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Sample records for computerised radioactive effluent

  1. Treating radioactive effluent

    International Nuclear Information System (INIS)

    Kirkham, I.A.

    1981-01-01

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

  2. Radiological consequences of radioactive effluents

    International Nuclear Information System (INIS)

    Clarke, R.H.

    1979-01-01

    A study of the differential radiological impact of the nuclear fuel cycle with and without plutonium recycle is being undertaken jointly by the National Radiological Protection Board and the Commissariat a l'Energie Atomique (CEA). A summary is given of the development of the methodology detailed in their first report to the Commission of the European Communities (CEC) (NRPB/CEA, A methodology for evaluating the radiological consequences of radioactive effluents released in normal operations. Luxembourg, CEC Doc. V/3011/75 EN (1979)). The Collective Effective Dose Equivalent Commitment was used in an attempt to assess the total health detriment. The application of the methodology within particular member states of the European Community has been discussed at seminars. Sensitivity analysis can identify the more important parameters for improving the accuracy of the assessment. (UK)

  3. Assessment methodology for radioactive effluents

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    The objective of this environmental assessment is to define and rank the needs for controlling radioactive effluents from nuclear fuel cycle facilities. The assessment is based on environmental standards and dose-to-man calculations. The study includes three calculations for each isotope from each facility: maximum individual dose for a 50-year dose commitment from a 1-yr exposure according to the organ affected; population dose for a 50-yr dose commitment from a 1-yr exposure according to the organ affected; and annual dose rate for the maximally exposed individual. The relative contribution of a specific nuclide and source to the total dose provides a method of ranking the nuclides, which in turn identifies the sources that should receive the greatest control in the future. These results will be used in subsequent tasks to assess the environmental impact of the total nuclear fuel cycle

  4. Solidification of radioactive waste effluents

    International Nuclear Information System (INIS)

    Mergan, L.M.; Cordier, J.-P.

    1981-01-01

    A process and apparatus for solidifying radioactive waste liquid containing dissolved and/or suspended solids is disclosed. The process includes chemically treating for pH adjustment and precipitation of solids, concentrating solids with a thin-film evaporator to provide liquid concentrate containing about 50% solids, and drying the concentrate with a heated mixing apparatus. The heated mixing apparatus includes a heated wall and working means for shearing dried concentrate from internal surfaces and subdividing dry concentrate into dry, powdery particles. The working means includes a rotor and helical means for positively advancing the concentrate and resulting dry particles from inlet to outlet of the mixing apparatus. The dry particles may also be encapsulated in a matrix material. Entrained particles in the vapor stream from the evaporator and mixer are removed in an integral particle separator and the vapor is subsequently condensed and may be recycled upstream of the thin-film evaporator. A section of the mixer may be used for mixing dry particles with the matrix material in a continuous drying and mixing sequence. A section of the mixer also may be used for mixing the treating chemical with the waste liquid

  5. Treatment of radioactive effluents at the Boris Kidric Institute

    International Nuclear Information System (INIS)

    Bojovic, P.; Drobnik, S.; Popara, D.

    1964-10-01

    The paper describes the origin, composition and activity of radioactive effluents at the Boris Kidric Institute, their collection at the places or origin, transport to the place of disposal and treatment of some smaller quantities. Special attention has been paid to effluents with short-lived isotopes produced in the Laboratory for radioactive isotope production (author)

  6. Limits to radioactive effluents and countermeasures in accidental situations

    International Nuclear Information System (INIS)

    Nowotny, G.; Gonzalez, A.

    1978-01-01

    The paper discusses the criteria used by the Argentine Atomic Energy Commission, as competent authority, to set limits to radioactive effluents from nuclear installations. It also discusses the selection of action levels for carrying out countermeasures in accidental situations. (author)

  7. Studies on osmotic concentration of radioactive effluents

    International Nuclear Information System (INIS)

    Thomas, K.C.; Ramachandhran, V.; Misra, B.M.

    1986-01-01

    The potential of direct osmosis for concentrating radioactive effluents is examined on the laboratory scale. Studies were carried out using asymmetric cellulose acetate membranes of a range of porosities under varying salinity gradients. A suitable bench scale osmotic concentrator employing tubular membrane systems has been fabricated and tested. An attempt to understand the mechanism of water permeation under osmotic and hydrostatic gradients has been made based on the irreversible thermodynamic approach. The solute separation of sodium chloride and radionuclides under osmosis is in the range of 85 to 95% for various osmotic sink solutions. The osmotic water flux is observed to be lower than the hydraulic water flux under reverse osmosis conditions. While the solute separation increases with an increase in annealing temperature, water flux decreases for both osmosis and reverse osmosis systems for various feed salinities. The effect of concentration polarization is analysed, and the effect of feed and osmotic sink velocity on the performance of the osmotic concentrator has also been studied. (orig.)

  8. Radioactive clearance discharge of effluent from nuclear and radiation facilities

    International Nuclear Information System (INIS)

    Liu Xinhua; Xu Chunyan

    2013-01-01

    On the basis of the basic concepts of radiation safety management system exemption, exclusion and clearance, we expound that the general industrial gaseous and liquid effluent discharges are exempted or excluded, gaseous and liquid effluent discharged from nuclear and radiation facilities are clearance, and non-radioactive. The main purpose of this paper is to clarify the concepts, reach a consensus that the gaseous and liquid effluent discharged from nuclear and radiation facilities are non-radioactive and have no hazard to human health and natural environment. (authors)

  9. Management of radioactive effluents from research Reactors and PHWRs

    International Nuclear Information System (INIS)

    Bodke, S.B.; Surender Kumar; Sinha, P.K.; Budhwar, R.K.; Raj, Kanwar

    2006-01-01

    Indian nuclear power programme is mainly based on pressurized heavy water reactors (PHWRs). In addition we have research reactors namely Apsara, CIRUS, Dhruva at Trombay. The operation and maintenance activities of these reactors generate radioactive liquid waste. These wastes require effective management so that the release of radioactivity to the environment is well within the authorized limits. India is self reliant in the design, erection, commissioning and operation of effluent management system for nuclear reactors. Segregation at source based on nature of effluents and radioactivity content is the first and foremost step in the over all management of liquid effluents. The effluents from the power reactors contain mainly activation products like 3 H. It also contains fission products like 137 Cs. Containment of these radionuclide along with 60 Co, 90 Sr, 131 I plays an important part in liquid waste management. Treatment processes for decontamination of these radionuclide include chemical treatment, ion exchange, evaporation etc. Effluents after treatment are monitored and discharged to the nearby water body after filtration and dilution. The concentrates from the processes are conditioned in cement matrix and disposed in Near Surface Disposal Facilities (NSDFs) co-located at each site. Some times large quantity of effluents with higher radioactivity concentration may get generated from the abnormal operation such as failure of heat exchangers. These effluents are handled on a campaign basis for which adequate storage capacity is provided. The treatment is given taking into consideration the required decontamination factor (DF), capacities of available treatment process, discharge limits and the availability of the dilution water. Similarly large quantities of effluents may get generated during fuel clad failure incident in reactors. In such situation, as in CIRUS large volume of effluent containing higher radioactivity are generated and are managed by delay

  10. Radioactive Effluents from Nuclear Power Plants Annual Report 2007

    International Nuclear Information System (INIS)

    2010-01-01

    This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2007. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

  11. Radioactive Effluents from Nuclear Power Plants Annual Report 2008

    International Nuclear Information System (INIS)

    2010-01-01

    This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2008. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

  12. Radioactive effluent monitoring at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Simpson, O.D.

    1975-01-01

    The Effluent and Radiation Measurements Laboratory at the Idaho National Engineering Laboratory (INEL) has recently upgraded capabilities in the field of monitoring and analysis of radioactive airborne and liquid effluents using the techniques of gamma-ray spectrometry. The techniques and equipment used include remotely-operated, computer-based Ge(Li) spectrometers which obtain data on a real-time basis. Permanent record files are maintained of both the effluent release values and the gamma-ray data from which the release values are calculated. Should values for release levels ever be challenged, the gamma-ray spectral information for any measurement can be recalled and analyzed as needed. Daily effluent release reports are provided to operating personnel which contributes to prompt correction of any operational problems. Monthly, quarterly, and annual reports are compiled which provide inventories of the radionuclides released. A description of the effluent monitoring, reporting and records system developed at INEL for this application will be presented

  13. Airborne radioactive effluents: releases and processing

    International Nuclear Information System (INIS)

    Grissom, M.C.

    1982-10-01

    This bibliography contains 870 citations on airborne radioactive waste included in the Department of Energy's Energy Data Base from January 1981 through August 1982. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

  14. Radioactive and electron microscope analysis of effluent monitor sample lines

    International Nuclear Information System (INIS)

    Kowalski, J.F.

    1986-01-01

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

  15. Principles for limiting releases of radioactive effluents into the environment

    International Nuclear Information System (INIS)

    1986-01-01

    This publication is concerned with the subject of limiting releases of radioactive effluents during normal, controlled operation of nuclear installations. It does not deal with releases from accidents where it is only possible to limit exposures by intervention. In 1978 the IAEA published guidance on the concepts and principles for use by the competent authorities in setting limits for planned releases of radioactive material into the environment (Safety Series No. 45). This publication is a complete revision of Safety Series No. 45 and its Annex

  16. Interpretation of the concepts of ALARA and bat for radioactive effluent releases from nuclear installation

    International Nuclear Information System (INIS)

    Chen Xiaoqiu

    2009-01-01

    Based on the understanding of the important concepts of both ALARA and BAT associated with the characteristics of effluent releases from the existing nuclear installations and the abatement techniques for effluents, this paper elaborates the principle of controlling radioactive effluent concentration from nuclear installation, that is based on the BAT focusing on the abatement techniques for effluents, introduces the good practice in the projects, and optimize the effluent releases with account taken of external factors such as the site condition. (authors)

  17. Management of effluents and radioactive wastes from nuclear power plants

    International Nuclear Information System (INIS)

    2005-01-01

    Management of effluents and radioactive waste from nuclear power plants, from the viewpoint of radiological protection, basically consists of three main themes: 1) developing and implementing actions that minimize, or where possible, eliminate generation. These actions ranging from simple awareness of people involved with the work on project modifications; 2) maintain a system of accounting and control that allows to know the characteristics of effluents and wastes, charting indicators that reveal the performance and trends of plant, and supplying data proving the compliance of national regulatory body standards; 3) Storing the solid waste generated in a safe manner, ensuring that the physical integrity of the packaged is maintained and that there is no impact to the population and the environment

  18. Packaging of radioactive sludges at the Saclay effluent processing plant

    International Nuclear Information System (INIS)

    Cerre, Pierre; Mestre, Emile; Bourdrez, Jean; Leconnetable, Jean

    1964-10-01

    The authors describe technical and technological aspects of the packaging workshop for radioactive sludges produced by processes of co-precipitation of Saclay effluents. This facility is an achievement of studies which aimed at improving working conditions for the plant staff. This workshop implements a process of solidification of filtered sludge by mixing with a hydraulic binding agent. After some generalities on the decontamination process applied to effluents produced by the Saclay research centre, the authors present and describe the adopted process, propose a physical description of the facility: building, chemical engineering equipment (filtration, packaging, and handling). They describe facility operation: introduction of a block into the cell, block filling, output of a packaged container. They briefly discuss the first results of facility exploitation [fr

  19. Processing of miscellaneous radioactive effluents by continous flocculation decantation

    International Nuclear Information System (INIS)

    Lundy, D.; Matton, P.; Petteau, J.L.; Roofthooft, R.

    1985-01-01

    In the nuclear power plant of Chooz an installation for flocculation and chemical precipitation has been built to treat miscellaneous radioactive effluents continuously. It is an industrial prototype of 5 m 3 /h resulting of several years of research, first on lab scale in a discontinous system and finally in a continuous pilot plant of small size (500 l/h). The process is based on the adsorption of radioactivity on a floc of copper-ferrocyanide precipitated by ferric chloride. The water is then filtered. After a series of preliminary tests and modifications, it has been possible to develop a technique which satisfies the specified decontamination conditions and to reduce the discharges of radioactivity to the Meuse to only 5 - 10% of the authorized limits. The process aims principally at the treatment of laundry waste, but other effluents such as drains from the rocks, pool water and used decontamination solutions (of the primary pumps) have been treated. A technico-economic evaluation of the process in comparison with evaporation is clearly in favour of the flocculation. 31 figs, 40 tables, 12 refs

  20. Siting considerations for radioactivity in reactor effluents during normal operation

    International Nuclear Information System (INIS)

    Graf, J.M.; Strom, P.O.

    1975-01-01

    In selecting a proper site for a nuclear power station, the consideration of radioactivity released in effluents can be handled in a straightforward manner using the U. S. Atomic Energy Commission's proposed Appendix I to 10 CFR 50, which gives numerical guidelines for design objectives for meeting the criterion ''as low as practicable'' for radioactive material in light-water-cooled nuclear power reactor effluents. By relating the release of radioactive material, the site meteorological conditions, and site boundary distance through appropriate dose models, the suitability of a given site can be determined. ''Rules of thumb'' for comparing anticipated releases to design objectives can be constructed for rapid assessment using the maximum permissible concentration values of 10 CFR 20 as dose factors. These rules of thumb tend to underpredict the allowed releases except in the case of radiocesium in liquids. For gaseous releases, these rules of thumb can be made up in convenient nomogram form for a quick assessment of allowed releases based on local site meteorological conditions. (U.S.)

  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. Radioactive effluents from CANDU 6 reactors during normal operation

    International Nuclear Information System (INIS)

    Boss, C.R.; Allsop, P.J.

    1995-12-01

    During routine operation of a CANDU 6 reactor, various gaseous, liquid, and solid radioactive wastes are generated. The layout of the CANDU 6 reactor and the design of its systems ensure that these are minimized, but small quantities of gaseous and liquid wastes are continually discharged at very low concentrations. This report discusses the make-up of these chronically generated gaseous and liquid effluents. From a safety perspective, the doses to individual members of the public resulting from radioactive wastes chronically discharged from CANDU 6 reactors have been negligible. Similarly, doses to the regional and global populations have been negligible, generally less than 0.001% of background. While far below regulatory limits, releases of tritium, noble gases and gross β - -γ have been the most radiologically significant emissions, while radioiodine and particulates have had the greatest potential to deliver public dose. (author). 8 refs., 16 tabs., 3 figs

  3. Environmental system applied to radioactive liquid effluent release

    International Nuclear Information System (INIS)

    Nisti, Marcelo Bessa

    2009-01-01

    The current environmental administration considers the productive activity as an environmental system, defined as a group of processes, interactions, parameters and factors involved in the production. This mastering dissertation evaluated the release of the liquid radioactive effluents at Instituto de Pesquisas Energeticas e Nucleares (IPEN), under a systemic environmental study. The study evaluated the source term at IPEN in the period from 2004 to 2008, making use of gamma-ray and alpha spectrometry, instrumental neutron activation analysis, liquid phase scintillation and atomic absorption spectrometry. The employed methodologies were verified using samples from the Intercomparison National Program - PNI/IRD and Reference Materials. The facilities that contributed the most in these releases were the Radiopharmaceutical Center (CR) and the Research Reactor Center (CRPq) with an average of 11,4% and 87,4%, respectively, relative to the present radioactive activity. The sewer system releases were within the radioactive protection regulations, showing the effectiveness of IPEN's Radioactive Effluents Monitoring Program. The concentration of the stable elements Ag, Cd, Cr, Fe, Mn, Ni, Pb and Zn was determined in the liquid effluent in ali the samples from the storage tanks TR1 and CR in the period from 2004 to 2008 and in some of the samples of other IPEN's facilities in the period from 2004 to 2007. Among the analyzed effluents, two samples were higher than the stable elements discharge standards established in the state of Sao Paulo, one sample was higher than the required value of the element cadmium and the other higher than required value of the element zinco The storage tank TR1 discharge flow was estimated in 10,9 ± 0,9 m3 h -1 . The dilution factor at discharge point E1 was estimated using a radiotracers the isotopes 3 H, 137 CS, 60 Co, 54 Mn and 65 Zn, which are commonly released into IPEN's sewer system. The executed radiotracer study was carried out

  4. Monitoring of released radioactive gaseous and liquid effluent at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Oka, M.; Keta, S.; Nagai, S.; Kano, M.; Ishihara, N.; Moriyama, T.; Ogaki, K.; Noda, K.

    2009-01-01

    Rokkasho Reprocessing Plant (RRP) Rokkasho Reprocessing Plant started its active tests with spent fuel at the end of March 2006. When spent fuels are sheared and dissolved, radioactive gaseous effluent and radioactive liquid effluent such as krypton-85, tritium, etc. are released into the environment. In order to limit the public dose as low as reasonably achievable in an efficient way, RRP removes radioactive material by evaporation, rinsing, filtering, etc., and then releases it through the main stack and the sea discharge pipeline that allow to make dispersion and dilution very efficiently. Also, concerning the radioactive gaseous and liquid effluent to be released into the environment, the target values of annual release have been defined in the Safety Rule based on the estimated annual release evaluated at the safety review of RRP. By monitoring the radioactive material in gaseous exhaust and liquid effluent RRP controls it not to exceed the target values. RRP reprocessed 430 tUpr of spent fuel during Active Test (March 2006 to October 2008). In this report, we report about: The outline of gaseous and liquid effluent monitoring. The amount of radioactive gaseous and liquid effluent during the active test. The performance of removal of radioactive materials in gaseous and liquid effluents. The impact on the public from radioactive effluents during the active test. (author)

  5. Regulatory review of releases from HIFAR of radioactive airborne effluent

    International Nuclear Information System (INIS)

    Westall, D.J.; Macnab, D.I.

    1996-01-01

    Full text: The Nuclear Safety Bureau (NSB) was set up by legislation in 1992 as an independent Commonwealth corporate body reporting to the Minister for Health and Family Services. Its functions include monitoring and reviewing the safety of nuclear plant owned or operated by the Australian Nuclear Science and Technology Organisation (ANSTO). The NSB sets requirements for authorisation of the operation of the HIFAR research reactor, and may impose restrictions and conditions on its operation. The authorisation for the operation of HIFAR includes a requirement for arrangements for the treatment, safe storage and disposal of solid, liquid and gaseous radioactive wastes from the reactor. The objective is to establish conditions which would ensure that radiation exposure to plant personnel and the public from radioactive wastes are within acceptable limits and that releases are maintained as low as reasonably achievable. The NSB has developed expectations based on international best practice, against which to review HIFAR's arrangements for satisfying the requirement and achieving the objective. Arrangements for the release of airborne radioactive effluent from HIFAR were reviewed by the NSB as part of an overall review of the upgrade of safety documentation for HIFAR. The NSB's expectations for the review were drawn from the International Atomic Energy Agency (IAEA) Basic Safety Standards (Safety Series No 115-I) and the National Health and Medical Research Council (NHMRC) Recommendations for Limiting Exposure to Ionizing Radiation (1995). These expectations included a hierarchy of primary dose limits, stack discharge limits and reference levels for HIFAR aimed at ensuring that radiation doses to the public due to airborne effluent are less than the national dose limits and ANSTO's dose constraints, and are as low as reasonably achievable. An approach favoured by the operator is to work directly to a primary dose limit using an airborne dispersion computer program to

  6. Control verification radioactive effluent discharges to the environment

    International Nuclear Information System (INIS)

    Alvarez, D.E.; Czerniczyniec, M.A.; Amado, V.A.; Curti, A.R.; Lee Gonzáles, H.M.

    2015-01-01

    The National Law of Nuclear Activity No. 24,804 establishes that the Nuclear Regulatory Authority (ARN) will be responsible for the function of regulation and control of nuclear activity, grant, suspend and revoke licenses, permits or authorizations and to issue regulatory standards on radiation and nuclear safety. According to the latter the ARN has issued a set of rules that make up the regulatory framework for nuclear activity. This includes the standards that determine the radiological criteria for controlling the release of radioactive effluents which were established to protect members of the public. In the process of licensing a facility, the ARN determines the authorized discharge of gaseous and liquid effluents which must comply with the installation values. These annual values are understood as an operating restriction (OR) and arise from the activity of each relevant radionuclide present in the discharge. For this is taken as a reference the level of optimized discharge considering an appropriate margin of flexibility to ensure public protection without interfering with the operation of the installation. This paper presents the results of the review of the above criteria and methodology for calculating the RO adopted by the RNA present. [es

  7. 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)

  8. A unique criterion for the classification of the activity of radioactive effluents according to the activity

    International Nuclear Information System (INIS)

    Tasovac, T.; Bojovic, P.; Svabic, A.

    1964-10-01

    The present classification of radioactive effluents into categories, i.e. low, medium, high and very high activity, has not been given a definite criterion. Therefore, some categories include specific activities from 2-6 and more potentials. Therefore, it occurs that the category of medium active effluents in one nuclear center is indicated as low active in the second or as highly active in the third. Therefore, a proposal is given in this paper for a unique criterion for the classification of radioactive effluents according to their activities. This proposal is based on the decontamination factors obtained by various methods and the maximum permissible concentrations of radioactive isotopes in water (author)

  9. Process and device for conditioning low and medium activity radioactive effluents with hydraulic binders

    International Nuclear Information System (INIS)

    Jaouen, C.; Magnin, G.; Renault, G.

    1986-01-01

    Chemical processing of borated radioactive effluents is claimed. Tetrahydrated calcium borate crystals are prepared by lime additions, the volume is reduced by evaporation under reduced pressure and the product obtained is mixed with hydraulic binders [fr

  10. Studies for improvement of regulatory control on the radioactive effluent released from nuclear facilities

    International Nuclear Information System (INIS)

    Cheong, Jae Hak; Park, H. M.; Song, M. C.; Lee, K. H.; Jang, J. K.; Chun, J. K.; Jeong, K. H.

    2005-05-01

    This report contains the second-year results of the research project titled 'Studies for Improvement of Regulatory Control on the Radioactive Effluent Released from Nuclear Facilities' and mainly provides technical and strategic approaches to improve performance of regulatory control on the gaseous effluent released from domestic nuclear facilities. The main result contained here includes overview and technical bases of radioactive gaseous effluent control (Chapter 1), reconsideration of the sensitivity requirements for measurement of radioactivity in gaseous effluent sample (Chapter 2), uncertainty analysis of the calculated radioactivity in gaseous effluent (Chapter 3), and improvement of quantification method of noble gas releases (Chapter 4). In addition, analysis of the impact due to combined sampling of particulate from multiple release points (Chapter 5), comparison of domestic nuclear reactors gaseous effluent data to foreign PWRs (Chapter 6), standardized sampling technique for collection of gaseous tritium (Chapter 7), and application of Xe-133 equivalent concept to gaseous effluent control (Chapter 8) are also provided. As a whole, this report provides a generic approach to improve the performance of regulatory control on the gaseous effluent. Therefore, actual enforcement of the recommendations should be preceded by establishment of a series of action plans reflecting on the site- and facility-specific design and operational features

  11. Study about the integrated treatment of chemical and radioactive effluents, introducing the zero release concept

    International Nuclear Information System (INIS)

    Mierzwa, Jose Carlos

    1996-01-01

    An Integrated System to the treatment of Chemical and Radioactive Effluents to the Centro Experimental Aramar is proposed and evaluated, introducing the Effluent Zero Release concept, where factors related to the environmental regulation in vigor in the country, as well as the availability of hydrological resources in the place where CEA have been implanted, are considered. Through a literature analysis of the main effluents treatment techniques available nowadays and after a case of study selection, take into account two industrial installations that will be implanted at CEA, it was defined an arrangement to compose the Integrated System to the Treatment of Chemicals and Radioactive Effluents, focusing the Zero Release concept consolidation. A defined arrangement uses a combination among three treatment processes, it means chemical precipitation, reverse osmosis and evaporation, that were experimentally evaluated. The proposed arrangement was evaluated using synthetic effluents, that were prepared based on data from literature and conception documents of the installation considered in this work. Three kinds of effluents were simulated, one arising from a nuclear reactor laundry, one arising from the water refrigeration system and demineralized water production to the nuclear reactor and the other one arising from a nuclear material production laboratory. Each effluent were individually submitted to the selected treatment processes, to get the best operational conditions for each treatment process. The results got during the laboratory assays show that the proposed Integrated System to the Treatment of Chemicals and Radioactive Effluents is feasible, consolidating the Effluent Zero Release concept, which is the proposition of this work. (author)

  12. Palisades Nuclear Plant. Radioactive effluents and environmental monitoring sections to second annual operating report

    International Nuclear Information System (INIS)

    1977-01-01

    A total of 0.435 Ci of radioactive liquid effluent less tritium was released with 19.63 Ci of tritium. Both liquid and gaseous releases were within permissible limits. There were 8 Ci of solid wastes stored on the site as of 12/31/76. Data clearly shows there was no detectable increase in radioactivity levels in the environmental media that can be attributed to plant effluents. Monitoring reports are presented concerning fish, meteorology, noise, and cooling tower drift

  13. Computerising documentation

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    The nuclear power generation industry is faced with public concern and government pressures over safety, efficiency and risk. Operators throughout the industry are addressing these issues with the aid of a new technology - technical document management systems (TDMS). Used for strategic and tactical advantage, the systems enable users to scan, archive, retrieve, store, edit, distribute worldwide and manage the huge volume of documentation (paper drawings, CAD data and film-based information) generated in building, maintaining and ensuring safety in the UK's power plants. The power generation industry has recognized that the management and modification of operation critical information is vital to the safety and efficiency of its power plants. Regulatory pressure from the Nuclear Installations Inspectorate (NII) to operate within strict safety margins or lose Site Licences has prompted the need for accurate, up-to-data documentation. A document capture and management retrieval system provides a powerful cost-effective solution, giving rapid access to documentation in a tightly controlled environment. The computerisation of documents and plans is discussed in this article. (Author)

  14. Improved technique for in situ measurement of radioactivity in liquid effluents

    International Nuclear Information System (INIS)

    Balasundar, S.; Jose, M.T.; Ravi, T.; Sundaram, V.M.; Raghunath, V.M.

    1993-01-01

    As a pre-requisite for handling and disposal of radioactive liquid effluents, they should be categorized according to their chemical nature and the type and level of radioactivity. A continuous monitoring of these effluents is necessary to assess the discharged activity and to detect any unusually large increase in the activity level. It may also be required to assess the beta, gamma specific activities in the effluents independently instead of just combined beta-gamma activity as is generally done. (author). 1 ref., 2 tabs

  15. Radioactive effluent sources and special system of channels on the RA Reactor at the Boris Kidric Institute

    International Nuclear Information System (INIS)

    Bojovic, P.; Gacinovic, O.; Milosevic, M.

    1964-10-01

    The paper describes the place of origin, composition and activity of radioactive effluents appearing in some reactor systems and special channels for carrying these effluents to disposal basins located outside the reactor building (author)

  16. Estimation of radioactive effluents dispersion from the nuclear power plants in Yugoslavia surrounding

    International Nuclear Information System (INIS)

    Vehauc, A.

    1997-01-01

    The computational method for atmospheric dispersion of radioactive effluents is applied to the nuclear power plants in Yugoslavia surrounding. On the basis of computation results, ground level concentrations and washout of radioactive nuclides on exposed Yugoslav territories during unfavourable meteorological conditions are estimated. (author)

  17. Gaseous radioactive effluent restrictions, measurement, and minimization at a PET/cyclotron facility

    International Nuclear Information System (INIS)

    Plascjak, P.S.; Kim, K.K.; Googins, S.W.; Meyer, W.C. Jr.

    1993-01-01

    In the US, restrictions on the release of radioactive effluents from PET (positron emission tomography)/cyclotron facilities are typically imposed by State regulatory agencies and may be based on various methodologies and limits published by numerous agencies. This work presents suitable effluent concentration limits for various chemical forms of radioisotopes routinely produced in PET/cyclotron facilities. They were determined by application of metabolic models defined by ICRP 53 and ICRP 26/30 which will result in compliance with effective dose equivalent limits of 100 mrem per year at the release point. The NIH Cyclotron Facility effluent air monitoring system, environmental dosimetry program, and simple, effective systems for radioactive effluent minimization are also described. (orig.)

  18. Consideration of radioecological studies in French regulations on the discharges of radioactive effluents

    International Nuclear Information System (INIS)

    Hebert, J.

    1980-01-01

    For each of the lines of approach of the regulations on radioactive effluent discharges utilized in France, the report examines the place of radioecology. Developments in greater depth will be devoted to the preliminary and definitive studies foreseen by the conditions of effluent discharges coming from the base nuclear facilities. The place of radioecology in general international law on pollution across national borders or of the sea will also be examined [fr

  19. The discharge of radioactive effluents from the nuclear power programme into western waters of Great Britain

    International Nuclear Information System (INIS)

    Allday, C.

    1977-01-01

    A brief account is presented of the British nuclear power programme and the types of radioactive effluent that arise from the power stations and from the Windscale reprocessing plant. Routes by which these effluents could affect human populations, and radiation dose limits which have been laid down, are discussed. The discharge of permitted amounts of activity into western coastal waters of Great Britain, and the requirements for monitoring the discharges, are described. (U.K.)

  20. Estimation of radioactive effluents concentrations in the vicinity of nuclear power plant

    International Nuclear Information System (INIS)

    Arsov, Lj.

    1977-01-01

    This paper deals with the problem of mathematical prediction of radioactive effluent concentrations around nuclear power plants. This mathematical model which describes the behaviour of the effluent in the atmosphere here in after is expanded and adapted for radioactive effluent treatment. In this way the mathematical model includes the description of the following effects: the rise of plume caused by its vertical momentum and its heat content, wind velocity profile and vertical growth of the coefficient of diffusion, fallout under gravity, ground deposition, precipitation scavenging, and radioactive decay. The advanced computer program DIFFUS has been applied to evaluate the ground concentration of the nuclides of I, which constitute the greatest risk for population.(author)

  1. Elimination of slightly radioactive liquid effluent by dilution. Its consequences (1960)

    International Nuclear Information System (INIS)

    Bovard, P.; Candillon, C.

    1960-01-01

    Nuclear centres often have to solve problems raised by the elimination of large volumes of slightly radioactive liquid effluent. As things stand at present, the method usually adopted consists in expelling this effluent into the main water system in order to dilute it to a maximum, and thus to lower its radioactive isotope concentration to below the norms imposed by the Public Health Service. This technique requires systematic checking of the water system and its dependences, and demands a thorough knowledge of adsorption and fixation processes. (author) [fr

  2. Process for processing and conditioning radioactive effluents of low and medium activity

    International Nuclear Information System (INIS)

    Taponier, Jean; Pierlas, Rene.

    1979-01-01

    Preferably continuous process for processing radioactive effluents of low and medium activity, comprising an effluent pre-treatment: precipitation of radioactive compounds to form a stable suspension that can be concentrated. Then a mix is made of 0.6 to 2 parts of cement by weight for one part by weight of suspension, from 0.5 to 5% by weight, in relation to the cement, of asbestos fibre and, if necessary, added water for the cement to set, this suspension containing from 15 to 75% by weight of dry extract and a suspension agent. The homogeneous mix achieved is poured into a container [fr

  3. The use of PHP in the radioactive effluent treatment in rare earth industry

    International Nuclear Information System (INIS)

    Shitang, Q.; Ruensheng, W.

    1985-01-01

    Monazite is one of the most important rare earth resources, processing monazite, however, is accompanied by radioactive effluent that needs treatment. A satisfactory treatment should be able not only to insolubilize the radioactive isotopes but also to clarify the suspension quickly and completely. In this study, out of 15 different coagulants, partially hydrolyzed polyacrylamide (PHP) of molecular weight 1000 has been chosen as the most efficient one for the clarification of the treated effluent in question. Satisfactory performance has been attained in a continuous clarifier

  4. Treatment of radioactive effluents at the Boris Kidric Institute; Postupak sa radioaktivnim elementima u Institutu Boris Kidric

    Energy Technology Data Exchange (ETDEWEB)

    Bojovic, P; Drobnik, S; Popara, D [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1964-10-15

    The paper describes the origin, composition and activity of radioactive effluents at the Boris Kidric Institute, their collection at the places or origin, transport to the place of disposal and treatment of some smaller quantities. Special attention has been paid to effluents with short-lived isotopes produced in the Laboratory for radioactive isotope production (author)

  5. High sensitivity on-line monitor for radioactive effluent

    Energy Technology Data Exchange (ETDEWEB)

    Sasaki, Toshimi [Tohoku Electric Power Co. Ltd., Sendai (Japan); Ishizuka, Akira; Abe, Eisuke; Inoue, Yasuhiko; Fujii, Masaaki; Kitaguchi, Hiroshi; Doi, Akira

    1983-04-01

    A new approach for a highly sensitive effluent monitor is presented. The free flow type monitor, which consists of a straightener, nozzle, monitoring section and ..gamma..-ray detector, is demonstrated to be effective in providing long term stability. The 160 start-and-stop cycles of effluent discharge were repeated in a 120-h testing period. Results showed a background increase was not observed for the free flow type monitor. The background count rate was calibrated to the lowest detection limit to be 2.2 x 10/sup -2/ Bq/ml for a 300 s measurement time.

  6. Radioactive effluents in the Savannah River: Summary report for 1989

    International Nuclear Information System (INIS)

    Winn, W.G.

    1991-09-01

    Researchers at the Savannah River Site have low-level radiometric studies of the Savannah River to distinguish between the effluent contributions of the Savannah River Site and Plant Vogtle. Since the startup of Plant Vogtle in 1987, researchers have routinely detected neutron-activated isotopes in controlled releases, but all have routinely detected neutron-activated isotopes in controlled releases, but all have been well below the Department of Energy's (DOE) guidelines. The study has found that processing improvement at Plant Vogtle during 1989 have lowered the activities of effluents from Plant Vogtle. These studies will continue on a routine basis because they provide disturbing trends before actual health concerns evolve

  7. Radioactive effluents, Portsmouth Gaseous Diffusion Plant, calendar year 1982

    International Nuclear Information System (INIS)

    Acox, T.A.; Hary, L.F.; Klein, L.S.

    1983-03-01

    Radioactive discharges from the Portsmouth Gaseous Diffusion Plant are discussed and tabulated. Tables indicate both the location of the discharge and the nuclides discharged. All discharges for 1982 are well below the Radioactive Concentration Guide limits specified in DOE Order 5480.1, Chapter XI. 1 figure

  8. Proposed radioactive liquid effluent monitoring requirements at the Savannah River Site

    International Nuclear Information System (INIS)

    Jannik, G.T.; Carlton, W.H.; Blunt, B.C.

    1994-01-01

    Clear regulatory guidance exists for structuring a radiological air monitoring program, however, there is no parallel guidance for radiological liquid monitoring. For Department of Energy (DOE) facilities, there are no existing applicable federal regulations, DOE orders, or DOE guidance documents that specify at what levels continuous monitoring, continuous sampling, or periodic confirmatory measurements of radioactive liquid effluents must be made. In order to bridge this gap and to technically justify and document liquid effluent monitoring decisions at DOE's Savannah River Site, Westinghouse Savannah River Company has proposed that a graded, dose-based approach be established, in conjunction with limits on facility radionuclide inventories, to determine the monitoring and sampling criteria to be applied at each potential liquid radioactive effluent point. The graded approach would be similar to--and a conservative extension of--the existing, agreed-upon SRS/EPA-IV airborne effluent monitoring approach documented in WSRC's NESHAP Quality Assurance Project Plan. The limits on facility radionuclide inventories are based on--and are a conservative extension of--the 10 CFR 834, 10 CFR 20, and SCR 61-63 annual limits on discharges to sanitary sewers. Used in conjunction with each other, the recommended source category criteria levels and facility radionuclide inventories would allow for the best utilization of resources and provide consistent, technically justifiable determinations of radioactive liquid effluent monitoring requirements

  9. Assessment of Radioactive Liquid Effluents Release at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Bessa Nisti, Marcelo; Godoy dos Santos, Adir Janete

    2008-01-01

    A continuous effluent monitoring program has been established at IPEN's plant in order to allow an environmental impact assessment due to radioactive liquid effluent discharge to sanitary system. Representative samples of radioactive liquid effluents are analyzed by using high resolution gamma spectroscopy and instrumental neutron activation analysis, facing to Brazilian radioprotection regulatory rules. The results are consolidating yearly in the Institute source-term. In this paper, results of the source-term are presented, concerning to years 2004, 2005 and 2006. The total activity discharged was 8.5xl0 8 Bq, 5.7x10 8 Bq and 2.7xl0 8 Bq, respectively. As the release is strongly dependent on the total amount of the effluent and on the dilution factor, special attention is needed in order to obtain the correct value of that last one. The estimated inside plant dilution factor, considering the recent facilities and the reshaping of the sewerage system was 80, 180 and 130, for period of 2004, 2005 and 2006 discharged liquid radioactive effluent

  10. Recommended parameters for effect assessment of radioactive airborne effluents under normal condition of nuclear facilities

    International Nuclear Information System (INIS)

    Li Hong; Fang Dong; Sun Chengzhi; Xiao Naihong

    2003-01-01

    A set of models and default parameters are recommended for effect assessment of radioactive airborne effluents under normal condition of nuclear facilities in order to standardize the environmental effect assessment of nuclear facilities, and to simplify the observation and investigation in early phase. The paper introduces the input data and default parameters used in the model

  11. Radioactive effluents, Portsmouth Uranium Enrichment Complex, calendar year 1983

    International Nuclear Information System (INIS)

    Acox, T.A.; Klein, L.S.

    1984-03-01

    Radioactive discharges from the Portsmouth Uranium Enrichment Complex are discussed and tabulated. Tables indicate both the location of the discharge and the nuclides discharged. Routine discharges for 1983 are well below the Radioactive Concentration Guide limits specified in DOE Order 5480.1, Chapter XI. There was, however, an unplanned release in December from the X-326 Building Side Purge which exceeded the limits. 1 figure

  12. Introduction of a cation in aqueous solution by electrolytic dissolution of metal. Applications to the decontamination of radioactive effluents

    International Nuclear Information System (INIS)

    Gauchon, Jean-Paul

    1979-01-01

    This research thesis aims at comparing results obtained in chemical decontamination of radioactive effluents with a metallic cation introduced by metal electro-dissolution or by dose addition. After an overview of methods used for the purification of radioactive effluents and a more precise presentation of chemical co-precipitation, the author reports preliminary tests of the application of chemical co-precipitation to the decontamination of radioactive effluents, reports the analysis of iron, zinc and copper behaviour in aqueous environment by means of thermodynamic diagrams and current-voltage curves. He reports the design and use of two electro-dissolution sets, and the application of copper electrolytic dissolution to the elimination of ruthenium in radioactive effluents. He finally addresses the purification treatment of effluents of nuclear reactors

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

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  14. Treatment of radioactive effluents by concentration in an installation with natural evaporation

    International Nuclear Information System (INIS)

    Wormser, G.; Chauvet, P.

    1963-01-01

    This document reports natural evaporation tests performed in Cadarache, notably to adapt the equipment to the treatment of radioactive effluents. After a brief description of the apparatus principle and operation, the authors propose a summary of the first test campaign (test apparatus, results), indicate modifications brought to the apparatus by taking the first results into account, and propose a detailed discussion of results obtained during the second test campaign. They finally discuss the possibility of concentration of effluents by means of natural evaporation [fr

  15. Tests of the use of cation exchange organic resins for the decontamination of radioactive aqueous effluents

    International Nuclear Information System (INIS)

    Bourdrez, Jean; Girault, Jacques; Wormser, Gerald

    1962-01-01

    The authors report tests performed in laboratory and results obtained during an investigation of the use of synthetic ion exchangers for the decontamination of radioactive effluents of moderate activity level and with a non neglectable salt loading. Resins are used under sodium form and regenerated after each fixing operation. Once decontaminated and free of its disturbing ions, the regenerating agent (NaCl) is used for several operations. The authors present the used resins, the treated effluents, describe the tests, and discuss the obtained results [fr

  16. Realization of sanitary requirements concerning standardization of rare radioactive gas effluents at NPPs

    International Nuclear Information System (INIS)

    Doroshenko, G.G.; Panchenko, S.V.; Chudajkin, O.G.

    1987-01-01

    The paper is aimed at determination of ways for practical realization of main sanitary requirements concerning environment and population protection under NPP operation. The idea of the requirements is reduced to not increasing permissible limits for radiation doses, minimum irradiation of population and decrease of unjustified irradiation of personnel. The given problem may be fully solved only in case of studying real chacteristics of operating reactors, taking into account statistic nature of effluents of inert radioactive gases (IRG). Methods of developing a system of working and reference standards of IRG effluents at NPPs are suggested. The considered approach may be realized in practice as the All-Union state on branch standards

  17. Treatment of Radioactive Effluents at the Saclay Nuclear Research Centre

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, Gerald [Atomic Energy Commission, Saclay (France)

    1960-07-01

    Investigations have also been made at Saclay to find out if the soil at the Centre could be used to receive SNRC effluents. The Saclay plateau is a sand plateau 75 m thick on a clay base (2). Its upper surface is covered by a heterogeneous layer of clay containing pieces of grindstone of varying sizes. The ion-exchange capacity of this soil is considerable, 25 meq/100 g. Low-activity waste could therefore be discharged into it, especially since the plateau has no lateral water outcrops of any size and underground water does not reappear for a long time. This method of disposal is still only experimental. It was tested with a solution of Sr{sup 90} and tritium having an activity equal to the permitted levels.

  18. Releases of radioactivity from uranium mills and effluent treatment costs

    International Nuclear Information System (INIS)

    Witherspoon, J.P.; Sears, M.B.; Blanco, R.E.

    1977-01-01

    Airborne releases of radioactive materials from uranium milling to the environment consist of ore dust, yellowcake dust, tailings dust, and radon gas while the mill is active. After a mill has ceased operations, tailings may be stabilized to minimize or prevent airborne releases of radioactive particulates. However, radon gas will continue to be released in amounts inversely proportional to the degree of stabilization treatment (and expense). Liquid waste disposal is by evaporation and natural seepage to the ground beneath the tailings impoundment area. The release of radioactive materials (and potential radiation exposures) determines the majority of costs associated with minimizing the environmental impact of uranium milling. Radwaste treatments to reduce estimated radiation doses to individuals to 3 to 5% of those received with current milling practices are equivalent to $0.66 per pounds of U 3 O 8 and 0.032 mill per kWhr of electricity. This cost would cover a high efficiency reverse jet bag filter and high energy venturi scrubbers for dusts, neutralization of liquids, and an asphalt-lined tailings basin with a clay core dam to reduce seepage. In addition, this increased cost would cover stabilization of tailings, after mill closure, with a 1-in. asphalt membrane topped by 2 ft of earth and 0.5 ft of crushed rock to provide protection against future leaching and wind erosion. The cost of reducing the radiological hazards associated with uranium milling to this degree would contribute about 0.4% to the current total cost of nuclear power

  19. Computerised Axial Tomography (CAT)

    Science.gov (United States)

    1990-06-01

    Ministry of’ Defence, Defence Research Information Centre, UK. Computerised Axial Tomography ( CAT ) Report Secufty C"uMiauion tide Onadtiicadon (U. R, Cor S...DRIC T 8485 COMPUTERISED AXIAL TOMOGRAPHY ( CAT ) F.P. GENTILE, F. SABETTA, V. TRO1* ISS R 78/4.Rome, 1.5 Mlarch 1978 (from Italian) B Distribution(f...dello Radiazioni ISSN 0390--6477 F.P. GENTILE, F. SABETTA. V. TROI Computerised Axial Tomography ( CAT ) March 15, 1978). This paper is a review of

  20. Processing and monitoring liquid, radioactive effluents from the Wiederaufarbeitungsanlage Karlsruhe

    International Nuclear Information System (INIS)

    Hoehlein, G.; Huppert, K.L.; Winter, M.

    1977-01-01

    The Wiederaufarbeitungsanlage Karlsruhe (WAK) serves as a demonstration plant for the processing of highly-irradiated uranous oxide. The high active waste concentrates find interim storage at the WAK until they are solidified at a later stage. In contrast to this, the slightly- and the medium-active liquid wastes are transported to the decontamination facility of the Nuclear Research Centre Karlsruhe, where they are immediately processed. These liquid wastes contain about 1 per thousand of the activity inventary of the fuel elements processed. Monitoring of the radioactive waste water of the WAK is carried out by the Nuclear Research Centre's department radiation protection and safety. (orig.) [de

  1. Effective equivalent dose in the critical group due to release of radioactive effluents

    International Nuclear Information System (INIS)

    Santos, John W.A. dos; Varandas, Luciana R.; Souza, Denise N.; Souza, Cristiano B.F.; Lima, Sandro Leonardo N.; Mattos, Marcos Fernando M.; Moraes, Jose Adenildo T.

    2005-01-01

    To ensure that the emissions of radioactive material by liquid and gaseous pathways are below applicable limits it is necessary to evaluate the effective equivalent dose in the critical group, which is a magnitude that takes into consideration the modeling used and the terms radioactive activity source. The calculation of this dose considers each radionuclide released by the activity of Nuclear plant, liquid and gaseous by, and the sum of the values obtained is controlled so that this dose does not exceed the goals of the regulatory body, the CNEN and the goals established by the Nuclear power plant. To hit these targets various controls are used such as: controls for effluent monitors instrumentation, environmental monitoring programs, effluent release controls and dose calculation in the environment. According to the findings, it is concluded that during the period of operation of the plants, this dose is below of the required limits

  2. Effluent monitoring Quality Assurance Project Plan for radioactive airborne emissions data. Revision 2

    International Nuclear Information System (INIS)

    Frazier, T.P.

    1995-12-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for compiling Hanford Site radioactive airborne emissions data. These data will be reported to the U.S. Environmental Protection Agency, the US Department of Energy, and the Washington State Department of Health. Effluent Monitoring performs compliance assessments on radioactive airborne sampling and monitoring systems. This Quality Assurance Project Plan is prepared in compliance with interim guidelines and specifications. Topics include: project description; project organization and management; quality assurance objectives; sampling procedures; sample custody; calibration procedures; analytical procedures; monitoring and reporting criteria; data reduction, verification, and reporting; internal quality control; performance and system audits; corrective actions; and quality assurance reports

  3. Development of carrier usage for the treatment of radioactive effluent

    Energy Technology Data Exchange (ETDEWEB)

    Kahraman, A [Cekmece Nuclear Research and Training Center, Istanbul (Turkey)

    1997-02-01

    Low level radioactive liquid wastes are produced in many nuclear applications. Their physico-chemical characteristics may very considerably. Chemical precipitation is a convenient treatment method for the liquid streams of high salinity or solid content containing different radionuclide types. Generally, the concentrations of nuclides in liquid wastes are extremely low. For example, 1000 Bq of {sup 137}Cs makes about 3{center_dot}10{sup -10} g of caesium. Therefore conventional precipitation cannot be applied since the solubility product value is not exceeded. The carriers which are capable to adsorb the nuclides are used to achieve the nuclide removal. Stable isotopes of the nuclide are usually added as the carriers but any reagent which has similar chemical specifications with the nuclide can also be used as the carrier. Precipitation of these non-radioactive carriers ion together with the radionuclide is called co-precipitation. The operational steps of the chemical precipitation process should be established and applied in a treatment facility. Thus, the most suitable carrier for a particular nuclide and its usage conditions are required to be determined. In this study, the carriers for removal of {sup 137}Cs and uranium, their accurate amounts and usage conditions to achieve highest decontamination factors (DF) have been investigated. Residual sludge volumes were evaluated for cementation purposes. The cement composite samples were prepared for each set of experiments and hardening times were measured. 9 refs, 9 figs.

  4. Development of carrier usage for the treatment of radioactive effluent

    International Nuclear Information System (INIS)

    Kahraman, A.

    1997-01-01

    Low level radioactive liquid wastes are produced in many nuclear applications. Their physico-chemical characteristics may very considerably. Chemical precipitation is a convenient treatment method for the liquid streams of high salinity or solid content containing different radionuclide types. Generally, the concentrations of nuclides in liquid wastes are extremely low. For example, 1000 Bq of 137 Cs makes about 3·10 -10 g of caesium. Therefore conventional precipitation cannot be applied since the solubility product value is not exceeded. The carriers which are capable to adsorb the nuclides are used to achieve the nuclide removal. Stable isotopes of the nuclide are usually added as the carriers but any reagent which has similar chemical specifications with the nuclide can also be used as the carrier. Precipitation of these non-radioactive carriers ion together with the radionuclide is called co-precipitation. The operational steps of the chemical precipitation process should be established and applied in a treatment facility. Thus, the most suitable carrier for a particular nuclide and its usage conditions are required to be determined. In this study, the carriers for removal of 137 Cs and uranium, their accurate amounts and usage conditions to achieve highest decontamination factors (DF) have been investigated. Residual sludge volumes were evaluated for cementation purposes. The cement composite samples were prepared for each set of experiments and hardening times were measured. 9 refs, 9 figs

  5. Radioactive liquid effluent management - state of art and the role of membrane processes

    International Nuclear Information System (INIS)

    Panicker, S.T.; Prabhakar, S.; Misra, B.M.; Ramani, M.P.S.

    1990-01-01

    This report reviews the conventional methods involving filtration, chemical precipitation, evaporation and ion exchange, employed for the treatment of low level radioactive effluents. The role of membrane processes, particularly reverse osmosis and ultrafiltration has been assessed with a view to increase the effectiveness of the existing methods. After overviewing the practices followed in major countries, a possible scheme has been proposed. (author). 66 refs., 4 tabs., figs

  6. Analysis of adaptability of radioactive liquid effluent discharge under normal condition of inland nuclear power plant

    International Nuclear Information System (INIS)

    Xu Yueping; Zhang Bing; Chen Yang; Zhu Lingqing; Tao Yunliang; Shangguan Zhihong

    2011-01-01

    The discharge of radioactive liquid effluent from inland nuclear power plant under normal operation is an important part to be considered in environmental impact assessment. Requirements of newly revised and upcoming standards GB 6249 and GB 14587 are introduced in this paper. Through an example of an inland NPP siting in the preliminary feasibility study phase, the adaptability to the relevant regulations in the site selection is analyzed. Also, the concerned problems in the design of AP1000 units are addressed. (authors)

  7. The regulation of radioactive effluent release in France (mainly from large nuclear installations)

    International Nuclear Information System (INIS)

    Hebert, Jean.

    1978-01-01

    In parallel with the licensing system for construction and operation of classified or so-called large nuclear installations (INB) there are in France regulations for the release of radioactive effuents from such installations. The regulations applicable to installations other than INBs are not specifically of a nuclear nature, while those covering INBs, which are analysed in this study, in particular, cover effluent release in liquid or gaseous form. The licensing and control procedures for such release are analysed in detail. (NEA) [fr

  8. Radiation protection requirements in the limitation of the release of radioactive effluents

    International Nuclear Information System (INIS)

    Beninson, D.

    1978-01-01

    The paper summarizes the requirements of radiation protection, as presented in the new ICRP recommendation, in relation to the limitation of the release of radioactive effluents. The concepts of effective dose equivalent and collective dose equivalent are used in the presentation of the optimization procedures and the dose limitation to individuals. The dose commitment is used for the procedures applied to control future exposures. An appendix describes the basic concepts and quantities used in assessments of human exposures and risks. (author)

  9. Experiences in radioactive gaseous effluent management in JAERI

    International Nuclear Information System (INIS)

    Yoshida, Y.; Matsui, H.; Yamamoto, H.; Ikezawa, Y.; Hirayama, K.; Kokubu, M.

    1983-01-01

    In the Japan Research Reactor-II (JRR-2), the main source of 41 Ar generation is the exhaust air from the horizontal experimental holes and the pneumatic tubes. For the horizontal experimental holes, the flow of exhaust air through the holes was decreased by improving the airtightness, and a decay duct of capacity 2.4 m 3 was installed in the middle of the exhaust line. In consequence, the release rate of 41 Ar was reduced by 6-8%. For the pneumatic tubes, a mechanical shutter was installed in the tube. The shutter stops the exhaust air flow, except when the pneumatic tube is used. Prior to the use, the activated air in the tube is led to a decay tank. As a result, the 41 Ar release rate was reduced by 10-20%. By the above means, the yearly exposure at the site boundary was reduced to 0.36 mR from 2.6 mR. In Hot Laboratory for metallurgical examination of spent fuel, the exhaust filtration system consists of filters in the cave, i.e. frame trap, prefilter, HEPA filter, and the main filter system, i.e. prefilter, two-stage HEPA filter and charcoal filter (the charcoal filter is by-passed to lengthen its life when radioiodine is not released). Values of removal efficiency and the dispersion factor for iodine were 80% and 4.4x10 - 3 and for cesium 97% and 3.5x10 - 3 , respectively. The exhaust filtration system in Radioactive Waste Incineration Plant consists of a two-stage ceramic filter installed immediately after the incinerator, air cooler, two-stage HEPA filter and final scrubber. The decontamination factor of the two-stage ceramic filter is 1x10 6 for particulate matter, when measured with radioactive particles from burning of simulated contaminants with 75 mCi of 137 Cs. The decontamination factor of the HEPA filter after the ceramic filter is about 10 3 . The overall decontamination factor for the plant is estimated to be more than 10 6

  10. Radioactivity distribution in phosphate products, by-products, effluents, and wastes

    International Nuclear Information System (INIS)

    Guimond, R.J.; Windham, S.T.

    1975-08-01

    Phosphate rock throughout the world contains uranium in concentrations ranging from a few ppM to a few hundred ppM. In the United States, phosphate rock normally contains between 100 to 150 ppM uranium. Mining and processing of these ores redistributes much of the uranium daughters among the various products, by-products, and wastes. These materials are then widely dispersed throughout the environment. This redistribution may lead to increased exposure of the public to these naturally-occurring radionuclides. In determining the magnitude of the population exposure caused by this redistribution and in developing environmental standards and controls to prevent contamination of the biosphere from these naturally-occurring radionuclides it is necessary to determine the concentrations and total quantities of these radionuclides in the products, by-products, effluents and wastes of phosphate mining and manufacturing. Samples of phosphate ores, products, by-products, effluents, and wastes were obtained and analyzed for their radioactivity content. Quantities of radioactivity entering the environment through various products, by-products, effluents, and wastes were estimated

  11. Summarization of radioactive effluent monitoring in Daya Bay Nuclear Power Station 1994-2002

    International Nuclear Information System (INIS)

    Ouyang Junjie; Chen Yue

    2004-01-01

    This paper introduces the radioactive effluent monitoring systems, measurement and quality control methods used in Daya Bay Nuclear Power Station from its commercial operation in 1994. The main work and experiences for the management of effluent release are discussed and analyzed. The radwaste data appear declining trend and are far blow the annual limit approved by the national Environmental Protection Bureau since 1995. The normalized release (unit GBq/GWa) of 9 years is as follows: liquid nuclides (except tritium) 11.1, liquid tritium 1.91 x 10 4 , noble gas 2.03 x 10 4 , halogen 0.13, aerosol 7.57 x 10 -3 . For 110m Ag, the average release from 1998 to 2002 has been reduced to 1/7 of the quantity in 1997

  12. Monitoring of low-level radioactive liquid effluent in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Mizutani, Tomoko; Koarashi, Jun; Takeishi, Minoru

    2009-01-01

    The Tokai reprocessing plant (TRP), the first reprocessing plant in Japan, has discharged low-level liquid wastes to the Pacific Ocean since the start of its operation in 1977. We have performed liquid effluent monitoring to realize an appropriate radioactive discharge control. Comparing simple and rapid analytical methods with labor-intensive radiochemical analyses demonstrated that the gross-alpha and gross-beta activities agreed well with the total activities of plutonium isotopes ( 238 Pu and 239+240 Pu) and major beta emitters (e.g., 90 Sr and 137 Cs), respectively. The records of the radioactive liquid discharge from the TRP showed that the normalized discharges of all nuclides, except for 3 H, were three or four orders of magnitude lower than those from the Sellafield and La Hague reprocessing plants. This was probably due to the installation of multistage evaporators in the liquid waste treatment process in 1980. The annual public doses for a hypothetical person were estimated to be less than 0.2 μSv y -1 from the aquatic pathway. Plutonium radioactivity ratios ( 238 Pu/ 239+240 Pu) of liquid effluents were determined to be 1.3-3.7, while those of the seabed sediment samples collected around the discharge point were 0.003-0.059, indicating no remarkable accumulation of plutonium in the regional aquatic environment. Thus, we concluded that there were no significant radiological effects on the public and the aquatic environment during the past 30-year operation of the TRP. (author)

  13. Toxicity regulation of radioactive liquid waste effluent from CANDU stations - lessons from Ontario's MISA program

    International Nuclear Information System (INIS)

    Rodgers, D.W.

    2009-01-01

    Toxicity testing became an issue for Ontario's CANDU stations, when it was required under Ontario's MISA regulations for the Electricity Generation Sector. In initial tests, radioactive liquid waste (RLW) effluent was intermittently toxic to both rainbow trout and Daphnia. Significant differences in RLW toxicity were apparent among stations and contributing streams. Specific treatment systems were designed for three stations, with the fourth electing to use existing treatment systems. Stations now use a combination of chemical analysis and treatment to regulate RLW toxicity. Studies of Ontario CANDU stations provide a basis for minimizing costs and environmental effects of new nuclear stations. (author)

  14. Radioactive airborne effluent discharged from Tokai reprocessing plant. 1998-2007

    International Nuclear Information System (INIS)

    Nakada, Akira; Miyauchi, Toru; Akiyama, Kiyomitsu; Momose, Takumaro; Kozawa, Tomoyasu; Yokota, Tomokazu; Ohtomo, Hiroyuki

    2008-10-01

    This report provides the data set of atmospheric discharges from Tokai reprocessing plant in Tokai-mura, Japan over the period from 1998 to 2007. Daily and weekly data are shown for 85 Kr that is continuously monitored and for the other nuclides (alpha emitters, beta emitters, 3 H, 14 C, 129 I and 131 I) whose activities are evaluated based on weekly samplings (Weekly sampling is continuous for 1 week). The data contained in this report are expected to apply for studying the behavior of the radioactive airborne effluent in the environment. (author)

  15. Radioactivity measurement of the liquid effluents of two university hospital methodology, problems arising

    International Nuclear Information System (INIS)

    Basse-Cathalinat, B.; Barthe, N.; Chatti, K.; Ducassou, D.

    2005-01-01

    The authors present methodology used to measure the radioactivity of the effluents at the output of two services of Nuclear medicine located in two Hospital complexes of the Area of Bordeaux. These measures are intended to answer at the requests of circular DGS/DHOS no 2001/323 of the Ministry for Employment and Solidarity. The selected method is more powerful since it is based on the use of a whole of spectrometry to very low background noise. These devices of measurements make it possible to take into account all the isotopes coming from a service of Nuclear medicine. The authors are conscious that of such measurements cannot be considered in all the services of Nuclear medicine. Other technical articles will specify simpler methods allowing a satisfactory management of the radioactive wastes. (author)

  16. A study on the diffusion of gaseous radioactive effluents based on the statistical method

    International Nuclear Information System (INIS)

    Na, Man Gyun; Lee, Goung Jin

    1998-01-01

    A diffusion model of radioactive gaseous effluents is improved to apply for domestic nuclear power plants. Up to now, XOQDOQ computer code package developed by U. S NRC has been used for the assessment of radioactive plume dispersion by normal operation of domestic nuclear power plants. XOQDOQ adopts the straight-line Gaussian plume model which was basically derived for the plane terrain. However, since there are so many mountains in Korea, the several shortcomings of XOQDOQ are improved to consider the complex terrain effects. In this work, wind direction change is considered by modifying the wind rose frequency using meteorological data of the local weather stations. In addition, an effective height correction model, a plume reduction model due to plume penetration into mountain, and a wet deposition model are adopted for more realistic assessments. The proposed methodology is implemented in Yonggwang nuclear power plants, and can be used for other domestic nuclear power plants

  17. Coir pith of the green coconut in the decontamination of radioactive aqueous effluent

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Raquel Almeida; Yamaura, Mitiko [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)]. E-mail: quequelll_monteiro@yahoo.com.br; myamaura@ipen.br

    2007-07-01

    Industrial segments as plant of mining, hospitals and university generate considerable volumes of radioactive wastewater containing uranium. The increasing development of the use of the nuclear energy to lead away to an expansion of the sectors of the nuclear fuel cycle, but it leads to security problems and it appears the necessity of control of the removing of uranium and radioactive effluent treatments. Researches evaluate if the technique of the biosorption would promote an alternative process with attractive characteristics of cost-benefit. The residual biomass from agricultural activities has been studied and used as adsorbent of metals and organic composts by low cost, abundance and for being biodegradable. In this work, it is presented the efficiency of the coir pith for the adsorption of ions UO{sub 2}{sup 2+}. The coir pith is a by-product of the harvest of the coconut, a renewable natural source. The study was accomplished using the batch techniques. The influence from pH 2 to 5, the dose of the coir pith, equilibrium time and the models of kinetic reaction were investigated. It was verified that the adsorption increased with the increase of pH and of the dose. The equilibrium time was of 30 min and the best correspondence with the model of pseudo second-order was observed. The results obtained has been promising, so use as adsorbent of metallic ions represents an economic alternative in relation to the conventional treatment of effluent. (author)

  18. Coir pith of the green coconut in the decontamination of radioactive aqueous effluent

    International Nuclear Information System (INIS)

    Monteiro, Raquel Almeida; Yamaura, Mitiko

    2007-01-01

    Industrial segments as plant of mining, hospitals and university generate considerable volumes of radioactive wastewater containing uranium. The increasing development of the use of the nuclear energy to lead away to an expansion of the sectors of the nuclear fuel cycle, but it leads to security problems and it appears the necessity of control of the removing of uranium and radioactive effluent treatments. Researches evaluate if the technique of the biosorption would promote an alternative process with attractive characteristics of cost-benefit. The residual biomass from agricultural activities has been studied and used as adsorbent of metals and organic composts by low cost, abundance and for being biodegradable. In this work, it is presented the efficiency of the coir pith for the adsorption of ions UO 2 2+ . The coir pith is a by-product of the harvest of the coconut, a renewable natural source. The study was accomplished using the batch techniques. The influence from pH 2 to 5, the dose of the coir pith, equilibrium time and the models of kinetic reaction were investigated. It was verified that the adsorption increased with the increase of pH and of the dose. The equilibrium time was of 30 min and the best correspondence with the model of pseudo second-order was observed. The results obtained has been promising, so use as adsorbent of metallic ions represents an economic alternative in relation to the conventional treatment of effluent. (author)

  19. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 23. Environmental effluent analyses

    International Nuclear Information System (INIS)

    1978-04-01

    This volume, Y/OWI/TM-36/23, ''Environmental Effluent Analysis,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Drat Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume discusses the releases to the environment of radioactive and non-radioactive materials that arise during facility construction and waste handling operations, as well as releases that could occur in the event of an operational accident. The results of the analyses are presented along with a detailed description of the analytical methodologies employed

  20. Calculation of releases of radioactive materials in gaseous effluents from nuclear-powered merchant ships (NMS-GEFF code)

    International Nuclear Information System (INIS)

    Cardile, F.P.; Bangart, R.L.; Collins, J.T.

    1978-06-01

    The Intergovernmental Maritime Consultative Organization IMCO) is currently preparing guidelines concerning the safety of nuclear-powered merchant ships. An important aspect of these guidelines is the determination of the releases of radioactive material in effluents from these ships and the control exercised by the ships over these releases. To provide a method for the determination of these releases, the NRC staff has developed a computerized model, the NMS-GEFF Code, which is described in the following chapters. The NMS-GEFF Code calculates releases of radioactive material in gaseous effluents for nuclear-powered merchant ships using pressurized water reactors

  1. Method for removing radioactive iodine and radioactive organic iodides from effluent gases

    International Nuclear Information System (INIS)

    1975-01-01

    A method and composition for removing radioactive and organic iodides from an 131 I-containing off-gas stream is provided. The composition for removal by adsorption is a ceramic material with a surface area of from about 5 m 2 /g to about 250 m 2 /g impregnated with a metallic salt. The method for removing the iodine or iodide is accomplished by passing the off-gas stream over the ceramic material impregnated with the metallic salt. It finds special application in air filters for nuclear power plants

  2. Elimination of slightly radioactive liquid effluent by dilution. Its consequences (1960); Elimination par dilution d'effluents liquides faiblement radioactifs. Leurs consequences (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Bovard, P; Candillon, C [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    Nuclear centres often have to solve problems raised by the elimination of large volumes of slightly radioactive liquid effluent. As things stand at present, the method usually adopted consists in expelling this effluent into the main water system in order to dilute it to a maximum, and thus to lower its radioactive isotope concentration to below the norms imposed by the Public Health Service. This technique requires systematic checking of the water system and its dependences, and demands a thorough knowledge of adsorption and fixation processes. (author) [French] Les centres nucleaires ont frequemment a resoudre des problemes poses par l'elimination de volumes importants d'effluents liquides faiblement radioactifs. Dans l'etat actuel des choses, la solution la plus utilisee consiste a rejeter ces effluents dans le reseau hydrographique de maniere a les diluer au maximum et abaisser ainsi leurs teneurs en isotopes radioactifs au-dessous des normes imposees par la Sante Publique. Cette technique necessite un controle systematique du reseau et de ses dependances et demande une connaissance approfondie des processus d'adsorption et de fixation. (auteur)

  3. A radioactive noble gas quantitative analysis of gaseous effluents from NPP

    International Nuclear Information System (INIS)

    Yanev, Y.; Georgiev, K.; Mavrodiev, V.; Kikarin, B.

    1993-01-01

    The radioactive isotopes of argon, krypton and xenon comprise a substantial part of the gaseous emission of a NPP. A quantitative determination of their specific activity in the controlled area and the gaseous effluents requires a special sampling technique, as well as measurement method. The zeolites and the activated charcoals have a differentiated behaviour towards radioisotopes of argon, krypton and xenon. The isotope fractionation is often a problem, especially with argon and xenon. Some additional difficulties arise due to the irreproductibility of temperature and atmospheric moisture. The present paper describes a method for a spectrometric determination of radioactive noble gases after the cryogenic sampling developed at the Radiochemical laboratory of the Sofia University. The quality control of the method, as well as some special difficulties in its performing are discussed. The estimated minimum detectable activity is 5-10 Bq/m 3 for radioactive noble gases with half-life > 1 hour and sampling time for (resp. gamma-spectrometry) 1 hour. (author)

  4. Radioactive effluents from nuclear power stations and reprocessing plants in the European Community

    International Nuclear Information System (INIS)

    1978-04-01

    The report presents the available data on radioactive gaseous and liquid effluents discharged by nuclear power stations and nuclear fuel reprocessing plants in the European Community from 1972 to 1976. Discharges are expressed both in absolute terms and relative to the net production of electricity from the fuel. On the basis of the discharges recorded for 1976 the resulting maximum exposure of members of the population is quantified and compared with the dose limits prescribed by Euratom radiological protection standards and with the exposure resulting from natural radioactivity. It is concluded that there is no case in which a discharge could have given rise to an exposure exceeding the relevant prescribed limit. Not only did the possible maximum exposures incurred by individuals leave an appreciable safety margin relative to that limit but, for the vast majority of installations, they were comparable with or were considerably lower than the geographical and temporal variations in exposures resulting from natural radioactivity. Where environmental levels have been detectable the measured results have of course been used but, with few exceptions, the levels have remained less than the very low limits of detection currently possible. In general, where theoretical models are used to evaluate exposure, they are designed to give conservative results and hence it is likely that the true exposures are even less than those calculated

  5. Technical Orders of 10 August 1976 on the limits and procedures applicable to radioactive effluent discharges from nuclear installations

    International Nuclear Information System (INIS)

    1976-01-01

    Seven technical Orders by the competent Ministers (mainly the Ministers of Health, of Industry and Research, of the Quality of Life) lay down the procedures, conditions and limits applicable to gaseous and liquid radioactive effluent discharges from nuclear installations. These Orders of 10 August were published on 12 September 1976 in the Official French Gazette and were made in implementation of the Decree of 6 November 1974 on gaseous radioactive effluent discharges from nuclear installations and the Decree of 31 December 1974 on liquid radioactive effluent discharges from nuclear installations. Apart from the general rules for setting limits and methods for effluent discharges, they specify the measures for environmental monitoring and for control by the Central Service for Protection against Ionizing Radiations. Certain of them contain the general rules for liquid or gaseous effluent discharges from all nuclear installations, while others lay down the rules proper to light water nuclear power plants. Other types of reactor ie. fast breeders are not yet subject to such regulations. (N.E.A.) [fr

  6. Monitoring of the radioactive liquid effluents discharged from IPEN-CNEN/SP. Optimization of the procedures adopted

    International Nuclear Information System (INIS)

    Seki, C.R.

    1990-01-01

    The main purpose of a radioactive liquid effluents monitoring of a nuclear installation is to determine the amount of radioactivity discharged to the environment, as well as, to verify if this activity is below the authorized discharge limits established by the competent authority. Although this control has been established on a routine basis since the beginning of operation of the nuclear installations available at IPEN, the growing of such facilities in the last years has implied in an increase in the number of samples to be analyzed. The aim of this work is, therefore, to optimize the procedures adopted in the Environmental Monitoring Division of IPEN-CNEN/SP for the activity measurement of the liquid effluents discharged to the environment. Since these effluents are discharged to Pinheiros river, which presents a high dilution factor, a study is also carried out in order to verify if the activity present can be measured by the equipment available. (author)

  7. Decree No 74-1181 of 31 December 1974 concerning liquid radioactive effluent releases from nuclear installations

    International Nuclear Information System (INIS)

    1975-01-01

    This Decree prescribes the licensing procedure for the release of liquid wastes from nuclear installations as well as the technical supervision of such operations. It does not apply to the transport of radioactive effluents which is governed by the regulations on the transport of dangerous goods. (NEA) [fr

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

    International Nuclear Information System (INIS)

    Fitoussi, L.

    1978-01-01

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

  9. Survey of radioactive effluent releases from byproduct material facilities. Technical report

    International Nuclear Information System (INIS)

    Cook, J.R.

    1981-08-01

    A survey of over 3,000 NRC byproduct material licensees was conducted in late 1980 to collect data on annual effluent releases of radioactivity. The survey was conducted through a questionnaire, which was sent to NRC licensees who handle radioactive material in unsealed form, i.e., research, medical, and industrial institutions. Principal findings from the survey analysis are as follows: More than 98% of the reported annual releases to air (484 to 490) yield calculated average concentrations at the boundary of the unrestricted area that were at 1% or less than the maximum permissible concentration (MPC) of Appendix B, Table II, Column 1 of 10 CFR 20. The largest reported annual release was estimated to yield a concentration that was approximately 12% of MPC, the 5 other releases ranged from 1 to 10% of MPC. All reported annual releases of liquid waste were within the limits specified by NRC with most facilities reporting annual releases of only a fraction of a curie. Based on the data provided by licensees and analyzed in this report, it appears that in general the environmental impacts from research, medical and industrial institutions and organizations licensed by the NRC to possess and use byproduct materials are minimal and correspond to a small fraction of that from natural background

  10. Calculation of releases of radioactive materials in gaseous and liquid effluents from boiling water reactors (BWR-GALE Code)

    International Nuclear Information System (INIS)

    Bangart, R.L.; Bell, L.G.; Boegli, J.S.; Burke, W.C.; Lee, J.Y.; Minns, J.L.; Stoddart, P.G.; Weller, R.A.; Collins, J.T.

    1978-12-01

    The calculational procedures described in the report reflect current NRC staff practice. The methods described will be used in the evaluation of applications for construction permits and operating licenses docketed after January 1, 1979, until this NUREG is revised as a result of additional staff review. The BWR-GALE (Boiling Water Reactor Gaseous and Liquid Effluents) Code is a computerized mathematical model for calculating the release of radioactive material in gaseous and liquid effluents from boiling water reactors (BWRs). The calculations are based on data generated from operating reactors, field tests, laboratory tests, and plant-specific design considerations incorporated to reduce the quantity of radioactive materials that may be released to the environment

  11. Analysis and study on generic models for use in assessing the impact of radioactive liquid effluent to the environment

    International Nuclear Information System (INIS)

    Ma Wenlin; Cao Jianzu; Fang Dong

    2008-01-01

    The assessment of the impact of discharges of radioactive substances into surface water under normal condition of nuclear facilities is an important part of the environmental impact analysis. Generic methods for assessing the impact of radioactive liquid effluent release into surface water provided by IAEA Safety Reports Series 19 are studied in this paper, and also an example calculation that assesses the impact of radioactive surface water discharge of HTR-PM ( High Temperature Air-cooled Reactor demonstration unit) in Anhui is presented in this paper to illustrate that a simplified but conservative assessment can be used for the purpose of screening proposed radioactive discharges. If the results meet the relevant requirements specified by the relevant regulatory authority, the further calculations are not needed. If they fails to meet the requirements, the more field data are to be sampled for calculations by more sophisticated mode or otherwise. (authors)

  12. Optimization of the retention of radioactive material from the airborne effluents of reprocessing plants

    International Nuclear Information System (INIS)

    Bonka, H.; Horn, H.-G.

    1984-01-01

    The radiation-protection ordinance of the Federal Republic of Germany does not know the expression 'optimization in radiological protection'. In order to gain experiences with the cost-benefit analysis for the retention of radioactive material from nuclear facilities as proposed in ICRP 26, this method has been applied on the emission of radioactive material with the airborne effluents of reprocessing plants. The reference plant has an annual throughput of 1500 t of spent LWR-fuel. Basing on this plant, two smaller plants (350 t/a, 700 t/a) are also analysed. The cost-benefit-analysis is carried-out for H3, C14, Kr85, J129 and aerosols. For these nuclides as well as for the three plant-sizes, the methods of retention, the estimated annual costs of retention, the emission rates for the different retention measures and the resulting collective-dose commitments are shown. Based on an α-value of 8000 $/man-Sv (20,000 DM/Man-Sv) the cost-benefit analysis shows no optimum for H3 and Kr 85. The optimum C14 as well as iodine retention is a high-efficiency scrubber and an iodine filter, respectively for the dissolver off-gas. For aerosols the cost-benefit analysis shows an optimum for the filtration of the dissolver off-gas by means of HEPA filters. For the other aerosol-sources, condensation, scrubbing and additional droplet separation from the off-gas is optimum. Reasons differing from cost-benefit analysis require HEPA filters for all major aerosol-sources. (author)

  13. Environmental aspects and public exposure doses of airborne radioactive effluents from a PWR-power plant

    International Nuclear Information System (INIS)

    Song Miaofa; Zhang Jin; Fu Rongchu; Hu Yinxiu

    1989-04-01

    It is estimated that the environmental aspects and public exposure doses of airborne radioactive effluents from a imaginary 0.3 GW PWR-power plant which sited on the site of a large coalfired power plant estimated before. The major contributor to public exposure is found to be the release of 14 C and the critical pathway is food ingestion. A maximum annual individual body effective dose equivalent of 7.112 x 10 -6 Sv · (GW · a) -1 is found at the point of 0.5 km southeast of the source. The collective dose equivalent in the area around the plant within a radius of 100 km is to be 0.5974 man-Sv · a) -1 . Both maximum individual and collective effective dose equivalents of the PWR-power plant are much lower than those of the coal-fired one. If the ash emission ratio of the latter decreases from 24.6% to 1%, public exposure doses of the two plants would be nearly equal

  14. Radioactive effluents from nuclear power stations and nuclear fuel reprocessing plants in the European Community

    International Nuclear Information System (INIS)

    Luykx, F.; Fraser, G.

    1983-01-01

    The report covers operational nuclear power stations of capacity greater than 5C MWe and nucler fuel reprocessing plants in the European Community. Radioactive gaseous and liquid effluent discharges from these installations are given for the period 1976 to 1980, expressed both in absolute terms and normalized to net electricity production from the fuel. An assesssment is then made of exposure of members of the public consequent to the 1980 discharges. Where environmental contamination levels were detectable the results have been taken into account in the dose assessment; however, environmental contamination was in general below the limit of detection. In these circumstances the dose estimates rely entirely on theoretical models which frequently incorporate conservative assumptions; hence these estimates are likely to be greater than the doses actually received. The estimated exposures have then been compared with the dose limits set out in the Euratom Directive of 15th July, 1980. It is concluded that the exposure of members of the public always left an appreciable safety margin relative to the limits and indeed lay within the variations in exposure which result from natural background

  15. Automated system of control of radioactive liquid effluents of patients submitted to therapy in hospitals of nuclear medicine (SACEL)

    International Nuclear Information System (INIS)

    Ruiz C, M.A.; Rivero G, T.; Celis del Angel, L.; Sainz M, E.; Molina, G.

    2006-01-01

    Different hospitals of nuclear medicine require of the technical attendance for the design, construction and instrumentation of an effluents retention system coming from the room dedicated to the medical application of iodine 131, with the one object of giving execution to the normative requirements of radiological protection, settled down in the General Regulation of Radiological Safety (RGSR) emitted by the CNSNS in November, 1988 and in the corresponding official standards. An automatic system of flow measurement, the activity concentration of the effluents to the drainage, the discharges control and the automated report it will allow the execution of the national regulations, also the elimination of unhealthy activities as the taking of samples, analysis of those same and the corresponding paperwork, its will allow that the SACEL is capable of to carry out registrations that are to consult in an automated way. The changes in the demands of the National Commission of Nuclear Safety and Safeguards in relation to the liberation of radioactive material in hospitals by medical treatments, it has created the necessity to develop a system that quantifies and dose the liquid effluents of people under thyroid treatment with iodine-131 to the drainage. The Automated System of Control of radioactive liquids effluents generated in Hospitals of Nuclear Medicine (SACEL) developed in the National Institute of Nuclear Research, it fulfills this regulation, besides improving the work conditions for the medical and technical personnel of the hospital in that are installed, since this system has the advantage of to be totally automated and to require of a minimum of attendance. The SACEL is an electro-hydraulic system of effluents control, based in the alternate operation of two decay deposits of the activity of the material contaminated with iodine-131. The system allows to take a registration of those volumes and liberated dose, besides being able to be monitoring in remote

  16. Radioactive effluent sources and special system of channels on the RA Reactor at the Boris Kidric Institute; Izvori radioaktivnih efluenata i specijalna kanalizacija u reaktoru RA Instituta Boris Kidric

    Energy Technology Data Exchange (ETDEWEB)

    Bojovic, P; Gacinovic, O; Milosevic, M [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1964-10-15

    The paper describes the place of origin, composition and activity of radioactive effluents appearing in some reactor systems and special channels for carrying these effluents to disposal basins located outside the reactor building (author)

  17. Order of 4 august 1989 on licensing the release of gaseous radioactive effluents by the Cattenom nuclear production centre (units 3 and 4)

    International Nuclear Information System (INIS)

    1989-08-01

    This Order fixes the conditions and limits of authorised releases of gaseous radioactive effluents from Units 3 and 4 of the Cattenom nuclear power plant. It specifies these are maximum limits, below which the radioactive releases should be as low as possible [fr

  18. Impact of treated effluents released from processing of radioactive mineral on the aquatic environment of Periyar river

    International Nuclear Information System (INIS)

    Radhakrishnan, Sujata; Haridasan, P.P.; Radhakrishna Pillai, K.; Pillai, P.M.B.; Khan, A.H.

    2005-01-01

    The chemical processing of monazite/ thorium concentrate for the separation of thorium, uranium and rare earths results in the generation of effluents, both acidic and alkaline. Indian Rare Earths Ltd (IREL), Udyogamandal was carrying out processing of monazite for nearly 50 years. Presently (since 2004) Indian Rare Earths Ltd, Udyogamandal is processing earlier stocked thorium hydroxide concentrate retrieved from Silos to produce Thorium Oxalate (along with a small percentage of Rare Earth elements), Nuclear Grade Ammonium Di-Uranate (NGADU), and small quantities of Nuclear Grade Thorium Oxide ('THRUST' Project). The treated effluents after monitoring are discharged to river Periyar. River Periyar is the recipient water body for treated effluents from IREL as well as a host of other chemical industries. Indian Rare Earths Ltd, Udyogamandal had been carrying out chemical processing of monazite for the past 50 years. Recently, from 2004, the plant has shifted from monazite processing to processing of thorium concentrate (THRUST Project). The present paper discusses the characteristics of the effluents generated as per this project, their treatment, monitoring methodology, discharge and impact on the aquatic environment of river Periyar. It has been noted that the impact on the aquatic environment by way of enhancing the natural background radioactivity in the river had been insignificant. (author)

  19. Order of the 10 january 2003 authorizing the national agency for the radioactive wastes management to follow the gaseous and liquid effluents release for the exploitation of the radioactive wastes storage center of the Manche

    International Nuclear Information System (INIS)

    2003-01-01

    This document, took out from the Official Journal, is the law text relative to the order of the 10 january 2003 authorizing the national agency for the radioactive wastes management to follow the gaseous and liquid effluents release for the exploitation of the radioactive wastes storage center of the Manche. (A.L.B.)

  20. An estimation of exposure from gaseous and volatile radioactive effluents released from EWA reactor between 1971 and 1975

    International Nuclear Information System (INIS)

    Filipiak, B.; Nowicki, K.

    1979-01-01

    The paper gives an estimation of radiation doses for individuals due to gaseous radioactive effluents released from EWA reactor between 1971 and 1975. The doses were estimated for three organs, three groups of people: adults, teenagers and children and for three of the most important exposure paths: the external radiation from a passing cloud, inhalation and from milk ingestion. The results of calculations indicate that the radiation doses received by individuals living in the vicinity of EWA reactor were much below the limit doses or those due to the background radiation. (author)

  1. Safety evaluation of liquid radioactive effluents treatment system in a BWR reactor, through the LIQM03 code

    International Nuclear Information System (INIS)

    Zorrilla R, S.H.

    1978-01-01

    In this work we made a safety evaluation of the liquid radioactive effluents system in a plant using a BWR similar to that now installed in Laguna Verde. For that purpose, the computation program ORIGENwas modified, in order to keep up to date and adapt it to the PDP 10 computer, which is operating at the Computation Department of the Nuclear Center of Mexico, the code LIQM03 was the result of this modification. As usual in this work we dealt with problems which were solved opportunely, now we have at our disposal the code LIQM03 which will be in the future a very useful tool for this kind of evaluations. (author)

  2. Development of improved liquid radioactive effluents treatment technology by precipitation and ion exchange and the related analytical control system

    Energy Technology Data Exchange (ETDEWEB)

    Rahman, M M; Mollah, A S; Alam, M K; Begum, A; Islam, S; Koddus, A [Institute of Nuclear Science and Technology, Savar, Dacca (Bangladesh)

    1997-02-01

    Chemical precipitation method for treatment of LLW and ILW by co-precipitation of caesium with nickel ferrocyanide was employed. High decontamination factors were observed in the pH range of 9 to {approx} 11. The percentage removals of {sup 137}Cs from 37 kBq, 370 kB and 3.4 MBq per litre of simulated effluents were {approx} 90%, 99.7% and 99.8% respectively. Liquid radioactive wastes generated from radioisotope production facilities of AERE, Savar were found to contain {sup 134}Cs and {sup 60}Co with the average activity levels of 13.23 kBq/L and 5.3 kBq/L, respectively. Test runs for removal of {sup 134}Cs from the wastes varied from {approx} 90% to 99%. The radioactive concentrates (sludges) were conditioned by cementation and safely stored in interim storage room. (author). 4 refs, 1 fig., 9 tabs.

  3. Development of improved liquid radioactive effluents treatment technology by precipitation and ion exchange and the related analytical control system

    International Nuclear Information System (INIS)

    Rahman, M.M.; Mollah, A.S.; Alam, M.K.; Begum, A.; Islam, S.; Koddus, A.

    1997-01-01

    Chemical precipitation method for treatment of LLW and ILW by co-precipitation of caesium with nickel ferrocyanide was employed. High decontamination factors were observed in the pH range of 9 to ∼ 11. The percentage removals of 137 Cs from 37 kBq, 370 kB and 3.4 MBq per litre of simulated effluents were ∼ 90%, 99.7% and 99.8% respectively. Liquid radioactive wastes generated from radioisotope production facilities of AERE, Savar were found to contain 134 Cs and 60 Co with the average activity levels of 13.23 kBq/L and 5.3 kBq/L, respectively. Test runs for removal of 134 Cs from the wastes varied from ∼ 90% to 99%. The radioactive concentrates (sludges) were conditioned by cementation and safely stored in interim storage room. (author). 4 refs, 1 fig., 9 tabs

  4. Estimation of radioactive effluents concentrations in the vicinity of nuclear power plant; Predviduvanje na koncentraciite na radioaktivni aerozagaduvaci vo okolinata na nuklearni energetski postrojni

    Energy Technology Data Exchange (ETDEWEB)

    Arsov, Lj [Elektrostopanstvo, Skopje (Yugoslavia)

    1977-07-01

    This paper deals with the problem of mathematical prediction of radioactive effluent concentrations around nuclear power plants. This mathematical model which describes the behaviour of the effluent in the atmosphere here in after is expanded and adapted for radioactive effluent treatment. In this way the mathematical model includes the description of the following effects: the rise of plume caused by its vertical momentum and its heat content, wind velocity profile and vertical growth of the coefficient of diffusion, fallout under gravity, ground deposition, precipitation scavenging, and radioactive decay. The advanced computer program DIFFUS has been applied to evaluate the ground concentration of the nuclides of I, which constitute the greatest risk for population.(author)

  5. Disposal of the radioactive effluents at the 'Commissariat a l'Energie Atomique'. Treatment leading to evacuation into a river

    International Nuclear Information System (INIS)

    Duhamel; Menoux; Candillon

    1958-01-01

    1) The problems dealing with the treatment of the radioactive effluents at the 'Commissariat a l'Energie Atomique' have been studied in order to allow evacuation into a river - after treatment - with respect for the standards regarding radiation protection. 2) At Saclay where there is no possibility of evacuating the effluents, the liquids are directed towards Fontenay-aux-Roses by means of tank wagons. They are removed temporarily into the sewers and will be evacuated later on into the Seine. 3) ln Le Bouchet, the effluents coming from the Factory where urano-thorianite ore is treated will undergo a two stages treatment. The elimination of radium in the first phase facilitates decontamination in the second phase. 4) In Marcoule: a study of synthetic effluents of the Marcoule type is being carried on in order to perfect a selective elimination method of Sr 90 and Cs 137 by coprecipitation. 5) In the general case of the final evacuation into a river, the following problems have been studied: - pre-dilution of treated waters between the storing tanks and the river; - admission in the river; dilution in the river (preliminary study by means of a tracer); - evolution of the activity in the water of the river (adsorption by inert or living elements), contamination of the banks; - locating of the site; - isotopic dilution. 6) Circumstantial study of that last problem. 7) The quantity of a given product in water conditions the isotopic dilution of its radioactive isotopes. When the analysis shows the lack of an element, stable isotopes should be added in order to compensate it. 8) That method led to difficult analysis (specially as far as Sr 90 is concerned), for the percentage of stable isotopes necessary to an important isotopic dilution is very low. 9) The standard regarding the quantity of Sr 90 in drinking water is 8.10 -8 c/m 3 or 4.10 -10 g/m 3 . So a percentage of 40 μg/litre of Sr is enough which is difficult to find out in loaded water, 10) Important elements

  6. Order of 21 October 1988 withdrawing the licence for the release of liquid radioactive effluents by the Cattenom nuclear production centre (units 1 and 2)

    International Nuclear Information System (INIS)

    1988-01-01

    The Court of Justice of the European Communities decided on 22 September 1988 that the Commission of the European Communities had to be notified and give its opinion before the competent authorities of Member States authorised the release of radioactive effluents from a nuclear installation. In compliance with that judgment, this Order repeals an Order of 21 February 1986 licensing such release (NEA) [fr

  7. Decree No 74-945 of 6 November 1974 concerning gaseous radioactive effluent releases from large nuclear installations and nuclear installations located on the same site

    International Nuclear Information System (INIS)

    1974-01-01

    This Decree prescribes the licensing for the release of gaseous wastes from nuclear installations as well as the technical supervision of such operations. It does not apply to the transport of radioactive effluents which is governed by the regulations on the transport of dangerous goods. (NEA) [fr

  8. Implementation of a model of atmospheric dispersion and dose calculation in the release of radioactive effluents in the Nuclear Centre

    International Nuclear Information System (INIS)

    Cruz L, C. A.

    2015-01-01

    In the present thesis, the software DERA (Dispersion of Radioactive Effluents into the Atmosphere) was developed in order to calculate the equivalent dose, external and internal, associated with the release of radioactive effluents into the atmosphere from a nuclear facility. The software describes such emissions in normal operation, and not considering the exceptional situations such as accidents. Several tools were integrated for describing the dispersion of radioactive effluents using site meteorological information (average speed and wind direction and the stability profile). Starting with the calculation of the concentration of the effluent as a function of position, DERA estimates equivalent doses using a set of EPA s and ICRP s coefficients. The software contains a module that integrates a database with these coefficients for a set of 825 different radioisotopes and uses the Gaussian method to calculate the effluents dispersion. This work analyzes how adequate is the Gaussian model to describe emissions type -puff-. Chapter 4 concludes, on the basis of a comparison of the recommended correlations of emissions type -puff-, that under certain conditions (in particular with intermittent emissions) it is possible to perform an adequate description using the Gaussian model. The dispersion coefficients (σ y and σ z ), that using the Gaussian model, were obtained from different correlations given in the literature. Also in Chapter 5 is presented the construction of a particular correlation using Lagrange polynomials, which takes information from the Pasquill-Gifford-Turner curves (PGT). This work also contains a state of the art about the coefficients that relate the concentration with the equivalent dose. This topic is discussed in Chapter 6, including a brief description of the biological-compartmental models developed by the ICRP. The software s development was performed using the programming language Python 2.7, for the Windows operating system (the XP

  9. Study on radioactive release of gaseous and liquid effluents during normal operation of AP1000

    International Nuclear Information System (INIS)

    Gong Quan; Zhou Jing; Liu Yu

    2014-01-01

    The gaseous and liquid radioactive releases of pressurized water reactors plant during normal operation are an important content of environmental impact assessment and play a significant role in the design of nuclear power plant. According to the design characters of AP1OOO radioactive waste management system and the study on the calculation method and the release pathways, the calculation model of the gaseous and liquid radioactive releases during normal operation for AP1OOO are established. Base on the established calculation model and the design parameters of AP1000, the expected value of gaseous and liquid radioactive releases of AP1OOO is calculated. The results of calculation are compared with the limits in GB 6249-2011 and explain the adder that is included tu account for anticipated operational occurrences, providing a reference for environmental impact assessment of pressurized water reactor. (authors)

  10. Study of sample-detector assemblies for application to in-situ measurement of radioactivity in liquid effluents

    International Nuclear Information System (INIS)

    Pendharkar, K.A.; Narayanan Kutty, K.; Krishnamony, S.

    1991-01-01

    This paper describes the experimental investigations carried out on four different types of sample-detector assemblies with a view to determining their detection limits and relative merits for application to in-situ measurement of radioactivity in liquid effluents. The four systems studied were: (1) gamma detection using 11 cm x 8 cm NaI (Tl) scintillation detector inserted in the cavity of a specially designed stainless steel chamber of capacity 15 liters, (2) gamma detection using a metal-walled G.M. counter in a similar manner, (3) beta detection using twin thin-walled G.M. counters immersed in liquid, and (4) end window G.M. counter positioned above the liquid surface in a shallow tray. The design features of an in-line monitor employing a 11 cm x 8 cm NaI (Tl) detector used for the routine monitoring of beta gamma activity concentrations in the low level effluents of the Tarapur Fuel Processing Plant are described. (author). 1 tab

  11. Magnox Swarf Storage Silo Liquor Effluent Management -Sellafield Site, Cumbria, UK - Legacy radioactive waste storage - 59271

    International Nuclear Information System (INIS)

    Le Clere, Stephen

    2012-01-01

    The Sellafield Magnox Swarf Storage Silo (MSSS) was constructed to provide an underwater storage facility for irradiated magnox cladding metal Swarf, as well as miscellaneous beta-gamma waste from several sources. Liquid effluent arisings from hazard reduction activities at this facility represent the toughest effluent treatment challenge within the company's Legacy Ponds and Silos portfolio. The key requirement for hazard reduction has generated many substantial challenges as the facility is readied for decommissioning. This has demanded the production of carefully thought out strategies for managing, and overcoming, the key difficulties to be encountered as hazard reduction progresses. The complexity associated with preparing for waste retrievals from the Magnox Swarf Storage Silo, has also generated the demand for a mix of creativity and perseverance to meet the challenges and make progress. Challenging the status quo and willingness to accept change is not easy and the road to overall hazard reduction for the high hazard MSSS facility will demand the skills and investment of individuals, teams, and entire facility work-forces. The first steps on this road have been taken with the successful introduction of liquor management operations, however much more is yet to be achieved. Clear communication, investing in stakeholder management, perseverance in the face of difficulty and a structured yet flexible programme delivery approach, will ensure the continued success of tackling the complex challenges of treating liquid effluent from a legacy fuel storage silo at the Sellafield Site. (authors)

  12. Design, calculation and testing on mock-up of B(U) f type LR 56 packaging for radioactive liquid effluent transport

    International Nuclear Information System (INIS)

    Belaud; Leconnetable; Daspet; Tombini; Tanguy

    1986-06-01

    Transport of radioactive acid liquid effluents are effected on tank truck inside nuclear center of the CEA. The cylindrical packaging type B(U) f has a capacity of 4,000l, a maximum permissible activity of 110 T Bq (3x10 4 Ci) and comprises a central element for liquid effluent containment to prevent contamination of environment and peripheral elements for mechanical, biological and thermal protection. This packaging is fixed on a trailer associated with a control box. Design and equipment of the packaging are studied for a maximum safety and in accordance with regulations [fr

  13. Synthesis of the IRSN report of the management of effluents in operating nuclear plants, and of associated radioactive and chemical rejections

    International Nuclear Information System (INIS)

    2009-05-01

    This report discusses the various improvements proposed by the IRSN to EDF for a better management of effluents and rejections in nuclear plants. These improvements should bear on a better understanding of the production, of the behaviour and of the treatment of radioactive compounds and of associated chemical compounds. They should also bear on the design of the installations and their inspection, operation practices, the use of local good practices, the organisation, the control of rejections, the control of underground waters of nuclear sites, experience feedback, the documentation on effluents and rejections

  14. Tests of the use of cation exchange organic resins for the decontamination of radioactive aqueous effluents; Essais d'emploi des resines organiques echangeuses de cations pour la decontamination des effluents aqueux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Bourdrez, Jean; Girault, Jacques; Wormser, Gerald

    1962-12-14

    The authors report tests performed in laboratory and results obtained during an investigation of the use of synthetic ion exchangers for the decontamination of radioactive effluents of moderate activity level and with a non neglectable salt loading. Resins are used under sodium form and regenerated after each fixing operation. Once decontaminated and free of its disturbing ions, the regenerating agent (NaCl) is used for several operations. The authors present the used resins, the treated effluents, describe the tests, and discuss the obtained results [French] Dans ce rapport nous faisons le point des essais et resultats obtenus au laboratoire au cours d'une etude concernant l'utilisation des echangeurs d'ions synthetiques pour la decontamination des effluents radioactifs de niveau d'activite moyenne et de charge en sels non negligeable. Les resines sont employees sous forme sodique et regenerees apres chaque operation de fixation. Le regenerant decontamine et debarrasse de ses ions genants est utilise pour plusieurs operations d'elution. Les seuls residus a stocker proviennent d'une part eventuellement d'un pretraitement de l'effluent, d'autre part, dans tous les cas des precipites consecutifs a la purification de l'eluant dont le traitement chimique est plus aise et donne lieu a des boues beaucoup moins volumineuses qu'une coprecipitation effectuee sur la totalite de l'effluent. (auteurs)

  15. Assessment of derived emission limits for radioactive effluents resulted from the decommissioning activities of the VVR-S nuclear research reactor

    International Nuclear Information System (INIS)

    Tuca, C.; Stochioiu, A.; Sahagia, M.; Gurau, D.; Dragusin, M.

    2015-01-01

    This paper presents complex studies on establishment of derived emission limits for potential radionuclides emitted as gaseous and liquid effluents, during the decommissioning activities (2nd and 3rd phases) of a nuclear research reactor, cooled and moderated with distilled water, type VVR-S, owned by the IFIN-HH. In the present paper there are described: the analysis methods and equipment used, the methodologies for calculating doses and the Derived Emission Limits (DEL), the experimentally measured activities of the representative radionuclides found in gaseous and liquid effluents resulted from decommissioning activities, as well as the effective derived limits of liquid and gaseous effluents, applying the calculation methodologies, specific to critical categories of exposed subjects. A constraint effective dose limit for a person from the critical group of 50 μSv/year was considered in calculations. From the comparison of the two series of values, measured released activities and DELs, there has been concluded that for the gaseous effluents they comply with the DELs, while in the case of liquid effluents they are higher and consequently they must be treated as liquid radioactive wastes. - Highlights: • The DELs for gaseous and liquid effluents in decommissioning were studied. • The impact on the environment and critical group was assessed. • Gamma-ray spectrometry was used to determine the radionuclide composition. • Based on the dosimetry models, the values of conservative DELs were calculated. • The DELs are compliant for gases, not for liquids; require the treatment as rad-waste

  16. Comparisons between written and computerised patient histories

    NARCIS (Netherlands)

    Quaak, Martien; Westerman, R. Frans; van Bemmel, Jan H.

    1987-01-01

    Patient histories were obtained from 99 patients in three different ways: by a computerised patient interview (patient record), by the usual written interview (medical record), and by the transcribed record, which was a computerised version of the medical record. Patient complaints, diagnostic

  17. Application of inorganic ion exchangers for low and medium activity radioactive effluent decontamination

    International Nuclear Information System (INIS)

    Dozol, J.F.; Eymard, S.; Gambade, R.; La Rosa, G.

    1986-01-01

    This study proposes an alternative pretreatment or treatment for low and medium activity liquid wastes, allowing to improve the quality of containment and decrease the cost of storage. Inorganic ion exchangers are used to remove alpha emitters and long lived fission products and concentrate them in a small volume; these exchangers can be converted into a stable matrix by thermal treatment. This treatment, at least for some liquid wastes, don't exclude a complementary decontamination by chemical precipitation. Sludges, arising from precipitation, exempt from alpha emitters and long lived fission products can be stored in a shallow land burial. This study includes two parts: - Measurements of distribution coefficients for the main nuclides in order to choose, for each liquid wastes, the most suitable ion exchanger. - Estimation of performances of selected inorganic ion exchangers, from tests of percolation of genuine effluents

  18. Treatment of radioactive liquid effluents by reverse osmosis membranes: From lab-scale to pilot-scale.

    Science.gov (United States)

    Combernoux, Nicolas; Schrive, Luc; Labed, Véronique; Wyart, Yvan; Carretier, Emilie; Moulin, Philippe

    2017-10-15

    The recent use of the reverse osmosis (RO) process at the damaged Fukushima-Daiichi nuclear power plant generated a growing interest in the application of this process for decontamination purposes. This study focused on the development of a robust RO process for decontamination of two kinds of liquid effluents: a contaminated groundwater after a nuclear disaster and a contaminated seawater during a nuclear accident. The SW30 HR membrane was selected among other in this study due to higher retentions (96% for Cs and 98% for Sr) in a true groundwater. Significant fouling and scaling phenomenon, attributed to calcium and strontium precipitation, were evidenced in this work: this underscored the importance of the lab scale experiment in the process. Validation of the separation performances on trace radionuclides concentration was performed with similar retention around 96% between surrogates Cs (inactive) and 137 Cs (radioactive). The scale up to a 2.6 m 2 spiral wound membrane led to equivalent retentions (around 96% for Cs and 99% for Sr) but lower flux values: this underlined that the hydrodynamic parameters (flowrate/cross-flow velocity) should be optimized. This methodology was also applied on the reconstituted seawater effluent: retentions were slightly lower than for the groundwater and the same hydrodynamic effects were observed on the pilot scale. Then, ageing of the membrane through irradiation experiments were performed. Results showed that the membrane active layer composition influenced the membrane resistance towards γ irradiation: the SW30 HR membrane performances (retention and permeability) were better than the Osmonics SE at 1 MGy. Finally, to supplement the scale up approach, the irradiation of a spiral wound membrane revealed a limited effect on the permeability and retention. This indicated that irradiation conditions need to be controlled for a further development of the process. Copyright © 2017 Elsevier Ltd. All rights reserved.

  19. Recovery of sludge from the treatment of liquid radioactive effluents by co-precipitation with calcium carbonate: laboratory study; Recuperation des boues de traitement des effluents radioactifs liquides par coprecipitation avec le carbonate de calcium: etude de laboratoire

    Energy Technology Data Exchange (ETDEWEB)

    Patti, F.; Gailledreau, C.; Cohen, P.

    1961-02-24

    As during the treatment by co-precipitation with calcium carbonate of liquid radioactive residues, a partial decontamination can be obtained by simply agitating an already formed radioactive sludge with the effluent to be processed, the authors study whether it would be possible to first perform a co-precipitation with a lower dose of calcium carbonate and then to complete decontamination by agitating with an adequate quantity of sludge stored during preceding operations. The authors report the study of the influence of reactant quantity on the chemical treatment efficiency, of the evolution of the activity of a radioactive residual solution in contact with a precipitate, of the cleaner element, of a precipitate reuse, of the technological and economic aspects, and of another possibility of reduction of the precipitate volume [French] Dans le traitement par coprecipitation avec le carbonate de calcium des residus radioactifs liquides, une decontamination partielle peut etre obtenue en agitant simplement une boue radioactive deja formee avec l'effluent a traiter. En consequence, il pourrait etre possible d'effectuer d'abord une coprecipitation avec une dose plus faible de carbonate de calcium et de completer ensuite la decontamination en agitant le liquide avec une quantite convenable de boue stockee a partir d'operations precedentes. (auteurs)

  20. Removal of radionuclides from radioactive effluents of Purex origin using biomass banana pith as sorbant

    International Nuclear Information System (INIS)

    Ramanujam, A.; Dhami, P.S.; Kannan, R.; Das, S.K.; Naik, P.W.; Gopalakrishnan, V.; Kansra, V.P.; Balu, K.

    1998-06-01

    Investigations have been carried out on the applicability of dried banana pith (inner stem) for the sorption of various radionuclides viz. U, Pu, 241 Am, 144 Ce, 147 Pm, 152+154 Eu and 137 Cs which are generally present at trace level in Purex process waste effluents. The sorption of trivalent radionuclides as well as tetravalent plutonium was found to be high at pH 2, whereas sorption of uranium was found to be maximum at pH 6. Cesium was not found to be sorbed. 241 Am sorption was investigated in detail as a representative element of trivalent actinides and fission products to study the general trend. Though its sorption was kinetically slow, near-quantitative sorption was observed on prolonged contact. 241 Am sorption was studied in presence of NaNO 3 (up to 1 M) and Nd(III) up to 500 mg/l. Whereas no significant change in distribution ratios (D) was observed in the presence of NaNO 3 , it increased with neodymium concentration in the range tested. This indicates the effectiveness of the biomass as sorbent even in presence of sodium salts. Sorbed metal ions could be recovered by leaching with 2 M nitric acid. The dried biomass samples prepared from different sources were found to be stable for months and gave similar results on testing. The biomass was tested for its applicability for sorbing radionuclides present in Purex evaporator condensate and diluted high level waste solution on once through basis. The sorption capacity of banana pith for trivalent actinide-lanthanide is in the range of 60 mg/g banana pith. The results indicate that the biomass can be used effectively for the treatment of Purex Waste effluents for the removal of strontium, tri- and tetravalent actinides and fission products. The biomass was also tested for the sorption of toxic metal ions viz. Sr, Hg, Pb, Cr, Cd, and As from a nitrate solution at pH 2 and 4. D values followed the order Hg>Sr>Cd>Pb at pH 2, with Cr and As showing no uptake. These results indicate the potential of this

  1. Modeling the atmospheric dispersion of radioactive effluents in a nuclear accident situation

    International Nuclear Information System (INIS)

    Margeanu, Sorin

    2002-01-01

    In case of a nuclear accident, which could lead to release of radioactive contaminants, fastest countermeasures are needed related to sheltering, iodine distribution, evacuation and interdiction of food and water consumption. All these decisions should be based either on estimation of inhaled dose and the dose due to external exposure for public, or on the estimation of radioactive concentration in food (which will depend on the radioactive concentration in air and ground deposition). The dispersion model used, was a Gaussian 'puff' model. The vertical dispersion was considered not dependent on the release high. The used meteorological data are specific for the SCN - Pitesti site, collected every hour for one year. The meteorological data file contains: the wind speed (in m/s), wind direction (degrees clockwise from north), atmospheric stability category, precipitation rate (in mm/h) and the high of the mixing layer (in m). A hypothetical major nuclear accident at TRIGA - SSR of INR - Pitesti, due to a serious damage of the reactor core leading, to a large release of radioactive contaminants was examined. The release was considered as a single phase with of one hour duration. The release factors for the considered isotopic mixture are 100% noble gases (of the reactor core inventory), 40% iodine (of the reactor core inventory) and 40% particulate, i.e., 40% of the fission products of core fission products inventory, released as particles. The accuracy of the model could be increased by implementation of the code on a real-time system, where the acquisition of the parameters done is on-line, namely, the data are introduced as soon as the modification of meteorological and dosimetric conditions are produced. In this case, the parameters used in formulas can be adjusted according with the field situation. Unfortunately the real-time systems need more powerful resources: monitoring stations which can measure and send on-line the data and which can cover a large area

  2. Influence of radioactive effluents from nuclear installations on mortality of the woods

    International Nuclear Information System (INIS)

    Stoutjesdijk, J.F.

    1986-11-01

    Referring to a theory of Reichelt that also radioactive materials, effused from nuclear installations and uranium ores, can contribute to mortality of the woods, it is checked, by studying corresponding literature, to what extent this agrees with the facts. According to this study the radionuclides seem to contribute to the internal and external radiation doses of plants. However these doses are so small with respect to natural radiation doses that it is highly unprobable that this effect contributes to damage of the woods. (Auth.)

  3. Some analytical methods used by the Marcoule Centre for the control of radioactive effluents; Quelques methodes analytiques, utilisees sur le centre de Marcoule pour le controle radioactif des effluents

    Energy Technology Data Exchange (ETDEWEB)

    Scheidhauer, J.; Messainguiral, L.; Drogue, N.; Meiranesio, A. M.

    1962-07-09

    After three years of operation, the authors propose a review of the various methods used to determine the radioactivity of wastewaters released by the Marcoule Centre Laboratory. They describe the three main steps of this control: firstly, measurements of the global alpha radioactivity and beta radioactivity (principle and measurement method), secondly, dosing of strontium 89 and strontium 90 (principle, used reactants, operation mode for nitric compound precipitation, ferric decontamination, separation of barium 140, oxalic precipitation, precipitate counting, exploitation of counting results), and thirdly, the possible dosing of other fission products present in the effluents: cerium 144, plutonium (by two different methods), natural uranium, caesium 137, zirconium 95, niobium 95, ruthenium 103 and 106, iodine 131. The principle, reactants, operational mode with different precipitations, measurement devices are indicated for each of these radio-elements.

  4. Environmental aspects of airbrone radioactive effluent from a coal-fired power station

    International Nuclear Information System (INIS)

    Song Miaofa; Fu Rongchu; Lu Zhizhao

    1987-01-01

    The authors determined the contents of natural uranium and thorium in coal and tunnel ash samples taken from a large coal-fired power station in the nearby area. The hourly climate data in 1980 are analysed and the atmospheric stability is cataloged by Pasquill-Turner method. Wind direction-atmospheric stability-wind velocity combined probabilities and rain-wind direction probabilities are calculated. The near ground air pollution concentrations, the ground depositions and the distributions of U and Th presented in airborne effluent (fly ash) within an area round the station with a radius of 60 km are also estimated. In the calculations, some factors such as wind velocity in the higher atmosphere, plume rise, still wind and decrease of air pollution concentration by the ground deposition (especially the wet deposition porduced by rain) have been considered. Some corrections necessary for the factors described above are also made. It is shown that the maximum annual average air pollution concentration (U max = 1.95 x 10 -7 mg.m -3 , Th max = 3.45 x 10 -7 mg.m -3 ) appears at the point 1 km away from the source in the fan SE. In the area round the station with a radius shorter than 10 km, the ground deposition is mainly by the wet deposition, but, where the radius longer than 10 km, the dry deposition must be taken into account

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  6. Environmental pollution by radioactive effluents: present situation facing the 21 Century. Part 2

    International Nuclear Information System (INIS)

    Nunez, Juan C.

    2005-01-01

    The awareness of the need to preserve the environment in the local, regional and international spheres has produced a large number of control and prevention rules that constitute the Environmental Law. The contamination of the sea has been the last field to be considered by the States. Since few years ago, marine pollution is appraised as an issue that affects all the States, taking account of its interdependency and the need to establish between governments a greater cooperation network. The radioactive contamination, i.e. the pollution produced by the discharge of radioactive wastes into the sea, is one of the types of contamination. Several discharge systems have been designed, so it is necessary to select in each case the most suitable one taking into account the type of wastes and other factors as the economy and the effectiveness of the method and the application of the radiation protection principles. International rules have evolved to solve different issues since the first United Nation Convention on the Law of the Sea in 1945 to the third Conference in 1982 that produced the United Nation Convention on the Law of the Sea and four Resolutions. The Convention and the Resolutions form an inseparable whole that show the evolution of the international cooperation in this field [es

  7. Environmental pollution by radioactive effluents: present situation facing the 21 Century. Part 1

    International Nuclear Information System (INIS)

    Nunez, Juan C.

    2005-01-01

    The awareness of the need to preserve the environment in the local, regional and international spheres has produced a large number of control and prevention rules that constitute the Environmental Law. The contamination of the sea has been the last field to be considered by the States. Since few years ago, marine pollution is appraised as an issue that affects all the States, taking account of its interdependency and the need to establish between governments a greater cooperation network. The radioactive contamination, i.e. the pollution produced by the discharge of radioactive wastes into the sea, is one of the types of contamination. Several discharge systems have been designed, so it is necessary to select in each case the most suitable one taking into account the type of wastes and other factors as the economy and the effectiveness of the method and the application of the radiation protection principles. International rules have evolved to solve different issues since the first United Nation Convention on the Law of the Sea in 1945 to the third Conference in 1982 that produced the United Nation Convention on the Law of the Sea and four Resolutions. The Convention and the Resolutions form an inseparable whole that show the evolution of the international cooperation in this field [es

  8. A database system for the control of radioactive effluents generated by the IPEN-CNEN/SP installations

    International Nuclear Information System (INIS)

    Maduar, M.F.

    1992-01-01

    A PC-compatible database system has been developed in order to optimize the control of liquid and gaseous effluents generated by the installations of IPEN-CNEN/SP. The system implements source-term generation, optimizes the discharge control of the effluents and allows several ways for the retrieval of data concerning to the effluents. (author)

  9. Radioactive effluents and present and future radiation exposure to the population from nuclear facilities in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Bonka, H.; Edelhauser, H.; Gans, I.; Wolter, R.

    1977-01-01

    As this time ten light water cooled nuclear power plants are operated outside of nuclear research centers in the Federal Republic of Germany. A review of the releases of radioactivity in gaseous and liquid effluents shows that increasing operational experience and improved technology combined with restrictive licensing policy and comprehensive control systems have resulted in decreasing release rates. Therefore radiation exposure to the population and critical groups calculated from these release rates on a local scale via different exposure pathways have been low until now. Predictions of future radiation exposure are based on the energy program of the Federal Republic of Germany up to 1985 and continuing forecasts for future energy demands, release rates of new reactor types and reprocessing plants being taken into account. In calculations of exposures to the population local models are combined with regional models superimposing contributions from sources in the Federal Republic and neighbouring countries and with a global multi-compartment model. If, with view to a continued development of the present state of science and technology in connection with major reprocessing plants, retention rates from 90-99% are assumed to be obtainable for H 3 and Kr 85, 99,5-99,9% for iodine and approximately 90% for C 14 from reprocessing plants, it can be demonstrated that also the future radiation exposure can be kept below the dose limits established in the Federal Republic of Germany

  10. Concept and approaches used in assessing individual and collective doses from releases of radioactive effluents

    International Nuclear Information System (INIS)

    1988-06-01

    To guide on the applications of the principles for limiting radioactive releases contained in Safety Series 77, the Agency is in the process of preparing a number of safety guides. The first one is this present document which deals with the principal aspects of the methods for the assessment of the individual and collective dose. It aims at giving a general guidance to those responsible for establishing programmes for the determination of individual doses as well as collective doses in connection with licensing a site for a nuclear installation. The document is concerned with the principles applied for calculating individual and collective doses from routine releases of radionuclides to the atmosphere and hydrosphere but not releases directly to the geosphere, as in waste management. These areas will be covered by other Agency publications. 75 refs, figs and tabs

  11. Application of functionalized calixarenes to the processing of radioactive effluents by supported liquid membranes

    International Nuclear Information System (INIS)

    Hill, Clement

    1994-01-01

    In a first part, this research thesis presents the general context of nuclear waste processing (nature of wastes to be processed, characteristics of the used method and products), and proposes an overview of results obtained during previous campaigns which were based on the use of the technique of supported liquid membranes, but with other types of extracting components. The second part focuses on the tracking of complexing and extractive properties of all functionalized calixarenes which had been synthesised by different research teams. Several experiments have been performed to determine the extraction efficiency and selectivity of these organic compounds with respect to the studied radio-elements. The third part reports the detailed study of a specific family of functionalized calixarenes for which two thermodynamic models of membrane transport described in the literature have been applied. Validity limits are discussed with respect to operation conditions. Some results are finally given on the caesium and actinide (neptunium, plutonium) decontamination of synthetic concentrates which simulate actual radioactive wastes [fr

  12. Automated system for the safe management of the radioactive wastes and liquid effluents in a Radiopharmaceutical an labelled compounds production center

    International Nuclear Information System (INIS)

    Amador B, Z.H.; Guerra V, R.

    2006-01-01

    The Center of Isotopes of the Republic of Cuba is a radioactive installation of first category that executes the administration of their radioactive waste under authorization of the National Regulatory Authority. The principles of the design and operation of the 'SADR' system for the safe administration of the radioactive waste and liquid effluents are presented. The Visual Basic 6 platform for the programming of the SADR is used and through of their schematic representation, the control flows and of data of the 7 modules that conform it are shown. For each module the functions are described and it presents an image of the corresponding interface. With the SADR its can be carried out the one registration and the upgrade of the inventory of radioactive waste, the planning of those disqualification operations, the annual consolidation of the volumes of waste generated and disqualified, the evaluation of specific and general indicators and the one tendencies analysis. The handling of the system through the intranet allows the enter of data from the operations place with the radioactive wastes. The results of the operation of the SADR show the utility of this work to elevate the efficiency of the administration of the radioactive wastes. (Author)

  13. Order of the 10 january 2003 authorizing the national agency for the radioactive wastes management to follow the gaseous and liquid effluents release for the exploitation of the radioactive wastes storage center of the Manche; Arrete du 10 janvier 2003 autorisant l'Agence nationale pour la gestion des dechets radioactifs a poursuivre les rejets d'effluents gazeux et liquides pour l'exploitation du centre de stockage de dechets radioactifs de la Manche

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-01-01

    This document, took out from the Official Journal, is the law text relative to the order of the 10 january 2003 authorizing the national agency for the radioactive wastes management to follow the gaseous and liquid effluents release for the exploitation of the radioactive wastes storage center of the Manche. (A.L.B.)

  14. Processing radioactive effluents with ion-exchanging resins: study of result extrapolation; Traitement des effluents radioactifs par resines echangeuses d'ions: etude de l'extrapolation des resultats

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G.

    1960-05-03

    As a previous study showed the ion-exchanging resins could be used in Saclay for the treatment of radioactive effluents, the author reports a study which aimed at investigating to which extent thus obtained results could be extrapolated to the case of higher industrial columns. The author reports experiments which aimed at determining extrapolation modes which could be used for columns of organic resin used for radioactive effluent decontamination. He notably studied whether the Hiester and Vermeulen extrapolation law could be applied. Experiments are performed at constant percolation flow rate, at varying flow rate, and at constant flow rate [French] Plusieurs etudes ont ete faites dans le but d'examiner les possibilites d'emploi des resines echangeuses d'ions pour le traitement des effluents radioactifs. Dans un rapport preliminaire, nous avons montre dans quelles limites un tel procede pouvait etre utilise au Centre d'Etudes Nucleaires de Saclay. Les essais ont ete effectues sur des petites colonnes de resine au laboratoire; il est apparu ensuite necessaire de prevoir dans quelle mesure les resultats ainsi obtenus peuvent etre extrapoles a des colonnes industrielles, de plus grande hauteur. Les experiences dont les resultats sont exposes dans ce rapport, ont pour but de determiner les modes d'extrapolation qui pourraient etre employes pour des colonnes de resine organique utilisees pour la decontamination d'effluents radioactifs. Nous avons en particulier recherche si la loi d'extrapolation de Hiester et Vermeulen qui donne de bons resultats dans le cas de fixation d'ions radioactifs en presence d'un ion macrocomposant sur des terres, pouvait etre appliquee. Les experiences, en nombre limite, ont montre que la loi d'extrapolation de Hiester et Vermeulen pouvait s'appliquer dans le cas de l'effluent considere quand les debits de percolation sont tres faibles; quand ils sont plus forts, les volumes de liquide percoles, a fixation egale, sont proportionnels aux

  15. Assessment of management alternatives for LWR wastes. Volume 5. Assessment of the radiological impact to the public resulting from discharges of radioactive effluents

    International Nuclear Information System (INIS)

    Centner, B.

    1993-01-01

    This report deals with the assessment of the radiological impact to the public resulting from discharges of radioactive effluents (liquid and gaseous) in connection with the implementation of the Belgian scenario for the management of PWR waste. Both individual and collective doses have been estimated for a critical group of the population living around the nuclear power plants concerned. This study is part of an overall theoretical exercise aimed at evaluating a selection of management wastes for LWR waste based on economical and radiological criteria

  16. Hybrid monitoring of environmental radioactivity as a perspective approach to rapid control and prediction of environmental contamination due to NPP wastes and effluents

    International Nuclear Information System (INIS)

    Eremeev, I.S.; Eremenko, V.A.; Zhernov, V.S.; Makarov, Yu.A.; Matveev, V.V.; Ryzhov, N.V.; Ryazanov, V.V.; Skatkin, V.M.

    1985-01-01

    Conseptucal model of the system of hybride monitoring of environmental radioactivity due to NPP wastes and effluents is proposed. The model a combination of measuring and simulating monitoring, provides correlation of methods and aims of simulation of environmental contamination spread methods and means of monitoring of its factual distribution in space, methods of separation of technogeneous signals from natural radiation background and provision of the given degree of reliability of results of information processing, in particular periodic coorection, model adaptation according to the factual measurement data

  17. Treated Effluent Disposal Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Treated non-hazardous and non-radioactive liquid wastes are collected and then disposed of through the systems at the Treated Effluent Disposal Facility (TEDF). More...

  18. Risk-Based Radioactive Liquid Effluent Monitoring Requirements at the U. S. Department of Energy's Savannah River Site

    International Nuclear Information System (INIS)

    Jannik, G.T.

    2001-01-01

    For Department of Energy (DOE) facilities, clear regulatory guidance exists for structuring radiological air emissions monitoring programs. However, there are no parallel regulations for radiological liquid effluent monitoring programs. In order to bridge this gap and to technically justify liquid effluent monitoring decisions at DOE's Savannah River Site, a graded, risk-basked approach has been established to determine the monitoring and sampling criteria to be applied at each liquid discharge point

  19. Saving time with a computerised handbook

    International Nuclear Information System (INIS)

    Henrie, D.K.

    1993-01-01

    The DE/CAASE computerised engineering handbook (Desktop Engineering, Mahwah, NJ, USA) is a software tool designed to automate a wide variety of engineering tasks that are typically performed with an engineering handbook and hand calculator. It significantly reduces the time taken to perform these tasks. For example, instead of spending 60 minutes on determining section properties of composite sections in control room panels and other equipment by hand, it might take less than 5 minutes by using the computerised handbook. Similarly, mode shapes and frequencies of simple structures may take less than 10 minutes to calculate, compared with the hours it used to take. (author)

  20. An intragastric trichobezoar: computerised tomographic appearance.

    Directory of Open Access Journals (Sweden)

    Morris B

    2000-04-01

    Full Text Available A 26-year-old lady presented with a history of abdominal pain and distension since two months. The ultrasound examination showed an epigastric mass, which was delineated as a filling defect in the stomach on barium studies. The computerised tomographic scan showed a gastric mass with pockets of air in it, without post-contrast enhancement. This case highlights the characteristic appearance on computerised tomography of a bezoar within the stomach, a feature that is not commonly described in medical literature.

  1. Computerised tomography in tuberculous Addison's disease

    International Nuclear Information System (INIS)

    Perry, M.C.; Eason, R.J.; Croxson, M.S.

    1983-01-01

    The important contribution computerised tomography played in the diagnosis of tuberculous Addison's disease is described. While conventional radiographic methods of demonstrating this disease are often unhelpful, C.T. is an excellent technique for demonstrating the morphology of normal and abnormal adrenal glands

  2. Radioactive effluents from nuclear power stations and nuclear fuel reprocessing plants in the European Community. Discharge data 1972-1976 radiological aspects

    International Nuclear Information System (INIS)

    Luykx, F.; Fraser, G.

    1978-04-01

    The report presents the available data on radioactive gaseous and liquid effluents discharged by nuclear power stations and nuclear fuel reprocessing plants in the European Community from 1972 to 1976. Discharges are expressed both in absolute terms and relative to the net production of electricity from the fuel. On the basis of the discharges recorded for 1976 the resulting maximum exposure of members of the population is quantified and compared with the dose limits prescribed by Euratom radiological protection standards and with the exposure resulting from natural radioactivity. It is concluded that there is no case in which a discharge could have given rise to an exposure exceeding the relevant prescribed limit. Not only did the possible maximum exposures incurred by individuals leave an appreciable safety margin relative to that limit but, for the vast majority of installations, they were comparable with or were considerably lower than the geographical and temporal variations in exposures resulting from natural radioactivity. Where environmental levels have been detectable the measured results have of course been used but, with few exceptions, the levels have remained less than the very low limits of detection currently possible. In general, where theoretical models are used to evaluate exposure, they are designed to give conservative results and hence it is likely that the true exposures are even less than those calculated

  3. Facility effluent monitoring plan for WESF

    Energy Technology Data Exchange (ETDEWEB)

    SIMMONS, F.M.

    1999-09-01

    The FEMP for the Waste Encapsulation and Storage Facility (WESF) provides sufficient information on the WESF effluent characteristics and the effluent monitoring systems so that a compliance assessment against applicable requirements may be performed. Radioactive and hazardous material source terms are related to specific effluent streams that are in turn, related to discharge points and, finally are compared to the effluent monitoring system capability.

  4. Radioactive tracer method as an instrument for testing effectiveness of effluent treatment installations and mixing patterns in natural streams

    Energy Technology Data Exchange (ETDEWEB)

    Szpilowski, S; Strzelczak, G; Winnicki, R [Institute of Nuclear Research, Warsaw (Poland)

    1976-01-01

    The radiotracer methods of evaluation of sewage flow rate, testing of effluent treatment plants and mixing patterns in natural streams have been described. Experimental works were carried out for industrial installations and natural streams. As a tracer of liquid phase an aqueous KBr solution labelled with /sup 82/Br have been used. The sediment materials have been labelled with /sup 198/Au in the form of colloidal gold. The results of investigations have been utilized for treatment process analysis and water pollution control.

  5. Radioactive airborne effluents and the environmental impact assessment of CAP1400 nuclear power plant under normal operation

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Qiong; Guo, RuiPing; Zhang, ChunMing; Chen, XiaoQiu; Wang, Bo, E-mail: wangbo@chinansc.cn

    2014-12-15

    Highlights: • Typical radionuclides dispersion from CAP1400 under normal operation was simulated. • Modified Gaussian model considered radioactive decay, dry and wet deposition and so on. • The radioactive impact pathways on the public through atmosphere were compared. • The maximum individual effective dose was lower than the public irradiation limit. - Abstract: China Advanced Passive nuclear power plant with installed capacity reaching to 1400 MW (CAP1400) is independently designed as the China's state-of-the-art third generation nuclear power brand based on AP1000 technology digestion and absorption. The concentration of typical radionuclides dispersed from CAP1400 under normal operation was calculated with modified Gaussian model, considering mixed layer height, dry deposition, wet deposition, radioactive decay and so on. The atmospheric dispersion factors, ground deposition rate, individual dose and public dose were also investigated to estimate the radioactive effects of CAP1400 under normal operation on surrounding environment and human beings. The radioactive impact pathways on the public through atmosphere, such as immersion irradiation in the smoke plume, internal irradiation from ingestion and inhalation and external irradiation from surface deposition were briefly introduced with focus on the comparison of the maximum individual effective dose to different group from atmospheric dispersion. All computation results show that the maximum individual irradiation dose happened to children with total effective irradiation dose of 4.52E−03 mSv/y, which was lower than the public irradiation limit of 0.25 mSv/y.

  6. Radioactive airborne effluents and the environmental impact assessment of CAP1400 nuclear power plant under normal operation

    International Nuclear Information System (INIS)

    Zhang, Qiong; Guo, RuiPing; Zhang, ChunMing; Chen, XiaoQiu; Wang, Bo

    2014-01-01

    Highlights: • Typical radionuclides dispersion from CAP1400 under normal operation was simulated. • Modified Gaussian model considered radioactive decay, dry and wet deposition and so on. • The radioactive impact pathways on the public through atmosphere were compared. • The maximum individual effective dose was lower than the public irradiation limit. - Abstract: China Advanced Passive nuclear power plant with installed capacity reaching to 1400 MW (CAP1400) is independently designed as the China's state-of-the-art third generation nuclear power brand based on AP1000 technology digestion and absorption. The concentration of typical radionuclides dispersed from CAP1400 under normal operation was calculated with modified Gaussian model, considering mixed layer height, dry deposition, wet deposition, radioactive decay and so on. The atmospheric dispersion factors, ground deposition rate, individual dose and public dose were also investigated to estimate the radioactive effects of CAP1400 under normal operation on surrounding environment and human beings. The radioactive impact pathways on the public through atmosphere, such as immersion irradiation in the smoke plume, internal irradiation from ingestion and inhalation and external irradiation from surface deposition were briefly introduced with focus on the comparison of the maximum individual effective dose to different group from atmospheric dispersion. All computation results show that the maximum individual irradiation dose happened to children with total effective irradiation dose of 4.52E−03 mSv/y, which was lower than the public irradiation limit of 0.25 mSv/y

  7. MOIRA: a computerised decision support system for the management of radionuclide contaminated freshwater ecosystems

    International Nuclear Information System (INIS)

    Gallego, Eduardo; Brittain, John E.; Hakanson, Lars; Heling, Rudie; Hofman, Dmitry; Monte, Luigi

    2004-01-01

    The radiation dose resulting from contamination of freshwater ecosystems due to the release of radioactive substances into the environment may be reduced by applying suitable countermeasures. Despite their benefits, intervention strategies may have detrimental effects of economic, ecological and social nature. Thus, it is of paramount importance to assess, by objective criteria, the global cost-benefit balance of different options. The MOIRA project (A MOdel based computerised system for management support to Identify optimal remedial strategies for Restoring radionuclide contaminated Aquatic ecosystems) has developed a user-friendly, computerised tool that will allow decision makers to choose optimal intervention strategies for freshwater ecosystems with different contamination scenarios. The aim of the paper is to briefly describe the main components of the MOIRA system and to demonstrate its application using real case based scenarios. (author)

  8. Bitumen coating of the radio-active sludges from the effluent treatment plant at the Marcoule centre. Review of the progress reports 1, 2, 3 and 4 (1963)

    International Nuclear Information System (INIS)

    Rodier, J.; Lefillatre, G.; Scheidhauer, J.

    1963-01-01

    Besides the very high activity liquids containing fission products, the chemical treatment of irradiated fuels produces a large volume of aqueous effluents and solid waste of relatively low radioactivity. These weakly active products can be eliminated in the ground, in a hydrographic land system or in the sea. Techniques of evaporation, of resin concentration, and of coprecipitation give rise to inorganic sludges with a high water content. All these residues occupy a large volume and represent a far from negligible weight. In the case of the sludge, their relative fluidity necessitates a conditioning guaranteeing safe storage. The solution to the problem will consist in passing directly from a liquid or a suspension, to a solid whose structure is homogeneous and whose matter is inert with respect to the storage medium (soil, sea, etc. ). We have proposed to coat the radioactive products with bitumen. This article is designed to give a review of the studies undertaken on this method. It consists of a progress report rather than a final assessment. (authors) [fr

  9. Design of a cement-based formulation for the conditioning of a NaNO3-rich intermediate-level long-lived radioactive effluent using a surrogate

    International Nuclear Information System (INIS)

    Coppens, E.; Antonucci, P.; Cau dit Coumes, C.

    2015-01-01

    Since the immobilization of concentrates in a bituminous matrix has been abandoned in Belgium in the late nineties, CEA and ONDRAF/NIRAS recently started developing an alternative conditioning technique for a historic radioactive effluent, rich in NaNO 3 . Multiple ways of treatment - in the domain of homogeneous cementation - were tested on a non-radioactive simulant of this aqueous waste stream, but due to its very low pH (∼ 0), the solution has to be neutralized to a higher pH in order to make it more compatible with general hydraulic binders. Therefore the research started by looking for a suitable base (i.e. KOH, NaOH or Ca(OH) 2 ) to neutralize the stream. Due to the formation of a viscous gel in different pH-domains, the resulting neutralization curve was separated in multiple areas of interest, i.e. those areas resulting in a highly liquid, water-like product. Only in a next step the research focused on selecting a suitable hydraulic binder (e.g. OPC, blended cement (OPC / blast-furnace slag with high contents of slag), KOH-activated slag, Fondu calcium aluminate cement). In a third step, two final formulations were established taking into account the specifications for grout implementation at industrial scale and further management of the waste packages. (authors)

  10. Radioactivity

    International Nuclear Information System (INIS)

    Chelet, Y.

    2006-01-01

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

  11. Radioactivity

    International Nuclear Information System (INIS)

    2002-01-01

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

  12. Nuclear reactor effluent monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Minns, J.L.; Essig, T.H. [Nuclear Regulatory Commission, Washington, DC (United States)

    1993-12-31

    Radiological environmental monitoring and effluent monitoring at nuclear power plants is important both for normal operations, as well as in the event of an accident. During normal operations, environmental monitoring verifies the effectiveness of in-plant measures for controlling the release of radioactive materials in the plant. Following an accident, it would be an additional mechanism for estimating doses to members of the general public. This paper identifies the U.S. Nuclear Regulatory Commission (NRC) regulatory basis for requiring radiological environmental and effluent monitoring, licensee conditions for effluent and environmental monitoring, NRC independent oversight activities, and NRC`s program results.

  13. Nuclear reactor effluent monitoring

    International Nuclear Information System (INIS)

    Minns, J.L.; Essig, T.H.

    1993-01-01

    Radiological environmental monitoring and effluent monitoring at nuclear power plants is important both for normal operations, as well as in the event of an accident. During normal operations, environmental monitoring verifies the effectiveness of in-plant measures for controlling the release of radioactive materials in the plant. Following an accident, it would be an additional mechanism for estimating doses to members of the general public. This paper identifies the U.S. Nuclear Regulatory Commission (NRC) regulatory basis for requiring radiological environmental and effluent monitoring, licensee conditions for effluent and environmental monitoring, NRC independent oversight activities, and NRC's program results

  14. [Reliability of Primary Care computerised medication records].

    Science.gov (United States)

    García-Molina Sáez, Celia; Urbieta Sanz, Elena; Madrigal de Torres, Manuel; Piñera Salmerón, Pascual; Pérez Cárceles, María D

    2016-03-01

    To quantify and to evaluate the reliability of Primary Care (PC) computerised medication records of as an information source of patient chronic medications, and to identify associated factors with the presence of discrepancies. A descriptive cross-sectional study. General Referral Hospital in Murcia. Patients admitted to the cardiology-chest diseases unit, during the months of February to April 2013, on home treatment, who agreed to participate in the study. Evaluation of the reliability of Primary Care computerised medication records by analysing the concordance, by identifying discrepancies, between the active medication in these records and that recorded in pharmacist interview with the patient/caregiver. Identification of associated factors with the presence of discrepancies was analysed using a multivariate logistic regression. The study included a total of 308 patients with a mean of 70.9 years (13.0 SD). The concordance of active ingredients was 83.7%, and this decreased to 34.7% when taking the dosage into account. Discrepancies were found in 97.1% of patients. The most frequent discrepancy was omission of frequency (35.6%), commission (drug added unjustifiably) (14.6%), and drug omission (12.7%). Age older than 65 years (1.98 [1.08 to 3.64]), multiple chronic diseases (1.89 [1.04 to 3.42]), and have a narcotic or psychotropic drug prescribed (2.22 [1.16 to 4.24]), were the factors associated with the presence of discrepancies. Primary Care computerised medication records, although of undoubted interest, are not be reliable enough to be used as the sole source of information on patient chronic medications when admitted to hospital. Copyright © 2015 Elsevier España, S.L.U. All rights reserved.

  15. Study of optimal transformation of liquid effluents resulting from the destruction of radioactive sodium by water into ultimate solid wastes

    International Nuclear Information System (INIS)

    Rodriguez, G.; Camaro, S.; Fiquet, O.; Bernard, A.; Le Bescop, P.

    1997-01-01

    In the framework of sodium waste processing, it has been proposed to retain only processes that treat the sodium using water, thus generating the same by-products: hydrogen and sodium hydroxide. As the objective is to minimise radioactive liquid releases and as, moreover, the authorizations with respect to sodium salt releases are highly restrictive, several solutions have been envisaged for transforming the active sodium hydroxide coming from sodium destruction processes into ultimate solid wastes that can be stored on the surface in a storage site approved by the ANDRA (National Radioactive Waste Management Agency): the Aube Storage Site (CSA). Two processes have been considered and compared: immobilisation in concrete (cementation) and immobilisation in ceramic (ceramisation). These two processes are evaluated according to several criteria: the state of advancement of the process, the quantity of sodium hydroxide (and therefore of sodium) that can be treated per package. (author)

  16. Software for computerised analysis of cardiotocographic traces.

    Science.gov (United States)

    Romano, M; Bifulco, P; Ruffo, M; Improta, G; Clemente, F; Cesarelli, M

    2016-02-01

    Despite the widespread use of cardiotocography in foetal monitoring, the evaluation of foetal status suffers from a considerable inter and intra-observer variability. In order to overcome the main limitations of visual cardiotocographic assessment, computerised methods to analyse cardiotocographic recordings have been recently developed. In this study, a new software for automated analysis of foetal heart rate is presented. It allows an automatic procedure for measuring the most relevant parameters derivable from cardiotocographic traces. Simulated and real cardiotocographic traces were analysed to test software reliability. In artificial traces, we simulated a set number of events (accelerations, decelerations and contractions) to be recognised. In the case of real signals, instead, results of the computerised analysis were compared with the visual assessment performed by 18 expert clinicians and three performance indexes were computed to gain information about performances of the proposed software. The software showed preliminary performance we judged satisfactory in that the results matched completely the requirements, as proved by tests on artificial signals in which all simulated events were detected from the software. Performance indexes computed in comparison with obstetricians' evaluations are, on the contrary, not so satisfactory; in fact they led to obtain the following values of the statistical parameters: sensitivity equal to 93%, positive predictive value equal to 82% and accuracy equal to 77%. Very probably this arises from the high variability of trace annotation carried out by clinicians. Copyright © 2015 Elsevier Ireland Ltd. All rights reserved.

  17. Review of IAEA recommendations on the principles and methodologies for limiting releases of radioactive effluents to the environment

    International Nuclear Information System (INIS)

    Ahmed, J.U.

    1988-01-01

    The limitation of radioactive releases is governed by the basic principles of radiation protection as presented in the ICRP Publication No. 26 and IAEA Safety Series No. 9. Unter its current programme on release limitation the IAEA issued Safety Series No. 77 on principles for release limitation and Safety Series No. 67 on protection against transboundary radiation exposures. A Safety Guide on global upper bounds is now nearly ready for publication, and to guide on the application of Safety Series No. 77, four documents are in various stages of completion

  18. Filtration device for active effluents

    International Nuclear Information System (INIS)

    Guerin, M.; Meunier, G.

    1994-01-01

    Among the various techniques relating to solid/liquid separations, filtration is currently utilized for treating radioactive effluents. After testing different equipments on various simulated effluents, the Valduc Center has decided to substitute a monoplate filter for a rotative diatomite precoated filter

  19. Beta-ray depth dose in tissue equivalent material due to gaseous radioactive effluents from nuclear power plants

    International Nuclear Information System (INIS)

    Schadt, W.W.

    1978-01-01

    The magnitude of the absorbed dose to skin from beta particles emitted by the radionuclides in gaseous effluents from boiling water nuclear power reactors is investigated in this dissertation. Using the radionuclide release patterns of F. Brutschy and the beta dosimetry methods of M. Berger, an equation is derived which gives the dose rate in rads per day when the total radionuclide concentration is one microcurie per gram of air. The coefficients in the equation are presented for a wide range of reactor gas hold-up times (48 minutes to 6 days) and plume environmental transit time (0.5 to 60 minutes). The beta dose rates at the skin surface are found to range from 3.9 to 26.7 rads per day. An upper limit of the relative standard deviation in the dose rate is estimated to be 30 percent. The techniques used to develop the equation are applied to data from the Millstone Nuclear Power Station obtained during the summer of 1972. The beta dose at a site 1.7 miles from the reactor is determined to have been 675 millirads per year at the skin surface and 476 millirads per year at a depth of 200 micrometers. At a site 5.1 miles from the reactor these dose rates were 138 and 100 millirads per year respectively

  20. Estimative of dilution factor for radioactive liquid effluents employing the H-3 and Cs-137 radiotracers present as pollutant

    International Nuclear Information System (INIS)

    Nisti, Marcelo Bessa; Santos, Adir Janete Godoy dos

    2011-01-01

    It was estimated the dilution factor for liquid effluents at the discharge points of the IPEN, Sao Paulo, Brazil, employing as radiotracers the radioisotope routinely liberated for the sewage of 'Cidade Universitaria Armando de Salles Oliveira' - CUASO 3 H and 137 Cs, not generating either monetary or environmental cost associated to the estimation. The 137 Cs was determined by gamma spectrometry and the 3 H was determined liquid phase scintillation. The results showed that the dilution factor varied according to the employed radiotracer in a crescent order of 3 H and 137 Cs according to the characteristics of each element. The average of dilution factors obtained at the first and second liberation day were 4.3 and 7.4 respectively for the 3 H and 6.2 and 13.9 for the 137 Cs. The ratio of dilution factors of calculated 3 H and 137 Cs were coherent with the ratio verified at the twelve hydrometers distributed by the IPEN campus. The dilution factors were estimated in operational and laboratory study, in a single controlled discharge of the TR1 tank

  1. Impact assessment for the aquatic biota arising from discharges of radioactive liquid effluents into the marine environment - Angra dos Reis nuclear power plants

    International Nuclear Information System (INIS)

    Lauria, D.C.; Peres, S.S.; Martins, S.F.

    2011-01-01

    The Piraquara de Fora Bay receives the liquid effluents from the two Brazilian nuclear power plants (NPPs): Angra I that has been operating since 1985 and Angra II that started operating in 2000. The monitoring data set obtained by IRD/CNEN for marine samples over a period of 25 years (from 1985 to 2010) were statistically evaluated. Despite the high presence of non detect observations, suitable statistical tests were applied to compare 60 Co levels in sediments between two periods of time and from different sampling locations. The natural dose and the dose derived from the NPPs routine radioactive releases on the marine biota were assessed by the Erica tool. The highest value of dose rate due to the naturally occurrence radionuclides was estimated to be around 0.6 μGy h -1 for phytoplankton, mainly due to internal dose contribution of 238 U, while fishes received the highest dose (value around 0.4 μGy h -1 ) due to the radionuclide discharges of the NPPs. Accordingly, the dose rates to the studied species (fish, crustacean, macroalgae, zooplankton and phytoplankton) were clearly below the Erica screening level of 10 μGy h -1 , indicating no significant radiological impact of NPPs on these species. (author)

  2. Facility effluent monitoring plan for WESF

    International Nuclear Information System (INIS)

    SIMMONS, F.M.

    1999-01-01

    The FEMP for the Waste Encapsulation and Storage Facility (WESF) provides sufficient information on the WESF effluent characteristics and the efferent monitoring systems so that a compliance assessment against applicable requirements may be performed. Radioactive and hazardous material source terms are related to specific effluent streams that are in turn, related to discharge points and, finally are compared to the effluent monitoring system capability

  3. Multitasking in non-computerised and computerised versions of the Breakfast Task in healthy adult aging

    OpenAIRE

    Kozlowska, Maria Teresa

    2010-01-01

    Older adults demonstrate poor performance on standard executive tests. However, age-related deficits have been found only on a number of more realistic executive tests. The present study investigated age effects in multitasking, requiring a range of executive, as well as non-executive, cognitive functions. Previous study by Craik and Bialystok (2006) showed impaired performance of older adults on a computerised multitasking test, which simulated cooking breakfast. Participants were instructed...

  4. Automated system of control of radioactive liquid effluents of patients submitted to therapy in hospitals of nuclear medicine (SACEL); Sistema automatizado de control de efluentes liquidos radiactivos de pacientes sometidos a terapia en hospitales de medicina nuclear (SACEL)

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz C, M A; Rivero G, T; Celis del Angel, L; Sainz M, E; Molina, G [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2006-07-01

    Different hospitals of nuclear medicine require of the technical attendance for the design, construction and instrumentation of an effluents retention system coming from the room dedicated to the medical application of iodine 131, with the one object of giving execution to the normative requirements of radiological protection, settled down in the General Regulation of Radiological Safety (RGSR) emitted by the CNSNS in November, 1988 and in the corresponding official standards. An automatic system of flow measurement, the activity concentration of the effluents to the drainage, the discharges control and the automated report it will allow the execution of the national regulations, also the elimination of unhealthy activities as the taking of samples, analysis of those same and the corresponding paperwork, its will allow that the SACEL is capable of to carry out registrations that are to consult in an automated way. The changes in the demands of the National Commission of Nuclear Safety and Safeguards in relation to the liberation of radioactive material in hospitals by medical treatments, it has created the necessity to develop a system that quantifies and dose the liquid effluents of people under thyroid treatment with iodine-131 to the drainage. The Automated System of Control of radioactive liquids effluents generated in Hospitals of Nuclear Medicine (SACEL) developed in the National Institute of Nuclear Research, it fulfills this regulation, besides improving the work conditions for the medical and technical personnel of the hospital in that are installed, since this system has the advantage of to be totally automated and to require of a minimum of attendance. The SACEL is an electro-hydraulic system of effluents control, based in the alternate operation of two decay deposits of the activity of the material contaminated with iodine-131. The system allows to take a registration of those volumes and liberated dose, besides being able to be monitoring in remote

  5. Optimum modellings of atmospheric diffusion of radioactive effluents and exposure doses in the accident consequence assessment (Level 3 PSA)

    International Nuclear Information System (INIS)

    Kim, Byung Woo; Lee, Young Bok; Han, Moon Hee; Kim, Eun Han; Suh, Kyung Suk; Hwang, Won Tae

    1992-12-01

    Atmospheric diffusion and exposure strongly dependent on the environment were firstly considered in the full spectrum of accident consequence assessment to establish based on Korean conditions. An optimum weather category based on Korean climate and site-specific meteorology of Kori region was established by statistical analysis of measured data for 10 years. And a trajectory model was selected as the optimal one in the ACA by reviewing several existing diffusion models. Following aspects were considered in this selection as availability of meteorological data, ability to treat the change to wind direction, easy applicability of the model, and restriction of CPU time and core memory in current computers. Numerical integration method of our own was selected as the optimal dose assessment tool of external exposure. Unit dose rate was firstly computed with this method as the function of energy level of radionuclide, size of lattice, and distance between source and receptor, and then the results were rearranged as the data library for the rapid access to the ACA run. Dynamic ecosystem modelling has been done in order to estimate the seasonal variation of radioactivity for the assessment of ingestion exposure, considering Korean ingestion behavior, agricultural practice and the transportation. There is a lot of uncertainty in a countermeasure model due to the assumed values of parameters such as fraction of population with different shielding factor and driving speed. A new countermeasure model was developed using the concept of fuzzy set theory, since it provided the mathematical tools which could characterize the uncertainty involved in countermeasure modelling. (Author)

  6. Debating the utility of computerised neurocognitive testing in the ...

    African Journals Online (AJOL)

    computerised neurocognitive baseline testing in the sports concus- sion context,. 1 ... testing for athletes at this time is scientifically unfounded, financially irresponsible and .... medical management in respect of the sports concussive injury. It.

  7. Computerisation of procedures. Lessons learned and future perspectives

    International Nuclear Information System (INIS)

    O'Hara, J.; Pirus, D.; Nilsen, S.; Bisio, R.; Hulsund, J.-E.; Zhang, W.

    2003-07-01

    The computerisation of the procedures has been investigated for several years. Even though guidelines for such computerisation have been proposed, there is a need to extend and revise these guidelines. In this report, we look at what has been achieved so far, both within the Halden Project as well as within other organisations related to nuclear power plants. These experiences are often related to testing of particular computerised procedure systems either in research laboratories or in nuclear utilities. These activities have accumulated a body of general knowledge on the subject, as documented in other 'lessons learned' reports of the past. This report will extend this accepted body of knowledge. Furthermore, we identify the unresolved problems that need to be further studied to make usable computerised procedures for the future. The report identifies selected qualities that should be reinforced to make computerised procedure systems better. In particular, the integration aspect is emphasised. A flexible integration with the operator tasks and the remaining interfaces of the control room is important. Unless this integration is accomplished, the computerised procedures will not be functional. Another aspect of integration is combination with other systems inclusive those systems that deal with the plant documentation, electronic or paper based. This kind of integration is important to the safe and reliable operation of the plant. Good integration with plant documentation is instrumental in creating reliable QA of the procedures that covers the whole life cycle of the procedure. (Author). 48 refs., 12 figs., 2 tabs

  8. Waste Treatment Plant Liquid Effluent Treatability Evaluation

    International Nuclear Information System (INIS)

    LUECK, K.J.

    2001-01-01

    Bechtel National, Inc. (BNI) provided a forecast of the radioactive, dangerous liquid effluents expected to be generated by the Waste Treatment Plant (WTP). The forecast represents the liquid effluents generated from the processing of 25 distinct batches of tank waste through the WTP. The WTP liquid effluents will be stored, treated, and disposed of in the Liquid Effluent Retention Facility (LERF) and the Effluent Treatment Facility (ETF). Fluor Hanford, Inc. (FH) evaluated the treatability of the WTP liquid effluents in the LERFIETF. The evaluation was conducted by comparing the forecast to the LERFIETF treatability envelope, which provides information on the items that determine if a liquid effluent is acceptable for receipt and treatment at the LERFIETF. The WTP liquid effluent forecast is outside the current LERFlETF treatability envelope. There are several concerns that must be addressed before the WTP liquid effluents can be accepted at the LERFIETF

  9. Prototype models for the MOIRA computerised system

    Energy Technology Data Exchange (ETDEWEB)

    Monte, Luigi [ENEA, Centro Ricerche Casaccia, Rome (Italy). Dipt. Ambiente; Hakanson, Lars [Uppsala, Univ. (Sweden). Institute of Earth Sciences; Brittain, John [Oslo, Univ. (Norway). Zoological Museum

    1997-06-01

    The main aim of the present report is to describe selected models and the principles of the Decision Analysis theory that will be applied to develop the model-based computerised system `MOIRA`. A dose model and a model for predicting radiocaesium migration in lakes and the effects of countermeasures to reduce the contamination levels in the components of lacustrine system are described in detail. The principles for developing prototype models for predicting the migration of {sup 90}Sr in lake abiotic and biotic components are discussed. The environmental models described in the report are based on the use of `collective parameters` which due to mutual compensation effects of different phenomena occurring in complex systems, show low variability when the environmental conditions change. Use of such `collective parameters` not only increases the predictive power of the models, but also increases the practical applicability of the model. Among the main results described in the report, the development of an objective hierarchy table for evaluating the effectiveness of a countermeasure when the economic, social and ecological impacts are accounted for, deserves special attention.

  10. Bitumen coating of the radio-active sludges from the effluent treatment plant at the Marcoule centre. Review of the progress reports 1, 2, 3 and 4 (1963); Enrobage par le bitume des boues radioactives de la station de traitement des effluents du centre de Marcoule. Mise au point des etats d'avancement 1, 2, 3 et 4. (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J.; Lefillatre, G.; Scheidhauer, J. [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1963-07-01

    Besides the very high activity liquids containing fission products, the chemical treatment of irradiated fuels produces a large volume of aqueous effluents and solid waste of relatively low radioactivity. These weakly active products can be eliminated in the ground, in a hydrographic land system or in the sea. Techniques of evaporation, of resin concentration, and of coprecipitation give rise to inorganic sludges with a high water content. All these residues occupy a large volume and represent a far from negligible weight. In the case of the sludge, their relative fluidity necessitates a conditioning guaranteeing safe storage. The solution to the problem will consist in passing directly from a liquid or a suspension, to a solid whose structure is homogeneous and whose matter is inert with respect to the storage medium (soil, sea, etc. ). We have proposed to coat the radioactive products with bitumen. This article is designed to give a review of the studies undertaken on this method. It consists of a progress report rather than a final assessment. (authors) [French] En dehors des liquides de tres haute activite contenant des produits de fission, le traitement chimique des combustibles irradies produit un volume important d'effluents aqueux et de residus solides de radioactivite relativement faible. Ces produits, faiblement actifs, peuvent etre elimines dans le sol, dans un systeme hydrographique terrestre ou dans la mer. Les techniques d'evaporation, de concentration sur resine, de coprecipitation, permettent la decontamination prealable des liquides. La coprecipitation donne naissance a des boues minerales dont la teneur en eau est elevee. Tous ces residus occupent un volume important et representent un poids non negligeable. Dans le cas des boues, leur fluidite relative exige un conditionnement donnant toutes garanties de securite au stockage. La solution du probleme consistera a passer directement d'un liquide ou d'une suspension a un solide

  11. Bitumen coating of the radio-active sludges from the effluent treatment plant at the Marcoule centre. Review of the progress reports 1, 2, 3 and 4 (1963); Enrobage par le bitume des boues radioactives de la station de traitement des effluents du centre de Marcoule. Mise au point des etats d'avancement 1, 2, 3 et 4. (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J; Lefillatre, G; Scheidhauer, J [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1963-07-01

    Besides the very high activity liquids containing fission products, the chemical treatment of irradiated fuels produces a large volume of aqueous effluents and solid waste of relatively low radioactivity. These weakly active products can be eliminated in the ground, in a hydrographic land system or in the sea. Techniques of evaporation, of resin concentration, and of coprecipitation give rise to inorganic sludges with a high water content. All these residues occupy a large volume and represent a far from negligible weight. In the case of the sludge, their relative fluidity necessitates a conditioning guaranteeing safe storage. The solution to the problem will consist in passing directly from a liquid or a suspension, to a solid whose structure is homogeneous and whose matter is inert with respect to the storage medium (soil, sea, etc. ). We have proposed to coat the radioactive products with bitumen. This article is designed to give a review of the studies undertaken on this method. It consists of a progress report rather than a final assessment. (authors) [French] En dehors des liquides de tres haute activite contenant des produits de fission, le traitement chimique des combustibles irradies produit un volume important d'effluents aqueux et de residus solides de radioactivite relativement faible. Ces produits, faiblement actifs, peuvent etre elimines dans le sol, dans un systeme hydrographique terrestre ou dans la mer. Les techniques d'evaporation, de concentration sur resine, de coprecipitation, permettent la decontamination prealable des liquides. La coprecipitation donne naissance a des boues minerales dont la teneur en eau est elevee. Tous ces residus occupent un volume important et representent un poids non negligeable. Dans le cas des boues, leur fluidite relative exige un conditionnement donnant toutes garanties de securite au stockage. La solution du probleme consistera a passer directement d'un liquide ou d'une suspension a un solide dont la structure

  12. Movement of Radioactive Effluents in Natural Waters at Hanford; Le Mouvement des Effluents Radioactifs dans les Eaux Naturelles a Hanford; 0414 0412 0418 0416 0414 ; Movimiento de los Efluentes Radiactivos en Aguas Naturales en Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Honstead, J. F.; Foster, R. F.; Bierschenk, W. H. [Hanford Laboratories Operation, Hanford Atomic Products Operation, General Electric Company, Richland, WA (United States)

    1960-07-01

    The Hanford plant is located in a semi-arid region on a very thick bed of unconsolidated water-deposited sediments resting on the basalt bedrock. This material may be considered in two geologic units, the lower bed being much less permeable than the upper. The Columbia River flows through the plant area and it is first used for human consumption about 55 km downstream from the last reactor plant. Low-level effluent from the reactors is discharged into the Columbia River after a one-to-three hours' hold-up period in retention basins. More than 60 radioisotopes have been identified in the effluent, nearly all of very short half-life. Depletion of various radioisotopes in river water by mechanisms other than decay is observed. This averages about 40% in the 55 km between the reactors and Pasco and is ascribed to biological assimilation and sedimentation processes. Low-level waste solutions from chemical processing plants are discharged into the ground where they seep through 70 to 120 m of sediments before reaching the local water table. Most of the radioactive material is immobilized by adsorption or other reactions during passage through the soil. The water and the few contaminants that reach the water-table move with the ground water towards the Columbia River. The rate and direction of travel are determined by the form of the water-table surface and the hydraulic characteristics of the transmitting aquifers. The local water-table configuration has been radically affected by the disposal of large volumes of water. From the gradient and the measured permeabilities of the aquifers an average 'travel time' for water of 180 years is estimated. Is is recognized that the maximum velocity may be several times the average. However, the effect of adsorption or other reactions is to greatly slow down the movement of dissolved material relative to the rate of movement of the water. No movement of fission products from the disposal sites to the river has been detected. (author

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

    International Nuclear Information System (INIS)

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

    1976-05-01

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

  14. Study of the synthesis of TiO2 layers on macroporous ceramic supports in supercritical (SC) CO2 for processing radioactive aqueous effluents in dynamic mode

    International Nuclear Information System (INIS)

    Duchateau, Maxime

    2014-01-01

    Public and military nuclear industry generates a significant amount of radioactive liquid waste which must be treated before being released into the environment. Decontamination methods alternative to the industrial techniques (evaporation, chemical treatment) are being developed, such as column treatments or coupled filtration/sorption processes. Current researches mainly focus on the development and shaping of specific sorbents. In this context, the objectives of this thesis were first to study the synthesis of TiO 2 layers on macroporous ceramic supports in supercritical (SC) CO 2 and then to evaluate their potential for radionuclide extraction in these alternative processes. A robust synthesis method has been developed, based on the thermal decomposition of titanium isopropoxide in SC CO 2 in the temperature range between 150 C and 350 C. Nano-structured TiO 2 films were formed on the macroporous supports (ceramic foams, tubular α-alumina supports) with good adhesion, already at 150 C. The effect of the synthesis temperature on sorbents physico-chemical characteristics and sorption properties has been studied with TiO 2 powders prepared under the same conditions as the supported films. The best sorption performance were observed for the powder prepared at 150 C, owing to its higher density of surface sites in comparison with powders prepared at either 250 C or 350 C. Consequently, this synthesis temperature (150 C) was selected for a detailed study of the composite sorbents (TiO 2 /support), in order to assess their sorption performance in continuous treatment processes. The sorption experiments have shown that a column of alumina macroporous foam (Φpore = 400μm) coated with TiO 2 was suitable for processing effluents in dynamic mode with high throughputs. Both macro-pore sizes and column height were revealed as important parameters to be controlled. For the coupled filtration/sorption treatment, TiO 2 membranes exhibit good mechanical strength and are able

  15. Order of 30 March 1988 on licensing of gaseous radioactive effluent releases by the Fontenay-aux-Roses Nuclear Research Centre

    International Nuclear Information System (INIS)

    1988-01-01

    This Decree prescribes the documents and information the Fontenay-aux-Roses Nuclear Research Centre must provide to the Central Service for Protection against Ionizing Radiation (SCPRI) and lays down the permissible effluent release limits for the Centre [fr

  16. Detection of left ventricular thrombi by computerised tomography

    International Nuclear Information System (INIS)

    Nair, C.K.; Sketch, M.H.; Mahoney, P.D.; Lynch, J.D.; Mooss, A.N.; Kenney, N.P.

    1981-01-01

    Sixteen patients suspected of having left ventricular mural thrombi were studied. All had suffered transmural myocardial infarction. Fifteen patients had a ventricular aneurysm. One had had systemic emboli. The mean length of time between the myocardial infarction and the study was 14.8 months, with a range of one month to 79 months. All patients underwent computerised tomography of the heart, M-mode echocardiography (M-mode), and two-dimensional echocardiography (2-D). Eight patients underwent left ventricular cineangiography. Five patients had surgical confirmation. Computerised tomography, two-dimensional, and M-mode echocardiography predicted left ventricular mural thrombi in 10, eight, and one of the 16 patients, respectively. Left ventricular cineangiography predicted left ventricular mural thrombi in four out of eight patients. Computerised tomography and left ventricular cineangiography correctly predicted the presence or absence of left ventricular thrombi in all five patients who underwent operation. In the same group, however, two-dimensional and M-mode echocardiography failed to predict the presence of thrombi in one and three patients, respectively. Among the 11 patients without surgical confirmation, one, in whom no left ventricular thrombi were shown by M-mode and two-dimensional echocardiography, was found to have thrombi on computerised tomography. In another, two-dimensional echocardiography was positive but this finding was not confirmed either by computerised tomography or by left ventricular angiography. (author)

  17. A Study Of The Dilution Of Radio-Active Waste In The Rhone (1961); Etude de la dilution dans le rhone des effluents radioactifs du Centre de Marcoule (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J; Scheidhauer, J; Marichal, M; Court, R [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1961-07-01

    The discharge into the Rhone of liquid radio-active waste from the Marcoule Centre necessitates a large number of measurements, in particular chemical and radio-chemical analysis of the waste, itself and of the waters of the Rhone both above arid below the point of discharge. The results thus obtained during 1960 made it possible to evaluate the total amount of active waste discharged and its dilution in the receiving medium. A statistical study of the results of the analysis of the Rhone waters shows that a satisfactory dilution of the waste occurs rapidly; the experimental results obtained with an experimental discharge of rhodamine are thus confirmed. (authors) [French] Le rejet au Rhone des effluents radioactifs liquides produits sur le Centre de Marcoule donne lieu a un grand nombre de mesures et en particulier d'analyses chimiques et radio-chimiques des effluents eux-memes ainsi que des eaux du Rhone avant et apres rejet. Au cours de l'annee 1960, l'ensemble des resultats ainsi obtenus a permis de dresser un bilan des activites rejetees et de leur dispersion dans le milieu recepteur. Une etude statistique des resultats d'analyses des eaux du Rhone montre qu'une dilution satisfaisante des effluents s'effectue rapidement confirmant ainsi les resultats obtenus lors d'un rejet experimental de rhodamine. (auteurs)

  18. A contribution to the study of radioactive waste dilution in the Rhone involving tests with a rhodamine B tracer; Contribution a l'etude de la dilution des effluents radioactifs dans le Rhone par le rejet experimental de rhodamine B

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J.; Marichal, M. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Centre de production de plutonium de Marcoule, Service de protection contre les radiations (France)

    1961-07-01

    The process whereby waste from the Marcoule plant mixes with the water in the Rhone was followed in tests with rhodamine as a chemical tracer. Satisfactory dispersion was noted less than 4 km downstream from the waste discharge duct outlet, and the degree of homogeneity was considered to be satisfactory at the bridge of Roquemaure, und perfect at Avignon. This investigation not only revealed a complete absence of any preferential flow paths containing high radioactive waste concentrations, but it also enabled the most representative points to be selected at which to take Rhone water samples during future radioactive waste discharges. Reprint of a paper published in 'La Houille Blanche' N. 5 - Aug 196, p. 636-641 [French] L'emploi de la rhodamine comme traceur chimique a permis de suivre l'evolution du melange des effluents du Centre de Marcoule aux eaux du Rhone. La dispersion est deja satisfaisante a moins de 4 km en aval de la conduite des rejets, et l'homogeneite peut etre consideree comme atteinte au pont de Roquemaure et parfaite a Avignon. Cette etude a montre que les veines preferentielles ou se concentrait l'ecoulement des effluents radioactifs n'existent pas. Elle a permis de preciser en outre les emplacements les plus representatifs des points d'echantillonnage des eaux du Rhone au cours des rejets. Reproduction d'un article publie dans 'La houille blanche' N. 5 - Aug 196, p. 636-641.

  19. Correlation of radioactive-waste-treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: conversion of yellow cake to uranium hexafluoride. Part II. The solvent extraction-fluorination process

    Energy Technology Data Exchange (ETDEWEB)

    Sears, M.B.; Etnier, E.L.; Hill, G.S.; Patton, B.D.; Witherspoon, J.P.; Yen, S.N.

    1983-03-01

    A cost/benefit study was made to determine the cost and effectiveness of radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials and chemicals from a model uranium hexafluoride (UF/sub 6/) production plant using the solvent extraction-fluorination process, and to evaluate the radiological impact (dose commitment) of the release materials on the environment. The model plant processes 10,000 metric tons of uranium per year. Base-case waste treatment is the minimum necessary to operate the process. Effluents meet the radiological requirements listed in the Code of Federal Regulations, Title 10, Part 20 (10 CFR 20), Appendix B, Table II, but may not be acceptable chemically at all sites. Additional radwaste treatment techniques are applied to the base-case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The costs for the added waste treatment operations and the corresponding dose committment are correlated with the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. Much of the technology used in the advanced cases will require development and demonstration, or else is proprietary and unavailable for immediate use. The methodology and assumptions for the radiological doses are found in ORNL-4992.

  20. Correlation of radioactive-waste-treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: conversion of yellow cake to uranium hexafluoride. Part II. The solvent extraction-fluorination process

    International Nuclear Information System (INIS)

    Sears, M.B.; Etnier, E.L.; Hill, G.S.; Patton, B.D.; Witherspoon, J.P.; Yen, S.N.

    1983-03-01

    A cost/benefit study was made to determine the cost and effectiveness of radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials and chemicals from a model uranium hexafluoride (UF 6 ) production plant using the solvent extraction-fluorination process, and to evaluate the radiological impact (dose commitment) of the release materials on the environment. The model plant processes 10,000 metric tons of uranium per year. Base-case waste treatment is the minimum necessary to operate the process. Effluents meet the radiological requirements listed in the Code of Federal Regulations, Title 10, Part 20 (10 CFR 20), Appendix B, Table II, but may not be acceptable chemically at all sites. Additional radwaste treatment techniques are applied to the base-case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The costs for the added waste treatment operations and the corresponding dose committment are correlated with the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. Much of the technology used in the advanced cases will require development and demonstration, or else is proprietary and unavailable for immediate use. The methodology and assumptions for the radiological doses are found in ORNL-4992

  1. The treatment of effluents

    International Nuclear Information System (INIS)

    Wormser, G.; Rodier, J.; Robien, E. de; Fernandez, N.

    1964-01-01

    For several years the French Atomic Energy Commission has been studying with interest problems presented by radio-active effluents. Since high activities have not yet received a definite solution we will deal only, in this paper, with the achievements and research concerning low and medium activity effluents. In the field of the achievements, we may mention the various effluent treatment stations which have been built in France; a brief list will be given together with an outline of their main new features. Thus in particular the latest treatment stations put into operation (Grenoble, Fontenay-aux-Roses, Cadarache) will be presented. From all these recent achievements three subjects will be dealt with in more detail. 1 - The workshop for treating with bitumen the sludge obtained after concentration of radionuclides. 2 - The workshop for treating radioactive solid waste by incineration. 3 - A unit for concentrating radio-active liquid effluents by evaporation. In the field of research, several topics have been undertaken, a list will be given. In most cases the research concerns the concentration of radionuclides with a view to a practical and low cost storage, a concentration involving an efficient decontamination of the aqueous liquids in the best possible economic conditions. For improving the treatments leading to the concentration of nuclides, our research has naturally been concerned with perfecting the treatments used in France: coprecipitation and evaporation. In our work we have taken into account in particular two conditions laid down in the French Centres. 1 - A very strict sorting out of the effluents at their source in order to limit in each category the volume of liquid to be dealt with. 2 - The necessity for a very complete decontamination due to the high population density in our country. In the last past we present two original methods for treating liquid effluents. 1 - The use of ion-exchange resins for liquids containing relatively many salts. The

  2. Study of the mineral absorbent precipitation phenomena used in decontamination of radioactive effluents; Etude des phenomenes de precipitation d'adsorbants mineraux utilises en decontamination d'effluents radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Pacary, V. [Institut National Polytechnique, 54 - Nancy (France)]|[CEA Valrho, Lab. des Procedes Avances de Decontamination (LPAD), 30 - Marcoule (France)

    2006-07-01

    The aim of this work is to determine the optimal conditions of the reactor running (feed rate, reagents concentration..) for which the effluent decontamination is the most efficient. Thus will be in particular studied the coprecipitation mechanisms and the influence of the physico-chemical conditions on these mechanisms. On the other hand, the processes occurred in the coprecipitation phenomenon being complex, the elaboration of a model is indispensable to guide and interpret the experimental work. This model will be based on the knowledge developed in precipitation and will allow to simulate the decontamination in two reactors types: the reactor fed in continuous in reagents and in effluents as the Hague's ones and the closed reactor fed only in reagents as the Marcoule's ones. (O.M.)

  3. Treatment of Radioactive Effluents at the Saclay Nuclear Research Centre; Traitement des Effluents Radioactifs au Centre d'Etudes Nucleaires de Saclay; 041e 0414 ; Tratamiento de los Efluentes Radiactivos en el Centro de Energia Nuclear de Saclay

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    The Report Gives The Account Of Four Years' Experience In Operating The Treatment Plant For Effluents From The Saclay Nuclear Research Centre. It Contains Data Relating To The Origin, Volume And Treatment Of Waste. (author) [French] Ce rapport presente un bilan d'exploitation de l'installation de traitement des effluents du Centre d'etudes nucleaires de Saclay depuis quatre ans. On donne des chiffres concernant l'origine des residus, leur volume, leur traitement. (author) [Spanish] El autor hace un balance de explotacion de la instalacion de tratamiento de efluentes del centro de Saclay desde hace cuatro anos, dando las cifras correspondientes al origen de los residuos, a su volumen y a su tratamiento. (author) [Russian] V jetom dokumente podvoditsja itog chetyrehletnej jekspluatacii ustanovki po obrabotke zhidkih othotov v Centre jadernyh issledovanij v Sakle. V doklade privodjatsja dannye o proishozhdenii othodov, jh ob'eme i obrabotke. (author)

  4. Do Computerised Training Programmes Designed to Improve Working Memory Work?

    Science.gov (United States)

    Apter, Brian J. B.

    2012-01-01

    A critical review of working memory training research during the last 10 years is provided. Particular attention is given to research that has attempted to investigate the efficacy of commercially marketed computerised training programmes such as "Cogmed" and "Jungle Memory". Claimed benefits are questioned on the basis that research methodologies…

  5. Computerised Accounting Software; A Curriculum That Enhances an Accounting Programme

    Science.gov (United States)

    Machera, Robert P.; Machera, Precious C.

    2017-01-01

    There has been an outcry in commerce and industry about students who fail to perform in the accounting department due to lack of "practical accounting skills". It is from this background that the researchers were motivated to investigate the impact of a Computerised Accounting Software Curriculum that enhances an Accounting Programme. At…

  6. Debating the utility of computerised neurocognitive testing in the ...

    African Journals Online (AJOL)

    The purpose of this article was to contribute to an argument regarding the utility of computerised baseline and follow-up neurocognitive testing within the sports concussion arena. Heated debate around this issue via a number of contributions has appeared recently in the journal Current Sports Medicine Reports, with its use ...

  7. Computerised decision support systems for healthcare professionals: an interpretative review.

    Science.gov (United States)

    Cresswell, Kathrin; Majeed, Azeem; Bates, David W; Sheikh, Aziz

    2012-01-01

    Computerised decision support systems are designed to support clinicians in making decisions and thereby enhance the quality and safety of care. We aimed to undertake an interpretative review of the empirical evidence on computerised decision support systems, their contexts of use, and summarise evidence on the effectiveness of these tools and insights into how these can be successfully implemented and adopted. We systematically searched the empirical literature to identify systematic literature reviews on computerised decision support applications and their impact on the quality and safety of healthcare delivery over a 13-year period (1997-2010). The databases searched included: MEDLINE, EMBASE, The Cochrane Database of Systematic Reviews, Database of Abstracts of Reviews of Effects, The Cochrane Central Register of Controlled Trials, The Cochrane Methodology Register, The Health Technology Assessment Database, and The National Health Service (NHS) Economic Evaluation Database. To be eligible for inclusion, systematic reviews needed to address computerised decision support systems, and at least one of the following: impact on safety; quality; or organisational, implementation or adoption considerations. Our searches yielded 121 systematic reviews relating to eHealth, of which we identified 41 as investigating computerised decision support systems. These indicated that, whilst there was a lack of investigating potential risks, such tools can result in improvements in practitioner performance in the promotion of preventive care and guideline adherence, particularly if specific information is available in real time and systems are effectively integrated into clinical workflows. However, the evidence regarding impact on patient outcomes was less clear-cut with reviews finding either no, inconsistent or modest benefits. Whilst the potential of clinical decision support systems in improving, in particular, practitioner performance is considerable, such technology may

  8. USERDA effluent data collection and reporting program

    International Nuclear Information System (INIS)

    Elle, D.R.; Schoen, A.A.

    1978-01-01

    Effluent and environmental monitoring has been conducted at United States Energy Research and Development Administration (formerly United States Atomic Energy Commission) facilities and sites virtually since the inception of atomic energy research and development. In 1971, computer systems were developed that permitted storage of information and data characterizing each effluent and onsite discharge point and relevant information on sources, effluent treatment and control systems, and discharge data, and serve as ERDA's computer-based management information systems for compiling waste discharge control and monitoring data on radioactivity released as airborne or liquid effluents or liquid discharges to onsite retention basins at ERDA facilities. The information systems and associated data outputs have proved to be an effective internal management tool for identifying effluent control problem areas and for surveying an agencywide Radioactive Effluent Reduction Program. The trend data facilitate the detection of gradual changes in the effectiveness of waste treatment systems, and errors or oversights in monitoring and data handling. Other computer outputs are useful for identifying effluent release points that have significantly higher or lower concentrations or quantities in the discharge stream than were measured the previous year. The year-to-year trend reports and the extensive computer edit and error checks have improved the reliability of the reported effluent data. Adoption of a uniform, centralized reporting system has improved the understanding and credibility of effluent data, and has allowed management to evaluate the effectiveness of effluent control practices at ERDA facilities. (author)

  9. Effluent Guidelines

    Science.gov (United States)

    Effluent guidelines are national standards for wastewater discharges to surface waters and municipal sewage treatment plants. We issue the regulations for industrial categories based on the performance of treatment and control technologies.

  10. Development of improved radioactive effluent treatment to remove Zn-65, Mo-99 and I-125 by the coagulation-flocculation process

    Energy Technology Data Exchange (ETDEWEB)

    Sakuma, S H [Malaysian Inst. for Nuclear Technology Research, Bangi, Selangor (Malaysia)

    1997-02-01

    Coagulation-flocculation treatment using aluminum sulphate, sodium carbonate, ferric chloride and coagulant aid was able to remove {sup 65}Zn, {sup 99}Mo and {sup 125}I from an aqueous effluent. Chemicals` dosages into the samples were varied which contributed different decontamination factors. For {sup 65}Zn removal, optimum pH value was 8 that provided the decontamination factor of 35. For {sup 125}I, optimum pH value was 7 with the decontamination factor of 4.8. Treatment of the effluent containing {sup 99}Mo at a laboratory scale was proved to be valid for the extrapolation to a plant scale. The pH range for optimum treatment was between 4.0 to 4.5. (author). 6 refs, 6 figs.

  11. Development of improved radioactive effluent treatment to remove Zn-65, Mo-99 and I-125 by the coagulation-flocculation process

    International Nuclear Information System (INIS)

    Sakuma, S.H.

    1997-01-01

    Coagulation-flocculation treatment using aluminum sulphate, sodium carbonate, ferric chloride and coagulant aid was able to remove 65 Zn, 99 Mo and 125 I from an aqueous effluent. Chemicals' dosages into the samples were varied which contributed different decontamination factors. For 65 Zn removal, optimum pH value was 8 that provided the decontamination factor of 35. For 125 I, optimum pH value was 7 with the decontamination factor of 4.8. Treatment of the effluent containing 99 Mo at a laboratory scale was proved to be valid for the extrapolation to a plant scale. The pH range for optimum treatment was between 4.0 to 4.5. (author). 6 refs, 6 figs

  12. Radiation protection at the RA reactor in 1984, Part III Removal of the liquid radioactive effluents for the needs of the RA reactor

    International Nuclear Information System (INIS)

    Mandic, M.; Plecas, I.; Vukovic, Z.; Knezevic, Lj.; Jankovic, O.; Kostadinovic, A.; Mihailovic, B.

    1984-01-01

    Contaminated water originates from: hot cells, heavy water distillation device, storage pools for cooling and cutting of fuel elements, water biological shield of the reactor. During 1984, 400 liters of water contaminated by 60 Co was treated. Most recent measurements showed that the VR-1 pool contains 280 m 3 of effluents having specific activity of 3.3 10 4 Bq/ml, and VR-2 contains 30 m 3 with specific activity of 4 10 3 Bq/ml

  13. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: conversion of yellow cake to uranium hexafluoride. Part I. The fluorination-fractionation process

    Energy Technology Data Exchange (ETDEWEB)

    Sears, M.B.; Blanco, R.E.; Finney, B.C.; Hill, G.S.; Moore, R.E.; Witherspoon, J.P.

    1977-07-01

    A cost/benefit study was made to determine the cost and effectiveness of radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials and chemicals from a model uranium hexafluoride (UF/sub 6/) production plant using the fluorination-fractionation (dry hydrofluor) process, and to evaluate the radiological impact (dose commitment) of the released materials on the environment. This study is designed to assist in defining the term as low as is reasonably achievable (ALARA) in relation to limiting the release of radioactive materials from nuclear facilities. The model plant processes 10,000 metric tons of uranium per year. Base-case waste treatment is the minimum necessary to operate the process. Effluents meet the radiological requirements listed in the Code of Federal Regulations, Title 10, Part 20 (10 CFR 20), Appendix B, Table II, but may not be acceptable chemically at all sites. Additional radwaste treatment techniques are applied to the base-case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The costs for the added waste treatment operations and the corresponding dose commitment are calculated for each case. In the final analysis, radiological dose is plotted vs the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. Much of the technology used in the advanced cases will require development and demonstration or else is proprietary and unavailable for immediate use. The methodology and assumptions for the radiological doses are found in ORNL-4992.

  14. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: conversion of yellow cake to uranium hexafluoride. Part I. The fluorination-fractionation process

    International Nuclear Information System (INIS)

    Sears, M.B.; Blanco, R.E.; Finney, B.C.; Hill, G.S.; Moore, R.E.; Witherspoon, J.P.

    1977-07-01

    A cost/benefit study was made to determine the cost and effectiveness of radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials and chemicals from a model uranium hexafluoride (UF 6 ) production plant using the fluorination-fractionation (dry hydrofluor) process, and to evaluate the radiological impact (dose commitment) of the released materials on the environment. This study is designed to assist in defining the term as low as is reasonably achievable (ALARA) in relation to limiting the release of radioactive materials from nuclear facilities. The model plant processes 10,000 metric tons of uranium per year. Base-case waste treatment is the minimum necessary to operate the process. Effluents meet the radiological requirements listed in the Code of Federal Regulations, Title 10, Part 20 (10 CFR 20), Appendix B, Table II, but may not be acceptable chemically at all sites. Additional radwaste treatment techniques are applied to the base-case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The costs for the added waste treatment operations and the corresponding dose commitment are calculated for each case. In the final analysis, radiological dose is plotted vs the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. Much of the technology used in the advanced cases will require development and demonstration or else is proprietary and unavailable for immediate use. The methodology and assumptions for the radiological doses are found in ORNL-4992

  15. Flow proportional sampling of low level liquid effluent

    International Nuclear Information System (INIS)

    Colley, D.; Jenkins, R.

    1989-01-01

    A flow proportional sampler for use on low level radioactive liquid effluent has been developed for installation on all CEGB nuclear power stations. The sampler, operates by drawing effluent continuously from the main effluent pipeline, through a sampler loop and returning it to the pipeline. The effluent in this loop is sampled by taking small, frequent aliquots using a linear acting shuttle valve. The frequency of operation of this valve is controlled by a flowmeter installed in the effluent line; sampling rate being directly proportional to effluent flowrate. (author)

  16. Computerised image analysis of biocrystallograms originating from agricultural products

    DEFF Research Database (Denmark)

    Andersen, Jens-Otto; Henriksen, Christian B.; Laursen, J.

    1999-01-01

    Procedures are presented for computerised image analysis of iocrystallogram images, originating from biocrystallization investigations of agricultural products. The biocrystallization method is based on the crystallographic phenomenon that when adding biological substances, such as plant extracts...... on up to eight parameters indicated strong relationships, with R2 up to 0.98. It is concluded that the procedures were able to discriminate the seven groups of images, and are applicable for biocrystallization investigations of agricultural products. Perspectives for the application of image analysis...

  17. Effluent standards

    Energy Technology Data Exchange (ETDEWEB)

    Geisler, G C [Pennsylvania State University (United States)

    1974-07-01

    At the conference there was a considerable interest in research reactor standards and effluent standards in particular. On the program, this is demonstrated by the panel discussion on effluents, the paper on argon 41 measured by Sims, and the summary paper by Ringle, et al. on the activities of ANS research reactor standards committee (ANS-15). As a result, a meeting was organized to discuss the proposed ANS standard on research reactor effluents (15.9). This was held on Tuesday evening, was attended by members of the ANS-15 committee who were present at the conference, participants in the panel discussion on the subject, and others interested. Out of this meeting came a number of excellent suggestions for changes which will increase the utility of the standard, and a strong recommendation that the effluent standard (15.9) be combined with the effluent monitoring standard. It is expected that these suggestions and recommendations will be incorporated and a revised draft issued for comment early this summer. (author)

  18. Effluent treatment plant and decontamination centre, Trombay

    International Nuclear Information System (INIS)

    Kaushik, C.P.; Agarwal, K.

    2017-01-01

    The Bhabha Atomic Research Centre, Trombay, has a number of plants and laboratories, which generate Radioactive Liquid Waste and Protective Wears. Two facilities have been established in late 1960s to cater to this requirement. The Centre, on the average generates about 50,000 m"3 of active liquid effluents of varying specific activities. The Effluent Treatment Plant was setup to receive and process radioactive liquids generated by various facilities of BARC in Trombay. It also serves a single-point discharge facility to enable monitoring of radioactive effluents discharged from the Trombay site. About 120-150 Te of protective wears and inactive apparel are generated annually from various radioactive facilities and laboratories of BARC. In addition, contaminated fuel assembly components are generated by DHRUVA and formerly by CIRUS. These components require decontamination before its recycle to the fuel assembly process. The Decontamination Centre, setup in late 1960s, is mandated to carry out the above mentioned decontamination activities

  19. Computerised decision support systems for healthcare professionals: an interpretative review

    Directory of Open Access Journals (Sweden)

    Kathrin Cresswell

    2013-03-01

    Full Text Available Purpose Computerised decision support systems are designed to support clinicians in making decisions and thereby enhance the quality and safety of care. We aimed to undertake an interpretative review of the empirical evidence on computerised decision support systems, their contexts of use, and summarise evidence on the effectiveness of these tools and insights into how these can be successfully implemented and adopted.Methods We systematically searched the empirical literature to identify systematic literature reviews on computerised decision support applications and their impact on the quality and safety of healthcare delivery over a 13-year period (1997–2010. The databases searched included: MEDLINE, EMBASE, The Cochrane Database of Systematic Reviews, Database of Abstracts of Reviews of Effects, The Cochrane Central Register of Controlled Trials, The Cochrane Methodology Register, The Health Technology Assessment Database, and The National Health Service (NHS Economic Evaluation Database. To be eligible for inclusion, systematic reviews needed to address computerised decision support systems, and at least one of the following: impact on safety; quality; or organisational, implementation or adoption considerations.Results Our searches yielded 121 systematic reviews relating to eHealth, of which we identified 41 as investigating computerised decision support systems. These indicated that, whilst there was a lack of investigating potential risks, such tools can result in improvements in practitioner performance in the promotion of preventive care and guideline adherence, particularly if specific information is available in real time and systems are effectively integrated into clinical workflows. However, the evidence regarding impact on patient outcomes was less clear-cut with reviews finding either no, inconsistent or modest benefits.Conclusions Whilst the potential of clinical decision support systems in improving, in particular

  20. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: reprocessing light-water reactor fuel

    International Nuclear Information System (INIS)

    Finney, B.C.; Blanco, R.E.; Dahlman, R.C.; Hill, G.S.; Kitts, F.G.; Moore, R.E.; Witherspoon, J.P.

    1976-10-01

    A cost/benefit study was made to determine the cost and effectiveness of radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from a model nuclear fuel reprocessing plant which processes light-water reactor (LWR) fuels, and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist in defining the term as low as reasonably achievable in relation to limiting the release of radioactive materials from nuclear facilities. The base case model plant is representative of current plant technology and has an annual capacity of 1500 metric tons of LWR fuel. Additional radwaste treatment systems are added to the base case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The cost for the added waste treatment operations and the corresponding dose commitments are calculated for each case. In the final analysis, radiological dose is plotted vs the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. Much of the technology used in the advanced cases is in an early stage of development and is not suitable for immediate use. The methodology used in estimating the costs, and the radiological doses, detailed calculations, and tabulations are presented in Appendix A and ORNL-4992. This report is a revision of the original study

  1. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: conversion of recycle uranium to UF6

    International Nuclear Information System (INIS)

    Roddy, J.W.; Blanco, R.E.; Finney, B.C.; Hill, G.S.; Moore, R.E.; Witherspoon, J.P.

    1977-04-01

    A cost/benefit study was made to determine the cost and effectiveness of various radioactive waste (radwaste) treatment systems for decreasing the amount of radioactive materials released from a model recycle uranium conversion and uranium hexafluoride (UF 6 ) production plant and to determine the radiological impact (dose commitment) of the released radioactive materials on the environment. This study is designed to assist the US NRC in defining the term ''as low as reasonably achievable'' as it applies to these nuclear facilities. The base case model plant is representative of a licensable UF 6 production plant and has an annual capacity of 1500 metric tons of uranium. Additional radwaste treatment systems are added to the base case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The cost for the added waste treatment operations and the corresponding dose commitments is calculated for each case. In the final analysis, radiological dose is plotted vs the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. The methodology used in estimating the costs is presented

  2. Radiation protection at the RA Reactor in 1985, Part -3, Removal and treatment of radioactive effluents for the needs of RA reactor

    International Nuclear Information System (INIS)

    Plecas, I.; Vukovic, Z.; Kostadinovic, A.

    1985-01-01

    Contaminated water originates from: hot cells, heavy water distillation device, storage pools for cooling and cutting of fuel elements, water biological shield of the reactor. During 1985 5 m of contaminated water was released from hot cells in the VR-pool containing highly radioactive waste water with 60 Co and trace amount of fission products [sr

  3. Quantitative analysis of strontium 90 in the radioactive wastes by means of thenoyltrifluoroacetone; Dosage du strontium 90 dans les effluents radioactifs par le thenoyltrifluoroacetone

    Energy Technology Data Exchange (ETDEWEB)

    Testemale, G; Leredde, J L [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1970-07-01

    A simple method of analysing the quantity of {sup 90}Sr has been perfected. It consists in a double extraction of it by means of thenoyltrifluoroacetone and tributylphosphate in tetrachloride of carbon followed by eliminating yttrium 90 by means of thenoyltrifluoroacetone in the benzene. Numberings on aliquot parts of wastes make the determination of that element possible. The yield is about 97 per cent. (authors) [French] Une technique simple du dosage du {sup 90}Sr a ete mise au point. Elle consiste en une double extraction par le thenoyltrifluoroacetone et le tributylphosphate dans le tetrachlorure de carbone, suivie de l'elimination de l'yttrium 90 par le thenoyltrifluoroacetone dans le benzene, Des comptages sur des parties aliquotes d'effluents permettent la dermination de cet element. Rendement environ 97 pour cent. (auteurs)

  4. Radiation protection at the RA Reactor in 1993, Part II, Decontamination and actions, collection of liquid effluents and solid radioactive waste

    International Nuclear Information System (INIS)

    Mandic, M.; Vukovic, Z.; Lazic, S.; Plecas, I.; Voko, A.

    1993-01-01

    Certain amount of solid waste results from RA reactor operation, the mean quantity of which depends on the duration of reactor operation and related activities. During repair, when reactor is not operated as well under accidental conditions, the quantity of waste is higher, dependent on the type of repair and comprehensiveness of decontamination of the working surface, contaminated tools and components. The waste is sorted and packed on the spot where they appeared according to the existing regulations and principles of radiation protection with aim to minimize unnecessary exposure of the radiation protection personnel who deals with control, transport, radioactive waste treatment and decontamination. During exceptional operations (decontamination, repair, bigger volume of contaminated material, etc.) professional staff of the Radiation protection department gives recommendations and helps in planning the actions related to repair, sorting and packaging of radioactive waste in special containers, identification of the contaminants, etc. [sr

  5. Radiation protection at the RA Reactor in 1998, Part 2, Annex 2, Decontamination and actions, collection of liquid effluents and solid radioactive waste

    International Nuclear Information System (INIS)

    Mandic, M.; Vukovic, Z.; Bacic, S.; Plecas, I.

    1998-01-01

    Certain amount of solid waste results from RA reactor operation, the mean quantity of which depends on the duration of reactor operation and related activities. During repair, when reactor is not operated as well under accidental conditions, the quantity of waste is higher, dependent on the type of repair and comprehensiveness of decontamination of the working surface, contaminated tools and components. The waste is sorted and packed on the spot where they appeared according to the existing regulations and principles of radiation protection with aim to minimize unnecessary exposure of the radiation protection personnel who deals with control, transport, radioactive waste treatment and decontamination. During exceptional operations (decontamination, repair, bigger volume of contaminated material, etc.) professional staff of the Radiation protection department gives recommendations and helps in planning the actions related to repair, sorting and packaging of radioactive waste in special containers, identification of the contaminants, etc. [sr

  6. Radiation protection at the RA Reactor in 1995, Part -2, Annex 2, Decontamination and actions, collection of liquid effluents and solid radioactive waste

    International Nuclear Information System (INIS)

    Mandic, M.; Vukovic, Z.; Lazic, S.; Plecas, I.; Voko, A.

    1995-01-01

    Certain amount of solid waste results from RA reactor operation, the mean quantity of which depends on the duration of reactor operation and related activities. During repair, when reactor is not operated as well under accidental conditions, the quantity of waste is higher, dependent on the type of repair and comprehensiveness of decontamination of the working surface, contaminated tools and components. The waste is sorted and packed on the spot where they appeared according to the existing regulations and principles of radiation protection with aim to minimize unnecessary exposure of the radiation protection personnel who deals with control, transport, radioactive waste treatment and decontamination. During exceptional operations (decontamination, repair, bigger volume of contaminated material, etc.) professional staff of the Radiation protection department gives recommendations and helps in planning the actions related to repair, sorting and packaging of radioactive waste in special containers, identification of the contaminants, etc. [sr

  7. Effluent Treatment Facility tritium emissions monitoring

    International Nuclear Information System (INIS)

    Dunn, D.L.

    1991-01-01

    An Environmental Protection Agency (EPA) approved sampling and analysis protocol was developed and executed to verify atmospheric emissions compliance for the new Savannah River Site (SRS) F/H area Effluent Treatment Facility. Sampling equipment was fabricated, installed, and tested at stack monitoring points for filtrable particulate radionuclides, radioactive iodine, and tritium. The only detectable anthropogenic radionuclides released from Effluent Treatment Facility stacks during monitoring were iodine-129 and tritium oxide. This paper only examines the collection and analysis of tritium oxide

  8. Facility effluent monitoring plan for the fast flux test facility

    International Nuclear Information System (INIS)

    Nickels, J.M.; Dahl, N.R.

    1992-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in US Department of Energy Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A Facility Effluent Monitoring Plan determination was performed during calendar year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

  9. Continuous monitoring of gaseous effluents

    International Nuclear Information System (INIS)

    Velasco, A.; Giraut, H.; Prado, M.; Bonino, A.D.

    1990-01-01

    The system allows to continuously determine the radioactive materials discharge (iodine, noble gases and aerosols) to the environment. It consists in compelling, by a pump, a known and fixed fraction of the total flow and preserving the aerosols by a filter. The gas -now free from aerosols- traverses an activated carbon filter which keeps the iodine; after being free from aerosols and iodine, the effluent traverses a measurement chambers for noble gases which has a scintillator. (Author) [es

  10. Computerised CBT for depressed adolescents: Randomised controlled trial.

    Science.gov (United States)

    Smith, Patrick; Scott, Rebecca; Eshkevari, Ertimiss; Jatta, Fatoumata; Leigh, Eleanor; Harris, Victoria; Robinson, Alex; Abeles, Paul; Proudfoot, Judy; Verduyn, Chrissie; Yule, William

    2015-10-01

    Depression in adolescents is a common and impairing problem. Effective psychological therapies for depression are not accessed by most adolescents. Computerised therapy offers huge potential for improving access to treatment. To test the efficacy of Stressbusters, a Computerised-CBT (C-CBT) programme for depression in young people. Multi-site, schools-based, RCT of C-CBT compared to Waiting List, for young people (N = 112; aged 12-16) with significant symptoms of depression, using multiple-informants (adolescents, parents, teachers), with follow-up at 3 and 6 months. Relative to being on a Waiting List, C-CBT was associated with statistically significant and clinically meaningful improvements in symptoms of depression and anxiety according to adolescent self-report; and with a trend towards improvements in depression and anxiety according to parent-report. Improvements were maintained at follow-up. Treatment gains were similar for boys and girls across the participating age range. Treatment effect was partially mediated by changes in ruminative thinking. Teachers rated adolescents as having few emotional or behavioural problems, both before and after intervention. C-CBT had no detectable effect on academic attainment. In the month after intervention, young people who received C-CBT had significantly fewer absences from school than those on the Waiting List. C-CBT shows considerable promise for the treatment of mild-moderate depression in adolescents. Copyright © 2015 Elsevier Ltd. All rights reserved.

  11. Computerised analysis of facial emotion expression in eating disorders

    Science.gov (United States)

    2017-01-01

    Background Problems with social-emotional processing are known to be an important contributor to the development and maintenance of eating disorders (EDs). Diminished facial communication of emotion has been frequently reported in individuals with anorexia nervosa (AN). Less is known about facial expressivity in bulimia nervosa (BN) and in people who have recovered from AN (RecAN). This study aimed to pilot the use of computerised facial expression analysis software to investigate emotion expression across the ED spectrum and recovery in a large sample of participants. Method 297 participants with AN, BN, RecAN, and healthy controls were recruited. Participants watched film clips designed to elicit happy or sad emotions, and facial expressions were then analysed using FaceReader. Results The finding mirrored those from previous work showing that healthy control and RecAN participants expressed significantly more positive emotions during the positive clip compared to the AN group. There were no differences in emotion expression during the sad film clip. Discussion These findings support the use of computerised methods to analyse emotion expression in EDs. The findings also demonstrate that reduced positive emotion expression is likely to be associated with the acute stage of AN illness, with individuals with BN showing an intermediate profile. PMID:28575109

  12. Computerised analysis of facial emotion expression in eating disorders.

    Science.gov (United States)

    Leppanen, Jenni; Dapelo, Marcela Marin; Davies, Helen; Lang, Katie; Treasure, Janet; Tchanturia, Kate

    2017-01-01

    Problems with social-emotional processing are known to be an important contributor to the development and maintenance of eating disorders (EDs). Diminished facial communication of emotion has been frequently reported in individuals with anorexia nervosa (AN). Less is known about facial expressivity in bulimia nervosa (BN) and in people who have recovered from AN (RecAN). This study aimed to pilot the use of computerised facial expression analysis software to investigate emotion expression across the ED spectrum and recovery in a large sample of participants. 297 participants with AN, BN, RecAN, and healthy controls were recruited. Participants watched film clips designed to elicit happy or sad emotions, and facial expressions were then analysed using FaceReader. The finding mirrored those from previous work showing that healthy control and RecAN participants expressed significantly more positive emotions during the positive clip compared to the AN group. There were no differences in emotion expression during the sad film clip. These findings support the use of computerised methods to analyse emotion expression in EDs. The findings also demonstrate that reduced positive emotion expression is likely to be associated with the acute stage of AN illness, with individuals with BN showing an intermediate profile.

  13. Methodology for the application of the I.C.R.P. optimization principle. The case of radioactive effluent control systems in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Lochard, Jacques; Maccia, Carlo; Pages, Pierre.

    1980-10-01

    This report aims at giving a detailed methodology to help improving decision making process in the radiation protection field, according to the optimization principle of the ICRP. A model was elaborated in such a general way as to be applicable for public as well as occupational radiation protection. The main steps of the model are: 1) the assessment of collective doses and residual health effects associated with a given radiation protection level, 2) the determination of protection costs, 3) the decision analysis: cost effectiveness and cost-benefit analysis. The model is implemented by means of a conversational computer program. This methodology is exemplified with the problem of the choice of waste treatment systems for the PWRs in France. The public impact of radioactive releases is evaluated for the population within 100 km around the site. The main results are presented for two existing sites of the French nuclear program [fr

  14. Legal provisions governing gaseous effluents radiological monitoring

    International Nuclear Information System (INIS)

    Winkelmann, I.

    1985-01-01

    This contribution explains the main provisions governing radiological monitoring of gaseous effluents from LWR type nuclear power plants. KTA rule 1503.1 defines the measuring methods and tasks to be fulfilled by reactor operators in order to safeguard due monitoring and accounting of radioactive substances in the plants' gaseous effluents. The routine measurements are checked by a supervisory programme by an independent expert. The routine controls include analysis of filter samples, comparative measurement of radioactive noble gases, interlaboratory comparisons, and comparative evaluation of measured values. (DG) [de

  15. Effluent Information System (EIS) / Onsite Discharge Information System (ODIS): 1986 executive summary

    International Nuclear Information System (INIS)

    Watanabe, T.

    1987-09-01

    Department of Energy (DOE) data base systems aid DOE-Headquarters and Field Offices in managing the radioactive air and liquid effluents from DOE facilities. Data on effluents released offsite are entered into effluent information system (EIS) and data on effluents discharged onsite and retained onsite are entered into Onsite Discharge Information System (ODIS). This document is a summary of information obtained from the CY 1986 effluent data received from all DOE and DOE contractor facilities and entered in the data bases. Data from previous years are also included. The summary consists of information for effluents released offsite, and information for effluents retained onsite

  16. Facility effluent monitoring plan for the plutonium uranium extraction facility

    Energy Technology Data Exchange (ETDEWEB)

    Wiegand, D.L.

    1994-09-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

  17. Facility Effluent Monitoring Plan for the uranium trioxide facility

    International Nuclear Information System (INIS)

    Lohrasbi, J.; Johnson, D.L.; De Lorenzo, D.S.

    1993-12-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

  18. Facility effluent monitoring plan for the plutonium uranium extraction facility

    International Nuclear Information System (INIS)

    Wiegand, D.L.

    1994-09-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

  19. Facility effluent monitoring plan for the Plutonium Uranium Extraction Facility

    International Nuclear Information System (INIS)

    Greager, E.M.

    1997-01-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan will ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, at a minimum, every 3 years

  20. Facility effluent monitoring plan for the B plant

    International Nuclear Information System (INIS)

    Lesser, J.E.

    1994-09-01

    A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plant assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated every three years

  1. Disposal of the radioactive effluents at the 'Commissariat a l'Energie Atomique'. Treatment leading to evacuation into a river; Probleme du rejet des residus radioactifs liquides au CEA. Traitements aboutissant a des rejets en riviere

    Energy Technology Data Exchange (ETDEWEB)

    Duhamel,; Menoux,; Candillon, [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The problems dealing with the treatment of the radioactive effluents at the 'Commissariat a l'Energie Atomique' have been studied in order to allow evacuation into a river - after treatment - with respect for the standards regarding radiation protection. 2) At Saclay where there is no possibility of evacuating the effluents, the liquids are directed towards Fontenay-aux-Roses by means of tank wagons. They are removed temporarily into the sewers and will be evacuated later on into the Seine. 3) ln Le Bouchet, the effluents coming from the Factory where urano-thorianite ore is treated will undergo a two stages treatment. The elimination of radium in the first phase facilitates decontamination in the second phase. 4) In Marcoule: a study of synthetic effluents of the Marcoule type is being carried on in order to perfect a selective elimination method of Sr{sup 90} and Cs{sup 137} by coprecipitation. 5) In the general case of the final evacuation into a river, the following problems have been studied: - pre-dilution of treated waters between the storing tanks and the river; - admission in the river; dilution in the river (preliminary study by means of a tracer); - evolution of the activity in the water of the river (adsorption by inert or living elements), contamination of the banks; - locating of the site; - isotopic dilution. 6) Circumstantial study of that last problem. 7) The quantity of a given product in water conditions the isotopic dilution of its radioactive isotopes. When the analysis shows the lack of an element, stable isotopes should be added in order to compensate it. 8) That method led to difficult analysis (specially as far as Sr{sup 90} is concerned), for the percentage of stable isotopes necessary to an important isotopic dilution is very low. 9) The standard regarding the quantity of Sr{sup 90} in drinking water is 8.10{sup -8} c/m{sup 3} or 4.10{sup -10} g/m{sup 3}. So a percentage of 40 {mu}g/litre of Sr is enough which is difficult to find out in

  2. Management on radioactive wastes

    International Nuclear Information System (INIS)

    Balu, K.; Bhatia, S.C.

    1979-01-01

    The basic philosophy governing the radioactive waste management activities in India is to concentrate and contain as much activity as possible and to discharge to the environment only such of these streams that have radioactive content much below the nationally and internationally accepted standards. The concept of ''Zero Release'' is also kept in view. At Tarapur, the effluents are discharged into coastal waters after the radioactivity of the effluents is brought down by a factor 100. The effluents fΩm Rajasthan reactors are discharged into a lake keeping their radioactivity well within permissible limits and a solar evaporation plant is being set up. The plant, when it becomes operational, will be a step towards the concept of ''Zero Release''. At Kalpakkam, the treated wastes are proposed to be diluted by circulating sea water and discharged away from the shore through a long pipe. At Narora, ion exchange followed by chemical precipitation is to be employed to treat effluents and solar evaporation process for total containment. Solid wastes are stored/dispsed in the concrete trenches, underground with the water proofing of external surfaces and the top of the trench is covered with concrete. Highly active wastes are stored/disposed in tile holes which are vaults made of steel-lined, reinforced concrete pipes. Gas cleaning, dilution and dispersion techniques are adopted to treat gaseous radioactive wastes. (M.G.B.)

  3. Experiment of decontamination of radioactive liquid by a biological method

    International Nuclear Information System (INIS)

    Wormser, G.

    1962-01-01

    The author reports experiments of treatment of radioactive liquid effluents by percolation on a bacterial bed like the one used for the treatment of sewer wastewaters. He also reports results obtained in other countries in terms of reduction of effluent radioactivity for various radioactive ions. The installation is described and results are presented in terms of variation of contamination of an effluent with respect to its recycling on a bacterial bed [fr

  4. Principles for the development and implementation of the moira computerised system

    Energy Technology Data Exchange (ETDEWEB)

    Monte, L [ENEA, Centro Ricerche Casaccia, Rome (Italy). Dip. Ambiente; Brittain, J E [Oslo Univ. (Norway). LFI Zoological Museum

    1999-12-31

    The present report is composed of a set of articles written by the patterns of the MOIRA project (a model based computerized system for management support to identify optimal remedial strategies for restoring radionuclide contaminated aquatic ecosystems and drainage areas). The project aims to describe and analyse computerised methodologies for the identification of the countermeasures in fresh water systems contaminated by radioactive substances. The structure of the MOIRA software and the criteria for the objective evaluation of the ecological impact of the countermeasures applied to lakes (defined by the `Lake Ecosystem Index`, which is used in the Multi attribute Decision Analysis process developed for MOIRA) are described in detail. A preliminary classification of the countermeasures in relation to their potential effectiveness and feasibility and a classification of the main European species of fishes of radioecological importance are presented. The described methodologies have been applied to the Norwegian lake Heimdalsvatn to demonstrate the feasibility of the MOIRA system. Two further articles in the report describe the principles for the development of a model for predicting the radionuclide migration from urban areas to fresh water systems and the migration of radionuclides in rivers. [Italiano] Lo scopo del presente rapporto, composto da articoli preparati dai ricercatori che partecipano al progetto MOIRA (A MODEL BASED COMPUTERISED SYSTEM FOR MANAGEMENT SUPPORT TO IDENTIFY OPTIMAL REMEDIAL STRATEGIES FOR RESTORING RADIONUCLIDE CONTAMINATED AQUATIC ECOSYSTEMS AND DRAINAGE AREAS), e` la descrizione e l`analisi delle metodologie computerizzate che consentono l`identificazione di contromisure atte a ridurre i livelli di contaminazione radioattiva di sistemi acquatici continentali. In particolare vengono descritte la struttura del software MOIRA e i criteri per una valutazione oggettiva dell`impatto ecologico delle contromisure applicate a sistem,i lacustri

  5. Principles for the development and implementation of the moira computerised system

    Energy Technology Data Exchange (ETDEWEB)

    Monte, L. [ENEA, Centro Ricerche Casaccia, Rome (Italy). Dip. Ambiente; Brittain, J.E. [Oslo Univ. (Norway). LFI Zoological Museum

    1998-12-31

    The present report is composed of a set of articles written by the patterns of the MOIRA project (a model based computerized system for management support to identify optimal remedial strategies for restoring radionuclide contaminated aquatic ecosystems and drainage areas). The project aims to describe and analyse computerised methodologies for the identification of the countermeasures in fresh water systems contaminated by radioactive substances. The structure of the MOIRA software and the criteria for the objective evaluation of the ecological impact of the countermeasures applied to lakes (defined by the `Lake Ecosystem Index`, which is used in the Multi attribute Decision Analysis process developed for MOIRA) are described in detail. A preliminary classification of the countermeasures in relation to their potential effectiveness and feasibility and a classification of the main European species of fishes of radioecological importance are presented. The described methodologies have been applied to the Norwegian lake Heimdalsvatn to demonstrate the feasibility of the MOIRA system. Two further articles in the report describe the principles for the development of a model for predicting the radionuclide migration from urban areas to fresh water systems and the migration of radionuclides in rivers. [Italiano] Lo scopo del presente rapporto, composto da articoli preparati dai ricercatori che partecipano al progetto MOIRA (A MODEL BASED COMPUTERISED SYSTEM FOR MANAGEMENT SUPPORT TO IDENTIFY OPTIMAL REMEDIAL STRATEGIES FOR RESTORING RADIONUCLIDE CONTAMINATED AQUATIC ECOSYSTEMS AND DRAINAGE AREAS), e` la descrizione e l`analisi delle metodologie computerizzate che consentono l`identificazione di contromisure atte a ridurre i livelli di contaminazione radioattiva di sistemi acquatici continentali. In particolare vengono descritte la struttura del software MOIRA e i criteri per una valutazione oggettiva dell`impatto ecologico delle contromisure applicate a sistem,i lacustri

  6. Computerised respiratory sounds can differentiate smokers and non-smokers.

    Science.gov (United States)

    Oliveira, Ana; Sen, Ipek; Kahya, Yasemin P; Afreixo, Vera; Marques, Alda

    2017-06-01

    Cigarette smoking is often associated with the development of several respiratory diseases however, if diagnosed early, the changes in the lung tissue caused by smoking may be reversible. Computerised respiratory sounds have shown to be sensitive to detect changes within the lung tissue before any other measure, however it is unknown if it is able to detect changes in the lungs of healthy smokers. This study investigated the differences between computerised respiratory sounds of healthy smokers and non-smokers. Healthy smokers and non-smokers were recruited from a university campus. Respiratory sounds were recorded simultaneously at 6 chest locations (right and left anterior, lateral and posterior) using air-coupled electret microphones. Airflow (1.0-1.5 l/s) was recorded with a pneumotachograph. Breathing phases were detected using airflow signals and respiratory sounds with validated algorithms. Forty-four participants were enrolled: 18 smokers (mean age 26.2, SD = 7 years; mean FEV 1 % predicted 104.7, SD = 9) and 26 non-smokers (mean age 25.9, SD = 3.7 years; mean FEV 1 % predicted 96.8, SD = 20.2). Smokers presented significantly higher frequency at maximum sound intensity during inspiration [(M = 117, SD = 16.2 Hz vs. M = 106.4, SD = 21.6 Hz; t(43) = -2.62, p = 0.0081, d z  = 0.55)], lower expiratory sound intensities (maximum intensity: [(M = 48.2, SD = 3.8 dB vs. M = 50.9, SD = 3.2 dB; t(43) = 2.68, p = 0.001, d z  = -0.78)]; mean intensity: [(M = 31.2, SD = 3.6 dB vs. M = 33.7,SD = 3 dB; t(43) = 2.42, p = 0.001, d z  = 0.75)] and higher number of inspiratory crackles (median [interquartile range] 2.2 [1.7-3.7] vs. 1.5 [1.2-2.2], p = 0.081, U = 110, r = -0.41) than non-smokers. Significant differences between computerised respiratory sounds of smokers and non-smokers have been found. Changes in respiratory sounds are often the earliest sign of disease. Thus, computerised respiratory sounds

  7. Construction Of A Computerised Information-Processing Test Battery

    Directory of Open Access Journals (Sweden)

    Johann M. Schepers

    2002-09-01

    Full Text Available The primary goal of the study was to construct a computerised information-processing test battery to measure choice reaction time for up to and including six bits of information, to measure discrimination reaction time with regard to colour patterns and form patterns, to measure rate of information processing with regard to perceptual stimuli and conceptual reasoning, and to develop a suitable scoring system for the respective tests. The battery of tests was applied to 58 pilots. Opsomming Die hoofdoel van die studie was om ‘n gerekenariseerde inligtingverwerkingstoets-battery te konstrueer om keusereaksietyd tot en met ses bis inligting te meet, om diskriminasie-reaksietyd ten opsigte van kleurpatrone en vormpatrone te meet, om tempo van inligtingverwerking ten opsigte van perseptuele stimuli en konseptuele redenering te meet en om ‘n gepaste nasienstelsel vir die onderskeie toetse te ontwikkel. Die battery toetse is op 58 vlieëniers toegepas

  8. IRSN's expertise about nuclear medicine hospital effluents

    International Nuclear Information System (INIS)

    2009-01-01

    This brief note aims at presenting the radioactivity follow up of hospital effluents performed by the French Institute of Radiation Protection and Nuclear Safety (IRSN). This follow up concerns the radioactive compounds and radiopharmaceuticals used in nuclear medicine, and principally technetium 99 and iodine 131. The IRSN has developed a network of remote measurement systems for the monitoring of sewers and waste water cleaning facilities. Data are compiled in a data base for analysis and subsequent expertise. (J.S.)

  9. Environmental radioactivity Ispra 1987

    International Nuclear Information System (INIS)

    Dominici, G.

    1988-01-01

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

  10. Environmental radioactivity Ispra 1989

    International Nuclear Information System (INIS)

    Dominici, G.

    1990-01-01

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

  11. Sellafield (release of radioactivity)

    Energy Technology Data Exchange (ETDEWEB)

    Cunningham, J; Goodlad, A; Morris, M

    1986-02-06

    A government statement is reported, about the release of plutonium nitrate at the Sellafield site of British Nuclear Fuels plc on 5 February 1986. Matters raised included: details of accident; personnel monitoring; whether radioactive material was released from the site; need for public acceptance of BNFL activities; whether plant should be closed; need to reduce level of radioactive effluent; number of incidents at the plant.

  12. Automated system for the safe management of the radioactive wastes and liquid effluents in a Radiopharmaceutical an labelled compounds production center; Sistema automatizado para la gestion segura de los desechos radiactivos y efluentes liquidos en un centro de produccion de radiofarmacos y compuestos marcados

    Energy Technology Data Exchange (ETDEWEB)

    Amador B, Z.H. [Centro de Isotopos, Ave. Monumental y Carretera La Rada, Km. 3, Guanabacoa, Apartado 3415, Ciudad de La Habana (Cuba); Guerra V, R. [Centro de Gestion de Informacion y Desarrollo de la Energia, Calle 20 No. 4111 e/47 y 18A, Playa, Ciudad La Habana (Cuba)]. e-mail: zabalbona@centis.edu.cu

    2006-07-01

    The Center of Isotopes of the Republic of Cuba is a radioactive installation of first category that executes the administration of their radioactive waste under authorization of the National Regulatory Authority. The principles of the design and operation of the 'SADR' system for the safe administration of the radioactive waste and liquid effluents are presented. The Visual Basic 6 platform for the programming of the SADR is used and through of their schematic representation, the control flows and of data of the 7 modules that conform it are shown. For each module the functions are described and it presents an image of the corresponding interface. With the SADR its can be carried out the one registration and the upgrade of the inventory of radioactive waste, the planning of those disqualification operations, the annual consolidation of the volumes of waste generated and disqualified, the evaluation of specific and general indicators and the one tendencies analysis. The handling of the system through the intranet allows the enter of data from the operations place with the radioactive wastes. The results of the operation of the SADR show the utility of this work to elevate the efficiency of the administration of the radioactive wastes. (Author)

  13. Effluent and water treatment at AERE Harwell

    International Nuclear Information System (INIS)

    Lewis, J.B.

    1977-01-01

    The treatment of liquid wastes at Harwell is based on two main principles: separation of surface water, domestic sewage, trade wastes and radioactive effluents at source, and a system of holding tanks which are sampled so that the appropriate treatment can be given to any batch. All discharges are subject to independent monitoring by the authorising departments and the Thames Water Inspectors. (author)

  14. Court of Justice of the European Communities ruling of September 22, 1988 - Rs 187/87: Radioactive effluents, EURATOM, Court of Justice of the EC - ruling concerning Art. 37 EURATOM Treaty (EAGV), nuclear power plants, member states - duties according to Art. 37 EAGV, radioactive effluents - approval of a plan of discharge according to Art. 37 EAGV, decision of the Commission concerning Art. 37 EAGV

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    Headnote: Article 37 of the treaty of March 25, 1957, establishing the European Atomic Energy Community (EURATOM) is to be interpreted as follows: General information regarding a plan for the discharge of radioactive material must be submitted to the Commission of the European Communities prior to the approval of such discharges by the authorities in charge in the respective member country. (orig./HP) [de

  15. Guide for effluent radiological measurements at DOE installations

    International Nuclear Information System (INIS)

    Corley, J.P.; Corbit, C.D.

    1983-07-01

    Effluent monitoring and reporting programs are maintained at all US Department of Energy (DOE) facilities that may: (1) discharge significant concentrations of radioactivity in relation to applicable standards, or (2) discharge quantities of radioactivity that have potential health and safety or other environmental significance. This Guide is intended to provide supplemental guidance to DOE Orders on methods, procedures, and performance criteria to bring more comparable rationale to DOE facility effluent measurement programs and promote compliance with applicable standards and provide the DOE Office of Operational Safety (OOS) and Operations Offices with an additional tool for evaluating effluent measurement programs at DOE facilities

  16. A method for conditioning radioactive-wastes

    International Nuclear Information System (INIS)

    Cuaz, Daniel; Thiery, Daniel.

    1974-01-01

    Description is given of a method for conditioning radioactive-wastes, according to the main patent. This method is characterized in that the radioactive wastes are constituted by radio-elements incorporated with filtration and/or floculation promoters. This can be applied to radioactive effluent processing [fr

  17. Facility effluent monitoring plan for the tank farm facility

    Energy Technology Data Exchange (ETDEWEB)

    Crummel, G.M.

    1998-05-18

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements.

  18. Effluent management and pollution control

    International Nuclear Information System (INIS)

    Ananda Narayanan, R.; Vedamoorthy, S.

    2006-01-01

    Generation of waste/effluent has a direct impact on environment, the higher the generation of waste higher the environmental impact. Though complete prevention of radioactive waste generation is a difficult task, keeping the waste generation to the minimum practicable is essential objective of Radioactive Waste Management. In doing so, it is essential to minimize waste generation at all the stages of a Nuclear Plant Cycle. Waste minimization refers to both a) Waste generation by operational and maintenance activities of plant and b) Secondary waste resulting from predisposal management of Radioactive Waste. The management of the effluent can be done in efficient manner by better designs, improved procedure, periodic reviews and above all inculcate the awareness amongst the waste generators since minimisation of waste, at source is the most efficient way to safe guard the environment. Commissioning and rich operating experience of waste management plant gather novel ideas which result in beneficial improvements in the system and operating procedure. Some of the steps initiated by designers and site agencies towards this are worth mentioning. (author)

  19. Facility Effluent Monitoring Plan for the Plutonium Finishing Plant

    International Nuclear Information System (INIS)

    FRAZIER, T.P.

    1999-01-01

    A facility effluent monitoring plan is required by the U. S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. To ensure the long-range integrity of the effluent monitoring systems, an update to this facility effluent monitoring plan is required whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document is reviewed annually even if there are no operational changes, and is updated, at a minimum, every 3 years

  20. Facility effluent monitoring plan for the tank farms facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bachand, D.D.; Crummel, G.M.

    1995-05-01

    A facility effluent monitoring plan is required by the US Department of Energy for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using specific guidelines. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years.

  1. Intraocular pressure asymmetry-Topcon Computerised Tonometer CT-20.

    Science.gov (United States)

    Ntim-Amponsah, C T

    1997-01-01

    The Topcon Computerised Tonometer CT-20, a non-contact tonometer (NCT), was used to measure intraocular pressure (IOP) in mmHg in 1,226 subjects above the age of 30 years with no ocular pathology. The mean IOP was 14.41 mmHg and the standard deviation 3.43. The mean IOP far was higher in female (14.60) than male (14.22). This gender difference in the mean IOP was significant; t stat = 2.69, P < 0.5. Right IOP exceeded left IOP and this was highly significant in both male (t stat 4.03) and female (t stat 5.64) p < 0.01. This IOP asymmetry approximates a normal distribution. The mean of the differences (right-left IOP) and standard deviation for all subjects were 0.57 and 2.26 respectively. The range for the differences was- 10 to 10 mmHg. Asymmetry was greater in females than males (t stat = 2.05, p < 0.05). Knowledge of these statistics will help in decisions concerning glaucoma screening with NCT.

  2. Facility effluent monitoring plan for 242-A Evaporator facility

    International Nuclear Information System (INIS)

    Crummel, G.M.; Gustavson, R.D.

    1993-03-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility effluent Monitoring Plans, WHC-EP-0438-1**. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

  3. Atomics International environmental monitoring and facility effluent annual report, 1976

    International Nuclear Information System (INIS)

    Moore, J.D.

    1977-01-01

    Environmental and facility effluent radioactivity monitoring at Atomics International (AI) is performend by the Radiation and Nuclear Safety Unit of the Health, Safety, and Radiation Services Department. Soil, vegetation, and surface water are routinely sampled to a distance of 10 miles from AI sites. Continuous ambient air sampling and thermoluminescent dosimetry are performed on site for monitoring airborne radioactivity and site ambient radiation levels. Radioactivity in effluents discharged to the atmosphere from AI facilities is continuously sampled and monitored to ensure that levels released to unrestricted areas are within appropriate limits, and to identify processes which may require additional engineering safeguards to minimize radioactivity levels in such effluents. In addition, selected nonradioactive constituents in surface water discharged to unrestricted areas are determined. This report summarizes and discusses monitoring results for 1976. The results of a special soil plutonium survey performed during the year are also summarized

  4. Low level radioactive waste management and discharge policies in Turkey

    International Nuclear Information System (INIS)

    Oezdemir, T.; Oezdemir, C.; Uslu, I.

    2005-01-01

    The legal infrastructure in Turkey for the management of low-level radioactive waste covers the liquid, solid and gaseous wastes. Management of these radioactive wastes is briefly described in this paper. Moreover, delay and decay tank systems that are used to collect and store the low level radioactive wastes as a part of low-level radioactive effluent discharge policy are introduced. (author)

  5. Radioactive wastes and effluents in hospitals

    International Nuclear Information System (INIS)

    Carlier, V.

    2000-01-01

    Out of sealed sources that have a particular management and regulation, the hospitals and laboratories use radioisotopes in liquid unsealed sources. The radioisotopes receive a particular surveillance, as well for their use as for the wastes they produce. At each step of their use, a follow up of these products and induced wastes is going to be made in a rigorous way, and their noxiousness taken into account. Whatever can be the product, the aim is the same: the matter is to preserve man and his environment from noxious effects of these products. (N.C.)

  6. Alternative process for treating radioactive effluents

    International Nuclear Information System (INIS)

    Puget, Flavia P.; Massarani, Giulio

    2002-01-01

    In this work an alternative process for treating a wastewater containing dissolved uranium is considered. In order to develop this work, a continuous separation unit, characterized by the solvent extraction, carried out inward the ejector is used. Alamina 336 (a mixture of tri-octyl and tri-decyl amines) is used as extractant in this process. The splitting of the amine-water emulsion formed is carried out in a gravitational separation tank. The result showed that it is possible to reach an efficiency of about 95% for the uranium extraction, for metal concentration in the feed of 10 ppm and a Q fa /Q fo ratio around 500. Furthermore, an efficiency of about 50% is reached for metal concentration in the feed of 1 ppm and for aQ fa /Q fo ratio around 1000, when the liquid flow rate is equal 1200 L/h. (author)

  7. Microscale diffusion analysis of gaseous radioactive effluents

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byung Woo; Chang, Kwang Phil; Jeong, Guy Soo; Lee, Kwang Hee; Choi, Yong Seok; An, Jin Young [Sungkyunkwan University, Seoul (Korea, Republic of)

    1997-07-01

    The state-of-the art review and relevant data bases have been made in this study. Microscale wind-field model has been made and applied to the site= of a target domestic plant - Younggwang units. Following researches have been made; - Review of modeling status in U.S.A., European countries, and Japan, those theoretical backgrounds, and experimental activities - Graphical display of topographical grid data in the surrounding with the Younggwang N.P.P. and basic investigation of the surrounding geography - Survey of site meteorological data of the Younggwang N.P.P.; precipitation distribution, yearly average wind direction and joint frequency, seasonal wind rose, distribution of seasonal sea and land breeze, joint frequency with respect to the atmospheric stability, mixing height - Presentation of a draft to update the existing Korea real-time dose assessment system, FADAS and to interface to the AWS(Automatic Weather System) of the Korea Meteorology Administration. - Establishment of nested-grid system with micro- and macro- scale cells around the Younggwang nuclear power plant -Consideration of solar radiation effect by using land-use map -Analysis of wind field in the region of 30 x 30 km n the Younggwang site (Author) 67 refs., 20 tabs., 28 figs.

  8. Facility effluent monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Gleckler, B.P.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report summarizes the facility effluent monitoring programs and provides an evaluation of effluent monitoring data. These evaluations are useful in assessing the effectiveness of effluent treatment and control systems, as well as management practices.

  9. The computerised procedure system COPMA and its user interface

    International Nuclear Information System (INIS)

    Krogsaeter, M.; Larsen, J.; Nilsen, S.; Oewre, F.

    1990-01-01

    At the OECD Halden Reactor Project, the COPMA system has been developed in order to investigate whether procedures can be executed more safety and efficiently if they are computerised, i.e. if the operator uses a CRT-based system instead of written manuals. Procedures are entered in a procedure data base using PED, a procedure editor. Each procedure is given a textual as well as a graphical representation. For the textual representation, the language PROLA is used, a language which has been designed for simple procedure specification. The COPMA online system lets the operator execute procedures that are stored in the procedure data base. The operator interface is a screen divided into non-overlapping windows each serving a different purpose. All commands to the system are given by moving a mouse device around and clicking buttons on top of the mouse. A procedure consists of steps, each step containing a number of instructions. The operator works on one activity at a time, an activity to be seen as a procedure instance. A graph shows the overall procedure (or activity) structure in a window and activity execution is traced in the graph. Another windows shows the instructions of the step currently being executed. The operator steps through the activity by selecting whether and how to execute the listed instructions. COPMA can maintain the status of several activities in parallel, so that the operator can easily switch between different activities. COPMA is linked to a PWR nuclear simulator over Ethernet using the TCP/IP protocol. This gives a number of advantages as compared to conventional written procedures, especially the fact that COPMA can help collect data from the procedure data base automatically

  10. A computerised automatic pellet inspection unit for FBTR fuel

    International Nuclear Information System (INIS)

    Ramakumar, M.S.; Mahule, K.N.; Ghosh, J.K.; Venkatesh, D.

    1984-01-01

    Physical inspection and certification of nuclear reactor fuel element components is an activity demanding utmost imagination and skill in devising accurate measuring systems. There is also need for remote handling, automation, rapid processing and inspection data print out when dealing with reactor fuel material. This report deals with an automatic computerised fuel pellet inspection system that has been developed in Radiometallurgy Division, B.A.R.C. to carry out dimensional and weight measurements on fuel pellets for the Fast Breeder Test Reactor (FBTR) at Kalpakkam near Madras. The system consists of several subsystems each developed especially for a specific purpose and as such items are not available off the shelf from manufacturers in India. If a general approach is adopted towards the report, there are many innovations and ideas that can be used in the automatic inspection of a variety of products in industry. As the system is fairly involved the report does not attempt to deal with detailed description of the equipment. The function of the system is to accept a certain quantity of fuel pellets in a bowl feeder, separate the pellets rejected owing to their exceeding dimensional and weight limits and form columns of accepted pellets. Dimensional and weight limits can be set as required and all inspection data are presented in a printed format. The system processes pellets at the rate of 15 per minute. The entire system can be run by operators with no special skills. The unit is currently in use for the inspection of mixed carbide fuel pellets for FBTR. (author)

  11. Computerised sepsis protocol management. Description of an early warning system.

    Science.gov (United States)

    de Dios, Begoña; Borges, Marcio; Smith, Timothy D; Del Castillo, Alberto; Socias, Antonia; Gutiérrez, Leticia; Nicolás, Jordi; Lladó, Bartolomé; Roche, Jose A; Díaz, Maria P; Lladó, Yolanda

    2018-02-01

    New strategies need to be developed for the early recognition and rapid response for the management of sepsis. To achieve this purpose, the Multidisciplinary Sepsis Team (MST) developed the Computerised Sepsis Protocol Management (PIMIS). The aim of this study was to evaluate the convenience of using PIMIS, as well as the activity of the MST. An analysis was performed on the data collected from solicited MST consultations (direct activation of PIMIS by attending physician or telephone request) and unsolicited ones (by referral from the microbiology laboratory or an automatic referral via the hospital vital signs recording software [SIDCV]), as well as the hospital department, source of infection, treatment recommendation, and acceptance of this. Of the 1,581 first consultations, 65.1% were solicited consultations (84.1% activation of PIMIS and 15.9% by telephone). The majority of unsolicited consultations were generated by the microbiology laboratory (95.2%), and 4.8% from the SIDCV. Referral from solicited consultations were generated sooner (5.63days vs 8.47days; P<.001) and came from clinical specialties rather than from the surgical ward (73.0% vs 39.1%; P<.001). A recommendation was made for antimicrobial prescription change in 32% of first consultations. The treating physician accepted 78.1% of recommendations. The high rate of solicited consultations and acceptance of recommended prescription changes suggest that a MST is seen as a helpful resource, and that PIMIS software is perceived to be useful and convenient to use, as it is the main source of referral. Copyright © 2016 Elsevier España, S.L.U. and Sociedad Española de Enfermedades Infecciosas y Microbiología Clínica. All rights reserved.

  12. Facility effluent monitoring plan for the 300 Area Fuels Fabrication Facility

    International Nuclear Information System (INIS)

    Nickels, J.M.; Brendel, D.F.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring system by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The Fuel Fabrication Facility in the Hanford 300 Area supported the production reactors from the 1940's until they were shut down in 1987. Prior to 1987 the Fuel Fabrication Facility released both airborne and liquid radioactive effluents. In January 1987 the emission of airborne radioactive effluents ceased with the shutdown of the fuels facility. The release of liquid radioactive effluents have continued although decreasing significantly from 1987 to 1990

  13. Cyborg practices: call-handlers and computerised decision support systems in urgent and emergency care.

    Science.gov (United States)

    Pope, Catherine; Halford, Susan; Turnbull, Joanne; Prichard, Jane

    2014-06-01

    This article draws on data collected during a 2-year project examining the deployment of a computerised decision support system. This computerised decision support system was designed to be used by non-clinical staff for dealing with calls to emergency (999) and urgent care (out-of-hours) services. One of the promises of computerised decisions support technologies is that they can 'hold' vast amounts of sophisticated clinical knowledge and combine it with decision algorithms to enable standardised decision-making by non-clinical (clerical) staff. This article draws on our ethnographic study of this computerised decision support system in use, and we use our analysis to question the 'automated' vision of decision-making in healthcare call-handling. We show that embodied and experiential (human) expertise remains central and highly salient in this work, and we propose that the deployment of the computerised decision support system creates something new, that this conjunction of computer and human creates a cyborg practice.

  14. Facility effluent monitoring plan for 242-A evaporator facility

    International Nuclear Information System (INIS)

    Crummel, G.M.; Gustavson, R.D.

    1995-02-01

    A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, as a minimum, every three years

  15. MOIRA: a computerised decision support system for the restoration of radionuclide contaminated freshwater ecosystems

    International Nuclear Information System (INIS)

    Gallego, Eduardo; Brittain, J.E.; Hakanson, Lars; Heling, Rudie; Hofman, Dmitry; Monte, Luigi

    2000-01-01

    The radiation dose resulting from contamination of freshwater ecosystems due to the release of radioactive substances into the environment may be reduced by applying suitable countermeasures. The options for intervention are wide-ranging and can be broadly grouped into three main categories: chemical, physical and social countermeasures. In some cases, a combination of actions -or even the no action- may be the optimal strategy. Despite their benefits, intervention strategies may have detrimental effects of economic, ecological and social nature. Thus, it is of paramount importance to assess, by objective criteria, the global cost-benefit balance of different options. The MOIRA project (A MOdel based computerised system for management support to Identity optimal remedial strategies for Restoring radionuclide contaminated Aquatic ecosystems, European Commission contract FI4P-CT96-0036) has developed a user-friendly, computerised tool that will allow decision makers to choose optimal intervention strategies for freshwater ecosystems with different contamination scenarios. To achieve that goal, the MOIRA software system -apart from a user-friendly interface- incorporates several innovative aspects: - eographical information system (GIS) and databases to get to get the values of the model parameters at different locations in Europe. - redictive ecosystem models for the behaviour of radionuclides (namely Cs-137 and Sr-90) in catchments, lakes and rivers, complemented with models of the effect of the countermeasures on the environmental contamination levels. These models are based on an extensive use of aggregate parameters' that summarise, in single quantities, the effects of a variety of environmental processes. Methods for critical model testing, sensitivity and uncertainty analyses have been applied to them getting a high reliability. - cosystem index (EI) to handle the influence chemical remedial measures may have on the structure, reproduction and biomass of key

  16. The effluent problem in a plutonium production centre; Probleme des effluents d'un centre de production de plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Galley, R; Cantel, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The first part of the report is devoted to generalities: the geographical situation of the Marcoule Centre, the sources of radio-active effluent, methods of treating this effluent. In the second part the authors gives a detailed description of the various installations in the Radio-active Effluent Treatment Station at the Marcoule Centre, and outline the conditions governing the rejection of treated effluent into the Rhone. A few lines are given to comparisons between the results obtained from the use of these installations up till may 1959 and the expected results published by the same authors at the Brussels Conference (1956). In conclusion the authors lay down some of the essential principles, applicable to the study of new installations. (author) [French] La premiere partie du rapport est consacree a quelques generalites: situation geographique du Centre de Marcoule, provenance des effluents radioactifs, methodes de traitement de ces effluents. Dans la seconde partie, les auteurs presentent une description detaillee des diverses installations de la Station de Traitement des Effluents radioactifs du Centre de Marcoule et precisent les conditions de rejet dans le Rhone des effluents radioactifs traites. Quelques lignes sont consacrees aux comparaisons entre les resultats de l'exploitation des installations jusqu'en mai 1959 et les previsions publiees par les memes auteurs a l'occasion de la Conference de Bruxelles (1956). En conclusion, les auteurs donnent quelques principes essentiels, applicables a l'etude de nouvelles installations. (auteur)

  17. Application of crown ethers to selective extraction and quantitative analysis of technetium 99, iodine 129 and cesium 135 in effluents

    International Nuclear Information System (INIS)

    Paviet, P.

    1992-01-01

    Properties of crown ethers are first recalled. Then extraction of technetium 99 is studied in actual radioactive effluents. Quantitative analysis is carried out by liquid scintillation and interference of tritium is corrected. Iodine 129 is extracted from radioactive effluents and determined by gamma spectrometry. Finally cesium 135 is extracted and determined by thermo ionization mass spectroscopy

  18. The effluent problem in a plutonium production centre

    International Nuclear Information System (INIS)

    Galley, R.; Cantel, J.

    1960-01-01

    The first part of the report is devoted to generalities: the geographical situation of the Marcoule Centre, the sources of radio-active effluent, methods of treating this effluent. In the second part the authors gives a detailed description of the various installations in the Radio-active Effluent Treatment Station at the Marcoule Centre, and outline the conditions governing the rejection of treated effluent into the Rhone. A few lines are given to comparisons between the results obtained from the use of these installations up till may 1959 and the expected results published by the same authors at the Brussels Conference (1956). In conclusion the authors lay down some of the essential principles, applicable to the study of new installations. (author) [fr

  19. Handbook of radioactivity measurements procedures. Second edition

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

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

  20. Method of removing iodine and compounds thereof from gaseous effluents

    International Nuclear Information System (INIS)

    Keener, R.L.; Kittle, P.A.

    1976-01-01

    Anion exchange resins including an acrylic backbone formed by the suspension polymerization of a mixture of an acrylic and a crosslinking monomer are useful in the removal of iodine and iodine compounds from gaseous effluents. Removal of radioactive iodine contaminants, particularly alkyl iodine compounds or hydrogen iodine, under extreme conditions, namely temperatures up to 180 0 C and humidities up to 100 percent, from effluents resulting from a major nuclear accident could probably be adsorbed by these resins described herein

  1. A guide for preparing Hanford Site facility effluent monitoring plans

    International Nuclear Information System (INIS)

    Nickels, J.M.

    1992-06-01

    This document provides guidance on the format and content of effluent monitoring plans for facilities at the Hanford Site. The guidance provided in this document is designed to ensure compliance with US Department of Energy (DOE) Orders 5400.1 (DOE 1988a), 5400.3 (DOE 1989a), 5400.4 (DOE 1989b), 5400.5 (DOE 1990a), 5480.1 (DOE 1982), 5480.11 (DOE 1988b), and 5484.1 (DOE 1981). These require environmental monitoring plans for each site, facility, or process that uses, generates, releases, or manages significant pollutants of radioactive or hazardous materials. In support of DOE Orders 5400.5 (Radiation Protection of the Public and the Environment) and 5400.1 (General Environmental Protection Program), the DOE Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE 1991) should be used to establish elements of a radiological effluent monitoring program in the Facility Effluent Monitoring Plan. Evaluation of facilities for compliance with the US Environmental Protection Agency Clean Air Act of 1977 requirements also is included in the airborne emissions section of the Facility Effluent Monitoring Plans. Sampling Analysis Plans for Liquid Effluents, as required by the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), also are included in the Facility Effluent Monitoring Plans. The Facility Effluent Monitoring Plans shall include complete documentation of gaseous and liquid effluent sampling and monitoring systems

  2. Facility effluent monitoring plan for the 284-E and 284-W power plants

    International Nuclear Information System (INIS)

    Nickels, J.M.; Herman, D.R.

    1992-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during calendar year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

  3. The management plan of liquid effluent in Korean advanced light water reactor

    International Nuclear Information System (INIS)

    Kim, S. H.; Lim, H. S.; Jeong, D. W.; Jeong, D. Y.

    2001-01-01

    Non-radioactive liquid effluent in Korean Advanced Light Water Reactor is transferred and treated in centralized waste treatment facility after the radioactivity in effluent is checked within power block. The liquid effluent from centralized waste treatment facility will be discharged by way of discharge canal in order to be in the sufficient condition. As a result of investigating the radiation monitoring design in accordance with 20 provisions by Korean Regulatory Authority, each effluent radiation monitoring with 20 provisions by Korean Regulatory Authority, each effluent radiation monitoring design satisfies the regulatory guideline. In relation to sampling and analyses, most systems satisfy the regulatory guideline except for some effluents from turbine building. And, though sampling and analyses are performed after radioactivity is monitored at each system in turbine building, these exceptions in turbine building effluents are expected to cause no significant problems because radioactivity is monitored by direct or indirect methods prior to release from turbine building. Integrated monitoring on liquid effluent from the centralized waste water treatment facility is not necessary because radiation monitoring, sampling and analyses on each system within power block are performed, and operational effectiveness compared with cost according to adding the radiation monitoring equipment is too low. So, whether the radiation monitoring in this effluent is reflected on design or not is planned to be determined through discussion with regulatory authority

  4. Facility Effluent Monitoring Plan for the N Reactor

    International Nuclear Information System (INIS)

    Watson, D.J.; Brendel, D.F.; Shields, K.D.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The primary purpose of the N Reactor Facility Effluent Monitoring Plan (FEMP), during standby, is to ensure that the radioactive effluents are properly monitored and evaluated for compliance with the applicable DOE orders and regulatory agencies at the federal, state, and local levels. A secondary purpose of the FEMP is to ensure that hazardous wastes are not released, in liquid effluents, to the environment even though the potential to do so is extremely low. The FEMP is to provide a monitoring system that collects representative samples in accordance with industry standards, performs analyses within stringent quality control (QC) requirements, and evaluates the data through the use of comparative analysis with the standards and acceptable environmental models

  5. Order of 24 July 1992 on the licensing of liquid radioactive effluent releases from the large nuclear installation called Atalante at the nuclear research centre in the Rhone valley on the Marcoule nuclear site

    International Nuclear Information System (INIS)

    1992-01-01

    This Order fixes the annual authorized limits and procedures for the transfer from Atalante to the Cogema establishment also at Marcoule of the low-level liquid effluents for treatment. It also specifies the measures for their control and surveillance. (NEA)

  6. Environmental radioactivity measurement. Ispra 1990

    International Nuclear Information System (INIS)

    Dominici, G.; Risposi, L.

    1992-01-01

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

  7. Facility effluent monitoring plan for the 327 Facility

    International Nuclear Information System (INIS)

    1994-11-01

    The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

  8. 200 Area Effluent Treatment Facility: Delisting petition

    International Nuclear Information System (INIS)

    1993-08-01

    Waste water has been generated for over 40 years as a result of operations conducted on the Hanford Site. This waste water previously was discharged to cribs, ponds, or ditches. An example of such waste water includes process condensate that might have been in contact with dangerous waste or mixed waste (containing both radioactive and dangerous components). This petition presents the treatment technologies that are designed into the 200 Area Effluent Treatment Facility to eliminate the dangerous characteristics of the waste and to delist the effluent in accordance with the requirements found in 40 Code of Federal Regulations 260.20 and 260.22. The purpose of this petition is to demonstrate that the 242-A Evaporator process condensate will be treated adequately so that the effluent from the 200 Area Effluent Treatment Facility will no longer require management as a regulated dangerous waste. This demonstration was performed by use of a surrogate (synthetic) waste, designed by the US Department of Energy, Richland Operations Office to include species that represent all organic and inorganic constituents (but not radionuclide species) expected to be found on the Hanford Site. Thus, the surrogate will encompass not only the expected 242-A Evaporator process condensate characteristics, but those of other potential 200 Area Effluent Treatment Facility waste streams and additional 40 CFR Appendix VIII constituents

  9. Facility Effluent Monitoring Plan for the 222-S Laboratory

    International Nuclear Information System (INIS)

    Robinson, A.V.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems against applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. The current operation of the 222-S facilities includes the provision of analytical and radiological chemistry services in support of Hanford Site processing plants. The emphasis is on waste management, chemical processing, environmental monitoring effluent programs at B Plant, the Uranium Oxide Plant, Tank Farms, the 242-A Evaporator, the Waste Encapsulation and Storage Facility, the Plutonium-Uranium Extraction Facility, the Plutonium Finishing Plant, process development/impact activities, and essential materials. The laboratory also supplies analytical services in support of ongoing waste tank characterization

  10. Optimised performance of industrial high resolution computerised tomography

    International Nuclear Information System (INIS)

    Maangaard, M.

    2000-01-01

    The purpose of non-destructive evaluation (NDE) is to acquire knowledge of the investigated sample. Digital x-ray imaging techniques such as radiography or computerised tomography (CT) produce images of the interior of a sample. The obtained image quality determines the possibility of detecting sample related features, e.g. details and flaws. This thesis presents a method of optimising the performance of industrial X-ray equipment for the imaging task at issue in order to obtain images with high quality. CT produces maps of the X-ray linear attenuation of the sample's interior. CT can produce two dimensional cross-section images or three-dimensional images with volumetric information on the investigated sample. The image contrast and noise depend on both the investigated sample and the equipment and settings used (X-ray tube potential, X-ray filtration, exposure time, etc.). Hence, it is vital to find the optimal equipment settings in order to obtain images of high quality. To be able to mathematically optimise the image quality, it is necessary to have a model of the X-ray imaging system together with an appropriate measure of image quality. The optimisation is performed with a developed model for an X-ray image-intensifier-based radiography system. The model predicts the mean value and variance of the measured signal level in the collected radiographic images. The traditionally used measure of physical image quality is the signal-to-noise ratio (SNR). To calculate the signal-to-noise ratio, a well-defined detail (flaw) is required. It was found that maximising the SNR leads to ambiguities, the optimised settings found by maximising the SNR were dependent on the material in the detail. When CT is performed on irregular shaped samples containing density and compositional variations, it is difficult to define which SNR to use for optimisation. This difficulty is solved by the measures of physical image quality proposed here, the ratios geometry

  11. NPP radioactive waste processing and solidification

    International Nuclear Information System (INIS)

    Nikiforov, A.S.; Polyakov, A.S.; Zakharova, K.P.

    1983-01-01

    The problems of proce-sing NPP intermediate level- and low-level liquid radioactive wastes (LRW) are considered. Various methods are compared of LWR solidification on the base of bituminization, cement grouting and inclusion into synthetic resins. It is concluded that the considered methods ensure radioactive radionuclides effluents into open hydronetwork at the level below the sanitary, standards

  12. Computerised Attention Training for Children with Intellectual and Developmental Disabilities: A Randomised Controlled Trial

    Science.gov (United States)

    Kirk, Hannah E.; Gray, Kylie M.; Ellis, Kirsten; Taffe, John; Cornish, Kim M.

    2016-01-01

    Background: Children with intellectual and developmental disabilities (IDD) experience heightened attention difficulties which have been linked to poorer cognitive, academic and social outcomes. Although, increasing research has focused on the potential of computerised cognitive training in reducing attention problems, limited studies have…

  13. Effectiveness of a Computerised Working Memory Training in Adolescents with Mild to Borderline Intellectual Disabilities

    Science.gov (United States)

    Van der Molen, M. J.; Van Luit, J. E. H.; Van der Molen, M. W.; Klugkist, I.; Jongmans, M. J.

    2010-01-01

    Background: The goal of this study is to evaluate the effectiveness of a computerised working memory (WM) training on memory, response inhibition, fluid intelligence, scholastic abilities and the recall of stories in adolescents with mild to borderline intellectual disabilities attending special education. Method: A total of 95 adolescents with…

  14. A New Computerised Advanced Theory of Mind Measure for Children with Asperger Syndrome: The ATOMIC

    Science.gov (United States)

    Beaumont, Renae B.; Sofronoff, Kate

    2008-01-01

    This study examined the ability of children with Asperger Syndrome (AS) to attribute mental states to characters in a new computerised, advanced theory of mind measure: The Animated Theory of Mind Inventory for Children (ATOMIC). Results showed that children with AS matched on IQ, verbal comprehension, age and gender performed equivalently on…

  15. Sample preparation and scanning protocol for computerised analysis of root length and diameter

    NARCIS (Netherlands)

    Bouma, T.J.; Nielsen, K.F.; Koutstaal, B.P.

    2000-01-01

    Root length and diameter distribution are important characteristics to be considered when describing and comparing root systems. Root length and root-diameter distribution may be obtained in two ways: by microscopical measurements, which are laborious, or by computerised analysis, which is fast but

  16. Effectiveness of a computerised working memory training in adolescents with mild to borderline intellectual disabilities

    NARCIS (Netherlands)

    van der Molen, M.J.; van Luit, J.E.H.; van der Molen, M.W.; Klugkist, I.; Jongmans, M.J.

    2010-01-01

    Background: The goal of this study is to evaluate the effectiveness of a computerised working memory (WM) training on memory, response inhibition, fluid intelligence, scholastic abilities and the recall of stories in adolescents with mild to borderline intellectual disabilities attending special

  17. Facility effluent monitoring plan for the plutonium-uranium extraction facility

    International Nuclear Information System (INIS)

    Lohrasbi, J.; Johnson, D.L.; De Lorenzo, D.S.

    1993-12-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

  18. Facility effluent monitoring plan for the Waste Receiving and Processing Facility Module 1

    International Nuclear Information System (INIS)

    Lewis, C.J.

    1995-10-01

    A facility effluent monitoring plan is required by the US Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal state, and local requirements. This facility effluent monitoring plan shall ensure lonq-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years

  19. Facility effluent monitoring plan for the plutonium-uranium extraction facility

    International Nuclear Information System (INIS)

    Thompson, R.J.; Sontage, S.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years

  20. Facility Effluent Monitoring Plan for the 2724-W Protective Equipment Decontamination Facility

    International Nuclear Information System (INIS)

    Carter, G.J.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updates as a minimum every three years

  1. Facility effluent monitoring plan for the plutonium-uranium extraction facility

    Energy Technology Data Exchange (ETDEWEB)

    Lohrasbi, J.; Johnson, D.L. [Westinghouse Hanford Co., Richland, WA (United States); De Lorenzo, D.S. [Los Alamos Technical Associates, NM (United States)

    1993-12-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

  2. Evaluating future detriment from radioactive discharges

    International Nuclear Information System (INIS)

    Fleishman, A.B.; Clark, M.J.

    1982-01-01

    A quantitative framework for expressing judgements on the relative valuation of both future protection costs and radiation detriment from radioactive discharges is discussed. The framework can be applied to a series of notional effluent control options, illustrating the sensitivity of optimum protection levels to variations in discount rates. Using data on the radiological significance and management of radioactive discharges arising from the nuclear fuel cycle, it was shown that this quantitative optimization method of evaluating future detriment has important implications for the management of radioactive effluents, particularly those containing long-lived nuclides. (U.K.)

  3. Implementation of a model of atmospheric dispersion and dose calculation in the release of radioactive effluents in the Nuclear Centre; Implementacion de un modelo de dispersion atmosferica y calculo de dosis en la liberacion de efluentes radiactivos en el Centro Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Cruz L, C. A.

    2015-07-01

    In the present thesis, the software DERA (Dispersion of Radioactive Effluents into the Atmosphere) was developed in order to calculate the equivalent dose, external and internal, associated with the release of radioactive effluents into the atmosphere from a nuclear facility. The software describes such emissions in normal operation, and not considering the exceptional situations such as accidents. Several tools were integrated for describing the dispersion of radioactive effluents using site meteorological information (average speed and wind direction and the stability profile). Starting with the calculation of the concentration of the effluent as a function of position, DERA estimates equivalent doses using a set of EPA s and ICRP s coefficients. The software contains a module that integrates a database with these coefficients for a set of 825 different radioisotopes and uses the Gaussian method to calculate the effluents dispersion. This work analyzes how adequate is the Gaussian model to describe emissions type -puff-. Chapter 4 concludes, on the basis of a comparison of the recommended correlations of emissions type -puff-, that under certain conditions (in particular with intermittent emissions) it is possible to perform an adequate description using the Gaussian model. The dispersion coefficients (σ{sub y} and σ{sub z}), that using the Gaussian model, were obtained from different correlations given in the literature. Also in Chapter 5 is presented the construction of a particular correlation using Lagrange polynomials, which takes information from the Pasquill-Gifford-Turner curves (PGT). This work also contains a state of the art about the coefficients that relate the concentration with the equivalent dose. This topic is discussed in Chapter 6, including a brief description of the biological-compartmental models developed by the ICRP. The software s development was performed using the programming language Python 2.7, for the Windows operating system (the

  4. Suspended solids in liquid effluents

    International Nuclear Information System (INIS)

    McGrath, J.J.

    1988-06-01

    An international literature review and telephone mail survey was conducted with respect to technical and regulatory aspects of suspended solids in radioactive liquid wastes from nuclear power stations. Results of the survey are summarized and show that suspended solids are an important component of some waste streams. The data available, while limited, show these solids to be associated largely with corrosion products. The solids are highly variable in quantity, size and composition. Filtration is commonly applied for their removal from liquid effluents and is effective. Complex interactions with receiving waters can result in physical/chemical changes of released radionuclides and these phenomena have been seen as reason for not applying regulatory controls based on suspended solids content. 340 refs

  5. Effluent monitoring for nuclear safeguards

    International Nuclear Information System (INIS)

    Stanchi, L.

    1977-01-01

    A microprocessor-based instrument operates a continuous surveillance on effluents from a nuclear facility. It receives and evaluates pulses from two NaI detectors and a set of single-channel analyzers. It has self-diagnosing capability so that it takes actions not only when it recognizes excessive radioactivity but also when it ascertains some abnormal behavior. Power failure procedure and automatic restart are provided. Operative constants such as alarm thresholds, times, and number of successive measurements are permanently stored in a read/write battery operated C-MOS memory. The program allows automatic succession of phases in a peculiar way and has a feature for loading an auxiliary program into RAMs

  6. Effluent monitoring for nuclear safeguards

    International Nuclear Information System (INIS)

    Stanchi, L.

    1976-01-01

    A microprocessor-based instrument operates a continuous surveillance on effluents from a nuclear facility. It receives and evaluates pulses from two NaI detectors and a set of single-channel analyzers. It has self-diagnosing capability so that it takes actions not only when it recognizes excessive radioactivity but also when it ascertains some abnormal behavior. Power failure procedure and automatic restart are provided. Operative constants such as alarm thresholds, times, and number of successive measurements are permanently stored in a read/write battery operated C-MOS memory. The program allows automatic succession of phases in a peculiar way and has a feature for loading an auxiliary program into RAMs

  7. Characterization of effluents from a high-temperature gas-cooled reactor fuel refabrication plant

    International Nuclear Information System (INIS)

    Judd, M.S.; Bradley, R.A.; Olsen, A.R.

    1975-12-01

    The types and quantities of chemical and radioactive effluents that would be released from a reference fuel refabrication facility for the High-Temperature Gas-Cooled Reactor (HTGR) have been determined. This information will be used to predict the impact of such a facility on the environment, to identify areas where additional development work needs to be done to further identify and quantify effluent streams, and to limit effluent release to the environment

  8. F/H Area Effluent Treatment Facility. Phase II. CAC basic data

    International Nuclear Information System (INIS)

    Collins, W.W.; O'Leary, C.D.

    1984-01-01

    Project objectives and requirements are listed for both Phase I and II. Schedule is listed with startup targeted for 1989. Storage facilities will be provided for both chemical and radioactive effluents. 8 figs., 19 tabs

  9. Ecological assessments of effluent impacts on communities of indigenous aquatic organisms (symposium), 1979

    International Nuclear Information System (INIS)

    Bates, J.M.; Weber, C.I.

    1981-01-01

    This conference proceedings contains 17 papers, of which 4 are indexed separately. All papers deal with the effects of chemical, radioactive, and thermal effluents on aquatic organisms. The emphasis is on the methods of evaluating the effects of effluents on the standing crop, community structure, and community function

  10. Treatment of effluent at the Saclay Centre d'Etudes Nucleaires (1960); Le traitement des effluents du Centre d'Etudes Nucleaires de Saclay (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    The Centre d'Etudes Nucleaires at Saclay possesses several installations from which liquid radioactive effluent is rejected, and it has thus been found necessary to construct a station for the purification of radioactive liquids and to settle various chemical, analytical and technological problems. This report describes, in the following order: - the disposal possibilities at the Centre d'Etudes Nucleaires, Saclay, - the effluents produced at the centre, - the set-up for collecting effluent, - treatment of the effluent, - results of these treatments. (author) [French] La presence, au Centre d'Etudes Nucleaires de Saclay, de plusieurs installations susceptibles de rejeter des effluents liquides radioactifs a necessite la construction d'une station d'epuration d'eaux radioactives et la mise au point de differents problemes chimiques, analytiques et technologiques. Dans ce rapport, nous exposerons successivement: - les possibilites de rejet du Centre d'Etudes Nucleaires de Saclay, - les effluents du centre, - le dispositif de collecte des effluents, - le traitement de ces effluents, - les resultats de ces traitements. (auteur)

  11. Inorganic ion exchangers. Application to liquid effluent processing

    International Nuclear Information System (INIS)

    Dozol, M.

    1983-10-01

    Main inorganic ion exchangers used for radioactive liquid effluents presented in this report are: synthetic and natural zeolites, in titanium oxides, titanates, niobates, tantalates, zirconates, some insoluble salts of zirconium, molybdenum and tin, heteropolyacids and polyantimonic acid. Properties of these ion exchangers are described: structure, adsoption, radiation effects and thermal stability, application to waste processing, radioactive waste storage uranium and cesium 137 recovery are evoked [fr

  12. modelling effluent assimila modelling effluent assimilat modelling

    African Journals Online (AJOL)

    eobe

    G EFFLUENT ASSIMILATIVE CAPACITY OF IKPOBA RIVE. BENIN CITY, NIGERIA ... l purposes to communities rse such as ... treat in order for it to meet the aforeme of the communities. It is therefore i ..... Substituting and integrating yields the following equations ..... Purification Potentials of Small Tropical Urban. Stream: A ...

  13. The application of XML in the effluents data modeling of nuclear facilities

    International Nuclear Information System (INIS)

    Yue Feng; Lin Quanyi; Yue Huiguo; Zhang Yan; Zhang Peng; Cao Jun; Chen Bo

    2013-01-01

    The radioactive effluent data, which can provide information to distinguish whether facilities, waste disposal, and control system run normally, is an important basis of safety regulation and emergency management. It can also provide the information to start emergency alarm system as soon as possible. XML technology is an effective tool to realize the standard of effluent data exchange, in favor of data collection, statistics and analysis, strengthening the effectiveness of effluent regulation. This paper first introduces the concept of XML, the choices of effluent data modeling method, and then emphasizes the process of effluent model, finally the model and application are shown, While there is deficiency about the application of XML in the effluents data modeling of nuclear facilities, it is a beneficial attempt to the informatization management of effluents. (authors)

  14. INEEL Liquid Effluent Inventory

    Energy Technology Data Exchange (ETDEWEB)

    Major, C.A.

    1997-06-01

    The INEEL contractors and their associated facilities are required to identify all liquid effluent discharges that may impact the environment at the INEEL. This liquid effluent information is then placed in the Liquid Effluent Inventory (LEI) database, which is maintained by the INEEL prime contractor. The purpose of the LEI is to identify and maintain a current listing of all liquid effluent discharge points and to identify which discharges are subject to federal, state, or local permitting or reporting requirements and DOE order requirements. Initial characterization, which represents most of the INEEL liquid effluents, has been performed, and additional characterization may be required in the future to meet regulations. LEI information is made available to persons responsible for or concerned with INEEL compliance with liquid effluent permitting or reporting requirements, such as the National Pollutant Discharge Elimination System, Wastewater Land Application, Storm Water Pollution Prevention, Spill Prevention Control and Countermeasures, and Industrial Wastewater Pretreatment. The State of Idaho Environmental Oversight and Monitoring Program also needs the information for tracking liquid effluent discharges at the INEEL. The information provides a baseline from which future liquid discharges can be identified, characterized, and regulated, if appropriate. The review covered new and removed buildings/structures, buildings/structures which most likely had new, relocated, or removed LEI discharge points, and at least 10% of the remaining discharge points.

  15. Ten years of investigation on radioactive contamination of the marine environment. Incorporation, by marine algae and animals, of hydrogen-3 and other radionuclides present in effluents of nuclear or industrial origin

    International Nuclear Information System (INIS)

    Bonotto, S.; Colard, J.; Koch, G.; Kirchmann, R.; Strack, S.; Luettke, A.; Carraro, G.

    1981-01-01

    Several marine plants and animals were investigated for their capability of incorporating the main radionuclides present in selected effluents. Accumulation factors are reported for 3 H, 134 Cs, 136 Cs, 137 Cs, 58 Co, 60 Co, 54 Mn, 131 I 226 Ra and 124 Sb. Marine algae, which are involved in food chains leading to man, show the highest accumulation factors. The stable element composition of the alga Acetabularia was determined by gamma-activation analysis. The preferential accumulation of particular radionuclides by marine organisms suggests that they may have a significant role in the turnover rate of elements in the marine environment. (author)

  16. Facility effluent monitoring plan for the 324 Facility

    International Nuclear Information System (INIS)

    1994-11-01

    The 324 Facility [Waste Technology Engineering Laboratory] in the 300 Area primarily supports the research and development of radioactive and nonradioactive waste vitrification technologies, biological waste remediation technologies, spent nuclear fuel studies, waste mixing and transport studies, and tritium development programs. All of the above-mentioned programs deal with, and have the potential to, release hazardous and/or radioactive material. The potential for discharge would primarily result from (1) conducting research activities using the hazardous materials, (2) storing radionuclides and hazardous chemicals, and (3) waste accumulation and storage. This report summarizes the airborne and liquid effluents, and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterizing effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

  17. Effluent management practices at the AAEC Research Establishment

    International Nuclear Information System (INIS)

    Khoe, G.

    1978-02-01

    A technical description is given of the facilities and operation of the waste water and liquid waste management system at the Australian Atomic Energy Commission Research Establishment at Lucas Heights. Also described are practices and principles involved in the control and recording of radioactivity in the effluents. (Author)

  18. Study of the {sup 60}Co speciation in the aqueous radioactive waste of the la Hague nuclear reprocessing plant; environmental behaviour after discharges in the waters of the channel; Etude de la speciation du {sup 60}Co dans les effluents de l'usine de retraitement de combustibles irradies de la Hague; devenir apres rejet dans les eaux de la Manche

    Energy Technology Data Exchange (ETDEWEB)

    Gaudaire, J.M

    1999-07-01

    {sup 60}Co is produced as an activation product and is present in the low-level aqueous radioactive waste released from the La Hague plant. At present, the concentration in the sea (non filtered at 0.45 {mu}m) at the Goury site are close to or even below, the detection limit: 0.2 mBq.l{sup -1}. The {sup 60}Co speciation depends on the type of effluent considered: in the effluent A ('active'), the cobalt is in the form of a stable trivalent complex; in the effluent V (to be checked), the cobalt is in majority (50% of the activity release) in the form of particles (>0.45 {mu}m), and then in the form of two soluble species: ionic divalent (Co{sup 2+}) and some stable complexes. The evolution of the reprocessing techniques used does not affect the speciation. So, since the nuclear reprocessing plant started at the La Hague plant in 1966, the chemical species discharged in the sea shows time variation related to the evolution of the type of effluent discharged. Thus, since 1994, the particles of cobalt are the main species discharged in the Channel (the V effluents represent more than 85% of the total {sup 60}Co activity released). The effect of instantaneous dilution into the marine conditions involving a variation of pH, oxido-reduction, ionic strength, a gradient of salinity, does not interfere with the evolution of the chemical species discharged. Nevertheless, during the discharge of the V effluent, the main constituents of the sea water (Mg{sup 2+} and Ca{sup 2+}) go through a precipitation. This comes with the coprecipitation of the ion Co{sup 2+} and with the particles of cobalt (complexes are not affected), and it can be responsible for an increase in the concentration in the particles. The chemical behaviour of the cobalt in the Channel is different from those of conservative element such as antimony. The ionic cobalt and the particles have a small dispersion in the water (cobalt has a very high particle/dissolved distribution factor, it is a non

  19. Study of the {sup 60}Co speciation in the aqueous radioactive waste of the la Hague nuclear reprocessing plant; environmental behaviour after discharges in the waters of the channel; Etude de la speciation du {sup 60}Co dans les effluents de l'usine de retraitement de combustibles irradies de la Hague; devenir apres rejet dans les eaux de la Manche

    Energy Technology Data Exchange (ETDEWEB)

    Gaudaire, J M

    1999-07-01

    {sup 60}Co is produced as an activation product and is present in the low-level aqueous radioactive waste released from the La Hague plant. At present, the concentration in the sea (non filtered at 0.45 {mu}m) at the Goury site are close to or even below, the detection limit: 0.2 mBq.l{sup -1}. The {sup 60}Co speciation depends on the type of effluent considered: in the effluent A ('active'), the cobalt is in the form of a stable trivalent complex; in the effluent V (to be checked), the cobalt is in majority (50% of the activity release) in the form of particles (>0.45 {mu}m), and then in the form of two soluble species: ionic divalent (Co{sup 2+}) and some stable complexes. The evolution of the reprocessing techniques used does not affect the speciation. So, since the nuclear reprocessing plant started at the La Hague plant in 1966, the chemical species discharged in the sea shows time variation related to the evolution of the type of effluent discharged. Thus, since 1994, the particles of cobalt are the main species discharged in the Channel (the V effluents represent more than 85% of the total {sup 60}Co activity released). The effect of instantaneous dilution into the marine conditions involving a variation of pH, oxido-reduction, ionic strength, a gradient of salinity, does not interfere with the evolution of the chemical species discharged. Nevertheless, during the discharge of the V effluent, the main constituents of the sea water (Mg{sup 2+} and Ca{sup 2+}) go through a precipitation. This comes with the coprecipitation of the ion Co{sup 2+} and with the particles of cobalt (complexes are not affected), and it can be responsible for an increase in the concentration in the particles. The chemical behaviour of the cobalt in the Channel is different from those of conservative element such as antimony. The ionic cobalt and the particles have a small dispersion in the water (cobalt has a very high particle/dissolved distribution factor, it is a non

  20. Genotoxicity of swine effluents.

    Science.gov (United States)

    Techio, V H; Stolberg, J; Kunz, A; Zanin, E; Perdomo, C C

    2011-01-01

    This study aimed at the investigation of genotoxic effects of swine effluents from different stages of a treatment system for swine wastes through bioassay of stamen hairs and micronuclei in Tradescantia (clone BNL 4430). No significant differences (p≥0.05) regarding the genic mutations were found in the bioassay of stamen hairs, independently of the effluent analysed. For the genotoxicity test with micronuclei, the plants exposed to raw wastes, to sludge, and to effluent of the biodigester have presented higher rates of chromosomal damages (micronuclei), with significant differences in relation to the control group and other effluent of the waste treatment system (p≤0.05). The association between the chemical parameters and the genotoxicity data have shown that the variables COD and TKN have presented significant correlation (p≤0.05) with the number of mutagenic events in the tetrads.

  1. Liquid Effluent Retention Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Liquid Effluent Retention Facility (LERF) is located in the central part of the Hanford Site. LERF is permitted by the State of Washington and has three liquid...

  2. [A computerised clinical decision-support system for the management of depression in Primary Care].

    Science.gov (United States)

    Aragonès, Enric; Comín, Eva; Cavero, Myriam; Pérez, Víctor; Molina, Cristina; Palao, Diego

    Despite its clinical relevance and its importance as a public health problem, there are major gaps in the management of depression. Evidence-based clinical guidelines are useful to improve processes and clinical outcomes. In order to make their implementation easier these guidelines have been transformed into computerised clinical decision support systems. In this article, a description is presented on the basics and characteristics of a new computerised clinical guideline for the management of major depression, developed in the public health system in Catalonia. This tool helps the clinician to establish reliable and accurate diagnoses of depression, to choose the best treatment a priori according to the disease and the patient characteristics. It also emphasises the importance of systematic monitoring to assess the clinical course, and to adjust therapeutic interventions to the patient's needs at all times. Copyright © 2016 Elsevier España, S.L.U. All rights reserved.

  3. The computerised accountancy system (MYDAS) for irradiated components in RNL's Mayfair Laboratory at Culcheth

    International Nuclear Information System (INIS)

    Stansfield, R.G.; Baker, A.R.

    1985-09-01

    The computerised Mayfair Accountancy System (MYDAS) has been developed to account for irradiated components in the Mayfair Laboratory at Culcheth and supersedes a card-index system. The computerised system greatly improves the availability of the data held and it ensures, by means of extensive data validation programs, that the data accurately represent the current inventory of irradiated components in the Laboratory. The system has been implemented on the Risley ICL 2966 main-frame computer and uses an IDMS database to store the data. The computer is accessed through the facilities of the Transaction Processing Management System (TPMS) providing rapid and secure access to the database from several visual display units and printers simultaneously. (author)

  4. 10 CFR 61.41 - Protection of the general population from releases of radioactivity.

    Science.gov (United States)

    2010-01-01

    ... radioactivity. 61.41 Section 61.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR... from releases of radioactivity. Concentrations of radioactive material which may be released to the... maintain releases of radioactivity in effluents to the general environment as low as is reasonably...

  5. CONCAWE effluent speciation project

    Energy Technology Data Exchange (ETDEWEB)

    Leonards, P.; Comber, M.; Forbes, S.; Whale, G.; Den Haan, K.

    2010-09-15

    In preparation for the implementation of the EU REACH regulation, a project was undertaken to transfer the high-resolution analytical method for determining hydrocarbon blocks in petroleum products by comprehensive two-dimensional gas chromatography (GCxGC) to a laboratory external to the petroleum industry (Institute for Environmental Studies (IVM) of the VU University of Amsterdam). The method was validated and used for the analysis of petroleum hydrocarbons extracted from refinery effluents. The report describes the technology transfer and the approaches used to demonstrate the successful transfer and application of the GCxGC methodology from analysing petroleum products to the quantitative determination of hydrocarbon blocks in refinery effluents. The report describes all the methods used for all the determinations on the effluent samples along with an overview of the results obtained which are presented in summary tables and graphs. These data have significantly improved CONCAWE's knowledge of what refineries emit in their effluents. A total of 111 Effluent Discharge Samples from 105 CONCAWE refineries in Europe were obtained in the period June 2008 to March 2009. These effluents were analysed for metals, standard effluent parameters (including COD, BOD), oil in water, BTEX and volatile organic compounds. The hydrocarbon speciation determinations and other hydrocarbon analyses are also reported. The individual refinery analytical results are included into this report, coded as per the CONCAWE system. These data will be, individually, communicated to companies and refineries. The report demonstrates that it is feasible to conduct a research programme to investigate the fate and effects of hydrocarbon blocks present in discharged refinery effluents.

  6. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle for use in establishing ''as low as practicable'' guides: nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Finney, B.C.; Blanco, R.E.; Dahlman, R.C.; Kitts, F.G.; Witherspoon, J.P.

    1975-05-01

    A cost-benefit study was made to determine the cost and effectiveness of radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from a model nuclear fuel reprocessing plant which processes light-water reactor (LWR) fuels, and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist in defining the term ''as low as practicable'' in relation to limiting the release of radioactive materials from nuclear facilities. The base case model plant is representative of current plant technology and has an annual capacity of 1500 metric tons of LWR fuel. Additional radwaste treatment systems are added to the base case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The cost for the added waste treatment operations and the corresponding dose commitments are calculated for each case. In the final analysis, radiological dose is plotted vs the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. Much of the technology used in the advanced cases is in an early stage of development and is not suitable for immediate use. The methodology used in estimating the costs and the radiological doses, detailed calculations, and tabulations is presented in Appendix A and ORNL-4992. (U.S.)

  7. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle for use in establishing ''as low as practicable'' guides: fabrication of light-water reactor fuels containing plutonium

    International Nuclear Information System (INIS)

    Groenier, W.S.; Blanco, R.E.; Dahlman, R.C.; Finney, B.C.; Kibbey, A.H.; Witherspoon, J.P.

    1975-05-01

    A cost-benefit study was made to determine the cost and effectiveness of radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from a model light-water plutonium recycle reactor fuel fabrication plant, and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist in defining the term ''as low as practicable'' in relation to limiting the release of radioactive materials from nuclear facilities. The base case model plant is representative of current plant technology and has an annual capacity of 300 metric tons of LWR plutonium recycle fuel. Additional radwaste treatment equipment is added to the base case plants in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The cost for the added waste treatment operations and the corresponding dose commitment are calculated for each case. In the final analysis, radiological dose is plotted vs the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. Some of the technology used in the advanced cases is in an early stage of development and is not suitable for immediate use. The methodology used in estimating the costsand the radiological doses, detailed calculations, and tabulations are presented in Appendixes A and B. (U.S.)

  8. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle for use in establishing ''as low as practicable'' guides: fabrication of light-water reactor fuel from enriched uranium dioxide

    International Nuclear Information System (INIS)

    Pechin, W.H.; Blanco, R.E.; Dahlman, R.C.; Finney, B.C.; Lindauer, R.B.; Witherspoon, J.P.

    1975-05-01

    A cost-benefit study was made to determine the cost and effectiveness of radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from a model enriched-uranium, light-water reactor (LWR) fuel fabrication plant, and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist in defining the term ''as low as practicable'' in relation to limiting the release of radioactive materials from nuclear facilities. The base case model plant is representative of current plant technology and has an annual capacity of 1500 metric tons of LWR fuel. Additional radwaste treatment equipment is added to the base case plants in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The cost for the added waste treatment operations and the corresponding dose commitment are calculated for each case. In the final analysis, radiological dose is plotted vs the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. Some of the technology used in the advanced cases is in an early stage of development and is not suitable for immediate use. The methodology used in estimating the costs and the radiological doses, detailed calculations, and tabulations are presented in Appendix A and ORNL-4992. (U.S.)

  9. Effluent releases at the TRIGA reactor facility

    Energy Technology Data Exchange (ETDEWEB)

    Whittemore, W L [General Atomic Co., San Diego, CA (United States)

    1974-07-01

    The principal effluent from the operating TRIGA reactors in our facility is argon-41. As monitored by a recording gas and particulate stack monitor, the values shown in the table, the Mark III operating 24 hours per day for very long periods produced the largest amount of radioactive argon. The quantity of 23.7 Ci A-41 when diluted by the normal reactor room ventilation system corresponded to 1.45 x 10{sup -6} {mu}Ci/cc. As diluted in the roof stack stream and the reactor building wake, the concentration immediately outside the reactor building was 25% MPC for an unrestricted area. The continued dilution of this effluent resulted in a concentration of a few percent MPC at the site boundary (unrestricted area) 350 meters from the reactor. (author)

  10. Comparing three methods of computerised cognitive training for older adults with subclinical cognitive decline.

    Science.gov (United States)

    Gooding, Amanda L; Choi, Jimmy; Fiszdon, Joanna M; Wilkins, Kirsten; Kirwin, Paul D; van Dyck, Christopher H; Devanand, Davangere; Bell, Morris D; Rivera Mindt, Monica

    2016-10-01

    Cognitive rehabilitation for mild cognitive impairment (MCI) and early Alzheimer's disease is readily available to the geriatric population. Initial evidence suggests that techniques incorporating motivational strategies to enhance treatment engagement may provide more benefit than computerised training alone. Seventy four adults with subclinical cognitive decline were randomly assigned to computerised cognitive training (CCT), Cognitive Vitality Training (CVT), or an Active Control Group (ACG), and underwent neuropsychological evaluations at baseline and four-month follow-up. Significant differences were found in changes in performance on the Modified Mini Mental State Examination (mMMSE) and measures of verbal learning and memory across treatment groups. Experimental groups showed greater preservation of functioning on the mMMSE than the ACG group, the CVT group performed better than the ACG group on one measure of verbal learning and both measures of verbal memory, and the CCT group performed better than the ACG group on one measure of verbal learning and one measure of verbal memory. There were no significant group differences between the CVT and CCT groups on measures of verbal learning or memory. It was concluded that computerised cognitive training may offer the most benefit when incorporated into a therapeutic milieu rather than administered alone, although both appear superior to more generic forms of cognitive stimulation.

  11. A systematic review of computerised serious educational games about alcohol and other drugs for adolescents.

    Science.gov (United States)

    Rodriguez, Daniel M; Teesson, Maree; Newton, Nicola C

    2014-03-01

    Serious educational games (SEG) have been shown to be effective in educating young people about a range of topics, including languages and maths. This paper identifies the use of computerised SEGs in education about alcohol and other drugs and reviews their impact on the prevention of alcohol and drug use. The Cochrane Library, EMBASE, MEDLINE, ERIC, Scopus, psychINFO, pubMED and DRUG databases were searched in February 2013. Additional publications were obtained from the reference lists of the relevant papers. Studies were included if they described an evaluation of a computerised SEG that targeted alcohol and/or other drugs and had been trialled with adolescents. Eight SEGs were identified targeting tobacco, alcohol, cannabis, methamphetamine, ecstasy, inhalants, cocaine and opioids. Six reported positive outcomes in terms of increased content knowledge and two reported increased negative attitudes towards the targeted drugs. Only one reported a decrease in the frequency of drug use. This is the first review of the efficacy of computerised SEGs for alcohol and other drugs for adolescents. Results suggest that SEGs can increase content knowledge of alcohol and other drugs. Evidence concerning impacts on negative attitudes and alcohol and drug use is limited, with few studies examining these outcomes. © 2013 Australasian Professional Society on Alcohol and other Drugs.

  12. WASTE TREATMENT PLANT (WTP) LIQUID EFFLUENT TREATABILITY EVALUATION

    International Nuclear Information System (INIS)

    LUECK, K.J.

    2004-01-01

    A forecast of the radioactive, dangerous liquid effluents expected to be produced by the Waste Treatment Plant (WTP) was provided by Bechtel National, Inc. (BNI 2004). The forecast represents the liquid effluents generated from the processing of Tank Farm waste through the end-of-mission for the WTP. The WTP forecast is provided in the Appendices. The WTP liquid effluents will be stored, treated, and disposed of in the Liquid Effluent Retention Facility (LERF) and the Effluent Treatment Facility (ETF). Both facilities are located in the 200 East Area and are operated by Fluor Hanford, Inc. (FH) for the US. Department of Energy (DOE). The treatability of the WTP liquid effluents in the LERF/ETF was evaluated. The evaluation was conducted by comparing the forecast to the LERF/ETF treatability envelope (Aromi 1997), which provides information on the items which determine if a liquid effluent is acceptable for receipt and treatment at the LERF/ETF. The format of the evaluation corresponds directly to the outline of the treatability envelope document. Except where noted, the maximum annual average concentrations over the range of the 27 year forecast was evaluated against the treatability envelope. This is an acceptable approach because the volume capacity in the LERF Basin will equalize the minimum and maximum peaks. Background information on the LERF/ETF design basis is provided in the treatability envelope document

  13. Airborne effluent control at uranium mills

    International Nuclear Information System (INIS)

    Sears, M.B.

    1976-01-01

    The Oak Ridge National Laboratory has made an engineering cost--environmental benefit study of radioactive waste treatment systems for decreasing the amount of radioactive materials released from uranium ore processing mills. This paper summarizes the results of the study which pertain to the control and/or abatement of airborne radioactive materials from the mill processes. The tailings area is not included. Present practices in the uranium milling industry, with particular emphasis on effluent control and waste management, have been surveyed. A questionnaire was distributed to each active mill in the United States. Replies were received from about 75 percent of the mill operators. Visits were made to six operating uranium mills that were selected because they represented the different processes in use today and the newest, most modern in mill designs. Discussions were held with members of the Region IV Office of NRC and the Grand Junction Office of ERDA. Nuclear Science Abstracts, as well as other sources, were searched for literature pertinent to uranium mill processes, effluent control, and waste management

  14. Facility effluent monitoring plan for K Area Spent Fuel. Revision 1

    International Nuclear Information System (INIS)

    Hunacek, G.S.

    1995-09-01

    The scope of this document includes program plans for monitoring and characterizing radioactive and nonradioactive hazardous materials discharged in the K Area effluents. This FEMP includes complete documentation for both airborne and liquid effluent monitoring systems that monitor radioactive and nonradioactive hazardous pollutants that could be discharged to the environment under routine and/or upset conditions. This documentation is provided for each K Area facility that uses, generates, releases, or manages significant quantities of radioactive and nonradioactive hazardous materials that could impact public and employee safety and the environment. This FEW describes the airborne and liquid effluent paths and the associated sampling and monitoring systems of the K Area facilities. Sufficient information is provided on the effluent characteristics and the effluent monitoring systems so that a compliance assessment against requirements may be performed. Adequate details are supplied such that radioactive and hazardous material source terms may be related to specific effluent streams which are, in turn, related to discharge points and finally compared to the effluent monitoring system capability

  15. Facility Effluent Monitoring Plan for the Waste Receiving and Processing (WRAP) Facility

    Energy Technology Data Exchange (ETDEWEB)

    DAVIS, W.E.

    2000-03-08

    A facility effluent monitoring plan is required by the U.S. Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee public safety, or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan ensures long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and must be updated, as a minimum, every 3 years.

  16. Facility effluent monitoring plan for K area spent fuel storage basin

    International Nuclear Information System (INIS)

    Hunacek, G.S.

    1996-01-01

    A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400. 1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document was prepared using the specific guidelines identified in WHC-EP-0438-1, A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, and assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the second revision to the original annual report. Long-range integrity of the effluent monitoring system shall be ensured with updates of this report whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

  17. Facility Effluent Monitoring Plan for the Waste Receiving and Processing (WRAP) Facility

    International Nuclear Information System (INIS)

    DAVIS, W.E.

    2000-01-01

    A facility effluent monitoring plan is required by the U.S. Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee public safety, or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan ensures long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and must be updated, as a minimum, every 3 years

  18. Facility Effluent Monitoring Plan for the Plutonium Finishing Plant (PFP); FINAL

    International Nuclear Information System (INIS)

    FRAZIER, T.P.

    1999-01-01

    A facility effluent monitoring plan is required by the U. S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. To ensure the long-range integrity of the effluent monitoring systems, an update to this facility effluent monitoring plan is required whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document is reviewed annually even if there are no operational changes, and is updated, at a minimum, every 3 years

  19. Radioactive Decay

    Science.gov (United States)

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

  20. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle for use in establishing ''as low as practicable'' guides: milling of uranium ores

    International Nuclear Information System (INIS)

    Sears, M.B.; Blanco, R.E.; Dahlman, R.C.; Hill, G.S.; Ryon, A.D.; Witherspoon, J.P.

    1975-05-01

    A cost-benefit study was made to determine the cost and effectiveness of radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from model uranium ore processing mills, and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist in defining the term ''as low as practicable'' in relation to limiting the release of radioactive materials from nuclear facilities. The base case model mills are representative of mills which will process a major fraction of the ore in the next 20 years. Each mill processes 2,000 short tons of ore per day. Additional radwaste treatment techniques are applied to the base case mill and the waste tailings area in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The cost for the added waste treatment operations and the corresponding dose commitment are calculated for each case. In the final analysis, radiological dose is plotted vs the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. Much of the technology used in the advanced cases will require development and demonstration and is not suitable for immediate use. The methodology used in estimating the costs, detailed calculations, and tabulations are presented in ORNL-TM-4903, Volume 2. The methodology and assumptions for the radiological doses are found in ORNL-4992. (U.S.)

  1. Administrative instruction D.G.S./S.D. 7 D./D.H.O.S./E. 4 n. 2001-323 of the 9 july 2001 relative to the management of effluents and wastes from treatment activity and contaminated by radioisotopes; Circulaire D.G.S./S.D. 7 D./D.H.O.S./E. 4 n. 2001-323 du 9 juillet 2001 relative a la gestion des effluents et des dechets d'activites de soins contamines par des radionucleides

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The three parts for this administrative instruction are general principles of management of effluents and waste at radioactive character, management individualized plan for effluents and wastes, articulation with regulation relative to classified installations for the environmental protection. (N.C.)

  2. Facility effluent monitoring plan for the 2724-W Protective Equipment Decontamination Facility

    International Nuclear Information System (INIS)

    Nickels, J.M.; Lavey, G.H.

    1992-12-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438**. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

  3. Facility effluent monitoring plan for the plutonium-uranium extraction facility

    International Nuclear Information System (INIS)

    Nickels, J.M.; Geiger, J.L.

    1992-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified. in. A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

  4. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: reprocessing of high-temperature gas-cooled reactor fuel containing U-233 and thorium

    International Nuclear Information System (INIS)

    Davis, W. Jr.; Blanco, R.E.; Finney, B.C.; Hill, G.S.; Moore, R.E.; Witherspoon, J.P.

    1976-05-01

    A cost/benefit study was made to determine the cost and effectiveness of various radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from a model high-temperature gas-cooled reactor (HTGR) fuel reprocessing plant and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist the U. S. Nuclear Regulatory Commission in defining the term as low as reasonably achievable as it applies to this nuclear facility. The base case is representative of conceptual, developing technology of head-end graphite-burning operations and of extensions of solvent-extraction technology of current designs for light-water-reactor (LWR) fuel reprocessing plants. The model plant has an annual capacity of 450 metric tons of heavy metal (MTHM, where heavy metal is uranium plus thorium), as charged to about fifty 1000-MW(e) HTGRs. Additional radwaste treatment systems are added to the base-case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The capital and annual costs for the added waste treatment operations and the corresponding reductions in dose commitments are calculated for each case. In the final analysis, the cost/benefit of each case, calculated as additional cost of radwaste system divided by the reduction in dose commitment, is tabulated or the dose commitment is plotted with cost as the variable. The status of each of the radwaste treatment methods used in the case studies is discussed

  5. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: fabrication of high-temperature gas-cooled reactor fuel containing uranium-233 and thorium

    International Nuclear Information System (INIS)

    Roddy, J.W.; Blanco, R.E.; Hill, G.S.; Moore, R.E.; Seagren, R.D.; Witherspoon, J.P.

    1976-06-01

    A cost/benefit study was made to determine the cost and effectiveness of various radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from model High-Temperature Gas-Cooled (HTGR) fuel fabrication plants and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist in defining the term ''as low as reasonably achievable'' as it applies to these nuclear facilities. The base cases of the two model plants, a fresh fuel fabrication plant and a refabrication plant, are representative of current proposed commercial designs or are based on technology that is being developed to fabricate uranium, thorium, and graphite into fuel elements. The annual capacities of the fresh fuel plant and the refabrication plant are 450 and 245 metric tons of heavy metal (where heavy metal is uranium plus thorium), as charged to about fifty 1000-MW(e) HTGRs. Additional radwaste treatment systems are added to the base case plants in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The capital and annual costs for the added waste treatment operations and the corresponding reductions in dose commitments are calculated for each case. In the final analysis, the cost/benefit of each case, calculated as additional cost of radwaste system divided by the reduction in dose commitment, is tabulated or the dose commitment is plotted with cost as the variable. The status of each of the radwaste treatment methods is discussed. 48 figures, 74 tables

  6. Radioactive waste management - with evidence

    International Nuclear Information System (INIS)

    1988-01-01

    The select committee was appointed to report on the present (1988) situation and future prospects in the field of radioactive waste management in the European Community. The report covers all aspects of the subject. After an introduction the parts of the report are concerned with the control of radiation hazards, the nuclear fuel cycle and radioactive waste, the control of radioactive effluents, storage and disposal of solid radioactive wastes, research programmes, surface storage versus deep geological disposal of long-term wastes, the future of reprocessing and the public debate. Part 10 is a resume of the main conclusions and recommendations. It is recommended that the House of Lords debate the issue. The oral and written evidence presented to the committee is included in the report. (U.K.)

  7. The use of magnetite for decontaminating alpha containing effluents

    International Nuclear Information System (INIS)

    Ivens, R.

    1988-06-01

    The feasibility of retention of precipitated magnetite by magnetic filtration followed by direct cementation offered an attractive alternative to conventional ferric hydroxide treatment of radioactive liquid effluents. The magnetically-assisted dewatering of laboratory-prepared magnetite was examined in a number of ways, none of which achieved the desired optimum solids content for cementation. Attempts to prepare magnetite in situ from typical effluents containing iron were unsuccessful owing to the presence of interfering ions. Preformed magnetite was reasonably effective at absorbing actinides from solution but did not appear to offer any significant advantage over ferric hydroxide. (author)

  8. Airborne effluent control for LMFBR fuel reprocessing plants

    International Nuclear Information System (INIS)

    Yarbro, O.O.; Groenier, W.S.; Stephenson, M.J.

    1976-01-01

    A significant part of the LMFBR fuel reprocessing development program has been devoted to the development of efficient removal systems for the volatile fission products, including 131 I, krypton, tritium, 129 I, and most recently 14 C. Flowsheet studies have indicated that very significant reductions of radioactive effluents can be achieved by integrating advanced effluent control systems with new concepts of containment and ventilation; however, the feasibility of such has not yet been established, nor have the economics been examined. This paper presents a flowsheet for the application of advanced containment systems to the processing of LMFBR fuels and summarizes the status and applicability of specific fission product removal systems

  9. Using radioactivity

    International Nuclear Information System (INIS)

    1982-10-01

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

  10. Radioactive aerosols

    International Nuclear Information System (INIS)

    Chamberlain, A.C.

    1991-01-01

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

  11. Estimative of dilution factor for radioactive liquid effluents employing the H-3 and Cs-137 radiotracers present as pollutant; Estimativa do fator de diluicao para efluentes radioativos liquidos empregando os radiotracadores H-3 e Cs-137 presentes como poluentes

    Energy Technology Data Exchange (ETDEWEB)

    Nisti, Marcelo Bessa; Santos, Adir Janete Godoy dos, E-mail: mbnisti@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    It was estimated the dilution factor for liquid effluents at the discharge points of the IPEN, Sao Paulo, Brazil, employing as radiotracers the radioisotope routinely liberated for the sewage of 'Cidade Universitaria Armando de Salles Oliveira' - CUASO {sup 3}H and {sup 137}Cs, not generating either monetary or environmental cost associated to the estimation. The {sup 137}Cs was determined by gamma spectrometry and the {sup 3}H was determined liquid phase scintillation. The results showed that the dilution factor varied according to the employed radiotracer in a crescent order of {sup 3}H and {sup 137}Cs according to the characteristics of each element. The average of dilution factors obtained at the first and second liberation day were 4.3 and 7.4 respectively for the {sup 3}H and 6.2 and 13.9 for the {sup 137}Cs. The ratio of dilution factors of calculated {sup 3}H and {sup 137}Cs were coherent with the ratio verified at the twelve hydrometers distributed by the IPEN campus. The dilution factors were estimated in operational and laboratory study, in a single controlled discharge of the TR1 tank

  12. Separation of tritium from aqueous effluents

    International Nuclear Information System (INIS)

    Geens, L.; Bruggeman, A.; Meynendonckx, L.; Parmentier, C.; Belien, H.; Ooms, E.; Smets, D.; Stevens, J.; van Vlerken, J.

    1988-01-01

    From 1975 until 1982 - within the framework of the CEC indirect action programme on management and storage of radioactive waste - the SCK/CEN has developed the ELEX process from laboratory scale experiments up to the construction of an integrated pilot installation. The ELEX process combines water electrolysis and catalytical isotope exchange for the separation of tritium from aqueous reprocessing effluents by isotope enrichment. Consequently, the pilot installation consists of two main parts: an 80 kW water electrolyser and a 10 cm diameter trickle bed exchange column. The feed rate of tritiated water amounts to 5 dm 3 .h -1 , containing up to 3.7 GBq.dm -3 of tritium. This report describes the further development of the process during the second phase of the second programme. Three main items are reported: (i) research work in the field of pretreatment of real reprocessing effluents, before feeding them to an ELEX installation; (ii) demonstration of the technical feasibility of the ELEX process with simulated active effluent streams in the pilot installation; (iii) a cost estimation for the ELEX installation, comprising the required investments and the annual operation costs

  13. Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

    International Nuclear Information System (INIS)

    Shields, K.D.; Ballinger, M.Y.

    1999-03-01

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities

  14. Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Shields, K.D.; Ballinger, M.Y.

    1999-04-02

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities.

  15. Richards Bay effluent pipeline

    CSIR Research Space (South Africa)

    Lord, DA

    1986-07-01

    Full Text Available of major concern identified in the effluent are the large volume of byproduct calcium sulphate (phosphogypsum) which would smother marine life, high concentrations of fluoride highly toxic to marine life, heavy metals, chlorinated organic material... ........................ 9 THE RICHARDS BAY PIPELINE ........................................ 16 Environmental considerations ................................... 16 - Phosphogypsum disposal ................................... 16 - Effects of fluoride on locally occurring...

  16. Liquid effluent at Dounreay

    International Nuclear Information System (INIS)

    Sinclair, N.R.

    1995-01-01

    This short paper reviews the liquid effluent treatment at the Dounreay site. The significant reductions in volume and activity discharged from the site to the environment have been achieved over the many years of operation, and some of the techniques are highlighted. The Regulator interaction and the effect on the environment is discussed, while some of the requirements of the Regulator are presented. (author)

  17. System requirements for a computerised patient record information system at a busy primary health care clinic

    Directory of Open Access Journals (Sweden)

    PJ Blignaut

    2001-09-01

    Full Text Available A prototyping approach was used to determine the essential system requirements of a computerised patient record information system for a typical township primary health care clinic. A pilot clinic was identified and the existing manual system and business processes in this clinic was studied intensively before the first prototype was implemented. Interviews with users, incidental observations and analysis of actual data entered were used as primary techniques to refine the prototype system iteratively until a system with an acceptable data set and adequate functionalities were in place. Several non-functional and user-related requirements were also discovered during the prototyping period.

  18. Cauda equina syndrome complicating ankylosing spondylitis: use of electromyography and computerised tomography in diagnosis.

    Science.gov (United States)

    Young, A; Dixon, A; Getty, J; Renton, P; Vacher, H

    1981-06-01

    A case of the cauda equina syndrome complicating ankylosing spondylitis (AS) is described. An unusual feature of this case was the relapsing and remitting nature of the condition, but there is sufficient evidence to explain the clinical picture on the basis of a recurrent intraspinal inflammatory process. The clinical and radiological features are similar to those of a further 28 reported in the literature. An electromyogram (EMG) proved important in defining the extent of neurological involvement. Computerised tomography (CT) showed marked laminar erosion and no bony exit foramen encroachment. We believe that the clinical diagnosis of this condition can be adequately confirmed with plain radiology, EMG, and CT scan.

  19. Measurement of environmental radioactivity. Ispra 1977

    International Nuclear Information System (INIS)

    Dominici, G.

    1979-01-01

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

  20. Environmental radioactivity. Ispra 1973-1974

    International Nuclear Information System (INIS)

    Dominici, G.

    1976-01-01

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

  1. Measurements of environmental radioactivity, Ispra 1988

    International Nuclear Information System (INIS)

    Dominici, G.

    1989-01-01

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

  2. Measurement of environmental radioactivity. Ispra 1976

    International Nuclear Information System (INIS)

    Dominici, G.

    1977-01-01

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

  3. The choice of sites considered with respect to problems of radioactive waste disposal; Le choix des sites considere dans ses rapports avec les problemes de rejets d'effluents radioactifs

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    The author of this article shows clearly that a knowledge of the behaviour of wastes together with an analysis of the risks of accidents makes it possible to define the general characteristics of a site as a function of, on the one hand the geological and meteorological factors, and on the other, the proposed installations. Consideration of the biological environment makes it possible to clarify the sitological study and to make a choice between the several sites possible. The author shows the real necessity for radio-protection specialists to share their knowledge, to establish regulations, and to cooperate with the authors responsible for the installations, from the moment of the choice of the site and of the planning of the apparatus up to the final reject of the waste. (author) [French] L'auteur de ce rapport montre clairement que la connaissance du comportement des effluents jointe a l'analyse des risques d'accident permettent de degager les caracteristiques generales d'un site en fonction d'une part, des donnees geologiques et meteorologiques, d'autre part des installations projetees. La consideration du milieu biologique permet de preciser l'etude sitologique et d'effectuer un choix entre plusieurs sites donnes. L'auteur met en evidence la necessite absolue pour les specialistes de la radioprotection d'echanger leurs connaissances, d'etablir des reglements et de cooperer avec les autorites responsables des installations depuis le choix des sites et le projet des appareillages jusqu'au rejet ultime des residus. (auteur)

  4. The integration of computerised accounting in the accounting curriculum as an educational learning curve for students entering the business world

    Directory of Open Access Journals (Sweden)

    Elmarie Papageorgiou

    2014-06-01

    Full Text Available At universities, educating students on real-life practices is one of the key drivers in a changing academic environment. Academic institutions encourage the study of the learning environment and ensure that appropriate strategies are in place for educating students. A first-year Accounting I student stated the importance of computerised accounting: ‘Computerised accounting is used in the workplace and therefore using it in varsity, grants students a view on how things will be after completion of their respective degrees.’ Accordingly, the purpose of this study was to empirically investigate the perceived acquisition of information technology (IT knowledge and determine the skills required for students to convert the knowledge gained into actions as a learning curve for accounting students entering the business world. The results indicated that students’ knowledge of Accounting I increased with the integration of computerised Accounting in the Accounting I Curriculum.

  5. Radiation protection at the RA Reactor in 1995, Part -2, Annex 2, Decontamination and actions, collection of liquid effluents and solid radioactive waste; Deo 2 - Prilog 2 - Dekontaminacija i intervencije, skupljanje tecnih efluenata i cvrstih radioaktivnih otpadnih materijala

    Energy Technology Data Exchange (ETDEWEB)

    Mandic, M; Vukovic, Z; Lazic, S; Plecas, I; Voko, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1995-12-01

    Certain amount of solid waste results from RA reactor operation, the mean quantity of which depends on the duration of reactor operation and related activities. During repair, when reactor is not operated as well under accidental conditions, the quantity of waste is higher, dependent on the type of repair and comprehensiveness of decontamination of the working surface, contaminated tools and components. The waste is sorted and packed on the spot where they appeared according to the existing regulations and principles of radiation protection with aim to minimize unnecessary exposure of the radiation protection personnel who deals with control, transport, radioactive waste treatment and decontamination. During exceptional operations (decontamination, repair, bigger volume of contaminated material, etc.) professional staff of the Radiation protection department gives recommendations and helps in planning the actions related to repair, sorting and packaging of radioactive waste in special containers, identification of the contaminants, etc. [Serbo-Croat] Tokom rada reaktora RA dolazi do stvaranja odredjenih cvrstih otpadnih materijala cija prosecna kolicina zavisi od vremena rada reaktora i aktivnosti koje se tamo obavljaju. Tokom remonta, kada reaktor ne radi kao i pri akcidentalnim situacijama nastaju vece kolicine otpadnih materijala koje zavise od obima i vrste remontnih operacija i obima dekontaminacije kontaminirane radne povrsine i kontaminiranog alata, predmeta, opreme, itd. Nastali otpadni materijali se razvrstavaju i pakuju na mestu nastanka prema odgovarajucim propisima u skladu sa principima zastite od zracenja i aspekta bezbednosti u cilju minimiziranja nepotrebnog ozracivanja ljudstva za preuzimanje, kontrolu, transport, naknadnu obradu RAO i dekontaminaciju. Pri nerutinskim operacijama (dekontaminacija, remont, kontaminiarni otpadni materijal velike zapremine i sl.), strucna sluzba Institita ZASTITA pruza strucne konsultacije i pomaze pri planiranju

  6. Clinical and cost-effectiveness of computerised cognitive behavioural therapy for depression in primary care: Design of a randomised trial

    Directory of Open Access Journals (Sweden)

    Severens Johan L

    2008-06-01

    Full Text Available Abstract Background Major depression is a common mental health problem in the general population, associated with a substantial impact on quality of life and societal costs. However, many depressed patients in primary care do not receive the care they need. Reason for this is that pharmacotherapy is only effective in severely depressed patients and psychological treatments in primary care are scarce and costly. A more feasible treatment in primary care might be computerised cognitive behavioural therapy. This can be a self-help computer program based on the principles of cognitive behavioural therapy. Although previous studies suggest that computerised cognitive behavioural therapy is effective, more research is necessary. Therefore, the objective of the current study is to evaluate the (cost- effectiveness of online computerised cognitive behavioural therapy for depression in primary care. Methods/Design In a randomised trial we will compare (a computerised cognitive behavioural therapy with (b treatment as usual by a GP, and (c computerised cognitive behavioural therapy in combination with usual GP care. Three hundred mild to moderately depressed patients (aged 18–65 will be recruited in the general population by means of a large-scale Internet-based screening (N = 200,000. Patients will be randomly allocated to one of the three treatment groups. Primary outcome measure of the clinical evaluation is the severity of depression. Other outcomes include psychological distress, social functioning, and dysfunctional beliefs. The economic evaluation will be performed from a societal perspective, in which all costs will be related to clinical effectiveness and health-related quality of life. All outcome assessments will take place on the Internet at baseline, two, three, six, nine, and twelve months. Costs are measured on a monthly basis. A time horizon of one year will be used without long-term extrapolation of either costs or quality of life

  7. The SMile Card: a computerised data card for multiple sclerosis patients. SMile Card Scientific Board.

    Science.gov (United States)

    Mancardi, G L; Uccelli, M M; Sonnati, M; Comi, G; Milanese, C; De Vincentiis, A; Battaglia, M A

    2000-04-01

    The SMile Card was developed as a means for computerising clinical information for the purpose of transferability, accessibility, standardisation and compilation of a national database of demographic and clinical information about multiple sclerosis (MS) patients. In many European countries, centres for MS are organised independently from one another making collaboration, consultation and patient referral complicated. Only the more highly advanced clinical centres, generally located in large urban areas, have had the possibility to utilise technical possibilities for improving the organisation of patient clinical and research information, although independently from other centres. The information system, developed utilising the Visual Basic language for Microsoft Windows 95, stores information via a 'smart card' in a database which is initiated and updated utilising a microprocessor, located at each neurological clinic. The SMile Card, currently being tested in Italy, permits patients to carry with them all relevant medical information without limitations. Neurologists are able to access and update, via the microprocessor, the patient's entire medical history and MS-related information, including the complete neurological examination and laboratory test results. The SMile Card provides MS patients and neurologists with a complete computerised archive of clinical information which is accessible throughout the country. In addition, data from the SMile Card system can be exported to other database programs.

  8. Voltametric study of formic and dihydroxy malonic acids on platinum for the definition of a process for the electrolytic destruction of carboxylic acids in radioactive aqueous effluents; Etude voltamperometrique des acides formiques et dihydroxymalonique sur platine en vue de la definition d`un procede de destruction electrolytique d`acides carboxyliques d`effluents aqueux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Le Naour, C.

    1994-05-01

    To limit the amount of nuclear glasses generated by the treatment of the degraded solvent from the PUREX process for reprocessing of nuclear fuels, by solutions of sodium carbonate and caustic soda, it is planned to exploit the complexing power of certain carboxylic acids to return the metallic cations to the aqueous phase. The concept of this new treatment of the solvent by `substitution` reagents demands a process for the decomposition of these reagents, especially to CO{sub 2}. The investigation of the electrochemical behaviour, on platinum, of a substance selected as a model for understanding the interfacial mechanisms (HCOOH), and of dihydroxy malonic acid, revealed two distinct electro-poisoning processes: one is due to the adsorption of CO on the surface sites of platinum, and the second to the formation of a passivating layer of P{dagger}O. The application of 20 kHz ultrasonic flux in the neighbourhood of the platinum / aqueous formic acid solution interface also appears to cause a change in the superficial structure of the electrode used, in a direction that favours the decomposition of this compound. To overcome problems of poisoning of the platinum surface, aqueous solutions of formic, dihydroxy malonic and oxalic acids were electrolysed, in a cell without diaphragm, by applying voltage and current ranges, at levels adapted to each of the species. It is necessary to bring the working electrode to a higher potential than the oxidation potential for formic acid, and to a lower potential for dihydroxy malonic and oxalic acids. The frequent modifications of the electrode potentials helped to achieve quantitative destruction of these species, to CO{sub 2} (and to water) with an electrochemical efficiency approaching 100 %. This wet oxidation process also offers the advantage of not raising the energy potential of the effluents to be treated, because it takes place in mild conditions (ambient temperature and pressure). (author). 131 refs., 90 figs., 48 tabs.

  9. Disposal of the radioactive effluents at the 'Commissariat a l'Energie Atomique'. Treatment leading to evacuation into a river; Probleme du rejet des residus radioactifs liquides au CEA. Traitements aboutissant a des rejets en riviere

    Energy Technology Data Exchange (ETDEWEB)

    Duhamel; Menoux; Candillon [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The problems dealing with the treatment of the radioactive effluents at the 'Commissariat a l'Energie Atomique' have been studied in order to allow evacuation into a river - after treatment - with respect for the standards regarding radiation protection. 2) At Saclay where there is no possibility of evacuating the effluents, the liquids are directed towards Fontenay-aux-Roses by means of tank wagons. They are removed temporarily into the sewers and will be evacuated later on into the Seine. 3) ln Le Bouchet, the effluents coming from the Factory where urano-thorianite ore is treated will undergo a two stages treatment. The elimination of radium in the first phase facilitates decontamination in the second phase. 4) In Marcoule: a study of synthetic effluents of the Marcoule type is being carried on in order to perfect a selective elimination method of Sr{sup 90} and Cs{sup 137} by coprecipitation. 5) In the general case of the final evacuation into a river, the following problems have been studied: - pre-dilution of treated waters between the storing tanks and the river; - admission in the river; dilution in the river (preliminary study by means of a tracer); - evolution of the activity in the water of the river (adsorption by inert or living elements), contamination of the banks; - locating of the site; - isotopic dilution. 6) Circumstantial study of that last problem. 7) The quantity of a given product in water conditions the isotopic dilution of its radioactive isotopes. When the analysis shows the lack of an element, stable isotopes should be added in order to compensate it. 8) That method led to difficult analysis (specially as far as Sr{sup 90} is concerned), for the percentage of stable isotopes necessary to an important isotopic dilution is very low. 9) The standard regarding the quantity of Sr{sup 90} in drinking water is 8.10{sup -8} c/m{sup 3} or 4.10{sup -10} g/m{sup 3}. So a percentage of 40 {mu}g/litre of Sr is enough which is difficult

  10. Radiological protection. Radioactivity and health. 4. rev. ed.

    International Nuclear Information System (INIS)

    Borsch, P.; Feinendegen, L.; Paschke, M.; Feldmann, A.

    1991-12-01

    The brochure tries to make understandable also for nonprofessionals the conncetion between radioactivity and health. After briefly discussing the foundations of radioactivity, radiation emanating from radioactive materials, and the terms of dose, it deals with natural and man-made exposure of man in the age of industry. Its effects on man are thoroughly considered with regard to possible health injuries and genotype changes. The explanation of radioecological correlations, from radioactive effluents from nuclear installations to the determination of radiation exposure of man, takes into account effluents during normal operation and effluents caused by accidents, giving as an example the Chernobyl reactor accident. It is supplemented by describing the risks involved in the application of ionizing radiation in medicine. Subsequent chapters reflect the results obtained in many years of research into questions of radiation hazards, and they are to contribute to a matter-of-fact information about this important area. A comprehensive bibliography facilitates access to specialized literature. (orig.) [de

  11. Facility effluent monitoring plan for the uranium trioxide facility

    International Nuclear Information System (INIS)

    Thompson, R.J.; Sontag, S.

    1991-11-01

    A facility effluent monitoring plant is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The UO 3 Plant is located in the south-central portion of the 200 West Area of the Hanford Site. The plant consists of two primary processing buildings and several ancillary facilities. The purpose of the UO 3 Plant is to receive uranyl nitrate hexahydrate (UNH) from the Plutonium-Uranium Extraction (PUREX) Plant, concentrate it, convert the UNH to uranium trioxide (UO 3 ) powder by calcination and package it for offsite shipment. The UO 3 Plant has been placed in a standby mode. There are two liquid discharges, and three gaseous exhaust stacks, and seven building exhausters that are active during standby conditions

  12. Facility effluent monitoring plan for the tank farms facilities

    International Nuclear Information System (INIS)

    Crummel, G.M.; Gustavson, R.D.; Kenoyer, J.L.; Moeller, M.P.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum three years. A variety of liquid wastes are generated in processing treatment, and disposal operations throughout the Hanford Site. The Tank Farms Project serves a major role in Hanford Site waste management activities as the temporary repository for these wastes. Stored wastes include hazardous components regulated under the Resource Conservation and Recovery Act of 1976 (RCRA) and as by-product material regulated under the Atomic Energy Act of 1954. A total of 177 single- and double-shell tanks (SST and DST) have been constructed in the 200 East and 200 West Areas of the Hanford Site. These facilities were constructed to various designs from 1943 to 1986. The Tank Farms Project is comprised of these tanks along with various transfer, receiving, and treatment facilities

  13. Dose apportionment using statistical modeling of the effluent release

    International Nuclear Information System (INIS)

    Datta, D.

    2011-01-01

    Nuclear power plants are always operated under the guidelines stipulated by the regulatory body. These guidelines basically contain the technical specifications of the specific power plant and provide the knowledge of the discharge limit of the radioactive effluent into the environment through atmospheric and aquatic route. However, operational constraints sometimes may violate the technical specification due to which there may be a failure to satisfy the stipulated dose apportioned to that plant. In a site having multi facilities sum total of the dose apportioned to all the facilities should be constrained to 1 mSv/year to the members of the public. Dose apportionment scheme basically stipulates the limit of the gaseous and liquid effluent released into the environment. Existing methodology of dose apportionment is subjective in nature that may result the discharge limit of the effluent in atmospheric and aquatic route in an adhoc manner. Appropriate scientific basis for dose apportionment is always preferable rather than judicial basis from the point of harmonization of establishing the dose apportionment. This paper presents an attempt of establishing the discharge limit of the gaseous and liquid effluent first on the basis of the existing value of the release of the same. Existing release data for a few years (for example 10 years) for any nuclear power station have taken into consideration. Bootstrap, a resampling technique, has been adopted on this data sets to generate the population which subsequently provide the corresponding population distribution of the effluent release. Cumulative distribution of the population distribution obtained is constructed and using this cumulative distribution, 95th percentile (upper bound) of the discharge limit of the radioactive effluents is computed. Dose apportioned for a facility is evaluated using this estimated upper bound of the release limit. Paper describes the detail of the bootstrap method in evaluating the

  14. The Winfrith effluent pipeline

    International Nuclear Information System (INIS)

    Palmer, G.H.

    1959-11-01

    The paper describes the preparatory work leading up to the design of the Winfrith pipeline. Details of the existing system are given and some information on the predicted safe levels of radio-active discharge. (author)

  15. Tritium effluent removal system

    International Nuclear Information System (INIS)

    Lamberger, P.H.; Gibbs, G.E.

    1978-01-01

    An air detritiation system has been developed and is in routine use for removing tritium and tritiated compounds from glovebox effluent streams before they are released to the atmosphere. The system is also used, in combination with temporary enclosures, to contain and decontaminate airborne releases resulting from the opening of tritium containment systems during maintenance and repair operations. This detritiation system, which services all the tritium handling areas at Mound Facility, has played an important role in reducing effluents and maintaining them at 2 percent of the level of 8 y ago. The system has a capacity of 1.7 m 3 /min and has operated around the clock for several years. A refrigerated in-line filtration system removes water, mercury, or pump oil and other organics from gaseous waste streams. The filtered waste stream is then heated and passed through two different types of oxidizing beds; the resulting tritiated water is collected on molecular sieve dryer beds. Liquids obtained from regenerating the dryers and from the refrigerated filtration system are collected and transferred to a waste solidification and packaging station. Component redundancy and by-pass capabilities ensure uninterrupted system operation during maintenance. When processing capacity is exceeded, an evacuated storage tank of 45 m 3 is automatically opened to the inlet side of the system. The gaseous effluent from the system is monitored for tritium content and recycled or released directly to the stack. The average release is less than 1 Ci/day. The tritium effluent can be reduced by isotopically swamping the tritium; this is accomplished by adding hydrogen prior to the oxidizer beds, or by adding water to the stream between the two final dryer beds

  16. A Solution for the Storage of Radioactive Sludge in the Ground at Marcoule

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, P.; Gailledreau, C. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a L' Energie Atomique, Saclay (France)

    1960-07-01

    This paper deals with radioactive sludge from the radioactive effluents of the plant at Marcoule. The sludge is stored in drums, and the authors have investigated the hazard created at Marcoule by the seepage of this radioactive sludge through the soil with the gradual deterioration of the drums. This economic solution may be applicable in certain cases. (author)

  17. Radioactive waste: the Nuclear Industry's response to the Environment Committee's report

    International Nuclear Information System (INIS)

    1986-07-01

    This paper represents the nuclear industry's response to the Environmental Committee's report on the handling and disposal of radioactive wastes. Topics covered include the historical aspects of the management of radioactive wastes, technical problems, comparisons with overseas management methods, liquid effluents, reprocessing problems, and public attitudes and perceptions of radioactive waste. Responses to the Environmental Committee's recommendations form an appendix. (U.K.)

  18. Zero effluent; Efluente zero

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Silvio Rogerio; Santos, Angelo Francisco dos [Liquigas Distribuidora S.A., Sao Paulo, SP (Brazil)

    2008-07-01

    A scenery of water shortage and the search for profitability improvement obligate the companies to exercise their creativity and to adopt alternative methods to the conventional ones to preserve the environmental resources. The 'Effluent Zero' project comes from a paradigms changing that the environmental preservation is a necessary cost. It brings a new analysis approach of this problem with the purpose to adapt the investments and operational costs with the effluents treatment to the demands of the productive processes. In Liquigas, the project brought significant results; made a potential reduction of nearly 90% in the investments of the effluents treatment systems. That means nearly 13% in reduction in the total investments in modernization and upgrade of the existents companies installations and of 1,6% in the total operational costs of the Company. Further more, it has contributed for a reduction of until 43% of the water consumption in the bottling process of the Liquefied Petroleum Gas (LPG). This way, the project resulted in effective actions of environmental protection with relevant economic benefits. (author)

  19. Radioactive source

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  20. Facility Effluent Monitoring Plan for the 284-E and 284-W power plants

    International Nuclear Information System (INIS)

    Herman, D.R.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The 284-E and 284-W Power Plants are coal-fired plants used to generate steam. Electricity is not generated at these facilities. The maximum production of steam is approximately 159 t (175 tons)/h at 101 kg (225 lb)/in 2 . Steam generated at these facilities is used in other process facilities (i. e., the B Plant, Plutonium-Uranium Extraction Plant, 242-A Evaporator) for heating and process operations. The functions or processes associated with these facilities do not have the potential to generate radioactive airborne effluents or radioactive liquid effluents, therefore, radiation monitoring equipment is not used on the discharge of these streams. The functions or processes associated with the production of steam result in the use, storage, management and disposal of hazardous materials

  1. Radioactivity metrology

    International Nuclear Information System (INIS)

    Legrand, J.

    1979-01-01

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

  2. Radioactive wastes

    International Nuclear Information System (INIS)

    Teillac, J.

    1988-01-01

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

  3. Disposal of Low-Activity Liquid Effluents by Dilution

    Energy Technology Data Exchange (ETDEWEB)

    Bovard, P.; Candillon, C. [Atomic Energy Commission, Saclay (France)

    1960-07-01

    Nuclear centres are frequently faced with problems of disposal of sizeable quantities of low-activity liquid effluents. Under present conditions the most practicable solution seems to be to discharge them into a natural or artificial water system, so as to dilute them as much as possible and thus reduce their radioactive isotope content below the public health levels. This technique is employed by all nuclear centres in France, which use the following convenient outlets: Saclay: the artificial ponds made by Louis XIV to feed the great Versailles fountains; Fontenay-aux-Roses: the Paris sewer system; Grenoble: the river Isere; Marcoule: the river Rhone. Until 1957 the amount of waste was negligible. It is still very slight at the first three centres, only a few dozen millicuries a month. At Marcoule the activity of the effluents is somewhat greater, but the Rhone's rate of flow ensures a very low final content of radioactive elements. The increasing discharge of wastes into river systems calls for a close watch on changes in radioactivity in the environment (i.e. in air, water and soil), and especially on areas in which radioactive isotopes may accumulate. We have therefore made laboratory studies of the mechanics of radioactivity concentration, in order to improve our sampling methods and ascertain the movement of wastes.

  4. The Radioactive Waste Management at Studsvik

    Energy Technology Data Exchange (ETDEWEB)

    Hedlund, R; Lindskog, A

    1966-04-15

    The report was originally prepared as a contribution to the discussions in an IAEA panel on economics of radioactive waste management held in Vienna from 13 - 17 December 1965. It contains the answers and comments to the questions of a questionnaire for the panel concerning the various operations associated with the management (collection, transport, treatment, discharge, storage, and operational monitoring) of: - radioactive liquid wastes, except high-level effluents from reactor fuel recovering operations; - solid wastes, except those produced from treatment of high level wastes; - gaseous wastes produced from treatment of the foregoing liquid and solid wastes; - equipment decontamination facilities and radioactive laundries.

  5. The Radioactive Waste Management at Studsvik

    International Nuclear Information System (INIS)

    Hedlund, R.; Lindskog, A.

    1966-04-01

    The report was originally prepared as a contribution to the discussions in an IAEA panel on economics of radioactive waste management held in Vienna from 13 - 17 December 1965. It contains the answers and comments to the questions of a questionnaire for the panel concerning the various operations associated with the management (collection, transport, treatment, discharge, storage, and operational monitoring) of: - radioactive liquid wastes, except high-level effluents from reactor fuel recovering operations; - solid wastes, except those produced from treatment of high level wastes; - gaseous wastes produced from treatment of the foregoing liquid and solid wastes; - equipment decontamination facilities and radioactive laundries

  6. The puzzle of nuclear wastes. Radioactive threat to your health..

    International Nuclear Information System (INIS)

    2007-01-01

    This document, published by the French association 'Sortir du nucleaire' (Get out of nuclear), gives some information on what is radioactivity, the radioactive materials as a risk for living organisms, nuclear wastes all over France (list and map of the storage sites, power plants and fuel cycle centers), nuclear wastes at every step of the nuclear connection, the insolvable problem of high activity wastes, burying nuclear wastes in order to better forget them, radioactivity as a time bomb for our health, radioactive effluents as an under-estimated risk, artificial radioactivity already responsible for the death of 61 million people in the world, and so on

  7. Treatment and processing of the effluents and wastes (other than fuel) produced by a 900 MWe nuclear power plant

    International Nuclear Information System (INIS)

    Giraud

    1983-01-01

    Effluents produced by a 900 MWe power plant, are of three sorts: gaseous, liquid and solid. According to their nature, effluents are either released or stored for decaying before being released to the atmosphere. The non-contaminated reactor coolant effluents are purified (filtration, gas stripping) and treated by evaporation for reuse. Depending upon their radioactive level, liquid waste is either treated by evaporation or discharged after filtration. Solid waste issuing from previous treatments (concentrates, resins, filters) is processed in concrete drums using an encapsulation process. The concrete drum provides biological self-protection consistent with the national and international regulations pertaining to the transport of radioactive substance. Finally, the various low-level radioactive solid waste collected throughout the plant, is compacted into metal drums. Annual estimates of the quantity of effluents (gaseous, liquid) released in the environment and the number of drums (concrete, metal) produced by the plant figure in the conclusion

  8. Radioactive battery

    International Nuclear Information System (INIS)

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

    1975-01-01

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

  9. Effectiveness of a computerised assessment tool to prompt individuals with diabetes to be more active in consultations

    DEFF Research Database (Denmark)

    Barnard, Katharine D.; Cradock, Sue; Parkin, Tracy

    2007-01-01

    The objective of this study was to assess whether using a computerised touch screen assessment tool prior to outpatient consultation makes patients more active in the consultation. In a non-randomised control group design, immediately after consultations, which were recorded, patients and profess...

  10. Clinical effectiveness of online computerised cognitive-behavioural therapy without support for depression in primary care: randomised trial

    NARCIS (Netherlands)

    de Graaf, L.E.; Gerhards, S.A.H.; Arntz, A.; Riper, H.; Metsemakers, J.F.M.; Evers, S.M.; Severens, J.L.; Widdershoven, G.A.M.; Huibers, M.J.H.

    2009-01-01

    BACKGROUND: Computerised cognitive-behavioural therapy (CCBT) might offer a solution to the current undertreatment of depression. AIMS: To determine the clinical effectiveness of online, unsupported CCBT for depression in primary care. METHOD: Three hundred and three people with depression were

  11. Re-evaluation of Magnetic Resonance and Computerised Tomographic Imaging in Neuro-Ophthalmic Patients in an Academic Centre

    NARCIS (Netherlands)

    Koekoek, Clarence G. J.; Meiners, Linda C.; Pott, Jan Willem R.

    The aim of the study is to report the frequency of missed diagnoses on magnetic resonance and computerised tomographic imaging in neuro-ophthalmic patients who were referred to an academic ophthalmology department, with apparent normal imaging. The authors included all neuro-ophthalmic patients,

  12. Chapter 8. The radioactivity sector

    International Nuclear Information System (INIS)

    Conti, Robert; Debetencourt, Michel; Cregut, Andre; Grauby, Andre; Sousselier, Yves

    1980-01-01

    The object of this work is to examine the interactions between the activities of the nuclear industry (generating, transmission and distribution) and the environment, whilst showing to what extent the facilities are likely to affect it adversely and describing the measures taken to lessen the detrimental effects. The chapter dealing with radioactivity among the 'nuisance sectors' includes the following headings: natural radioactivity and the biological effects of radiation, the operation of a power station (principle, generating steam from nuclear energy, different types of reactors, safety barriers), radioactive effluents and wastes, nuclear controls and the environment, measures taken in the event of an accident occurring in a nuclear power station, the dismantling and decommissioning of power stations [fr

  13. A history of effluent releases from the Texas A and M University reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bates, E F; Neff, R D; Sandel, P S; Schoenbucher, B [Texas A and M University (United States)

    1974-07-01

    Since 1966 records of radioactive effluents releases from the Texas A and M University Research Reactor have been compiled. These data include particulate activity, noble gases, and liquid effluent releases. Particulate activity releases with half-lives greater than eight days were negligible and are not included in this presentation. Conversion from an MTR plate reactor to a TRIGA fueled reactor was completed in August 1968. Records of effluent releases of Argon-4l and liquids for the past, five years are summarized, in this presentation. These release data are compared to the current limits specified: in 10 CPR 20 and the limits appearing in proposed Appendix.

  14. Application of reverse osmosis to the treatment of liquid effluents produced by nuclear power plants

    International Nuclear Information System (INIS)

    Huet, Y.; Poulat, B.; Menjeaud, C.

    1989-01-01

    Radioactive liquid effluents generated during the operation of PWR nuclear power units are currently treated by two independent systems. The effluents from the reactor coolant system are recycled, unlike the others, which, after treatment, are released into the river or ocean that provides cooling water for the unit. The objective of the treatment of nonrecycled effluents is to separate from them as much of the radioactive particles that they contain as possible, so as to release into the environment a maximum volume of nonradioactive waste, and to be left with only a minimum volume of concentrated waste, containing most of the initial radioactivity, which must be loaded into casks for storage. Membrane-based filtration techniques, because they have excellent separation performances, can logically be used for this decontamination of the liquid effluents. Having developed its own reverse osmosis membrane, a possible application in a nuclear power plant, i.e., integration of a reverse osmosis unit into a radioactive liquid effluent treatment system is presented. (author)

  15. Silver precipitation from electrolytic effluents

    International Nuclear Information System (INIS)

    Rivera, I.; Patino, F.; Cruells, M.; Roca, A.; Vinals, J.

    2004-01-01

    The recovery of silver contained in electrolytic effluents is attractive due to its high economic value. These effluents are considered toxic wastes and it is not possible to dump them directly without any detoxification process. One of the most important way for silver recovery is the precipitation with sodium ditionite, sodium borohidride or hydrazine monohidrate. In this work, the most significant aspects related to the use of these reagents is presented. Results of silver precipitation with sodium ditionite from effluents containing thiosulfate without previous elimination of other species are also presented. silver concentration in the final effluents w <1 ppm. (Author) 15 refs

  16. The conceptual flowsheet of effluent treatment during preparing spherical fuel elements of HTR

    Energy Technology Data Exchange (ETDEWEB)

    Ying, Quan, E-mail: quanying@tsinghua.edu.cn; Xiao-tong, Chen; Bing, Liu; Gen-na, Fu; Yang, Wang; You-lin, Shao; Zhen-ming, Lu; Ya-ping, Tang; Chun-he, Tang

    2014-05-01

    High temperature gas-cooled reactor (HTR) is one of the advanced nuclear reactors owing to its inherent safety and broad applications. For HTR, one of the key components is the ceramic fuel element. During the preparation of spherical fuel elements, the radioactive effluent treatment is necessary. Referring to the current treatment technologies and methods, the conceptual flowsheet of low-level radioactive effluent treatment during preparing spherical fuel elements was established. According to the above treatment process, the uranium concentration was decreased from 200 mg/l to the level of discharged standard.

  17. Ethical issues related to computerised family medical histories in sickle cell disease: Inforare.

    Science.gov (United States)

    Franrenet, Sandra; Duchange, Nathalie; Galactéros, Fréderic; Quantin, Catherine; Cohen, Olivier; Nzouakou, Ruben; Sudraud, Sophie; Hervé, Christian; Moutel, Grégoire

    2010-10-01

    The Inforare project aims to set up a system for the sharing of clinical and familial data, in order to study how genes are related to the severity of sickle cell disease. While the computerisation of clinical records represents a valuable research goal, an ethical framework is necessary to guarantee patients' protection and their rights in this developing field. Issues relating to patient information during the Inforare study were analysed by the steering committee. Several major concerns were discussed by the committee and formalized in the patients' information letter: educating patients to aid the recruitment of family members, rules of confidentiality and the disclosure of aggregate, individual and unexpected research results. This paper presents the main issues addressed.

  18. Dosimetry and Image Quality in Control Studies in Computerised Tomography Realized to Paediatric Patients

    International Nuclear Information System (INIS)

    Hernandez, M. R.; Gamboa-deBuen, I.; Dies, P.; Rickards, J.; Ruiz, C.

    2008-01-01

    Computerised tomography (CT) is a favourite method of medical diagnosis. Its use has thus increased rapidly throughout the world, particularly in studies relating to children. However to avoid administering unnecessarily high doses of radiation to paediatric patients it is important to have correct dose reference levels to minimize risk. The research is being developed within the public health sector at the Hospital Infantil de Mexico ''Dr. Federico Gomez.'' We measured the entrance surface air kerma (K P ) in paediatric patients, during the radiological studies of control in CT (studies of head, thorax and abdomen). Phantom was used to evaluate image quality as the tomograph requires a high resolution image in order to operate at its optimum level

  19. Geospatial Data for Computerisation of Public Administration in the Czech Republic

    Science.gov (United States)

    Cada, V.; Mildorf, T.

    2011-08-01

    The main aim of the eGovernment programme in the Czech Republic is to enhance the efficiency of public administration. The Digital Map of Public Administration (DMVS) should be composed of digital orthophotographs of the Czech Republic, digital and digitised cadastral maps, digital purpose cadastral map (ÚKM) and a technical map of municipality, if available. The DMVS project is a part of computerisation of public administration in the Czech Republic. The project enhances the productivity of government administration and also simplifies the processes between citizens and public administration. The DMVS project, that should be compliant with the INSPIRE (Infrastructure for Spatial Information in the European Community) initiative, generates definite demand for geodata on the level of detail of land data model. The user needs that are clearly specified and required are not met due to inconsistencies in terminology, data management and level of detail.

  20. Micro-computerised tomography optimisation for the measurement of bone mineral density around titanium dental implants

    International Nuclear Information System (INIS)

    Park, C.; Swain, M.; Duncan, W.

    2010-01-01

    Titanium dental implants (screws) are commonly used to replace missing teeth by forming a biological union with bone ('osseointegration'). Micro-computerised tomography (μCT) may be useful for measuring bone mineral density around dental implants. Major issues arise because of various artefacts that occur with polychromatic X-rays associated bench type instruments that may compromise interpretation of the observations. In this study various approaches to minimise artefacts such as; beam hardening, filtering and edge effects are explored with a homogeneous polymeric material, Teflon, with and without an implant present. The implications of the limitations of using such polychromatic μCT systems to quantify bone mineral density adjacent to the implant are discussed. (author)

  1. Decentralised wastewater treatment effluent fertigation: preliminary ...

    African Journals Online (AJOL)

    Decentralised wastewater treatment effluent fertigation: preliminary technical assessment. ... living in informal settlements with the effluent produced being used on agricultural land. ... Banana and taro required 3 514 mm of irrigation effluent.

  2. Storage of solid and liquid radioactive material

    International Nuclear Information System (INIS)

    Matijasic, A.; Gacinovic, O.

    1961-01-01

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

  3. The conceptual flowsheet of effluent treatment during total gelation of uranium process for preparing ceramic UO2 particles of high temperature gas-cooled reactors

    International Nuclear Information System (INIS)

    Quan Ying; Chen Xiaotong; Wang Yang; Liu Bing; Tang Yaping; Tang Chunhe

    2014-01-01

    Today, more and more people pay attention to the environmental protection and ecological environment. Along with the development of nuclear industry, many radioactive effluents may be discharged into environment, which can lead to the pollutions of water, atmosphere and soil. So radioactive effluents including low-activity and medium-level wastes solution treatments have been becoming one of significant subjects. High temperature gas-cooled reactor (HTR) is one of advanced nuclear reactors owing to its reliability, security and broad application in which the fabrication of spherical fuel element is a key technology. During the production of spherical fuel elements, the radioactive effluent treatment is necessary. Referring to the current treatment technologies and methods, the conceptual flowsheet of low-level radioactive effluent treatment during preparing spherical fuel elements was summarized which met the 'Zero Emission' demand. (authors)

  4. Radioactive waste treatment apparatus

    International Nuclear Information System (INIS)

    Abrams, R.F.; Chellis, J.G.

    1983-01-01

    Radioactive waste treatment apparatus is disclosed in which the waste is burned in a controlled combustion process, the ash residue from the combustion process is removed and buried, the gaseous effluent is treated in a scrubbing solution the pH of which is maintained constant by adding an alkaline compound to the solution while concurrently extracting a portion of the scrubbing solution, called the blowdown stream. The blowdown stream is fed to the incinerator where it is evaporated and the combustibles in the blowdown stream burned and the gaseous residue sent to the scrubbing solution. Gases left after the scrubbing process are treated to remove iodides and are filtered and passed into the atmosphere

  5. Health and environment. Authorized limits for the radioactive wastes: the beginning of falling new limits

    International Nuclear Information System (INIS)

    Sorin, F.

    2000-01-01

    As a proposal of the Safety Authorities, radioactive effluents release limits, will decrease to approach the true values. Hopeful a sanitary and technological approach, this paper takes stock on this new regulation. (A.L.B.)

  6. New radioactivities

    International Nuclear Information System (INIS)

    Greiner, W.; Sandulescu, A.

    1996-01-01

    Some atomic nuclei reorganize their structure by ejection of big protons and neutrons aggregates. The observation of these new radioactivities specifies the theories of the nuclear dynamics. (authors)

  7. Radioactive materials

    International Nuclear Information System (INIS)

    Sugiura, Yoshio; Shimizu, Makoto.

    1975-01-01

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

  8. Radioactivity Handbook

    International Nuclear Information System (INIS)

    Firestone, R.B.; Browne, E.

    1985-01-01

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

  9. Study of dilution of effluent discharged through a sea outfall near Mangalore using radiotracer technique

    International Nuclear Information System (INIS)

    Eapen, A.C.; Jain, S.K.

    1987-01-01

    The fate of effluent discharged into water bodies is a matter of concern from the point of view of environmental pollution. Radiotracer techniques have been successfully used to study the change in concentration of effluents while being mixed with large water bodies. The technique used is to add a known concentration of radioactive tracer into the effluent stream and to measure the dilutions at different locations near the effluent discharge point with radiation detectors. M/s Mangalore Chemicals and Fertilizers Ltd (MCF) at Mangalore on the west coast of India disposes off the treated and initially diluted effluent at the rate of about 360 m 3 /h into the sea near by through an outfall extending about 100 meters into the sea. The effluent mainly contains ammonia in the range of 40-50 ppm as the pollutant. It was desired to measure the extent of dilution occurring to the effluent at a few locations of known distances along the sea shore from the discharge point of the effluent. Radiotracers 82 Br as ammonium bromide solution and tritium as tritiated water were employed for the study. The concentration measurement was done at site for 82 Br and by estimation of samples in the laboratory in the case of tritium. Dilution of the order of 1000 was obtained at about 100 meters distance for a continuous injection of about 4 hours. (author). 3 tables, 3 figures

  10. Removal of radium-226 from uranium mining effluents

    International Nuclear Information System (INIS)

    Averill, D.W.; Moffett, D.; Webber, R.T.; Whittle, L.; Wood, J.A.

    1984-12-01

    Uranium mining and milling operations usually generate large quantities of solid and liquid waste materials. A slurry, consisting of waste rock and chemical solutions from the milling operation, is discharged to impoundment areas (tailings basins). Most of the radioactive material dissolved in tailings slurries is precipitated by the addition of lime and limestone prior to discharge from the mill. However, the activity of one radioisotope, radium-226, remains relatively high in the tailings basin effluents. In Canada, radium-226 is removed from uranium mining and milling effluents by the addition of barium chloride to precipitate barium-radium sulphate [(Ba,Ra)SO 4 ]. Although dissolved radium-226 activities are generally reduced effectively, the process is considered to have two undesirable characteristics: the first related to suspended radium-226 in the effluents and the second to ultimate disposal of the (Ba,Ra)SO 4 sludge. A government-industry mining task force established a radioactivity sub-group in 1974 to assist in the development of effluent guidelines and regulations for the uranium mining industry (Radioactivity Sub-group, 1974). The investigation of more effective removal methods was recommended, including the development of mechanical treatment systems as alternatives to settling ponds. Environment Canada's Wastewater Technology Centre (WTC) initiated a bench scale study in March, 1976 which was designed to assess the feasibility of using precipitation, coagulation, flocculation and sedimentation for the removal of radium-226. In 1977, the study was accelerated with financial assistance from the Atomic Energy Control Board. The results were favourable, with improved radium removals obtained in bench scale batch tests using barium chloride as the precipitant and either alum or ferric chloride as the coagulant. A more comprehensive bench scale and pilot scale process development and demonstration program was formulated. The results of the joint study

  11. Radioactive wastes management in a radiochemistry laboratory

    International Nuclear Information System (INIS)

    Silva, Ana C.A.; Pereira, Wagner de S; Py Junior, Delcy de A.; Antunes, Ivan M.; Kelecom, Alphonse

    2009-01-01

    The Laboratorio de Monitoracao Ambiental (AMB) of the Unidade de Tratamento de Minerio (UTM) belonging to the Industrias Nucleares do Brasil is a chemical, radiochemical and radiometric laboratory, that analyses the natural radionuclides present in samples coming from the various installation of Industrias Nucleares do Brasil (INB). To minimize the radiological environmental impact, that laboratory has adopted a washing system of the chapel exhausting, that recirculate the washing water. These water can accumulate the radionuclides coming from the samples, that are liberated together the exhaustion gases from the chapels. Also, the water coming from the analyses and the sample releases (environmental and of the process) represent the liquid effluents of the AMB. The release of this effluent must pass by chemical and radiological criteria. From the radiological viewpoint, that release must be based on the Brazilian Nuclear Energy Commission (CNEN) regulations. This work try to establish the monitoring frequency, the radionuclides to be analysed, the form of liberation of those effluents, and the analytical techniques to be used. The radionuclides to be analysed will be U-nat, Ra-226 and Pb-210, of the uranium series, and the Th-232 and Ra-228, of the thorium series. The effluents must be monitored either before the release or, at least, twice a year. The effluents considered radioactive wastes, will be send to waste dam by the radioprotection service, or to the effluent treatment for controlled liberation for the environment

  12. Radioactive Waste Management information for 1994 and record-to-date

    International Nuclear Information System (INIS)

    French, D.L.; Lisee, D.J.; Taylor, K.A.

    1995-07-01

    This document, Radioactive Waste Management Information for 1994 and Record-To-Date, contains computerized radioactive waste data records from the Idaho National Engineering Laboratory (INEL). Data are compiled from information supplied by the US Department of Energy (DOE) contractors. Data listed are on airborne and liquid radioactive effluents and solid radioactive waste that is stored, disposed, and sent to the INEL for reduction. Data are summarized for the years 1952 through 1993. Data are detailed for the calendar year 1994

  13. Radioactivity. Centenary of radioactivity discovery

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  14. Radionuclide content of wastewater and solid waste from a low-level effluent treatment plant

    International Nuclear Information System (INIS)

    Muhamat Omar; Zalina Laili; Nik Marzukee Nik Ibrahim; Mat Bakar Mahusin

    2010-01-01

    A study on radioactivity levels of wastewater and solid waste from a Low-level Effluent Treatment Plant has been carried out. The measurement of radionuclide concentration was carried out using gamma spectrometry. Natural and anthropogenic radionuclides were detected in solid radioactive waste recovered from the treatment plant. The presence of radionuclides in waste water varies depending on activities carried out in laboratories and facilities connected to the plant. (author)

  15. Disposal of tritiated effluents

    International Nuclear Information System (INIS)

    Hartmann, K.; Bruecher, H.

    1981-06-01

    After some introductory remarks on the origin of tritium, its properties and its behaviour in a reprocessing plant three alternative methods for the disposal of tritiated effluents produced during reprocessing are described (deep well injection, in-situ solidification, deep-sea dumping) and compared with each other under various aspects. The study is based on the concept of a 1400 t/a reprocessing plant for LWR fuel, which annually produces 3000 m 3 of tritiated waste water with a tritium content of 6.5 x 10 12 Bq/m 3 as well as a residual fission product and actinide content. An assessment of the three methods under the aspects of simplicity, reliability, safety, costs, state of development and materials handling revealed advantages in favour of 'injection', followed by 'dumping' and 'in-situ solidification'. (orig./HP) [de

  16. A study of effluent control technologies employed by radiopharmaceutical users and suppliers

    International Nuclear Information System (INIS)

    Leventhal, L.; Slider, J.; Chakoff, E.; Chen, J.I.; Savage, E.

    1980-01-01

    The quantities of radiopharmaceuticals produced for in-vivo diagnostic and therapy procedures has been estimated to be growing at the rate of 16% per year, based on 1978 sales figures. Nuclear medicine facilities are experiencing an average annual growth rate of 5% per year. The principle radionuclides produced and used for nuclear medicine are 131 I, 131 Xe, and sup(9m)Tc. Of particular concern is that amount of these radionuclides which might become airborne and escape into the environment during the process of manufacture or during aliquotting or administration by hospital personnel. Therefore, a study was made of the effluent control technology employed by radiopharmaceutical suppliers and users. Generally, the means used to control airborne radioactive effluents fall into two classes according to function. The controls either dilute and direct the effluent to a specific point of release or hold up the effluent to reduce by decay the amount of radioactivity released. Radiopharmaceutical suppliers and hospitals were contacted, and a survey made of the control technology used. The classes and types of effluent control equipment and their general characteristics, cost and effectiveness were determined. It was concluded that control equipment was readily available, reliable, and effective in reducing radioactive releases from radiopharmaceutical facilities. (author)

  17. Radiation effluent suppression system

    International Nuclear Information System (INIS)

    Watanabe, Atsushi.

    1992-01-01

    In a radiation release suppression system upon accident, an electromotive valve, a pneumatic operation valve or a manual operation valve is disposed to gas ventilation pipelines which are extended from both of a dry well and a wet well of a reactor container to a stuck. In addition, a combination filter of a metal fiber filter made of stainless steel etc. and an activated carbon fiber filter is disposed in the midway of pipelines in a reactor building. With such a constitution, the inside of the container can be depressurized (prevention of ruptures) and the amount of radioactive substances released to circumstances is remarkably suppressed by the effect of radioactive substance capturing effect of the metal fiber filter made of stainless steel etc. disposed in the vent pipe in the container and a radioactive substance capturing effect by the combination filter of the metal fiber filter made of stainless steel, etc. and the activated carbon fiber filter disposed in the gas ventilation pipelines even upon occurrence of an accident exceeding design basis. Systems can be simplified and minimized, and cost down can also be attained. (N.H.)

  18. Facility Effluent Monitoring Plan for the 3720 Building

    Energy Technology Data Exchange (ETDEWEB)

    Shields, K.D.; Ballinger, M.Y.

    1999-04-02

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the Environmental Science Laboratory (3720 Facility) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs'' This FEMP has been prepared for the 3720 Facility primarily because it has a major (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The 3720 Facility provides office and laboratory space for PNNL scientific and engineering staff conducting multidisciplinary research in the areas of materials characterization and testing and waste management. The facility is designed to accommodate the use of radioactive and hazardous materials to conduct these activities. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, and dispersible particulate. The facility is in the process of being vacated for shutdown, but is considered a Major Emission Point as of the date of this document approval.

  19. Facility effluent monitoring plan for the 325 Facility

    International Nuclear Information System (INIS)

    1998-01-01

    The Applied Chemistry Laboratory (325 Facility) houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and mixed hazardous waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials, and a waste treatment facility for processing hazardous, mixed, low-level, and transuranic wastes generated by Pacific Northwest Laboratory. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, particulate, and gas. Some of these materials are also heated during testing which can produce vapors. The research activities have been assigned to the following activity designations: High-Level Hot Cell, Hazardous Waste Treatment Unit, Waste Form Development, Special Testing Projects, Chemical Process Development, Analytical Hot Cell, and Analytical Chemistry. The following summarizes the airborne and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

  20. Environmental and human exposure as a result of radioactive discharges

    International Nuclear Information System (INIS)

    2010-02-01

    Nuclear accidents can lead to the discharge of radioactive particulates, gases, and liquid effluents into the environment. Effluents are characterized by their composition, duration and by other characteristics which can influence the dispersion of radioactivity in the environment. Populations can be exposed directly or through the contamination of the terrestrial and aquatic environments. Therefore, it is necessary to take into consideration both the environmental contamination pathways and the human contamination pathways through the environment. This document summarizes these different pathways: contamination by atmospheric discharge (surface contamination, surface waters, terrestrial fauna and flora); contamination by liquid discharge; spreading of contaminated areas; human contamination pathways (external irradiation, internal contamination, skin contamination). (J.S.)

  1. TEM validation of immunohistochemical staining prior to assessment of tumour angiogenesis by computerised image analysis

    International Nuclear Information System (INIS)

    Killingsworth, M.C.

    2002-01-01

    Full text: Counts of microvessel density (MVD) within solid tumours have been shown to be an independent predictor of outcome with higher counts generally associated with a worse prognosis. These assessments are commonly performed on immunoperoxidase stained (IPX) sections with antibodies to CD34, CD31 and Factor VIII-related antigen routinely used as vascular markers. Tumour vascular density is thought to reflect the demand the growing neoplasm is placing on its feeding blood supply. Vascular density also appears to be associated with spread of invasive cells to distant sites. The present study of tumour angiogenesis in prostate cancer specimens aims to assess new vessel growth in addition to MVD counts. The hypothesis being that an assessment which takes into account vascular migration and proliferation as well as the number of patent vessels present may have improved predictive power over assessments based on MVD counts alone. We are employing anti-CD34 stained IPX sections which are digitally photographed and assessed by a computerised image analysis system. Our aim is to develop parameters whereby tumour angiogenesis may be assessed at the light microscopic level and then correlated with existing histological methods of tumour assessment such as Gleason grading. In order to use IPX stained sections for angiogenic assessment validation and understanding of the anti-CD34 immunostaining pattern was necessary. This involved the following steps: i) Morphological assessment of angiogenic changes present in tumour blood vessels. Morphological changes in endothelial cells and pericytes indicative of angiogenic activation are generally below the level of resolution available with light microscopy. TEM examination revealed endothelial cell budding, pericyte retraction, basement membrane duplication and endothelial sprout formation in capillaries and venules surrounding tumour glands. This information assisted with the development of parameters by which IPX sections

  2. Liquid Effluent Retention Facility/Effluent Treatment Facility Hazards Assessment

    International Nuclear Information System (INIS)

    Simiele, G.A.

    1994-01-01

    This document establishes the technical basis in support of Emergency Planning activities for the Liquid Effluent Retention Facility and Effluent Treatment Facility the Hanford Site. The document represents an acceptable interpretation of the implementing guidance document for DOE ORDER 5500.3A. Through this document, the technical basis for the development of facility specific Emergency Action Levels and the Emergency Planning Zone is demonstrated

  3. Computerised therapies for anxiety and depression in children and young people: a systematic review and meta-analysis.

    Science.gov (United States)

    Pennant, Mary E; Loucas, Christina E; Whittington, Craig; Creswell, Cathy; Fonagy, Peter; Fuggle, Peter; Kelvin, Raphael; Naqvi, Sabrina; Stockton, Sarah; Kendall, Tim

    2015-04-01

    One quarter of children and young people (CYP) experience anxiety and/or depression before adulthood, but treatment is sometimes unavailable or inadequate. Self-help interventions may have a role in augmenting treatment and this work aimed to systematically review the evidence for computerised anxiety and depression interventions in CYP aged 5-25 years old. Databases were searched for randomised controlled trials and 27 studies were identified. For young people (12-25 years) with risk of diagnosed anxiety disorders or depression, computerised CBT (cCBT) had positive effects for symptoms of anxiety (SMD -0.77, 95% CI -1.45 to -0.09, k = 6, N = 220) and depression (SMD -0.62, 95% CI -1.13 to -0.11, k = 7, N = 279). In a general population study of young people, there were small positive effects for anxiety (SMD -0.15, 95% CI -0.26 to -0.03; N = 1273) and depression (SMD -0.15, 95% CI -0.26 to -0.03; N = 1280). There was uncertainty around the effectiveness of cCBT in children (5-11 years). Evidence for other computerised interventions was sparse and inconclusive. Computerised CBT has potential for treating and preventing anxiety and depression in clinical and general populations of young people. Further program development and research is required to extend its use and establish its benefit in children. Copyright © 2015 Elsevier Ltd. All rights reserved.

  4. Design, implementation and functional aspects of the control and instrumentation systems of computerised remote operated sludge lancing equipment

    International Nuclear Information System (INIS)

    Aparna, J.; Mehra, K.S.; Sharma, B.S.V.G.; Mohan, L.R.

    2005-01-01

    The computerised and remote operated sludge lancing equipment (SLE) uses high velocity narrow water jets for dislodging and removal of hard and strongly adhesive sludge from the secondary side tube sheet of mushroom type steam generators of Indian PHWRs. During the years of plant operation, corrosion products and other solids deposit in the form of sludge on the tube sheet of steam generators. The sludge formation not only affects adversely the steam generator performance but also diminishes its service life if left unchecked

  5. Rehabilitation of awareness of deficits in patients with traumatic brain injury applying a user-friendly computerised intervention approach

    LENUS (Irish Health Repository)

    Morgan, Dr Jacinta

    2010-01-01

    Objective : Awareness of errors is an important prerequisite in rehabilitation. Few studies have investigated rehabilitation of error awareness following acquired brain injury. Pilot research has shown that receiving feedback about errors during a computerised task of sustained attention improves performance in patients who have sustained a traumatic brain injury. In this study, a computer-based intervention training programme aimed at improving error awareness was developed. \\r\

  6. The design, construction and implementation of a computerised trauma registry in a developing South African metropolitan trauma service.

    Science.gov (United States)

    Laing, G L; Bruce, J L; Aldous, C; Clarke, D L

    2014-01-01

    The Pietermaritzburg Metropolitan Trauma Service formerly lacked a robust computerised trauma registry. This made surgical audit difficult for the purpose of quality of care improvement and development. We aimed to design, construct and implement a computerised trauma registry within our service. Twelve months following its implementation, we sought to examine and report on the quality of the registry. Formal ethical approval to maintain a computerised trauma registry was obtained prior to undertaking any design and development. Appropriate commercial software was sourced to develop this project. The registry was designed as a flat file. A flat file is a plain text or mixed text and binary file which usually contains one record per line or physical record. Thereafter the registry file was launched onto a secure server. This provided the benefits of access security and automated backups. Registry training was provided to clients by the developer. The exercise of data capture was then integrated into the process of service delivery, taking place at the endpoint of patient care (discharge, transfer or death). Twelve months following its implementation, the compliance rates of data entry were measured. The developer of this project managed to design, construct and implement an electronic trauma registry into the service. Twelve months following its implementation the data were extracted and audited to assess the quality. A total of 2640 patient entries were captured onto the registry. Compliance rates were in the order of eighty percent and client satisfaction rates were high. A number of deficits were identified. These included the omission of weekend discharges and underreporting of deaths. The construction and implementation of the computerised trauma registry was the beginning of an endeavour to continue improvements in the quality of care within our service. The registry provided a reliable audit at twelve months post implementation. Deficits and limitations were

  7. A study of effluent control technologies employed by radiopharmaceutical users and suppliers

    International Nuclear Information System (INIS)

    Leventhal, L.; Slider, J.; Chakoff, E.; Cehn, J.I.; Savage, E.

    1980-01-01

    The radiopharmaceutical industry facilities in the U.S.A. have been reviewed to identify factors that could lead to the airborne release of radioactive isotopes, and to assess the control technology employed. The subject is dealt with in brief outline under the following headings: 1) Hospital usage, the radionuclides being grouped according to use. The main potential airborne effluents were 131 I, 133 Xe, and sup(99m)Tc. 2) Monitoring of facilities for airborne effluents. 3) Control technology, either by dilution or by storage to reduce radioactivity; suppliers and users effluent controls. It was found that the control equipment is readily available, reliable, and effective. Cost appears to increase proportionately with the dose reduction provided. NRC requirements and cost-benefit ratios determine choice. It was concluded that current practices in the industry are adequate. (U.K.)

  8. Characterization and consequences from CEA nuclear fuel cycle facilities effluents releases - 1995 up to 2007 period

    International Nuclear Information System (INIS)

    Ferreira, Nelson Luiz Dias; Fonseca, Lizandra Pereira de Souza

    2009-01-01

    Discharges to the environment of airborne and/or liquid radioactive effluents from the normal operation of nuclear facilities can become a potential source of radiation exposure to humans. The highest exposed members of the public are defined as the critical group. The requirements for the control and monitoring of radioactive discharges to the environment and the degree of environmental monitoring required are linked to the assessed critical group dose. The assessed dose can be compared to dose constraint, which is a fraction of the annual effective dose to members of the public, as well as the level of exemption specified by the National Commission for Nuclear Energy (CNEN). Effluents releases from the Centro Experimental Aramar (CEA) facilities are registered and described at CEA Effluent Report, semestrally sent to CNEN. Basically, that report provides information related to the type and the quantity of chemical and radioactive substances released to the environment due the routine operation of CEA nuclear fuel cycle facilities (LEI - Isotopic Enrichment Laboratory, USIDE - Pilot Plant for Industrial Verification of Uranium Enrichment and LABMAT - Nuclear Materials Laboratory). CEA Annual Effluent Report includes assessment of the annual effective doses for members of the critical group for the CEA site. This work presents the characterization of the radioactive release source terms and a historical of the critical group annual doses from 1995 up to 2007. (author)

  9. UNC Nuclear Industries reactor and fuels production facilities 1985 effluent release report

    International Nuclear Information System (INIS)

    Rokkan, D.J.

    1986-01-01

    Analyses of routine samples from radioactive liquid and airborne streams were performed using UNC's Radioanalytical Laboratory and the analytical services of US Testing Company. All significant effluent discharges from UNC facilities to the environment during CY 1985 are reported in this document

  10. Annual report on the effluent control of low level liquid water in Tokai Works. FY2004

    International Nuclear Information System (INIS)

    Takeishi, Minoru; Miyagawa, Naoto; Watanabe, Hitoshi

    2005-08-01

    This report was written about the effluent control of low level liquid waste in JNC Tokai Works Fiscal Year 2004, from 1st April 2004 to 31th March 2005. In this period, the quantities and concentrations of radioactivity in liquid waste from Tokai Works were under the discharge limits of 'Safety Regulations for the Tokai Reprocessing Plant' and regulations of government. (author)

  11. Radioactive Liquid Waste Treatment Facility Discharges in 2011

    Energy Technology Data Exchange (ETDEWEB)

    Del Signore, John C. [Los Alamos National Laboratory

    2012-05-16

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

  12. Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

    International Nuclear Information System (INIS)

    Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L.

    1978-10-01

    The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems

  13. Hydric effluents; Os efluentes hidricos

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This chapter gives a general overview on the general effects of the hydric pollution, the principal pollutants emitted by the oil refineries, control actions for the hydric emissions, the minimization actions, and the effluent treatment.

  14. Facility Effluent Monitoring Plan for the Spent Nuclear Fuel (SNF) Project

    International Nuclear Information System (INIS)

    HUNACEK, G.S.

    2000-01-01

    A facility effluent monitoring plan is required by the US. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document was prepared using the specific guidelines identified in Westinghouse Hanford Company (WHC)-EP-0438-1, ''A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans'', and assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the third revision to the original annual report. This document is reviewed annually even if there are no operational changes, and it is updated as necessary

  15. CEA and its radioactive wastes

    International Nuclear Information System (INIS)

    Marano, S.

    1999-01-01

    CEA annually produces about 3500 tons of radioactive wastes in its 43 basic nuclear installations. CEA ranks third behind EDF and Cogema. Low-level wastes (A wastes) are sent to ANDRA (national agency for the management of nuclear wastes)whereas medium-level wastes (B wastes) are stored by CEA itself. CEA has checked off its storing places and has set up an installation Cedra to process and store ancient and new nuclear wastes. 3 other installations are planned to operate within 6 years: Agate (Cadarache) will treat liquid effluents, Stella (Saclay) will process liquid wastes that are beta or gamma emitters, and Atena (Marcoule) will treat and store radioactive sodium coming from Phenix reactor and IPSN laboratories. The use of plasma torch for vitrifying wastes is detailed, the management of all the nuclear wastes produced by CEA laboratories and installations is presented. (A.C.)

  16. Filter case for separating out radioactive effluents from gas flows

    International Nuclear Information System (INIS)

    Jannakos, K.; Zabel, G.

    1982-01-01

    A remotely operated change of filter in a filter case can be done with an annular or cylindrical filter insert, where the contaminated air side remains separate from the clean air side. A lid is provided which can be divided into two parts, and by which the openings of the filter insert and also in the intermediate floor can be opened or closed using the double lid technique. When closing the filter case lid, the double lid closure is always opened. (DG) [de

  17. Epidemiological study of brucellosis in eight Greek villages using a Computerised Mapping Programme

    International Nuclear Information System (INIS)

    Hadjichristodoulou, Ch.; Papatheodorou, Ch.; Soteriades, E.; Panagakos, G.; Kastritis, I.; Goutziana, G.; Charvalos, E.; Tselentis, Y.

    1999-01-01

    A Computerised Mapping Programme (CMP) was created step by step to cover all the needs of a cross sectional population survey conducted in eight villages of Fokida, a rural area of central Greece. The maps of Greece (boundary) and the topographical maps of the eight villages were created using the CMP. A volunteer sample of 1121 out of 2607 inhabitants of the study area participated in the population survey. The participants were tested for brucellosis using serological tests (ELISA and Rose Bengal) and the intradermal reaction test. A questionnaire was used to obtain information concerning the risk factors for brucellosis. The risk factors found through statistical analysis were occupation (RR: 5.81, p < 0.00001), consumption of raw milk (RR: 1.98, p < 0.001) and unpasteurized fresh cheese (RR: 2.13, p < 0.01). The same factors were indicated by the CMP. The CMP also indicated manure-contaminated playgrounds in residential yards as a potential risk factor for children. The origin and dissemination were delineated using time-space association display. The CMP proved to be a useful tool in this epidemiological study

  18. Computerised cognitive-behavioural therapy for adults with intellectual disability: randomised controlled trial.

    Science.gov (United States)

    Cooney, Patricia; Jackman, Catherine; Coyle, David; O'Reilly, Gary

    2017-08-01

    Background Despite the evidence base for computer-assisted cognitive-behavioural therapy (CBT) in the general population, it has not yet been adapted for use with adults who have an intellectual disability. Aims To evaluate the utility of a CBT computer game for adults who have an intellectual disability. Method A 2 × 3 (group × time) randomised controlled trial design was used. Fifty-two adults with mild to moderate intellectual disability and anxiety or depression were randomly allocated to two groups: computerised CBT (cCBT) or psychiatric treatment as usual (TAU), and assessed at pre-treatment, post-treatment and 3-month follow-up. Forty-nine participants were included in the final analysis. Results A significant group × time interaction was observed on the primary outcome measure of anxiety (Glasgow Anxiety Scale for people with an Intellectual Disability), favouring cCBT over TAU, but not on the primary outcome measure of depression (Glasgow Depression Scale for people with a Learning Disability). A medium effect size for anxiety symptoms was observed at post-treatment and a large effect size was observed after follow-up. Reliability of Change Indices indicated that the intervention produced clinically significant change in the cCBT group in comparison with TAU. Conclusions As the first application of cCBT for adults with intellectual disability, this intervention appears to be a useful treatment option to reduce anxiety symptoms in this population. © The Royal College of Psychiatrists 2017.

  19. Computerised Analysis of Telemonitored Respiratory Sounds for Predicting Acute Exacerbations of COPD.

    Science.gov (United States)

    Fernandez-Granero, Miguel Angel; Sanchez-Morillo, Daniel; Leon-Jimenez, Antonio

    2015-10-23

    Chronic obstructive pulmonary disease (COPD) is one of the commonest causes of death in the world and poses a substantial burden on healthcare systems and patients' quality of life. The largest component of the related healthcare costs is attributable to admissions due to acute exacerbation (AECOPD). The evidence that might support the effectiveness of the telemonitoring interventions in COPD is limited partially due to the lack of useful predictors for the early detection of AECOPD. Electronic stethoscopes and computerised analyses of respiratory sounds (CARS) techniques provide an opportunity for substantial improvement in the management of respiratory diseases. This exploratory study aimed to evaluate the feasibility of using: (a) a respiratory sensor embedded in a self-tailored housing for ageing users; (b) a telehealth framework; (c) CARS and (d) machine learning techniques for the remote early detection of the AECOPD. In a 6-month pilot study, 16 patients with COPD were equipped with a home base-station and a sensor to daily record their respiratory sounds. Principal component analysis (PCA) and a support vector machine (SVM) classifier was designed to predict AECOPD. 75.8% exacerbations were early detected with an average of 5 ± 1.9 days in advance at medical attention. The proposed method could provide support to patients, physicians and healthcare systems.

  20. Development and impact of computerised decision support systems for clinical management of depression: A systematic review.

    Science.gov (United States)

    Triñanes, Yolanda; Atienza, Gerardo; Louro-González, Arturo; de-las-Heras-Liñero, Elena; Alvarez-Ariza, María; Palao, Diego J

    2015-01-01

    One of the proposals for improving clinical practice is to introduce computerised decision support systems (CDSS) and integrate these with electronic medical records. Accordingly, this study sought to systematically review evidence on the effectiveness of CDSS in the management of depression. A search was performed in Medline, EMBASE and PsycInfo, in order to do this. The quality of quantitative studies was assessed using the SIGN method, and qualitative studies using the CASPe checklist. Seven studies were identified (3 randomised clinical trials, 3 non-randomised trials, and one qualitative study). The CDSS assessed incorporated content drawn from guidelines and other evidence-based products. In general, the CDSS had a positive impact on different aspects, such as the screening and diagnosis, treatment, improvement in depressive symptoms and quality of life, and referral of patients. The use of CDSS could thus serve to optimise care of depression in various scenarios by providing recommendations based on the best evidence available and facilitating decision-making in clinical practice. Copyright © 2014 SEP y SEPB. Published by Elsevier España. All rights reserved.

  1. Computerised Analysis of Telemonitored Respiratory Sounds for Predicting Acute Exacerbations of COPD

    Directory of Open Access Journals (Sweden)

    Miguel Angel Fernandez-Granero

    2015-10-01

    Full Text Available Chronic obstructive pulmonary disease (COPD is one of the commonest causes of death in the world and poses a substantial burden on healthcare systems and patients’ quality of life. The largest component of the related healthcare costs is attributable to admissions due to acute exacerbation (AECOPD. The evidence that might support the effectiveness of the telemonitoring interventions in COPD is limited partially due to the lack of useful predictors for the early detection of AECOPD. Electronic stethoscopes and computerised analyses of respiratory sounds (CARS techniques provide an opportunity for substantial improvement in the management of respiratory diseases. This exploratory study aimed to evaluate the feasibility of using: (a a respiratory sensor embedded in a self-tailored housing for ageing users; (b a telehealth framework; (c CARS and (d machine learning techniques for the remote early detection of the AECOPD. In a 6-month pilot study, 16 patients with COPD were equipped with a home base-station and a sensor to daily record their respiratory sounds. Principal component analysis (PCA and a support vector machine (SVM classifier was designed to predict AECOPD. 75.8% exacerbations were early detected with an average of 5 ± 1.9 days in advance at medical attention. The proposed method could provide support to patients, physicians and healthcare systems.

  2. Diagnostic ranking of computerised tomography in mediastinal diseases depending on their localisation

    Energy Technology Data Exchange (ETDEWEB)

    Sommer, B.; Doppman, J.L.; Mayr, B.; Rienmueller, R.; Lissner, J.; Stelter, W.

    1981-04-01

    The diagnostic ranking and importance of computerised tomography was examined in 116 with abnormal findings in the mediastinal region, and was compared with conventional, non-invasive X-ray examinations. This method also yielded significant CT-specific additional information in the anterior mediastinum in 74.4% of the cases, in the mesomediastinum in 69.1%, in the posterior mediastinum in 79.2% in the upper thoracic aperture in 94.4% and in the paracardial region in 100% of the cases. The hilar region is an exception; in 68.8% of the cases, both methods were rated equal, whereas in 28.1% of the cases assessment via the CT method was even inferior. The specific additional information furnshed by the CT method justifies a wider application of CT in solving the following problems concerning the mediastinum: Clarification of a suspected but not yet established space-occupying growth in the mediastinum, before using invasive diagnostic methods such as mediastinoscopy and angiography; staging of an already identified primary mediastinal tumor or malignant lymphoma; in case of suspected changes in the large mediastinal vessels before employing angiography; on-target in the following diseases: bronchogenic carcinoma (because of improved pretherapeutic staging according to the TNM system), myasthenia gravis and identification of thymoma, hyperparathyroidism with suspected dystopic parathyroid glands.

  3. The diagnostic ranking of computerised tomography in mediastinal diseases depending on their localisation

    International Nuclear Information System (INIS)

    Sommer, B.; Doppman, J.L.; Mayr, B.; Rienmueller, R.; Lissner, J.; Stelter, W.

    1981-01-01

    The diagnostic ranking and importance of computerised tomography was examined in 116 with abnormal findings in the mediastinal region, and was compared with conventional, non-invasive X-ray examinations. This method also yielded significant CT-specific additional information in the anterior mediastinum in 74.4% of the cases, in the mesomediastinum in 69.1%, in the posterior mediastinum in 79.2% in the upper thoracic aperture in 94.4% and in the paracardial region in 100% of the cases. The hilar region is an exception; in 68.8% of the cases, both methods were rated equal, whereas in 28.1% of the cases assessment via the CT method was even inferior. The specific additional information furnshed by the CT method justifies a wider application of CT in solving the following problems concerning the mediastinum: Clarification of a suspected but not yet established space-occupying growth in the mediastinum, before using invasive diagnostic methods such as mediastinoscopy and angiography; staging of an already identified primary mediastinal tumor or malignant lymphoma; in case of suspected changes in the large mediastinal vessels before employing angiography; on-target in the following diseases: bronchogenic carcinoma (because of improved pretherapeutic staging according to the TNM system), myasthenia gravis and identification of thymoma, hyperparathyroidism with suspected dystopic parathyroid glands. (orig.) [de

  4. Colonoscopy and computerised tomography scan are not sufficient to localise right sided colonic lesions accurately.

    LENUS (Irish Health Repository)

    Solon, Jacqueline Gemma

    2009-11-23

    : Aim: accurate pre-operative localisation of colonic lesions is critical especially in laparoscopic colectomy where tactile localisation is absent particularly in screen-detected tumours. The study aimed to evaluate the accuracy of colonoscopy and double-contrast computerised tomography (CT) to localise lesions treated by right hemicolectomy. Method: a retrospective chart review was performed of patients treated by right hemicolectomy under the colorectal service between July 2003 and October 2006. Pre-operative tumour location determined by CT scan and colonoscopy were compared with the intra-operative and histopathologic findings. Results: of 101 patients, 73 (73%) were for adenoma or cancer, with a final diagnosis of adenocarcinoma in 59 (59%). Pre-operative localisation was inaccurate in 29% of lesions using both CT and colonoscopy. In the transverse colon colonoscopy alone was only 37.5% accurate, increasing to 62.5% when information from the CT scan was added. Conclusion: pre-operative localisation of right-sided colon cancers using colonoscopy and CT scanning is unreliable in at least 29% of cases. Inaccurate localisation of transverse colon tumours risks inadequate lymphadenectomy with an adverse cancer outcome. Pre-operative abdominal CT scan improves accuracy but endoscopic tattoo localisation should be employed routinely especially in patients undergoing laparoscopic resection.

  5. Effectiveness of a computerised working memory training in adolescents with mild to borderline intellectual disabilities.

    Science.gov (United States)

    Van der Molen, M J; Van Luit, J E H; Van der Molen, M W; Klugkist, I; Jongmans, M J

    2010-05-01

    The goal of this study is to evaluate the effectiveness of a computerised working memory (WM) training on memory, response inhibition, fluid intelligence, scholastic abilities and the recall of stories in adolescents with mild to borderline intellectual disabilities attending special education. A total of 95 adolescents with mild to borderline intellectual disabilities were randomly assigned to either a training adaptive to each child's progress in WM, a non-adaptive WM training, or to a control group. Verbal short-term memory (STM) improved significantly from pre- to post-testing in the group who received the adaptive training compared with the control group. The beneficial effect on verbal STM was maintained at follow-up and other effects became clear at that time as well. Both the adaptive and non-adaptive WM training led to higher scores at follow-up than at post-intervention on visual STM, arithmetic and story recall compared with the control condition. In addition, the non-adaptive training group showed a significant increase in visuo-spatial WM capacity. The current study provides the first demonstration that WM can be effectively trained in adolescents with mild to borderline intellectual disabilities.

  6. Simulated Radioactivity

    Science.gov (United States)

    Boettler, James L.

    1972-01-01

    Describes the errors in the sugar-cube experiment related to radioactivity as described in Project Physics course. The discussion considers some of the steps overlooked in the experiment and generalizes the theory beyond the sugar-cube stage. (PS)

  7. Concentrating Radioactivity

    Science.gov (United States)

    Herrmann, Richard A.

    1974-01-01

    By concentrating radioactivity contained on luminous dials, a teacher can make a high reading source for classroom experiments on radiation. The preparation of the source and its uses are described. (DT)

  8. Study on thorium removal from effluent by electrocoagulation

    International Nuclear Information System (INIS)

    Nath, Baidurjya; Swaroopa Lakshmi, Y.V.; Tiwari, S.K.; Setty, D.S.; Kalyanakrishnan, G.; Saibaba, N.

    2015-01-01

    Coagulation-flocculation, membrane separation and ion-exchange are traditional methods for treatment of radioactive wastewater generated primarily from the front end processes of the fuel cycle. Electrocoagulation presents a robust and novel alternative to conventional coagulation process. The present study involves the establishment of electrocoagulation as a treatment process for thorium bearing non-process effluents in batch mode. This involved an electrolytic reactor with iron electrodes. The non-process effluent was subjected to coagulation and floatation by Fe(II) ions dissolved from the anode with the resultant flocs floating on the surface after being captured by hydrogen gas bubbles generated at the cathode. The effect of various operational parameters like initial pH, residence time, current density and initial thorium concentration on the removal efficiency was investigated. Maximum decontamination factor obtained was of the order of 10 4 . (author)

  9. Source of radioactivity in the ocean environment

    International Nuclear Information System (INIS)

    Solomon, K.A.

    1988-01-01

    This paper summarizes both natural and man-made radioactivity in the marine environment. Radioactivity occurs naturally in both the sea water and in the ocean sediment. Radioactivity in the sea water is fairly uniform geographically and is dominated by the naturally occurring isotope 40/K (potassium-40). Unlike sea water, sediment radiation levels vary with sediment type and location. The primary source of natural radiation in the sediment results from deposition of insoluble thorium isotopes formed by the decay of water-soluble uranium. Man-made sources of radioactivity arise from, in descending order of importance: - sinking of two U.S. and two Soviet nuclear submarines; fallout from nuclear weapons testing; dumping of primarily British and Americal low-level nuclear waste; and dumping of reprocessing plant radiated effluents from the British Windscale facility and other European and Indian reprocessing facilities. 1 table

  10. Radioactive wastes

    International Nuclear Information System (INIS)

    Grass, F.

    1982-01-01

    Following a definition of the term 'radioactive waste', including a discussion of possible criteria allowing a delimitation of low-level radioactive against inactive wastes, present techniques of handling high-level, intermediate-level and low-level wastes are described. The factors relevant for the establishment of definitive disposals for high-level wastes are discussed in some detail. Finally, the waste management organization currently operative in Austria is described. (G.G.)

  11. Radioactive pollution

    International Nuclear Information System (INIS)

    Steiner, R.

    1987-01-01

    In the wake of the Chernobyl reactor accident on April 26, 1986, many individual values for radioactivity in the air, in foodstuffs and in the soil were measured and published. Prof. Dr. Rolf Steiner, Wiesbaden, the author of this paper, evaluated the host of data - mostly official pollution data -, drew conclusions regarding the radioactivity actually released at Chernobyl, and used the data to test the calculation model adotped by the Radiation Protection Ordinance. (orig./RB) [de

  12. Effluent information system (EIS)/onsite discharge information system (ODIS) 1985 executive summary

    International Nuclear Information System (INIS)

    Watanabe, T.

    1986-09-01

    The Effluent Information System (EIS) and Onsite Discharge Information System (ODIS) are Department of Energy (DOE) data base systems that aid DOE-Headquarters and Field Offices in managing the radioactive air and liquid effluents from DOE facilities. Data on effluents released offsite are entered into EIS and data on effluents discharged onsite and retained onsite are entered into ODIS. This document is a summary of information obtained from the CY 1985 effluent data received from all DOE and DOE contractor facilities and entered in the data bases. Data from previous years are also included. The summary consists of two parts. The first part summarizes information for effluents released offsite, and the second part summarizes information for effluents retained onsite. These summaries are taken from the routine annual reports sent to each DOE Operations Office. Special tabulations or specific data can be supplied upon request. Explanations of the significant changes are included in the EIS and ODIS graphic sections. Only those changes in activity greater than a factor of two and having a magnitude greater than 0.1 Ci are considered significant and are addressed in the explanation

  13. Forest decline, natural and technically generated radioactivity

    International Nuclear Information System (INIS)

    Teufel, D.

    1983-06-01

    The question investigated is whether the radioactive rare gases emanating from nuclear plants are causative or participate in the triggering of forest disease. For one thing, a chemical reaction could be responsible for such an effect exerted by these artificial radioactive effluents. However, a calculation shows the concentration of radionuclides, respectively, in this case, their decomposition products, to be by many orders of magnitude smaller than other constituents in air; so a chemical reaction of this kind may be excluded. For the other part, rare gases might contribute to forest damage by their radioactive decomposition and late physical, chemical, and biological effects. In this connection, a detailed analysis is made of the comparability of natural radioactivity with radioactivity generated by nuclear plants. A possible contribution towards the total stress situation of forests (chemical air pollution, natural radioactivity, artificially produced radioactive rare gases, weather conditions and conditions arising from forest management and the like) would amount to a proportion smaller than 1/1000 considering natural radioactivity as a possible stress factor only. (orig.) [de

  14. Radioactive wastes: the challenge of volumes reduction

    International Nuclear Information System (INIS)

    Lepetit, V.

    2005-01-01

    The reduction of radioactive waste volumes is a priority for the French atomic energy commission (CEA) and for the Areva group. This article gives a rapid overview of the equipments and processes used to separate the valorizable materials from the ultimate wastes: pulsed separation columns and evaporators for the liquid-liquid extraction, compactification of spent fuel hulls, remote handling systems, recoverable colloid for surface decontamination, decontaminating foam, hydrothermal oxidation of organic and aqueous effluents, cold crucible vitrification etc. (J.S.)

  15. Radioactive materials released from nuclear power plants

    International Nuclear Information System (INIS)

    Tichler, J.; Norden, K.; Congemi, J.

    1991-05-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1988 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1988 release data are summarized in tabular form. Data covering specific radionuclides are summarized. 16 tabs

  16. Review of radioactive discharges from nuclear power stations

    International Nuclear Information System (INIS)

    1991-02-01

    HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report is a review of the arisings and concludes that suitable technologies exist, which if applied, could reduce discharges from nuclear power plants in England and Wales in line with the rest of Europe. (author)

  17. Radioactive waste management in Belgium

    International Nuclear Information System (INIS)

    Dejonghe, P.

    1977-01-01

    In 1975 the research association BELGOWASTE was founded in order to prepare a technical and administrative plan for radioactive waste management in Belgium and to take the preliminary steps for establishing an organization which would be responsible for this activity. The association made a survey of all forecasts concerning radioactive waste production by power reactors and the fuel cycle industry based on various schemes of development of the nuclear industry. From the technical point of view, the reference plan for waste management envisages: Purification at the production site of large volumes of low-level effluents; construction of a central facility for the treatment and intermediate storage of process concentrates (slurries, resins, etc.) and medium-level waste; centralization assumes the making of adequate arrangements for transporting waste before final treatment; maximum recovery of plutonium from waste and treatment of resiudal material by incineration at very high temperatures; treatment at the production site of high-level effluents from irradiated fuel reprocessing; construction of an underground long-term storage site for high-level treated waste and plutonium fuel fabrication waste; deep clay formations are at present preferred; disposal of low-level treated waste into the Atlantic ocean. It is intended to entrust the entire responsibility for treatment, disposal and storage of treated waste to a single body with participation by the State, the Nuclear Energy Research Centre (CEN/SCK), the electricity companies and Belgonucleaire. The partners intend to set up their facilities and services in the area of Mol [fr

  18. 40 CFR 427.43 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS ASBESTOS MANUFACTURING POINT SOURCE CATEGORY Asbestos Paper (Elastomeric Binder) Subcategory § 427.43 Effluent limitations guidelines representing the degree of effluent...

  19. 40 CFR 427.33 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS ASBESTOS MANUFACTURING POINT SOURCE CATEGORY Asbestos Paper (Starch Binder) Subcategory § 427.33 Effluent limitations guidelines representing the degree of effluent...

  20. 40 CFR 426.113 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS GLASS MANUFACTURING POINT SOURCE CATEGORY Television Picture... applicable to the abrasive polishing and acid polishing waste water streams. Effluent characteristic Effluent...

  1. 40 CFR 426.112 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... AGENCY (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS GLASS MANUFACTURING POINT SOURCE CATEGORY Television... stream): Effluent characteristic Effluent limitations Maximum for any 1 day Average of daily values for...

  2. 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

  3. TBP production plant effluent treatment process

    International Nuclear Information System (INIS)

    Sriniwas, C.; Sugilal, G.; Wattal, P.K.

    2004-06-01

    TBP production facility at Heavy Water Plant, Talcher generates about 2000 litres of effluent per 200 kg batch. The effluent is basically an aqueous solution containing dissolved and dispersed organics such as dibutyl phosphate, butanol etc. The effluent has high salinity, chemical oxygen demand (30-80 g/L) and pungent odour. It requires treatment before discharge. A chemical precipitation process using ferric chloride was developed for quantitative separation of organics from the aqueous part of the effluent. This process facilitates the discharge of the aqueous effluent. Results of the laboratory and bench scale experiments on actual effluent samples are presented in this report. (author)

  4. Westinghouse Hanford Company effluent discharges and solid waste management report for calendar year 1989: 200/600 Areas

    International Nuclear Information System (INIS)

    Brown, M.J.; P'Pool, R.K.; Thomas, S.P.

    1990-05-01

    This report presents calendar year 1989 radiological and nonradiological effluent discharge data from facilities in the 200 Areas and the 600 Area of the Hanford Site. Both summary and detailed effluent data are presented. In addition, radioactive and nonradioactive solid waste storage and disposal data for calendar year 1989 are furnished. Where appropriate, comparisons to previous years are made. The intent of the report is to demonstrate compliance of Westinghouse Hanford Company-operated facilities with administrative control values for radioactive constituents and applicable guidelines and standards (including Federal permit limits) for nonradioactive constituents. 11 refs., 20 tabs

  5. The effectiveness of computerised decision support on antibiotic use in hospitals: A systematic review

    Science.gov (United States)

    2017-01-01

    Background Inappropriate antimicrobial use has been shown to be an important determinant of the emergence of antimicrobial resistance (AMR). Health information technology (HIT) in the form of Computerised Decision Support (CDS) represents an option for improving antimicrobial prescribing and containing AMR. Objectives To evaluate the evidence for CDS in improving quantitative and qualitative measures of antibiotic prescribing in inpatient hospital settings. Methods A systematic literature search was conducted of articles published from inception to 20th December 2014 using eight electronic databases: MEDLINE, EMBASE, PUBMED, Web of Science, CINAHL, Cochrane Library, HMIC and PsychINFo. An updated systematic literature search was conducted from January 1st 2015 to October 1st 2016 using PUBMED. The search strategy used combinations of the following terms: (electronic prescribing) OR (clinical decision support) AND (antibiotic or antibacterial or antimicrobial) AND (hospital or secondary care or inpatient). Studies were evaluated for quality using a 10-point rating scale. Results Eighty-one studies were identified matching the inclusion criteria. Seven outcome measures were evaluated: adequacy of antibiotic coverage, mortality, volume of antibiotic usage, length of stay, antibiotic cost, compliance with guidelines, antimicrobial resistance, and CDS implementation and uptake. Meta-analysis of pooled outcomes showed CDS significantly improved the adequacy of antibiotic coverage (n = 13; odds ratio [OR], 2.11 [95% CI, 1.67 to 2.66, p ≤ 0.00001]). Also, CDS was associated with marginally lowered mortality (n = 20; OR, 0.85 [CI, 0.75 to 0.96, p = 0.01]). CDS was associated with lower antibiotic utilisation, increased compliance with antibiotic guidelines and reductions in antimicrobial resistance. Conflicting effects of CDS on length of stay, antibiotic costs and system uptake were also noted. Conclusions CDS has the potential to improve the adequacy of antibiotic

  6. A comparison of scoring models for computerised mental health screening for federal prison inmates.

    Science.gov (United States)

    Martin, Michael S; Wamboldt, Ashley D; O'Connor, Shannon L; Fortier, Julie; Simpson, Alexander I F

    2013-02-01

    There are high rates of mental disorder in correctional environments, so effective mental health screening is needed. Implementation of the computerised mental health screen of the Correctional Service of Canada has led to improved identification of offenders with mental health needs but with high rates of false positives. The goal of this study is to evaluate the use of an iterative classification tree (ICT) approach to mental health screening compared with a simple binary approach using cut-off scores on screening tools. A total of 504 consecutive admissions to federal prison completed the screen and were also interviewed by a mental health professional. Relationships between screening results and more extended assessment and clinical team discussion were tested. The ICT was more parsimonious in identifying probable 'cases' than standard binary screening. ICT was also highly accurate at detecting mental health needs (AUC=0.87, 95% CI 0.84-0.90). The model identified 118 (23.4%) offenders as likely to need further assessment or treatment, 87% of whom were confirmed cases at clinical interview. Of the 244 (48.4%) offenders who were screened out, only 9% were clinically assessed as requiring further assessment or treatment. Standard binary screening was characterised by more false positives and a comparable false negative rate. The use of ICTs to interpret screening data on the mental health of prisoners needs further evaluation in independent samples in Canada and elsewhere. This first evaluation of the application of such an approach offers the prospect of more effective and efficient use of the scarce resource of mental health services in prisons. Although not required, the use of computers can increase the ease of implementing an ICT model. Copyright © 2013 John Wiley & Sons, Ltd.

  7. Mortality Benefits of Antibiotic Computerised Decision Support System: Modifying Effects of Age

    Science.gov (United States)

    Chow, Angela L. P.; Lye, David C.; Arah, Onyebuchi A.

    2015-11-01

    Antibiotic computerised decision support systems (CDSSs) are shown to improve antibiotic prescribing, but evidence of beneficial patient outcomes is limited. We conducted a prospective cohort study in a 1500-bed tertiary-care hospital in Singapore, to evaluate the effectiveness of the hospital’s antibiotic CDSS on patients’ clinical outcomes, and the modification of these effects by patient factors. To account for clustering, we used multilevel logistic regression models. One-quarter of 1886 eligible inpatients received CDSS-recommended antibiotics. Receipt of antibiotics according to CDSS’s recommendations seemed to halve mortality risk of patients (OR 0.54, 95% CI 0.26-1.10, P = 0.09). Patients aged ≤65 years had greater mortality benefit (OR 0.45, 95% CI 0.20-1.00, P = 0.05) than patients that were older than 65 (OR 1.28, 95% CI 0.91-1.82, P = 0.16). No effect was observed on incidence of Clostridium difficile (OR 1.02, 95% CI 0.34-3.01), and multidrug-resistant organism (OR 1.06, 95% CI 0.42-2.71) infections. No increase in infection-related readmission (OR 1.16, 95% CI 0.48-2.79) was found in survivors. Receipt of CDSS-recommended antibiotics reduced mortality risk in patients aged 65 years or younger and did not increase the risk in older patients. Physicians should be informed of the benefits to increase their acceptance of CDSS recommendations.

  8. Targeted computerised tomography scanning of the ankle syndesmosis with low dose radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    Kotwal, Rahul [Princess of Wales Hospital, Bridgend (United Kingdom); Rath, Narendra [Royal Gwent Hospital, Newport (United Kingdom); Paringe, Vishal; Hemmadi, Sandeep; Thomas, Rhys; Lyons, Kath [University Hospital of Wales, Cardiff (United Kingdom)

    2016-03-15

    To devise a new protocol for targeted CT scanning of the distal tibiofibular syndesmosis with minimal radiation exposure to patients. We also aimed to correlate the reduction of the syndesmosis as seen on CT scans with the functional outcome of patients. Prospective study. Forty adults undergoing surgical stabilisation of an acute distal tibiofibular syndesmosis injury were recruited. A targeted five-cut computerised tomography scan protocol was developed. The radiation exposure to the patient with this protocol was only 0.002 mSv. Scans were performed 12 weeks after surgery. The contralateral ankle of every patient was used as a control to determine the accuracy of the reduction of the syndesmosis for that individual patient. American Orthopaedic Foot and Ankle Society (AOFAS) scores were obtained at a minimum of 1 year after surgery. After considering the exclusions, 36 patients formed the study group. A wide variation was observed in the anatomy of the normal syndesmosis. If we considered a difference of more than 2 mm between the normal and injured syndesmosis relationship as significant, 15 (41.6 %) of our patients had a significant difference between the injured and normal sides. AOFAS scores were available for 13 of these patients and were good to excellent in 11(84.6 %). Our study describes a reliable new CT scanning technique for the distal tibiofibular syndesmosis using only five cuts and a low-radiation-dose protocol. Clinical correlation of the findings on the scan with functional outcomes suggests that routine post-operative CT of the syndesmosis is probably not justified. (orig.)

  9. The effectiveness of computerised decision support on antibiotic use in hospitals: A systematic review.

    Directory of Open Access Journals (Sweden)

    Christopher E Curtis

    Full Text Available Inappropriate antimicrobial use has been shown to be an important determinant of the emergence of antimicrobial resistance (AMR. Health information technology (HIT in the form of Computerised Decision Support (CDS represents an option for improving antimicrobial prescribing and containing AMR.To evaluate the evidence for CDS in improving quantitative and qualitative measures of antibiotic prescribing in inpatient hospital settings.A systematic literature search was conducted of articles published from inception to 20th December 2014 using eight electronic databases: MEDLINE, EMBASE, PUBMED, Web of Science, CINAHL, Cochrane Library, HMIC and PsychINFo. An updated systematic literature search was conducted from January 1st 2015 to October 1st 2016 using PUBMED. The search strategy used combinations of the following terms: (electronic prescribing OR (clinical decision support AND (antibiotic or antibacterial or antimicrobial AND (hospital or secondary care or inpatient. Studies were evaluated for quality using a 10-point rating scale.Eighty-one studies were identified matching the inclusion criteria. Seven outcome measures were evaluated: adequacy of antibiotic coverage, mortality, volume of antibiotic usage, length of stay, antibiotic cost, compliance with guidelines, antimicrobial resistance, and CDS implementation and uptake. Meta-analysis of pooled outcomes showed CDS significantly improved the adequacy of antibiotic coverage (n = 13; odds ratio [OR], 2.11 [95% CI, 1.67 to 2.66, p ≤ 0.00001]. Also, CDS was associated with marginally lowered mortality (n = 20; OR, 0.85 [CI, 0.75 to 0.96, p = 0.01]. CDS was associated with lower antibiotic utilisation, increased compliance with antibiotic guidelines and reductions in antimicrobial resistance. Conflicting effects of CDS on length of stay, antibiotic costs and system uptake were also noted.CDS has the potential to improve the adequacy of antibiotic coverage and marginally decrease mortality in

  10. Targeted computerised tomography scanning of the ankle syndesmosis with low dose radiation exposure

    International Nuclear Information System (INIS)

    Kotwal, Rahul; Rath, Narendra; Paringe, Vishal; Hemmadi, Sandeep; Thomas, Rhys; Lyons, Kath

    2016-01-01

    To devise a new protocol for targeted CT scanning of the distal tibiofibular syndesmosis with minimal radiation exposure to patients. We also aimed to correlate the reduction of the syndesmosis as seen on CT scans with the functional outcome of patients. Prospective study. Forty adults undergoing surgical stabilisation of an acute distal tibiofibular syndesmosis injury were recruited. A targeted five-cut computerised tomography scan protocol was developed. The radiation exposure to the patient with this protocol was only 0.002 mSv. Scans were performed 12 weeks after surgery. The contralateral ankle of every patient was used as a control to determine the accuracy of the reduction of the syndesmosis for that individual patient. American Orthopaedic Foot and Ankle Society (AOFAS) scores were obtained at a minimum of 1 year after surgery. After considering the exclusions, 36 patients formed the study group. A wide variation was observed in the anatomy of the normal syndesmosis. If we considered a difference of more than 2 mm between the normal and injured syndesmosis relationship as significant, 15 (41.6 %) of our patients had a significant difference between the injured and normal sides. AOFAS scores were available for 13 of these patients and were good to excellent in 11(84.6 %). Our study describes a reliable new CT scanning technique for the distal tibiofibular syndesmosis using only five cuts and a low-radiation-dose protocol. Clinical correlation of the findings on the scan with functional outcomes suggests that routine post-operative CT of the syndesmosis is probably not justified. (orig.)

  11. Ethnicity Recording in Primary Care Computerised Medical Record Systems: An Ontological Approach

    Directory of Open Access Journals (Sweden)

    Zayd Tippu

    2017-03-01

    Full Text Available Background Ethnicity recording within primary care computerised medical record (CMR systems is suboptimal, exacerbated by tangled taxonomies within current coding systems. Objective To develop a method for extending ethnicity identification using routinely collected data. Methods We used an ontological method to maximise the reliability and prevalence of ethnicity information in the Royal College of General Practitioner’s Research and Surveillance database. Clinical codes were either directly mapped to ethnicity group or utilised as proxy markers (such as language spoken from which ethnicity could be inferred. We compared the performance of our method with the recording rates that would be identified by code lists utilised by the UK pay for the performance system, with the help of the Quality and Outcomes Framework (QOF. Results Data from 2,059,453 patients across 110 practices were included. The overall categorisable ethnicity using QOF codes was 36.26% (95% confidence interval (CI: 36.20%–36.33%. This rose to 48.57% (CI:48.50%–48.64% using the described ethnicity mapping process. Mapping increased across all ethnic groups. The largest increase was seen in the white ethnicity category (30.61%; CI: 30.55%–30.67% to 40.24%; CI: 40.17%–40.30%. The highest relative increase was in the ethnic group categorised as the other (0.04%; CI: 0.03%–0.04% to 0.92%; CI: 0.91%–0.93%. Conclusions This mapping method substantially increases the prevalence of known ethnicity in CMR data and may aid future epidemiological research based on routine data.

  12. Methanization of industrial liquid effluents; Methanisation des effluents industriels liquides

    Energy Technology Data Exchange (ETDEWEB)

    Frederic, S.; Lugardon, A. [Societe Naskeo Environnement, 92 - Levallois-Perret (France)

    2007-09-15

    In a first part, this work deals with the theoretical aspects of the methanization of the industrial effluents; the associated reactional processes are detailed. The second part presents the technological criteria for choosing the methanization process in terms of the characteristics of the effluent to be treated. Some of the methanization processes are presented with their respective advantages and disadvantages. At last, is described the implementation of an industrial methanization unit. The size and the main choices are detailed: the anaerobic reactor, the control, the valorization aspects of the biogas produced. Some examples of industrial developments illustrate the different used options. (O.M.)

  13. Radioactive wastes

    International Nuclear Information System (INIS)

    Dupuis, M.C.

    2007-01-01

    Managing radioactive wastes used to be a peripheral activity for the French atomic energy commission (Cea). Over the past 40 years, it has become a full-fledged phase in the fuel cycle of producing electricity from the atom. In 2005, the national radioactive waste management agency (ANDRA) presented to the government a comprehensive overview of the results drawn from 15 years of research. This landmark report has received recognition beyond France's borders. By broadening this agency's powers, an act of 28 June 2006 acknowledges the progress made and the quality of the results. It also sets an objective for the coming years: work out solutions for managing all forms of radioactive wastes. The possibility of recovering wastes packages from the disposal site must be assured as it was asked by the government in 1998. The next step will be the official demand for the creation of a geological disposal site in 2016

  14. Management of Discharge of Low Level Liquid Radioactive Waste Generated in Medical, Educational, Research and Industrial Facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-15

    Although published information on management technologies suitable for radioactive effluents is readily available, smaller facilities such as hospitals, universities and research laboratories in some countries can benefit from more detailed guidance on identifying optimal arrangements for effectively managing their radioactive liquid effluents. A wide range of circumstances exist globally, given that the generation of radioactive liquid effluents may be regular or irregular, and the liquid effluents may be suitable for direct discharge to the environment, or may require a period of decay storage prior to discharge. Countries typically fit into one of the four following categories with respect to the status of their arrangements for the management of radioactive liquid effluents: (1) The country does not have sufficient technical, regulatory and organizational infrastructure to effectively manage its radioactive liquid effluents; (2) The country's technical infrastructure for effectively managing its radioactive liquid effluents is almost sufficient, but it is not supported by an acceptable level of regulatory and organizational capacity (e.g. legal infrastructure, administrative infrastructure); (3) The country has sufficient technical, regulatory and organizational capacity, but it is known that the application of the requirements for proper management of radioactive liquid effluents is, in many cases, not being carried out to the standard indicated by official reports; (4) The country has well developed and established regulatory and organizational capacity, which is complemented by an acceptable level of relevant technical infrastructure such that the radioactive liquid effluents can be properly managed. Facilities, as well as countries, in the first three categories will find information in this publication to assist their further development. Even countries that already have the necessary infrastructure to properly manage their liquid radioactive effluents may

  15. Management of Discharge of Low Level Liquid Radioactive Waste Generated in Medical, Educational, Research and Industrial Facilities

    International Nuclear Information System (INIS)

    2013-07-01

    Although published information on management technologies suitable for radioactive effluents is readily available, smaller facilities such as hospitals, universities and research laboratories in some countries can benefit from more detailed guidance on identifying optimal arrangements for effectively managing their radioactive liquid effluents. A wide range of circumstances exist globally, given that the generation of radioactive liquid effluents may be regular or irregular, and the liquid effluents may be suitable for direct discharge to the environment, or may require a period of decay storage prior to discharge. Countries typically fit into one of the four following categories with respect to the status of their arrangements for the management of radioactive liquid effluents: (1) The country does not have sufficient technical, regulatory and organizational infrastructure to effectively manage its radioactive liquid effluents; (2) The country's technical infrastructure for effectively managing its radioactive liquid effluents is almost sufficient, but it is not supported by an acceptable level of regulatory and organizational capacity (e.g. legal infrastructure, administrative infrastructure); (3) The country has sufficient technical, regulatory and organizational capacity, but it is known that the application of the requirements for proper management of radioactive liquid effluents is, in many cases, not being carried out to the standard indicated by official reports; (4) The country has well developed and established regulatory and organizational capacity, which is complemented by an acceptable level of relevant technical infrastructure such that the radioactive liquid effluents can be properly managed. Facilities, as well as countries, in the first three categories will find information in this publication to assist their further development. Even countries that already have the necessary infrastructure to properly manage their liquid radioactive effluents may

  16. Radioactivity measurement

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  17. 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

  18. Revision of by-laws about effluents of EdF's nuclear power plants

    International Nuclear Information System (INIS)

    2002-01-01

    In France, in application of the clean water law from January 3, 1992 and since the decree 95-540 from May 4, 1995, each basic nuclear facility receives a single permission which covers both its water takes and its radioactive and non-radioactive effluents. This decree, initially dedicated to new facilities has been enlarged to all existing installations for which the prefectorial by-laws have reached their date-line. Thus, up to now, five inter-ministerial by-laws have renewed the permissions of water takes and effluents evacuation of the power plants of Saint-Laurent-des-Eaux (Loir-et-Cher), Flamanville (Manche), Paluel (Seine-Maritime), Belleville (Cher) and Saint-Alban (Isere). These by-laws foresee an important abatement of the effluents and concern more particularly the tritium, 14 C, the iodine isotopes and also some other non-radioactive chemical compounds. This document is a compilation of all revised by-laws about effluents and concerning the nuclear power plants listed above. (J.S.)

  19. Methanization of industrial liquid effluents

    International Nuclear Information System (INIS)

    Frederic, S.; Lugardon, A.

    2007-01-01

    In a first part, this work deals with the theoretical aspects of the methanization of the industrial effluents; the associated reactional processes are detailed. The second part presents the technological criteria for choosing the methanization process in terms of the characteristics of the effluent to be treated. Some of the methanization processes are presented with their respective advantages and disadvantages. At last, is described the implementation of an industrial methanization unit. The size and the main choices are detailed: the anaerobic reactor, the control, the valorization aspects of the biogas produced. Some examples of industrial developments illustrate the different used options. (O.M.)

  20. Source terms for airborne effluents

    International Nuclear Information System (INIS)

    Blomeke, J.O.; Perona, J.J.

    1976-01-01

    The origin and nature of fuel cycle wastes are discussed with regard to high-level wastes, cladding, noble gases, iodine, tritium, 14 C, low-level and intermediate-level transuranic wastes, non-transuranic wastes, and ore tailings. The current practice for gaseous effluent treatment is described for light water reactors and high-temperature gas-cooled reactors. Other topics discussed are projections of nuclear power generation; projected accumulation of gaseous wastes; the impact of nuclear fuel cycle centers; and global buildup of airborne effluents

  1. The computerisation of Australian general practice 1998_2001 - what did we get for AU$15 000 000?

    Directory of Open Access Journals (Sweden)

    Michael Kidd

    2002-03-01

    Full Text Available In 1998 the Commonwealth government provided AU$15 000 000 towards a three-year project to support the computerisation of Australian general practice. This initiative was carried forward by the peak national body for information technology in general practice, the General Practice Computing Group (GPCG. This paper describes the activities of the GPCG, how this money was spent, and includes the evaluation of this three-year project which has resulted in computers on the desktops of the majority of Australia's GPs.

  2. Developing the Coach Analysis and Intervention System (CAIS): establishing validity and reliability of a computerised systematic observation instrument.

    Science.gov (United States)

    Cushion, Christopher; Harvey, Stephen; Muir, Bob; Nelson, Lee

    2012-01-01

    We outline the evolution of a computerised systematic observation tool and describe the process for establishing the validity and reliability of this new instrument. The Coach Analysis and Interventions System (CAIS) has 23 primary behaviours related to physical behaviour, feedback/reinforcement, instruction, verbal/non-verbal, questioning and management. The instrument also analyses secondary coach behaviour related to performance states, recipient, timing, content and questioning/silence. The CAIS is a multi-dimensional and multi-level mechanism able to provide detailed and contextualised data about specific coaching behaviours occurring in complex and nuanced coaching interventions and environments that can be applied to both practice sessions and competition.

  3. Radioactive Waste.

    Science.gov (United States)

    Blaylock, B. G.

    1978-01-01

    Presents a literature review of radioactive waste disposal, covering publications of 1976-77. Some of the studies included are: (1) high-level and long-lived wastes, and (2) release and burial of low-level wastes. A list of 42 references is also presented. (HM)

  4. Radioactivity measurements

    International Nuclear Information System (INIS)

    Schwach, G.

    1986-01-01

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

  5. Experience with effluent release from the Omaha V. A. Hospital TRIGA reactor

    International Nuclear Information System (INIS)

    Blotcky, A.J.

    1974-01-01

    The effluent release from experiments is controlled by limiting the size of each sample irradiated so that if it was accidentally completely volatized into the closed room, the radioactive concentration would not exceed the permitted limits. The possible releases of Ar-41 and N-16 from the reactor are also considered. The experimentally determined levels of radiation around the Omaha facility are shown. From the data and calculations it was concluded that the levels of effluent release from the Omaha TRIGA are very small

  6. The treatment of low level effluents by flocculation and settling at the Chooz nuclear power plant

    International Nuclear Information System (INIS)

    Petteau, J.L.; Roofthooft, R.

    1989-01-01

    At the Chooz plant, radioactive effluents were formerly treated by evaporation, but because throughput was low, another method was studied. After laboratory tests, a 500 L/h flocculation and settling pilot plant was constructed, followed later by a 5 m 3 /h installation. The main isotopes eliminated are caesium-134 and caesium-137. Flocculation with copper ferrocyanide reduces the total activity to less than 500 Bq/L. The installation described in the paper was commissioned in 1984 and has been in industrial operation since 1985, processing all types of effluent. The evaporator can be set aside for boric acid recovery. (author). 3 figs, 1 tab

  7. The treatment of liquid effluents of reprocessing plants by a chemical process: French experience

    International Nuclear Information System (INIS)

    Fernandez, N.; Taillard, D.

    1977-01-01

    The goal of radioactive effluent processing is to obtain a liquid with a residual activity level allowing disposal and a minimum amount of slurries. Insolubilization methods used in France are described to eliminate fission products in reprocessing plants effluents i.e. strontium, cesium, ruthenium and antimony; others radioelements are generally carried away with others precipitates. Evolution of the process is expressed in terms of reprocessing needs and improvements. Decontamination factors better than 100 are now possible with concentration factors between 30 and 50 [fr

  8. Experience with effluent release from the Omaha V. A. Hospital TRIGA reactor

    Energy Technology Data Exchange (ETDEWEB)

    Blotcky, A J [Veterans Administration Hospital (United States)

    1974-07-01

    The effluent release from experiments is controlled by limiting the size of each sample irradiated so that if it was accidentally completely volatized into the closed room, the radioactive concentration would not exceed the permitted limits. The possible releases of Ar-41 and N-16 from the reactor are also considered. The experimentally determined levels of radiation around the Omaha facility are shown. From the data and calculations it was concluded that the levels of effluent release from the Omaha TRIGA are very small.

  9. Disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Dlouhy, Z.

    1982-01-01

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

  10. Characterisation of potential aquaculture pond effluents, and ...

    African Journals Online (AJOL)

    Conventional treatment of effluents from these small-scale, low-volume operations, which discharge relatively dilute effluents infrequently, might not be cost-effective. Keywords: aquaculture–environment interaction, earthen ponds, effluent characterisation, K-means clustering, t ilapia, water quality. African Journal of Aquatic ...

  11. The uranium recovery from UO{sub 2} kernel production effluent

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Xiaotong, E-mail: chenxiaotong@tsinghua.edu.cn; He, Linfeng; Liu, Bing; Tang, Yaping; Tang, Chunhe

    2016-12-15

    Graphical abstract: In this study, a flow sheet including evaporation, flocculation, filtration, adsorption, and reverse osmosis was established for the UO{sub 2} kernel production effluent of HTR spherical fuel elements. The uranium recovery could reach 99.9% after the treatment, with almost no secondary pollution produced. Based on the above experimental results, the treating flow process in this study would be feasible for laboratory- and engineering-scale treatment of UO{sub 2} kernel production effluent of HTR spherical fuel elements. - Highlights: • A flow sheet including evaporation, flocculation, filtration, adsorption, and reverse osmosis was established for the UO{sub 2} kernel production effluent. • The uranium recovery could reach 99.9% after the treatment, with almost no secondary pollution produced. • The treating flow process would be feasible for laboratory- and engineering-scale treatment of UO{sub 2} kernel production effluent. - Abstract: For the fabrication of coated particle fuel elements of high temperature gas cooled reactors, the ceramic UO{sub 2} kernels are prepared through chemical gelation of uranyl nitrate solution droplets, which produces radioactive effluent with components of ammonia, uranium, organic compounds and ammonium nitrate. In this study, a flow sheet including evaporation, flocculation, filtration, adsorption, and reverse osmosis was established for the effluent treating. The uranium recovery could reach 99.9% after the treatment, with almost no secondary pollution produced.

  12. Report of radioactivity survey research in fiscal year 1988

    International Nuclear Information System (INIS)

    1989-12-01

    The National Institute of Radiological Sciences has been surveyed, as part of the radioactivity research project by the Science and Technology Agency, radioactivity levels in the environment and safety analysis for radioactive fallouts associated with nuclear weapons tests since 1959 and effluents from nuclear installations. With a remarkable advent of the peaceful applications of radionuclides, radioactivity in the environment has been becoming a matter of concern for the population in Japan. Radioactivity research is considered to become more important because it may provide clues for the basis of its influences upon the human body and environment. This report gives a survey of the radioactivity research project performed in the fiscal year 1988. The following topics are covered: (1) radioactivity levels and dosimetry in the environment, foods, and human body; (2) radioactivity levels surrounding nuclear installations; (3) services in the Radioactivity Survey Data Center; (4) basic survey of evaluation for the results of radioactivity levels; (5) training of technichians for monitoring environmental radioactivity; and (6) survey research for dosimetry and countermeasures at emergency. (N.K.)

  13. Releases of radioactivity at the Savannah River Plant, 1954--1985

    International Nuclear Information System (INIS)

    Zeigler, C.C.; Lawrimore, I.B.

    1988-07-01

    Radioactive releases from Savannah River Plant (SRP) facilities to air, water and earthen seepage basins have been monitored and tabulated throughout the history of the site. The purpose of this report is to provide a source of data on routine releases of radioactivity to air, water and seepage basins that can be used for analyses of trends, environmental impact, etc. As used in this report, routine radioactive releases means radioactive materials that are released through established effluents from process facilities. This report provides a summary of radioactive releases that inflects the release values contained m records and documents from startup through 1985

  14. Radioactive waste management

    International Nuclear Information System (INIS)

    2013-01-01

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

  15. Disposal of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-01-15

    The problem of disposal can be tackled in two ways: the waste can be diluted and dispersed so that the radiation to which any single individual would be subjected would be negligible, or it can be concentrated and permanently isolated from man and his immediate environment. A variety of methods for the discharge of radioactive waste into the ground were described at the Monaco conference. They range from letting liquid effluent run into pits or wells at appropriately chosen sites to the permanent storage of high activity material at great depth in geologically suitable strata. Another method discussed consists in the incorporation of high level fission products in glass which is either buried or stored in vaults. Waste disposal into rivers, harbours, outer continental shelves and the open sea as well as air disposal are also discussed. Many of the experts at the Monaco conference were of the view that most of the proposed, or actually applied, methods of waste disposal were compatible with safety requirements. Some experts, felt that certain of these methods might not be harmless. This applied to the possible hazards of disposal in the sea. There seemed to be general agreement, however, that much additional research was needed to devise more effective and economical methods of disposal and to gain a better knowledge of the effects of various types of disposal operations, particularly in view of the increasing amounts of waste material that will be produced as the nuclear energy industry expands

  16. Incineration of radioactive waste

    International Nuclear Information System (INIS)

    Caramelle, D.; Florestan, J.; Waldura, C.

    1990-01-01

    This paper reports that one of the methods used to reduce the volume of radioactive wastes is incineration. Incineration also allows combustible organic wastes to be transformed into inert matter that is stable from the physico-chemical viewpoint and ready to be conditioned for long-term stockage. The quality of the ashes obtained (low carbon content) depends on the efficiency of combustion. A good level of efficiency requires a combustion yield higher than 99% at the furnace door. Removal efficiency is defined as the relation between the CO 2 /CO + CO 2 concentrations multiplied by 100. This implies a CO concentration of the order of a few vpm. However, the gases produced by an incineration facility can represent a danger for the environment especially if toxic or corrosive gases (HCL,NO x ,SO 2 , hydrocarbons...) are given off. The gaseous effluents must therefore be checked after purification before they are released into the atmosphere. The CO and CO 2 measurement gives us the removal efficiency value. This value can also be measured in situ at the door of the combustion chamber. Infrared spectrometry is used for the various measurements: Fourier transform infrared spectrometry for the off-gases, and diode laser spectrometry for combustion

  17. Radioactive waste

    International Nuclear Information System (INIS)

    Berkhout, F.

    1991-01-01

    Focusing on radioactive waste management and disposal policies in the United Kingdom, Sweden and the Federal Republic of Germany, this book gives a detailed historical account of the policy process in these three countries, and draws out the implications for theory and public policy. This comparative approach underlines how profoundly different the policy process has been in different countries. By comparing the evolution of policy in three countries, fundamental questions about the formation and resolution of technical decisions under uncertainty are clarified. The analysis of nuclear strategy, the politics of nuclear power, and the shifting emphasis of government regulation redefines the issue of radwaste management and sets it at the heat of the current debate about power, the environment and society. The combination of up-to-date technological assessment with an account of the social and political implications of radwaste management makes'Radioactive Waste'particularly useful to students of environmental studies, geography and public administration. (author)

  18. Radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Berkhout, F

    1991-01-01

    Focusing on radioactive waste management and disposal policies in the United Kingdom, Sweden and the Federal Republic of Germany, this book gives a detailed historical account of the policy process in these three countries, and draws out the implications for theory and public policy. This comparative approach underlines how profoundly different the policy process has been in different countries. By comparing the evolution of policy in three countries, fundamental questions about the formation and resolution of technical decisions under uncertainty are clarified. The analysis of nuclear strategy, the politics of nuclear power, and the shifting emphasis of government regulation redefines the issue of radwaste management and sets it at the heat of the current debate about power, the environment and society. The combination of up-to-date technological assessment with an account of the social and political implications of radwaste management makes'Radioactive Waste'particularly useful to students of environmental studies, geography and public administration. (author).

  19. Radioactive transformations

    CERN Document Server

    Rutherford, Ernest

    2012-01-01

    Radioactive Transformations describes Ernest Rutherford's Nobel Prize-winning investigations into the mysteries of radioactive matter. In this historic work, Rutherford outlines the scientific investigations that led to and coincided with his own research--including the work of Wilhelm Rӧntgen, J. J. Thomson, and Marie Curie--and explains in detail the experiments that provided a glimpse at special relativity, quantum mechanics, and other concepts that would shape modern physics. This new edition features a comprehensive introduction by Nobel Laureate Frank Wilczek which engagingly explains how Rutherford's early research led to a better understanding of topics as diverse as the workings of the atom's nucleus, the age of our planet, and the fusion in stars.

  20. Disposal options for radioactive waste

    International Nuclear Information System (INIS)

    Olivier, J.P.

    1991-01-01

    On the basis of the radionuclide composition and the relative toxicity of radioactive wastes, a range of different options are available for their disposal. Practically all disposal options rely on confinement of radioactive materials and isolation from the biosphere. Dilution and dispersion into the environment are only used for slightly contaminated gaseous and liquid effluents produced during the routine operation of nuclear facilities, such as power plants. For the bulk of solid radioactive waste, whatever the contamination level and decay of radiotoxicity with time are, isolation from the biosphere is the objective of waste disposal policies. The paper describes disposal approaches and the various techniques used in this respect, such as shallow land burial with minimum engineered barriers, engineered facilities built at/near the surface, rock cavities at great depth and finally deep geologic repositories for long-lived waste. The concept of disposing long-lived waste into seabed sediment layers is also discussed, as well as more remote possibilities, such as disposal in outer space or transmutation. For each of these disposal methods, the measures to be adopted at institutional level to reinforce technical isolation concepts are described. To the extent possible, some comments are made with regard to the applicability of such disposal methods to other hazardous wastes. (au)

  1. 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)

  2. 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)

  3. Radioactive wastes

    International Nuclear Information System (INIS)

    Devarakonda, M.S.; Melvin, J.M.

    1994-01-01

    This paper is part of the Annual Literature Review issue of Water Environment Research. The review attempts to provide a concise summary of important water-related environmental science and engineering literature of the past year, of which 40 separate topics are discussed. On the topic of radioactive wastes, the present paper deals with the following aspects: national programs; waste repositories; mixed wastes; waste processing and decommissioning; environmental occurrence and transport of radionuclides; and remedial actions and treatment. 178 refs

  4. Derived release limits (DRL's) for airborne and liquid effluents from the Chalk River Nuclear Laboratories during normal operations

    International Nuclear Information System (INIS)

    Palmer, J.F.

    1981-02-01

    Derived release limits (DRL's), based on regulatory dose limits, have been calculated for routine discharges of radioactivity in airborne and liquid effluents from the Chalk River Nuclear Laboratories. Three types of sources of airborne effluents were considered: the NRX/NRU stack, the 61 m stack connected to the 99 Mo production facility, and a roof vent typical of those installed on several buildings on the site. Sources of liquid effluents to the Ottawa River were treated as a single source from the site as a whole. Various exposure pathways to workers on the site and to members of the public outside the site boundary were considered in the calculations. The DRL's represent upper limits for routine emissions of radioactivity from the Chalk River Nuclear Laboratories to the surrounding environment. Actual releases are regulated by Administrative Levels, set lower than the DRL's, and are confirmed by monitoring. (author)

  5. Collective dose to the European Community from nuclear industry effluents discharge in 1978

    CERN Document Server

    Camplin, W C

    1983-01-01

    The results are presented of a study to evaluate the collective dose commitment to the population of the European Community from effluents released by the nuclear industry within the EC in 1978. Airborne and liquid effluent discharge data have been taken from published sources, and computer modelling techniques have been used to predict the transfer of radioactivity through the environment to man. The collective dose commitments due to discharges from each nuclear installation have been evaluated and the comparative significance of individual radionuclides and their pathways to man have been considered. Airborne releases resulted in an estimated collective effective dose equivalent commitment of 95 man Sv, the major part of which is due to carbon-14 from both power stations and reprocessing plants. The collective effective dose equivalent commitment from liquid effluents is estimated to be 408 man Sv, mostly due to caesium-137 and other radionuclides from the Sellafield (formerly Windscale) reprocessing plant...

  6. New treatment facility for low level process effluents at the Savannah River site

    International Nuclear Information System (INIS)

    Ebra, M.A.; Bibler, J.P.; Johnston, B.S.; Kilpatrick, L.L.; Poy, F.L.; Wallace, R.M.

    1987-01-01

    A new facility, the F/H Effluent Treatment Facility (F/H ETF) is under construction at the Savannah River site. It will decontaminate process effluents containing low levels of radionuclides and hazardous chemicals prior to discharge to a surface stream. These effluents, which are currently discharged to seepage basins, originate in the chemical separations and high-level radioactive waste processing areas, known as F-Area and H-Area. The new facility will allow closure of the basins in order to meet the provisions of the Resource Conservation and Recovery Act by November 1988. A high degree of reliability is expected from this design as a result of extensive process development work that has been conducted at the Savannah River Laboratory. This work has included both bench scale testing of individual unit operations and pilot scale testing of an integrated facility, 150 to 285 L/min (40 to 75 gpm), that contains the major operations

  7. Updated on effluents releases of the CEA nuclear fuel cycle facilities - 1995 to 2010 period

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Nelson Luiz Dias [Centro Tecnologico da Marinha em Sao Paulo (CTMSP) Sao Paulo, SP (Brazil)

    2011-07-01

    The environmental impact assessment of the Centro Experimental Aramar (CEA) facilities has been presented in a former work, based on the measured effluent releases data, for the period from 1995 to 2007. This work shows the update up to 2010. The effluents releases to the environment result from the routine operation of CEA nuclear fuel cycle facilities (LEI - Isotopic Enrichment Laboratory, USIDE - Pilot Plant for Industrial Verification of Uranium Enrichment and LABMAT - Nuclear Materials Laboratory). Basically, this work presents the radioactive release source terms, as described at the CEA Effluent Report sent to the National Commission for Nuclear Energy (CNEN) each semester, and a historical assessment of the critical group annual doses from 1995 up to 2010. The assessed doses are compared to the maximum dose constraint as well as to the exemption level specified by CNEN. (author)

  8. Updated on effluents releases of the CEA nuclear fuel cycle facilities - 1995 to 2010 period

    International Nuclear Information System (INIS)

    Ferreira, Nelson Luiz Dias

    2011-01-01

    The environmental impact assessment of the Centro Experimental Aramar (CEA) facilities has been presented in a former work, based on the measured effluent releases data, for the period from 1995 to 2007. This work shows the update up to 2010. The effluents releases to the environment result from the routine operation of CEA nuclear fuel cycle facilities (LEI - Isotopic Enrichment Laboratory, USIDE - Pilot Plant for Industrial Verification of Uranium Enrichment and LABMAT - Nuclear Materials Laboratory). Basically, this work presents the radioactive release source terms, as described at the CEA Effluent Report sent to the National Commission for Nuclear Energy (CNEN) each semester, and a historical assessment of the critical group annual doses from 1995 up to 2010. The assessed doses are compared to the maximum dose constraint as well as to the exemption level specified by CNEN. (author)

  9. Estimation of radionuclide releases in atmosphere from Cernavoda NPP based on continuous gaseous effluent monitoring

    International Nuclear Information System (INIS)

    Bobric, E.; Murgoci, S.; Popescu, I.; Ibadula, R.

    2001-01-01

    Monitoring of gaseous effluents from Cernavoda NPP is performed to assess the environmental impact of the plant operation. The results of the monitoring program are used to evaluate the population doses in order to ensure that the emissions of radionuclides in air are below regulatory limits and radiation doses are maintained ALARA. It complements, but is independent from the Operational Environmental Monitoring Program for Cernavoda NPP. Gaseous effluent monitors provide continuous indication of the radioactivity content in atmospheric emissions. Except for noble gases, these monitors also collect samples for later detailed analysis in the station Health Physics Laboratory. This paper presents the main equipment and the results of the gaseous effluents monitoring program in order to assess the impact of Cernavoda NPP operation and to predict the future releases as function of radionuclides concentrations in CANDU systems, based on the identified trends.(author)

  10. Control system of liquid effluents generated in treatment with I-131

    International Nuclear Information System (INIS)

    Garcia M, T.; Ruiz C, M. A.; Angeles C, A.; Ramirez S, R.

    2015-09-01

    In recent years, nuclear medicine has developed greatly in our country and around the world. Techniques for both medical diagnosis and therapy have increased the use of radiopharmaceuticals, notably the I-131. In Mexico there are around 150 nuclear medicine establishments authorized by the Comision Nacional de Seguridad Nuclear y Salvaguardias. Most of these establishments do not have an appropriate facility for the treatment of radioactive liquid effluents, to ensure compliance with the concentration limits established in the regulations. The Instituto Nacional de Investigaciones Nucleares (ININ) developed and implemented successfully, a control system of radioactive effluents (named SACEL) from a nuclear medicine facility. This system ensures an effective compliance with regulations and also better management and control of these radioactive effluents. Calculations and design of SACEL were made with respect to I-131, because is one of the most commonly used in radiotherapy and medical diagnostics, besides its half-life is greater in relation to other radionuclides. SACEL is comprised of four storage tanks and decay and a fifth tank for measuring the concentration of I-131 and later discharge to the drain; these tanks are connected to an automated system that controls the effluents passage. The calculation to determine the volume of the tanks was carried out according to the demand that has the hospital, to the maximum activity being poured in effluents and time required to decay. In this paper the design and installation of SACEL system, in addition to functioning as a facility that enables the Hospital meet the required standards is presented. Dose calculations performed with MCNPX and the methodology used in the calibration of the detection system is also presented. (Author)

  11. Effluent from Wastewater Treatment Plants

    DEFF Research Database (Denmark)

    Kristensen, Jannie Munk; Nierychlo, Marta; Albertsen, Mads

    Incoming microorganisms to wastewater treatment plants (WWTPs) are usually considered to be removed in the treatment process. Analyses of the effluent generally show a very high degree of reduction of pathogens supporting this assumption. However, standard techniques for detecting bacteria......-independent 16SrRNA gene amplicon sequencing was applied for the identification and quantification of the microorganisms. In total 84 effluent samples from 14 full-scale Danish wastewater treatment plants were investigated over a period of 3 months. The microbial community composition was investigated by 16S r...... contain pathogenic species. One of these was Arcobacter (Campylobacteraceae) which was found in up to 16% relative abundance. This indicates that Arcobacter, and perhaps other pathogenic genera, are not being removed efficiently in full-scale plants and may pose a potential health safety problem. Further...

  12. Control of effluents and environmental surveillance of the CEA centres. 1997 status

    International Nuclear Information System (INIS)

    1998-06-01

    The environmental quality in the vicinity of CEA facilities is a major concern of the safety policy of the CEA. The aim of this document is to inform the public about the gaseous and liquids radioactive effluents released by the CEA centres under the permission of the ministry. It provides a status of the effluents and of the radioactivity levels measured near the CEA centres in 1997, using air, water, vegetation and milk samples. A comparison is made with the measurements performed during the 1993-1996 period. The data presented comes from the regulatory registers transmitted to the agency for the protection against ionizing radiations (OPRI) which belongs to the ministry of health. (J.S.)

  13. Waste monitoring system for effluents

    International Nuclear Information System (INIS)

    Macdonald, J.M.; Gomez, B.; Trujillo, L.; Malcom, J.E.; Nekimken, H.; Pope, N.; Bibeau, R.

    1995-07-01

    The waste monitoring system in use at Los Alamos National Laboratory's Plutonium Facility, TA-55, is a computer-based system that proves real-time information on industrial effluents. Remote computers monitor discharge events and data moves from one system to another via a local area network. This report describes the history, system design, summary, instrumentation list, displays, trending screens, and layout of the waste monitoring system

  14. Radioactivity telemetry

    International Nuclear Information System (INIS)

    Bouras, Florent; Legrand, Bernard; Montigaud, Jean-Marie; Grandin, Marc

    1969-05-01

    The authors present an assembly which aims at radio-transmitting from mobile stations information on radioactivity. It comprises 20 mobile stations which can be located within the Cadarache Centre or outside of it within a 10 km radius, and a central station which centralises information. The report proposes a general presentation of these stations, their characteristics and principles of operation. It describes operation sequences, central station functions (call programmer, address and memory management, recording, peripherals) and its energy supply, and mobile station functions. The last part presents the installation, its start-up and exploitation, its threshold devices and its safety device

  15. Liquid Effluents Program mission analysis

    International Nuclear Information System (INIS)

    Lowe, S.S.

    1994-01-01

    Systems engineering is being used to identify work to cleanup the Hanford Site. The systems engineering process transforms an identified mission need into a set of performance parameters and a preferred system configuration. Mission analysis is the first step in the process. Mission analysis supports early decision-making by clearly defining the program objectives, and evaluating the feasibility and risks associated with achieving those objectives. The results of the mission analysis provide a consistent basis for subsequent systems engineering work. A mission analysis was performed earlier for the overall Hanford Site. This work was continued by a ''capstone'' team which developed a top-level functional analysis. Continuing in a top-down manner, systems engineering is now being applied at the program and project levels. A mission analysis was conducted for the Liquid Effluents Program. The results are described herein. This report identifies the initial conditions and acceptable final conditions, defines the programmatic and physical interfaces and sources of constraints, estimates the resources to carry out the mission, and establishes measures of success. The mission analysis reflects current program planning for the Liquid Effluents Program as described in Liquid Effluents FY 1995 Multi-Year Program Plan

  16. Development of computerised adaptive testing (CAT) for the EORTC QLQ-C30 dimensions - general approach and initial results for physical functioning

    DEFF Research Database (Denmark)

    Petersen, Morten Aa; Groenvold, Mogens; Aaronson, Neil K

    2010-01-01

    Health-related quality of life (HRQOL) questionnaires should ideally be adapted to the individual patient and at the same time scores should be directly comparable across patients. This is achievable using a computerised adaptive test (CAT). Basing the CAT on an existing instrument enables measur...

  17. Radiological characterization of liquid effluent hold up tank for generating data base for future decommissioning

    International Nuclear Information System (INIS)

    Sapkal, Jyotsna A.; Singh, Pratap; Verma, Amit; Yadav, R.K.B.; Thakare, S.V.

    2018-01-01

    Operations at Radiological laboratory facilities are involved in fabrication of high activity radioactive sources like 60 Co, 192 1r and 137 Cs, handling of long lived radionuclides like 137 Cs/ 90 Sr, radiochemical processing and production of short-lived radioisotopes for medical diagnosis and treatment of patients. Typical liquid waste management feature at any Radiological Laboratory facility primarily consists of effluent tanks which store the liquid effluent wastes generated during radiochemical processing and fabrication of reactor produced radioisotopes. The liquid waste generated from various laboratories are collected to low level sump tanks from where it is transferred to hold up tanks. The liquid waste is transferred to centralized effluent treatment plant, analysis and characterization of the same is carried out. This paper explains the characterization study of samples drawn from the liquid effluent tank which would be helpful for planning for decontamination as well as for decommissioning and in management of radioactive wastes. In this study the crud deposited at the bottom of tank was collected for gamma spectrometry analysis. Radiation field was measured, at the bottom of the tank for correlating the activity present and the radiation field

  18. Radioactive waste management in Belgium

    International Nuclear Information System (INIS)

    Dejonghe, P.

    1977-01-01

    In 1975 the research association BelgoWaste was founded in order to prepare a technical and administrative plan for radioactive waste management in Belgium and to take the preliminary steps for establishing an organization which would be responsible for this activity. The association made a survey of all forecasts concerning radioactive waste production by power reactors and the fuel cycle industry based on various schemes of development of the nuclear industry. From the technical point of view, the reference plan for waste management envisages: purification at the production site of large volumes of low-level effluents; construction of a central facility for the treatment and intermediate storage of process concentrates (slurries, resins, etc.) and medium-level waste, centralization assuming that adequate arrangements are made for transporting waste before final treatment; maximum recovery of plutonium from waste and treatment of residual material by incineration at very high temperatures; treatment at the production site of high-level effluents from irradiated fuel reprocessing; construction of an underground long-term storage site for high-level treated waste and plutonium fuel fabrication waste (deep clay formations are at present preferred); and disposal of low-level treated waste into the Atlantic Ocean. It is intended to entrust the entire responsibility for treatment, disposal and storage of treated waste to a single body with participation by the State, the Nuclear Energy Research Centre (CEN/SCK), the electricity companies and Belgonucleaire. The partners intend to set up their facilities and services in the area of Mol. (author)

  19. Test of active coal capacity for retaining gaseous effluents contaminated by 131 I

    International Nuclear Information System (INIS)

    Campeanu, Catalina; Cruceru, Madalina; Neacsu, Elena

    1999-01-01

    The aim of this paper is to test the retaining capacity of the active coal of the filters for gaseous effluents contaminated by 131 I. The active coal filters are design for equipping ventilation installations of nuclear plants in which radioactive iodine and combination of it were produced and handled. Such active coal filters are provided also to sorbonnes for radiochemical and physical handling of radioactive iodine. Testing the retaining capacity of active coal for filters is an obvious step, particularly, when the material was stored long time after preparation

  20. Management and Handling of Rejected Fuel of MTR Type and Process Effluents Contained Uranium at FEPI

    International Nuclear Information System (INIS)

    Ghaib Widodo; Bambang Herutomo

    2007-01-01

    Research Reactor Fuel Element Production Installation (FEPI) - Serpong has performed management and handling of all kinds of rejected fuel material during production (solids, liquids, and gases) and process effluents contained uranium. The methods that has been implemented are precipitation, absorption, evaporation, electrolysis, and electrodialysis. By these methods will finally be obtained forms of product which can be used directly as fuel material feed and solid/liquid radioactive waste that fulfil the requirements (uranium contents < 50 ppm) to be send to Radioactive Waste Management Installation. (author)