of radioactive substances in marine environments, seaweeds play an important role because of their higher concentration factors for many radionuclides and because they constitute a link of food chain in the sea. In the present work, uptake, distribution and excretion of radioactive cobalt were studied on several kinds of seaweeds by radioisotope tracer experiments under laboratory conditions and concentration factors were calculated. The concentration factors were also estimated from the results of stable cobalt determination by activation analysis or atomic absorption spectrometry on seaweeds and seawater, and compared with the results of tracer expts. The seaweeds showed the species specificity for the concentration of stable and radioactive cobalt with diverse values of concentration factors and biological half-lives. The transfer of radioactive cobalt in the food chain from contaminated seaweeds to mollusca was examined by feeding abalones, Haliotis discus, with four kinds of seaweed labelled with 60 Co and observing retention. Absorption rate for radioactive cobalt by abalones calculated at two days after feeding showed diverse values depending upon the species of seaweed, as follows: 47% through Laminaria japonica and Ulva pertusa, 31% through Undaria pinnatifida and 26 through Eisenia bicyclis, respectively. From the results, it was assumed that the accumulation of radioactive cobalt by mollusca is affected by the species of seaweeds as food. A very high concentration of ingested radioactive cobalt in the midgut gland was seen on the autoradiograph of abalone samples. (auth.)

  9. Concentration of radioactive cobalt by seaweeds in the food chain

    International Nuclear Information System (INIS)

    Nakahara, M.; Koyanagi, T.; Saiki, M.

    1975-01-01

    On the pathway of radioactive substances in marine environments, seaweeds play an important role because of their higher concentration factors for many radionuclides and because they constitute a link in the food chain. In the present work, uptake, distribution and excretion of radioactive cobalt were studied on several kinds of seaweeds by radioisotope tracer experiments under laboratory conditions and concentration factors were calculated. The concentration factors were also estimated from the results of stable cobalt determination by activation analysis or atomic absorption spectrometry on seaweeds and seawater, and compared with the results of tracer experiments. The seaweeds showed the species specificity for the concentration of stable and radioactive cobalt with diverse values of concentration factors and biological half-lives. The transfer of radioactive cobalt in the food chain from contaminated seaweeds to mollusca was examined by feeding abalones, Haliotis discus, with four kinds of seaweed labelled with 60 Co and observing retention. Absorption rate for radioactive cobalt by abalones calculated at two days after feeding showed diverse values depending upon the species of seaweed, as follows: 47% through Laminaria japonica and Ulva pertusa, 31% through Undaria pinnatifida and 26% through Eisenia bicyclis, respectively. From the results, it was assumed that the accumulation of radioactive cobalt by mollusca is affected by the species of seaweeds as food. A very high concentration of ingested radioactive cobalt in the midgut gland was seen on the autoradiograph of abalone samples. (author)

  10. Structure and dynamics of humic substances and model poly-electrolytes in solution

    International Nuclear Information System (INIS)

    Roger, G.

    2010-09-01

    In the frame of a study about the feasibility of an underground storage of radioactive wastes, we focused on the role of degraded natural organic matter in the eventual transport of radionuclides in the environment. We are more interested by the determination of electro kinetic properties of these humic substances rather than the description of speciation reaction already widely discussed in the literature. We chose to determine the size and the charge of these humic substances thanks to an original method: high precision conductometry. This technique, associated to a suited transport theory, allows to describe the mobility of charged species in solution when taking into account the pairs interactions. We have participated in the development of this transport theory and we use it in order to determine the size and the charge of humic substances and a reference polyelectrolyte in different conditions of pH and ionic strength. All these experimental results obtained by conductometry were correlated with other experimental and theoretical methods: Atomic Force Microscopy, dynamic light scattering, laser zeta-metry and Monte-Carlo simulations. The obtained results confirm the generally admitted idea that humic substances are nano-metric entities having complexing properties towards cations and that can aggregate to form supra molecular structures. The effect of the ions present in the environment (sodium, calcium, magnesium) has been investigated. Finally the complexation of europium (which is considered as a good analogue of americium 241) has also been analysed by square wave voltammetry. (author)

  11. Determination of natural radioactivity levels in sediments: Caravelas river, BA, Brazil

    International Nuclear Information System (INIS)

    Carmo, R.F.; Trindade Filho, O.L.; Delgado, J.U.; Peixoto, J.G. P.; Evangelista, H.

    2016-01-01

    Due to intensive human activity in the region and disorderly occupation, the Caravelas River estuary has not yet evaluated the contribution of natural radioactivity. In order to determine the natural radioactivity levels in sediments, the activities of "2"3"8U, "2"3"2Th and "4"0K, were calculated using a gamma spectrometry system for measuring the concentration of radiation in samples. Results for "2"3"8U, "2"3"2Th and "4"0K ranged from (18.03 to 191.51), (28.57 to 118.25) and (134.06 to 186.80) Bq.kg"-"1, respectively, within of detection limits. The estimated uncertainty levels were less than 10% (k = 1). (author)

  12. Determination of natural radioactivity levels in sediments: Caravelas river, BA, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Carmo, R.F.; Trindade Filho, O.L.; Delgado, J.U.; Peixoto, J.G. P., E-mail: rfcarmo@bolsista.ird.gov.br, E-mail: octavio@ird.gov.br, E-mail: delgado@ird.gov.br, E-mail: guilherm@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Evangelista, H., E-mail: evangelista.uerj@gmail.com [Lab. de Radioecologia e Mudancas Globais (LARAMG/UERJ), Rio de Janeiro, RJ (Brazil)

    2016-07-01

    Due to intensive human activity in the region and disorderly occupation, the Caravelas River estuary has not yet evaluated the contribution of natural radioactivity. In order to determine the natural radioactivity levels in sediments, the activities of {sup 238}U, {sup 232}Th and {sup 40}K, were calculated using a gamma spectrometry system for measuring the concentration of radiation in samples. Results for {sup 238}U, {sup 232}Th and {sup 40}K ranged from (18.03 to 191.51), (28.57 to 118.25) and (134.06 to 186.80) Bq.kg{sup -1}, respectively, within of detection limits. The estimated uncertainty levels were less than 10% (k = 1). (author)

  13. Biological effects of concomitant influence of radioactive and chemical factors. (Experimental research)

    International Nuclear Information System (INIS)

    Meshkov, N.A.

    1995-01-01

    Remote consequences of concomitant influence of radioactive and chemical hazards substances, modeling the ecological situation at the territory of the Altaj region after the nuclear tests at the Semipalatinsk test site is studied on the mice. Negative effect of the concomitant impact of radioactive and hazardous chemical substances on the basic morpho-functional systems of animals is revealed; the reproduction function proved to be the most sensitive one. It is noted that the radiation factor constitutes the basis of all violations of bone marrow blood-producing function by concomitant influence

  14. Determinants of psychoactive substances use among Woldia University students in Northeastern Ethiopia.

    Science.gov (United States)

    Adere, Ashete; Yimer, Nigus Bililign; Kumsa, Henok; Liben, Misgan Legesse

    2017-09-05

    Psychoactive substance use has become a major public health problem among students in Ethiopian universities. Hence, this study aimed to investigate the magnitude and determinants of psychoactive substances use (khat chewing, alcohol drinking and cigarette smoking) among undergraduate students of Woldia University, Ethiopia. Institution based quantitative cross-sectional study was employed on Woldia University students in April 2015. 730 students were included in the study. Data were collected using self-administered questionnaires. EpiData version 3.02 was used to enter data. Then, data were exported to SPSS version 20 for analysis. The lifetime prevalence of alcohol drinking, khat chewing and cigarette smoking among the study students were 33.1, 13 and 7.9%, respectively. Likewise, the current prevalence of alcohol drinking, khat chewing and cigarette smoking was 27.9, 10.4 and 6.4%, respectively. More than half of the surveyed students (59.1%) were introduced to psychoactive substance use by peer pressure. About 66% of the study participants believed that psychoactive substances are important for relaxation, and 19% to relief from stress. Students who were Muslims [adjusted odds ratio (AOR) 3.74, 95% CI (1.57, 8.91)], Oromo ethnic group [AOR 2.63, 95% CI (1.19, 5.81)], ever drunk alcohol [AOR 6.32, 95% CI (2.96, 13.48)] and ever smoked cigarette [AOR: 9.16, 95% CI (4.33, 19.38)] were positively associated with khat chewing. Furthermore, pocket money and ever khat chewing were associated with alcohol drinking and cigarette smoking. This study showed that psychoactive substances use is somewhat prevalent among students in Woldia University. Hence, support of religious institutions in providing education aimed at preventing substance use, establishing and strengthening peer educators in the university are important interventions to tackle psychoactive substances use.

  15. The determination of cesium and rubidium in highly radioactive waste liquid

    International Nuclear Information System (INIS)

    Wei Songsheng

    1991-01-01

    Cesium and rubidium in high-level waste liquid were determined by atomic absorption spectrometry with the instrument modified for analyzing radioactive samples. The results show that the method is effective and safe. The error of the method is less than +- 3%, and it has been used in the production of cesium

  16. Radioactive materials in scrap metal, the situation in Switzerland

    International Nuclear Information System (INIS)

    Jossen, H.

    2005-01-01

    About 10 years ago, different happenings in the Swiss and international metal scrap recycling scene created a sensibility to unwanted radioactive substances in scrap metal. Italy, one of the main buyers for scrap metals, started at its borders with systematic checks, arranged by authorities. As a consequence, in Switzerland a concept was elaborated under cooperation of the recycling companies, the Italian authorities, the Federal Office of Public Health (BAG), Swiss Federal Nuclear Safety Inspectorate (HSK) and the Swiss National Accident Insurance Fund (Suva) to fulfil the different requirements. Individual radioprotection, protection of environment, protection of work yard and machinery and the quality assurance of the recycled metals and the resulting products requires adapted solutions with the main issues: training, suitable measuring equipment and an intervention-and waste management. Detected radioactive substances are professionally recovered, stored and submitted to the radioactive waste collection. The investigation of the happenings can lead to useful hints on gaps and on chances for improvements in general radioprotection. (orig.)

  17. Radioactive hazards

    International Nuclear Information System (INIS)

    Gill, J.R.

    1980-01-01

    The use of radioactive substances in hospital laboratories is discussed and the attendant hazards and necessary precautions examined. The new legislation under the Health and Safety at Work Act which, it is proposed, will replace existing legal requirements in the field of health and safety at work by a system of regulations and approved codes of practice designed to maintain or improve the standards of health, safety and welfare already established, is considered with particular reference to protection against ionising radiations. (UK)

  18. Aquatic ecosystems within the Chernobyl NPP exclusion zone: radioactive contamination, doses and effects

    International Nuclear Information System (INIS)

    Gudkov, D.I.; Kuzmenko, M.I.; Krot, Y.G.; Kipnis, L.S.; Mardarevich, M.G.; Ponomaryov, A.V.; Derevets, V.V.; Nazarov, A.B.

    2003-01-01

    For past 17 years after accident the character of radioactive contamination of water objects within the Chernobyl NPP exclusion zone has undergone essential changes. First of all it connected with realisation on a wide area of deactivation works, and also with transformation of radioactive substances in water-soil systems. Besides, during 1991-95 the complex of hydraulic engineering structures as protection dams, interfering washing away of radioactive substances from soils of the left-bank catchment basin and changed a hydrological regime of these territories during a high water, was constructed. The levels of radionuclide contamination of water objects within the Chernobyl NPP exclusion zone was rather stabilised. Due to high water change rate the river bottom sediments have undergone decontamination processes (especially during floods and periods of high water) and over the years have ceased to play the essential role as a secondary source of water contamination. On the other hand, the closed reservoirs have considerably higher levels of radioactive contamination caused by limited water change and by relatively high concentration of radionuclides deposited in the bottom sediments. Therefore, for the majority of standing reservoirs the level of radionuclide content is determined mainly by the rates of mobile radionuclide forms exchange between bottom sediment and water, as well as by the external washout from the catchment basin. In this paper will be considered: (1) the latest data on radionuclide content (Sr-90, Cs-137, Pu-238, Pu-239+240 and Am-241) and dynamics in water, seston, bottom sediments and hydrobionts of different trophic levels and ecological groups; (2) the peculiarities of formation of vegetative communities from lakes within embankment territory of Pripyat River flood-lands and its impact on radionuclide redistribution in aquatic ecosystems; (3) the major hydrochemical factors, which determine the behaviour of radionuclides in the aquatic

  19. Laser photodetachment of radioactive ions: towards the determination of the electronegativity of astatine

    CERN Multimedia

    Rothe, Sebastian; Welander, Jakob Emanuel; Chrysalidis, Katerina; Day Goodacre, Thomas; Fedosseev, Valentine; Fiotakis, Spyridon; Forstner, Oliver; Heinke, Reinhard Matthias; Johnston, Karl; Kron, Tobias; Koester, Ulli; Liu, Yuan; Marsh, Bruce; Ringvall Moberg, Annie; Rossel, Ralf Erik; Seiffert, Christoph; Studer, Dominik; Wendt, Klaus; Hanstorp, Dag

    2017-01-01

    Negatively charged ions are mainly stabilized through the electron correlation effect. A measure of the stability of a negative ion is the electron affinity, which the energy gain by attaching an electron to a neutral atom. This fundamental quantity is, due to the almost general lack of bound excited states, the only atomic property that can be determined with high accuracy for negative ions. We will present the results of the first laser photodetachment studies of radioactive negative ions at CERN-ISOLDE. The photodetachment threshold for the radiogenic iodine isotope 128I was measured successfully, demonstrating the performance of the upgraded GANDALPH experimental beam line. The first detection of photo-detached astatine atoms marks a milestone towards the determination of the EA of this radioactive element.

  20. Releases of radioactive substances from Swedish nuclear power plants (RAKU)

    Energy Technology Data Exchange (ETDEWEB)

    Ingemansson, T.; Bergstroem, C. [ALARA Engineering AB, Skultuna (Sweden)

    1997-04-01

    Releases of radioactivity to air and water from Swedish nuclear power plants have been studied and compared with those from foreign reactors. Averaged over the years from commissioning of the reactors to the last year data are available, the release of radioactive noble gas from the Swedish BWRs has been about the same as from comparable foreign reactors. The oldest Swedish BWRs, Oskarshamn 1 and 2 (O1 and O2) and Ringhals 1 (R1), have simple off-gas systems with only one delay volume. All BWRs in US, Germany, Japan and Switzerland are equipped with more sophisticated off-gas systems. It can be expected that O1, O2 and R1 therefore will have the highest release of noble gas activity at an international comparison if they do not modernize their off-gas system. BWRs in US, Germany and Japan are today equipped with recombiners and with one exception also charcoal columns. Japanese BWRs report zero releases to air. Releases of radioactivity to water after commissioning was about the same for most of the studied reactors. Some of the newest German plants have had low annual releases already at commissioning. Improvements of the treatment systems at old German, Swiss and US reactors have significantly lowered the releases. For most of the Swedish plants the annual releases to water have remained at the initial level. Forsmark 3 has succeeded in decreasing the release of radionuclides to water by a factor of almost one hundred compared to other Swedish reactors. Also O3 has managed to decrease the liquid effluents. Japanese plants have zero release of radioactivity excluding tritium to water. The release of tritium is about the same for all reactors of the same type in the world. 35 refs, 31 figs, 24 tabs.

  1. Impacts and issues of the radioactive substances due to the nuclear disaster. Cases of municipalities and elementary schools in Fukushima prefecture

    International Nuclear Information System (INIS)

    Murayama, Takehiko; Itaya, Sohei

    2012-01-01

    While all stakeholders make efforts by all means for mitigating impacts induced by radioactive substances after the accident, we would have to have a long way to restore the situation. Particularly, it would be difficult to promote meaningful communication about various risks. For making clear of current situation and issues to be resolved, we conducted a questionnaire survey for local governments and elementary schools in Fukushima prefecture. While local governments' officials and schools' teachers are willing to promote communication with public, they have substantial difficulties to do so. One reason is insufficient volume of information dissemination from national and prefectural governments. It would be important to increase manpower to promote better communication. (author)

  2. Report of radioactivity survey research in fiscal year 1996

    International Nuclear Information System (INIS)

    1997-12-01

    In National Institute of Radiological Sciences, a survey was made on radioactivities in the environment due to the substances released from nuclear installations and radioactive fall-out brought out by nuclear explosion tests since 1959. As the marked progress of non-military utilization of nuclear energy the national concern on environmental radioactivity has been increasing in Japan and thus it has become more and more important to make a survey research of radioactivities, which might affect the environment and human health. In these situations, the institute attempted to make the following six surveys in the fiscal year of 1996; 'a survey on radioactive levels in environment, foods and human bodies', 'survey on the radioactive level in the regions around nuclear installations', 'works in radioactive data center', 'fundamental survey on the evaluation of the results from radioactivity survey', 'workshop for technical experts of environmental radioactivity monitoring' and 'survey research on the measurement and countermeasures for emergency exposure'. (M.N.)

  3. Report of radioactivity survey research in fiscal year 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    In National Institute of Radiological Sciences, a survey was made on radioactivities in the environment due to the substances released from nuclear installations and radioactive fall-out brought out by nuclear explosion tests since 1959. As the marked progress of non-military utilization of nuclear energy the national concern on environmental radioactivity has been increasing in Japan and thus it has become more and more important to make a survey research of radioactivities, which might affect the environment and human health. In these situations, the institute attempted to make the following six surveys in the fiscal year of 1997; `a survey on radioactive levels in environment, foods and human bodies`, `survey on the radioactive level in the regions around nuclear installations`, `works in radioactive data center`, `fundamental survey on the evaluation of the results from radioactivity survey`, `workshop for technical experts of environmental radioactivity monitoring` and `survey research on the measurement and countermeasures for emergency exposure`. (J.P.N.)

  4. Stability-indicating UPLC method for determining related substances and degradants in dronedarone.

    Science.gov (United States)

    Pydimarry, Surya Prakash Rao; Cholleti, Vijay Kumar; Vangala, Ranga Reddy

    2014-08-01

    A simple, sensitive and reproducible method was developed on ultra-performance liquid chromatography coupled with photodiode array detection for the quantitative determination of dronedarone hydrochloride (DRO) in drug substance and pharmaceutical dosage forms. The method is applicable for the quantification of related substances and assays of drug substances. Chromatographic separation was achieved on Acquity UPLC BEH C8 100 mm, 2.1 mm and 1.7 µm columns, using gradient elution within a short run time of 10.0 min. The eluted compounds were monitored at 288 nm, the flow rate was 0.5 mL/min and the column oven temperature was maintained at 40°C. The resolution of DRO and 11 impurities (potentials and by-products) was greater than 2.0 for all pairs of components. The high correlation coefficient value (>0.9995) indicates the clear correlations between the concentrations of investigated compound and their peak areas within the test ranges. The repeatability and intermediate precision, expressed by the relative standard deviation, were less than 2.5%. The accuracy and validity of the method were further ascertained by performing recovery studies via a spike method. The accuracy of the method, expressed as relative error, was satisfactory. No interference was observed from concomitant substances normally added to the tablets. DRO was subjected to the stress conditions of oxidative, acid, base, hydrolytic, thermal and photolytic degradation. DRO was found to degrade significantly in acid and base stress conditions and to remain stable in thermal, photolytic degradation, oxidative and hydrolytic conditions. The degradation products were well resolved from primary peak and its impurities, proving that the method is stability indicating. The developed method was validated as per International Conference on Harmonization guidelines with respect to specificity, limit of detection, limit of quantification, linearity, accuracy, precision, solution stability and robustness

  5. Method of burning flammable radioactive wastes

    International Nuclear Information System (INIS)

    Yahata, Taneaki.

    1980-01-01

    Purpose: To completely oxidize flammable radioactive wastes such as organic compounds, ion exchange materials or oils. Method: Contaminated flammable radioactive wastes are heated and pyrolytically decomposed in the range 400 0 to 500 0 C in the presence of oxygen under lower pressure than atmospheric pressure. Volatile organic substance, hydrogen and soot subsequently produced are passed over oxidation catalyst. The catalysts such as copper oxide, iron oxide, cobalt oxide, nickel oxide, chromium oxide are heated in the range 600 0 to 700 0 C to produce stable oxides. (J.P.N.)

  6. 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)

  7. 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)

  8. Radioactive substances in wild mushrooms and other bioindicators. Inventory, Lower Saxony. As of April 1991

    International Nuclear Information System (INIS)

    Rohleder, K.

    1991-04-01

    The studies performed on wild mushrooms and other indicators were continued in 1990. Lower Saxony forestry authorities and food monitoring athorities co-operated in sampling. 153 wild mushroom samples and 14 samples of other bioindicators were examined in 1990. Activity values were corrected for decay and related to May 1986. The curves of Cesium-134 as a measure for contimination caused by the reactor accident, and of the sum of Cesium-137 and Cesium-134 run in parallel which means that the previous Cesium-137 contamination load does not affect the course of the curve. The maximum was found for chestnut boletus in 1987 and for cep in 1989. When comparing the means of the other mushroom with those of 1989, a slight rise was found for same-species mushrooms which grow in symbiosis with trees e.g. honey mushroom. No statement can be made on the other same-species mushrooms because of their low sample numbers. In 1990, some forestry authorities also sent samples of grass, beech leaves and spruce needles to be tested for radioactive substances. The means of 1989 and 1990 are compared. (orig./Uhe) [de

  9. Instruction No. 108, on handling of radioactive materials at Ministry of public health establishments

    International Nuclear Information System (INIS)

    1975-01-01

    The regulation applies to the design, construction, reconstruction, and operation of any medical establishment, facilities using radioactive substances for diagnostic, therapeutic, or research purposes. Designs for nuclear medicine laboratories (or departments) must be approbated by, and commissioning performed with the participation of representatives of the State Sanitary Control. Use of radioactive materials is licensed by the Ministry of Public Health and the Committee for Peaceful Uses of Atomic Energy. Radiation safety responsibility is assigned to a specific staff member of the laboratory (or department). Any receipt or transfer of radioactive material is entered into appropriate records, acts, or requests. Special storage facilities must be available; their design and equipment have to meet the particular requirements for the corresponding class of work, as determined by the activity levels, radiotoxicities, and physical conditions of the radioactive substances used. With storage of unsealed sources, the class is at least second. Sealed source treatment requires primarily protection from external exposure. In such cases provisions are made for one basic and one intermediate storage facility; an applicator preparation room; and application room; a sterilization room; a surgery room; wards; toilets and washrooms for patients treated; a routine manipulation room; and a stock room. A number of safety rules in handling sealed sources are listed. A detailed system of radiation protection safeguards and rules is prescribed with regard to ventilation, sewer systems, remote control devices, work clothing and gloves, etc. Handling of unsealed radioactive materials used for diagnostic or research purposes should meet the requirements placed upon the respective radioisotope laboratory class, which has to be at least second. (G.G.)

  10. Specific determination of clinical and toxicological important substances in biological samples by LC-MS

    International Nuclear Information System (INIS)

    Mitulovic, G.

    2001-02-01

    This thesis of this dissertation is the specific determination of clinical and toxicological important substances in biological samples by LC-MS. Nicotine was determined in serum after application of nicotine plaster and nicotine nasal spray with HPLC-ESI-MS. Cotinine was determined direct in urine with HPLC-ESI-MS. Short time anesthetics were determined in blood and cytostatics were determined in liquor with HPLC-ESI-MS. (botek)

  11. Application of mathematical models in assessing environmental impacts of nuclear facilities

    International Nuclear Information System (INIS)

    Dlouhy, Z.

    Mathematical models are divided into atmospheric models which monitoring the migration of radioactive substances in the atmosphere, hydrological models which monitoring the discharge of radioactive substances into the hydrosphere and their concentrations in sediments, water flora and fauna, and hydrogeological models which monitoring the migration of radioactive substances in ground water. The application is described of the hydrogeological model in the evaluation of the radiation burden in the environment of the Dobronin radioactive waste disposal site. This model contains the determination of the maximal amounts of disposed radioactive substances, maximal design-basis accident, the amounts of leached radioactive substances, the calculation of the time of migration of substances in the soil, the determination of the dispersion in the aquifer and the determination of the radiation burden of the population. (H.S.)

  12. Radioactive dust in the air

    Energy Technology Data Exchange (ETDEWEB)

    Yano, N

    1956-01-01

    An electric precipitator is used to collect dust in the air because its collection efficiency for radioactive substances is up to 10 times that of the impactor of filter-paper types. About 10 cu m of air is filtered during 5 hours, and the trapped dust is measured more than 24 hours after collection to avoid the influence of naturally active substances. The average radioactivity of the air is approximately 10/sup -16/ c/cc. During the period of observation 4 peaks occurred. The dates and maximum levels of artificial activity, respectively, are November 4 to 10, 1954, 1.2 x 10/sup -7/ uc/l; April 11 to 13, 1955, 4.3 x 10/sup -8/ uc/l; November 25 to 28, 1955, maximum unknown; and March 22 to 25, 1956, 1.- x 10/sup -7/ uc/l. The presumed dates and places of detonation corresponding to the peaks are October 31, 1954 northwest of Japan; March 29, 1955, Nevada, US; November 22, 1955, near L. Baikal, USSR; and March 13 to 15, 1956 unknown.

  13. An analytical model for radioactive pollutant release simulation in the atmospheric boundary layer

    International Nuclear Information System (INIS)

    Weymar, Guilherme J.; Vilhena, Marco T.; Bodmann, Bardo E.J.; Buske, Daniela; Quadros, Regis

    2013-01-01

    Simulations of emission of radioactive substances in the atmosphere from the Brazilian nuclear power plant Angra 1 are a necessary tool for control and elaboration of emergency plans as a preventive action for possible accidents. In the present work we present an analytical solution for radioactive pollutant dispersion in the atmosphere, solving the time-dependent three-dimensional advection-diffusion equation. The experiment here used as a reference in the simulations consisted of the controlled releases of radioactive tritiated water vapor from the meteorological tower close to the power plant at Itaorna Beach. The wind profile was determined using experimental meteorological data and the micrometeorological parameters were calculated from empirical equations obtained in the literature. We report on a novel analytical formulation for the concentration of products of a radioactive chain released in the atmospheric boundary layer and solve the set of coupled equations for each chain radionuclide by the GILTT solution, assuming the decay of all progenitors radionuclide for each equation as source term. Further we report on numerical simulations, as an explicit but fictitious example and consider three radionuclides in the radioactive chain of Uranium 235. (author)

  14. An analytical model for radioactive pollutant release simulation in the atmospheric boundary layer

    Energy Technology Data Exchange (ETDEWEB)

    Weymar, Guilherme J.; Vilhena, Marco T.; Bodmann, Bardo E.J., E-mail: guicefetrs@gmail.com, E-mail: mtmbvilhena@gmail.com, E-mail: bejbodmann@gmail.com [Universidade Federal do Rio Grande do Sul (UFRGS), Porto Alegre, RS (Brazil). Programa de Pos-Graduacao em Engenharia Mecanica; Buske, Daniela; Quadros, Regis, E-mail: danielabuske@gmail.com, E-mail: quadros99@gmail.com [Universidade Federal de Pelotas (UFPel), Capao do Leao, RS (Brazil). Programa de Pos-Graduacao em Modelagem Matematica

    2013-07-01

    Simulations of emission of radioactive substances in the atmosphere from the Brazilian nuclear power plant Angra 1 are a necessary tool for control and elaboration of emergency plans as a preventive action for possible accidents. In the present work we present an analytical solution for radioactive pollutant dispersion in the atmosphere, solving the time-dependent three-dimensional advection-diffusion equation. The experiment here used as a reference in the simulations consisted of the controlled releases of radioactive tritiated water vapor from the meteorological tower close to the power plant at Itaorna Beach. The wind profile was determined using experimental meteorological data and the micrometeorological parameters were calculated from empirical equations obtained in the literature. We report on a novel analytical formulation for the concentration of products of a radioactive chain released in the atmospheric boundary layer and solve the set of coupled equations for each chain radionuclide by the GILTT solution, assuming the decay of all progenitors radionuclide for each equation as source term. Further we report on numerical simulations, as an explicit but fictitious example and consider three radionuclides in the radioactive chain of Uranium 235. (author)

  15. Regulatory requirements for the transport of radioactive materials in Canada

    Energy Technology Data Exchange (ETDEWEB)

    Garg, R. [Canadian Nuclear Safety Commission, Ottawa (Canada)

    2004-07-01

    Canada is a major producer and shipper of radioactive material. Each year more than a million packages are transported in Canada. The safety record with the transport of RAM in Canada has historically been excellent. There have never been any serious injuries, overexposure or fatality or environmental consequences attributable to the radioactive nature of such material being transported or being involved in a transport accident. In Canada, the Canadian Nuclear Safety Commission (CNSC) is the prime agency of the federal government entrusted with regulating all activities related to the use of nuclear energy and nuclear substances including the packaging and transport of nuclear substances. The mission of the CNSC is to regulate the use of nuclear energy and materials to protect health, safety, security of the person and the environment and to respect Canada's international commitments on the peaceful use of nuclear energy. The division of responsibility for the regulation of transport of radioactive material has been split between Transport Canada and the CNSC. The governing Transport Canada's regulations are Transport of Dangerous Goods (TDG) Regulations and the CNSC regulations are Packaging and Transport of Nuclear Substances Regulations (PTNSR). Canada has actively participated in the development of the IAEA regulations for the safe transport of radioactive material since 1960. As an IAEA member state, Canada generally follows the requirements of IAEA regulations with few deviations. The Nuclear Safety and Control Act (NSCA) strongly supports Canada's international obligations to ensure safe packaging, transport, storage and disposal of nuclear substances, prescribed equipment and prescribed information. Prescribed equipment and prescribed information are defined in the CNSC General Nuclear Safety and Control Regulations. This paper presents the current CNSC regulatory requirements and initiatives taken by the CNSC to improve its effectiveness and

  16. Regulatory requirements for the transport of radioactive materials in Canada

    International Nuclear Information System (INIS)

    Garg, R.

    2004-01-01

    Canada is a major producer and shipper of radioactive material. Each year more than a million packages are transported in Canada. The safety record with the transport of RAM in Canada has historically been excellent. There have never been any serious injuries, overexposure or fatality or environmental consequences attributable to the radioactive nature of such material being transported or being involved in a transport accident. In Canada, the Canadian Nuclear Safety Commission (CNSC) is the prime agency of the federal government entrusted with regulating all activities related to the use of nuclear energy and nuclear substances including the packaging and transport of nuclear substances. The mission of the CNSC is to regulate the use of nuclear energy and materials to protect health, safety, security of the person and the environment and to respect Canada's international commitments on the peaceful use of nuclear energy. The division of responsibility for the regulation of transport of radioactive material has been split between Transport Canada and the CNSC. The governing Transport Canada's regulations are Transport of Dangerous Goods (TDG) Regulations and the CNSC regulations are Packaging and Transport of Nuclear Substances Regulations (PTNSR). Canada has actively participated in the development of the IAEA regulations for the safe transport of radioactive material since 1960. As an IAEA member state, Canada generally follows the requirements of IAEA regulations with few deviations. The Nuclear Safety and Control Act (NSCA) strongly supports Canada's international obligations to ensure safe packaging, transport, storage and disposal of nuclear substances, prescribed equipment and prescribed information. Prescribed equipment and prescribed information are defined in the CNSC General Nuclear Safety and Control Regulations. This paper presents the current CNSC regulatory requirements and initiatives taken by the CNSC to improve its effectiveness and efficiency

  17. Technical feasibility of a Dutch radioactive waste repository in Boom Clay : Tunnel crossings

    NARCIS (Netherlands)

    Yuan, Jun; Vardon, P.J.; Hicks, M.A.; Hart, J; Fokker, PA

    2017-01-01

    OPERA-PU-TUD321b
    Radioactive substances and ionizing radiation are used in medicine, industry, agriculture, re- search, education and electricity production. This generates radioactive waste. In the Neth- erlands, this waste is collected, treated and stored by COVRA (Centrale Organisatie Voor

  18. Environment assessing for airborne radioactive particulate release-introduction of methods in IAEA safety report series No.19

    International Nuclear Information System (INIS)

    Meng, Dan; Yang, Liu; Shen, Fu; Yang, Yi; Ma, Yinghao; Ma, Tao; Zhang, Zhilong; Fu, Cuiming

    2016-01-01

    Airborne radioactive particulate in many important nuclear facilities (particularly nuclear power plants) will have a strong impact on the relative public dose if they are released into the corresponding environment traversing the stack or vents. The radiation protection researchers have regarded the relative environment assessing and estimation of public doses. And the model of assessing impact of discharges radioactive substance to the environment have been recommended by many international organizations (e.g. IAEA) with the nuclear energy safety and radiation protection. This paper introduced the generic models that were suggested by International Atomic Energy Agency (IAEA), for use in assessing the impact of discharges of radioactive substances to the environment (e.g. IAEA Safety Report Series No.19). The writers of this paper, based on the recommend methods, assessed the discharge limits in some airborne radioactive substances discharging standards. The reasons that IAEA method are introduced are mainly the following considerations: IAEA is one of international organizations with some authorities in the nuclear energy safety and radiation protection; and, more important, the recommend modes are operational methods rather than the methods having little operations such as that have used by some researchers. It is wish that the introduced methods in this paper can be referenced in draft or revise of the standards related to discharges of radioactive substances to the environment

  19. Environment assessing for airborne radioactive particulate release-introduction of methods in IAEA safety report series No.19

    Energy Technology Data Exchange (ETDEWEB)

    Meng, Dan; Yang, Liu; Shen, Fu; Yang, Yi; Ma, Yinghao; Ma, Tao; Zhang, Zhilong; Fu, Cuiming [China Institute for Radiation Protection, Taiyuan (China)

    2016-12-15

    Airborne radioactive particulate in many important nuclear facilities (particularly nuclear power plants) will have a strong impact on the relative public dose if they are released into the corresponding environment traversing the stack or vents. The radiation protection researchers have regarded the relative environment assessing and estimation of public doses. And the model of assessing impact of discharges radioactive substance to the environment have been recommended by many international organizations (e.g. IAEA) with the nuclear energy safety and radiation protection. This paper introduced the generic models that were suggested by International Atomic Energy Agency (IAEA), for use in assessing the impact of discharges of radioactive substances to the environment (e.g. IAEA Safety Report Series No.19). The writers of this paper, based on the recommend methods, assessed the discharge limits in some airborne radioactive substances discharging standards. The reasons that IAEA method are introduced are mainly the following considerations: IAEA is one of international organizations with some authorities in the nuclear energy safety and radiation protection; and, more important, the recommend modes are operational methods rather than the methods having little operations such as that have used by some researchers. It is wish that the introduced methods in this paper can be referenced in draft or revise of the standards related to discharges of radioactive substances to the environment.

  20. Determination of the dispersion coefficient, in rivers through radioactive and fluorescent tracers

    International Nuclear Information System (INIS)

    Almeida Rosso, T.C. de.

    1986-03-01

    The purpose of this work was to determine experimentally the dispersion coefficient in natural streams through the aplication of radioactive and fluorescent tracers. The technique used to obtain the experimental data was the simmultaneous injection of the radioactive tracer Bromim - 82 and the fluorescent ones, Amidorodamine G. extra and Uranine. A comparison among these different tracers is shown as well as the performance of Uranine in a poluented stream in the presence of suspended sediments. The site chosen for the experiments was the Piabanha River, between Pedro do Rio and Areal, located at Rio de Janeiro state, in a nearly 20 Km strech. (Author) [pt

  1. Determination of Natural Radioactivity in Groundwater in Tanke ...

    African Journals Online (AJOL)

    User

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

  2. Zooplankton nutrition study under conditions close to natural with the use of radioactive phosphorus

    OpenAIRE

    Pavlovskaya, T; Zesenko, A

    1984-01-01

    Lack of a sensitive method for in situ study of the nutrition quantitative characteristics (and food balance in particular) for zooplankton populations in low-productivity regions was the reason for developing one. For the basis of such a method the authors selected the property of radioactive phosphorus isotopes of fast and effective embedding into all plankton components. The method described above allowed not only to quantitatively determine the consumption and transportation of a substanc...

  3. Ministerial Order of 24 April 1964 on the approval of types of devices containing radioactive substances, made in implementation of Section 3.1 d/2 of the Royal Order of 28 February 1963 embodying the General Regulations for the Protection of the Population and Workers against the Hazards of Ionizing Radiations

    International Nuclear Information System (INIS)

    1964-01-01

    This Order lays down that approval of devices containing radioactive substances and referred to in the Royal Order of 28 February 1963 embodying the General Regulations on Protection of the Population and Workers against the Hazards of Ionizing Radiations will only be granted if the total quantity of radioisotopes contained therein does not exceed certain values laid down by the 1963 Royal Order, and the radioactive substances are adequately shielded. It also lays down the procedure to be complied with for obtaining such approval and the conditions the applicant must meet to obtain the certificate of approval, which is valid for six years and may be renewed. The Ministry of Employment and Labour, Institute of Hygiene and Epidemiology, and the Ministry of Public Health and the Family are the competent authorities in respect of applications for a certificate of approval. Finally, suspension or withdrawal of the certificate or confiscation of the radioactive substances or devices do not give rise to compensation. (NEA) [fr

  4. Determination of annual limit of intake for long-lived radioactive dust

    International Nuclear Information System (INIS)

    Ching, S.H.; Horvath, F.J.

    1989-08-01

    A method for the determination of the annual limit on intake (ALI) for long-lived radioactive dust that is associated with every step in the uranium production process is proposed. It is based on methodology indicated in ICRP 26. A sample calculation for the ALI of fresh yellowcake is provided to assist in explaining this method

  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. Technical feasibility of a Dutch radioactive waste repository in Boom Clay : Plugs and seals

    NARCIS (Netherlands)

    Yuan, Jun; Vardon, P.J.; Hicks, M.A.; Hart, J; Fokker, PA

    2017-01-01

    Radioactive substances and ionizing radiation are used in medicine, industry, agriculture, re- search, education and electricity production. This generates radioactive waste. In the Neth- erlands, this waste is collected, treated and stored by COVRA (Centrale Organisatie Voor Radioactief Afval).

  7. DETERMINATION OF RELATED IMPURITIES IN THE ANILOCAINE SUBSTANCE BY HPLC METHOD

    Directory of Open Access Journals (Sweden)

    D. R. Sabirzyanov

    2017-01-01

    Full Text Available Anilocaine is a local anesthetic from the group of substituted amides, synthesized in the Perm State Pharmaceutical Academy. Anilocaine shows high surface anesthetic, infiltration and conduction anesthesia and shows the high efficiency in the various fields of medical practice. The quality of produced medicines depends on the quality of pharmaceutical substances. The purity is one of the most important parameters of the quality of pharmaceutical substances. The aim of this work was the development and validation of methods for identification of specific impurities in the substance of anilocaine by high-performance liquid chromatography (HPLC. Materials and methods. Studies were performed on liquid chromatography LC-20 Prominence (Shimadzu, Japan equipped with a diode-array detector (SPD-M20A. Chromatographic column was Zorbax SB-C18 (4.6 mm × 250 mm, 5 μm. Validation assessment of the developed method conducted in accordance with the requirements of FP XIII and international requirementsICH (International Conference on Harmonization. Results and discussion. An experiment on the selection of the conditions of chromatographically showed that optimal separation of anilocaine and possible impurities (identified and unidentified by the method of reversed-phase HPLC is observed in isocratic mode, using an eluent based on phosphate buffer pH 3 and acetonitrile. The flow rate of mobile phase is 1 ml/min; wavelength detection is 210 nm. Time check chromatogram is 20 minutes. Conclusion. The method for the quantitative determination of impurities in the substance of anilocaine by high-performance liquid chromatography was developed as the result of the research. The validation procedure of the analytical methods established its specificity, linearity, precision and accuracy. This method is included in the project monograph on substance of anilocaine.

  8. Influence of humic substances of fixation of fission products in silicate media

    Energy Technology Data Exchange (ETDEWEB)

    Shaban, I S; Macasek, F [Department of Nuclear Chemistry, Faculty of Natural Sciences, Comenius University, Bratislave, Slovakia (Slovakia)

    1997-12-31

    Clay minerals are exploited in both the land and sea emplacement and as backfill materials for the storage of radioactive waste to increase their radioactive safety. In addition, the influence of inorganic constituents, humic substances may modify the speciation of pollutant cations by solubilization of metal ions and formation of organic coating which may block the ion-exchange sites of clays. The objective of the present work was to characterize the effect of humic acid addition on the capacity of inorganic sorbents to radioactive caesium and strontium. Montmorillonite has been particular studied because the high cation exchange capacity and swelling properties make them sutiable for waste disposal. However, an accumulation of humic acid on disposal containers during the time of waste treatment may change the mobility of fission products. The results are treated in respect of sorption isotherms both of humic substances and sorbed ions. 3 figs., 3 tabs.

  9. Radioactive waste removing device

    International Nuclear Information System (INIS)

    Sakai, Takuhiko.

    1982-01-01

    Purpose: To cleanup primary coolants for LMFBR type reactors by magnetically generating a high speed rotational flow in the flow of liquid metal, and adsorbing radioactive corrosion products and fission products onto capturing material of a complicated shape. Constitution: Three-phase AC coils for generating a rotational magnetic field are provided to the outside of a container through which liquid sodium is passed to thereby generate a high speed rotational stream in the liquid sodium flowing into the container. A radioactive substance capturing material made of a metal plate such as of nickel and stainless steel in the corrugated shape with shape edges is secured within a flow channel. Magnetic field at a great slope is generated in the flow channel by the capturing material to adsorb radioactive corrosion products and fission products present in the liquid sodium onto the capturing material and removing therefrom. This enables to capture the ferri-magnetic impurities by adsorption. (Moriyama, K.)

  10. DETERMINING PARAMETERS OF THE DIELECTRIC FUNCTION OF A SUBSTANCE IN AQUEOUS SOLUTION BY SELF-REFERENCED REFLECTION THZ SPECTROSCOPY

    DEFF Research Database (Denmark)

    2008-01-01

    Method and apparatus for determining dielectric function of liquid solutions and thereby concentrations of substances in aqueous solution or the volatile/non-volatile nature of the liquid by self-referenced reflection THz spectroscopy. Having the aqueous solution in any container with a window al....... The invention is particularly useful for determining alcohol (ethanol) content in aqueous solution containing other substances and particles....

  11. Studies on the radioactivity of the atmosphere. [In French

    Energy Technology Data Exchange (ETDEWEB)

    Garrigue, H

    1951-01-01

    The existence in the atmosphere of a radioactive substance, labeled A, of several hours half life has been confirmed in flights at 3300 m, and at a ground station at 1460 m. Concentrations of Rn, Tn, A, and A' observed from March 15 to August 14, 1951, are tabulated. The concentration of substance A, of 20- to 30- hr half life, is related to atomic explosions and precipitation.

  12. Determination of radioactivity levels from some Egyptian building materials

    International Nuclear Information System (INIS)

    Abd EL Sattar, M.; Morsy, A.A.

    2007-01-01

    Our world is radioactive and has been, since it was created. Over 60 radionuclides (radioactive elements) can be found in nature. Radon is naturally occurring radioactive gas, that is produced by the radioactive decay of radium. Breathing high concentration of radon can cause lung cancer. A set of experiments were carried out using Cr-39 as solid state nuclear track detectors with the optimum etching conditions, 6.25 N Na OH at 70 o C for 8 hours. The radon-222 activity in this survey was found to be in the range of 0.303 kBq/m 3 to 5.04 KBq/m 3 for different building materials in Egypt

  13. Study on radioactivity in consumer goods

    International Nuclear Information System (INIS)

    1976-01-01

    Consumer goods containing radionuclides are increasingly utilized, sometimes for having chemical or technological properties which nonradioactive materials cannot fulfill (e.g. uranium paints) or it may be that radioactivity is especially required (e.g. fluorescent paints, fire-alarm-boxes, electronic instruments). The present study makes a compilation of consumer goods containing radioactive substances which are available to the general public in the nine countries of the Community, carries out a medium and long term study to assess how accumulated radiation from these goods could affect the population as a whole, and proposes measures to minimize the effects of such accumulation

  14. Actions of a protocol for radioactive waste management

    International Nuclear Information System (INIS)

    Sousa, Joyce Caroline de Oliveira; Andrade, Idalmar Gomes da Silva; Frazão, Denys Wanderson Pereira; Abreu, Lukas Maxwell Oliveira de; França, Clyslane Alves; Macedo, Paulo de Tarso Silva de

    2017-01-01

    Radioactive wastes are all those materials generated in the various uses of radioactive materials, which can not be reused and which have radioactive substances in quantities that can not be treated as ordinary waste. All management of these wastes must be carried out carefully, including actions ranging from its collection to the point where they are generated to their final destination. However, any and all procedures must be carried out in order to comply with the requirements for the protection of workers, individuals, the public and the environment. The final product of the study was a descriptive tutorial on the procedures and actions of a standard radioactive waste management protocol developed from scientific publications on radiation protection. The management of radioactive waste is one of the essential procedures in the radiological protection of man and the environment where the manipulation of radioactive materials occurs. The standard radioactive management protocol includes: collection, segregation of various types of wastes, transport, characterization, treatment, storage and final disposal. The radioactive wastes typology interferes with sequencing and the way in which actions are developed. The standardization of mechanisms in the management of radioactive waste contributes to the radiological safety of all those involved

  15. Relationships as determinants of substance use amongst street ...

    African Journals Online (AJOL)

    Background: Unrestrained exposure to street life often makes the street child vulnerable to psychoactive substances. In other settings, the social relationships of the substance user with those around him or her and family norms of parenting have been docu-mented to modulate use. However, there is a dearth of literature on ...

  16. Latest movements associated with radioactive contamination and disaster waste management (2)

    International Nuclear Information System (INIS)

    Omura, Tomomi

    2012-01-01

    As for the radioactive contamination countermeasures and disaster waste countermeasures taken for the accidents of the Great East Japan Earthquake and the Fukushima Daiichi Nuclear Station of Tokyo Electric Power Company, this paper introduces in the digest version the following movements from mid-April to May 15, 2012. (1) Radioactive substance countermeasures such as decontamination. (a) Decontamination operations under direct control of the Ministry of the Environment, (b) Establishment of compensation benchmarks by the Ministry of the Environment for the garden plants and land use in Special Decontamination Area, (c) Publication of technical guidelines by the Ministry of Agriculture, Forestry and Fisheries, on the removal and diffusion suppression of radioactive substances in forests, (d) Announcement of research center development / promotion idea by the government in the policy making for Fukushima reconstruction, (e) Request of the government for the interim storage facility site in the opinion exchange meetings in Futaba district towns and villages in Fukushima Prefecture, (f) Announcement of radioactive substance forecast map in Fukushima City for the first time by the government, and (g) Action plan development at the Health Anxiety Countermeasure Coordination Council for nuclear victims. (2) Disaster waste countermeasures. (a) Introduction of challenges in each of Miyagi Prefecture and Iwate Prefecture on the acceleration of the secondary temporary storage field development for disaster waste treatment, and (b) Introduction of progress in new interim incinerator construction plan for disaster waste treatment in Fukushima Prefecture. (O.A.)

  17. Rapid in situ gamma spectrometric determination of fallout radioactivity in the environment. Progress report

    International Nuclear Information System (INIS)

    Zombori, Peter

    1995-01-01

    The main aim of the present CRP is to identify the existing analytical methods and develop new ones, if possible, which provide rapid, reliable, and detailed information on the radioactive contamination of the environment after a major nuclear accident. Gamma spectrometry has long been regarded as one of the most applicable radioanalytical techniques but its use for environmental studies requires some further considerations. There are two possible approaches to measure environmental radioactivity: (a) taking samples of the different environmental media and measuring them in a laboratory or (b) taking the spectrometer to the place of interest and making in situ measurements. In the former case sampling is a crucial factor hindering the rapid analysis while the latter case is not always reliable due to the problems and uncertainties of the measurement interpretation. The application of in situ gamma spectrometry for the determination of environmental radioactivity has become increasingly attractive since the advent of the high resolution semiconductor gamma detectors, especially, more recently, portable high purity Ge diodes (HpGe). The applicability of this technique was very well proved after the Chernobyl reactor accident when in situ spectrometry played an important role in the rapid evaluation of the fall-out situation. Our measurements provided information on the amount and composition of the radioactive contamination of the ground surface already in the first hours. These measurements enabled us to predict the time variation of the environmental radioactivity after the stabilization of the situation. The portability of the system was an important factor in performing a rapid and efficient survey in different parts of the country. A serious disadvantage of this method is, however, that it requires some knowledge about the radionuclide distribution in the soil, which is normally determined by tedious and time consuming sample analysis of the different soil

  18. Humic substances in ground waters

    International Nuclear Information System (INIS)

    Paxeus, N.; Allard, B.; Olofsson, U.; Bengtsson, M.

    1986-01-01

    The presence of naturally occurring complexing agents that may enhance the migration of disposed radionuclikes and thus facilitate their uptake by plantsis a problem associated with the underground disposal of radioactive wastes in bedrock. The main purpose of this work is to characterized humic substances from ground water and compare them with humic substances from surface water. The humic materials isolated from ground waters of a borehole in Fjaellveden (Sweden) were characterized by elemental and functional group analyses. Spectroscopic properties, molecular weight distributions as well as acid-base properties of the fulvic and humic fractions were also studied. The ground water humic substances were found to be quite similar in many respects (but not identical) to the Swedish surface water humics concentrated from the Goeta River but appeared to be quite different from the American ground water humics from Biscayne Florida Aquifer or Laramie Fox-Hills in Colorado. The physico-chemical properties of the isolated humic materials are discussed

  19. Method of treatment in a system passing radioactive material

    Energy Technology Data Exchange (ETDEWEB)

    Kamiya, K; Kinoshita, M; Asakura, Y

    1976-05-14

    A method to ensure the safety of the reactor and reduce radiation exposure dose by preventing oxygen hydrogen reaction of the reactor off-gas and accumulation of the radioactive material is described. Substances which are accumulated in an off-gas duct and are likely to capture radioactive material (for instance Pd catalyst falling from a recombiner) is changed into a stable material (for instance, PdI/sub 2/) which is hot likely to capture radioactive material through reaction with a stabilizer (for instance, I/sub 2/, Cl/sub 2/, HCl, etc.). This stabilized material is washed off the atomic power plant system.

  20. 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.)

  1. Determinants of knowledge and use of psychoactive substance among commercial motorcyclist in Sokoto metropolis, Northwest Nigeria

    Directory of Open Access Journals (Sweden)

    M.O.Raji

    2017-01-01

    Full Text Available Background Substance abuse, also known as drug abuse, is a patterned use of a drug in which the user consumes the substance in amounts or with methods which are harmful to themselves or others, and is a form of substance related disorder. Riding commercial motorcycle entails lot of risk, compounded by abuse of drugs, the scenario can only be worse. This study aimed to assess the determinants of knowledge and use of psychoactive substances among commercial motorcyclist in Sokoto metropolis. Methods The study was a cross sectional descriptive study conducted in Sokoto metropolis, among Commercial motorcyclist, 253 respondents were recruited using multi stage sampling technique. Data was obtained using interviewer administered structured questionnaire containing 47‐item structured questions. Data was analysed using IBM statistical software package version 21, 5% was set as level of significance Result Majority of respondent believed that use of alcohol 214 (84.6, cannabis 147 (58.1 and codeine 171 (67.6 can lead to mental problems. Thirty percent of the respondents reported ever use of psychoactive substances. Most of the respondents (49.3% initiated use of Psychoactive substances between 16‐20 years of age. Respondents who had some formal education had less odds of ever using psychoactive substances (p=0.001, OR= 0.337. Respondents who had ever encouraged fellow commercial motorcyclist to use psychoactive substances had 22 times odds of ever having used psychoactive substances (p=0.000 Conclusion Substance abuse is prevalent among commercial motorcyclist. Despite good knowledge of psychoactive substances and the consequences associated with it, the use was still relatively high. The main predictor of ever use of psychoactive substances was willingness to be friends with someone who use psychoactive substance. There is need for continuous counselling and education of commercial motorcyclist, by road safety workers, on the dangers associated

  2. A study on environmental pollution caused by radioactive substances and its countermeasure techniques. Part 2. Present situation of radioactive pollution and decontamination

    International Nuclear Information System (INIS)

    Nozaki, Atsuo; Kakuma, Takayuki; Narita, Yasunori; Yoshino, Hiroshi

    2012-01-01

    In present research, in order to clarify the actual condition of contamination, the radioactive concentration of the soil and the plant in Koriyama city was measured. It turned out that the radioactive concentration of soil or plants were heavily polluted by caesium-134 and 137, and iodine-131 was already disappeared by its lifetime. Especially, cesium-134 + 137 was ranged 3400 Bq/kg at the surface of soil in garden, however, it was remarkably decreased in the deeper point at 10 cm and ranged 23 Bq/kg, and we cannot detect the cesium at 15 cm. It is necessary for people in Fukushima to decontaminate for reducing radioactivity level. And it turned out that the evergreen plants have been polluted at high radioactive concentration and decontamination by cutting down the plant was decreased by 14% average. Most of radioactive material is removed by removing soils. (author)

  3. Radioactive methionine: determination, and distribution of radioactivity in the sulfur, methyl and 4-carbon moieties

    International Nuclear Information System (INIS)

    Giovanelli, J.; Mudd, S.H.

    1985-01-01

    A simple and inexpensive method is described for isolation and determination of [ 14 C]methionine in the non-protein fraction of tissues extensively labeled with 14 C. The effectiveness of the method was demonstrated by isolation of non-protein [ 14 C]methionine (as the carboxymethylsulfonium salt) of proven radiopurity from the plant Lemna which had been grown for a number of generations on (U- 14 C]sucrose and contained a 2000-fold excess of 14 C in undefined non-protein compounds. An advantage is that the isolated methioninecarboxymethlysulfonium salt is readily degraded to permit separate determination of radioactivity in the 4-carbon, methyl and sulfur moieties of methionine. During this work, a facile labilization of 3 H attached to the (carboxy)methylene carbon of methioninecarboxymethylsulfonium salt was observed. This labilization is ascribed to formation of a sulfur ylid. (Auth.)

  4. Method of processing nitrate-containing radioactive liquid wastes

    International Nuclear Information System (INIS)

    Ogawa, Norito; Nagase, Kiyoharu; Otsuka, Katsuyuki; Ouchi, Jin.

    1983-01-01

    Purpose: To efficiently concentrate nitrate-containing low level radioactive liquid wastes by electrolytically dialyzing radioactive liquid wastes to decompose the nitrate salt by using an electrolytic cell comprising three chambers having ion exchange membranes and anodes made of special materials. Method: Nitrate-containing low level radioactive liquid wastes are supplied to and electrolytically dialyzed in a central chamber of an electrolytic cell comprising three chambers having cationic exchange membranes and anionic exchange membranes made of flouro-polymer as partition membranes, whereby the nitrate is decomposed to form nitric acid in the anode chamber and alkali hydroxide compound or ammonium hydroxide in the cathode chamber, as well as concentrate the radioactive substance in the central chamber. Coated metals of at least one type of platinum metal is used as the anode for the electrolytic cell. This enables efficient industrial concentration of nitrate-containing low level radioactive liquid wastes. (Yoshihara, H.)

  5. Treatment and storage of radioactive waste at a nuclear power plant

    International Nuclear Information System (INIS)

    1996-01-01

    The guide gives the general principles that shall be followed when planning and implementing the treatment, storing, transfer, activity monitoring and record keeping of radioactive wastes. The guide does not include provisions for spent fuel or for treatment and discharges of liquids or gases containing radioactive substances. Neither does the guide include any detailed design criteria for treatment facilities or storages. (4 refs.)

  6. Exemption and clearance of radioactive waste from non-nuclear industry: A UK regulator's perspective

    International Nuclear Information System (INIS)

    McHugh, J.O.

    1997-01-01

    In the UK radioactive substances are regulated by means of registrations and authorizations issued under the Radioactive Substances Act. For certain practices and types of radioactive materials, there are orders which allow exemption from registration/authorization, conditionally or unconditionally. The seventeen Exemption Orders in force cover a wide variety of types of radioactive materials and practices. Conditional Exemption Orders allow a degree of regulatory control without imposing undue burdens on users of radioactivity. For most orders, radiation doses to individuals would be about 1OμSv or less, and collective doses would be less than 1 man - Sievert. The UK is reviewing the exemption orders against the requirements of the 1996 Euratom Basic Safety Standards Directive. It intends to develop a coherent strategy for exemption and to rationalize the current orders. Recently there has been a degree of public concern over the release of items from the nuclear industry. Careful presentation of exemption and clearance concepts is necessary if public confidence in the regulatory system is to be maintained. (author)

  7. The issue of safety in the transports of radioactive materials; Le probleme de la securite dans les transports de substances radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Pallier, Lucien

    1961-11-20

    This report addresses and discusses the various hazards associated with transports of radioactive materials, their prevention, intervention measures, and precautions to be taken by rescuers, notably how these issues are addressed in regulations. For each of these issues, this report proposes guidelines, good practices, or procedures to handle the situation. The author first addresses hazards related to a transport of radioactive products: multiplicity of hazards, different hazards due to radioactivity, hazards due to transport modes, scale of dangerous doses. The second part addresses precautionary measures: for road transports, for air transports, for maritime transports, control procedures. The third part addresses the intervention in case of accident: case of a road accident with an unhurt or not vehicle crew, role of the first official rescuers, other kinds of accidents. The fourth part briefly addresses the case of transport of fissile materials. The fifth part discusses the implications of safety measures. Appendices indicate standards, and give guidelines for the construction of a storage building for radioactive products, for the control and storage of parcels containing radioactive products, and for the establishment of instructions for the first aid personnel.

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

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  9. A methodology for determining environmental threshold quantities for substances covered by CEPA's Environmental Emergency Regulation

    International Nuclear Information System (INIS)

    Ketcheson, K.; Shrives, J.

    2005-01-01

    Sections 199 and 200 of the Canadian Environmental Protection Act (CEPA) 1999 oblige persons who own or manage specified toxic and hazardous substances to develop and implement environmental emergency plans. This paper discussed the methodology for determining how a chemical is assessed for recommending an environmental emergency plan. For Section 199, once substances are declared toxic, each chemical is assessed to determine whether it requires a plan or not. For Section 200, any chemical can be added under the E2 regulations, as long as it can be ascertained that the substance is toxic according to the following criteria: it has an immediate or long-term harmful effect on the environment or its biological diversity; it constitutes a danger to the environment on which human life depends; and/or it constitutes a danger in Canada to human life or health. An overview of the risk evaluation framework was provided, including details of the pre-assessment filter. Summaries of trigger criteria were presented, as well as environmental hazard ratings and details of persistence of organic chemicals in the environment and bioaccumulation. Aquatic toxicity and ingestion toxicity details were also provided. Human hazard ratings included carcinogenicity, inhalation toxicity, dermal toxicity, rabbit and rat toxicity and corrosion and skin irritation ratings. Issues concerning vapour cloud explosions were examined. A reactivity table was presented with hazard descriptions. European Union Threshold quantities were examined, as well as a list of comparisons of selected substances of CEPA with the European Union. It was concluded that the Environmental Emergency Branch (EEB) has created environmental thresholds by first examining how other countries have protected the environment. Substance thresholds for the United States have focused on protecting humans, while Europe has established threshold quantities that work for their countries. The EEB has selected classification tables

  10. Development of very low-level radioactive waste sequestration process criteria

    Energy Technology Data Exchange (ETDEWEB)

    Chan, N.; Wong, P., E-mail: nicholas.chan@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

    2015-12-15

    Segregating radioactive waste at the source and reclassifying radioactive waste to lower waste classes are the key activities to reduce the environmental footprint and long-term liability. In the Canadian Standards Association's radioactive waste classification system, there are 2 sub-classes within low-level radioactive waste: very short-lived radioactive waste and very low-level radioactive waste (VLLW). VLLW has a low hazard potential but is above the Canadian unconditional clearance criteria as set out in Schedule 2 of Nuclear Substances and Devices Regulations. Long-term waste management facilities for VLLW do not require a high degree of containment and isolation. In general, a relatively low-cost near-surface facility with limited regulatory control is suitable for VLLW. At Canadian Nuclear Laboratories' Chalk River Laboratories site an initiative, VLLW Sequestration, was implemented in 2013 to set aside potential VLLW for temporary storage and to be later dispositioned in the planned VLLW facility. As of May 2015, a total of 236m{sup 3} resulting in approximately $1.1 million in total savings have been sequestered. One of the main hurdles in implementing VLLW Sequestration is the development of process criteria. Waste Acceptance Criteria (WAC) are used as a guide or as requirements for determining whether waste is accepted by the waste management facility. Establishment of the process criteria ensures that segregated waste materials have a high likelihood to meet the VLLW WAC and be accepted into the planned VLLW facility. This paper outlines the challenges and various factors which were considered in the development of interim process criteria. (author)

  11. Limitations on the concentration of radioactive elements substances (natural or enhanced by human activity) in building materials - a proposal for draft Israeli regulations

    International Nuclear Information System (INIS)

    Schlesinger, T.; Hareuveny, R.; Margaliot, M.

    1997-01-01

    Natural radioactive elements 40 K 228 U and 232 Th and their decay product such as 226 Ra and its short lived daughters occur in building materials in relatively high concentrations. 40 K and part of the above mentioned radionuclides cause external exposure while the inhalation of 222 Ra and its short lived progeny lead to internal exposure of the respiratory tract to alpha particles. In recent years there is a growing tendency to use new construction materials with naturally or technologically enhanced levels of radioactivity (e.g. phosphogypsum, fly ash, exotic minerals etc). This trend causes a growing health concern.The result of this concern is legislation activity and publication of guidance notes by national authorities and international professional organizations related to the radiological implications of these novel technologies. The Ministry of the Environment in Israel is authorized by Israeli legislation to control the exposure of the public to ionising radiation. The ministry asked in 1996 a professional group in the Radiation Protection Division in the Soreq NRC (the authors of this presentation) to study the radiological implications of the use of building materials with naturally or technologically enhanced concentrations of radioactive substances, and to submit draft regulations setting primary limits on excess exposure of the public to ionizing radiation from building materials, and derived limits related to concentrations of specific radionuclides in these materials.The draft regulations will be presented and the way of their derivation will be reviewed (authors)

  12. Determination of Isotopes Types and Activities in Radioactive Waste of Kosovo A Power Plant

    OpenAIRE

    , B Cena; , K Dollani; , G Hodolli

    2013-01-01

    The second nnportant event after the 1nventory of rad10act1ve waste 1n Kosovo, their location and the number of radioactive sources, is the determination of the type of radioisotope and their activities. This activity was conducted entirely in difŞcult terrain and was taken due to the absence in most cases of resource certiŞcates or any other document with the necessary information that will enable the identiŞcation of radioactive sources and their activity. In this way the activity was under...

  13. The work of the International Laboratory of Marine Radioactivity

    International Nuclear Information System (INIS)

    Walton, A.

    1981-01-01

    It is only during the past three decades that international interest has focused on the need to manage and nurture one of our most valued resources - the oceans. In spite of this growing recognition, however, it is only during the past ten years that international agreement has been reached on the control of dumping of wastes (including nuclear wastes) at sea. The International Laboratory of Marine Radioactivity was established in 1961 well before the international agreement came into force. Indeed the Laboratory came into existence as a result of the foresight and appreciation by the International Atomic Energy Agency of the need to attack the problem of the behaviour of radioactive substances in the oceans - a subject about which little was known prior to the 1950s. With the co-operation of the Government of Monaco and the Institut Oceanographique, the Laboratory was established in 1961 in the Musee Oceanographique, Monaco. It is appropriate that the Laboratory was established in a building created by one of the most prominent pioneers in oceanography - Prince Albert 1sup(er) of Monaco. Since 1961 the programme and activities of the Monaco Laboratory have expanded and changed with the changing emphasis in pollution problems in the oceans. Throughout the many changes in emphasis which have occurred during the past 20 years, however, it is probably fair to say that the broad objectives have remained the same. The Laboratory exists therefore: to perform research on the occurrence and behaviour of radioactive substances and other forms of pollution in the marine environment; to ensure the quality of the performance and comparability of studies of radioactive substances and other forms of pollution in the marine environment by national laboratories through inter-laboratory comparisons, calibration and standardization of methodology; to assist Member States with regard to marine radioactivity and environmental problems by training personnel, establishing co

  14. Device for treating plastic counting vials containing radioactive liquids

    International Nuclear Information System (INIS)

    Neidhart, B.; Brindoepke, H.W.; Flocke, W.; Kringe, K.P.; Lippmann, C.H.

    1985-01-01

    The treatment consists of separating the radioactive contents of the counting vial from its plastic components. The apparatus consists of a device for continuously supplying the counting vials to be treated, a means for crushing the vials into chips of plastic and a facility by means of which the radioactive contents of the counting vial and the separated plastic chips are collected separately from one another. A stirring assembly with a motor-driven stirrer and an alignment device are also provided. The radioactive substances pass through a sieve while the plastic chips slide down the sieve chute and into another container. All the metal parts of the facility are of stainless steel. The plastic chips collected in the sieve holder are washed and, after drying, are removed as negligibly radioactive solids. The weakly radioactive wash liquid is separated and collected. (orig./PW)

  15. Technical feasibility of a Dutch radioactive waste repository in Boom Clay : Thermo-hydro-mechanical behaviour

    NARCIS (Netherlands)

    Vardon, P.J.; Buragohain, Poly; Hicks, M.A.; Hart, J; Fokker, PA; Graham, C

    2017-01-01

    OPERA-PU-TUD321c
    Radioactive substances and ionizing radiation are used in medicine, industry, agriculture, re- search, education and electricity production. This generates radioactive waste. In the Neth- erlands, this waste is collected, treated and stored by COVRA (Centrale Organisatie Voor

  16. Determination of Natural Radioactivity in the North East Beach Sands of Madagascar

    International Nuclear Information System (INIS)

    Randriamora, T.H.; Razafindramiandra, H.A.; Raoelina Andraimbololona; Ravelomanantsoa, S.D.; Ralaivelo, M.A.L.; Rasolonirina, M.; Zafimanjato, J. L. R.; Randriantseheno, H.F.

    2017-01-01

    Exploration and exploitation of radioactive ores (ilmenite, zircon and monazite) are considered as the main source of exposure to ionizing radiation of the population living in the coast of Analanjorofo Region (Fenerive-Est Districts, Rural municipality Ampasimbe Manantsatrana). Radioactivity measurements have been performed in this region. The distribution of natural radionuclide gamma-emitters ( 238 U, 232 Th and 40 K) and their respective annual effective dose rates have been determined for sand(s), water and air. The samples have been collected along and around the coast of the region. The radiation emitted from the natural radionuclide containing in the environmental samples has been determined by gamma spectrometry system and Radon meter (SARAD). Exposure dose rates at 1 m above the ground have been measured along the coast and in the villages around the exploitation sites. Dose rate measurements have been performed by Dosimeter Graetz X5DE, equipped of Geiger Muller Counter. Results have been compared with the reference values provided by IAEA (BSS 115) and UNSCEAR 2000.

  17. The Use of Radioactive Gases in the Evaluation of Lung Function

    International Nuclear Information System (INIS)

    Maclntyre, W.J.; Inkley, S.R.

    1970-01-01

    This paper reviews methods for the evaluation of lung ventilation and perfusion based on measurements of the uptake of radioactive substances in the lung tissues after their respective administration by inhalation and injection. Radioactive substances used for such investigations include 133 Xe administered either by inhalation as a gas or by injection as a saline solution, 15 O 2 , C 15 O and C 15 O 2 administered by inhalation as gases and macroaggregated 131 I-labelled albumin administered by injection as a suspension. Methods used for the measurement of radioactivity in the lungs include methods based on the use of fixed multiple-detector systems, methods based on the use of single- or multiple-detector scanning systems and methods based on the use of gamma camera systems. In general, only relative measurements of radioactivity are required. The main physical problems in such measurements are shown to arise from uncertainty regarding the degree of absorption of the low-energy 133 Xe γ radiation in the body tissues and from the statistical errors inherent in the recording of fast dynamic changes. The radioisotope 135 Xe is shown to offer certain advantages over 133 Xe for the evaluation of lung function. (author)

  18. Measurement of the absolute activity of alpha or beta emitters by measuring product nuclei (daughter) activity increase or by studing its radioactive decay

    International Nuclear Information System (INIS)

    Campos, L.C. de.

    1981-01-01

    A new method for determining absolute activity of alpha or beta emitters by measuring daughter product radioactive decay is presented. The separation method of UX from hexahydrated uranyl nitrate UO 2 (NO 3 ) 2 6H 2 O based on its dissolution in ethyl ether is described and the accuracy of this method is shown. The factors which accuate on total efficiency of a Geiger Mueller detector for beta particles are determined. The possibility to determine the mass of precursor element by daughter nuclei activity is shown. The results are compared with the one obtained by direct measurement of the mass (or number of atoms) of precursor radioactive substance and with theoretical values calculated for isotopes in secular equilibrium. (Author) [pt

  19. 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)

  20. Radioactive waste and transport. Chapter 6

    International Nuclear Information System (INIS)

    1978-01-01

    A brief definition of the nature of radioactive waste is followed by a more detailed discussion of high level waste, its composition the amounts involved, storage in liquid and in solid form and the storage of non-reprocessed spent fuel. The final disposal of high level waste in deep geological structures is then described, based on the Swedish KBS study. The effectiveness of the artificial and natural barriers in preventing the radioactive substances from reaching the biosphere is discussed. American and Swedish risk analyses are briefly discussed, and practical experience presented. Low and medium level wastes are thereafter treated in a similar, though briefer manner. Transport of radioactive materials, fresh fuel, spent fuel and waste is then dealt with. Regulations for the containers and their tests are briefly presented and the risk of accidents, theft and sabotage during transport are discussed. (JIW)

  1. Nuclear plant refurbishment calls for patience. [Construction of radioactive effluent plant

    Energy Technology Data Exchange (ETDEWEB)

    Henly, Anna

    1989-08-01

    All nuclear power plants produce a small quantity of liquid effluent from wash hand basins, showers and surface drains on the site. The effluent is termed low-level radioactive waste and under the 'Radioactive Substances Act' can be discharged into estuaries or the sea. Before a controlled discharge can be made the effluent has to be chemically treated and have any radioactive particulate matter removed. The replacing of the radioactive effluent plant at the Berkeley nuclear power station in the United Kingdom is described, with particular reference to the vigorous safety standards and quality assurance programme operated by the Central Electricity Generating Board. (author).

  2. Methods of the conversion of radioactive wastes. Look into the past

    International Nuclear Information System (INIS)

    Rezchikov, D.

    2001-01-01

    In 1948 Government of the USSR made provisions to gear industrial complex for obtain Pu-239 in Chelyabinsk region. Making Pu-239 in metal form leaded to formation of big quantity of liquid radioactive wastes. It was impossible to provide cleaning water. The radioactive waste were put into Techa river till 1951. Many people lived near Techa and took big dose of radiation. It is very important that people did not know anything about behavior of the radioactive substances in the environment and action on the health. (authors)

  3. 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.

  4. Radioactivity in the Baltic Sea, 1999-2006 HELCOM thematic assessment

    International Nuclear Information System (INIS)

    Herrmann, J.; Ikaeheimonen, T.K.; Ilus, E.; Kanisch, G.; Luning, M.; Mattila, J.; Nielsen, S.P.; Osvath, I.; Outola, I.

    2009-01-01

    The report describes work carried out by HELCOM's (Helsinki Commission, Baltic Marine Environment Commission) project on the Monitoring of Radioactive Substances in the Baltic Sea (MORS-PRO) during the period 1999-2006. The main topics include: sources of man-made radioactivity in the Baltic Sea; levels of man-made radionuclides in seawater, sediments and biota; work on modelling and evaluations of the riks to man caused by radioactivity in the Baltic Sea; comparison of man-made radionuclides in the Baltic Sea with levels in other sea regions. The concequent recommendations and work on data quality are presented in the Appendix

  5. Compensation of damage caused by diverted nuclear substances

    International Nuclear Information System (INIS)

    Deprimoz, J.

    1981-10-01

    This paper provides a comprehensive analysis of the insurance system for nuclear liability. As a rule, if nuclear fuel, radioactive products or waste are governed by nuclear energy law providing for strict and channelled liability, their legal holder will pay for damage arising from them anywhere within 20 years after theft or diversion and 10 years after the nuclear incident. In most countries, atomic liability insurers will implicitly grant their cover through policies underwritten by legal holders. If diverted substances have a low specific radioactivity, their legal holder remains liable according to common law and insurance policies cover this conventional liability. (NEA) [fr

  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. Determination of 90Sr in low-level radioactive wastes using extraction chromatography and LSC

    International Nuclear Information System (INIS)

    Temba, Eliane S.C.; Reis Junior, Aluisio S.; Mingote, Raquel M.; Monteiro, Roberto P.G.

    2009-01-01

    A procedure for the determination of 90 Sr in low-level radioactive wastes is presented in this work. It is a part of a methodology developed for the sequential radiochemical separation of radionuclides in low-level radioactive wastes. These radionuclides comprises the actinides and 55 Fe, 63 Ni and 90 Sr, classified as difficult-to-measure (DTM) radionuclides in the radioactive waste characterization, because they cannot be measured by direct measurements, like gamma spectrometry. A variety of methods have been reported in the literature, based on precipitation, liquid-liquid extraction and ion exchange. In this work, the separation was carried out using precipitation and extraction chromatography using the Sr Resin (Eichrom). This resin is strontium-selective, the extractant is a crown ether-derivative immobilized on an inert polymeric support. The 90 Sr eluted from column was measured by LSC. The counting was carried out within 5 hours of the start of yttrium ingrowth to minimize interferences from 90 Y. The counting efficiency was calculated by using a 90 Sr standard solution purified by the specific resin. The chemical yield of the procedure was determined gravimetrically by the addition of a stable Sr carrier. Optimum conditions for the pretreatment, separation and LSC setting were determined using simulated samples. This procedure showed to be rapid and achieved a good chemical recovery, with an average of 84 %, and a detection limit of 0.6 Bq L -1 . (author)

  8. Experience with local lymph node assay performance standards using standard radioactivity and nonradioactive cell count measurements.

    Science.gov (United States)

    Basketter, David; Kolle, Susanne N; Schrage, Arnhild; Honarvar, Naveed; Gamer, Armin O; van Ravenzwaay, Bennard; Landsiedel, Robert

    2012-08-01

    The local lymph node assay (LLNA) is the preferred test for identification of skin-sensitizing substances by measuring radioactive thymidine incorporation into the lymph node. To facilitate acceptance of nonradioactive variants, validation authorities have published harmonized minimum performance standards (PS) that the alternative endpoint assay must meet. In the present work, these standards were applied to a variant of the LLNA based on lymph node cell counts (LNCC) run in parallel as a control with the standard LLNA with radioactivity measurements, with threshold concentrations (EC3) being determined for the sensitizers. Of the 22 PS chemicals tested in this study, 21 yielded the same results from standard radioactivity and cell count measurements; only 2-mercaptobenzothiazole was positive by LLNA but negative by LNCC. Of the 16 PS positives, 15 were positive by LLNA and 14 by LNCC; methylmethacrylate was not identified as sensitizer by either of the measurements. Two of the six PS negatives tested negative in our study by both LLNA and LNCC. Of the four PS negatives which were positive in our study, chlorobenzene and methyl salicylate were tested at higher concentrations than the published PS, whereas the corresponding concentrations resulted in consistent negative results. Methylmethacrylate and nickel chloride tested positive within the concentration range used for the published PS. The results indicate cell counts and radioactive measurements are in good accordance within the same LLNA using the 22 PS test substances. Comparisons with the published PS results may, however, require balanced analysis rather than a simple checklist approach. Copyright © 2011 John Wiley & Sons, Ltd.

  9. Removal of organics from radioactive waste. V. 2

    International Nuclear Information System (INIS)

    Williams, J.; Kitchin, J.; Burton, W.H.

    1989-05-01

    This report reviews the available literature concerning the removal of organic substances from radioactive waste streams. A substantial portion of low level wastes generated in the various parts of the nuclear fuel cycle, nuclear laboratories and other places where radionuclides are used for research, industrial medical and defense related activities is organic (paper, wood, plastics, rubber etc.) and combustible. These combustible wastes can be processed by incineration. Incineration converts combustible wastes into radioactive ashes and residues that are non-flammable, chemically inert and more homogenous than the initial waste. (author)

  10. Radioactive contamination of workers. General recommendation and procedures

    International Nuclear Information System (INIS)

    Mastro, N.L. del; Santos, O.R. dos; Silva, E.N.D.; Santos, A.J. dos.

    1987-09-01

    The present publication has an objective to provide data and information to be used by workers who handle with or eventually could enter in touch with radioactives substances. The authors have made a compilation of subjects got from the literature on several aspects about radiocontamination, physical and chemical characteristics of radioisotopes, main sources of radioactive contamination, biological basis and treatement of internal and external decontamination. Special attention was paid to iodine and actinides contamination, particularly to uranium and plutonium. The conclusion are presented as general recommendation and synoptic tables. (Author) [pt

  11. Methods of surveying and monitoring marine radioactivity. Report of an ad hoc panel of experts

    International Nuclear Information System (INIS)

    1965-01-01

    An effective control of the radioactive pollution of the sea depends partly on the availability of adequate technical methods for surveying and monitoring the sea and marine products with regard to the presence of radioactive substances. The purpose of this manual is to offer such methods.

  12. Determination of radioactive emission origins based on analyses of isotopic composition

    International Nuclear Information System (INIS)

    Devell, L.

    1987-01-01

    The nature of radioactivity emissions can be determined through gamma spectroscopy of air samples with good precision, which means that the type of source of the emission may be found, e.g. nuclear weapons test, of nuclear power plant accident. Combined with information on wind trajectories it is normally possible to recognize time and area for the emission. In this preliminary study, the knowledge of and preparedness for such measurements are described. (L.E.)

  13. Some observations indicating a low brain uptake of [3H]Nle11-Substance P

    International Nuclear Information System (INIS)

    Landgraf, R.; Klauschenz, E.; Bienert, M.; Ermisch, A.; Oehme, P.

    1983-01-01

    The studies concerning the problem of whether an exogenous neuropeptide is able to enter the brain tissue were extended to the undecapeptide Substance P (SP). The amount of radioactivity 15 s after intracarotid injection of [ 3 H]Nle 11 -SP or [ 14 C]inulin was determined in 18 brain regions and the anterior pituitary of male rats. As compared to the reference [ 14 C]inulin, the amount of radioactivity was higher after [ 3 H]Nle 11 -SP injection (0.233 +- 0.039%, p < 0.001). Statistically significant differences could be found particularly in cortical and caudal areas as well as in the circumventricular organs studied. These observations do not refute the assumption that a low brain uptake of the labelled neuropeptide occurred due to an accumulation within structures of the blood-brain barrier and/or a penetration of the barrier system. (author)

  14. Seepage determinations through auxiliary dike in Chingaza reservoir using radioactive tracers

    International Nuclear Information System (INIS)

    Sanches, L.; Obando, E.; Jimenez, G.; Torrez, E.

    1986-01-01

    Isotope techniques used in hydrology and developed during the last ten years in Colombia are usually tracer techniques based on the use of nuclides either introduced or naturally present in water. A problem of current content importance in hydraulics structures is seepage and the problems connected with it, such as impermeability of dams docks and their foundations. Many approaches are used to investigate these questions, but the simplest and most successful is the radiometric method. Radiometric observation of the flow of water through the earth dock involves introducing at a fixed point in the flow of water a radioactive solution and then following its movement downstream of the dock, and finding the place where it goes using appropriate detectors arranged at fixed control points. This paper describes the mean of choosing the injection points, the techniques for introducing radioactive solution and the conditions that must be borne in mind when selecting the radioisotope and determining its optimum activity. (author)

  15. Radioactive waste management in Tanzania

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  16. Management of radioactive waste generated in nuclear medicine; Gestion de los residuos radiactivos generados en medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lorenz Perez, P.

    2015-07-01

    Nuclear medicine is a clinical specialty in which radioactive material is used in non-encapsulated form, for the diagnosis and treatment of patients. Nuclear medicine involves administering to a patient a radioactive substance, usually liquid, both diagnostic and therapeutic purposes. This process generates solid radioactive waste (syringes, vials, gloves) and liquid (mainly the patient's urine). (Author)

  17. DETERMINATION OF THE HABITS OF ASTHMATIC PATIENTS ABOUT USING SUBSTANCE CONTAINING PERFUME

    Directory of Open Access Journals (Sweden)

    Ercan GOCGELDI

    2005-06-01

    Full Text Available Introduction: Air pollution, perfume, aerosol substances, odors of paint and detergent are the most important non-specific irritants stimulating the asthmatic attack. The odors of these substances exist for long time and form the serious risk for the asthmatic patients. This study was planned to determine the frequency of using perfume and substance containing perfume and the sensitivities to the substances among the asthmatic patients using inhaling steroid and b2-mimetic ant asthmatic drugs. Methods: This is a descriptive study and conducted among patients who applied to the Allergic Diseases outpatient service of Gulhane Military Medical Academia in October-December 2004. 83 asthmatic patients who accepted to participate to the study filled out a questionnaire that including patients habits relating perfume, cleaners with perfume, perfume for living room, toilets and bathrooms, and having dyspnea or not when exposed any kind of perfumes and using any b2-mimetik or not. Results: 73.5% (n=61 of participants were male, and 26.5 % (n=22 were women. Their ages were from 18 to 57 years. 79.5% (n=66 of participants expressed that they were sensitive to the odors mentioned and experienced the respiratory problems when they were at the surroundings by odour and 26.5% (n=22 of participants sometimes used the B2-mimetic antiasthmatic drugs for this reason. On the other hand; It was found that 68.7% (n=57 of participants regularly used the perfume for themselves everyday, 85.5% (n=71 of participants washed their clothings by using cleaners and/or softeners with perfume, 44.6% (n=37 of participants used the perfume for their rooms frequently, 62.7% (n=52 of participants used substance with perfume in their toilets and bathrooms. Conclusion: We conclude that the asthmatic patients have not sufficient knowledge about non-spesific irritants stimulating the asthmatic attack, and don’t behave sensitive. It’s important to plan properly the medical

  18. Determination of the gaseous emission of toxic substances in the Curva de Rodas sanitary landfill in Medellin

    International Nuclear Information System (INIS)

    Garcia Renteria, Francisco Fernando; Agudelo Garcia, Ruben Alberto

    2005-01-01

    Results of the investigation conducted at the sanitary landfill Curva de Rodas, aimed to determine the emission and migration of toxic substances are presented. Traces of benzene, toluene, hexane, vinyl chloride and xylene were found. Concentrations of these substances were, however, below threshold limits at the landfill and below detectable limits in the air of populated areas adjacent to the sanitary landfill

  19. 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

  20. Possibility of using radioactivity control measurements for determining contamination paths in nutritional vectors

    International Nuclear Information System (INIS)

    Garnier, A.

    1966-01-01

    The object of the report is to study the possibility of using results of radioactivity controls for determining the paths followed by contamination in nutritional vectors; these are necessary for calculating protection norms. Radioactive contamination of a nutritional vector is expressed in terms of parameters which suggest that a certain number of criteria may be used for choosing the results which are to be exploited. An actual example of a 'vertical' study based on results of measurements made purely for control purposes shows the difficulties which may be encountered. A list of the results obtained by the control networks set up in the Community Countries, either for the atmosphere, for milk, or for other foodstuffs, shows that these networks are not at the present organised in such a way as to make such a study possible. It appears desirable that a large part of the work carried out by the control Services be oriented in such a way as to yield the complementary information required for experimental studies of radioactive contamination transfers. (author) [fr

  1. Environmental Radioactivity from Natural, Industrial, and Military Sources

    International Nuclear Information System (INIS)

    Maarouf, B. H.

    2007-01-01

    This book is a translation of the fourth edition of the original book which was written as a reference source for the scientist, engineer, or administrator with a professional interest in the subject, but it may also be a value to the reader who wishes to understand the technical facts behind the public debate. The subject of environmental radioactivity has aspects of vast dimensions. The text of the book concerns primarily with the behavior of radioactive substances when they enter the environment. The important and elaborate technology by which passage of radioactive materials to the environment may be prevented and the equally important field of health physics that is concerned with protecting the atomic energy worker were thus placed beyond the bounds of this work.

  2. Determination of favorable conditions of detonation in liquid and solid substance mixtures

    International Nuclear Information System (INIS)

    Aubeau, Raymond; Carles, Maurice; Cochet Muchy, Bernard; Ducouret, Andre

    1976-03-01

    Theoretical methods or testing techniques may be employed to provide for possible detonations of chemical substances capable of interreactions. The theoretical methods are based upon the determination of the specific energy of possible mixtures and the system geometry. But the testing techniques are the only ones to insure whether a given mixture may detonate, deflagrate or to be inert. Different possible examples are given [fr

  3. 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)

  4. Determination of radiation exposure of humans due to dermal contact with radionuclides

    International Nuclear Information System (INIS)

    Pratzel, H.G.

    1992-01-01

    It is the aim of this research project to determine the distribution of radioactive substances in the skin and organism, in order to be able to predict from these data the radiation exposure to be expected following contamination of the skin with radionuclides. Further investigations are to be carried out into the suitability of measures of prevention and decontamination. In view of the fact that only small amounts of those compounds are absorbed by the skin, the determination of the parameters chosen was carried out in radionuclide studies in young pigs. With the exception of the skin of the palms and soles, the radiation effects in man could easily be extrapolated from the results of these experiments. The findings revealed permit the following conclusions to be drawn: The incorporation of radioactive substances after dermal contamination is quite unavoidable, even if this is immediately followed by decontamination measures. The degree of incorporation and resulting radiation dose are only minor and remain several orders of magnitude below the dermal radiation dose. If the skin is contaminated with radioactive liquids, the extent of incorporation and accumulation is proportionate to the activity concentration of those liquids. The incorporated radiation dose is in direct proportion to the contaminated skin area and also shows a relationship to the duration of contamination, if the skin is wet. The uptake by the organism may be somewhat reduced, if decontamination is initiated immediately. Dermal protectives may help to reduce skin permeability and, thus, the uptake of radioactivity into the corneal layer and follicles. (orig./MG) [de

  5. Order of 25 April 1979 fixing the list and the conditions for labelling and packaging certain dangerous substances and preparations

    International Nuclear Information System (INIS)

    1979-01-01

    This Order which is effective as from 1 November 1979 repeals the Order of 14 Sep 1972, as amended, fixing the list and conditions for labelling and packaging of certain dangerous substances and preparations and sets out a modified list and conditions. Such substances include certain radioactive substances. (NEA) [fr

  6. Methodology in the handling of the waste radioactive material

    International Nuclear Information System (INIS)

    Emeterio H, M.

    2013-10-01

    The methodology in the management of radioactive waste is constituted by an administrative part and seven technical stages: transport, classification, segregation, conditioning, treatment, packages qualification and final disposition (storage). In their diverse stages the management deserves a special attention, due to the increment of the use and application of the nuclear energy and radioactive substances, for such a reason should be managed in such a way that the exposed personnel safety and the public in general is guaranteed, protecting the integrity of the environment. (Author)

  7. Determination of radionuclide migration parameters through immobilised radioactive waste; Odredjivanje migracionih parametara radionuklida kroz imobilisani radioaktivni otpad

    Energy Technology Data Exchange (ETDEWEB)

    Plecas, I; Drljaca, J; Peric, A; Kostadinovic, A [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)

    1988-07-01

    In this paper are presented results obtained from leakage rate determination of specific radionuclides (Co-60, Cs-137, Mn-54, Sr-85) in PWR NPP waste. Measurements were carried out using original IBK-Vinca method. This method permits simulation of radionuclide leakage through multiple safety barriers in engineered tranches system for radioactive waste disposal. These results will be used for future Yugoslav radioactive waste storing center. (author)

  8. Simple determination of 99Tc in radioactive waste using Tc extraction disk and imaging plates

    International Nuclear Information System (INIS)

    Kameo, Y.; Katayama, A.; Hoshi, A.; Haraga, T.; Nakashima, M.

    2010-01-01

    A simple method was developed for determination of 99 Tc in low-level radioactive waste: Technetium-99 retained by a solid phase extraction disk was directly measured with imaging plates system. It was found that more than 97% of Tc were retained by the disk from a solution of pH 2 to 12, whereas depth profile of Tc in the disk, which greatly influences the counting efficiency, depended on solution pH. The present method was successfully applied to actual radioactive liquid waste samples arising from nuclear research facilities.

  9. α-amylase assay and action pattern determination using radioactive substrate, HPLC, and a radioactive flow detector

    International Nuclear Information System (INIS)

    Marsili, R.T.; Ostapenko, H.

    1987-01-01

    A new assay system is presented for the analysis of α-amylase. The disappearance of 14 C-labeled starch substrate and the appearance of its radioactive degradation products were monitored by HPLC and a radioactive flow detector/integrator. The hydrolysis of radioactive substrate was proportional to enzyme concentration when two commercially available α-amylase preparations of Bacillus subtilis origin were studied. The method demonstrated an average recovery of 101.7 +/- 6.5% when modified food starch was spiked with amylase and analyzed. In addition, the method was shown to be useful for predicting detailed action patterns of various types of amylases

  10. Natural radiation, radioactive waste and chemical risk determinants

    International Nuclear Information System (INIS)

    Christensen, T.; Mustonen, R.; Edhwall, H.; Hansen, H.; Soerensen, A.; Stranden, E.

    1990-01-01

    Doses from natural radiation to the population in the Nordic countries are summarized, and man-made modifications of the natural radiation environment are discussed. An account is given for the radiological concequences of energy concervation by reduced ventilation. Risks from possible future releases of radioactivity from final depositories of spent nuclear fuel are compared to the risks from present natural radioactivity in the environment. The possibilities for comparison between chemical and radiological risks are discussed. 104 refs., 36 figs., 47 tabs

  11. Information by the Federal Government. Report of the Federal Governement on 'Environmental radioactivity and radiation load in 1975'

    International Nuclear Information System (INIS)

    1977-01-01

    The report on environmental radioactivity and radiation load, to be published annually by the Federal government, contains data on artificial exposure from nuclear facilities, data on the application of radioactive substances and ionizing rays in research and technology, on occupational activities, medical application and special occurrences. Not only the annual release of radioactive substances from nuclear fcilities is presented but also data on the maximum permissible radiation exposures and the average gonadal exposure within the vicinity of plants. Furthermore, data is presented on the influence of X-ray investigations on the genetically significant dose as well as on the proportion in percent of the various radionuclides when applied in nuclear medicine. (ORU) [de

  12. The Control of Pollution (Radioactive Waste) Regulations 1976 of 10 June 1976

    International Nuclear Information System (INIS)

    1976-01-01

    The discharge into a public sewer of trade effluent is governed by the Control of Pollution Act 1974, under which water authorities in England and Wales have certain powers to regulate such discharges. These provisions have not however applied hitherto to radioactive waste, the disposal of which required mainly authorisation by the Minister of State for the Environment. Under the present Regulations, the 1974 Act will apply to radioactive waste so as to give water authorities control over liquid discharges into their sewers, notwithstanding that they contain radioactive waste while the powers of the Minister of State are maintained regarding control and disposal of the radioactive parts of such waste under the 1960 act on Radioactive substances. (N.E.A.) [fr

  13. Changes is radioactive iodine metabolism in acute chemical intoxications

    International Nuclear Information System (INIS)

    Selyutitskij, G.V.; Likhtarev, I.A.; Volkova, N.V.; Zvonova, I.A.; Ostryakova, N.I.

    1978-01-01

    It is shown that the response of the endocrine system (iodine-absorbing and hormone-secreting fUnctions of the thyroid) as studied by the radioactive iodine test may be a reasonably versatile indicator of the response of the thyroid component of the endocrine system to acute intoxication of the organism. Trials of this test using seven chemical substances have confirmed that the radioiodine test is a sufficienty universal method to be used in setting sanitary and hygienic standards for permissible levels of chemical substances

  14. Radioactivity handbook. Volume 2: radioactive disintegrations, radiations-matter interactions, applications of radioactivity

    International Nuclear Information System (INIS)

    Foos, J.; Bonfand, E.; Rimbert, J.N.

    1994-01-01

    This volume is the second one of a group of three. The first one exposed nuclides, with neutrons and protons in a stable building: atomic nucleus. Here is the second one with unstable, radioactive nucleus. After the description of different kinds of disintegrations, it is justified to follow radiations in matter and modifications attached to them; different uses of radioactivity are developed in medicine, age determination, industrial utilization and biology

  15. Incineration of radioactive wastes containing only C-14 and H-3

    International Nuclear Information System (INIS)

    Garcia, Corazon M.

    1992-01-01

    C-14 and H-3 arc popularly used in chemical and biological research institutions in the Philippines. Most of the solid radioactive wastes generated by these institutions consist of combustible materials such as paper and accumulated environmental samples. Liquid wastes usually contain organic substances. The method proposed for managing C-14 and H-3 wastes is incineration which is expected to provide an acceptable means of disposal for C-14 and H-3 and their hazardous organic constituent. In the incineration process) the radioactively contaminated waste will be mixed with non-radioactive combustible wastes to lower the activity concentration and to improve the efficiency of combustion which will be carried out in a locally fabricated drum incinerator. The calculations presented determines the concentration limit for the incinerable wastes and the restriction on specific activity of the particles of the incinerable wastes containing C-14 or H-3 on the basis of the accepted air concentration and on the annual dose limit for an average radiation worker in the country. In the calculations for C-14, considerations were taken on the exposure received from the deposition of radioactive particles in the lungs containing unoxidized carbon. Calculations for H-3, however, is based on the assumption that the concentration of the radionuclide in the body water is the same as that in the environment. (author)

  16. Partial sequence determination of metabolically labeled radioactive proteins and peptides

    International Nuclear Information System (INIS)

    Anderson, C.W.

    1982-01-01

    The author has used the sequence analysis of radioactive proteins and peptides to approach several problems during the past few years. They, in collaboration with others, have mapped precisely several adenovirus proteins with respect to the nucleotide sequence of the adenovirus genome; identified hitherto missed proteins encoded by bacteriophage MS2 and by simian virus 40; analyzed the aminoterminal maturation of several virus proteins; determined the cleavage sites for processing of the poliovirus polyprotein; and analyzed the mechanism of frameshifting by excess normal tRNAs during cell-free protein synthesis. This chapter is designed to aid those without prior experience at protein sequence determinations. It is based primarily on the experience gained in the studies cited above, which made use of the Beckman 890 series automated protein sequencers

  17. Method for purification of environmental objects, contaminated with radioactive substancesas a result of natural disasters

    International Nuclear Information System (INIS)

    Mammadov, Kh.; Shiraliyeva, Kh.; Mirzayev, N.; Garibov, R.; Allahverdiyev, G.; Aliyeva, U.; Farajova, A.

    2017-01-01

    Numerous sources of different radioactive substances, irradiating installations are used in many manufacturing, transportation, industrial, oil-producing, nuclear energy, sterilization and multi-purpose scientific research enterprises of Azerbaijan and the storage of radioactive waste and nuclear materials is built in the territory of special plant of the Ministry of Emergency Situations.Control of safety of operational procedures of the radioactive sources and samples of nuclear materials is carried out by the State Agency on Settlement of Nuclear and Radiological Activity at the Ministry of Emergency Situations. An increase in the concentration of inorganic and organic xenobiotics was observed in water samples taken from the transcontinental Araz River.The territory of Azerbaijan and Armenia is characterized by high seismic activity. Therefore, the occurrence of cases of anthropogenic catastrophe, the spread of radioactive substances, nuclear materials and waste on the territory of environmental objects, disturbance of tightness of installations on electricity generation from nuclear fuel in the Metsamor NPP, emission of radioactive fuel on the environment, pollution of grounds and water reservoirs by radioactive isotopes isn't excluded in case of natural disasters.Complex studies were conducted to determine the radioactive background, exposure dose rate, the radiation intensity of all types of radioactive radiation (α, β, γ, UV and X-rays) for purification of contaminated areas of the environment, soil, water reservoirs from radioisotopes. Complex organoleptic, radiochemical, analytical-chemical, physical-chemical and microbiological studies were carried out to study the chemical composition and degree of contamination of soil, water sources, vegetation by inorganic and organic xenobiotics and radioisotopes in all regions of the republic.Mineralization of water samples /evaporation/, soil /extraction with distilled water in a ratio of 1: 4, filtration

  18. Determination of radioactive materials in granite used as ornamental rocks; Determinacao de materiais radioativos em granitos utilizados como rochas ornamentais

    Energy Technology Data Exchange (ETDEWEB)

    Salas, Humberto Terrazas; Barbosa, Joao Batista Santos; Murta, Clecio Campi; Rocha, Francisco de Assis [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil)). E-mail: salasht@urano.cdtn.br; Nalini Junior, Herminio Arias; Mendes, Julio Cesar [Ouro Preto Univ., MG (Brazil). Escola de Minas. Dept. de Geologia

    2000-07-01

    For environment quality control, either in a global or regional perspective, the determination of the radioactivity present in the minerals of rocks must be included. This control is carried out through specific analysis, applied to all geological materials used in civil architecture design and other applications (e.g. artistic). To date, the radioactivity of rocks has not been specifically studied, from which an adequate and comprehensive systematics is applied, in order to determine the radioactive minerals and their corresponding alterations. In Brazil, the industry of ornamental rocks is continually increasing at high rates, with a growing variety of rocks being commercialized locally as well as abroad. To a certain extent, the technical characterization of these rocks, through standard procedures defined by standardization institutions, is already available worldwide. However, among the petrographic properties specified for these rocks, minor or accessory minerals (less than 1%) are not adequately determined and detected. Among these components are radioactive minerals and, occasionally, carriers of precious metals, rare earths and other economically important minerals. (author)

  19. Radioactive fallout has different effects in Lapland

    International Nuclear Information System (INIS)

    Rissanen, K.

    1993-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1981-11-15

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

  1. Use of Formal Procedures in Developing Dialogue Between Operator and Regulator on Radioactive Waste Disposal

    International Nuclear Information System (INIS)

    Yearsley, Roger; Duerden, Susan; Bennett, David

    2001-01-01

    The Environment Agency (the Agency) is responsible, in England and Wales, for authorisation of radioactive waste disposal under the Radioactive Substances Act 1993. British Nuclear Fuels plc (BNFL) is currently authorised to dispose of solid low level radioactive waste at its Drigg site near Sellafield in Cumbria. Drigg is the primary site for the disposal of solid low level radioactive waste generated by the UK nuclear industry. A small facility operated by United Kingdom Atomic Energy Authority (UKAEA) at Dounreay on the north coast of Scotland is used solely for wastes arising on the UKAEA site. Drigg also offers a disposal route for smaller users of radioactive substances, such as hospitals and universities. Significant benefits have been derived from implementing a formal Issue Resolution Procedure as part of a soundly based process for dialogue between the Agency and BNFL. Benefits include improved understanding of the Agency's expectations, which has in turn led to improvements in BNFL's documentation and technical approach. The Agency considers the use of a formal Issue Resolution Procedure has placed the dialogue with BNFL on firm foundations for the planned assessment of the PostClosure Safety Case for Drigg when it is submitted in September 2002

  2. Royal Order of 27 July 1966 relating to the reciprocal recognition of licences for the import, transport, transit, and distribution of radioactive substances between the countries of the Benelux Economic Union

    International Nuclear Information System (INIS)

    1966-01-01

    This Royal Order made taking into account the 1958 Act on protection of the population against the hazards of ionizing radiations, the 1963 Royal Order embodying the general regulations on protection of the population and workers against the hazards of ionizing radiations and the 1966 recommendation of the Committee of Ministers of the Benelux Economic Union lays down that, notwithstanding Section 38 and 57 of the 1963 Royal Order, licences for the import, transport and transit of radioactive substances or devices containing them which are issued by the competent authorities of the Netherlands or Luxembourg are valid in Belgium. Also, a Belgia distributor of such substances or devices containing them must ensure that a consignee residing in either of these countries holds the licences required by his national law. (NEA) [fr

  3. Radioactive material in the radiologically contaminated fishes caught in the Pacific Ocean in 1954

    Energy Technology Data Exchange (ETDEWEB)

    Saiki, M; Okano, S; Mori, T

    1955-01-01

    The radioactivity of several samples of Coryphaena Hippyrus caught in the southern Pacific in May, 1954, after the atomic explosion at Bikini, was found, in decreasing order, in spleen, kidney, liver, pyloric ceca, heart, gill, intestine, gastric wall, ovary, testis, gastric content, red muscle, skin, vertebrae, and muscle. The red muscle of Neothunnus Macropterus showed 54.8 counts/min./0.20 g. activity on dry basis, the activity was decreased to 27.6 by soaking 25 g. muscle in 25 cc. water, and to 14.1 by soaking in 0.5% Na ethylenediaminetetraacetate solution. The radioactive substances in these fish tissues were found, upon analysis, to belong to the III group, particularly to III-B group. Examination of synchroscope patterns by scintillation counter indicated the presence of /sup 65/Zn among the radioactive substances. /sup 90/Sr was suggested to be present in very small amount.

  4. A survey of radioactive levels of agricultural products in Saitama prefecture

    Energy Technology Data Exchange (ETDEWEB)

    Motegi, Misako; Miyake, Sadaaki; Oosawa, Takashi; Nakazawa, Kiyoaki [Saitama Inst. of Public health, Saitama (Japan)

    1997-09-01

    Past atmospheric nuclear testing which have been conducted frequently, have caused environmental pollution due to the diffusion of radioactive substances into the atmosphere and from the radioactive fallout. The environmental pollution from nuclear testing into the atmosphere has resulted in the radioactive contamination in agricultural products and has continued for a long time. The radioactive contamination of agricultural products occurs through air, water and soil which were contaminated by radioactive fallout. In this paper, for the purpose of analyzing the extent of the radioactive contamination levels in the agricultural products of Saitama Prefecture, spinach, green soybeans, dried shiitake and welsh onion, were selected among products, as the amount of the harvest is abundant in all of Japan. Radioactivity concentration was investigated by gamma-ray spectrometry and radiochemical analysis. The radioactivity concentrations of artificial radioactive nuclides, cesium-137 ({sup 137}Cs) and strontium-90 ({sup 90}Sr), were detected in the range which is considered to be the result of radioactive fallout. Moreover, in order to examine the effect on radioactivity concentrations in agricultural products by culinary processing, the raw agricultural products were boiled, and their radioactivity concentrations were compared with the raw produce. The radioactivity concentrations in the boiled were lower than those in the raw produce. (author)

  5. A survey of radioactive levels of agricultural products in Saitama prefecture

    International Nuclear Information System (INIS)

    Motegi, Misako; Miyake, Sadaaki; Oosawa, Takashi; Nakazawa, Kiyoaki

    1997-01-01

    Past atmospheric nuclear testing which have been conducted frequently, have caused environmental pollution due to the diffusion of radioactive substances into the atmosphere and from the radioactive fallout. The environmental pollution from nuclear testing into the atmosphere has resulted in the radioactive contamination in agricultural products and has continued for a long time. The radioactive contamination of agricultural products occurs through air, water and soil which were contaminated by radioactive fallout. In this paper, for the purpose of analyzing the extent of the radioactive contamination levels in the agricultural products of Saitama Prefecture, spinach, green soybeans, dried shiitake and welsh onion, were selected among products, as the amount of the harvest is abundant in all of Japan. Radioactivity concentration was investigated by gamma-ray spectrometry and radiochemical analysis. The radioactivity concentrations of artificial radioactive nuclides, cesium-137 ( 137 Cs) and strontium-90 ( 90 Sr), were detected in the range which is considered to be the result of radioactive fallout. Moreover, in order to examine the effect on radioactivity concentrations in agricultural products by culinary processing, the raw agricultural products were boiled, and their radioactivity concentrations were compared with the raw produce. The radioactivity concentrations in the boiled were lower than those in the raw produce. (author)

  6. Design basis for the safe disposal of radioactive waste

    International Nuclear Information System (INIS)

    Lewi, J.; Kaluzny, Y.

    1990-01-01

    All radioactive waste disposal sites, regardless of disposal concept, are designed to isolate the radioactive substances contained in such waste for a period at least equal to the time it may remain potentially harmful. Isolation is achieved through the use of containment barriers. This paper summarises the function and limits of different types of barrier used in various disposal systems. For each type of barrier, the paper describes and comments on the site selection criteria and waste packaging requirements applicable in various countries. 13 refs., 1 fig [fr

  7. Key radionuclides and parameters that determine performance of geologic repositories for high-level radioactive wastes

    International Nuclear Information System (INIS)

    Joonhong Ahn; Atsuyuki Suzuki

    1993-01-01

    This paper presents results of a mathematical analysis for performance of the engineered barriers of high-level radioactive waste repositories. The main body of the mathematical model developed in this study is mass transport of actinides in a bentonite region. In an analysis of actinide transport, radioactive decay chain and effects of low solubilities must be taken into account. In many previous models for mass transport in engineered barriers including radioactive decay chain, however, boundary conditions at the interface between the waste form and the bentonite region cannot be determined flexibly. In some models, solubility-limited boundary condition is assumed for all the members in a chain. In order to investigate what are key radionuclides and parameters that control performance of engineered barriers of a geologic repository, we must evaluate mass transport with the source boundary condition determined by a detailed analysis on mass transfer at the boundary. In this study, we developed a mathematical model, which can determine whether the inner boundary condition is solubility-limited or congruent release, based on a mathematical analysis for mass transfer at the glass dissolution location, and how long the solubility-limited boundary condition applies. Based on the mathematical model, we point out radionuclides and parameters that have primary influences on the performance of a repository, and investigate a reasonable strategy for coupling geologic disposal and partitioning of those key radionuclides from the standpoint of reducing hazard of geologic disposal. (authors). 4 tabs., 2 figs., 8 refs

  8. Radioresistance of aboriginal earthworms of Absheron peninsula in radioactive model systems

    International Nuclear Information System (INIS)

    Suleymanova, A.S.; Garibov, A.A.; Abdullayev, A.A.; Naghiyev, J.A.; Farajov, M.F.; Samedov, P.A.

    2011-01-01

    Full tex:Soil animals are the most suitable biological indicators of radioactive pollution because they are parts of nutritional chains and webs, occur in relatively high numbers and can be collected during most parts of the year.The use of earthworms in the soils from Ramana iodine plant area of Absheron peninsula, which is rich with radionuclide and in the soil mixed with RaCl2 and UO2SO4 salt solutions in different concentrations, for resistance to ionizing radiation in soil is reviewed.Effect of radionuclides on vital functions of earthworms and determination of radionuclides (before and after experiments) in contaminated soils by ?-spectrometer were carried out in laboratory condition during a month. Regarding to ?-spectrometric results there were determined that earthworms had absorbed most of radioactive elements and allocated them as coprogenous substances on the upper layer of soil. In Ramana soils mostly the 238U radionuclides were highly accumulated in gut cells of the earthworms. By the influence of radioactive elements it was shown that the earthworms from Ramana iodine plant territory variants had proved particularly sensitive to an increased Ra-radiation background and to iodine factor.It was interestingly established the proportional dependence between rising level of accumulation in earthworms' body and in their coprolites and increasing of radioactive salts containing in the soils treated by UO2SO4 and RaCl2 solutions.Thus there is different level of radioresistance for earthworms and they are among the best bioindicators of polluted soils. There was an obvious perspective of using of earthworms as bioremediators in polluted soil with radionuclides in future as well.

  9. Report of radioactivity investigation and research in fiscal year 1984

    International Nuclear Information System (INIS)

    1985-11-01

    National Institute of Radiological Sciences has continuously carried out the investigation and research on the environmental radioactivity level due to the radioactive fallout accompanying nuclear explosion experiments and the radioactive substances released from nuclear facilities and on the safety analysis of those since fiscal year 1959 as a part of the radioactivity investigation and research of Science and Technology Agency. The importance of radioactivity investigation and research increases more accompanying the remarkable progress of the peaceful use of atomic energy and the emphasis placed on the safety analysis of atomic energy utilization. In such situation, in fiscal year 1984, by appropriating the total budget of about 105 million yen, the investigation of the radioactivity level and dose in environment, foods and human bodies, the investigation of the level around nuclear facilities, the business of radioactivity data center, the basic research on the evaluation of the results of radioactivity investigation, the training of environmental radiation monitoring technicians, and the investigation and research on the measurement of and countermeasures to emergency radiation exposure were carried out. In this book, the results of these investigation and research are reported. (Kako, I.)

  10. Process for dissolving the radioactive corrosion products from internal surfaces in nuclear reactors

    International Nuclear Information System (INIS)

    Brown, W.W.

    1976-01-01

    This invention concerns a process for dissolving in the coolant flowing in a reactor the radioactive substances from the corrosion of the internal surfaces of the reactor to which they cling. When a reactor is operating, the fission occurring in the fuel generates gases and fission substances, such as iodine 131 and 133, cesium 134 and 137, molybdenum 99, xenon 133 and activates the structural materials of the reactor such as nickel by giving off cobalt 58 and similar substances. Under this invention an oxygen rich solution is injected in the reactor coolant after the temperature and pressure reduction stage, during the preparation prior to refuelling and repairs. The oxygen in the solution speeds up the release of cobalt 58 and other radioactive substances from the internal surfaces of the reactor and their dissolving in the oxygenated cold coolant at the start of the cooling procedures of the installation. This allows them to be removed by an ion exchanger before the reactor is emptied. By utilising this process, about half a day may be gained in refuelling time when this has to be done once a week [fr

  11. 30 years of monitoring environmental radioactivity in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    1985-01-01

    The individual sections of the report describe the development of monitoring functions and of the contamination of the atmosphere and the biosphere by radioactive substances. After environmental radioactivity due to the fallout of nuclear explosions reached a peak level in 1963, its contribution to radiation exposure today is insignificant in comparison with natural radioactivity. Moreover, monitoring by authorities of the emissions and the environmental impact of nuclear installations has been extended during the past 20 years in such a way that the existing network of measuring stations takes full account of the increased number of nuclear installations. The monitoring results show that nuclear installations do not make any considerable contribution to environmental radioactivity. (orig./PW) [de

  12. The design, construction and testing of packaging[Radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-07-01

    Essentially uniform regulations, based on the IAEA Regulations for the Safe Transport of Radioactive Materials, have been adopted on a world-wide basis with the aim of ensuring safety in the transport of radioactive and fissile substances by road, rail, sea and air. The application of these regulations over a period of almost 20 years has resulted in practically complete safety in the sense that there has been no evidence of death or injury that could be attributed to the special properties of the material even when consignments were involved in serious accidents. In the regulations, reliance is placed, to the greatest extent possible, on the packaging to provide adequate shielding and containment of the contents under both normal transport and accident conditions. The Agency organized an international seminar in 1971 to consider the performance tests that have to be applied to packaging to demonstrate compliance with the regulatory requirements. The general conclusion was that the testing programme specified in the regulations was adequate for the near future, but that further consideration should be given to assessing the risks presented by the increasing volume of transport. The second international seminar, which is the subject of this report, dealt with all aspects of the design, construction and testing of packaging for the transport both of relatively small quantities of radioactive substances, which are being used to an ever increasing extent for medical and research purposes, and of the much larger quantities arising in various stages of the nuclear fuel cycle. The programme covered the general requirements for packaging; risk assessment for the transport of various radioactive and fissile substances, including plutonium; specific features of the design and construction of packaging; quality assurance; damage simulation tests, including calculational methods and scale-model testing; tests for the retention of shielding and containment after damage; and the

  13. Diagnostic value of radioactive fibrinogen and rheography in phlebitis

    International Nuclear Information System (INIS)

    Serradimigni, A.; Bory, M.; Djiane, P.; Sacerdote, P.; Mathieu, P.; Leonetti, J.; Egre, A.

    1975-01-01

    In 212 patients the diagnostic value of radioactive fibrinogen and rheography in deep venous thrombosis in the leg was studied by comparing the results from these two methods with phlebography. Radioactive fibrinogen seems the better means of diagnosis in early distal phlebitis. However, the method is expensive, the radioactive substance can only be manipulated in certain specialized centers, and is useless in the presence of hematoma. Rheography is less expensive, more easily manipulated, yet less sensitive as only proximal phlebitis can be detected especially when completely occlusive. In addition, active patient cooperation is necessary. The time needed to realize the two methods is a major obstacle; however, they can be fruitful if integrated into a specialized department for the diagnosis and treatment of thrombo-embolic disease [fr

  14. Radioactive fall out in Switzerland. Where does it come from and where does it go to

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    This article describes the radioactive radiation to which the Earth is subjected by the Sun, the natural and man made radioactive substances on the Earth which are identical in their action, discusses the benefits that certain radioactive isotopes can provide in medicine, industry, agriculture and scientific research and deals with protective measures against harmful radioactive materials. After a description of the means of obtaining uranium and plutonium and their use in the production of nuclear energy the article discusses the research being performed to ensure that radioactive materials are safely handled and that unusable waste is deposited in safe places. (G.W.)

  15. 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)

  16. Lessons to be learned from radioactive waste disposal practices for non-radioactive hazardous waste management

    International Nuclear Information System (INIS)

    Merz, E.R.

    1991-01-01

    The criteria to be set up for any kind of hazardous waste disposal must always be put in perspective: 1. what are the waste characteristics? 2. what time period for safe isolation is of interest? 3. which geological disposal alternatives exist? Different approaches may be used in the short- and long-term perspective. In either case, a general procedure is recommended which involves concentrating, containing and isolating the source of toxicity, both radioactive and chemotoxic substances, as far as practicable. Waste characterization of either chemotoxic or radioactive wastes should be performed applying comparable scientifically based principles. The important question which arises is whether their hazard potential can be quantified on the basis of dose comparison regarding the morbidity effects of radiation and of chemical pollutants. Good control over the consequences of hazardous waste disposal requires threat detailed criteria for tolerable contamination of radioactive as well as chemical pollutants should be established, and that compliance with these criteria can be demonstrated. As yet, there are no well developed principles for assessing the detriment from most types of genotoxic waste other than radioactive material. The time horizon discussed for both categories of waste for their proof of safe isolation differs by a factor of about one hundred. (au)

  17. HMIP monitoring programme: radioactive substances report for 1990

    International Nuclear Information System (INIS)

    1992-03-01

    Discharges of radioactive wastes to the environment can only be made under authorisation from government bodies. The main potential sources of environmental contamination in England are nuclear sites (power stations, fuel fabrication and reprocessing plants), some industrial premises such as metal smelters, and landfill sites. As well as the environmental monitoring programmes undertaken by the operators of such sites various government bodies also undertake monitoring. In January 1988 Her Majesty's Inspectorate of Pollution (HMIP) initiated a programme to monitor exposure of the public from non-food pathways such as could occur from occupation of beaches, river banks etc. Radiation levels and radiochemical and gamma spectra of samples collected at specified locations near nuclear sites and industrial premises have been monitored every quarter since then. The results for 1990 are presented and discussed. (UK)

  18. Hazard of radioactive releases resulted from coal burning; Opasnost` vysvobozhdeniya radioaktivnykh produktov pri szhiganii uglya

    Energy Technology Data Exchange (ETDEWEB)

    Gabbard, V

    1995-09-01

    Consideration is given to the data, pointing to the fact, that coal-burning power plants release of radioactive substances, contained in gaseous wastes, is not less, than the same one of nuclear power plants. The necessity of regulating emission of these substance in atmosphere by analogy with nuclear power industry is shown. 1 fig.

  19. A kinematic model to estimate the effective dose of radioactive isotopes in the human body for radiological protection

    Science.gov (United States)

    Sasaki, S.; Yamada, T.

    2013-12-01

    The great earthquake attacked the north-east area in Japan in March 11, 2011. The system of electrical facilities to control Fukushima Daiichi nuclear power station was completely destroyed by the following tsunamis. From the damaged reactor containment vessels, an amount of radioactive substances had leaked and been diffused in the vicinity of this station. Radiological internal exposure becomes a serious social issue both in Japan and all over the world. The present study provides an easily understandable, kinematic-based model to estimate the effective dose of radioactive substances in a human body by simplified the complicated mechanism of metabolism. International Commission on Radiological Protection (ICRP) has developed an exact model, which is well-known as a standard method to calculate the effective dose for radiological protection. However, owing to that the above method accord too much with the actual mechanism of metabolism in human bodies, it becomes rather difficult for non-professional people of radiology to gasp the whole images of the movement and the influences of radioactive substances in a human body. Therefore, in the present paper we propose a newly-derived and easily-understandable model to estimate the effective dose. The present method is very similar with the traditional and conventional hydrological tank model. Ingestion flux of radioactive substances corresponds to rain intensity and the storage of radioactive substances to the water storage in a basin in runoff analysis. The key of this method is to estimate the energy radiated from the radioactive nuclear disintegration of an atom by using classical theory of E. Fermi of beta decay and special relativity for various kinds of radioactive atoms. The parameters used in this study are only physical half-time and biological half-time, and there are no intentional and operational parameters of coefficients to adjust our theoretical runoff to observation of ICRP. Figure.1 compares time

  20. Algorithm for calculating an availability factor for the inhalation of radioactive and chemical materials

    International Nuclear Information System (INIS)

    1984-02-01

    This report presents a method of calculating the availability of buried radioactive and nonradioactive materials via an inhalation pathway. Availability is the relationship between the concentration of a substance in the soil and the dose rate to a human receptor. Algorithms presented for calculating availabiliy of elemental inorganic substances are based on atmospheric enrichment factors; those presented for calculating availability of organic substances are based on vapor pressures. The basis, use, and limitations of the developed equations are discussed. 32 references, 5 tables

  1. Determination of environmental radioactivity for dose assessment

    International Nuclear Information System (INIS)

    Nakoaka, A.; Fukushima, M.; Takagi, S.

    1980-01-01

    A method was devised to determine detection limits for radioactivity in environmental samples. The method is based on the 5 mrem/yr whole-body dose objective established by the Japan Atomic Enerty Commission and is valid for assessing the internal dose from radionuclides in the environment around a nuclear facility. Eleven samples and 15 radionuclides were considered. Internal dose was assumed to be one-half of the total dose (5 mrem/yr) and was assessed using the critical pathway method. Needed detection limits (NDLs) were established to confirm the dose of 5 mrem/yr when there was more than one radionuclide per sample. The NDLs for γ-emitters were 10 -5 pCi/l. for air; 10 -3 pCi/l. for seawater; 10 -1 pCi/l. for drinking water; 10 0 pCi/kg for vegetables and fish; 10 0 pCi/l. for milk; and 10 1 pCi/kg for molluscs, crustaceans, seaweeds, soil and submarine sediments. The NDLs for β-emitters were 1-1/100 of those for γ-emitters. (author)

  2. 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

  3. Determination of the probability for radioactive materials on properties in Monticello, Utah

    International Nuclear Information System (INIS)

    Wilson, M.J.; Crutcher, J.W.

    1991-02-01

    In 1978, under the authority of the Atomic Energy Act, the US Department of Energy (DOE) established the Surplus Facilities Management Program (SFMP) to manage the maintenance and surveillance of numerous DOE-owned, radioactively contaminated facilities that have been declared surplus and to conduct a program leading to the ultimate disposition of those facilities. The primary responsibility of SFMP is to protect public health and the environment from potentially harmful radioactive contamination contained within or derived from DOE-owned facilities. Management of SFMP is directed by the DOE Office of Environmental Restoration and Waste Management, Washington, DC. Prior to mill site remediation, Monticello properties surrounding the site and designated privately owned are being assessed for inclusion in the SFMP. Oak Ridge National Laboratory (ORNL) was directed by DOE in July 1988 to assess the radiological condition of privately owned properties in Monticello that have been identified as possibly containing Monticello mill-related materials. Properties containing Monticello mill-related materials and with associated radiation levels that exceed US Environmental Protection Agency (EPA) and DOE standards are eligible for cleanup under SFMP. The objective of this study was to determine the probability that a property which contained Monticello mill-related residual radioactive material in excess of the guidelines would not be assessed under the current protocol. 3 refs., 3 figs., 2 tabs

  4. UK strategy for radioactive discharges 2001-2020. Consultation document

    International Nuclear Information System (INIS)

    2000-06-01

    This consultation draft of a strategy for radioactive discharges describes how the United Kingdom (UK) will implement the agreements reached at the 1998 Ministerial meeting of the OSPAR Commission, with regard to radioactive substances. It also provides a policy base for future reviews of discharge authorisations by the regulatory bodies and for strategic planning by the nuclear operators. The strategy sets a framework for radioactive discharges from UK installations over the next twenty years. Its aims are: progressive and substantial reductions in radioactive discharges from the UK as a whole and from each of the main sectors responsible for such discharges; progressive reduction of human exposure to ionising radiation resulting from radioactive discharges, so that no member of the general public in the UK will be exposed to a dose of more than 0.02 mSv a year, as a result of authorised radioactive discharges made from 2020 onwards; progressive reductions in concentrations of radionuclides in the marine environment resulting from radioactive discharges, such that by 2020 they add close to zero to historic levels. The scope of the UK strategy encompasses radioactive discharges from nuclear licensed sites, defence activities and other nuclear and non-nuclear sources of radioactive discharges. It covers both liquid and aerial discharges, although it is assumed that in general liquid discharges will have the largest and most measurable effects in the marine environment

  5. A Study to Determine Clearance Levels of Radioactive Wastes in Kenya

    Energy Technology Data Exchange (ETDEWEB)

    Mukakaa, Zaphania O. [KAIST, Daejeon (Korea, Republic of); Kim, Sung Il [KINS, Daejeon (Korea, Republic of)

    2015-10-15

    Due to lack of a radioactive waste disposal facility in Kenya, radioactive wastes are stored in a bonded warehouse until such a time when their activity is low and they meet the criterion for clearance. The International Atomic Energy Agency (IAEA) has established activity concentrations of radionuclides to act as a universal guideline or standard for clearance in member countries. Radioactive wastes whose activity would yield a trivial risk to the people and environment, i.e. with an annual dose below 10 µSv are usually cleared from regulatory control with no further regulatory control mechanisms being taken. The Radiation Protection Board currently depends on the IAEA's generic clearance level activity concentrations for purposes of clearing the radiation wastes within its inventory. This study aims to determine activity concentrations of radionuclides in the Kenyan inventory that correspond to the clearance level dose of 10 µSv/a as set by the IAEA. The RESidual RADioactivity (RESRAD) computer code, an important tool developed in 1989 to aid in evaluation of sites with radioactive contamination, will aid in modeling these clearance level values using a pathways analysis method and available site-specific data from Kenya. Afterwards, the obtained clearance level values will be compared with the IAEA's generic clearance level values of the corresponding radionuclides. The results modeled using the RESRAD code are conservative. For most of the radionuclides in the Kenyan inventory, the values do correspond with the IAEA standard generic clearance level values, albeit with minor differences. For most of the radionuclides, the difference is within the acceptable uncertainty limit. For these low probability events the effective dose resulting from them should not exceed 1 mSv per year. Thus, consideration was given to doses to the skin and an equivalent dose to the skin of 50 mSv per year was duly used in estimating the clearance level activities. The

  6. Determination of Heavy Metals and Radioactive Elements in Alluvial Soil using Atomic Absorption and Gamma Spectroscopy

    International Nuclear Information System (INIS)

    Hamed, S.S.; Walley EI Dine, N.; Soliman, S.I.; Moussa, W.M.

    2008-01-01

    The paper describes some methods dealing with measurements of some heavy and radioactive elements (U, Th and K) in Egyptian cultivated soil samples. Samples were collected from Toshka area. Also, soil and plant samples were collected from Kalube and EI - Gabal EI - Asfar to compare the obtained results from both region. Flame atomic absorption spectrometry (FAAS),Neutron activation analysis (INAA) and Natural radioactivity techniques were followed. FAAS and INAA techniques agreed fairly well for the compared elements Co,Zn and Fe which determined by the two techniques. Also for K which was determined by FAAS and natural radioactivity. It was found that the concentration range in soil samples for Co, Fe, K and Zn lies between 4.18 and 29.2 μg/g, 3.0 and 3.8 mg/g, 3.49 and 13.28 mg/g and 120 and 663 μg/g respectively while in plant samples the concentration of Co was from 3.02 to 4.02 μg/g, Fe from 1.18 to 1.35 mg/g and Zn from 29.63 to 73.02 μg/g

  7. Automatized system of radioactive material analysis

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  8. Determination of quality standard of cemented radioactive wastes

    International Nuclear Information System (INIS)

    Johan, B.

    1997-01-01

    The standard determination of cemented low activity radioactive waste has been carried out. This study was intended to find the quality of immobilized product as a guaranty to the public and the environmental safety. As preliminary study, there parameters type have been studied i.e, the density, compressive strength and the leaching rate. By adopted the formulations of advanced country and field data, it can be concluded that the cementation waste should have the density, p, between 1.70 and 2.50 g.cm - 3, the compressive strength, S, between 20 and 50 N.mm - 2, the leaching rates R n between 1.70 x 10 - 2 and 2.50 x 10 - 3 g.cm - 2.day - 1 and after 150 days leaching time the leaching rate R n - 3 g.cm - 2.day - 1. This study is expected to be used to propose the Indonesian National Standard (INS) (author)

  9. Evaluation of radiation doses from radioactive drugs

    International Nuclear Information System (INIS)

    Halperin, J.A.; Grove, G.R.

    1977-01-01

    Radioactive new drugs are regulated by the Food and Drug Administration (FDA) in the United States. Before a new drug can be marketed it must have an approved New Drug Application (NDA). Clinical investigations of a radioactive new drug are carried out under a Notice of Claimed Investigational Exemption for a New Drug (IND), submitted to the FDA. In the review of the IND, radiation doses are projected on the basis of experimental data from animal models and from calculations based upon radiation characteristics, predicted biodistribution of the drug in humans, and activity to be administered. FDA physicians review anticipated doses and prevent clinical investigations in humans when the potential risk of the use of a radioactive substance outweighs the prospect of achieving beneficial results from the administration of the drug. In the evaluation of an NDA, FDA staff attempt to assure that the intended diagnostic or therapeutic effect is achievable with the lowest practicable radiation dose. Radiation doses from radioactive new drugs are evaluated by physicians within the FDA. Important radioactive new drugs are also evaluated by the Radiopharmaceuticals Advisory Committee. FDA also supports the Center for Internal Radiation Dosimetry at Oak Ridge, to provide information regarding in vivo distribution and dosimetry to critical organs and the whole body from radioactive new drugs. The process for evaluation of radiation doses from radioactive new drugs for protection against use of unnecessary radiation exposure by patients in nuclear medicine procedures, a

  10. U.S. port commerce in radioactive materials

    International Nuclear Information System (INIS)

    Marti, B.E.

    1987-01-01

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

  11. Numerical modelling of suspended radioactive sediment transport in a stream using matlab

    International Nuclear Information System (INIS)

    Sarpong, Linda

    2017-07-01

    The use of materials that contain radioactive substances has gained grounds in Ghana due to numerous benefits derived from them. These radioactive materials can be found in the areas of medicine, agriculture and industries such as mining. Though there are strict measures to ensure such material do not find its way into the environment, improper management of the waste poses a threat to the environment. To be able to understand the impact the radioactive material has on the environment, mathematical models play a very relevant role in tracking the level of pollution in any medium. This thesis was concerned with the numerical modelling for the transport of the radioactive solute material that suspends in a stream using Matlab at different velocities as a result of flooding or an accident for research purposes. The modelling was done by using partial differential equations describing relevant physical processes evolution which includes water level, dissolved and suspended substances concentration and velocities. The equation system basis are the mass conservation and momentum laws, state equation and state transport equations. The implicit finite difference scheme was used to evaluate the transport equation, Advection-Dispersion Equation (ADE) with respect to time and space. Solution algorithms for Matlab programming were developed and implemented for generating results for analysis. The results obtained showed that the model was able to simulate accurately the various levels of suspended radioactive sediment concentration changes in the flowing stream longitudinally. (au)

  12. Radioactivity. To better manage polluted soils and sites. Pargny-sur-Saulx, more than 15 years of interventions. Chef de Baie, radioactivity mapping

    International Nuclear Information System (INIS)

    Caplin, Helene; Baumont, Genevieve; Tardieu, Laure; Brisson, Nicolas; Guillevic, Jerome; Serres, Christophe; Barrieu, Olivier

    2016-01-01

    A set of articles proposes an overview of the various actions performed by the IRSN for the management of sites and soils polluted by radioactive substances. A first article outlines the need for a national strategy to manage about forty polluted sites, the lack of a waste elimination sector (the storage is organised, but not the elimination), the action of the IRSN in mapping the radioactivity, in assessing the associated exposure, and in supporting decontamination actions. Costs, benefits, risks and actors are also evoked. A second article describes the various interventions organised over 15 years to manage a site which had been contaminated by the thorium from an ancient plant: site safety, interviews of personnel, elimination of all significant radioactivity. The last article addresses the case of another site, Chef de Baie in La Rochelle, which had been used as a deposit for contaminated materials produced by a neighbouring plant, and where the IRSN intervened to map the radioactivity

  13. Safety in the management of radioactive substances; Seguridad en el manejo de sustancias radiactivas

    Energy Technology Data Exchange (ETDEWEB)

    Balter, Henia [Centro de Investigaciones Nucleares, Montevideo (Uruguay); Rey, Ana; Leon, Alba; Jelen, Miguel [Universidad de la Republica, Montevideo (Uruguay). Facultad de Quimica

    1994-12-31

    A brief explanation of radiation protection,external irradiation,internal contamination,risk factors, active laboratory design,localization,ventilation,working surfaces,area distribution,classification of active laboratory.Radiopharmacy laboratory,shielding, area monitoring,personal dosimetry,rules for management of open sources,maximum admitted limits for radionuclides currently used in radiopharmacy.Decontamination of active areas and materials,surfaces,equipment s.Decontamination of hands.Waste disposal.Radioactive materials transportation.Reception of radioactive materials.Bibliography.

  14. Characterization of the solid radioactive waste from Cernavoda NPP

    International Nuclear Information System (INIS)

    Iordache, M.; Lautaru, V.; Bujoreanu, D.

    2005-01-01

    During the operation of a nuclear plant significant quantities of radioactive waste result that have a very large diversity. At Cernavoda NPP large amounts of wastes are either non-radioactive wastes or radioactive wastes, each of these being managed completely different from each other. For a CANDU type reactor, the occurrence of radioactive wastes is due to contamination with the following types of radioactive substances: - fission products resulting from nuclear fuel burning; - activated products from materials composing the technological systems; - activated products in process fluids. Radioactive wastes can be in solid, liquid or gas form. At Cernavoda NPP the solid wastes represent about 70% of the waste volume which is produced during plant operation and as a consequence of maintenance and decontamination operations. The most important types of solid wastes that are obtained and then handled, processed (if necessary) and temporarily stored are: solid low-level radioactive wastes (classified as compactible and non-compactible), solid medium radioactive wastes, spent resins, used filters and filter cartridges. The liquid radioactive waste class includes organic liquids (used oil, scintillator liquids and used solvents) and aqueous wastes resulting from process system operating, from decontamination and maintenance operations. Radioactive gas wastes occur subsequently to the fission process inside the fuel elements as well as due to the neutron activation of process fluids in the reactor systems. As result of plant operation, iodine, noble gases, tritium and radioactive particles occur and are passed toward the ventilation stack in a controlled manner so that environmental release of radioactive materials with concentrations exceeding the maximum permissible level could not occur. (authors)

  15. DETERMINATION OF SATURATION VAPOR PRESSURE OF LOW VOLATILE SUBSTANCES THROUGH THE STUDY OF EVAPORATION RATE BY THERMOGRAVIMETRIC ANALYSIS

    Directory of Open Access Journals (Sweden)

    R. V. Ralys

    2015-11-01

    Full Text Available Subject of Study.Research of vapor pressure of low volatile substances is a complicated problem due to both direct experimental implementation complexity and, most significantly, the issues faced correctness of the analysis and processing of experimental data. That is why it is usually required engaging the reference substances (with vapor pressures well studied. The latter drastically reduces the effectiveness of the experimental methods used and narrows their applicability. The paper deals with an approach to the evaporation process description (sublimation of low volatile substances based on molecular kinetic description in view of diffusive and convection processes. The proposed approach relies on experimental thermogravimetricfindingsina wide range of temperatures, flow rates ofthe purge gas and time. Method. A new approach is based on the calculation of the vapor pressure and uses the data about the speed of evaporation by thermogravimetric analysis depending on the temperature, the flow rate of the purge gas, and the evaporation time. The basis for calculation is the diffusion-kinetic description of the process of evaporation (mass loss of the substance from the exposed surface. The method is applicable to determine the thermodynamic characteristics for both the evaporation (the equilibrium liquid - vapor and sublimation (the equilibrium solid - vapor. We proposed the appropriate method of the experiment and analysis of its data in order to find the saturated vapor pressure of individual substances of low volatility. Main Results. The method has been tested on substances with insufficiently reliable and complete study of the thermodynamic characteristics but, despite this, are often used (because of the other data limitations as reference ones. The vaporization process (liquid-vapor has been studied for di-n-butyl phthalate C16H22O4 at 323,15–443,15 К, and sublimation for benzoic acid C7H6O2at 303,15–183,15 К. Both processes have

  16. Decontamination of radioactive clothing using microemulsion in carbon dioxide

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Jaeryong; Jang, Jina; Park, Kwangheon; Kim, Hongdoo; Kim, Hakwon [Kyunghee Univ., Seoul (Korea, Republic of); Yim, Sanghak; Yoon, Weonseob [Ulchin Nuclear Power Site, Ulchin (Korea, Republic of)

    2006-07-01

    Nuclear power is intrinsically a clean energy source due to its high energy density and low generation of waste. However, as the nuclear industry grows, a variety of radioactive wastes are increased gradually. Major subjects include contaminated components, tools, equipment, containers and facilities as well as nuclear waste such as uranium scrap and radioactive clothing. The radioactive waste can be classified by its creation. There are Trans-Uranium Nuclides (TRU), Fission Products (FP) and corrosion products. Nuclear decontamination has become an important issue in the nuclear industry. The conventional methods have some problems such as the production of secondary wastes and the use of toxic solvents. We need to develop a new method of decontamination and suggest a use of microemulsion in carbon dioxide to overcome these disadvantages. The microemulsion is the clear solution that contains the water, surfactant and carbon dioxide. The surfactant surrounded the droplet into carbon dioxide and this state is thermodynamically stable. That is, the microemulsion has a structure similar to that of a conventional water-based surfactant system. Generally, the size of droplet is about 5 {approx} 10nm. The microemulsion is able to decontaminate radioactive waste so that the polar substance is removed by water and the non-polar substance is removed by carbon dioxide. After the decontamination process, the microemulsion is separated easily to surfactant and water by decreasing the pressure under the cloud point. This way, only radioactive wastes are left in the system. Cleaned carbon dioxide is then collected and reused. Thus, there are no secondary wastes. Carbon dioxide is considered an alternative process medium. This is because it is non-toxic, non-flammable, inexpensive and easy to handle. Additionally, the tunable properties of carbon dioxide through pressure and temperature control are versatile for use in extracting organic materials. In this paper, we examine the

  17. Decontamination of radioactive clothing using microemulsion in carbon dioxide

    International Nuclear Information System (INIS)

    Yoo, Jaeryong; Jang, Jina; Park, Kwangheon; Kim, Hongdoo; Kim, Hakwon; Yim, Sanghak; Yoon, Weonseob

    2006-01-01

    Nuclear power is intrinsically a clean energy source due to its high energy density and low generation of waste. However, as the nuclear industry grows, a variety of radioactive wastes are increased gradually. Major subjects include contaminated components, tools, equipment, containers and facilities as well as nuclear waste such as uranium scrap and radioactive clothing. The radioactive waste can be classified by its creation. There are Trans-Uranium Nuclides (TRU), Fission Products (FP) and corrosion products. Nuclear decontamination has become an important issue in the nuclear industry. The conventional methods have some problems such as the production of secondary wastes and the use of toxic solvents. We need to develop a new method of decontamination and suggest a use of microemulsion in carbon dioxide to overcome these disadvantages. The microemulsion is the clear solution that contains the water, surfactant and carbon dioxide. The surfactant surrounded the droplet into carbon dioxide and this state is thermodynamically stable. That is, the microemulsion has a structure similar to that of a conventional water-based surfactant system. Generally, the size of droplet is about 5 ∼ 10nm. The microemulsion is able to decontaminate radioactive waste so that the polar substance is removed by water and the non-polar substance is removed by carbon dioxide. After the decontamination process, the microemulsion is separated easily to surfactant and water by decreasing the pressure under the cloud point. This way, only radioactive wastes are left in the system. Cleaned carbon dioxide is then collected and reused. Thus, there are no secondary wastes. Carbon dioxide is considered an alternative process medium. This is because it is non-toxic, non-flammable, inexpensive and easy to handle. Additionally, the tunable properties of carbon dioxide through pressure and temperature control are versatile for use in extracting organic materials. In this paper, we examine the

  18. Measurement of radioactive contamination and decontamination on wooden exteriors and garden trees in Northern Fukushima Prefecture

    International Nuclear Information System (INIS)

    Sugiura, Hiroyuki; Kawano, Keisuke; Kayama, Yukihiko

    2012-01-01

    Measurement and decontamination of surface of trees and surrounding wooden structures contaminated by radioactive substance were studied in the gardens and public parks of Northern Fukushima Prefecture which experienced radioactive contamination due to the accident at the TEPCO's Fukushima Daiichi Nuclear Power Plant. The counts per minute (CPM) above the centre surface of wooden garden tables in open air were 1.5 times higher than those of garden benches and 9 times higher than that of a garden bench in the square gazebo. Decontamination of wooden garden benches by high-pressure washing was more effective than planing. The counts per minute (CPM) above the soil around garden trees increased by 1.2 times after high-pressure washing. Radioactivity counting rate did not decrease when the leaves fallen from zelocova trees were removed; however, they decreased by about half when soil cover was installed at the base of the trees. Clearly, the upper surfaces of garden trees and wooden surrounding structures were strongly contaminated by radioactive substances, and they should be decontaminated by high-pressure washing before removing the surface soil. (author)

  19. Biokinetics and dosimetry of radioactively labelled organic C-14 compounds

    International Nuclear Information System (INIS)

    Krins, A.; Sahre, P.; Schoenmuth, T.

    2003-12-01

    The report starts with summarising research work and the resulting scientific information in connection with the dosimetry of C-14 labelled organic compounds. Biokinetic models are developed for compounds such as benzene, phenol, aniline, nitrobenzene, and a selection of pharmaceuticals, in order to show the radioactivity distribution after administration of the C-14 labelled substances. Based on the those models, dose coefficients and excretion rates are derived. The following synoptic view of the available data library leads on to a discussion of various aspects, as eg. the question of whether and how monitoring for detection of incorporation of C-14 administered with labelled organic compounds is possible. None of the questions and aspects arising in connection with this subject can be adequately dealt with in the present document, but concepts and methods are presented which permit an interpretation of radioactivity excretion data measured after incorporation of C-14 labelled organic substances. (orig./CB) [de

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

    International Nuclear Information System (INIS)

    Muhammad Dzulkhairi Zulkifly

    2012-01-01

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

  1. The Role of Perceived Peer Prejudice and Teacher Discrimination on Adolescent Substance Use: A Social Determinants Approach

    Science.gov (United States)

    Respress, Brandon N.; Small, Eusebius; Francis, Shelley A.; Cordova, David

    2013-01-01

    Although Black adolescents have reported a lower prevalence of substance use relative to non-Hispanic Whites, Black youth are disproportionately affected by adverse social outcomes. Social scientists have highlighted that using a framework that includes perceived peer prejudice and teacher discrimination as social determinants of adolescent risk behaviors is essential to fully understanding substance use behaviors in adolescents. However, this area of research remains underdeveloped. This study examined whether and to what extent perceived peer prejudice and teacher discrimination affect binge drinking and marijuana use by Black (n = 514) and non-Hispanic White (n = 2,818) adolescents using data from the National Longitudinal Study of Adolescent Health, Wave 2, Public Use dataset. Findings suggest that peer prejudice increased the risk of substance use in non-Hispanic White youth only, whereas experiences of teacher discrimination increased the risk of substance use in both Black and non-Hispanic White youth. The study’s limitations are noted, and implications for future research are discussed. PMID:24215222

  2. Radioactive waste containment - a literature study

    International Nuclear Information System (INIS)

    Mohiuddin, G.

    1985-01-01

    One of the basic requirements of safe radioactive waste disposal is isolation of the radioactive substances to prevent leakage into the biosphere. The multi-barrier concept has been developed to meet this requirement. Within the framework of the concept, barriers can be either natural or man-made. Natural barriers, i.e. geologic formations,have been investigated for their suitability, with host rock and their different properties being determined and compared. It has been found that the qualification of a proposed repository medium cannot be defined on the basis of physical, chemical, and mineralogical criteria alone, but that these data have to be completed by a global evaluation of the entire system consisting of waste products and waste forms, host rock, and surrounding rock. The study in hand reviews the reports and also lists the studies made on engineered barriers, as e.g. immobilisation barriers, container and package barriers, of various waste forms. A review of the studies dealing with the various waste disposal techniques shows that the sub-surface waste disposal and the deep underground disposal in mines are the best developed techniques currently. A review of ultimate disposal concepts adopted abroad shows that most countries favour the mining technology approach, with the exception of Denmark where R and D work in this field is focused on deep well disposal. (orig./HP) [de

  3. The risk of storing radioactive wastes from nuclear power plants

    International Nuclear Information System (INIS)

    Gruemm, H.

    1976-09-01

    Serious bottle-necks exist in the nuclear fuel cycle and will continue for the next decade. A total of 800 nuclear reactors are now in operation. 153 nuclear power plants represent an installed capacity of 70 GVe. Until 1985 five hundred nuclear power plants will be in operation from which up to this date 53.000 t uranium will have been discharged. Part of this will have to be reprocessed. Associated with the above mentioned amount are 500 t plutonium and 1.500 t highly radioactive wastes. Two risks for the population have to be considered: firstly, the effect of small amounts of radioactive substances released during normal operation of nuclear power plants (the annual dose is about 1 mrem per person). Secondly, the possibility of the release of great amounts of radioactivity during heavy accidents (the probability for which is extremely small). A series of feasible possibilities for conditioning are shown. Firstly, the wastes are packed in substances which are insoluble in water. Secondly, for low and medium wastes these can be mixed with concrete or bitumen and filled into stable containers. Thirdly, the wastes could also be solidified. Fourthly, the wastes could be enclosed in small glass spheres which are embedded in a metal matrix. (H.G.)

  4. Environmental policy. Ambient radioactivity levels and radiation doses in 1998

    International Nuclear Information System (INIS)

    1999-11-01

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

  5. 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.

  6. Principles for disposal of radioactive and chemical hazardous wastes

    International Nuclear Information System (INIS)

    Merz, E. R.

    1991-01-01

    The double hazard of mixed wastes is characterized by several criteria: radioactivity on the one hand, and chemical toxicity, flammability, corrosiveness as well as chemical reactivity on the other hand. Chemotoxic waste normally has a much more complex composition than radioactive waste and appears in much larger quantities. However, the two types of waste have some properties in common when it comes to their long-term impact on health and the environment. In order to minimize the risk associated with mixed waste management, the material assigned for ultimate disposal should be thoroughly detoxified, inertized, or mineralized prior to conditioning and packaging. Good control over the environmental consequence of waste disposal requires that detailed criteria for tolerable contamination should be established, and that compliance with these criteria can be demonstrated. For radioactive waste, there has been an extensive international development of criteria to protect human health. For non-radioactive waste, derived criteria exist only for a limited number of substances

  7. The regulation concerning transportation of radioactive materials by vehicles

    International Nuclear Information System (INIS)

    1978-01-01

    The Regulation is established on the basis of The law for the regulations of nuclear source materials, nuclear fuel materials and reactors'' and the ''Law for the prevention of radiation injuries due to radioisotopes.'' The prescriptions cover the transport of radioactive materials by railway, street rail way, ropeway, trolley buses, motorcars and light vehicles. Terms are explained, such as nuclear fuel materials, radioisotopes, radioactive substances, transported radioactive things, transported fissile things, vehicles, containers, exclusive loading, surrounding inspection area. Four types of transported radioactive things are specified, L and A types being less dangerous and BM and BU being more dangerous. Transported fissile things are classified to three kinds according to the safety to criticality of such things. Transported radioactive things except those of L type and containers with transported fissile things shall not be loaded or unloaded at the places where persons other than those concerned come in usually. Loading and unloading of such things shall be carried out so that the safety of such things is not injured. The maximum dose rate of radiation of the containers with transported radioactive things shall not be more than 200 millirem per hour on the surface and 10 millirem per hour at the distance of 1 meter. Specified transported radioactive things shall be particularly marked by the letter of ''radioactive'' or other signs indicating as such. (Okada, K.)

  8. Act No. 84 amending the decision of the Ministry of Communications on Transport of Dangerous Substances by Road

    International Nuclear Information System (INIS)

    1987-01-01

    This Act amends Decision No. 610 of 1978 of the Ministry of Communications on the Transport of Dangerous Substances by Road, which also covers radioactive substances; the amendments in their respect set out in the Annexes are of a technical nature. The Act entered into force on 1 April 1987. (NEA) [fr

  9. Radiation exposure of the population by residual substances from nuclear power plants

    International Nuclear Information System (INIS)

    Neider, R.

    1985-01-01

    This contribution gives a survey of common practice in the Federal Republic of Germany with model studies carried out so far to derive limit values. In this context, the SSK recommendations for 'Possibilities and Limits of Collective Doses' is applied to this specific problem and compared with the ideas of the ICRP. Questions on the 'cut-off dose' and on the 'de minimis' concept are discussed. Finally, a suggestion is developed and substantiated for the uniform determination of limit values for non-harmful utilization of low-level radioactive residual substances. The radiation exposure taken as 'de minimis' for individual persons out of a general public is taken as a basic. (orig./HP) [de

  10. 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.

  11. Polarized secondary radioactive beams

    International Nuclear Information System (INIS)

    Zaika, N.I.

    1992-01-01

    Three methods of polarized radioactive nuclei beam production: a) a method nuclear interaction of the non-polarized or polarized charged projectiles with target nuclei; b) a method of polarization of stopped reaction radioactive products in a special polarized ion source with than following acceleration; c) a polarization of radioactive nuclei circulating in a storage ring are considered. Possible life times of the radioactive ions for these methods are determined. General schemes of the polarization method realizations and depolarization problems are discussed

  12. Determination of the probability for radioactive materials on properties in Monticello, Utah

    International Nuclear Information System (INIS)

    Wilson, M.J.; Crutcher, J.W.; Halford, D.K.

    1991-01-01

    The former uranium mill site at Monticello, Utah, is a surplus facility subject to clean-up under the Surplus Facilities Management Program (SFMP). Surrounding properties contaminated with mill site material are also subject to cleanup, and are referred to as Monticello Vicinity Properties (MVP). The Pollutant Assessments Group (PAG) of Oak Ridge National Laboratory (ORNL), Grand Junction, Colorado (GJ), was directed by the US Department of Energy (DOE) in July 1988 to assess the radiological condition of properties in Monticello, Utah. Since the Monticello activities are on the National Priority List, extra measures to identify potentially contaminated properties were undertaken. Thus, the likelihood that a random property could contain radioactive materials became a concern to the DOE. The objective of this study was to determine the probability that a vicinity property not addressed under the MVP project could contain Monticello mill-related residual radioactive material in excess of the DOE guidelines. Results suggest approximately 20% of the properties in the Monticello area contain Monticello mill-related residual radioactive material in excess of the DOE guidelines. This suggested that further designation measures be taken prior to the close of the designation phase. A public relations effort that included a property-owner mailing effort, public posting, and newspaper advertisement was one measure taken to ensure that most properties were assessed. As a consequence of this study, DOE directed that radiological screening surveys be conducted on the entirety of the Monticello area

  13. Radioactive air and surface contamination in Czechia and Slovakia

    International Nuclear Information System (INIS)

    Rumyantsev, V.V.

    1992-01-01

    Data are presented on the radioactive substance effluents into the environment in conditions of NPP normal operation and on the air contamination by 85 Kr due to operation of the European and Soviet plants for reprocessing spent nuclear fuel. Data are given on the dosage of the Czechoslovakia population due to the Chernobyl NPP accident

  14. Methods for Characterisation of unknown Suspect Radioactive Samples

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  15. Determination of the Radon Concentration and Radioactivity Level in Karaca Cave

    International Nuclear Information System (INIS)

    Kara, A.

    2008-01-01

    In this study, the radon gas concentration in the Karaca cave which is open to tourism has been determined and the negative effects of radon gas on people were discussed. Karaca cave (Gumushane) is visited by many tourists every year. The measurements of radon gas concentration which affects the health of human beings negatively and even causes the lung cancer when it reaches high points have been done for the summer and winter season. LR-115 passive radon detector was used to determine radon concentrations in the cave both winter and summer season. The average radon concentration in the Karaca cave were determined as 823 Bq/m 3 and 1023 Bq/m 3 for the summer and winter season, respectively. Moreover, to find out the natural radioactivity in the cave, the gamma spectroscopic analysis of soil, stone and stalagmite samples were carried out and their relations with the radon gas in the cave atmosphere was analyzed

  16. Controlling radioactive waste

    International Nuclear Information System (INIS)

    Wurtinger, W.

    1992-01-01

    The guideline of the Ministry for Environmental Protection for controlling radioactive waste with a negligible development of heat defines in detail what data are relevant to the control of radioactive waste and should be followed up on and included in a system of documentation. By introducing the AVK (product control system for tracing the course of waste disposal) the operators of German nuclear power plants have taken the requirements of this guideline into account. In particular, possibilities for determining the degree of radioactivity of radioactive waste, which the BMU-guidelines call for, were put into practice by means of the programming technology of the product control system's module MOPRO. (orig.) [de

  17. Parameter determination in a groundwater field polluted by radioactive pollutant

    International Nuclear Information System (INIS)

    Sidauruk, P.; Barokah A; Syafalni; Wibagiyo

    1998-01-01

    The determination of source location and the corresponding parameters in a contaminated groundwater is very important. To be able to predict the distribution of radioactive contaminant in a contaminated field, the knowledge about the source location and the corresponding parameters is a necessity. The model developed in this paper is based on the fact that the relation between the logarithm of the concentration of the radio active contaminant with the squared coordinate is linear. The contaminant transport parameters as well as the a straight line. In other words, the parameters and the source location are determined in a such way that the linear correlation coefficient between the logarithm of the concentration of the radio active contaminant with the squared coordinate is optimized. The developed model is tested with a synthetic data with a satisfactory results. The synthetic data is generated such that can represent the real field. The synthetic data are generated because the real field data is not available. (authors)

  18. Results of measurements of the radioactive contamination of the biosphere in the Netherlands, compiled by the CCRX 1983

    International Nuclear Information System (INIS)

    1983-01-01

    In this internal annual report results are given of measurements of the radioactive contamination of the biosphere in the Netherlands. These measurements are coordinated by the Coordinating Committee for the Monitoring of Radioactive and Xenobiotic Substances (CCRX). Also samples of milk and grass from surroundings of nuclear reactors have been analysed

  19. Characterization of the solid radioactive waste From Cernavoda NPP

    International Nuclear Information System (INIS)

    Iordache, M.; Laotaru, V.

    2005-01-01

    Full text: During the operation of a nuclear plant significant quantities of radioactive waste result that have a very large diversity. At Cernavoda NPP large amounts of wastes are either non-radioactive wastes or radioactive wastes, each of these being managed completely different from which other. For a CANDU type reactor, the appearance of radioactive wastes is due to contamination with the following types of radioactive substances: - fission products resulting from nuclear fuel burning; - activated products from materials composing the technological systems; - activated products in process fluids. Radioactive wastes can be in solid, liquid or gas form. At Cernavoda NPP the solid wastes represent about 70% of the waste volume which is produced during plant operation and as a consequence of maintenance and decontamination operations. The most important types of solid wastes that are obtained and then handled, processed (if necessary) and temporarily stored are: solid low-level radioactive wastes (classified as compactible and non-compactible), solid medium radioactive wastes, spent resins, used filters and filter cartridges. The liquid radioactive waste class includes organic liquids (used oil, scintillator liquids and used solvents) and aqueous wastes resulting from process system operating, from decontamination and maintenance operations. Radioactive gas wastes occur subsequently to the fission process inside the fuel elements as well as due to the neutron activation of process fluids in the reactor systems. As result of plant operation, iodine, noble gases, tritium and radioactive particles occur and are passed toward the ventilation stack in a controlled manner so that environmental release of radioactive materials with concentrations exceeding the maximum permissible level could not occur. (authors)

  20. Modelling migration in the marine environment of radioactive substances from Fukushima Daiichi with the use of computer code POMRad

    Energy Technology Data Exchange (ETDEWEB)

    Krylov, A.L.; Nossov, A.V.; Kisselev, V.P. [Nuclear Safety Institute of Russian Academy of Sciences, 52, B. Tulskaya, Moscow (Russian Federation)

    2014-07-01

    Fukushima accident proved once more the necessity of computer codes for modelling of radioactive substances migration in the marine environment. Radionuclides were discharged (and leaked) into the sea with contaminated waters and fell-out from the atmosphere. Unfortunately assessments of the radioactivity sources differ significantly. The uncertainty is significant as for contamination that took place in months following the disaster as for leakages that took place in 2013. According to most researches, in the spring of 2011 the most important sources of radioactive pollution of the sea were direct inflows of contaminated water. In the long-term, due to contamination of river basins, the inflow of radioactivity with river waters may become the most significant source. Strontium, iodine and cesium tend to migrate in seas in dissolved state due to small values of K{sub d} (distribution factor water - suspended sediments). However distribution factor of Cs in fresh water is high. Thus it can be assumed that most of cesium entering the sea with a river flow will be sorbed on suspended particles. Sedimentation of the particles can lead to development of contaminated areas of bottom sediments. Thus modelling migration and transformation of radionuclides in water bodies is an important radioecological problem. The three-dimensional dynamic computer code POMRad is a tool for solution of the problem. It can be used to implement full cycle of modelling: - hydrological modelling - computation of fields of currents (and other important hydrological characteristics); - sediment transport modelling (cohesive, non-cohesive and 'hot particles' if necessary); - radioactivity transport modelling (taking into account decay, sorption, desorption, etc). The article is aimed to give a brief description of the computer code and examples of its use for modelling of migration in the sea of radionuclides from Fukushima Daiichi nuclear power plant (NPP). The base of POMRad is the

  1. Release procedures and disposal of radioactive residual substances at the Medical University Hanover (MHH)

    International Nuclear Information System (INIS)

    Scheller, F.; Behrendt, R.; Harke, H.

    2005-01-01

    The disposal of all radioactive residual packages of the MHH is regulated by the German radiation protection ordinance from 26 th July 2001; shown in appendix III, table 1, column 5: unrestricted release of solid materials and liquids. All radioactive waste packages are collected and handled by the central MHH department for radiation protection. They are sorted for type, nuclide and specific radioactivity. A few packages can directly be released as conventional waste after performing incoming measurements showing very low activity concentrations. Longer living radionuclides with specific activities above the release limits have to be delivered to the national waste disposal. For direct measurements of gamma-emitting radionuclides we use two in-situ-measuring units (ISOCS, Canberra) and a special release unit with 9 plastic scintillators in a fixed geometry (FR-9 PVT, MED Medizintechnik). Fluid beta-emitting radionuclides are measured by taking a fraction and using liquid scintillation counting (LSC). Solid beta-emitting radionuclides activity are calculated. (orig.)

  2. Device for removing radioactive solids in wet gases

    International Nuclear Information System (INIS)

    Ootsuka, Katsuyuki; Miyo, Hiroaki.

    1981-01-01

    Purpose: To enable removal and decontamination of radioactive solids in wet gases simply, easily and securely by removing radioactive solids in gases by filteration and applying microwaves to filters to evaporate condensed moistures. Constitution: Objects to be heated such as solutions, sludges and solids containing radioactive substances are placed in an evaporation vessel and a microwave generator is operated. Microwaves are applied to the objects in the evaporation vessel through a shielding plate and filters. The objects are evaporated and exhausted gases are passed through the filters and sent to an exhaust gas processing system by way of an exhaust gas pipe. Condensed moistures deposited on the filters which would otherwise cause cloggings are evaporated being heated by the microwaves to prevent cloggings. The number of stages for the filters may optionally be adjusted depending on the extent of the contamination in the exhaust gases. (Kawakami, Y.)

  3. Electronic tongue - an array of non-specific chemical sensors - for analysis of radioactive solutions

    International Nuclear Information System (INIS)

    Legin, A.; Rudnitskaya, A.; Babain, V.

    2006-01-01

    Multisensor systems, combining chemical sensor arrays with multivariate data processing engines (electronic tongue) rapidly and successfully developing in the last years are capable of simultaneous quantitative analysis of several species, e.g. metals, in complex real solutions. The expansion of the metals (metal ions) and species to be detected in radioactive waste requires permanent enhancement of sensing materials and sensors, with seriously different properties from those known earlier. A prospective direction of R and D of novel sensing materials is exploitation of radiochemical extraction systems and application of extraction substances as active components of new sensors. The sensors based on bidentate phosphorous organic compounds and their combinations with chlorinated cobalt dicarbollide displayed high sensitivity and selectivity to rare-earth metal ions La 3+ , Pr 3+ , Nd 3+ , Eu 3+ . The results indicated good promise for the development of novel analytical tools for detection of multivalent metal cations in different media, particularly in corrosive solutions such as radioactive wastes and solutions derived from spent nuclear fuel. The sensors and sensor arrays made on their basis can play an important role in the development of 'electronic tongue' systems for rapid analytical determinations of different components in complex radioactive solutions

  4. Analysis of cows' milk in the content of radioactive cs137 gamma-spectrometric method

    International Nuclear Information System (INIS)

    Zagidulin, Z.Z.; Isayev, R.Sh.; Guseynova, I.A.

    2010-01-01

    Full text : The most intense pollution of the environment Cs137 (after the ban of atmospheric nuclear weapons tests), was the result of the Chernobyl accident in 1986. The consequence of this accident was the accumulation of large amounts of Cs-137 in the atmosphere, which was the source of the global fallout of this isotope in the Earth's surface, including the territory of Azerbaijan. When considering livestock as one of the links of contamination by radioactive substances in food chains should be recognized that the main risk associated with the accumulation of radioactive Cs137 in the soil, plants and animal products originating ultimately in the human diet. The aim of this study was to determine the radioactive Cs137 in cow's milk. Subsequent samples of milk were purchased in stores and have been measured in the native form. Pal Sud milk produced in Azerbaijan. On Health - Russia. Savushkin product - Belarus. As a radiometric measurement setup Cs137 in cow's milk was used semiconductor gamma-ray spectrometer with a detection unit based on the detection of high-purity germanium (manufactured by Canberra) in the lead shielding.

  5. Radioactivity in the environment. A summary and radiological assessment of the Environment Agency's monitoring programmes; report for 1997

    International Nuclear Information System (INIS)

    1997-01-01

    The Radioactive Substances Act 1993 provides for controls to be exercised over the keeping and use of radioactive materials and, in particular, on the accumulation and disposal of radioactive wastes. The Environment Agency is responsible for administration and enforcement of the Act in England and Wales. In support of these regulatory functions and as part of the UK Government's arrangements for providing information to the European Commission under the Euratom Treaty, the Agency commissions independent monitoring of radioactive waste disposals and their impact on the environment, and monitoring of radioactivity in air, rainwater and drinking water sources. This report presents the data from these monitoring programmes and provides a commentary on their radiological significance. It includes assessments of radiation exposure of members of the public for compliance with the annual dose limit recommended by the International Commission on Radiological Protection. Concentrations of radioactivity in water are also assessed in relation to the guidelines on drinking water quality recommended by the World Health Organisation. This report for 1997 is one of an annual series published by the Agency. It is being distributed to local authorities as part of the arrangements under the Radioactive Substances Act 1993 for provision of access to environmental information. The monitoring programmes and preparation of this report are managed by the Agency's National Compliance Assessment Service. (author)

  6. Long-lived radioactive waste and nuclear plant decommissioning a legacy to future generations

    International Nuclear Information System (INIS)

    McAulay, I.R.

    1996-01-01

    Radioactive waste is an inevitable by-product of all uses of radioactive substances. This is the case of natural radioactivity as well as for artificially produced radioactive isotopes, and it is easy to overlook the significance of the waste problem in the case of technologically enhanced natural radioactivity. Several options are available for the disposal of radioactive waste and the paper considers these in detail from the point of view of the possible future impact of radiation doses to individuals or populations. Particular consideration is given to the use of deep disposal at stable geological sites as a means of dealing with large amounts of radioactive waste. It should not be forgotten that some of what we term waste today need not necessarily always be so. Indeed, there is a good case to make for the recycling of low activity materials rather than the uneconomic expedient of burying them. The paper will consider the possible recycling of valuable materials following suitable reprocessing and dilution and mention the dose implications of examples of such re-utilisation of radioactive materials

  7. Long-lived radioactive waste and nuclear plant decommissioning a legacy to future generations

    Energy Technology Data Exchange (ETDEWEB)

    McAulay, I R [Trinity Coll., Dublin (Ireland). Physical Lab.

    1996-10-01

    Radioactive waste is an inevitable by-product of all uses of radioactive substances. This is the case of natural radioactivity as well as for artificially produced radioactive isotopes, and it is easy to overlook the significance of the waste problem in the case of technologically enhanced natural radioactivity. Several options are available for the disposal of radioactive waste and the paper considers these in detail from the point of view of the possible future impact of radiation doses to individuals or populations. Particular consideration is given to the use of deep disposal at stable geological sites as a means of dealing with large amounts of radioactive waste. It should not be forgotten that some of what we term waste today need not necessarily always be so. Indeed, there is a good case to make for the recycling of low activity materials rather than the uneconomic expedient of burying them. The paper will consider the possible recycling of valuable materials following suitable reprocessing and dilution and mention the dose implications of examples of such re-utilisation of radioactive materials.

  8. 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

  9. Complexo-potentiometric determination of mercury (II) in chlormerodrin and mercuric chloride labelled with radioactive mercury

    International Nuclear Information System (INIS)

    Duek, E.E.

    1976-09-01

    A method is described for determining the amount of mercury (II) in radioactively labelled chlormerodrin and mercuric chloride. By measuring the absolute activity in an ionization chamber, the specific activity is therefore immediately obtained. The determination of Hg (II) is based on a complexometric titration. Because of method characteristics and speed convenience, the end point is observed by means of a pH-meter. A comparison is made with a determination performed by detecting the end point with color-change indicators. The error is estimated, and the results are statistically interpreted. (author) [es

  10. Ministerial Decree of 15 June 1966 determining the activity of radioactive substances for purposes of classification of commercial operations under Section 32 of the Decree of the President of the Republic No. 185 of 13 February 1964

    International Nuclear Information System (INIS)

    1966-01-01

    This Decree was made to determine the quantity of radioactivity which constitutes the threshold for classifying commercial operations into a less or more hazardous category, namely A and B categories respectively. The IAEA criteria in this field were used as a basis for this classification. (NEA) [fr

  11. Radioactive whey concentrate - a case to apply section 3 of the Radiation Protection Ordinance

    International Nuclear Information System (INIS)

    Sauer, G.W.; Zypries, B.

    1988-01-01

    According to the authors, section 4 StrlSchV does not apply, the case has to be handled applying section 3 StrlSchV (Radiation Protection Ordinance). This means that the storage, treatment and disposal of the radioactive whey concentrate is subject to licensing. Disposal as radioactive waste, however, will require a licence only if the limit given in section 4 IV, No. 2 lit. e, the 10 -4 -fold of the allowed radioactivity per gramme (i.e. 3700 Bq/kg) is exceeded. The averaged radioactivity data measured do exceed this limit. Only the transport of the radioactive whey concentrate does not fall under the provisions of the ordinances on road transport or rail transport of hazardons substances, as the limit given there is 74 Bq/g of specific activity. (orig./HP) [de

  12. Determination of technetium-99 in environmental and radioactive waste samples

    International Nuclear Information System (INIS)

    Ferencova, M.; Peter Tkac, P.

    2007-01-01

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

  13. New EDTA determination method based on ion chromatography with suppressed conductimetric detection

    International Nuclear Information System (INIS)

    Gyoergy Patzay; Yahya Ramadan; Csilla Tonko

    2014-01-01

    A novel direct method for the determination of EDTA in alkaline radioactive evaporator residue solution was developed and validated based on ion chromatography with suppressed conductimetric detection and anion exchange columns (A Supp 4, 4 mm × 250 mm and A Supp 5, 4 mm × 150 mm). The yttrium-EDTA complex resulted one single chromatographic peak in the eluent and allowed the correct determination of EDTA in an alkaline, high concentration radioactive waste water. Depending on coexisting substances, suitable eluent is 10.0 mM carbonate buffer/pH 10.6 or 10.75 (t R ,Y-EDTA = 7.01 and 6.4 min, respectively). For 10.0 mM carbonate buffer/pH 10.6 and isocratic flow rate of 1.0 cm 3 /min, a linear calibration curve was obtained from 5 to 40 mg/dm 3 (r > 0.999) EDTA. Good resolution was achieved from commonly coexisting anions (chloride, nitrite, nitrate, sulphate, phosphate, bromide and citrate). The developed simple ion chromatographic method was applied for the assay of EDTA in various radioactive alkaline solutions. (author)

  14. 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

  15. Method of reducing the volume of radioactive waste

    International Nuclear Information System (INIS)

    Buckley, L.P.; Burrill, K.A.; Desjardins, C.D.; Salter, R.S.

    1984-01-01

    There is provided a method of reducing the volume of radioactive waste, comprising: pyrolyzing the radioactive waste in the interior of a vessel, while passing superheated steam through the vessel at a temperature in the range 500 to 700 degrees C, a pressure in the range 1.0 to 3.5 MPa, and at a flow rate in the range 4 to 50 mL/s/m 3 of the volume of the vessel interior, to cause pyrohydrolysis of the waste and to remove carbon-containing components of the pyrolyzed waste from the vessel as gaseous oxides, leaving an ash residue in the vessel. Entrained particles present with the gaseous oxides are filtered and acidic vapours present with the gaseous oxides are removed by solid sorbent. Steam and any organic substances present with the gaseous oxides are condensed and the ash is removed from the vessel. The radioactive waste may be deposited upon an upper screen in the vessel, so that a substantial portion of the pyrolysis of the radioactive waste takes place while the radioactive waste is on the upper screen, and pyrolyzed waste falls through the upper screen onto a lower screen, where another substantial portion of the pyrohydrolysis takes place. The ash residue falls through the lower screen

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  17. SGSreco. A method for accurate and reliable determination of the radioactive inventory in radioactive waste barrels; SGSreco. Eine Methode zur genauen und verlaesslichen Bestimmung des Aktivitaetsinventares in radioaktiven Abfallfaessern

    Energy Technology Data Exchange (ETDEWEB)

    Krings, Thomas; Mauerhofer, Eric [Forschungszentrum Juelich GmbH (Germany). Inst. fuer Energie und Klimaforschung (IEK), Nukleare Entsorgung und Reaktorsicherheit (IEK-6)

    2013-07-01

    The computer code SGSreco is used for the evaluation of counting rate distributions from SGS (segmented gamma scan) measurements on radioactive waste barrels. The code is based on data fitting to a physical model function; the results include position parameters, point source activities and the activity of a homogeneous activity distribution. A simulation study has shown that the point source activity can be determined with 2% accuracy. Conventional methods are based on the assumption of a homogeneous activity distribution which is wrong for about 75% of the radioactive waste barrels, the determined nuclide specific activities have significant error rates. The use of SGSreco improves the accuracy and reliability of activity determinations and reduces the conservatism of activity estimations. The latter one allows an optimal utilization of the repository capacity with respect to the maximum activities at the end of the operational phase of the repository Konrad.

  18. Process for determining the remediation category of hazardous substance sites

    International Nuclear Information System (INIS)

    Sieben, A.K.

    1994-01-01

    An evaluation process has been developed that aids in selecting the appropriate remediation category of hazardous substance sites. Three general remediation categories have been established: No further Action: Potential Early Action: and Defer for RI/FS or Transition/Decontamination and Decommissioning. This evaluation method is a preliminary screening process only and will not identify the most appropriate remediation alternative for each site. The remedy selection process can proceed only after a remediation category is determined for each site. All sites are evaluated at a preliminary screening level to determine the general remediation category. After the first screen, a secondary evaluation is performed on both the PEA sites and the DEFER sites. For PEAs, this secondary evaluation will incorporate additional specific factors, such as a screening level risk assessment. For the DEFER sites feasibility factors will be used to distinguish between the sites which should undergo a normal RI/FS and the sites which will be recommended to be remediated in association with D ampersand D of buildings. Ultimately, all of the sites will be placed into one of four remediation categories

  19. Order No 485 on the use of unsealed radioactive sources in hospitals, laboratories, etc

    International Nuclear Information System (INIS)

    1985-11-01

    This Order, made in furtherance of an Order of 20 Novembre 1975 concerning safety precautions in the use of radioactive substances, implements in Directive 80/836/Euratom on radiation protection. It lays down a licensing system for the purchase and use of unsealed radioactive sources and also provides for their storage and disposal. The National Board of Health is the licensing authority. The Order also prescribes radiation protection measures for laboratory personnel [fr

  20. Methodology for determining acceptable residual radioactive contamination levels at decommissioned nuclear facilities/sites

    International Nuclear Information System (INIS)

    Watson, E.C.; Kennedy, W.E. Jr.; Hoenes, G.R.; Waite, D.A.

    1979-01-01

    The ultimate disposition of decommissioned nuclear facilities and their surrrounding sites depends upon the degree and type of residual contamination. Examination of existing guidelines and regulations has led to the conclusion that there is a need for a general method to derive residual radioactive contamination levels that are acceptable for public use of any decommissioned nuclear facility or site. This paper describes a methodology for determining acceptable residual radioactive contamination levels based on the concept of limiting the annual dose to members of the public. It is not the purpose of this paper to recommend or even propose dose limits for the exposure of the public to residual radioactive contamination left at decommissioned nuclear facilities or sites. Unrestricted release of facilities and/or land is based on the premise that the potential annual dose to any member of the public using this property from all possible exposure pathways will not exceed appropriate limits as may be defined by Federal regulatory agencies. For decommissioned land areas, consideration should be given to people living directly on previously contaminated areas, growing crops, grazing food animals and using well water. Mixtures of radionuclides in the residual contamination representative of fuel reprocessing plants, light water reactors and their respective sites are presented. These mixtures are then used to demonstrate the methodology. Example acceptable residual radioactive contamination levels, based on an assumed maximum annual dose of one millirem, are calculated for several selected times following shutdown of a facility. It is concluded that the methodology presented in this paper results in defensible acceptable residual contamination levels that are directly relatable to risk assessment with the proviso that an acceptable limit to the maximum annual dose will be established. (author)

  1. Relationships as determinants of substance use amongst street ...

    African Journals Online (AJOL)

    stress, peer relationships and frequency of family meals.7,8,9,10 Amongst ... students with the fewest peer interaction problems.12 Furthermore, the ..... substance use among street children in a local government area of Nigeria: Drug and.

  2. Accident with radioactive substances in laboratory. An exercise during the education of persons in radiation protection, who are working with open radioactive sources

    International Nuclear Information System (INIS)

    Stolze, B.

    2003-01-01

    In spite of carefulness it is possible,that contamination occur by handling unscaled radioactive sources or in case of an accident. It is demonstrated in an exercise managing an accident with unscaled radioactive sources. The persons, who are educated in radiation protection for handling unsealed radioactive sources, must have knowledge of theoretical regulations of the radiation protection law and of the limits in radiation protection. Also they have to know the handling to reduce possible contamination. They have to be able to calculate the dose of skin contamination. In my lecture I give some information on regulations of accidents with radioactive sources in Germany and a scenario of an accident and I explain, what is to do to manage this event. A person opened an ampoule. The activity splashed and contaminated the person's hand, arm and face. Also in the room there was a contamination. The desk and the floor were contaminated. There were 50 MBq P-32 as NaH 2 P''32O 3 in water solution, I give a report on practices in our courses, which the participants have to do. The radiological experts have to decontaminate the skin and they have to calculate the skin-dose and to give the information to the authorities. (Author) 4 refs

  3. Determination of true optical absorption and scattering coefficient of wooden cell wall substance by time-of-flight near infrared spectroscopy.

    Science.gov (United States)

    Kitamura, Ryunosuke; Inagaki, Tetsuya; Tsuchikawa, Satoru

    2016-02-22

    The true absorption coefficient (μa) and reduced scattering coefficient (μ´s) of the cell wall substance in Douglas fir were determined using time-of-flight near infrared spectroscopy. Samples were saturated with hexane, toluene or quinolone to minimize the multiple reflections of light on the boundary between pore-cell wall substance in wood. μ´s exhibited its minimum value when the wood was saturated with toluene because the refractive index of toluene is close to that of the wood cell wall substance. The optical parameters of the wood cell wall substance calculated were μa = 0.030 mm(-1) and μ´s= 18.4 mm(-1). Monte Carlo simulations using these values were in good agreement with the measured time-resolved transmittance profiles.

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

    International Nuclear Information System (INIS)

    Matsubara, Shohei

    2006-01-01

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

  5. 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.)

  6. A calculation strategy for the determination of the temperature distribution in radioactive waste repositories

    International Nuclear Information System (INIS)

    Hahne, K.; Biurrun, E.

    1989-01-01

    In the past many calculation tools have been developed for the determination of instationary temperature distributions in radioactive waste repositories (single source model/large scale model/unit cell model using analytical or numerical methods; overall model using analytical or numerical methods). This paper discusses how, in practice, all these calculation tools have to be associated sensibly in a special calculation strategy making use of their actual advantages

  7. [Psychoactive substances in biological samples--toxicological laboratory data].

    Science.gov (United States)

    Gomółka, Ewa; Wilimowska, Jolanta; Piekoszewski, Wojciech; Groszek, Barbara

    2004-01-01

    The subject of the research was the analysis of frequency and type of psychoactive substances used, basing on the determinations the blood and/or urine samples, performed in the toxicological laboratory of the Department of Clinical and Industrial Toxicology Jagiellonian University in Kraków in the period from December 2001 to November 2003. From 17,649 performed determinations--45.5% were positive. 50% of the positive determinations were psychoactive substances. The most often psychoactive substance determined was ethyl alcohol (52.86%), next benzodiazepines (17.41%), amphetamines (10.54%), opiates (8.05%), THC (6.87%), barbiturates (3.74%), and occasionally atropine and cocaine. There was observed a variety of mixed, simultaneously taking psychoactive substances, especially ethyl alcohol, opiates, amphetamine derivatives and cannabinoids. The analysis of the occurrence of psychoactive substances in biological samples from patients treated in different hospital departments, others hospitals and ordered by private persons also was performed. In the last two years 369 private patients ordered psychoactive substances determinations and 78 of them were positive.

  8. Device for the disposal of radioactive liquid wastes

    International Nuclear Information System (INIS)

    Tomizawa, Toshi; Inoue, Tadashi.

    1976-01-01

    Object: To adsorb and collect radioactive nuclide ions contained in the radioactive liquid waste to select and separate thereof. Structure: A unitary disposing tank comprises an insulative cylindrical tank, an unsoluble cathode plate positioned thereunder and formed with a number of liquid inlet holes, an adsorbent layer filled with unsoluble electrically conductive substances having a large surface area in contact with the cathode plate, and an unsoluble anode plate positioned at the upper part of the cylindrical disposing tank so as not to come into contact with the adsorbent layer and formed with a number of liquid inlets, whereby one or more disposing tanks are stacked in a layer fashion, and a DC voltage is applied between the anode and cathode plates to flow a liquid to be disposed into the disposing tanks so that the radioactive metal ion nuclide in the liquid may be adsorbed and collected by the cathode and the adsorbent layer for selection and separation. (Ohara, T.)

  9. Method of solidifying and disposing radioactive waste plastic

    International Nuclear Information System (INIS)

    Matsuura, Hiroyuki; Yasumura, Keijiro

    1981-01-01

    Purpose: To solidify radioactive waste as it is with plastic by forming a W/O (Water-in-Oil) emulsion with the radioactive waste and a plastic solidifier, and treating it with a polymerization starting agent, an accelerator, and the like. Method: A predetermined amount of alkaline substance such as sodium hydroxide, triethanol, or the like is added quantitatively to radioactive waste and it is mixed by an agitator. A predetermined amount of solidifier such as unsaturated polyester or the like is added to the mixture and it is further mixed by the agitator to form a stable W/O emulsion. Subsequently, predetermined amounts of polymerization starting agent such as methyl ethyl ketone peroxide and polymerization accelerator such as cobalt naphthenate or the like are added thereto, the mixture is mixed, and is then allowed to stand for at room temperature for the plastic solidification thereof. No reaction occurs after the solidification. (Sekiya, K.)

  10. Uranium Glass: A Glowing Alternative to Conventional Sources of Radioactivity

    Science.gov (United States)

    Boot, Roeland

    2017-01-01

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

  11. Radioactive decay and labeled compounds

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

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

  12. Strategy plan of Minchornobyl for radioactive waste management in the Ukraine.; Strategicheskij plan Minchernobylya v sfere obrashcheniya s radioaktivnymi otkhodami v Ukraine.

    Energy Technology Data Exchange (ETDEWEB)

    Kholosha, V I; Korchagin, P A; Udod, V V [Naukovo-Tekhnyichnij Tsentr z dezaktyivatsyiyi ta kompleksnogo povodzhennya z radyioaktivnimi vyidkhodami, Zhovtyi Vodi (Ukraine)

    1994-12-31

    The plan of long-term activity in the field of radioactive waste management in Ukraine is presented. Radioactive wastes of the Chernobyl origin as well as those from usage of nuclear technologies and radioactive substances in the industry, medicine and scientific researches are taken into account. The main directions of activities and estimates of financial requirements and time-table are presented.

  13. 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.

  14. Environmental radioactivity and radiation exposure

    International Nuclear Information System (INIS)

    1980-01-01

    In 1977 population exposure in the Federal Republic of Germany has not changed as compared to the previous years. The main share of the total exposure, nearly two thirds, is attributed to natural radioactive substances and cosmic radiation. The largest part (around 85%) of the artificial radiation exposure is caused by X-ray diagnostics. In comparison to this, radiation exposure from application of ionizing radiation in medical therapy, use of radioactive material in research and technology, or from nuclear facilities is small. As in the years before, population exposure caused by nuclear power plants and other nuclear facilities is distinctly less than 1% of the natural radiation exposure. This is also true for the average radiation exposure within a radius of 3 km around nuclear facilities. On the whole, the report makes clear that the total amount of artificial population exposure will substantially decrease only if one succeeds in reducing the high contribution to the radiation exposure caused by medical measures. (orig.) [de

  15. Regulatory aspects of underground disposal of radioactive waste in the United Kingdom

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    It is a basic principle of radioactive waste management in the U.K. to comply with the system of dose limitations laid down by the International Commission on Radiological Protection. The Radioactive Substances Act, 1960, prohibits the disposal of radioactive waste on or from all premises (except those belonging to the Crown) unless authorised by the appropriate authority. Consultation, as necessary, with local and public authorities is provided for. Under the Nuclear Installations Act, 1965, nuclear installations, with some exceptions, require to be licensed by the Health and safety executive. Installations for the disposal of radioactive waste are not, as such, prescribed as nuclear installations under the Nuclear Installations Act, 1965 (and thereby governed by the licensing procedure under the Act), but they may be, if they involve the storage of bulk quantities of radioactive waste. The Secretary of State for the Environment, together with the Secretaries of State for Scotland and Wales are responsible for the development of a nuclear waste management policy, helped in this task by the newly-formed Radioactive Waste Management Advisory Committee. (NEA) [fr

  16. Radioactivity of fresh water fish in Finland after the Chernobyl accident in 1986

    International Nuclear Information System (INIS)

    Saxen, R.; Rantavaara, A.

    1987-06-01

    The Chernobyl accident raised the deposition levels of radioactive substances in Finland. Fish were affected by radioactive substances in watersheds. Extensive study of areal and temporal changes in the radioactivity of freshwater fish was started soon after the accident. The aim of the study was to obtain new data on a situation involving fresh deposition and to estimate the importance of freshwater fish as a source of radiocesium for consumers. Attenuation was also paid to various factors affecting the radioactivity of fish. Samples were taken from about 200 lakes. In all, about 600 samples were analysed gammaspectrometrically. A few samples were also analysed radiochemically for beta-emitting 89 Sr and 90 Sr. The samples contained about ten different species of fish. The highest concentrations of radiocesium in fish were found in the areas of highest radioactive deposition in Finland. In areas with the same level of 137 Cs deposition, concentrations in fish depended on the size of the lake: the smaller the area of the lake in which the fish were caught the higher the concentration. Of the fish species studied, perches had the highest concentrations of radiocesium. Intake estimations were based on the average concentrations, weighted for catches, in each drainage area and in the whole country, and on the average intake of 137 Cs via freshwater fish. In Finland, the average intake of 137 Cs via freshwater fish in May-December 1986 was about 1200 Bq. The values obtained for different drainage basins varied from about 160 to 3400 Bq

  17. The use of a radioactive tracer for the determination of distillation end point in a coke oven

    International Nuclear Information System (INIS)

    Burgio, N.; Capannesi, G.; Ciavola, C.; Sedda, F.

    1995-01-01

    A novel high precision detection method for the determination of the distillation end point of the coking process (usually in the 950 deg C range) has been developed. The system is based on the use of a metallic capsule that melts at a fixed temperature and releases a radioactive gas tracer ( 133 Xe) in the stream of the distillation gas. A series of tests on a pilot oven confirmed the feasibility of the method on industrial scale. Application of the radioactive tracer method to the staging and monitoring in the coking process appears to be possible. (author). 6 refs., 5 figs., 3 tabs

  18. Radioactive waste management and their ultimate disposal technologies in India: recent practices and developments

    International Nuclear Information System (INIS)

    Bajpai, R.K.

    2015-01-01

    The radioactive wastes that arise from the use of uranium, thorium and other radioactive isotopes during their various applications in the field of power generation, industry, agriculture and medicine are among the most talked about and at time even highly dreaded substances created by man in recent past. Most of the fears owe their genesis to extraordinary periods of time over which such waste remain radioactive and continue to emit radiations which are invisible to human eyes. These time periods run into tens of thousands of years and as a result any solution for management and permanent isolation of such waste needs to demonstrate safety of mankind and environment over such lengthy time frames. For example a radioactive isotope of strontium, known as 90 Sr takes about 300 years to loose its entire radioactivity. Similarly a popular isotope of plutonium 239 Pu needs almost 2.5 lakhs years to shed its entire radioactivity by converting itself to a non radioactive element. In this talk some salient aspects of radioactive waste management and solutions for their permanent isolation under consideration in India are discussed

  19. Method of treatment of radioactive silts and soils

    International Nuclear Information System (INIS)

    Varlakov, A.P.; Sobolev, I.A.; Barinov, A.S.; Dmitriev, S.A.; Karlin, S.V.; Flit, V.U.

    1997-01-01

    To solve the problem of silts and soils that are contaminated with radioactive and toxic substances, the following method has been developed at SIA RADON. The material is mixed with limestone and other components, including up to 70% (mass) of dried residue of liquid radioactive waste. The mixture is heated at 800 to 1,000 C, shredded, and used to form cement. This cementation process may be used to treat radioactive or other chemical waste. The work demonstrated that in the case of silts, for example, the product volume is reduced by a factor of 1.5 to 3 compared to the initial silts volume. A fast hardening, durable product is obtained, the quality of which is not inferior to that obtained by using the traditional binders. For some parameters, e.g., hardening rate and macroelement leaching, the current method is significantly better than the traditional cementation process. It has also been demonstrated that, over a wide range of parameters, when dry residue of liquid radioactive waste is used in the initial mixture, the part of NO x can be reduced to nitrogen, thereby reducing NO x emissions

  20. Environmental radioactivity and radiation exposure in Switzerland 1993

    International Nuclear Information System (INIS)

    1994-01-01

    Systematic monitoring of radioactivity in the environment and food has been going on in Switzerland since the mid 1950s. This report contains a summary of the values measured in 1993, along with the interpretation of the data and the resultant radiation dose for the population. The monitoring programme deals with radioactivity in the atmosphere, precipitation, aquatic systems, grass, foodstuffs and the human body, but also includes natural radiation, doses due to radon inside dwellings, emissions from nuclear power stations and other radiation sources. With two exceptions, the nuclear power plants and other facilities licensed to handle radioactive substances remained within their annual release limits in 1993, and measurements carried out in the environment revealed no inadmissible radioactivity concentrations or dose values. The population's mean annual radiation dose totals 4 mSv. Some 40% of this is due to radon in the home, with a mean of 1.6 mSv and extreme values as high as around 100 mSv; 30% or 1.2 mSv, may be ascribed to natural radiation, leaving less then 0.2 mSv ascribable to man-made sources, excluding medical applications. (author) figs., tabs