WorldWideScience

Sample records for radioactive discharge control

  1. 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

  2. Radioactive wastes and discharges

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

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

  3. Radioactive wastes and discharges

    International Nuclear Information System (INIS)

    2000-01-01

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

  4. Radioactive wastes and discharges

    International Nuclear Information System (INIS)

    1993-01-01

    According to the Section 24 of the Finnish Radiation Decree (1512/91), the Finnish Centre for Radiation and Nuclear Safety shall specify the concentration and activity limits and principles for the determination whether a waste can be defined as a radioactive waste or not. The radiation safety requirements and limits for the disposal of radioactive waste are given in the guide. They must be observed when discharging radioactive waste into the atmosphere or sewer system, or when delivering solid low-activity waste to a landfill site without a separate waste disposal plan. The guide does not apply to the radioactive waste resulting from the utilization of nuclear energy of natural resources. (4 refs., 1 tab.)

  5. The IAEA Standards for the Radioactive Discharge Control: Present Status and Future Development

    International Nuclear Information System (INIS)

    Balonov, M.; Linsley, G.; Robinson, C.; Cabianca, T.

    2004-01-01

    The International Atomic Energy Agency (IAEA) is the organization within the UN family with a statutory mandate to establish standards for the protection of health and environment against ionizing radiation, and to provide for the application of those standards. As part of these functions, the IAEA periodically reviews the status and continued relevance of the standards to the needs of its Member States. Recent work on the development of standards for the radioactive discharge control includes development of practical guidance for setting discharge limits, elaboration on methodology for the radiation protection of non-human species, and preparation of guidance on environmental monitoring for radiation protection purposes. Development of these safety documents is influenced by recent international and regional tendencies, based on social initiatives, to reduce radioactive discharges substantially below levels justified by radiological criteria. The IAEA has developed preliminary guidance on practical aspects of setting discharge limits, which included a review of national regulatory experience in this regard. This review suggested that societal pressures and regulatory practicalities results in discharge controls that were likely to be more restrictive that those that would be implied by formal optimization techniques. Regulatory review of authorizations includes a number of considerations, including predicted doses to members of the critical group, but the suitability of abatement forms a greater part in the decision-making process than allowed for in previous safety guidance. The IAEA has, in recent years, established a programme of work specifically addressing the development of safety standards on assessing the impact of ionizing radiation on non-human species, in co-operation with other relevant international organizations. The main issues arising will be summarised in the paper with the main focus on an exploration of the possible form of future regulatory

  6. 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.)

  7. Radioactive discharges from Sellafield (UK)

    International Nuclear Information System (INIS)

    Pentreath, R.J.

    1985-01-01

    This study of low-level liquid radioactive discharges from the British Nuclear Fuels Ltd Sellafield site into the eastern basin of the Irish Sea, prepared on the basis of existing publications and documents, reviews chemical forms and rate of discharges, physical oceanography, sediment distribution and fisheries of the Irish Sea, behaviour of radionuclides in seawater, association with sedimentary materials, accumulation of radionuclides by biological materials, environmental monitoring, surveillance and assessment of radiation exposure of the public and impact on the environment

  8. Standards for the control of radioactive discharges to the environment a changing situation

    International Nuclear Information System (INIS)

    Robinson, C.; Cabiance, T.; Linsley, G.

    2004-01-01

    The International Atomic Energy Agency (IAEA) is the organization within the UN family with a statutory mandate to establish standards for the protection of health and property against ionizing radiation, and to provide for the application of those standards. As part of these functions, the IAEA periodically reviews the status and continued relevance of its standards to the needs of Member States. Recent work on the development of a framework for the protection of non-human species, and on practical guidance for setting discharge limits, has highlighted a number of issues that have a bearing on the further development and application of standards for the control of discharges of radionuclides to the environment. The status of IAEA work on the protection of non-human species and the main findings of the International Conference on Protection of the Environment from the Effects of Ionizing Radiation, held in Stockholm, Sweden in October 2003 are presented. As part of a parallel programme of work, in support of existing standards on the regulatory control of discharges, a review of relevant national experience has been undertaken. This suggests that societal pressures and regulatory practicalities have resulted in discharge controls that are often more restrictive that those that would be implied by formal optimization techniques. A number of factors taken into account in setting discharge limits are identified and the application of the optimization principle to discharge regulation is discussed. The possible form of future standards that address both these developments is explored. (Author) 28 refs

  9. Limitation and control of radioactive liquid discharges at the Tihange power plant

    International Nuclear Information System (INIS)

    Dresse, H.

    1985-01-01

    Regulations on which is based the definition of limits stipulated in the licence are recalled. As american rules apply for the last power plants built in Belgium, the criteria of 10 CFR 50 App. 1 (ALARA) were followed, not only to justify the conception of installations as in U.S., but also to define limits for the yearly discharge of various isotopes. The observed procedure is described, and the limits are indicated, as well as the hypothetical doses which could result for the different classes of critical species to be considered. The author then defined the retained principles for the control and accounting of discharged activity [fr

  10. Annual survey of radioactive discharges in Great Britain 1978

    International Nuclear Information System (INIS)

    1979-09-01

    Details are given of main discharges to the environment of radioactive waste in 1978 together with those in 1977 and 1976 for comparison with comment on the environmental effect of the discharges in 1977. The statutory control over the discharges of radioactive wastes in Great Britain is outlined in the Introduction. Details of the discharges are set out in tabular form, grouped under: UKAEA establishments; the Radiochemical Centre Limited; British Nuclear Fuels Limited; CEGB and SSEB nuclear power stations; Ministry of Defence. Part 7 deals with radioactivity in drinking waters and rivers. (U.K.)

  11. 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)

  12. Discharges of radioactive materials to the environment in Argentina

    International Nuclear Information System (INIS)

    Curti, Adriana R.

    2003-01-01

    The International Atomic Energy Agency (IAEA) is creating a database of information on radioactive discharges to atmospheric and aquatic environments from nuclear and radioactive installations, and from facilities using radionuclides in medicine, industry and research. The database is expected to facilitate the analysis of worldwide trends in discharge levels and provide a basis for assessing the impact of the discharges on humans and on the environment. In November 2002 took place the first meeting of national contact points and the Nuclear Regulatory Authority (ARN in Spanish) was present as the counterpart for the provision of discharge data from Argentina. This paper, presented in the above mentioned meeting, is a general overview of the radioactive discharges control in Argentina including the legal infrastructure, the population dose assessment methodology and the main characteristics of the facilities in the country with authorized radioactive discharges to the environment. It is mentioned their location, release mode, surface water body type, main radionuclides and typical annual release activities. (author)

  13. Discharges of radioactive materials to the environment in Argentina

    CERN Document Server

    Curti, A R

    2003-01-01

    The International Atomic Energy Agency (IAEA) is creating a database of information on radioactive discharges to atmospheric and aquatic environments from nuclear and radioactive installations, and from facilities using radionuclides in medicine, industry and research. The database is expected to facilitate the analysis of worldwide trends in discharge levels and provide a basis for assessing the impact of the discharges on humans and on the environment. In November 2002 took place the first meeting of national contact points and the Nuclear Regulatory Authority (ARN in Spanish) was present as the counterpart for the provision of discharge data from Argentina. This paper, presented in the above mentioned meeting, is a general overview of the radioactive discharges control in Argentina including the legal infrastructure, the population dose assessment methodology and the main characteristics of the facilities in the country with radioactive discharges to the environment. It is mentioned their location, release...

  14. On regulation of radioactive airborne discharge

    International Nuclear Information System (INIS)

    Stroganov, A.A.; Kuryndin, A.V.; Shapovalov, A.S.; Orlov, M.Yu.

    2013-01-01

    Authors present the Russian regulatory basis of radioactive airborne discharges which was updated after enactment of the Methodology for airborne discharge limits development. Criteria for establishing of airborne discharge limits, scope and other features of methodology are also considered in the article [ru

  15. Radioactive liquid wastes discharged to ground in the 200 areas during 1974

    International Nuclear Information System (INIS)

    Anderson, J.D.

    1975-01-01

    Radioactive liquid wastes discharged to ground during 1974 and since startup within the Production and Waste Management control zone are summarized in tabular form. Estimates of the radioactivity discharged to individual ponds, cribs, and retention sites are also summarized. (LK)

  16. Reference methodologies for radioactive controlled discharges an activity within the IAEA's Program Environmental Modelling for Radiation Safety II (EMRAS II)

    International Nuclear Information System (INIS)

    Stocki, T.J.; Bergman, L.; Tellería, D.M.; Proehl, G.; Amado, V.; Curti, A.; Bonchuk, I.; Boyer, P.; Mourlon, C.; Chyly, P.; Heling, R.; Sági, L.; Kliaus, V.; Krajewski, P.; Latouche, G.; Lauria, D.C.; Newsome, L.; Smith, J.

    2011-01-01

    In January 2009, the IAEA EMRAS II (Environmental Modelling for Radiation Safety II) program was launched. The goal of the program is to develop, compare and test models for the assessment of radiological impacts to the public and the environment due to radionuclides being released or already existing in the environment; to help countries build and harmonize their capabilities; and to model the movement of radionuclides in the environment. Within EMRAS II, nine working groups are active; this paper will focus on the activities of Working Group 1: Reference Methodologies for Controlling Discharges of Routine Releases. Within this working group environmental transfer and dose assessment models are tested under different scenarios by participating countries and the results compared. This process allows each participating country to identify characteristics of their models that need to be refined. The goal of this working group is to identify reference methodologies for the assessment of exposures to the public due to routine discharges of radionuclides to the terrestrial and aquatic environments. Several different models are being applied to estimate the transfer of radionuclides in the environment for various scenarios. The first phase of the project involves a scenario of nuclear power reactor with a coastal location which routinely (continuously) discharges 60Co, 85Kr, 131I, and 137Cs to the atmosphere and 60Co, 137Cs, and 90Sr to the marine environment. In this scenario many of the parameters and characteristics of the representative group were given to the modelers and cannot be altered. Various models have been used by the different participants in this inter-comparison (PC-CREAM, CROM, IMPACT, CLRP POSEIDON, SYMBIOSE and others). This first scenario is to enable a comparison of the radionuclide transport and dose modelling. These scenarios will facilitate the development of reference methodologies for controlled discharges. (authors)

  17. UK strategy for radioactive discharges 2001-2020. Consultation document

    International Nuclear Information System (INIS)

    2000-06-01

    This consultation draft of a strategy for radioactive discharges describes how the United Kingdom (UK) will implement the agreements reached at the 1998 Ministerial meeting of the OSPAR Commission, with regard to radioactive substances. It also provides a policy base for future reviews of discharge authorisations by the regulatory bodies and for strategic planning by the nuclear operators. The strategy sets a framework for radioactive discharges from UK installations over the next twenty years. Its aims are: progressive and substantial reductions in radioactive discharges from the UK as a whole and from each of the main sectors responsible for such discharges; progressive reduction of human exposure to ionising radiation resulting from radioactive discharges, so that no member of the general public in the UK will be exposed to a dose of more than 0.02 mSv a year, as a result of authorised radioactive discharges made from 2020 onwards; progressive reductions in concentrations of radionuclides in the marine environment resulting from radioactive discharges, such that by 2020 they add close to zero to historic levels. The scope of the UK strategy encompasses radioactive discharges from nuclear licensed sites, defence activities and other nuclear and non-nuclear sources of radioactive discharges. It covers both liquid and aerial discharges, although it is assumed that in general liquid discharges will have the largest and most measurable effects in the marine environment

  18. An approach to the new ICRP recommendations on protection of the environment for the control of radioactive discharges

    International Nuclear Information System (INIS)

    Telleria, Diego

    2008-01-01

    Full text: For many years it has been agreed at the international level that the regulations for the control of discharges during normal operation from nuclear installation shall be based in the principles of individual dose limitation and optimization of the radiation protection focused on man. These regulations using a process of constrained optimization of protection, when properly applied to limit the discharges of radionuclides, were assumed to protect also other species than man and, within the available level of scientific knowledge, this assumption is still likely to be certain. After the International Conference on the Protection of the Environment from the Effects of Ionizing Radiation in Stockholm, 2003, many national, international, regional and non-governmental organizations have been working to develop a coherent international policy on the protection of the environment from effects attributable to exposures to ionizing radiation. One of the key issues to solve is how to include in the analysis and judgment process explicitly non-human species. Most of the organizations, particularly at the international level, have expressed their expectative in connection with the results of the work of the ICRP. In December 2007 the ICRP published its new recommendations and during 2008 key documents for the international community like the UNSCEAR document on effects of radiation on non-human biota and the ICRP publication on the approach to a framework for non-human protection using the concept of reference plants and animals could close, at least, the first chapter in this complex evolutionary process in the field of radiation protection. While some of the relevant topics for the protection of the environment from all the pollutants, like the global distribution patterns, the long term bioaccumulation effects, the relation of the individual effects regarding the communities and populations, Etc are still not fully discerned and noting that ICRP in its

  19. 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)

  20. Controlling radioactive waste

    International Nuclear Information System (INIS)

    Wurtinger, W.

    1992-01-01

    The guideline of the Ministry for Environmental Protection for controlling radioactive waste with a negligible development of heat defines in detail what data are relevant to the control of radioactive waste and should be followed up on and included in a system of documentation. By introducing the AVK (product control system for tracing the course of waste disposal) the operators of German nuclear power plants have taken the requirements of this guideline into account. In particular, possibilities for determining the degree of radioactivity of radioactive waste, which the BMU-guidelines call for, were put into practice by means of the programming technology of the product control system's module MOPRO. (orig.) [de

  1. Radioactive discharges and monitoring of the environment 1988

    International Nuclear Information System (INIS)

    1989-01-01

    This annual report on Radioactive Discharges and Monitoring the Environment, 1988, summarises the programmes of Sellafield, Drigg, Chapelcross, Springfields and Capenhurst for monitoring the discharges of radioactive materials to the sea and the environment. Critical groups and environmental exposure pathways are identified and collective doses to these groups estimated. The disposal of radioactive wastes at each site is discussed. Certificates of authorisation are presented. A summary of recommended doses of specific radionuclides is given. (Author)

  2. The reduction of radioactive discharges from Sellafield

    International Nuclear Information System (INIS)

    Horsley, D.M.C.

    1990-01-01

    This paper outlines the continuing efforts of British Nuclear Fuels to reduce the levels of discharges from the Sellafield site. Emphasis is placed on two plants: the Site Ion Exchange Effluent Plant (SIXEP), commissioned in 1985 and the Enhanced Actinide Removal Plant (EARP), programmed to be commissioned in 1991. The content matter deals with process and engineering concepts developed to solve problems peculiar to the nuclear industry but will be of interest to any organization faced with the processing, control and containment of hazardous media. (author)

  3. Regulation, proportionality and discharges of radioactive wastes: UK perspective

    International Nuclear Information System (INIS)

    Morley, Bob; Butler, Gregg; Mc Glynn, Grace

    2008-01-01

    In recent years, the UK Government and the Regulators have made a commitment to further improve the operation of the regulatory regime and to its operating within the principles of proportionality, transparency, consistency and accountability which underpin the Government's approach to regulation in general. Particular emphasis was to be placed upon ensuring that there is greater consistency in the treatment of risk and hazard; proportionate and cost effective delivery of public, worker and environmental protection; and an open and transparently applied regulatory system. It is noteworthy that with regard to radiation protection, there are different limits for public doses and workforce doses, with the latter 15 times greater. Allowable doses for medical patients are higher still. This discrepancy raises a question in itself. This presentation focuses on the practical application of the regulatory regime with particular regard to environmental discharges and disposals. Under the Radioactive Substances Act 1993, Operators within the UK nuclear industry are required to employ Best Practicable Means (BPM) to control and minimise radioactive discharges to ensure that doses from discharges are As Low As Reasonably Achievable (ALARA). Scientific assessments to date indicate that there are no expectations of environmental harm from discharges at Sellafield (and hence likewise at other UK nuclear sites where the discharges are lower), even where those discharges have historically been up to two orders of magnitude higher than current levels. Current discharges result in doses which are a small fraction of those received by the UK population due to natural background radiation. In addition, there is no proven environmental harm from foreseeable future discharges from Sellafield or other UK nuclear sites. This is supported by independent work which illustrates that the public collective dose from Sellafield discharges is almost all delivered at risks of less that one in a

  4. 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.)

  5. 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)

  6. Radioactive liquid wastes discharged to ground in the 200 areas during the first three quarters of 1974

    International Nuclear Information System (INIS)

    Anderson, J.D.

    1974-01-01

    An overall summary of radioactive liquid wastes discharged to ground during the first three quarters of 1974 and since startup within the Production and Waste Management control zone is presented in tabular form. Estimates of the radioactivity discharged to individual ponds, cribs, and specific retention sites are given. (LK)

  7. 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.

  8. Controlling the discharge of molten material

    International Nuclear Information System (INIS)

    Geel, J. van; Dobbels, F.; Theunissen, W.

    1980-01-01

    A method and device are described for controlling the discharge of molten material from a melter or an intermediate vessel, in which a primary outflow is fed to an overflow system, the working level of which is regulated by means of pneumatic pressure on a communicating chamber pertaining to the overflow system. Molten material may be led into a primary overflow by means of a pneumatic lift. The material melted may be a glass used for disposing of radioactive liquid wastes. (author)

  9. Processing method for discharged radioactive laundry water waste

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  10. The control of water radioactivity

    International Nuclear Information System (INIS)

    Bovard, P.; Graubey, A.

    1962-01-01

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

  11. Radioactivity control after Fukushima accident

    International Nuclear Information System (INIS)

    Vukovic, D.; Mitrovic, R.; Vicentijevic, M.; Pantelic, G.

    2011-01-01

    Fukushima nuclear accident has influence on more attention when radioactivity of fish were controlled. Sea fish, freshwater fish, fish products and fish flour were analysed ( 95 samples). All products were safe for use with radiation-hygienic aspects. [sr

  12. Customs control of radioactive materials

    International Nuclear Information System (INIS)

    Causse, B.

    1998-01-01

    Customs officers take part in the combat against illicit traffic od radioactive materials by means of different regulations dealing with nuclear materials, artificial radiation sources or radioactive wastes. The capability of customs officers is frequently incomplete and difficult to apply due to incompatibility of the intervention basis. In case of contaminated materials, it seems that the customs is not authorised directly and can only perform incidental control. In order to fulfil better its mission of fighting against illicit traffic of radioactive materials customs established partnership with CEA which actually includes practical and theoretical training meant to augment the capabilities of customs officers

  13. Annual report on radioactive discharges from Winfrith and monitoring the environment 1987

    International Nuclear Information System (INIS)

    1988-04-01

    The 1987 Annual Report on radioactive discharges from Winfrith Atomic Energy Establishment and monitoring of the environment is given. The report covers waste discharges to the sea and the earth atmosphere and the associated environmental monitoring. (UK)

  14. Changing methodology for measuring airborne radioactive discharges from nuclear facilities

    International Nuclear Information System (INIS)

    Glissmeyer, J.A.; Ligotke, M.W.

    1995-05-01

    The US Environmental Protection Agency (USEPA) requires that measurements of airborne radioactive discharges from nuclear facilities be performed following outdated methods contained in the American National Standards Institute (ANSI) N13.1-1969 Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities. Improved methods are being introduced via two paths. First, the ANSI standard is being revised, and second, EPA's equivalency granting process is being used to implement new technology on a case-by-case or broad basis. The ANSI standard is being revised by a working group under the auspices of the Health Physics Society Standards Committee. The revised standard includes updated methods based on current technology and a performance-based approach to design. The performance-based standard will present new challenges, especially in the area of performance validation. Progress in revising the standard is discussed. The US Department of Energy recently received approval from the USEPA for an alternate approach to complying with air-sampling regulations. The alternate approach is similar to the revised ANSI standard. New design tools include new types of sample extraction probes and a model for estimating line-losses for particles and radioiodine. Wind tunnel tests are being performed on various sample extraction probes for use at small stacks. The data show that single-point sampling probes are superior to ANSI-Nl3.1-1969 style multiple-point sample extraction probes

  15. Processing device for discharged water from radioactive material handling facility

    International Nuclear Information System (INIS)

    Kono, Takao; Kono, Hiroyuki; Yasui, Katsuaki; Kataiki, Koichi.

    1995-01-01

    The device of the present invention comprises a mechanical floating material-removing means for removing floating materials in discharged water, an ultrafiltration device for separating processed water discharged from the removing means by membranes, a reverse osmotic filtration device for separating the permeated water and a condensing means for evaporating condensed water. Since processed water after mechanically removing floating materials is supplied to the ultrafiltration device, the load applied on the filtering membrane is reduced, to simplify the operation control as a total. In addition, since the amount of resultant condensed water is reduced, and the devolumed condensed water is condensed and dried, the condensing device is made compact and the amount of resultant wastes is reduced. (T.M.)

  16. What Controls Submarine Groundwater Discharge?

    Science.gov (United States)

    Martin, J. B.; Cable, J. E.; Cherrier, J.; Roy, M.; Smith, C. G.; Dorsett, A.

    2008-05-01

    Numerous processes have been implicated in controlling submarine groundwater discharge (SGD) to coastal zones since Ghyben, Herzberg and Dupuit developed models of fresh water discharge from coastal aquifers at the turn of the 19th century. Multiple empirical and modeling techniques have also been applied to these environments to measure the flow. By the mid-1950's, Cooper had demonstrated that dispersion across the fresh water-salt water boundary required salt water entrained into fresh water flow be balanced by recharge of salt water across the sediment-water interface seaward of the outflow face. Percolation of water into the beach face from wind and tidal wave run up and changes in pressure at the sediment-water interface with fluctuating tides have now been recognized, and observed, as processes driving seawater into the sediments. Within the past few years, variations in water table levels and the 1:40 amplification from density difference in fresh water and seawater have been implicated to pump salt water seasonally across the sediment- water interface. Salt water driven by waves, tides and seasonal water table fluctuations is now recognized as a component of SGD when it flows back to overlying surface waters. None of these processes are sufficiently large to provide measured volumes of SGD in Indian River Lagoon, Florida, however, because minimal tides and waves exist, flat topography and transmissive aquifers minimize fluctuations of the water table, and little water is entrained across the salt water-fresh water boundary. Nonetheless, the saline fraction of SGD represents more than 99% of the volume of total SGD in the Indian River Lagoon. This volume of saline SGD can be driven by the abundance of burrowing organisms in the lagoon, which pump sufficient amounts of water through the sediment- water interface. These bioirrigating organisms are ubiquitous at all water depths in sandy sediment and thus may provide one of the major sources of SGD world wide

  17. Setting Authorized Limits for Radioactive Discharges: Practical Issues to Consider. Report for Discussion

    International Nuclear Information System (INIS)

    2010-03-01

    Application of the principles of radioactive waste management requires the implementation of measures that afford protection of human health and of the environment, now and in the future. The IAEA has issued safety standards and other publications that provide a framework for the control of releases of radionuclides to the environment. This framework is relevant for regulatory bodies that issue authorizations and for organizations that (i) use radionuclides for medical or research purposes, (ii) operate nuclear reactors or (iii) reprocess nuclear material. An IAEA Safety Guide on Regulatory Control of Radioactive Discharges to the Environment was issued in 2000 that outlines the roles and responsibilities of regulatory bodies, licensees and registrants and provides guidance on the authorization procedure. However, there have been significant developments in radiological protection policy since the publication of this Safety Guide, most notably the issue of ICRP Publications No. 101 on Assessing Dose of the Representative Person for the Purpose of Radiation Protection of the Public and the Optimisation of Radiological Protection and No. 103 on The 2007 Recommendations of the ICRP. The objective of this IAEA-TECDOC is to stimulate discussion on the practical implementation of the control of radioactive releases in order to inform the review and revision of IAEA guidance on this subject. This IAEA-TECDOC is based on the practical experience of Member States and on information provided at Technical Committee Meetings held in 2003 and 2008 and gained by means of a questionnaire. It summarizes international experience on the optimization of discharges and the setting by the regulatory body of authorized limits on discharges for nuclear installations and non-nuclear facilities. Its issue at this stage is intended for consultation as a preparatory step pending the current process of revision of the IAEA's International Basic Safety Standards for Protection against Ionizing

  18. 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)

  19. Annual report on radioactive discharges and monitoring of the environment 1992. V. 1

    International Nuclear Information System (INIS)

    1993-01-01

    This Annual Report supplements the Company's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1990 this report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  20. Annual report on radioactive discharges and monitoring of the environment 1990. V. 2

    International Nuclear Information System (INIS)

    1991-01-01

    This Annual Report supplements the Company's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1990 this report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  1. Annual report on radioactive discharges and monitoring of the environment 1990. V. 1

    International Nuclear Information System (INIS)

    1991-01-01

    This Annual Report supplements the Company's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1990 this report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  2. A new method for decontamination of radioactive waste using low-pressure arc discharge

    International Nuclear Information System (INIS)

    Fujiwara, Kazutoshi; Furukawa, Shizue; Adachi, Kazuo; Amakawa, Tadashi; Kanbe, Hiromi

    2006-01-01

    In this paper, the decontamination features of the low-pressure arc-discharge method for radioactive waste generated in the operation and maintenance of nuclear power plants were examined. The low-pressure arc-discharge method was applied to type 304 stainless-steel, type 316L stainless-steel, alloy 600 and carbon-steel covered with radioactive corrosion products. Approximately, 80% of the radioactivity build up on stainless-steels could be removed by the low-pressure arc discharge

  3. Annual report on radioactive discharges and monitoring of the environment 1991. V. 1

    International Nuclear Information System (INIS)

    1992-01-01

    This Annual Report supplements and updates British Nuclear Fuel plc's Health and Safety and the Environment Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical groups doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment since 1977. This year the report is again sub-divided into two complementary volumes. Volume I includes, for each of the Company's sites, annual data on radioactive discharges into the environment and the associated environmental monitoring programmes. Critical groups doses for each site are presented in summary tables at the beginning of each chapter. (author)

  4. Annual report on radioactive discharges and monitoring of the environment, 1996. V. 1

    International Nuclear Information System (INIS)

    1997-01-01

    British Nuclear Fuels Limited (BNFL)'s 1996 report on radioactive discharges from its various sites and monitoring of the surrounding environments are described. For each of the Sellafield, Drigg, Chapelcross, Springfields and Capenhurst sites, details are given on normal operations, radioactive discharges in gaseous, liquid or solid forms, environmental monitoring routines and collective dose and critical group estimates. The second, linked, volume of this report covers certificates of authorisation issued to the company. (UK)

  5. Radioactivity measurements and control solutions

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  6. Radioactive liquid waste discharged from Nuclear Electric licensed sites during 1991

    International Nuclear Information System (INIS)

    Austin, L.S.; Odell, K.J.

    1993-03-01

    This report presents the detailed isotopic composition of radioactive liquid waste discharged from Nuclear Electric licensed sites in 1991. Liquid discharges from those Magnox stations using pond storage of irradiated fuel contained low levels of activation and fission products, while those from Wylfa and the AGR stations contained lower levels of activation products with only traces of fission products. Discharges were similar to those observed in previous years, with any changes concordant with changes in stations' generation performance. (author)

  7. Generic models for use in assessing the impact of discharges of radioactive substances to the environment

    International Nuclear Information System (INIS)

    2001-01-01

    The concern of society in general for the quality of the environment and the realization that all human activities have some environmental effect has led to the development of a procedure for environmental impact analysis. This procedure is a predictive one, which forecasts probable environmental effects before some action, such as the construction and operation of a nuclear power station, is decided upon. The method of prediction is by the application of models that describe the environmental processes in mathematical terms in order to produce a quantitative result which can be used in the decision making process. This report describes such a procedure for application to radioactive discharges and is addressed to the national regulatory bodies and technical and administrative personnel responsible for performing environmental impact analyses. The report is also intended to support the recently published IAEA Safety Guide on Regulatory Control of Radioactive Discharges to the Environment. It expands on and supersedes previous advice published in IAEA Safety Series No. 57 on Generic Models and Parameters for Assessing the Environmental Transfer of Radionuclides from Routine Releases. This Safety Report was developed through a series of consultants meetings and three Advisory Group Meetings

  8. Summary of personnel doses and discharge of radioactivity at Swedish nuclear power plants 1971-1975

    International Nuclear Information System (INIS)

    Malmqvist, L.; Persson, Aa.

    1977-01-01

    The report is a summary of personnel doses and activity discharges from Swedish nuclear power plants during the first five years of electric power production by nuclear plants. The personnel doses for the Sweedish plants are lower than the corresponding values for American plants. The highest Swedish value is o,13 manrem per MWE and year. The discharge of radioactivity to the atmosphere from the Swedish plants has been for below the maximum permissible limits. The discharge of radioactivity to the water recipients was less than 1 % of what is permissible

  9. 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

  10. Radioactive liquid wastes discharged to ground in the 200 areas during 1985

    International Nuclear Information System (INIS)

    Aldrich, R.C.

    1986-03-01

    This document summarizes radioactive liquids discharged to the ground in the 200 areas of the Hanford site and is provided pursuant to Department of Energy (DOE) Order 5484.1A, ''Environmental Protection, Safety, and Health Protection Information Reporting Requirements.'' There are twenty-eight liquid discharge streams in the 200 areas excluding sanitary sewers. Twenty-five streams were normally or potentially contaminated with radioactive material in 1985. Two streams had no potential for radioactive contamination but were included as adjustments in this report to maintain an accurate record of the total volume of the discharges to each disposal site. One stream, the 242-S Evaporator cooling water discharge, was not used during 1985

  11. Annual report on radioactive discharges and monitoring of the environment 1992. V. 1

    International Nuclear Information System (INIS)

    1993-01-01

    This Annual Report supplements and updates the Company's Environment Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment since 1977. This year the report is again sub-divided into two complementary volumes. Volume I consists of site papers, one for each of the Company's sites and includes annual data on radioactive discharges into the environment and the associated environmental monitoring programmes. Critical group doses for each site are presented in summary tables at the beginning of each Site paper. Volume II reproduces the Certificates of Authorisation regulating the Company's discharges and the statutory environmental monitoring programmes which relate to them. (Author)

  12. Flywheel Charge/Discharge Control Developed

    Science.gov (United States)

    Beach, Raymond.F.; Kenny, Barbara H.

    2001-01-01

    A control algorithm developed at the NASA Glenn Research Center will allow a flywheel energy storage system to interface with the electrical bus of a space power system. The controller allows the flywheel to operate in both charge and discharge modes. Charge mode is used to store additional energy generated by the solar arrays on the spacecraft during insolation. During charge mode, the flywheel spins up to store the additional electrical energy as rotational mechanical energy. Discharge mode is used during eclipse when the flywheel provides the power to the spacecraft. During discharge mode, the flywheel spins down to release the stored rotational energy.

  13. Report on radioactive discharges and environmental monitoring at nuclear power stations during 1991

    International Nuclear Information System (INIS)

    Hurst, M.J.; Thomas, D.W.

    1992-09-01

    This report presents the details for 1991 of radioactive discharges and environmental monitoring at Nuclear Electric sites. In addition to the main section which summarises the discharges and monitoring at the Company's nuclear sites as a whole, appendices are presented covering the data in detail for individual sites. In each case the radiological impact on the general public has been estimated. Discharges generally were not substantially different from those of recent years. All radioactive effluent discharges from power stations were within authorised limits. Radiation doses to members of the public resulting from these discharges, and from direct radiation from the Stations, were in all cases less than the limit of 1 mSv per year which has been recommended by ICRP since 1985. (Author)

  14. Elimination of liquid discharge to the environment from the TA-50 Radioactive Liquid Waste Treatment Facility

    International Nuclear Information System (INIS)

    Moss, D.; Williams, N.; Hall, D.; Hargis, K.; Saladen, M.; Sanders, M.; Voit, S.; Worland, P.; Yarbro, S.

    1998-06-01

    Alternatives were evaluated for management of treated radioactive liquid waste from the radioactive liquid waste treatment facility (RLWTF) at Los Alamos National Laboratory. The alternatives included continued discharge into Mortandad Canyon, diversion to the sanitary wastewater treatment facility and discharge of its effluent to Sandia Canyon or Canada del Buey, and zero liquid discharge. Implementation of a zero liquid discharge system is recommended in addition to two phases of upgrades currently under way. Three additional phases of upgrades to the present radioactive liquid waste system are proposed to accomplish zero liquid discharge. The first phase involves minimization of liquid waste generation, along with improved characterization and monitoring of the remaining liquid waste. The second phase removes dissolved salts from the reverse osmosis concentrate stream to yield a higher effluent quality. In the final phase, the high-quality effluent is reused for industrial purposes within the Laboratory or evaporated. Completion of these three phases will result in zero discharge of treated radioactive liquid wastewater from the RLWTF

  15. Elimination of liquid discharge to the environment from the TA-50 Radioactive Liquid Waste Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    Moss, D.; Williams, N.; Hall, D.; Hargis, K.; Saladen, M.; Sanders, M.; Voit, S.; Worland, P.; Yarbro, S.

    1998-06-01

    Alternatives were evaluated for management of treated radioactive liquid waste from the radioactive liquid waste treatment facility (RLWTF) at Los Alamos National Laboratory. The alternatives included continued discharge into Mortandad Canyon, diversion to the sanitary wastewater treatment facility and discharge of its effluent to Sandia Canyon or Canada del Buey, and zero liquid discharge. Implementation of a zero liquid discharge system is recommended in addition to two phases of upgrades currently under way. Three additional phases of upgrades to the present radioactive liquid waste system are proposed to accomplish zero liquid discharge. The first phase involves minimization of liquid waste generation, along with improved characterization and monitoring of the remaining liquid waste. The second phase removes dissolved salts from the reverse osmosis concentrate stream to yield a higher effluent quality. In the final phase, the high-quality effluent is reused for industrial purposes within the Laboratory or evaporated. Completion of these three phases will result in zero discharge of treated radioactive liquid wastewater from the RLWTF.

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

    International Nuclear Information System (INIS)

    1976-01-01

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

  17. Predicting the environmental risks of radioactive discharges from Belgian nuclear power plants

    International Nuclear Information System (INIS)

    Vandenhove, H.; Sweeck, L.; Vives i Batlle, J.; Wannijn, J.; Van Hees, M.; Camps, J.; Olyslaegers, G.; Miliche, C.; Lance, B.

    2013-01-01

    An environmental risk assessment (ERA) was performed to evaluate the impact on non-human biota from liquid and atmospheric radioactive discharges by the Belgian Nuclear Power Plants (NPP) of Doel and Tihange. For both sites, characterisation of the source term and wildlife population around the NPPs was provided, whereupon the selection of reference organisms and the general approach taken for the environmental risk assessment was established. A deterministic risk assessment for aquatic and terrestrial ecosystems was performed using the ERICA assessment tool and applying the ERICA screening value of 10 μGy h −1 . The study was performed for the radioactive discharge limits and for the actual releases (maxima and averages over the period 1999–2008 or 2000–2009). It is concluded that the current discharge limits for the Belgian NPPs considered do not result in significant risks to the aquatic and terrestrial environment and that the actual discharges, which are a fraction of the release limits, are unlikely to harm the environment. -- Highlights: • Impact of radioactive discharges by the Belgian NPPs of Doel and Tihange on wildlife was evaluated. • Deterministic risk assessment for aquatic and terrestrial ecosystems performed with the ERICA tool. • NPP discharge limits do not result in significant risks to the aquatic and terrestrial environment. • Actual discharges, a fraction of the release limits, are unlikely to harm the environment

  18. Device for discharging drain in a control rod driving apparatus

    International Nuclear Information System (INIS)

    Ikeda, Tadasu; Ikuta, Takuzo; Yoshida, Tomiji; Tsukahara, Katsumi.

    1975-01-01

    Object: To efficiently and safely collect and discharge drain by a simple construction in which a drain cover and a drain tank in a control rod driving apparatus are integrally formed, and an overhauling wrench of said apparatus and a drain hose are mounted on the drain tank. Structure: When a mounting bolt is untightened by a torque wrench so as to be removed from a flange surface of the control rod driving apparatus in a nuclear reactor, axial movement of said apparatus is absorbed by a spring so that drain containing a radioactive material is discharged into a drain tank through the flange surface of said apparatus and is then guided into a collecting tank through a drain hose. (Kamimura, M.)

  19. Annual report on radioactive discharges and monitoring of the environment 1991. V. 2

    International Nuclear Information System (INIS)

    1992-01-01

    This Annual Report supplements British Nuclear Fuel plc's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environmental and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1991 this report has been sub-divided into two complementary parts. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  20. Annual report on radioactive discharges and monitoring of the environment 1982

    International Nuclear Information System (INIS)

    1983-08-01

    A report is given on the liquid, airborne and solid radioactive discharges through authorised outlets and on environmental monitoring for all of BNFL's Works and sites for 1982, i.e. Sellafield Site and the Drigg Storage and Disposal Site; Chapelcross Works; Springfields Works and the Ulnes Walton Disposal Site; and Capenhurst Works. The report includes assessment of radiation doses to representative members of the most highly exposed group of the general population for the most important environmental pathways. At no time during 1982 have discharges and disposals of radioactive wastes through authorised outlets at any of the above Works exceeded those laid down in any of the Authorisations. (U.K.)

  1. Annual report on radioactive discharges and monitoring of the environment 1992. V. 2

    International Nuclear Information System (INIS)

    1993-01-01

    This Annual Report supplements British Nuclear Fuel plc's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environmental and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1991 this report has been sub-divided into two complementary parts. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  2. Annual report on radioactive discharges and monitoring of the environment 1981

    International Nuclear Information System (INIS)

    1982-07-01

    A report is given on discharges and disposal of radioactive wastes through authorised outlets and on environmental monitoring for all of BNFL's Company Works and Sites during 1981. At no time during 1981 have discharges and disposals of radioactive wastes at any of the Works or Sites exceeded those laid down in any of the Authorisations. Similarly, environmental monitoring studies have shown that the radiation doses to the most highly exposed group of the general population were significantly lower than the dose limit recommended by the ICRP. (U.K.)

  3. 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

  4. 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.)

  5. 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 contains details of the technologies used at many nuclear power stations to treat and control radioactive discharges and gives, where information was available, details of discharges and authorised discharge limits. (author)

  6. Radioactive waste discharges from UKAEA establishments during 1996 and associated monitoring results

    International Nuclear Information System (INIS)

    Morton, A.K.M.; Forbes, S.A.; Hughes, B.; Richardson, E.

    1997-08-01

    This annual report is published by the Safety Directorate of the United Kingdom Atomic Energy Authority (UKAEA) and provides information on radioactive discharges from its sites. The Culcheth site was closed and then redeveloped during the end of 1993 and the Springfields site became part of BNFL in October 1994. No operations involving the need to discharge radioactivity are undertaken at the Risley site. After discussions with the Authorising Departments at that time, the discharge authorisations were revoked on 1 July 1994. These sites are therefore no longer included in this report. UKAEA has published annual radioactive waste discharges and associated monitoring results since 1963. This report is intended to give a relatively short factual overview of UKAEA waste discharge and disposal, and its impact on the environment. Additional information may be found in annual discharge reports published by the individual UKAEA establishments and the UKAEA Report on Safety and the Environment 1996-97 due to be issued at the end of September 1997. (UK)

  7. Monitoring of radioactive discharges from nuclear power plants

    International Nuclear Information System (INIS)

    Winkelmann, I.; Becker, D.E.; Ruehle, H.

    1994-01-01

    The system of measurement of gaseous and liquid releases from NPP's into the environment in Germany is described. The emissions are continuously monitored by the operators according to uniform regulations and reported to the authorities. The quality of the measurements is assured by officially commissioned experts in accordance with the federal rule. The operators' measurements are supplemented by remote monitoring system operated by the state authorities. The measured discharges are the basis for calculation of the radiation exposure of the public. 5 tabs., 10 refs. (orig.)

  8. Sensitivity of the assessment of public exposure originating from radioactive discharges as a subject of the methodology

    International Nuclear Information System (INIS)

    Krizman, M.J.; Peteh, D.; Vokal Nemec, B.; Cindro, M.

    2007-01-01

    Operational control of nuclear and radiation facilities is partly carried out by continuous monitoring of radioactive discharges into the environment and by direct radioactivity measurements of the environmental samples. The impact of a nuclear or radiation facility is then evaluated in terms of exposure to the public living nearby and in terms of levels of environmental contamination. The dose assessment for the public depends very much on the propositions and scenarios selected by the expert(s), who perform(s) the exposure calculation and on the methodology used. Essential changes of population doses occur when the methodology is changed. The aim of this paper is to present some cases of public exposure based on the data from the environmental radioactivity monitoring programmes, currently performed in Slovenia: for control of global radioactive contamination (atmospheric nuclear tests and Chernobyl) and for control of the Slovenian nuclear and radiation facilities such as the Krsko NPP, the research reactor TRIGA and the radioactive waste storage at Brinje, and the Zirovski vrh uranium mine. There have been significant changes in a dose assessment methodology in the recent years and the resulting dose levels have been changed for one order of magnitude lower or higher values. Public exposure values for five particular sources of contamination versus time of operation are presented as well as the reasons for methodology changes. These changes had to be made due to several reasons, described in the paper. (author)

  9. Gaseous discharge display panel including pilot electrodes and radioactive wire

    International Nuclear Information System (INIS)

    Edwards, R.J.; Hairabedian, B.Z.; Poley, N.M.

    1975-01-01

    In a plasma display panel consisting of gas enclosed between adjacent insulating members, a light source is used to supply charged particles in the gas to permit firing of the gas when coordinate conductors identifying a site location are energized. The use of such pilot lamps facilitates ignition in firing with uniform selection and firing potentials within all sites of the display panel. To eliminate the difficulty in achieving firing during cold starts a radioactive source comprised of a copper wire electroplated with nickel 63 and overcoated with a protective coat of nickel is placed within the gas panel to provide a source of free electrons. The wire is held in place by friction against the inside walls of the panel. Since the wire emits only beta radiation, no radiation hazard exists externally to the panel

  10. Radioactive liquid wastes discharged to ground in the 200 Areas during 1978

    International Nuclear Information System (INIS)

    Anderson, J.D.; Poremba, B.E.

    1979-01-01

    This document is issued quarterly for the purpose of summarizing the radioactive liquid wastes that have been discharged to the ground in the 200 Areas. In addition to data for 1978, cumulative data since plant startup are presented. Also, in this document is a listing of decayed activity to the various plant sites

  11. Radioactivity in gaseous waste discharged from the separations facilities during 1978

    International Nuclear Information System (INIS)

    Anderson, J.D.; Poremba, B.E.

    1979-01-01

    This document is issued quarterly for the purpose of summarizing the radioactive gaseous wastes that are discharged from the facilities of the Rockwell Hanford Operations. Data on alpha and beta emissions during 1978 are presented where relevant to the gaseous effluent. Emission data are not included on gaseous wastes produced within the 200 Areas by other Hanford contractors

  12. Development of Data Base on Radioactive Discharges and Environmental Activity Levels in Slovenia

    International Nuclear Information System (INIS)

    Vokal, B.; Krizman, M.

    2003-01-01

    Radioactivity monitoring in the environment in Slovenia has been currently performed on a regular basis as a monitoring of global radioactive contamination and as operational monitoring in the surroundings of facilities with radioactive discharges. Environmental radioactivity monitoring due to atmospheric nuclear bomb tests in Slovenia started in 1961, while monitoring of radioactive discharges from nuclear facilities in Slovenia started in early 1980s with the extent programmes: in the Krsko nuclear power plant in 1981, in the uranium mining and milling facility at Zirovski vrh (1985) and in the research reactor at Brinje near Ljubljana (1986). Both categories of the results are documented in written reports and sent to the competent authorities, mostly on annual basis. According to the requirements of the European Commission (Commission Recommendation of 8. June 2000 on the application of Article 36 of the Euratom Treaty concerning the monitoring of the levels of the radioactivity in the environment for the purpose of assessing the exposure of the population as a whole (2000/473/Euratom) and Commission Recommendation of 6. December 1999 on the application of Article 37 of the Euratom Treaty (1999/829/Euratom)) and on initiative of the IAEA (IAEA Document International Atomic Energy Agency (IAEA). Project International Data base on Discharges of Radioactive Material to the Environment, 2000) the Slovenian Nuclear Safety Administration (SNSA) started in 2002 with development of the computerised data base on environmental data and radioactive discharges data for the most facilities, specially for the nuclear fuel cycle. At present the environmental database contains the data on global contamination of air, surface waters, tap water sources and food chain (1 37C s, 9 0S r) and also on levels of major natural radionuclides (7 B e, 2 10P b, 2 26R a, 4 0K ). Data base on radioactive discharges for the recent years comprises the activities of fission and activation

  13. Annual report on radioactive discharges and monitoring of the environment 1990. V. 2

    International Nuclear Information System (INIS)

    1991-01-01

    This Annual Report supplements the Health and Safety Annual Report of British Nuclear Fuels plc by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. This report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. The sites involved are: Sellafield where the main activities are irradiated nuclear fuel reprocessing and the Calder Hall nuclear station; the Drigg radioactive waste storage and disposal site; the Chapelcross nuclear power station; Springfields Works which manufactures nuclear fuels; Capenhurst Works where uranium isotopic enrichment plants are operated. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  14. Annual report on radioactive discharges and monitoring of the environment 1990. V. 1

    International Nuclear Information System (INIS)

    1991-01-01

    This Annual Report supplements the Health and Safety Annual Report of British Nuclear Fuels plc by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. This report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. The sites involved are: Sellafield where the main activities are irradiated nuclear fuel reprocessing and the Calder Hall nuclear station; the Drigg radioactive waste storage and disposal site; the Chapelcross nuclear power station; Springfields Works which manufactures nuclear fuels; Capenhurst Works where uranium isotopic enrichment plants are operated. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  15. Presence of radioactivity in a sewage system: a proposal for radioactivity control

    International Nuclear Information System (INIS)

    Serradell, Vicente; Ballesteros, Luisa; Ortiz, Josefina

    2008-01-01

    Most hospitals use radioisotopes in diagnostics and to a lesser extent in therapy. The liquid residues thus generated are usually subjected to treatment before being discharged into the sewage system. Nevertheless, a certain amount of these residues escape from the treatment system and are poured directly into the sewer. In addition, other radioactive products used for research and industrial purposes may also be disposed of in the same way. The waste waters in many sewage systems can therefore be expected to be radiologically contaminated and the need for at least a basic control system in such situations seems obvious. When designing a procedure to measure radioactivity, certain conditions should be borne in mind: 1) The control program has to be simple and inexpensive; 2) Samples must be taken from the appropriate places; 3) Short life radionuclides will probably be present in significant amounts, so that specific recipes should be prepared; 4) Iodine is also frequently present. Special precautions should be taken to keep it in solution. In recent years, the Environmental Radioactivity Laboratory of the Universidad Politecnica de Valencia (Spain) has carried out a series of tests on the Valencia city sewage system and sewage treatment plant in order to design a permanent program to control radioactive contamination of the city's sewage system. This paper presents a proposal which we believe can provide the answer to this problem. (author)

  16. Discharge control and evolution in TFTR

    International Nuclear Information System (INIS)

    Mueller, D.; Bell, M.; Boody, F.; Bush, C.; Cecchi, J.L.; Davis, S.; Dylla, H.F.; Efthimion, P.C.

    1985-01-01

    The Tokamak Fusion Test Reactor (TFTR) was designed to explore plasma confinement and heating at reactor-like parameters. Operation of both the toroidal field and plasma current at full design parameters has been achieved and the plasma parameters are summarized in this work. Control of the discharge evolution has played an important role in attaining these parameters. The control of impurities in a tokamak is largely a result of the choice of limiter and wall materials, conditioning techniques and gettering. The impurity control procedures adopted during the run period ending April 13, 1985 are discussed. The discussion of discharge evolution and control is broken down into discharge initiation, volt-second consumption, current and density ramp-up and ramp-down. Also discussed is control of the current ramp-up using a plasma growing technique and the control of density using gas puffing, pellet injection and neutral beam fueling, along with a discussion of the density range which is found to increase plasma current

  17. Annual report on radioactive discharges and monitoring of the environment 1986

    International Nuclear Information System (INIS)

    1987-01-01

    British Nuclear Fuels plc (BNFL) provides a comprehensive range of nuclear fuel cycle services, ie the purification and processing of uranium ore concentrates, the enrichment of uranium, the manufacture of uranium and plutonium based fuels, the reprocessing of irradiated fuel, and the conditioning and storage of nuclear materials and radioactive wastes. Some of these activities give rise to discharges of radioactive isotopes to the environment. This annual report follows the pattern established in 1977 in that it gives information on radioactive discharges, through authorised and scheduled outlets, and on environmental monitoring for all of the Company's Works and sites, ie Sellafield Site and the Drigg Storage and Disposal Site; Chapelcross Works; Springfield Works and the Ulnes Walton Disposal Site; and Capenhurst Works. Where a site also encompasses laboratories of the United Kingdom Atomic Energy Authority (UKAEA) reference is made to the significance of the discharges from the latter. It also includes assessment of radiation doses to representative members of the most highly exposed group of the general population (the critical group) for the most important environmental pathways in the vicinity of each site. Information for the period 1971-76 inclusive has also been published by BNFL and prior to 1971, the year in which BNFL was formed, information was published by the UKAEA. An appendix contains certificates of Authorisation granted by the DOE, MAFF and Scottish Office imposing limits and conditions relating to methods of disposal and quantities to be discharged. (author)

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

    International Nuclear Information System (INIS)

    Ludwieg, F.

    1976-01-01

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

  19. 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)

  20. Annual report on radioactive discharges and monitoring of the environment 1984

    International Nuclear Information System (INIS)

    1985-01-01

    Information is given on the liquid, airborne, and solid radioactive discharges through authorised outlets, and on environmental monitoring for all of BNFL's works and sites for 1984; ie Sellafield site and Drigg storage and disposal site; Chapelcross works; Springfields works and Ulnes Walton disposal site; Capenhurst works. Included is assessment of radiation doses to representative members of the most highly exposed group of the general population for the most important environmental pathways. (author)

  1. BPEO as a Guide to Decision Making in the Authorisation of Radioactive Waste Discharges

    International Nuclear Information System (INIS)

    Egan, Michael; Collier, David; Stone, Andrew; Keep, Matthew

    2003-01-01

    The Environment Agency (EA) and the Scottish Environment Protection Agency (SEPA) are the independent public bodies responsible for regulating the disposal of radioactive wastes in the UK in order to ensure protection of people and the environment. Operators at nuclear sites must obtain authorisation from the relevant Agency, granted under the Radioactive Substances Act 1993 (RSA93), in order to make disposals of radioactive waste. Draft Statutory Guidance to the EA on the Regulation of Radioactive Discharges into the Environment from Nuclear Licensed Sites was published by the Government in October 2000. The Guidance establishes an obligation on the EA to ensure that proper consideration is given to the identification and evaluation of alternatives, in order to ensure that the Best Practicable Environmental Option (BPEO) is chosen, before authorisations can be granted. Such a requirement supplements and reinforces current regulatory practice in the UK, whereby nuclear site operators may be required (under Improvement Conditions attached to existing authorisations) to review waste management strategies on a regular basis in order to demonstrate that they represent the BPEO. SEPA shares a common interest with EA in use of the BPEO concept in the regulation of radioactive waste management, for both operational licensing and decommissioning projects. There has been no single standard methodology or guidance to Agency staff on application of the BPEO concept to radioactive waste management. BPEO studies presented by nuclear site operators have therefore been considered on a case-by-case basis. In the light of this, and taking account of the specific requirements emerging from the new Statutory Guidance, EA and SEPA have jointly supported the development of guidance for use by the Agencies in reviewing and assessing BPEO studies submitted in relation to authorisations granted under RSA93. This paper describes activities that have been undertaken to support the

  2. Annual report on radioactive discharges and monitoring of the environment 1980

    International Nuclear Information System (INIS)

    1981-07-01

    A report is given on radioactive discharges through authorised outlets and on environmental monitoring for all of British Nuclear Fuels Limited Works and Sites, i.e. the Windscale and Calder Works and the Drigg Storage and Disposal Site; Chapelcross Works; Springfields Works and the Ulnes Walton Disposal Site; and Capenhurst Works. The report includes information on liquid and airborne radioactive effluents and solid radioactive waste at each of the Company's Works and Sites. Assessments are made of maximum radiological exposures to individual members of the public expressed in terms of limits based on ICRP recommendations and in accordance with advice given by the NRPB. The report showed that at no time during 1980 did discharges and disposals of radioactive wastes through authorised outlets at any of the Works exceed those laid down in any of the Authorisations. Environmental monitoring studies also showed that the radiation exposure in 1980 of the most highly exposed groups of the general population was significantly lower than the Annual Limit recommended by the ICRP. (U.K.)

  3. Radioactivity analysis of food and accuracy control

    International Nuclear Information System (INIS)

    Ota, Tomoko

    2013-01-01

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

  4. Predicting the environmental risks of radioactive discharges from Belgian nuclear power plants.

    Science.gov (United States)

    Vandenhove, H; Sweeck, L; Vives I Batlle, J; Wannijn, J; Van Hees, M; Camps, J; Olyslaegers, G; Miliche, C; Lance, B

    2013-12-01

    An environmental risk assessment (ERA) was performed to evaluate the impact on non-human biota from liquid and atmospheric radioactive discharges by the Belgian Nuclear Power Plants (NPP) of Doel and Tihange. For both sites, characterisation of the source term and wildlife population around the NPPs was provided, whereupon the selection of reference organisms and the general approach taken for the environmental risk assessment was established. A deterministic risk assessment for aquatic and terrestrial ecosystems was performed using the ERICA assessment tool and applying the ERICA screening value of 10 μGy h(-1). The study was performed for the radioactive discharge limits and for the actual releases (maxima and averages over the period 1999-2008 or 2000-2009). It is concluded that the current discharge limits for the Belgian NPPs considered do not result in significant risks to the aquatic and terrestrial environment and that the actual discharges, which are a fraction of the release limits, are unlikely to harm the environment. Copyright © 2013 Elsevier Ltd. All rights reserved.

  5. Regulatory Control of Radioactive Sources in Spain

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez, M.; Martin, J.L., E-mail: mrm@csn.es [Nuclear Safety Council, Madrid (Spain)

    2011-07-15

    The arrangements for the regulatory control of the safety and security of sealed radioactive sources in Spain are described. Emphasis is given to the situations which are most likely to result in the loss of control of sources and on the procedures introduced to reduce the likelihood of losses in these cases. Finally, the strategy for locating sources which have been lost from control (orphan sources) is described. (author)

  6. Quality control in the radioactive waste management

    International Nuclear Information System (INIS)

    Rzyski, B.M.

    1989-01-01

    Radioactive waste management as in industrial activities must mantain in all steps a quality control programme. This control extended from materials acquisition, for waste treatment, to the package deposition is one of the most important activities because it aims to observe the waste acceptance criteria in repositories and allows to guarantee the security of the nuclear facilities. In this work basic knowledges about quality control in waste management and some examples of adopted procedures in other countries are given. (author) [pt

  7. Control of sealed radioactive sources in Peru

    International Nuclear Information System (INIS)

    Ramirez Quijada, R.

    2001-01-01

    The paper describes the inventory of radioactive sources in Peru and assesses the control. Three groups of source conditions are established: controlled sources, known sources, and lost and orphan sources. The potential risk, described as not significant, for producing accidents is established and the needed measures are discussed. The paper concludes that, while the control on sealed sources is good, there is still room for improvement. (author)

  8. The IAEA and Control of Radioactive Sources

    International Nuclear Information System (INIS)

    Dodd, B.

    2004-01-01

    The presentation discusses the authoritative functions and the departments of the IAEA, especially the Department of Nuclear Safety and Security and its Safety and Security of Radiation Sources Unit. IAEA safety series and IAEA safety standards series inform about international standards, provide underlying principles, specify obligations and responsibilities and give recommendations to support requirements. Other IAEA relevant publications comprise safety reports, technical documents (TECDOCs), conferences and symposium papers series and accident reports. Impacts of loss of source control is discussed, definitions of orphan sources and vulnerable sources is given. Accidents with orphan sources, radiological accidents statistic (1944-2000) and its consequences are discussed. These incidents lead to development of the IAEA guidance. The IAEA's action plan for the safety of radiation sources and the security of radioactive material was approved by the IAEA Board of Governors and the General Conference in September 1999. This led to the 'Categorization of Radiation Sources' and the 'Code of Conduct on the Safety and Security of Radioactive Sources'. After 0911 the IAEA developed a nuclear security plan of activities including physical protection of nuclear material and nuclear facilities, detection of malicious activities involving nuclear and other radioactive materials, state systems for nuclear material accountancy and control, security of radioactive material other than nuclear material, assessment of safety and security related vulnerability of nuclear facilities, response to malicious acts, or threats thereof, adherence to and implementation of international agreements, guidelines and recommendations and nuclear security co-ordination and information management. The remediation of past problems comprised collection and disposal of known disused sources, securing vulnerable sources and especially high-risk sources (Tripartite initiative), searching for

  9. Integrated Computer Controlled Glow Discharge Tube

    Science.gov (United States)

    Kaiser, Erik; Post-Zwicker, Andrew

    2002-11-01

    An "Interactive Plasma Display" was created for the Princeton Plasma Physics Laboratory to demonstrate the characteristics of plasma to various science education outreach programs. From high school students and teachers, to undergraduate students and visitors to the lab, the plasma device will be a key component in advancing the public's basic knowledge of plasma physics. The device is fully computer controlled using LabVIEW, a touchscreen Graphical User Interface [GUI], and a GPIB interface. Utilizing a feedback loop, the display is fully autonomous in controlling pressure, as well as in monitoring the safety aspects of the apparatus. With a digital convectron gauge continuously monitoring pressure, the computer interface analyzes the input signals, while making changes to a digital flow controller. This function works independently of the GUI, allowing the user to simply input and receive a desired pressure; quickly, easily, and intuitively. The discharge tube is a 36" x 4"id glass cylinder with 3" side port. A 3000 volt, 10mA power supply, is used to breakdown the plasma. A 300 turn solenoid was created to demonstrate the magnetic pinching of a plasma. All primary functions of the device are controlled through the GUI digital controllers. This configuration allows for operators to safely control the pressure (100mTorr-1Torr), magnetic field (0-90Gauss, 7amps, 10volts), and finally, the voltage applied across the electrodes (0-3000v, 10mA).

  10. Report on radioactive discharges and environmental monitoring at nuclear sites during 1988

    International Nuclear Information System (INIS)

    Short, A.; Davies, A.R.

    1989-09-01

    The details of radioactive discharges from and environmental monitoring in the vicinity of nuclear sites in the Untied Kingdom are presented. The highest predicted dose, resulting from a station's liquid discharges, was to a small group of fish eaters at Trawsfynydd, and is estimated at 120μSv. This is lower than in previous years. Based on the measurements made in marine samples, the dose to a group of fish and shellfish eaters at Heysham is estimated at 160μSv and the external dose to a group living and working on the tidal mud-flats of the nearby Lune Estuary, 120μSv. Only a small fraction of these doses can be attributed to discharges from Heysham. Discharges of Ar-41 are highest from stations with shield cooling air systems. In 1988, the maximum predicted dose associated with Ar-41 releases occurred at Sizewell and was calculated to be 60μSv. At some stations there is a contribution from direct radiation from the plant at locations in close proximity to the boundary fence. In 1988, the estimated highest dose from this source was 0.7mSv and occurs at Bradwell. Radiation doses to members of the public, resulting from discharges and from direct radiation were, in all cases, less than the principal limit of 1mSv/year recommended by ICRP. (author)

  11. Airborne radioactive emission control technology. Volume II

    International Nuclear Information System (INIS)

    Skoski, L.; Berlin, R.; Corby, D.; Clancy, J.; Hoopes, G.

    1980-03-01

    This report reviews the current and future control technology for airborne emissions from a wide variety of industries/facilities, including uranium mining and milling, other nuclear fuel cycle facilities, other NRC-licensed and DOE facilities, fossil fuel facilities, selected metal and non-metal extraction industries, and others. Where specific radioactivity control technology is lacking, a description of any existing control technology is given. Future control technology is assessed in terms of improvements to equipment performance and process alterations. A catalogue of investigated research on advanced control technologies is presented

  12. Airborne radioactive emission control technology. Volume III

    International Nuclear Information System (INIS)

    Skoski, L.; Berlin, R.; Corby, D.; Clancy, J.; Hoopes, G.

    1980-03-01

    This report reviews the current and future control technology for airborne emissions from a wide variety of industries/facilities, including uranium mining and milling, other nuclear fuel cycle facilities, other NRC-licensed and DOE facilities, fossil fuel facilities, selected metal and non-metal extraction industries, and others. Where specific radioactivity control technology is lacking, a description of any existing control technology is given. Future control technology is assessed in terms of improvements to equipment performance and process alterations. A catalogue of investigated research on advanced control technologies is presented

  13. Airborne radioactive emission control technology. Volume I

    International Nuclear Information System (INIS)

    Skoski, L.; Berlin, R.; Corby, D.; Clancy, J.; Hoopes, G.

    1980-03-01

    This report reviews the current and future control technology for airborne emissions from a wide variety of industries/facilities, includimg uranium mining and milling, other nuclear fuel cycle facilities, other NRC-licensed and DOE facilities, fossil fuel facilities, selected metal and non-metal extraction industries, and others. Where specific radioactivity control technology is lacking a description of any existing control technology is given. Future control technology is assessed in terms of improvements to equipment performance and process alterations. A catalogue of investigated research on advanced control technologies is presented

  14. Annual report on radioactive discharges and monitoring of the environment 1993. V. 2: Certificates of authorisation and environmental monitoring programmes

    International Nuclear Information System (INIS)

    1994-01-01

    British Nuclear Fuels plc's Certificates of Authorisation, under which it operates, are reproduced in the second volume of the 1993 Annual Report on Radioactive Discharges and Monitoring of the Environment. The report also includes environmental monitoring programmes relating to discharge authorisation for each of the Sellafield, Drigg, Chapelcross, Springfields and Capenhurst sites. (UK)

  15. Product control of radioactive waste

    International Nuclear Information System (INIS)

    Warnecke, E.; Giller, H.

    1989-09-01

    The aim of the seminar was to give a survey of product quality control and to find out whether the producers/conditioners of waste set and fulfil requirements for the quality of the waste. The program included the following main areas: Random sample tests; Container tests; Process qualification and inspection, and Inspections of waste from fuel element reprocessing abroad. In other lectures, there are reports on measures for producers of waste for guaranteeing the final storage requirements, on quality assurance measurements in the conditioning of waste from large research establishments and from fuel element manufacture. The calling up of waste containers and the documentation of waste data is also introduced. (orig./HP) [de

  16. A procedure for estimating site specific derived limits for the discharge of radioactive material to the atmosphere

    CERN Document Server

    Hallam, J; Jones, J A

    1983-01-01

    Generalised Derived Limits (GDLs) for the discharge of radioactive material to the atmosphere are evaluated using parameter values to ensure that the exposure of the critical group is unlikely to be underestimated significantly. Where the discharge is greater than about 5% of the GDL, a more rigorous estimate of the derived limit may be warranted. This report describes a procedure for estimating site specific derived limits for discharges of radioactivity to the atmosphere taking into account the conditions of the release and the location and habits of the exposed population. A worksheet is provided to assist in carrying out the required calculations.

  17. 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)

  18. Assessment of prospective foodchain doses from radioactive discharges from BNFL Sellafield

    International Nuclear Information System (INIS)

    Ould-Dada, Z.; Tucker, S.; Webbe-Wood, D.; Mondon, K.; Hunt, J.

    2002-01-01

    This paper presents the method used by the UK Food Standards Agency (FSA) to assess the potential impact of proposed radioactive discharges from the Sellafield nuclear site on food and determine their acceptability. It explains aspects of a cautious method that has been adopted to reflect the UK government policy and uncertainties related to people's habits with regard to food production and consumption. Two types of ingestion doses are considered in this method: 'possible' and 'probable' doses. The method is specifically applied to Sellafield discharge limits and calculated possible and probable ingestion doses are presented and discussed. Estimated critical group ingestion doses are below the dose limit and constraint set for members of the public. The method may be subject to future amendments to take account of changes in government policy and the outcome of a recent Consultative Exercise on Dose Assessments carried out by FSA. Uncertainties inherent in dose assessments are discussed and quantified wherever possible

  19. Toxicity limitation on radioactive liquid waste discharge at OPG Nuclear Stations

    International Nuclear Information System (INIS)

    Dobson, T.; Lovasic, Z.; Nicolaides, G.

    2000-01-01

    This paper describes the Municipal and Industrial Strategy for Abatement (MISA) regulation, which came into effect in 1995 in Ontario (Ontario Regulation 215/95 under the Environmental Protection Act). This imposed additional limitations on liquid discharges from power generating stations. The MISA regulation has divided discharges into non-event and event streams, which have to be monitored for the prescribed parameters and for toxicity. Radioactive Waste Management Systems fall into the category of non-event streams. Standard toxicity testing involves monitoring lethality of Daphnia Magna and Rainbow trout in the effluent. The new legislation has imposed a need to address several issues: acute toxicity, complying with the specific limits prescribed by the regulation and, in the long run chronic toxicity

  20. The control of radioactive sources in Brazil

    International Nuclear Information System (INIS)

    Oliveira, S.M.V.; Menezes, C.F.; Alves Filho, A.D.; Xavier, A.M.

    1998-01-01

    The radiological accident of Goiania in 1987 brought to light several deficiencies in the licensing of medical, industrial and research facilities, which handle radioisotopes, as well as in the control of radioactive sources in Brazil. The article describes some of the technical and administrative measures taken to ensure the adoption of appropriate radiological safety standards throughout the country and thereby reduce the incidence of radiological accidents. (author)

  1. Facility for remote filling and discharging of containers and tanks in nuclear power plants with radioactive concentrates and sorbents

    International Nuclear Information System (INIS)

    Kucharik, D.

    1987-01-01

    The facility consists of a remote controlled filling and discharge head pressed with a pneumatic cylinder to the container adapters. The head is provided with hoses for the feeding and/or withdrawal of the concentrate and for container ventilation. It is suspended on the pneumatic cylinder which is mounted on a revolving arm. On the pin of the revolving arm there is a drip tray which captures drops of the concentrate when the container has been filled and the head unsealed. The ball valves in the container adapters are electromagnetically controlled. The machine serves to mechanize certain manual operations, improves work safety and reduces contact of personnel with radioactive concentrates. (J.B.). 1 fig

  2. Inadequate control of world's radioactive sources

    International Nuclear Information System (INIS)

    2002-01-01

    The radioactive materials needed to build a 'dirty bomb' can be found in almost any country in the world, and more than 100 countries may have inadequate control and monitoring programs necessary to prevent or even detect the theft of these materials. The IAEA points out that while radioactive sources number in the millions, only a small percentage have enough strength to cause serious radiological harm. It is these powerful sources that need to be focused on as a priority. In a significant recent development, the IAEA, working in collaboration with the United States Department of Energy (DOE) and the Russian Federation's Ministry for Atomic Energy (MINATOM), have established a tripartite working group on 'Securing and Managing Radioactive Sources'. Through its program to help countries improve their national infrastructures for radiation safety and security, the IAEA has found that more than 100 countries may have no minimum infrastructure in place to properly control radiation sources. However, many IAEA Member States - in Africa, Asia, Latin America, and Europe - are making progress through an IAEA project to strengthen their capabilities to control and regulate radioactive sources. The IAEA is also concerned about the over 50 countries that are not IAEA Member States (there are 134), as they do not benefit from IAEA assistance and are likely to have no regulatory infrastructure. The IAEA has been active in lending its expertise to search out and secure orphaned sources in several countries. More than 70 States have joined with the IAEA to collect and share information on trafficking incidents and other unauthorized movements of radioactive sources and other radioactive materials. The IAEA and its Member States are working hard to raise levels of radiation safety and security, especially focusing on countries known to have urgent needs. The IAEA has taken the leading role in the United Nations system in establishing standards of safety, the most significant of

  3. Control of radioactive waste-glass melters

    International Nuclear Information System (INIS)

    Bickford, D.F.; Smith, P.K.; Hrma, P.; Bowan, B.W.

    1987-01-01

    Radioactive waste-glass melters require physical control limits and redox control of glass to assure continuous operation, and maximize production rates. Typical waste-glass melter operating conditions, and waste-glass chemical reaction paths are discussed. Glass composition, batching and melter temperature control are used to avoid the information of phases which are disruptive to melting or reduce melter life. The necessity and probable limitations of control for electric melters with complex waste feed compositions are discussed. Preliminary control limits, their bases, and alternative control methods are described for use in the Defense Waste Processing Facility (DWPF) at the US Department of Energy's Savannah River Plant (SRP), and at the West Valley Demonstration Project (WVDP). Slurries of simulated high level radioactive waste and ground glass frit or glass formers have been isothermally reacted and analyzed to identify the sequence of the major chemical reactions in waste vitrification, and their effect on waste-glass production rates. Relatively high melting rates of waste batches containing mixtures of reducing agents (formic acid, sucrose) and nitrates are attributable to exothermic reactions which occur at critical stages in the vitrification process. The effect of foaming on waste glass production rates is analyzed, and limits defined for existing waste-glass melters, based upon measurable thermophysical properties. Through balancing the high nitrate wastes of the WVDP with reducing agents, the high glass melting rates and sustained melting without foaming required for successful WVDP operations have been demonstrated. 65 refs., 4 figs., 15 tabs

  4. Liquid discharges from the Ringhals and Barsebaeck nuclear power plants. Report to the OSPAR commission in accordance with PARCOM recommendation 91/4 on radioactive discharges

    International Nuclear Information System (INIS)

    2000-05-01

    With regard to the general objectives of the Convention for the Protection of the Marine Environment of the North-East Atlantic (OSPAR Convention), the contracting parties have agreed, as stated in PARCOM Recommendation 91/4 on Radioactive Discharges, to apply best available technique (BAT) to reduce radioactive releases from the nuclear industry. Progress in implementing BAT shall be reported to the OSPAR Commission every four years. This report contains the Swedish submission for the third round of implementation reporting according to PARCOM Recommendation 91/4. The data provided are relevant to the Ringhals NPP which discharge into Convention waters, and the Barsebaeck NPP which discharge into waters close to the Convention area. The report was submitted to the Commission in December 1999

  5. Liquid discharges from the Ringhals and Barsebaeck nuclear power plants. Report to the OSPAR commission in accordance with PARCOM recommendation 91/4 on radioactive discharges

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-05-01

    With regard to the general objectives of the Convention for the Protection of the Marine Environment of the North-East Atlantic (OSPAR Convention), the contracting parties have agreed, as stated in PARCOM Recommendation 91/4 on Radioactive Discharges, to apply best available technique (BAT) to reduce radioactive releases from the nuclear industry. Progress in implementing BAT shall be reported to the OSPAR Commission every four years. This report contains the Swedish submission for the third round of implementation reporting according to PARCOM Recommendation 91/4. The data provided are relevant to the Ringhals NPP which discharge into Convention waters, and the Barsebaeck NPP which discharge into waters close to the Convention area. The report was submitted to the Commission in December 1999.

  6. Seasonal changes in mRNA encoding for cell stress markers in the oyster Crassostrea gigas exposed to radioactive discharges in their natural environment

    International Nuclear Information System (INIS)

    Farcy, Emilie; Voiseux, Claire; Lebel, Jean-Marc; Fievet, Bruno

    2007-01-01

    The North Cotentin area (Normandy, France) hosts several nuclear facilities among which the AREVA reprocessing plant of La Hague is responsible for controlled discharges of liquid radioactive wastes into the marine environment. The resulting increase in radioactivity is very small compared to natural radioactivity. However, concerns about environment protection prompted the scientific community to focus on the effects of the chronic exposure to low concentrations of radionuclides in non-human biota. This study contributes to the evaluation of the possible impact of radioactive discharges on the oyster Crassostrea gigas in the field. Real-time polymerase chain reaction was used to quantify the expression levels of genes involved in cell stress in the oyster. They included members of the heat shock protein family (Hsp70, Hsc72, Hsp90), superoxide dismutase (SOD) and metallothionein (MT). Times series measurements were built from periodic samplings in the natural environment in order to characterize the natural variability as well as possible seasonal fluctuations. The genes studied exhibited a general seasonal expression pattern with a peak value in winter. The data inversely correlated with seawater temperature and the nature of the relationship between gene expression and temperature is discussed. In parallel, oysters were collected in four locations on the French shores, exposed or not to radioactive liquid wastes from the nuclear facilities hosted in the North Cotentin. The comparison of data obtained in the reference location on the Atlantic coast (not exposed) and data from oysters of the English Channel (exposed) gave no evidence for any statistical difference. However, because of the complexity of the natural environment, we cannot rule out the possibility that other parameters may have masked the impact of radioactive discharges. This dense set of data is a basis for the use of the expression levels of those genes as biomarkers to address the question of the

  7. Guide for the control and recording of radioactive wastes

    International Nuclear Information System (INIS)

    1987-01-01

    This guide present the aspects related to the control and recording of radioactive wastes in their points of origin. Then it is of great importance to fulfill these instructions so as to achieve a successful management of radioactive waste

  8. Method of controlling radioactive waste processing systems

    International Nuclear Information System (INIS)

    Mikawa, Hiroji; Sato, Takao.

    1981-01-01

    Purpose: To minimize the pellet production amount, maximize the working life of a solidifying device and maintaining the mechanical strength of pellets to a predetermined value irrespective of the type and the cycle of occurrence of the secondary waste in the secondary waste solidifying device for radioactive waste processing systems in nuclear power plants. Method: Forecasting periods for the type, production amount and radioactivity level of the secondary wastes are determined in input/output devices connected to a control system and resulted signals are sent to computing elements. The computing elements forecast the production amount of regenerated liquid wastes after predetermined days based on the running conditions of a condensate desalter and the production amounts of filter sludges and liquid resin wastes after predetermined days based on the liquid waste processing amount or the like in a processing device respectively. Then, the mass balance between the type and the amount of the secondary wastes presently stored in a tank are calculated and the composition and concentration for the processing liquid are set so as to obtain predetermined values for the strength of pellets that can be dried to solidify, the working life of the solidifying device itself and the radioactivity level of the pellets. Thereafter, the running conditions for the solidifying device are determined so as to maximize the working life of the solidifying device. (Horiuchi, T.)

  9. Radioactive hospital wastes. Radiations under control

    International Nuclear Information System (INIS)

    Bondeelle, A.; Delmotte, H.; Gauron, C.

    2006-07-01

    A set of articles proposes an overview of legal and regulatory evolutions regarding radioactive hospital wastes. These legal measures and evolutions are notably present in the Public Health code, in the Labour code. An article outlines the role of the radiation protection expert in the process of elimination of contaminated wastes (four major steps for this elimination are indicated; peculiarities of the hospital are outlined, as well as control procedures and the importance of training and information). An article describes the specific activity of the Creteil incinerator which comprises a unit for the incineration of care activity wastes under a very constraining regulation

  10. [Automatic adjustment control system for DC glow discharge plasma source].

    Science.gov (United States)

    Wan, Zhen-zhen; Wang, Yong-qing; Li, Xiao-jia; Wang, Hai-zhou; Shi, Ning

    2011-03-01

    There are three important parameters in the DC glow discharge process, the discharge current, discharge voltage and argon pressure in discharge source. These parameters influence each other during glow discharge process. This paper presents an automatic control system for DC glow discharge plasma source. This system collects and controls discharge voltage automatically by adjusting discharge source pressure while the discharge current is constant in the glow discharge process. The design concept, circuit principle and control program of this automatic control system are described. The accuracy is improved by this automatic control system with the method of reducing the complex operations and manual control errors. This system enhances the control accuracy of glow discharge voltage, and reduces the time to reach discharge voltage stability. The glow discharge voltage stability test results with automatic control system are provided as well, the accuracy with automatic control system is better than 1% FS which is improved from 4% FS by manual control. Time to reach discharge voltage stability has been shortened to within 30 s by automatic control from more than 90 s by manual control. Standard samples like middle-low alloy steel and tin bronze have been tested by this automatic control system. The concentration analysis precision has been significantly improved. The RSDs of all the test result are better than 3.5%. In middle-low alloy steel standard sample, the RSD range of concentration test result of Ti, Co and Mn elements is reduced from 3.0%-4.3% by manual control to 1.7%-2.4% by automatic control, and that for S and Mo is also reduced from 5.2%-5.9% to 3.3%-3.5%. In tin bronze standard sample, the RSD range of Sn, Zn and Al elements is reduced from 2.6%-4.4% to 1.0%-2.4%, and that for Si, Ni and Fe is reduced from 6.6%-13.9% to 2.6%-3.5%. The test data is also shown in this paper.

  11. Recent UK Experience of Involving the Public in Decisions on Radioactive Discharges

    International Nuclear Information System (INIS)

    Smith, R.E.; Weedon, C.J.; McGoff, A.; Bower, M.

    2001-01-01

    In January 1998 BNFL applied to the Agency for authorisations to dispose of gaseous, liquid, combustible and solid radioactive wastes in respect of each of Magnox Electric's power stations. The Agency is currently considering BNFL's applications. This is the first time that authorisations for radioactive waste disposal have been considered for all these stations together as a package. It has been a major task for BNFL to assemble all the relevant information and for the Agency to drive the process forward through public consultation to the decision-making stage. As part of its role of protecting and improving the environment, the Agency is committed to progressive reductions in radioactive discharges where practicable, seeking to achieve this through the limits and conditions of any authorisation it issues. It aims to review nuclear site authorisations on a four-yearly cycle and has used BNFL's applications as the basis for its review of the Magnox power station sites. The Agency carefully scrutinised the applications and obtained additional detailed information and clarification from BNFL in response to six rounds of questions. The applications and responses from the company to Agency questions were made publicly available. They include information on: the benefits and detriments of continued operation/decommissioning (as appropriate); the sources and amounts of radioactive waste associated with continued operation/decommissioning; the current levels of discharge of radioactive waste to the environment; and the application of best practicable means (BPM) to minimise discharges. The Agency is considering all the application information and must decide, separately for each power station, whether an authorisation should be issued to BNFL. It has consulted publicly to assist its decision making, the objective being to enable people and organisations to draw to the Agency's attention any matters they would wish it to consider when reaching its decisions on the

  12. Recent UK Experience of Involving the Public in Decisions on Radioactive Discharges

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.E. [Environment Agency, London (United Kingdom); Weedon, C.J. [Environment Agency, Penrith (United Kingdom); McGoff, A.; Bower, M. [Environment Agency, Bedford (United Kingdom)

    2001-07-01

    In January 1998 BNFL applied to the Agency for authorisations to dispose of gaseous, liquid, combustible and solid radioactive wastes in respect of each of Magnox Electric's power stations. The Agency is currently considering BNFL's applications. This is the first time that authorisations for radioactive waste disposal have been considered for all these stations together as a package. It has been a major task for BNFL to assemble all the relevant information and for the Agency to drive the process forward through public consultation to the decision-making stage. As part of its role of protecting and improving the environment, the Agency is committed to progressive reductions in radioactive discharges where practicable, seeking to achieve this through the limits and conditions of any authorisation it issues. It aims to review nuclear site authorisations on a four-yearly cycle and has used BNFL's applications as the basis for its review of the Magnox power station sites. The Agency carefully scrutinised the applications and obtained additional detailed information and clarification from BNFL in response to six rounds of questions. The applications and responses from the company to Agency questions were made publicly available. They include information on: the benefits and detriments of continued operation/decommissioning (as appropriate); the sources and amounts of radioactive waste associated with continued operation/decommissioning; the current levels of discharge of radioactive waste to the environment; and the application of best practicable means (BPM) to minimise discharges. The Agency is considering all the application information and must decide, separately for each power station, whether an authorisation should be issued to BNFL. It has consulted publicly to assist its decision making, the objective being to enable people and organisations to draw to the Agency's attention any matters they would wish it to consider when reaching its

  13. Wire chamber radiation detector with discharge control

    International Nuclear Information System (INIS)

    Perez-Mendez, V.; Mulera, T.A.

    1984-01-01

    A wire chamber radiation detector has spaced apart parallel electrodes and grids defining an ignition region in which charged particles or other ionizing radiations initiate brief localized avalanche discharges and defining an adjacent memory region in which sustained glow discharges are initiated by the primary discharges. Conductors of the grids at each side of the memory section extend in orthogonal directions enabling readout of the X-Y coordinates of locations at which charged particles were detected by sequentially transmitting pulses to the conductors of one grid while detecting transmissions of the pulses to the orthogonal conductors of the other grid through glow discharges. One of the grids bounding the memory region is defined by an array of conductive elements each of which is connected to the associated readout conductor through a separate resistance. The wire chamber avoids ambiguities and imprecisions in the readout of coordinates when large numbers of simultaneous or near simultaneous charged particles have been detected. Down time between detection periods and the generation of radio frequency noise are also reduced

  14. A methodology for the evaluation of collective doses arising from radioactive discharges to the atmosphere

    International Nuclear Information System (INIS)

    Hallam, J.; Linsley, G.S.

    1980-01-01

    The ICRP recommend the use of optimisation as a means of ensuring that the total detriment from any practice is appropriately small in relation to the benefit resulting from its introduction. The calculation of total health detriment requires the evaluation of the complete dose distribution throughout the irradiated population from all isotopes via all pathways. This paper describes methods for the evaluation of collective dose, which may be used in the assessment of detriment. The stages in the assessment of collective dose from an atmospheric release can be summarised as follows: (1) An atmospheric dispersion model is used to evaluate the spatial distribution of activity and thereby the dose to an individual from inhalation and external irradiation at any position with respect to the discharge point. (2) The UK population distribution on a 1 x 1 km grid is then used for the evaluation of collective dose from these pathways. (3) Foodchain models are used to estimate the radioactivity per unit mass in a range of different foodstuffs per unit deposition rate or surface deposit. (4) The distribution of agricultural practices in the UK on a 5 x 5 km grid, taken together with the atmospheric dispersion model allows the estimation of the total activity reaching man via food, and hence the collective dose. This combination of models and data arrays allows assessments to be made of the collective dose due to atmospheric releases of radioactive materials at any geographical location in the United Kingdom. (author)

  15. Radioactive discharges and environmental monitoring at the Swedish nuclear facilities 2001; Utslaepps- och omgivningskontroll vid de kaerntekniska anlaeggningarna 2001

    Energy Technology Data Exchange (ETDEWEB)

    Sandwall, Johanna

    2002-11-01

    This report contains an evaluation of the discharge and environmental programme for the Swedish nuclear facilities. It also contains the work on quality control performed by SSI. This is done as random sampling of discharge water and environmental samples.

  16. Radioactive demonstration of DWPF product control strategy

    International Nuclear Information System (INIS)

    Andrews, M.K.; Bibler, N.E.

    1992-01-01

    The effectiveness of the product and process control strategies that will be utilized by the Defense Waste Processing Facility (DWPF) was demonstrated during a campaign in the Shielded Cells Facility (SCF) of the Savannah River Technology Center (SRTC). The remotely operated process included the preparation of the melter feed, vitrification in a slurry-fed 1/100th scale melter and analysis of the glass product both for its composition and durability. The campaign processed approximately 10 kg (on a dry basis) of radioactive sludge from Tank 51. This sludge is representative of the first batch of sludge that will be sent to the DWPF for immobilization into borosilicate glass. Additions to the sludge were made based on calculations using the Product Composition Control System (PCCS). Analysis of the glass produced during the campaign showed that a durable glass was produced with a composition similar to that predicted using the PCCS

  17. Neural control of phrenic motoneuron discharge

    Science.gov (United States)

    Lee, Kun-Ze; Fuller, David D.

    2011-01-01

    Phrenic motoneurons (PMNs) provide a synaptic relay between bulbospinal respiratory pathways and the diaphragm muscle. PMNs also receive propriospinal inputs, although the functional role of these interneuronal projections has not been established. Here we review the literature regarding PMN discharge patterns during breathing and the potential mechanisms that underlie PMN recruitment. Anatomical and neurophysiological studies indicate that PMNs form a heterogeneous pool, with respiratory-related PMN discharge and recruitment patterns likely determined by a balance between intrinsic MN properties and extrinsic synaptic inputs. We also review the limited literature regarding PMN bursting during respiratory plasticity. Differential recruitment or rate modulation of PMN subtypes may underlie phrenic motor plasticity following neural injury and/or respiratory stimulation; however this possibility remains relatively unexplored. PMID:21376841

  18. Contribution to the study of radioactive and heavy jets discharged in the presence of a cross-stream

    International Nuclear Information System (INIS)

    Badre, A.

    1981-01-01

    A mathematical model is presented for the prediction of spreading and rising of radioactive and heavy jets discharged into a flowing ambient fluid. The model is based on the differential equations for the conversion of mass, momentum, concentration and thermal energy. The model has been tested by comparing the results with experimental data concerning atmospheric dispersion of gaseous effluents [fr

  19. Environmental radioactive contamination and its control for nuclear power plants

    International Nuclear Information System (INIS)

    Shi Zhongqi; Qu Jingyuan; Cui Yongli

    1998-01-01

    The environmental radioactive releases and exposure to human being due to operation of nuclear power plants in the world and in China, environmental contamination and consequences caused by severe nuclear power plant accidents in the history, control of the radioactive contamination in China, and some nuclear laws on the radioactive contamination control established by international organizations and USA etc. are described according to literature investigation and research. Some problems and comments in radioactive contamination control for nuclear power plants in China are presented. Therefore, perfecting laws and regulations and enhancing surveillances on the contamination control are recommended

  20. Radioactive demonstration of DWPF product control strategy

    International Nuclear Information System (INIS)

    Andrews, M.K.; Bibler, N.E.

    1994-01-01

    The Defense Waste Processing Facility at the Savannah River Site (SRS) will vitrify high-level nuclear waste into borosilicate glass. The waste will be mixed with properly formulated glass-making frit and fed to a melter at 1150 degrees C. Process reliability and product quality are ensured by proper control of the melter feed composition. The effectiveness of the product and process control strategies that will be utilized by the Defense Waste Processing Facility (DWPF) was demonstrated during a campaign in the Shielded Cells Facility of the Savannah River Technology Center (SRTC). The remotely operated process included the preparation of the melter feed, vitrification in a slurry-fed 1/100th scale melter an analysis of the glass product both for its composition an durability. The campaign processed approximately 10 kg (on a dry basis) of radioactive sludge from Tank 51. This sludge is representative of the first batch of sludge that will be sent to the DWPF for immobilization into borosilicate glass. Additions to the sludge were made based on calculations using the Product Composition Control System (PCCS). Analysis of the glass produced during the campaign showed that a durable glass was produced with a composition very close to that predicted using the PCCS. 10 refs., 4 tabs

  1. Preliminary design of HL-2A discharge control system

    International Nuclear Information System (INIS)

    Jiang Chao; Song Xianming; Li Qiang

    2001-01-01

    HL-2A Discharge Control System consists of one or more VXI work stations so as to compose an all digital control system. The DCS are used to measure and control the poloidal coils, the main tasks of the poloidal coils are exploding, keeping and controlling the current of plasma. These coils explode plasma and keep it in the determined position

  2. The impact of radioactive discharges on native British wild-life and the implications for environmental protection

    International Nuclear Information System (INIS)

    Woodhead, D.

    1998-01-01

    In the context of managing and regulating radioactive waste disposal in the UK, the aim has been to limit the radiation exposure of humans within nationally accepted dose rate limits and to constrain exposures to be as low as reasonably achievable (ALARA). In practice, a system of radiological control has been applied to protect more restricted 'critical groups' within the human population who, through their habits, are likely to receive the highest radiation exposures. This has had the effect of ensuring that the overall average radiation exposure of an individual member of the UK general public from radioactive waste disposal to the environment is a small fraction of the relevant dose rate limit. The radiological protection of the environment per se has received little explicit regulatory attention. Indeed, there are no criteria currently defined specifically for the protection of the environment. The aims of this report are to: determine how far currently available environmental information provides support for the current UK regulatory approach to radioactive discharges and disposal; identify significant gaps or key uncertainties in information and define research required in order for the Environment Agency to meet the requirements of the current legislation; and, provide guidance on the Environment Agency's regulatory approach to protecting the environment in the context of the current legislation and international developments. To meet these objectives, the terms of reference have been re-interpreted as to: determine the current regulatory position in respect of the protection of the environment from the effects of incremental radiation exposure arising from any aspect of the UK radioactive waste management programme; provide a critical review of the available assessments of the radiation exposure of native wild organisms from both the natural background and the radionuclide contamination of the environment arising from human activities; review available

  3. Annual report on radioactive discharges and monitoring of the environment 1979

    International Nuclear Information System (INIS)

    1980-07-01

    This report gives information on radioactive discharges through authorised outlets and on environmental monitoring, for all of the British Nuclear Fuel Company's Works and Sites ie the Windscale and Calder Works and the Drigg Storage and Disposal site; Chapelcross Works; Springfields Works and the Ulnes Walton Disposal Site; and Capenhurst Works. Where a site also encompasses laboratories of the United Kingdom Atomic Energy Authority (UKAEA) reference is made to the significance of the discharges from the latter. The report includes assessment of maximum radiological exposures to individual members of the public expressed in terms of limits based on the recommendations of the International Commission on Radiological Protection (ICRP) and in accordance with advice given by the National Radiological Protection Board (NRPB) on the application of the Commission's recommendations in the UK. It is recognised that certain consequences of exposure are believed not to occur unless a threshold dose to a particular part of the body is exceeded and that other possible consequences can be evaluated by computing an effective dose equivalent. In both cases limits are stated, the latter being 5 millisievert (500 millirem) per annum, together with the comment that it would be prudent to restrict actual continuous exposure over a whole lifetime to an average of 1 millisievert (100 millirem) per annum. The assessments are based on data recommended by ICRP. Where these data are not yet available the assessments are based on data published by NRPB as interim recommendations. The percentage of the effective dose equivalent limit is quoted together with the individual contributions to it. Where other limits, which are 'threshold' in nature and cannot be summed, are apparently more restrictive a textual comment is made. (author)

  4. 10 CFR 39.69 - Radioactive contamination control.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Radioactive contamination control. 39.69 Section 39.69... Radiation Safety Requirements § 39.69 Radioactive contamination control. (a) If the licensee detects evidence that a sealed source has ruptured or licensed materials have caused contamination, the licensee...

  5. Method of controlling plasma discharge in a thermonuclear device

    International Nuclear Information System (INIS)

    Kawasaki, Kozo; Ishida, Takayuki; Takemaru, Koichi; Kawasaki, Takahide.

    1982-01-01

    Purpose: To prolong the plasma discharging period by previously increasing the temperature at the thick portion of a vacuum container prior to the plasma discharge to thereby decrease the temperature difference caused by the plasma discharge between the thick portion and the bellows. Method: Temperature values at the outer surface of the thick portion and the bellows of a vacuum container detected by temperature sensors are applied to the input processing section of a temperature control device, and baking control is carried out by way of the output processing section so that each of the portions of the vacuum container may be maintained at the temperature set by the temperature setting section based on the calculation performed in the control processing section. By previously increasing the temperature β at the thick portion higher by about 100 0 C than the temperature α for the bellows in the baking treatment prior to the plasma discharge, the plasma discharge period during which the temperature levels at both of the portions are reversed after the plasma discharge and the temperature difference arrives at a predetermined level i.g., of 100 0 C can significantly be prolonged as compared with the case where the plasma discharge is started at the same temperature for both of the portions. (Yoshino, Y.)

  6. Real time equilibrium reconstruction for tokamak discharge control

    International Nuclear Information System (INIS)

    Ferron, J.R.; Walker, M.L.; Lao, L.L.; St John, H.E.; Humphreys, D.A.; Leuer, J.A.

    1998-01-01

    A practical method for performing a tokamak equilibrium reconstruction in real time for arbitrary time varying discharge shapes and current profiles is described. An approximate solution to the Grad-Shafranov equilibrium relation is found which best fits the diagnostic measurements. Thus, a solution for the spatial distribution of poloidal flux and toroidal current density is available in real time that is consistent with plasma force balance, allowing accurate evaluation of parameters such as discharge shape and safety factor profile. The equilibrium solutions are produced at a rate sufficient for discharge control. This equilibrium reconstruction algorithm has been implemented on the digital plasma control system for the DIII-D tokamak. The first application of real time equilibrium reconstruction to discharge shape control is described. (author)

  7. The reduction of radioactive discharges from mine workings: rehabilitation results conducted by WISMUTH GmbH

    International Nuclear Information System (INIS)

    Knoch-Weber, J.

    2002-01-01

    With operations designed to rehabilitate uranium mining operations terminated in late 1990 running for ten years now, significant progress is evident at all sites of Wismut GmbH. Of the total of DM 13 billion earmarked by the federal authorities in 1991 for the implementation of this exceptionally large environmental restoration project, about DM 6.7 billion were spent by the end of 2000, and of this DM 3.7 billion for the remediation of sites located in Eastern Thuringia and DM 3 billion for sites located in Saxony. Safe shutdown of underground mine workings remains an essential remediation task at all former mining sites. Following international standard practices, the preferred option retained called for flooding of the underground workings, i.e. cessation of water pumping and filling of mine workings by the naturally rising ground water level. Filling and sealing of mines is aimed at achieving geomechanical stabilisation of the ground surface and at reducing and/or avoiding gaseous and aerosolised radioactive discharges into the environment as a source of mine-related public exposure. (orig.)

  8. A model to calculate exposure from radioactive discharges into the coastal waters of Northern Europe

    International Nuclear Information System (INIS)

    Clark, M.J.; Grimwood, P.D.; Camplin, W.C.

    1980-11-01

    A regional marine model is described which can be used to estimate the exposure of populations as a result of the discharge of radioactive effluents into the coastal waters of Northern Europe. The model simulates the dispersion of radionuclides in marine waters, Their interaction with marine sediments and the concentration mechanisms occurring in seafoods. There is a local/regional interface defined in the modelling approach whereby releases are assumed to first enter a local marine compartment prior to widespread dispersion in coastal waters. Depletion mechanisms operate within both the local and regional environments influencing the fraction of radionuclide release which contributes to collective exposure. General results of the regional marine model are presented in a form which can be combined with independent local marine models; collective intakes per unit release of various radionuclides into coastal waters are given for a series of integration times. For caesium-137 and plutonium-239 collective effective dose equivalent commitments have been calculated using a defined local marine model. Some general conclusions have been drawn from the results and there is some discussion of the various features of the modelling approach. (author)

  9. Annual report on radioactive discharges and monitoring of the environment 1978

    International Nuclear Information System (INIS)

    1979-07-01

    The report gives information on radioactive discharges and environmental monitoring for all the Works and Sites of British Nuclear Fuels Ltd. Where a site also encompasses laboratories of the United kingdom Atomic Energy Authority (UKAEA) reference is made to the latter. The report includes assessment of maximum radiological exposures to individual members of the public based on the recommendations of the International Commission on Radiological Protection (ICRP) as advised by the National Radiological Protection Board (NRPB). This year account is taken of new recommendations, ICRP 26, which emphasise the importance of justification and optimisation of practices leading to radiological exposure, and revises the method for evaluating the significance of such exposure. This method recognises that certain consequences of exposure are believed not to occur unless a threshold dose to a particular part of the body is exceeded and that other possible consequences can be evaluated by computing an effective dose equivalent. In both cases limits are stated, the latter being numerically equal to the previous 5 millisievert (500 millirem) per annum whole body dose limit. In addition ICRP comment that it would be prudent to restrict actual continuous exposure over a whole life time to within an average of 1 millisievert (100 millirem) per annum. The assessments are based on data published by NRPB as interim recommendations until ICRP data becomes available. (author)

  10. Investigation of the sources and fate of radioactive discharges to public sewers

    International Nuclear Information System (INIS)

    Titley, J.; Carey, A.; Crockett, G.

    2000-01-01

    The practise of disposing of small amounts of liquid radioactive waste from non-nuclear organisations to public sewer systems, is currently being reviewed by the Environment Agency, Scottish Environmental Protection Agency and the Industrial Pollution and Radiochemical Inspectorate. Changing sewage treatment and disposal practises, particularly the increasing use of incineration to treat sewage sludge in urban areas, have prompted this review. This study was undertaken as part of the review process to determine whether disposal into the public sewer system remains a safe disposal option. This report describes a study to investigate the sources and fates of authorised discharges of radionuclides into the sewer system. Sewage transport, treatment, discharge and incineration systems are described and the fate of radionuclides in the systems considered. A model (SMART) was developed to predict radionuclide behaviour through these systems and calculate the resulting doses. Case studies of two large urban sewerage systems were carried out in Leeds and Central London. Leeds is served by one sewage treatment works at Knostrop, which receives disposals of ten radionuclides from six disposers. Up to seven of the radionuclides were measurable in effluents, sludges or incinerator ash at the works. Naturally occurring and fallout radionuclides were also detected. Central London is served by one large works at Beckton which receives disposals of twenty radionuclides from 65 disposers. Up to ten of the disposed radionuclides, plus naturally occurring and fallout radionuclides were detected in effluents, sludges, incinerator cake or ash at Beckton. For both sites the largest authorised disposals were of Tc-99m, C-14, I-125, I-131 and H-3. The behaviour of radionuclides during incineration was assessed using measurements and literature values. The radiological implications of disposals in Leeds and Central London were assessed using the model SMART and by measuring dose rates

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

    Science.gov (United States)

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

    2017-11-15

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

  12. 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

  13. 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

  14. Transporting dynamics of radioactive cesium in a forest ecosystem and its discharge processes

    Energy Technology Data Exchange (ETDEWEB)

    Iseda, Kohei; Ohte, Nobuhito; Tanoi, Keitaro; Endo, Izuki; Oda, Tomoki; Kato, Hiroyu [Graduate School of Agricultural and Life Sciences, University of Tokyo (Japan)

    2014-07-01

    A lot of radioactive substance including {sup 137}Cs, {sup 134}Cs fell out to Tohoku and Kanto region in particular Fukushima prefecture after the accident of Fukushima-daiichi nuclear power plant. Generally, cesium tends to attach to clay particle and organic matter. These clay particle and organic matter can potentially flow out from the forest through the river to the downstream not only as particulate matter but also dissolved matter. It is likely that behavior of cesium is similar to sediment locomotion. The objective of this study is to understand transporting dynamics of radioactive cesium inside and outside of the forest. We started investigations on transporting dynamics of cesium in the forest upper stream of Kami-Oguni river in Date city Fukushima prefecture located in about 50 km from the nuclear power plant since July 2012. We conducted river water sampling at 9 points along the river from the uppermost stream to the middle reaches during low flow condition once a month. We also sampled river water during storm event for 5 times in order to capture the change of {sup 137}Cs concentration in a flood stage. Samples were filtered and separated into particulate and dissolved matters using glass micro-fiber filters (GF/F). Samples were analyzed their {sup 137}Cs concentration by Germanium semiconductor detector at University of Tokyo. During low flow condition, {sup 137}Cs was detected only a very small amount both in particulate and dissolved matters. In contrast, during high flow condition, {sup 137}Cs was detected about 10-100 times higher than that of during low flow condition in particulate matter. We estimated discharge flux of {sup 137}Cs from the forest using the relations between water discharge and {sup 137}Cs concentration. It was 0.977 Bq/(m2 day ) (2012/8/31-2013/4/19). In the forest, we set 2 deciduous tree plots (Quercus serrata, Zelkova serrata and so on) and 1 evergreen confer plot (Cyptomeria japonica). Atmospheric depositions of {sup 137

  15. A solar charge and discharge controller for wireless sensor nodes

    Science.gov (United States)

    Dang, Yibo; Shen, Shu

    2018-02-01

    Aiming at the energy supply problem that restricts the life of wireless sensor nodes, a solar energy charge and discharge controller suitable for wireless sensor nodes is designed in this paper. A Microcontroller is used as the core of the solar charge and discharge controller. The software of the solar charge and discharge controller adopts the C language to realize the program of the main control module. Firstly, the function of monitoring solar panel voltage and lithium battery voltage are simulated by Protel software, and the charge time is tested in cloudy and overcast outdoor environment. The results of the experiment show that our controller meets the power supply demand of wireless sensor nodes.

  16. Controlling low-level radioactive waste

    International Nuclear Information System (INIS)

    1990-01-01

    This series of information sheets describes at a popular level the sources of low-level radioactive wastes, their associated hazards, methods of storage, transportation and disposal, and the Canadian regulations that cover low-level wastes

  17. Real-time control for long ohmic alternate current discharges

    International Nuclear Information System (INIS)

    Carvalho, Ivo S.; Duarte, Paulo; Fernandes, Horácio; Valcárcel, Daniel F.; Carvalho, Pedro J.; Silva, Carlos; Duarte, André S.; Neto, André; Sousa, Jorge; Batista, António J.N.; Hekkert, Tiago; Carvalho, Bernardo B.; Gomes, Rui B.

    2014-01-01

    Highlights: • 40 Alternate plasma current (AC) semi-cycles without loss of ionization, more than 1 s of operation. • AC discharges automatic control: feedback loops, time-windows control strategy, goal oriented time-windows and exception handling. • Energy deposition and Carbon radiation evolution during the AC discharges. - Abstract: The ISTTOK tokamak has a long tradition on alternate plasma current (AC) discharges, but the old control system was limiting and lacked full system integration. In order to improve the AC discharges performance the ISTTOK fast control system was updated. This control system developed on site based on the Advanced Telecommunications Computing Architecture (ATCA) standard now integrates the information gathered by all the tokamak real-time diagnostics to produce an accurate observation of the plasma parameters. The real-time actuators were also integrated, allowing a Multiple Input Multiple Output (MIMO) control environment with several synchronization strategies available. The control system software was developed in C++ on top of a Linux system with the Multi-threaded Application Real-Time executor (MARTe) Framework to synchronize the real-time code execution under a 100μs control cycle. In addition, to simplify the discharge programming, a visual Human–Machine Interface (HMI) was also developed using the BaseLib2 libraries included in the MARTe Framework. This paper presents the ISTTOK control system and the optimizations that extended the AC current discharges duration to more than 1 s, corresponding to 40 semi-cycles without apparent degradation of the plasma parameters. This upgrade allows ISTTOK to be used as a low-cost material testing facility with long time exposures to nuclear fusion relevant plasmas, comparable (in duration) with medium size tokamaks

  18. Real-time control for long ohmic alternate current discharges

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Ivo S., E-mail: ivoc@ipfn.ist.utl.pt; Duarte, Paulo; Fernandes, Horácio; Valcárcel, Daniel F.; Carvalho, Pedro J.; Silva, Carlos; Duarte, André S.; Neto, André; Sousa, Jorge; Batista, António J.N.; Hekkert, Tiago; Carvalho, Bernardo B.; Gomes, Rui B.

    2014-05-15

    Highlights: • 40 Alternate plasma current (AC) semi-cycles without loss of ionization, more than 1 s of operation. • AC discharges automatic control: feedback loops, time-windows control strategy, goal oriented time-windows and exception handling. • Energy deposition and Carbon radiation evolution during the AC discharges. - Abstract: The ISTTOK tokamak has a long tradition on alternate plasma current (AC) discharges, but the old control system was limiting and lacked full system integration. In order to improve the AC discharges performance the ISTTOK fast control system was updated. This control system developed on site based on the Advanced Telecommunications Computing Architecture (ATCA) standard now integrates the information gathered by all the tokamak real-time diagnostics to produce an accurate observation of the plasma parameters. The real-time actuators were also integrated, allowing a Multiple Input Multiple Output (MIMO) control environment with several synchronization strategies available. The control system software was developed in C++ on top of a Linux system with the Multi-threaded Application Real-Time executor (MARTe) Framework to synchronize the real-time code execution under a 100μs control cycle. In addition, to simplify the discharge programming, a visual Human–Machine Interface (HMI) was also developed using the BaseLib2 libraries included in the MARTe Framework. This paper presents the ISTTOK control system and the optimizations that extended the AC current discharges duration to more than 1 s, corresponding to 40 semi-cycles without apparent degradation of the plasma parameters. This upgrade allows ISTTOK to be used as a low-cost material testing facility with long time exposures to nuclear fusion relevant plasmas, comparable (in duration) with medium size tokamaks.

  19. Evaluating future detriment from radioactive discharges Judgements and implications for optimisation of protection

    CERN Document Server

    Fleishman, A B

    1982-01-01

    For long-lived nuclides released into the environment, it is possible to calculate dose commitments extending over thousands or millions of years. The inclusion of this detriment to future populations in present day decision-making is not a technical matter, but represents an area where judgement must be applied. This report shows how different judgements on the relative valuation of future doses can have significant implications for the management of radioactive effluents. A quantitative framework for the expression of such judgements is proposed for optimisation studies, to clarify for decision-makers these implications in the assessment of alternative management options. This is based on the economic principles of discounting, but is related to the use of incomplete collective dose commitments (truncated in time), and includes a zero discount rate which assigns the same weight to doses whenever received. The framework is applied to a series of potential management options for the control of carbon-14, kryp...

  20. Control of radioactive material transport in sodium-cooled reactors

    International Nuclear Information System (INIS)

    Brehm, W.F.

    1980-03-01

    The Radioactivity Control Technology (RCT) program was established by the Department of Energy to develop and demonstrate methods to control radionuclide transport to ex-core regions of sodium-cooled reactors. This radioactive material is contained within the reactor heat transport system with any release to the environment well below limits established by regulations. However, maintenance, repair, decontamination, and disposal operations potentially expose plant workers to radiation fields arising from radionuclides transported to primary system components. This paper deals with radioactive material generated and transported during steady-state operation, which remains after 24 Na decay. Potential release of radioactivity during postulated accident conditions is not discussed. The control methods for radionuclide transport, with emphasis on new information obtained since the last Environmental Control Symposium, are described. Development of control methods is an achievable goal

  1. Problems of control of radioactive waste

    International Nuclear Information System (INIS)

    Doi, Kazumi

    2000-01-01

    The isolation period of high level radioactive waste from human biotope is some ten thousand years or more. Especially, many crustal movement zones are located in our country, so that very careful measures should be taken. Isolation of high level radioactive waste in lithosphere needs to confirm good isolation site. Boring is a chief method to determine the location conditions for radioactive waste. In order to study crack of rock and behavior of groundwater, high density of drilling must be necessary. However, high density drilling should be avoided. In place of it, a geophysical exploration is an ideal method, one of non-destructive inspection. It is important for many countries to establish the technologies to determine the conditions of crack and groundwater by this method. A large amount of data about the contact condition of radionuclide and minerals, pH, oxidative-reduction potential and temperature are needed. (S.Y.)

  2. Control of Radioactive Lightning-Conductor

    International Nuclear Information System (INIS)

    Esposito, E.

    2004-01-01

    The radioactive lightning-conductor production in Brazil was started in 1970 and after a period of 19 years of commercialization of these devices, the National Nuclear Energy Commission (CNEN), based in studies done in Brazil and abroad, proved that the radioactive lightning-conductor performance wasn't superior to the conventional one, so the use of radioactive source is not justified. Thence, the authorization for its production was suspended and the installation of this type of lightning-conductor was forbidden. The radioactive material that results from the dismount of these devices must be immediately sent to CNEN, for treatment and temporary storage. After this prohibition and its publication in several specialized magazines, CNEN was searched for several institutions, factories, churches, etc, interested in obtaining information about the handling and shipment procedures of radioactive lightning-conductors that are inoperative and that must be sent to CNEN's Institutes, in a correct and secure form. From this moment CNEN technicians realize that the owners of radioactive lightning-conductors didn't have any knowledge and training in radiation protection, neither in equipment to monitoring the radiation. The radioactive material from these sources is, in almost all cases, the radioisotope 241Am which has a maximum activity of an order of 5 mCi (1,85 x 10-2 TBq); as the radiation emitted by 241Am is of alpha type, whose range in the air, is just few centimeters and the gamma rays are of low energy, an irradiation offer small risk. However, there is a contamination risk on someone hands, by the contact with the source. Aiming to attend, in an objective way, the users' interests in obtaining some pertinent technical information about the shipping of radioactive lightning-conductor that is inoperative or is being replaced and also to optimize its receipt in CNEN's Institutes, because there still has a great number of these lightning-conductors installed and still

  3. Control of radiocaesium discharges to the Irish Sea: ICRP-26 in practice

    International Nuclear Information System (INIS)

    Handyside, I.; Hunt, G.J.; Partington, C.

    1982-01-01

    Experience of application of the ICRP dose limitation system is described in the context of control of radioactive waste discharges to the north-east Irish Sea from the British Nuclear Fuels Limited (BNFL) Sellafield Works. The radiological significance of these discharges is mainly due to radiocaesium from the magnox fuel storage ponds. The discharges increased in 1974 owing to corrosion of magnox fuel; radiation exposure of the public mainly through the fish and shellfish consumption pathway also increased. BNFL, in consultation with Government Departments, decided to install an ion-exchange treatment plant to remove radioactivity from pond effluents. This plant is presently being built and will provide a long-term reduction in radiocaesium discharges. Optimization will play a major part in determining its operating regime. Meanwhile, measures to reduce discharges have been taken by circulating pond water through skips of zeolite installed in the ponds. Differential cost-benefit analysis has been used to indicate the optimum replacement rate of skips; experience of this is described. A range of skip costs was used to allow for some factors which were not uniquely definable. Detrimental costs were estimated from collective dose commitments and a range of values of the man-Sv from Pound 2000 to Pound 50,000. Other, non-quantifiable, factors were relevant. Following these considerations, the current skip replacement frequency is about 30 year -1 . Skips are presently reducing collective effective dose equivalent commitments to the UK and European populations by about half, or some 150 man-Sv.year -1 . Finally, to demonstrate conformity with the overall ICRP dose limitation system, compliance with dose limits is described. Effective dose equivalents to the relevant critical groups for the years 1977 to 1980 are presented. The use of zeolite skips has, here too, given significant reductions over this time, from 33% to (provisionally) 15% of the ICRP-recommended dose

  4. Radiological discharges

    International Nuclear Information System (INIS)

    Woodliffe, J.

    1990-01-01

    Current practice of North Sea States on the discharge and disposal of liquid radioactive wastes to the North Sea are based on the declaration issued at the Second International Conference on the Protection of the North Sea, known as the London Declaration. This has three main points the first of which emphasises the application of the Best Available Technology to protect the North Sea, the second provides a framework on which future controls on radioactive discharges should be based. The third identifies two parts of the framework; to take into account the recommendations of international organizations and that any repositories of radioactive waste which are built should not pollute the North Sea. This chapter looks at how the concensus based on the London Declaration is working, gauges the progress made in the implementation of the policy goal, identifies existing and future areas for concern and proposes ways of strengthening the control of radioactive discharges. The emphasis is on the United Kingdom practice and regulations for liquid wastes, most of which comes from the Sellafield Reprocessing Plant. (author)

  5. Radioactive wastes and residues: government participation in a control policy

    International Nuclear Information System (INIS)

    Gelli, Guido

    1993-01-01

    This paper discusses the politic aspects of the State participation in inspection and control of the radioactive wastes residues with the supervise of Brazilian Nuclear Energy Commission (CNEN), by a national program

  6. Method for controlling incineration in combustor for radioactive wastes

    International Nuclear Information System (INIS)

    Takaoku, Y.; Uehara, A.

    1991-01-01

    This invention relates to a method for controlling incineration in a combustor for low-level radioactive wastes. In particular, it relates to a method for economizing in the consumption of supplemental fuel while maintaining a stable incineration state by controlling the amount of fuel and of radioactive wastes fed to the combustor. The amount of fuel supplied is determined by the outlet gas temperature of the combustor. (L.L.)

  7. Radioactive material inventory control at a waste characterization facility

    International Nuclear Information System (INIS)

    Yong, L.K.; Chapman, J.A.; Schultz, F.J.

    1996-01-01

    Due to the recent introduction of more stringent Department of Energy (DOE) regulations and requirements pertaining to nuclear and criticality safety, the control of radioactive material inventory has emerged as an important facet of operations at DOE nuclear facilities. In order to comply with nuclear safety regulations and nuclear criticality requirements, radioactive material inventories at each nuclear facility have to be maintained below limits specified for the facility in its safety authorization basis documentation. Exceeding these radioactive material limits constitutes a breach of the facility's nuclear and criticality safety envelope and could potentially result in an accident, cause a shut-down of the facility, and bring about imminent regulatory repercussions. The practice of maintaining control of radioactive material, especially sealed and unsealed sources, is commonplace and widely implemented; however, the requirement to track the entire radioactivity inventory at each nuclear facility for the purpose of ensuring nuclear safety is a new development. To meet the new requirements, the Applied Radiation Measurements Department at Oak Ridge National Laboratory (ORNL) has developed an information system, called the open-quotes Radioactive Material Inventory Systemclose quotes (RMIS), to track the radioactive material inventory at an ORNL facility, the Waste Examination and Assay Facility (WEAF). The operations at WEAF, which revolve around the nondestructive assay and nondestructive examination of waste and related research and development activities, results in an ever-changing radioactive material inventory. Waste packages and radioactive sources are constantly being brought in or taken out of the facility; hence, use of the RMIS is necessary to ensure that the radioactive material inventory limits are not exceeded

  8. Annual report on radioactive discharges from Winfrith and monitoring the environment 1991

    International Nuclear Information System (INIS)

    1992-05-01

    This annual report, the seventh, aims to provide full information on our discharges and environmental monitoring. The report is mainly graphical, comparing past and current levels with authorised limits, derived limits or the recommended limits of the International Commission on Radiological Protection (ICRP). Discharges from Winfrith are subject to Authorisations issued jointly by the Department of the Environment (DOE) and the Ministry of Agriculture, Fisheries and Food (MAFF). These Authorisations, one for discharges to the sea and one for discharges to the atmosphere, require that Winfrith establish a need to discharge; that we apply Best Practicable Means (BPM) to reduce our discharges; that our discharges are below set Authorised Limits; and that schedules of effluent and environmental monitoring are established. As a 'back stop', discharges at the limits must not result in doses to the most potentially exposed part of the local population - the critical group -exceeding 0.5 mSv per year. The limit recommended by the International Commission on Radiological Protection (ICRP) for dose to a member of the general public is 1.0 mSv per year. In September 1990 Winfrith's Steam Generating Heavy Water Reactor (SGHWR) was shut down therefore the pattern of discharges for 1991 differs from previous years. Discharges are generally reduced resulting in an even lower dose to the critical group, well below 1% of the ICRP limit and much less than 1% of the UK average natural background dose. (author)

  9. Evaluating future detriment from radioactive discharges: Judgements and implications for optimisation of protection

    International Nuclear Information System (INIS)

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

    1982-04-01

    For long-lived nuclides released into the environment, it is possible to calculate dose commitments extending over thousands or millions of years. The inclusion of this detriment to future populations in present day decision-making is not a technical matter, but represents an area where judgement must be applied. This report shows how different judgements on the relative valuation of future doses can have significant implications for the management of radioactive effluents. A quantitative framework for the expression of such judgements is proposed for optimisation studies, to clarify for decision-makers these implications in the assessment of alternative management options. This is based on the economic principles of discounting, but is related to the use of incomplete collective dose commitments (truncated in time), and includes a zero discount rate which assigns the same weight to doses whenever received. The framework is applied to a series of potential management options for the control of carbon-14, krypton-85 and iodine-129 arising from a notional fuel reprocessing plant. Using published data on plant costs and a range of costs of unit collective dose, the sensitivity of 'optimum' options to variations in discount rates is analysed. A number of general conclusions are drawn from the results but the optimisation is intended for illustrative purposes, and therefore cannot be used to reach judgements on the desirability of implementing specific effluent controls. This work was partially funded by the Commission of the European Communities. (author)

  10. Monitoring and assessment of radiation exposure from routine radioactive discharges, and its relevance to the question of disease clusters

    International Nuclear Information System (INIS)

    Jones, S.R.

    1989-01-01

    Over the period of more than 30 years in which nuclear facilities have been operating, monitoring of the environment around such facilities has produced a wealth of information about the levels of radioactivity in the environment and about how radioactivity, introduced into the environment from effluent discharges, behaves in natural systems. Techniques for estimating radiation exposure to people from environmental measurements, or from theoretical models relating discharges to radiation exposure, have also been developed and validated where possible. The existence of localised excesses of leukaemia near the reprocessing plants at Sellafield and Dounreay, which cannot be explained on the basis of radiation exposure using these established methodologies, could be taken to imply that the methodologies are defective. However the radiation risk estimates have been shown to be robust to many of the suggested deficiencies and there are other, more qualitative, indications that discharges may not be a causative factor. It is argued that a broader search for possible causative factors may be more productive in resolving the conundrum. (author)

  11. The FOCON model to assess doses due to the atmospheric radioactive discharges of nuclear facilities during normal operation

    International Nuclear Information System (INIS)

    Rommens, C.; Morin, A.; Merle-Szeremeta, A.

    1999-01-01

    The FOCON model to assess doses due to the atmospheric radioactive discharges of nuclear facilities during normal operation. To assess the dosimetric impact to the public due to atmospheric radioactive discharges of nuclear facilities during normal operation, the Institute for Protection and Nuclear Safety has developed the FOCON96 code. FOCON96 calculates the dispersion of gases and aerosols into the environment (atmosphere contamination and ground deposition), their transfer in the biosphere (soils, plants and animals) and their impact to a member of the public (individual effective and equivalent doses, external exposure to the plume and to the deposits, internal exposure by inhalation and ingestion). FOCON96 uses ergonomic windows and proposes many capabilities (modular architecture, default values, choice of libraries, access to all the parameters of the models, listing or results, management of result files, calculations made directly, etc.). In the European context, and intercomparison with the PC-CREAM code, developed by the National Radiological Protection Board, has shown the coherence of the results of the two codes. A comparison of the windows and capabilities has shown that FOCON96 was easier to use. FOCON96 is not adapted to calculate the doses received during one particular year that are due to the discharges of a facility in operation for a long period of time. An evolution of the software will be considered if this kind of assessment is generalized. (authors)

  12. Electron energy distribution function control in gas discharge plasmas

    International Nuclear Information System (INIS)

    Godyak, V. A.

    2013-01-01

    The formation of the electron energy distribution function (EEDF) and electron temperature in low temperature gas discharge plasmas is analyzed in frames of local and non-local electron kinetics. It is shown, that contrary to the local case, typical for plasma in uniform electric field, there is the possibility for EEDF modification, at the condition of non-local electron kinetics in strongly non-uniform electric fields. Such conditions “naturally” occur in some self-organized steady state dc and rf discharge plasmas, and they suggest the variety of artificial methods for EEDF modification. EEDF modification and electron temperature control in non-equilibrium conditions occurring naturally and those stimulated by different kinds of plasma disturbances are illustrated with numerous experiments. The necessary conditions for EEDF modification in gas discharge plasmas are formulated

  13. The regulatory control of radioactive sources in Argentina

    Energy Technology Data Exchange (ETDEWEB)

    Rojkind, Roberto Hector [Autoridade Regulatoria Nuclear, Buenos Aires (Argentina)

    1997-12-31

    Argentina has been conducting nuclear activities for more than forty years, and as early as in 1956 established a Regulatory Authority. Procedures for compliance monitoring and enforcement have been in use in the regulatory control of radioactive sources, and regulatory standards and regulations had been set in Argentina, before the accident in Goiania. The conclusions drawn from that accident encouraged in Argentina the improvement of some regulatory procedures and helped to enhance the quality of the regulatory process. Therefore, the effectiveness of the control of spent radioactive sources has gradually increased, and enforcement actions to prevent radioactive sources ending up in the public domain improved. Some lessons learned in Argentina from the accident in Goiania and the main characteristics of an effective enforcement program helpful to prevent radiological accidents in industrial, medical, research and teaching uses of radioactive sources are presented. (author) 9 refs; e-mail: rrojkind at sede.arn.gov.br

  14. The regulatory control of radioactive sources in Argentina

    International Nuclear Information System (INIS)

    Rojkind, R.H.

    1998-01-01

    Argentina has been conducting nuclear activities for more than forty years, and had established a Regulatory Authority as early as in 1956. Procedures for compliance monitoring and enforcement have been in use in the regulatory control of radioactive sources, and regulatory standards and regulations were in force in Argentina before the accident in Goiania. The conclusions drawn from the Goiania accident encouraged the Argentine authorities to improve some regulatory procedures and helped to enhance the quality of the regulatory process. As a result, the effectiveness of the control of spent radioactive sources has gradually increased, and enforcement actions to prevent radioactive sources ending up in the public domain have improved. Lessons learned in Argentina from the accident in Goiania are presented as well as the main characteristics of an effective enforcement programme to prevent radiological accidents when radioactive sources are used for industrial, medical, research and teaching purposes. (author)

  15. The regulatory control of radioactive sources in Argentina

    International Nuclear Information System (INIS)

    Rojkind, Roberto Hector

    1997-01-01

    Argentina has been conducting nuclear activities for more than forty years, and as early as in 1956 established a Regulatory Authority. Procedures for compliance monitoring and enforcement have been in use in the regulatory control of radioactive sources, and regulatory standards and regulations had been set in Argentina, before the accident in Goiania. The conclusions drawn from that accident encouraged in Argentina the improvement of some regulatory procedures and helped to enhance the quality of the regulatory process. Therefore, the effectiveness of the control of spent radioactive sources has gradually increased, and enforcement actions to prevent radioactive sources ending up in the public domain improved. Some lessons learned in Argentina from the accident in Goiania and the main characteristics of an effective enforcement program helpful to prevent radiological accidents in industrial, medical, research and teaching uses of radioactive sources are presented. (author)

  16. A quantification method for peroxyacetyl nitrate (PAN) using gas chromatography (GC) with a non-radioactive pulsed discharge detector (PDD)

    Science.gov (United States)

    Zhang, Lei; Jaffe, Daniel A.; Gao, Xin; McClure, Crystal D.

    2018-04-01

    In this study, we developed a method for continuous PAN measurements by gas chromatography (GC) with a non-radioactive pulsed discharge detector (PDD). Operational parameters were optimized based on the ratio of peak height over baseline noise (P/N ratio). The GC/PDD system was compared with a traditional radioactive electron-capture detector (ECD). In the lab, the method detection limit (MDL) of the new GC/PDD method (9 pptv) was lower than the radioactive GC/ECD method (15 pptv), demonstrating its excellent potential. The MDL of GC/PDD in the field campaign at the Mt. Bachelor Observatory (MBO) was 23 pptv, higher than in the lab. This was caused in part by the decreased slope of the calibration curve resulting from the low air pressure level at MBO. However, the MDL level of GC/PDD at MBO is still low enough for accurate PAN measurements, although special attention should be paid to its application at high-elevation sites. Observations of PAN were conducted at MBO in the summer of 2016 with the GC/PDD system, and provided more evidence of the performance of the system. PAN was found to be highly correlated with CO. The promising performance of GC/PDD which does not require a radioactive source makes it a useful approach for accurate PAN measurements in the field.

  17. Quality control of radioactive waste disposal container for borehole project

    International Nuclear Information System (INIS)

    Mohamad Pauzi Ismail; Suhairy Sani; Azhar Azmi; Ilham Mukhriz Zainal Abidin

    2014-01-01

    This paper explained quality control of radioactive disposal container for the borehole project. Non-destructive Testing (NDT) is one of the quality tool used for evaluating the product. The disposal container is made of 316L stainless steel. The suitable NDT method for this object is radiography, ultrasonic, penetrant and eddy current testing. This container will be filled with radioactive capsules and cement mortar is grouted to fill the gap. The results of NDT measurements are explained and discussed. (author)

  18. Effective Regulatory Control of Radioactive Sources in Taiwan

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  19. Characterization and switching performance of electron-beam controlled discharges

    International Nuclear Information System (INIS)

    Lowry, J.F.; Kline, L.E.; Heberlein, J.V.R.

    1986-01-01

    The electron-beam sustained discharge switch is an attractive concept for repetitive pulsed power switching because it has a demonstrated capability to interrupt direct current and because it is inherently scalable. The authors report on experiments with this type of switch in a 4-kV dc circuit. A wire-ion-plasma (WIP) electron-beam (e-beam) gun is used to irradiate and sustain a switch discharge with a 100-cm/sup 2/ cross-sectional area in l atm of N/sub 2/ or CH/sub 4/. Interruption of 8-10-μs pulses of up to 1.9 kA, and of 100-μs pulses of 150 A has been demonstrated in methane, and interruption against higher recovery voltages (11 kV) has been performed at 1.2 kA by adding series inductance to the circuit. These values represent power supply limitations rather than limitations of the switch itself. A comparison of the measured discharge characteristics with theoretical predictions shows that the measured switch conductivities are higher than the predicted values for given e-beam current values. A qualitative explanation for this observation is offered by considering the effects of electron reflection from the discharge anode and of nonlinear paths for the beam electrons across the discharge gap. The authors conclude that the switching performance of the e-beam controlled discharge switch corresponds to its design parameters, and that for a given switch size a lower voltage drop during the on time can be expected compared with the voltage drop predicted by previously published theory

  20. Strengthening the control on radioactive sources - Cernavoda NPP operating experience

    International Nuclear Information System (INIS)

    Daian, I.; Simionov, V.

    2005-01-01

    This paper presents the national legal frame governing the radioactive source management, legislative requirements introduced during last years and current status of controlled radioactive sources program at Cernavoda NPP. Romania has only one nuclear power plant, Cernavoda NPP, equipped with five PHWR - CANDU-6 Canadian type reactors - with a 700 MW(e) gross capacity each, in different implementation stages. The legal representative of the nuclear power production sector in Romania is 'Nuclearelectrica' S.A. National Company (SNN). SNN is a governmental company controlled by the Ministry of Industry and Trade. The company has headquarters in Bucharest and three subsidiaries: - CNE-PROD Cernavoda (CNE-PROD), operating the Cernavoda NPP - Unit 1; - CNE-INVEST Cernavoda, in charge with the completion of Unit 2 and with the preservation of Units 3,4,5; - Nuclear Fuel Plant in Pitesti (FCN). Unit 1 is in commercial operation since December 2, 1996, Unit 2 is under construction (80% completed) and Units 3, 4, 5 are under preservation. The operation of Cernavoda NPP implies use of radioactive sources that may present a significant risk to health, property and the environment when control is lost. Within the last years CNCAN issued new regulations stating clear responsibilities for the different institutions involved in radioactive materials control programs. To manage radioactive sources in a safe way CNE-PROD established and revised the Controlled Radioactive Sources Program, as part of Station Radiation Protection Regulation, ensuring strict recording of the radioactive sources and their usage, ensuring physical and radiological security, protecting the personnel, members of the public and the environment from the hazards of ionizing radiation during the life cycle of the plant, including decommissioning. (authors)

  1. Strengthening the control on radioactive sources - Cernavoda NPP operating experience

    International Nuclear Information System (INIS)

    Daian, I.; Simionov, V.

    2005-01-01

    Full text: This paper presents the national legal frame governing the radioactive source management, legislative requirements introduced during last years and current status of controlled radioactive sources program at Cernavoda NPP. Romania has only one nuclear power plant, Cernavoda NPP, equipped with five PHWR - CANDU-6 Canadian type reactors - with a 700 MW(e) gross capacity each, in different implementation stages. The legal representative of the nuclear power production sector in Romania is 'Nuclearelectrica' S.A. National Company (SNN). SNN is a governmental company controlled by the Ministry of Industry and Trade. The company has headquarters in Bucharest and three subsidiaries: - CNE-PROD Cernavoda (CNE-PROD), operating the Cernavoda NPP - Unit 1; - CNE-INVEST Cernavoda, in charge with the completion of Unit 2 and with the preservation of Units 3,4,5; - Nuclear Fuel Plant in Pitesti (FCN). Unit 1 is in commercial operation since December 2, 1996, Unit 2 is under construction (80% completed) and Units 3, 4, 5 are under preservation. The operation of Cernavoda NPP implies use of radioactive sources that may present a significant risk to health, property and the environment when control is lost. Within the last years CNCAN issued new regulations stating clear responsibilities for the different institutions involved in radioactive materials control programs. To manage radioactive sources in a safe way CNE-PROD established and revised the Controlled Radioactive Sources Program, as part of Station Radiation Protection Regulation, ensuring strict recording of the radioactive sources and their usage, ensuring physical and radiological security, protecting the personnel, members of the public and the environment from the hazards of ionizing radiation during the life cycle of the plant. (authors)

  2. Control of radioactive materials on the medical science campus

    International Nuclear Information System (INIS)

    Thompson, C.H.; Vandergrift, J.F.; Slayden, S.A.; Dalrymple, G.V.

    1977-01-01

    There are persistent and difficult control problems associated with the large scale use of radionuclides: nowhere are these more apparent than in a large university medical center. If a safe environment is to be maintained with respect to employees, students, patients, and the general public, a program must be devised for effective supervision and control of radioactive sources. An automated system has been developed for the inventory and control of radioactive materials that has proven a valuable asset in a large institution. The reports generated have assisted in making responsible judgements, as well as assuring the continuation of single licensure for the medical science campus. (author)

  3. Radioactive waste control at the reprocessing facility in fiscal 1980

    International Nuclear Information System (INIS)

    1982-01-01

    At the fuel reprocessing facility of the Power Reactor and Nuclear Fuel Development Corporation (PNC), the release of radioactive gaseous and liquid wastes are controlled so as not to exceed the specific levels. Concentrated low and high level liquid wastes, sludge, etc. are contained in storage tanks. Low and high level solid wastes are stored in appropriate containers. In fiscal 1980 (April to March), the release of gaseous and liquid wastes was below the specific levels (as in the previous years). Based on the report made by PNC in accordance with the law concerning the regulation of reactors, etc., the following data are presented in tables: the released quantity of radioactive gaseous and liquid wastes in fiscal 1980, the cumulative stored quantity of radioactive liquid wastes up to fiscal 1980; the cumulative stored quantity of radioactive solid wastes up to fiscal 1980 and the quantity of the same stored in fiscal 1980. (J.P.N.)

  4. Control System Radioactive Contamination in Food Samples in Poland

    International Nuclear Information System (INIS)

    Grabowski, D.; Kurowski, W.; Muszynski, W.; Rubel, B.; Smagala, G.; Swietochowska, J.

    2001-01-01

    Full text: The analyses of the level of radioactive contamination in food samples are carried out by the Service for Measurements of Radioactive Contamination (SMRC) in Poland. The Service was brought into existence in 1961. The Service comprises of a network of measurement stations and the Centre of Radioactive Contamination Measurements (CRCM). The duty of the Centre is being executed by the Central Laboratory for Radiological Protection (CLRP). The uniform methods of sampling are used in measurement stations. All important foodstuff: milk, meat, vegetables, fruit, cereals are controlled in the Service stations. The radiochemical and spectrometric methods are used to determine the activity of radioactive isotopes. The standard equipment of the measurement station is the measurement system type SAPOS-90 and multichannel analyser with scintillation or germanium detector. The structure of the Service, kinds of samples tested by each station, program of sampling in normal and during accident situation are presented in this paper. (author)

  5. Environmental radioactivity: the importance of controlling exposure of the public: some experiences in Cuba

    International Nuclear Information System (INIS)

    Fernandez Gomez, Isis Maria

    2008-01-01

    The nuclear power is offering considerable advantages, it is considering the option to produce energy and the economy has moved in favour of the nuclear power. Therefore, the security is important within of the industry because ensures the control of public exposure and the environment and it plays a crucial role. Public exposure refers to exposure that is not of the direct work with ionizing radiation or the application of nuclear techniques in medical treatment and diagnosis. There are potential sources of discharges into the environment as the spent fuel and the waste disposal. Some of the routes of exposure are atmospheric discharge, liquid discharge, irrigation, environment, decomposition of the rain, food chains, etc. International regulations on subject of radiological safety are set by the IAEA and have a hierarchical order: fundamentals, requirements and guidelines. The International Commission of Radiological Protection and the Committee of the General Assembly of the United Nations are described in the research. The action is exposed in Cuba with regard to nuclear programs that have been realized or that are executed in relation to the control of the exposure of the public in existing applications. It mentions the centralized management of radioactive rights generated, the control of other sources of exposure, and the Red Nacional de Vigilancia Radiologica Ambiental. It also includes numerical data of studies realized on the extent of the sources of public exposure, the external doses received by the Cuban population product of environmental sources of radiation, the estimating of the doses received by the Cuban population by the incorporation of radionuclides present in the water and food. Likewise, the radioactive environmental funds; the phosphate mining; the protection and extraction of oil and the presence of radon inside the house are shown. The exposure to gamma radiation in thermal spas; the exposure to environmental sources of radiation

  6. Annual report on radioactive discharges and monitoring of the environment 1988

    International Nuclear Information System (INIS)

    1989-01-01

    This report supplements BNFL's Health and Safety Annual Report and lists 1988 discharges and environmental monitoring for the following sites: Sellafield, Chapelcross, Drigg Storage and Disposal Site, Springfields Works, Capenhurst Works. (UK)

  7. Radiation exposure of sewer workers associated with radioactive discharges from hospitals

    International Nuclear Information System (INIS)

    McDonnell, C.E.; Wilkins, S.

    1991-07-01

    Models have been developed to estimate the dispersion of radionuclides discharged into the sewer system serving a hospital where nuclear medicine and other techniques are used, and to assess the radiation doses to sewer workers and maintenance staff who may be exposed to these discharges. The dispersion model has been tested in a practical situation for the radionuclide 131 I. For a typical combination of hospital and sewer works, the estimated critical group doses arising from discharges of four selected radionuclides, 32 P, 99m Tc, 125 I and 131 I, are 30 μSv y -1 and 20 μSv y -1 respectively for a worker at the sewer works and for a sewer maintenance worker exposed for prolonged periods in the region of the sewer system adjacent to the hospital discharge point. (author)

  8. Operational control of material release and discharges from nuclear power plant

    International Nuclear Information System (INIS)

    Szabo, I. C.; Ranga, T.; Daroczi, L.; Deme, S.; Kerekes, A.

    2003-01-01

    The operational control of radioactive materials during atmospheric release and aquatic discharge from nuclear power plant is a licensing criterion for NPPs. Originally at the Paks NPP the release control was based on activity limits for four groups of elements. These groups were noble gases, long living radio-aerosols, radioiodine and radiostrontium for atmospheric release and specified activity limit for beta emitters, strontium and tritium for aquatic discharge into Danube. These groups were controlled with proper sampling and/or measuring instrumentation. The limit for atmospheric release was given as a 30-day moving average, for liquid discharges the annual limit was stipulated. The new release and discharge limitation system is based on the environmental dose limitation. The dose constraint for Paks NPP is 90 Sv/year of the critical group for all release pathways and the investigation dose limit is equal to 27 Sv/year. The regulation did not subdivide the dose limit for atmospheric and liquid components but for operational control subdivision of dose limits for atmospheric release and aquatic discharge and shorter time period (one day-one month) seems to be useful. The subdivision can be based on past release data and/or previous activity limits. To satisfy dose below the investigation dose limit there should be a proper operation control level for each separately measured component and pathway belonging to reasonable time interval significantly shorter than one year. The main task of the NPP staff is elaboration of reasonable control levels and reference time intervals for different radionuclide and element groups to be used in operational control. Operational control levels are based on measured daily or monthly release rates. In case of noble gases, aerosols and iodine the daily release rates have several sharp peaks per year. Operational control levels give opportunity to detect these peaks for internal investigation purposes. Investigation release limits

  9. Environmental risks of radioactive discharges from a low-level radioactive waste disposal site at Dessel, Belgium.

    Science.gov (United States)

    Batlle, J Vives I; Sweeck, L; Wannijn, J; Vandenhove, H

    2016-10-01

    The potential radiological impact of releases from a low-level radioactive waste (Category A waste) repository in Dessel, Belgium on the local fauna and flora was assessed under a reference scenario for gradual leaching. The potential impact situations for terrestrial and aquatic fauna and flora considered in this study were soil contamination due to irrigation with contaminated groundwater from a well at 70 m from the repository, contamination of the local wetlands receiving the highest radionuclide flux after migration through the aquifer and contamination of the local river receiving the highest radionuclide flux after migration through the aquifer. In addition, an exploratory study was carried out for biota residing in the groundwater. All impact assessments were performed using the Environmental Risk from Ionising Contaminants: Assessment and Management (ERICA) tool. For all scenarios considered, absorbed dose rates to biota were found to be well below the ERICA 10 μGy h -1 screening value. The highest dose rates were observed for the scenario where soil was irrigated with groundwater from the vicinity of the repository. For biota residing in the groundwater well, a few dose rates were slightly above the screening level but significantly below the dose rates at which the smallest effects are observed for those relevant species or groups of species. Given the conservative nature of the assessment, it can be concluded that manmade radionuclides deposited into the environment by the near surface disposal of category A waste at Dessel do not have a significant radiological impact to wildlife. Copyright © 2016 Elsevier Ltd. All rights reserved.

  10. A flexible software architecture for tokamak discharge control systems

    International Nuclear Information System (INIS)

    Ferron, J.R.; Penaflor, B.; Walker, M.L.; Moller, J.; Butner, D.

    1995-01-01

    The software structure of the plasma control system in use on the DIII-D tokamak experiment is described. This system implements control functions through software executing in real time on one or more digital computers. The software is organized into a hierarchy that allows new control functions needed to support the DIII-D experimental program to be added easily without affecting previously implemented functions. This also allows the software to be portable in order to create control systems for other applications. The tokamak operator uses an X-windows based interface to specify the time evolution of a tokamak discharge. The interface provides a high level view for the operator that reduces the need for detailed knowledge of the control system operation. There is provision for an asynchronous change to an alternate discharge time evolution in response to an event that is detected in real time. Quality control is enhanced through off-line testing that can make use of software-based tokamak simulators

  11. Radioecological aspects of the discharge of radioactive substances with waste water and exhaust air

    International Nuclear Information System (INIS)

    Bachner, D.; Becker, A.; Biesold, H.

    1976-01-01

    Radioecological aspects concerning radioactive effluents via air and water are under discussion. The essential patterns are defined and two food-chains (green vegetables-man, fish-man) will be taken here as an example for a look at the main parameters. Under typical emission conditions the environmental impacts for various pathways are given. (orig.) [de

  12. Safety control and minimization of radioactive wastes

    International Nuclear Information System (INIS)

    Wang Jinming; Rong Feng; Li Jinyan; Wang Xin

    2010-01-01

    Compared with the developed countries, the safety control and minimization of the radwastes in China are under-developed. The research of measures for the safety control and minimization of the radwastes is very important for the safety control of the radwastes, and the reduction of the treatment and disposal cost and environment radiation hazards. This paper has systematically discussed the safety control and the minimization of the radwastes produced in the nuclear fuel circulation, nuclear technology applications and the process of decommission of nuclear facilities, and has provided some measures and methods for the safety control and minimization of the radwastes. (authors)

  13. Limitation of radioactive discharges from NPP based on radionuclide specific monitoring

    International Nuclear Information System (INIS)

    Bucina, I.; Malatova, I.; Vidlakova, J.

    1998-01-01

    Monitoring of gaseous and liquid discharges from nuclear power plants based on particulate-iodine-gas measurements and gross beta or gamma plus tritium measurements is being improved by performing radionuclide specific measurements using semiconductor gamma and beta spectrometers and radiochemical methods. A new concept of regulatory effluent limits is being developed. The activities of all the relevant radionuclides discharged during a years, multiplied by the appropriate Sv/Bq conversion coefficient based on a standard multi-pathway model, are summed up, and the effective dose is compared with the new limit. Such limits should be laid down as the per capita collective commitment effective dose in the plant surroundings for atmospheric discharges, and as the committed effective dose to a critical group member for the hydrospheric releases

  14. A development of radioactive material tracking and location control system

    International Nuclear Information System (INIS)

    Joo, Gwang Tae; Jung Seung Yong; Song, Jung Ho

    2005-01-01

    As the whole industry fields such as construction, chemistry, machine, medicine including nuclear-related field have extended the range of radioactive material uses, it is tendency that domestic uses of radioactive material have been increased in quantity and number. In addition, as the transportation, transfer and use of radioactive material have been frequent, its loss, robbery, and carelessness of handling may cause not only employees in charge but the public to worry about damage of explosion and put an obstacle to increase trust in nuclear-related industry. At present, though the transportation, use and storage of radioactive material conform to the institution and standard of the atomic energy law, if we tracking radioactive material in real time, we can take immediate actions to prevent its loss, robbery. As our research institute developed a terminal that control location and tracking real time location for gamma-ray projector used in transporting, transferring, and using nondestructive test, we take a good look at utilities by using GPS-Cell ID bases location control

  15. Discharge optimization and the control of edge stability

    International Nuclear Information System (INIS)

    Nave, M.F.F.; Lomas, P.J.; Huysmans, G.T.A.

    1999-01-01

    Discharge optimization for improving MHD stability of both core and edge was essential for the achievement of record fusion power discharges, in the ELM-free hot ion H mode regime, in the recent JET DT operation. The techniques used to increase edge stability are described. In particular the successful technique of current rampdown used to suppress the outer mode is reported. The increased stability of the outer mode by decreasing the edge current density confirms its identification as an n = 1 external kink. Decreasing the plasma current, however, decreases the ELM-free period, which is consistent with stability calculations that show an earlier onset of the ballooning limit. In order to increase external kink stability without causing a deterioration in the ELM-free period, a compromise was achieved by using plasma current rampdown, while working at the highest plasma current values possible. Results from a plasma current scan show that at the time of occurrence of the first giant ELM, the plasma stored energy, as well as the pressure measured at the top of the edge pedestal increase linearly with plasma current, for a given plasma configuration and power. This is consistent with models of the edge transport barrier, where the transport barrier width is proportional to the ion (or fast ion) poloidal Larmor radius. The MHD observations in DT and deuterium only discharges were found to be similar. Thus the experience gained on the control of MHD modes in deuterium plasmas could be fully exploited in the DT campaign. (author)

  16. Annual report on radioactive discharges from Winfrith and monitoring the environment 1990

    International Nuclear Information System (INIS)

    1991-06-01

    This annual report, the sixth of its type, aims to provide full information on discharges and environmental monitoring. The report is mainly graphical, comparing past and current levels with authorised limits, derived limits or the recommended limits of the International Commission on Radiological Protection (ICRP). All the data are presented at the end of the report in tabular form. Discharges from Winfrith are subject to Authorisations issued jointly by the Department of the Environment (DOE) and the Ministry of Agriculture, Fisheries and Food (MAFF). The numerical values of the Authorised Limits are based on past performance, future requirements and the application of Best Practicable Means (BPM). As a ''back stop'', discharges at the limits must not result in doses to the most potentially exposed part of the local population - the critical group - exceeding 0.5 mSv per year. The limit recommended by the International Commission on Radiological Protection (ICRP) for dose to a member of the general public is 1.0 mSv per year. In September 1990 Winfrith's Steam Generating Heavy Water Reactor (SGHWR) was shut down and a decision taken, later, that reactor operation would cease. The pattern of discharges thus changed in the last quarter of the year and discharges in future will be lower, and of a different pattern, than those of the past twenty years. The dose to the critical group, which is already less than 2% of the ICRP limit and less than 1% of the UK average natural background dose will drop further in future years. (Author)

  17. The management of radioactive materials and its control

    International Nuclear Information System (INIS)

    Flory, D.; Charles, T.

    1998-01-01

    The present work is destined to present the arrangements taken by users of radioactive materials to follow them and to manage them efficiency; it takes stock of the different control systems that work towards checking the efficiency of these arrangements. Some particular cases are evoked relative to nuclear facilities. (N.C.)

  18. Quality control of radioactive waste products

    International Nuclear Information System (INIS)

    Martens, B.R.; Warnecke, E.; Odoj, R.

    1986-01-01

    The variety of incoming untreated wastes, treatment methods, waste forms and containers requires a great variety of controlling methods and principles to be applied both during waste treatment and on the final product. The paper describes product control schemes and methods, sampling systems and transportable testing equipment for waste drums, and equipment for waste cementation using in-drum stirring and subsequent fixation of solid wastes in the flowable product. (DG) [de

  19. Dielectric barrier discharge plasma actuator for flow control

    Science.gov (United States)

    Opaits, Dmitry Florievich

    Electrohydrodynamic (EHD) and magnetohydrodynamic phenomena are being widely studied for aerodynamic applications. The major effects of these phenomena are heating of the gas, body force generation, and enthalpy addition or extraction, [1, 2, 3]. In particular, asymmetric dielectric barrier discharge (DBD) plasma actuators are known to be effective EHD device in aerodynamic control, [4, 5]. Experiments have demonstrated their effectiveness in separation control, acoustic noise reduction, and other aeronautic applications. In contrast to conventional DBD actuators driven by sinusoidal voltages, we proposed and used a voltage profile consisting of nanosecond pulses superimposed on dc bias voltage. This produces what is essentially a non-self-sustained discharge: the plasma is generated by repetitive short pulses, and the pushing of the gas occurs primarily due to the bias voltage. The advantage of this non-self-sustained discharge is that the parameters of ionizing pulses and the driving bias voltage can be varied independently, which adds flexibility to control and optimization of the actuators performance. Experimental studies were conducted of a flow induced in a quiescent room air by a single DBD actuator. A new approach for non-intrusive diagnostics of plasma actuator induced flows in quiescent gas was proposed, consisting of three elements coupled together: the Schlieren technique, burst mode of plasma actuator operation, and 2-D numerical fluid modeling. During the experiments, it was found that DBD performance is severely limited by surface charge accumulation on the dielectric. Several ways to mitigate the surface charge were found: using a reversing DC bias potential, three-electrode configuration, slightly conductive dielectrics, and semi conductive coatings. Force balance measurements proved the effectiveness of the suggested configurations and advantages of the new voltage profile (pulses+bias) over the traditional sinusoidal one at relatively low

  20. Survey of product quality control of radioactive waste

    International Nuclear Information System (INIS)

    Warnecke, E.

    1989-01-01

    The PTB has developed basic procedures with regard to deriving final storage conditions and product quality control. After this, requirements for radioactive waste are derived via safety analysers, in which information about the radioactive waste, the geological overall situation of the site and the layout of the final storage mine, in particular, are included as basic data. The final storage conditions are only determined with the awarding of the planning decision. Compliance with them can be proved by random sample tests on waste containers or via a qualification and inspection of the conditioning process. (DG) [de

  1. Automatized material and radioactivity flow control tool in decommissioning process

    International Nuclear Information System (INIS)

    Rehak, I.; Vasko, M.; Daniska, V.; Schultz, O.

    2009-01-01

    In this presentation the automatized material and radioactivity flow control tool in decommissioning process is discussed. It is concluded that: computer simulation of the decommissioning process is one of the important attributes of computer code Omega; one of the basic tools of computer optimisation of decommissioning waste processing are the tools of integral material and radioactivity flow; all the calculated parameters of materials are stored in each point of calculation process and they can be viewed; computer code Omega represents opened modular system, which can be improved; improvement of the module of optimisation of decommissioning waste processing will be performed in the frame of improvement of material procedures and scenarios.

  2. Control of radioactive sources in industry through regulatory inspections

    International Nuclear Information System (INIS)

    Leocadio, J.C.; Ramalho, A.T.; Pinho, A.S.; Lourenco, M.M.J.; Nicola, M.S.; D'Avila, R.L.; Melo, I.F.; Cucco, A.C.S.

    2005-01-01

    In Brazil, the applications of ionizing radiation in industry are accomplished about 900 radioactive facilities, which handle approximately 3.000 radiation sources. The control of radioactive sources used in industrial installations authorized by the Brazilian Nuclear Energy Commission (CNEN) is accomplished by Servico de Radioprotecao na Industria Radiativa (SERIR) of the Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ, Brazil. This service carries out regulatory inspections in the practices of industrial radiography, nuclear gauges, industrial irradiators and oil wells logging. The frequency of inspections depends on the type of practice, ranging from a year to 5 years, depending on the risk involved. This paper presents a brief description of the situation of radiation safety in the use of radioactive sources in the industries of the country. The results obtained with regulatory inspections at industrial installations demonstrate that the conditions of safety and radiation protection in these facilities are satisfactory when compared with the technical regulations, both national and international

  3. Pilot scale ion exchange column study for reducing radioactivity discharges to environment

    International Nuclear Information System (INIS)

    Kore, S.G.; Yadav, V.K.; Sonar, N.L.; Valsala, T.P.; Narayan, J.; Sharma, S.P.; Chattopadhyay, S.; Dani, U.; Vishwaraj, I.

    2013-01-01

    Low level liquid waste (LLW) is generated during operation of Tarapur Atomic Power Station (TAPS). Chemical co-precipitation is the treatment method used for decontamination of this waste with respect to radionuclide prior to discharge to environment. Further polishing of effluent from the treated LLW was planned using ion exchange column to reduce the discharges to the environment In view of this ion exchange column study was carried out in the laboratory using in-house prepared cobalt ferrocyanide (COFC) based composite resin. Based on the encouraging results obtained in the lab studies, pilot scale study was carried out in the plant. Decontamination factor (DF) of 14-15 was obtained with respect to Cs isotopes and overall DF of 2-5 was obtained with respect to gross beta activity. (author)

  4. Annual report on radioactive discharges from Winfrith and monitoring the environment 1989

    International Nuclear Information System (INIS)

    1990-03-01

    The numerical values of the authorised limits are based on past performance, future requirements and the application of BPM. As a 'back-stop', discharges at the limits must not result in doses to the most potentially exposed part of the local population -the critical group - exceeding 0.5 mSv per year. The limit of the International Commission on Radiological Protection (ICRP) for dose to a member of the general public is 1.0 mSv per year. During 1989 some small changes took place in our discharge patterns, our environmental monitoring and in the assessment of critical group doses. These changes are discussed in the introductions to the two parts of this report where the relevant Authorisations are also discussed. This report, the fifth of our annual series, has as its aim the provision, to the general public, of full information on discharges from the SGHWR reactor and other smaller sources at Winfrith and the associated environmental monitoring programmes. Some improvements in presentation have been made. The data, mainly provided graphically in the main text, are still compared with authorised limits or derived levels, but numerical values are now given. The graphs refer to specifically authorised radio-nuclides e.g. tritium, rather than to gross activity. Previous reports were restricted to monitoring at the site boundary and to off-site monitoring. Some data are now given in the report for on-site monitoring. (author)

  5. Limitation of radioactive discharges from NPP based on radionuclide specific monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Bucina, I; Malatova, I; Vidlakova, J [National Radaition Protection Institute, Prague (Czech Republic)

    1996-12-31

    Monitoring of nuclear power plants (NPP) discharges into atmosphere and hydrosphere based on particulate-iodine-gas (PIG) measurements and gross beta and gamma plus tritium measurements respectively is being improved by nuclide specific measurements employing semiconductor gamma and alpha spectrometry and radiochemical methods. In connection with the progress new concept of authorized effluent limits and the related regulations is being implemented in the Czech Republic. Activities of all principally contributing to the effective dose radionuclides discharges during a year multiplied by a Sv/Bq conversion coefficient based on a standard model are summed up and the effective dose is compared with the new limit. These limits should be authorized for discharges into atmosphere as per caput collective committed effective dose in the NPP surrounding or as its value multiplied by the number of surrounding segment providing thus committed effective dose to member of a vital critical group and into the hydrosphere as committed effective dose to the critical group member. The criteria for obligatory evaluation of the specific radionuclide contribution and the resulting requirements on minimum detectable activities for both the shorter and longer monitoring intervals are included in the new regulations. The PIG and gross activity measurement results will be compared with investigation levels only and no more used for limitation purposes. (authors).

  6. Quality control concept for radioactive waste packages

    International Nuclear Information System (INIS)

    Warnecke, E.; Martens, B.R.; Odoj, R.

    1990-01-01

    In the Federal Republic of Germany a contract with the BfS for the performance of quality control measures is necessary. It is principally possible to apply two alternative methods: random checks on waste packages or qualification of conditioning processes with subsequent inspections. Priority is given to the control by the process qualification. Both methods have successfully been developed in the Federal Republic of Germany and can be applied. In the course of the qualification of conditioning processes it must be demonstrated by inactive and/or active runs that waste packages are produced which fulfil the waste acceptance requirements. The qualification results in the fixation of a handbook for the operation of the respective conditioning process including the process instrumentation and the operational margins. The qualified process will be inspected to assure the compliance of the actual operation with the conditions fixed in the handbook. (orig./DG)

  7. Effective regulatory control of radioactive sources

    International Nuclear Information System (INIS)

    Meserve, R.A.

    2001-01-01

    This paper provides an overview of the situation in the USA regarding government control over use of radiation sources, the challenges it faces and the potential paths to their resolution. In the light of the large number of radiation sources in use worldwide, the safety record on balance is remarkably good. But there is still considerable room for improvement. The IAEA has an important role to play, and it is playing it effectively

  8. Regulatory control of radioactivity and nuclear fuel cycle in Canada

    International Nuclear Information System (INIS)

    Hamel, P.E.; Jennekens, J.H.

    1977-05-01

    Legislation and regulations giving birth to the Atomic Energy Control Board (AECB) are outlined, as well as current licencing procedures. The AECB bases its health and safety criteria on ICRP recommendations. R and D is funded to aid regulatory activity. Licencing activities cover uranium resource management, uranium mining and milling, nuclear generating stations, heavy water plants, and radioactive waste management. Safeguards, physical security, and international controls are also concerns of the AECB. (E.C.B.)

  9. Assessment of the Impact of Radioactive Disposals and Discharges from the United Kingdom Low Level Waste Repository on the Ecosystem

    International Nuclear Information System (INIS)

    Barber, N.

    2009-01-01

    This paper describes an assessment of the impacts to ecosystems and wildlife species from radioactive discharges and disposals at the United Kingdom's low level waste disposal facility in West Cumbria. The assessment was undertaken in response to a requirement in the site's current authorisation and comprised a detailed desk based review along with an exercise to screen relevant monitoring data from the site against generic assessment criteria and undertake a numerical risk assessment. Much of the site is vegetated, comprising a variety of habitats including grassland, relict dune heath and surface water bodies. Furthermore, the site is located adjacent to a coastal/estuarine area which is protected as it provides a habitat of high ecological value and species of animals and plants are present that are rare, endangered or vulnerable. However, the current impact of aerial and liquid radioactive discharges from the low level waste repository on ecosystems and wildlife species is considered to be low. Site monitoring data also indicate that there has been a reduction of radionuclide activities in ground and surface water and leachates over time, a result of measures initiated to minimise rainwater infiltration and improve leachate management associated with the disposal area. A quantitative assessment was undertaken to assess future impacts to relevant terrestrial, fresh water and marine ecosystems. This showed that modelled peak radionuclide concentrations in the first 4,000 years after site closure were not sufficiently high to cause potential impact to any of these ecosystems or associated wildlife. This cut-off date was chosen as it is considered probable that, due to the effects of future climate and landscape change and, unless actions are taken to defend the coastline, the site is likely to be disrupted by coastal erosion in the next 4,000 years. (authors)

  10. Analysis of radioactivity in coal, cinders, fly ash and discharges from the stack

    International Nuclear Information System (INIS)

    Meide, A.

    1985-01-01

    Gamma measurements of coal samples originating from several supplying countries proved that the South African coal has about double U-238 and Ra-226 concentration and about treble Th-232 concentration compared to coal from the other countries. Gamma measurements of coal, cinders and fly ash samples from five coal-fueled plants indicate somewhat higher concentrations of Th-232 in cinders and U-238 and Th-232 in fly ashes than those described in literature. The ratio Po-210/Pb-210 was about 2 for fly ash particulates <35μ. A positive correlation between ash percentage and radioactivity of coal might be assumed. (EG)

  11. Prostate brachytherapy - discharge

    Science.gov (United States)

    Implant therapy - prostate cancer - discharge; Radioactive seed placement - discharge ... You had a procedure called brachytherapy to treat prostate cancer. Your treatment lasted 30 minutes or more, ...

  12. Evaluation of environmental dosimetry models for applicability to possible radioactive waste repository discharges

    International Nuclear Information System (INIS)

    Mauro, J.J.; Michlewicz, D.; Letizia, A.

    1977-09-01

    This report presents the results of a review of the available codes, for application to the National Waste Terminal Storage (NWTS) Program. Consideration was given to the types of radionuclides which may be of concern, the possible modes of release of these radionuclides and the various pathways by which members of the general public in the vicinity of a terminal storage facility may be exposed to the releases. Results reveal that the types and quantities of radioactive material requiring disposal will depend on the type of back and fuel cycle adopted. It can be assumed that under normal operating conditions there will be virtually no liquid effluent and inconsequentially small quantities of radioactive gaseous effluent. Under accident conditions during operation, both liquid and gaseous releases could occur resulting in exposures to the general public. Failure of the facility subsequent to decommissioning could also result in exposures but primarily via the aquatic pathways. A review of three atmospheric dispersion models and 32 environmental dosimetry codes presently used by the nuclear industry was performed. A discussion is presented on standard NRC methodologies for determining the dispersion coefficients used as input to the various models and the inherent limitations of many of the techniques routinely used to evaluate site specific atmospheric dispersion. The review of the dosimetry codes reveals that no one code is generally applicable to the NWTS Program, but some codes permit radiological assessment of the most important exposure pathways

  13. Control of radioactivity at the Luxembourg steel-making facilities

    International Nuclear Information System (INIS)

    Werner, C.

    1999-01-01

    The Luxembourg steel industry has a yearly capacity of close to 3 million tonnes of raw steel produced from scrap at three electric arc furnace steel-making plants. It has introduced in 1994 a comprehensive system of measuring devices to prevent radioactive material from being introduced into its meltshops. Detection equipment has been installed at the road and railroad accesses to the three plants. Further to the controls of incoming scrap, radioactivity is monitored on both the steel and the slag samples of each heat produced at the plants. This measure is taken in order to detect any incident involving the melting of a radioactive source that might have escaped the controls of incoming material as soon as possible. The triple purpose of these controls is: (i) to protect the personnel of the steel making plants from radiation hazards; (ii) to maintain the integrity of the equipment; and (iii) to assure integrity of the products. The presentation describes the possible origins of radioactive contamination in steel scrap as well as the behaviour in the steel making process of the different radionuclides that can be expected to be introduced into the steel making vessels through steel scrap. Together with the government agency for radiation protection, procedures have been developed for the management of any event of detection of radioactivity in the plants and to assure optimum availability of the measuring equipment. These procedures are described and commented in the presentation. The presentation includes also a report on the experience from 4 years of monitoring, during which more than 10 million tonnes of scrap have passed the gates of the steel-making plants of ProfilARBED and ARES. (author)

  14. 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.)

  15. 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.)

  16. Public exposure due to radioactive liquid effluent discharges from Instituto de Pesquisas Energeticas Nucleares/IPEN

    International Nuclear Information System (INIS)

    Rocca, Fatima F.D.

    1995-01-01

    The physical and social-economic characterization of aquatic environment influenced by IPEN was performed and possible exposure pathways were identified. The effective dose equivalent to the critical groups were estimated by using a mathematic model that simulate radionuclide transport through environment components, and dosimetric models that relate activity at environment components to public exposure. This study has concluded that there is not a single critical group that receives the highest dose equivalents from the source, but all the populational groups potentially exposed receive doses at the same level, and then all of them must be considered in a radiological assessment process. The results showed that the public exposure due to liquid discharges from IPEN remains bellow established dose limits. (author). 58 refs., 28 figs., 24 tabs

  17. Surveillance and control of containment by means of radioactive measurements

    International Nuclear Information System (INIS)

    Roche, H.; Seveon, J.J.; Rousseau, L.; Delalande, J.

    1983-12-01

    In this paper, the radioactive measurements participating in the surveillance and control of the reactor containment as well as the possible procedures or operating rules related to, especially the ultimate procedures which could be implemented in case of a beyond of design accident, are presented. However, an overall view of the plant radiation monitoring system installed on the French plants is first given. If necessary, difference between 900 MW and 1300 MW units are emphasized

  18. Magnetic-field control of low-pressure diffuse discharges

    International Nuclear Information System (INIS)

    Cooper, J.R.

    1986-01-01

    Application of a magnetic field in a direction transverse to the electric field in a diffuse discharge can have a strong effect on the transport parameters in the discharge medium and on the external characteristics of the discharge as a whole. Deviations in these transport parameters were investigated in this work by means of Monte Carlo calculations, and the electrical characteristics of the total discharge were observed experimentally. Results of the theoretical investigation show that, in attaching gas mixtures, both the ionization and attachment-rate coefficients in the positive column of the discharge are changed such that the combined effect results in an increase in resistivity. Experimentally, it is seen that application of a crossed magnetic field to an abnormal glow discharge in attaching gases in a certain parameter range causes the discharge voltage to increase significantly. The effect seems to be most strongly influenced by processes in the cathode-fall region

  19. Controlling branching in streamer discharge by laser background ionization

    International Nuclear Information System (INIS)

    Takahashi, E; Kato, S; Furutani, H; Sasaki, A; Kishimoto, Y

    2011-01-01

    Irradiation with a KrF laser controlled the positive streamer branching in atmospheric argon gas. This laser irradiation changed the amount of background ionization before the streamer discharge. Measuring the ionization current allowed us to evaluate the initial electron density formed by the KrF laser. We observed characteristic feather-like branching structure and found that it was only suppressed in the irradiated region. The threshold of ionization density which can influence the branching was evaluated to be 5 x 10 5 cm -3 . The relationship between the size of avalanche head and mean distance between initial electrons explained this suppression behaviour. These experimental results support that the feather-like structure originates from the branching model of Loeb-Meek, a probabilistic merging of individual avalanches.

  20. HABIT, Toxic and Radioactive Release Hazards in Reactor Control Room

    International Nuclear Information System (INIS)

    Stage, S.A.

    2005-01-01

    1 - Description of program or function: HABIT is a package of computer codes designed to be used for the evaluation of control room habitability in the event of an accidental release of toxic chemicals or radioactive materials. 2 - Methods: Given information about the design of a nuclear power plant, a scenario for the release of toxic or radionuclides, and information about the air flows and protection systems of the control room, HABIT can be used to estimate the chemical exposure or radiological dose to control room personnel

  1. Bluff Body Flow Control Using Dielectric Barrier Discharge Plasma Actuators

    Science.gov (United States)

    Thomas, Flint; Kozlov, Alexey

    2008-11-01

    The results of an experimental investigation involving the use of dielectric barrier discharge plasma actuators to control bluff body flow is presented. The motivation for the work is plasma landing gear noise control for commercial transport aircraft. For these flow control experiments, the cylinder in cross-flow is chosen for study since it represents a generic flow geometry that is similar in all essential aspects to a landing gear strut. The current work is aimed both at extending the plasma flow control concept to Reynolds numbers typical of landing approach and take-off and on the development of optimum plasma actuation strategies. The cylinder wake flow with and without actuation are documented in detail using particle image velocimetry (PIV) and constant temperature hot-wire anemometry. The experiments are performed over a Reynolds number range extending to ReD=10^5. Using either steady or unsteady plasma actuation, it is demonstrated that even at the highest Reynolds number Karman shedding is totally eliminated and turbulence levels in the wake decrease by more than 50%. By minimizing the unsteady flow separation from the cylinder and associated large-scale wake vorticity, the radiated aerodynamic noise is also reduced.

  2. A guide for controlling consumer products containing radioactive substances

    International Nuclear Information System (INIS)

    1985-01-01

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

  3. Radioactive discharges and environmental monitoring at the Swedish nuclear facilities 2002-2004; Utslaepps- och omgivningskontroll vid de kaerntekniska anlaeggningarna 2002-2004

    Energy Technology Data Exchange (ETDEWEB)

    Luening, Maria

    2005-11-15

    According to Swedish regulations the effective dose to an individual in the critical group, from one year of releases of radioactive substances to air and water from all facilities located in the same geographically delimited area, shall not exceed 0.1 mSv. The effective dose, which concerns the dose from external radiation and the committed effective dose from internal radiation, shall be integrated over a period of 50 years. When calculating the dose to individuals in the critical group, both children and adults shall be taken into consideration. If the calculated dose exceeds 0.01 mSv per calendar year, realistic calculations of radiation doses shall be conducted for the most affected area. SSI has not defined any radionuclide specific discharge limits. Limitation of releases is being implemented through the restriction of dose to the critical group members. For each nuclear facility, e.g. each reactor, and for each radionuclide that may be released, specific release-to-dose factors have been calculated. The factors have been calculated for hypothetical critical groups, and take into consideration local dispersion conditions in air and in the environment, local settlements, local production of food-stuffs as well as moderately conservative assumptions on diet and contribution of locally produced food-stuff to the diet of the group. For nuclear power reactors, release-to-dose factors (mSv/Bq) have been calculated for 97 radionuclides that may be discharged to the marine environment and 159 radionuclides that may be emitted to air. Discharges shall be controlled through the measurement of representative samples for each release pathway. The analyses shall include nuclide-specific measurements of gamma and alpha-emitting radioactive substances as well as, where relevant, strontium-90 and tritium. The discharges of radioactive substances from the Swedish NPPs result in very low doses well below the limits issued by SSI. Even so, the concentration of radionuclides in

  4. Non-Destructive Testing for Control of Radioactive Waste Package

    Science.gov (United States)

    Plumeri, S.; Carrel, F.

    2015-10-01

    Characterization and control of radioactive waste packages are important issues in the management of a radioactive waste repository. Therefore, Andra performs quality control inspection on radwaste package before disposal to ensure the compliance of the radwast characteristics with Andra waste disposal specifications and to check the consistency between Andra measurements results and producer declared properties. Objectives of this quality control are: assessment and improvement of producer radwaste packages quality mastery, guarantee of the radwaste disposal safety, maintain of the public confidence. To control radiological characteristics of radwaste package, non-destructive passive methods (gamma spectrometry and neutrons counting) are commonly used. These passive methods may not be sufficient, for instance to control the mass of fissile material contained inside radwaste package. This is particularly true for large concrete hull of heterogeneous radwaste containing several actinides mixed with fission products like 137Cs. Non-destructive active methods, like measurement of photofission delayed neutrons, allow to quantify the global mass of actinides and is a promising method to quantify mass of fissile material. Andra has performed different non-destructive measurements on concrete intermediate-level short lived nuclear waste (ILW-SL) package to control its nuclear material content. These tests have allowed Andra to have a first evaluation of the performance of photofission delayed neutron measurement and to identify development needed to have a reliable method, especially for fissile material mass control in intermediate-level long lived waste package.

  5. Competent authority regulatory control of the transport of radioactive material

    International Nuclear Information System (INIS)

    1987-04-01

    The purpose of this guide is to assist competent authorities in regulating the transport of radioactive materials and to assist users of transport regulations in their interactions with competent authorities. The guide should assist specifically those countries which are establishing their regulatory framework and further assist countries with established procedures to harmonize their application and implementation of the IAEA Regulations. This guide specifically covers various aspects of the competent authority implementation of the IAEA Regulations for the Safe Transport of Radioactive Material. In addition, physical protection and safeguards control of the transport of nuclear materials as well as third party liability aspects are briefly discussed. This is because they have to be taken into account in overall transport regulatory activities, especially when establishing the regulatory framework

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

    Science.gov (United States)

    2012-01-01

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

  7. High-energy molecular lasers self-controlled volume-discharge lasers and applications

    CERN Document Server

    Apollonov, V V

    2016-01-01

    This book displays the physics and design of high-power molecular lasers. The lasers described are self-controlled volume-discharge lasers. The book explains self-sustained discharge lasers, self-initiated discharge lasers and technical approaches to laser design. Important topics discussed are laser efficiency, laser beam quality and electric field homogeneity. The book contains many new innovative applications.

  8. Spoken commands control robot that handles radioactive materials

    International Nuclear Information System (INIS)

    Phelan, P.F.; Keddy, C.; Beugelsdojk, T.J.

    1989-01-01

    Several robotic systems have been developed by Los Alamos National Laboratory to handle radioactive material. Because of safety considerations, the robotic system must be under direct human supervision and interactive control continuously. In this paper, we describe the implementation of a voice-recognition system that permits this control, yet allows the robot to perform complex preprogrammed manipulations without the operator's intervention. To provide better interactive control, we connected to the robot's control computer, a speech synthesis unit, which provides audible feedback to the operator. Thus upon completion of a task or if an emergency arises, an appropriate spoken message can be reported by the control computer. The training programming and operation of this commercially available system are discussed, as are the practical problems encountered during operations

  9. 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

  10. Management and control of radioactive wastes in Ghana | Gbadago ...

    African Journals Online (AJOL)

    ... is responsible for monitoring and tracking all radioactive materials imported, stored or exported. The profile of radioactive sources in active use are also presented, in addition to spent radioactive sources currently in the custody of the NRWMC as part of the inventory for creating databases on radioactive wastes in Ghana.

  11. National infrastructure for detecting, controlling and monitoring radioactive materials

    International Nuclear Information System (INIS)

    Othman, I.

    2001-01-01

    Full text: The Atomic Energy Commission of Syria (AECS) has the direct responsibility to assure proper safety for handling, accounting for and controlling of nuclear materials and radioactive sources which based on a solid regulatory infrastructure , its elements contains the following items: preventing, responding, training, exchanging of information. Based on the National Law for AECS's Establishment no. 12/1976, a Ministerial Decree for Radiation Safety no. 6514 dated 8.12.1997, issued by the Prime Minister. This Decree authorizes the Syrian Atomic Energy Commission to regulate all kinds of radiation sources. It fulfills the basic requirements of radiation protection and enforce the rules and regulations. The Radiation and Nuclear Regulatory Office (RNRO) is responsible for preparing all the draft regulations. In 1999 the General Regulations for Radiation Protection was issued by the Director General of the AECS, under Decision no. 112/99 dated 3.2.1999. It is based on an IAEA publication, Safety Series no. 115 (1996), and adopted to meet the national requirements. Syria has nine Boarding Centers seeking to prevent unauthorized movement of nuclear material and radioactive sources in and out side the country. They are related to the Atomic Energy Commission (AECS), and are located at the main entrances of the country. Each is provided with the practical tools and equipment in order to assist Radiation Protection Officers (RPO) in fulfilling their commitments, by promoting greater transparency in legal transfers of radioactive materials and devices. They apply complete procedures for the safe import, export and transit of radioactive sources. The RPOs provide authorizations by issuing an entry approval document, after making sure that each concerned shipments has an authorized license from the Syrian Regulatory Body (RNRO) before permitting shipments to leave, arrive or transit across their territory, enabling law enforcement to track the legal movement of

  12. Dose control in road transport of radioactive material

    International Nuclear Information System (INIS)

    Gerulis, Eduardo

    2013-01-01

    The radiation doses to workers in the transport of radioactive material should be as low as reasonably achievable. The average doses of drivers and loaders, sampled in this thesis should be decreased. The demonstration of doses control in a road vehicle with radioactive material required by the current Brazilian regulation, CNEN NE 5.01 should be written in its own printed form with exposure values obtained in normally occupied positions from workers and members of the public, even when the consignment does not need 'exclusive use' (⅀IT ≤50). Through bibliographic research, modeling and field research, this research work shows that this demonstration of the control should be done by writing the registration accumulation of load, limited (⅀IT ≤50), also in the own printed form. It is for a better control method, in order to avoid the use of measuring equipment, to build standardization with foreign regulations, to the current occupational doses of radioprotection technicians, the costs and time, (important for consignment with radiopharmaceuticals short half-life) would be all smaller. Exposure values of the parameters used with this method are smaller than regulatory limits. The segregation distances between loads and the cabins of vehicles shall be showed by Brazilian regulation updated to contribute to these aims. (author)

  13. Regulatory inspection: a powerful tool to control industrial radioactive sources

    International Nuclear Information System (INIS)

    Silva, F.C.A. da; Leocadio, J.C.; Ramalho, A.T.

    2008-01-01

    An important contribution for Brazilian development, especially for the quality control of products, is the use of radiation sources by conventional industries. There are in Brazil roughly 3,000 radioactive sources spread out among 950 industries. The main industrial practices involved are: industrial radiography, industrial irradiators, industrial accelerators, well logging petroleum and nuclear gauges. More than 1,800 Radiation Protection Officers (RPOs) were qualified to work in these practices. The present work presents a brief description of the safety control over industrial radioactive installations performed by the Brazilian Regulatory Authority, i.e. the National Commission of Nuclear Energy (CNEN). This paper also describes the national system for radiation safety inspections, the regulation infrastructure and the national inventory of industrial installations. The inspections are based on specific indicators, and their periodicity depends on the risk and type of installation. The present work discusses some relevant aspects that must be considered during the inspections, in order to make the inspections more efficient in controlling the sources. One of these aspects regards the evaluation of the storage place for the sources, a very important parameter for preventing future risky situations. (author)

  14. Experience of ALARA in controlling radiocaesium discharges to the Irish Sea

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1984-01-01

    Radiocaesium discharges to the Irish Sea, which primarily originate from corrosion of magnox fuel in the Sellafield storage ponds, are a source of public radiation exposure mainly through the fish and shellfish consumption pathway. Experience of ALARA in the context of reducing these discharges is described. The operators, British Nuclear Fuels Limited (BNFL), in consultation with Government Departments, decided to install an ion exchange plant to remove radioactivity from pond effluents. This plant is scheduled for commissioning in 1984 and optimisation will play a major part in determining its operating regime. Meanwhile, measures have been taken to reduce discharges using skips of zeolite installed in the ponds. Experience of ALARA in determining the optimum replacement rate of skips is described. A major consideration was differential cost-benefit analysis. Following installation of skips at the rate thereby indicated, discharges are being reduced by about half. A further major reduction is expected when the ion exchange plant becomes available. (author)

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

    International Nuclear Information System (INIS)

    Mao Yong; Li Aiwu

    1997-01-01

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

  16. An inverse optimal control problem in the electrical discharge ...

    Indian Academy of Sciences (India)

    Marin Gostimirovic

    2018-05-10

    May 10, 2018 ... Keywords. EDM process; discharge energy; heat source parameters; inverse problem; optimization. 1. Introduction .... ation, thermal modeling of the EDM process would become ..... simulation of die-sinking EDM. CIRP Ann.

  17. EPA proposes options for control of industrial radioactivity

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    The US Environmental Protection Agency on February 28 proposed four alternative approaches for controlling radionuclides from a dozen industrial sources. The proposal outlines four alternatives for regulating toxic air pollutant. The proposal is designed to elicit comment on such regulatory issues as: What are acceptable health risks? What are appropriate criteria for establishing a margin of safety? What are the technological feasibility and the costs of regulatory controls? How should uncertainty by considered? EPA intends to use the approach finally selected as the framework for future hazardous-air pollutant-control decisions. Industry uses hundreds of distinct radionuclides in solid, liquid and gaseous forms. Industrial radionuclide emissions occur either as a result of an inability to contain the radioactive materials or as an unintended consequence of other activity, such as radionuclide emissions from mining or milling

  18. Characterization of a dielectric barrier discharge in controlled atmosphere

    Science.gov (United States)

    Kogelheide, Friederike; Offerhaus, Björn; Bibinov, Nikita; Bracht, Vera; Smith, Ryan; Lackmann, Jan-Wilm; Awakowicz, Peter; Stapelmann, Katharina; Bimap Team; Aept Team

    2016-09-01

    Non-thermal atmospheric-pressure plasmas are advantageous for various biomedical applications as they make a contact- and painless therapy possible. Due to the potential medical relevance of such plasma sources further understanding of the chemical and physical impact on biological tissue regarding the efficacy and health-promoting effect is necessary. The knowledge of properties and effects offers the possibility to configure plasmas free of risk for humans. Therefore, tailoring the discharge chemistry in regard to resulting oxidative and nitrosative effects on biological tissue by adjusting different parameters is of growing interest. In order to ensure stable conditions for the characterization of the discharge, the used dielectric barrier discharge was mounted in a vessel. Absolutely calibrated optical emission spectroscopy was carried out to analyze the electron density and the reduced electric field. The rather oxygen-based discharge was tuned towards a more nitrogen-based discharge by adjusting several parameters as reactive nitrogen species are known to promote wound healing. Furthermore, the impact of an ozone-free discharge has to be studied. This work was funded by the German Research Foundation (DFG) with the packet grant PAK 816 `Plasma Cell Interaction in Dermatology'.

  19. Excitation of rare gases in an electron-beam-controlled discharge: report on preliminary experiments

    International Nuclear Information System (INIS)

    Bingham, F.W.

    1976-05-01

    Data from the preliminary phase of a study of rare-gas-excimer production in an electron-beam-controlled discharge are presented. The results indicate that it is possible to maintain an arc-free discharge in preionized Ar and Xe gas for a period of several microseconds at applied external E/p values up to 5 V/cm/Torr. In these experiments ultraviolet radiation emitted during the discharge signaled the presence of excited rare-gas molecules. Application of the external electric field significantly enhanced the ultraviolet intensity from xenon-gas discharges but produced little enhancement from argon-gas discharges

  20. The application of the German reg. guides ('elements of calculation') for radioactive discharges via exhaust air and waste water on fuel element fabrication

    International Nuclear Information System (INIS)

    Hille, R.; Rudolph, W.

    1978-01-01

    The fuel element fabricating plants at Hanau are handlung uranium, plutonium and thorium. The process essentially of converting these heavy metals into oxide, carbide or metal compounds. Thereby occur radioactive discharges into the exhaust air and the waste water. The most important pathway for exposure from these substances is inhalation, the released radionuclides mostly being α-emitters. Compared to this the external irradiation from immersion in γ, β, and neutron radiation is of less importance. (orig./HP) [de

  1. Environmental effects of thermal and radioactive discharges from nuclear power plants in the boreal brackish-water conditions of the northern Baltic Sea

    OpenAIRE

    Ilus, Erkki

    2009-01-01

    During recent decades, thermal and radioactive discharges from nuclear power plants into the aquatic environment have become the subject of lively debate as an ecological concern. The target of this thesis was to summarize the large quantity of results obtained in extensive monitoring programmes and studies carried out in recipient sea areas off the Finnish nuclear power plants at Loviisa and Olkiluoto during more than four decades. The Loviisa NPP is located on the coast of the Gulf of Finla...

  2. Hydrogeological controls on spatial patterns of groundwater discharge in peatlands

    Directory of Open Access Journals (Sweden)

    D. K. Hare

    2017-11-01

    Full Text Available Peatland environments provide important ecosystem services including water and carbon storage, nutrient processing and retention, and wildlife habitat. However, these systems and the services they provide have been degraded through historical anthropogenic agricultural conversion and dewatering practices. Effective wetland restoration requires incorporating site hydrology and understanding groundwater discharge spatial patterns. Groundwater discharge maintains wetland ecosystems by providing relatively stable hydrologic conditions, nutrient inputs, and thermal buffering important for ecological structure and function; however, a comprehensive site-specific evaluation is rarely feasible for such resource-constrained projects. An improved process-based understanding of groundwater discharge in peatlands may help guide ecological restoration design without the need for invasive methodologies and detailed site-specific investigation. Here we examine a kettle-hole peatland in southeast Massachusetts historically modified for commercial cranberry farming. During the time of our investigation, a large process-based ecological restoration project was in the assessment and design phases. To gain insight into the drivers of site hydrology, we evaluated the spatial patterning of groundwater discharge and the subsurface structure of the peatland complex using heat-tracing methods and ground-penetrating radar. Our results illustrate that two groundwater discharge processes contribute to the peatland hydrologic system: diffuse lower-flux marginal matrix seepage and discrete higher-flux preferential-flow-path seepage. Both types of groundwater discharge develop through interactions with subsurface peatland basin structure, often where the basin slope is at a high angle to the regional groundwater gradient. These field observations indicate strong correlation between subsurface structures and surficial groundwater discharge. Understanding these general patterns

  3. Hydrogeological controls on spatial patterns of groundwater discharge in peatlands

    Science.gov (United States)

    Hare, Danielle K.; Boutt, David F.; Clement, William P.; Hatch, Christine E.; Davenport, Glorianna; Hackman, Alex

    2017-11-01

    Peatland environments provide important ecosystem services including water and carbon storage, nutrient processing and retention, and wildlife habitat. However, these systems and the services they provide have been degraded through historical anthropogenic agricultural conversion and dewatering practices. Effective wetland restoration requires incorporating site hydrology and understanding groundwater discharge spatial patterns. Groundwater discharge maintains wetland ecosystems by providing relatively stable hydrologic conditions, nutrient inputs, and thermal buffering important for ecological structure and function; however, a comprehensive site-specific evaluation is rarely feasible for such resource-constrained projects. An improved process-based understanding of groundwater discharge in peatlands may help guide ecological restoration design without the need for invasive methodologies and detailed site-specific investigation. Here we examine a kettle-hole peatland in southeast Massachusetts historically modified for commercial cranberry farming. During the time of our investigation, a large process-based ecological restoration project was in the assessment and design phases. To gain insight into the drivers of site hydrology, we evaluated the spatial patterning of groundwater discharge and the subsurface structure of the peatland complex using heat-tracing methods and ground-penetrating radar. Our results illustrate that two groundwater discharge processes contribute to the peatland hydrologic system: diffuse lower-flux marginal matrix seepage and discrete higher-flux preferential-flow-path seepage. Both types of groundwater discharge develop through interactions with subsurface peatland basin structure, often where the basin slope is at a high angle to the regional groundwater gradient. These field observations indicate strong correlation between subsurface structures and surficial groundwater discharge. Understanding these general patterns may allow resource

  4. Organization of customs control of fissionable and other radioactive materials

    International Nuclear Information System (INIS)

    Ukhlinov, L.; Bojko, V.

    2001-01-01

    Among the routine inspection tasks of the Sheremetyevo customs office are tasks stemming from international commitments of Russia to prevent proliferation of nuclear weapons and material that can be used for making these weapons. These tasks are: radiation monitoring of all vehicles, passengers, their luggage and goods crossing the state border; inspection of fissionable and radioactive materials (FRM) legally transported by participants in the foreign trade activities with a view to checking that the declared data fully correspond to the actual radioactive cargo. Organizational measures and technical measures at the Sheremetyevo customs office are described in detail. The efficiency of the scheme is illustrated by the following figures. In 1997, when appropriate technical means and trained personnel were lacking, there were only 2 events of detecting items with a rather high radioactivity level in the luggage. In 1999, after the entire radiation monitoring system was fully deployed (i.e. the flight checkpoint was equipped with technical means of radiation monitoring, personnel was trained, special technologies and algorithms were developed), there were 61 events of radiation detection, and in 2000 there have been 90 events, including breaches of legal FRM traffic regulations through disagreement of declared and actual parameters. We believe that the above-considered organization of radiation monitoring allows effective and quite reliable control of and adequate response to possible illicit transport of FRM through the airport Sheremetyevo to other countries, including CIS. In the near future we plan to increase the efficiency of the radiation monitoring by integrating the currently operational customs-used stationary FRM detection systems into a single information network capable of providing simultaneous video-aided continuous nuclear monitoring at three terminals (Sheremetyevo-1, Sheremetyevo-2, Sheremetyevo-Cargo) with display of information at the workstation

  5. The control of the radioactive pollution of milk (1962)

    International Nuclear Information System (INIS)

    Michon, G.

    1962-01-01

    Milk, an essential foodstuff, is the object of a supervision and vigilant controls governed by numerous laws which protect its commercial and sanitary qualities. The development of the use of nuclear energy poses and will pose new problems of hygiene and the milk should benefit from controls concerning its possible contamination. Grass-eating animals are particularly subjected to radioactive contaminations and the milk which they produce does not escape contamination because of of its saline composition and of the particular metabolism of the mammary gland. As a result, milk is a contamination integrator and its analysis makes it possible to detect radioelements which can only be detected with great difficulty in an average size plant sample. (author) [fr

  6. Criteria of exemption of regulatory control for radioactive material

    International Nuclear Information System (INIS)

    Marco A. Medrano Lopez

    1991-01-01

    Being based on the information contained in the 10 CFR Part 20, of the section 20.301 until the 20.306 where the mechanisms by means of which can prepare the waste of low level are indicated. While the Nuclear Regulatory Commission (NRC) it amended in the year of 1985 the Act of Politics on Low level Wastes, in particular the section 10 of the amendment of the Act, relative to the concept BRC treats those groups of radioactive waste in that their activity contents are so low that they could be exempt of the regulatory control, either liberating them toward the environment or to exempt people or organizations of the regulatory control

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

    International Nuclear Information System (INIS)

    1985-01-01

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

  8. 40 CFR 230.72 - Actions controlling the material after discharge.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Actions controlling the material after discharge. 230.72 Section 230.72 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) OCEAN... Actions To Minimize Adverse Effects § 230.72 Actions controlling the material after discharge. The effects...

  9. INDAR: a computer code for the calculation of critical group radiation exposure from routine discharges of radioactivity to seas and estuaries - description and users' guide

    International Nuclear Information System (INIS)

    Maul, P.R.; Wilmott, S.

    1988-12-01

    The computer program INDAR enables detailed estimates to be made of critical group radiation exposure arising from routine discharges of radioactivity for coastal sites where the discharge is close to the shore and the shoreline is reasonably straight, and for estuarine sites where radioactivity is rapidly mixed across the width of the estuary. Important processes which can be taken into account include the turbulence generated by the discharge, the effects of a sloping sea bed and the variation with time of the lateral dispersion coefficient. The significance of the timing of discharges can also be assessed. INDAR uses physically meaningful hydrographic parameters directly. For most sites the most important exposure pathways are seafood consumption, external exposure over estuarine sediments and beaches, and the handling of fishing gear. As well as for these primary pathways, INDAR enables direct calculations to be made for some additional exposure pathways. The secondary pathways considered are seaweed consumption, swimming, the handling of materials other than fishing gear and the inhalation of activity. (author)

  10. National policy for control of radioactive sources and radioactive waste from non-power applications in Lithuania

    International Nuclear Information System (INIS)

    Klevinskas, G.; Mastauskas, A.

    2001-01-01

    According to the Law on Radiation Protection of the Republic of Lithuania (passed in 1999), the Radiation Protection Centre of the Ministry of Health is the regulatory authority responsible for the radiation protection of public and of workers using sources of ionizing radiation in Lithuania. One of its responsibilities is the control of radioactive sources from the beginning of their 'life cycle', when they are imported in, used, transported and placed as spent into the radioactive waste storage facilities. For the effective control of sources there is national authorization system (notification- registration-licensing) based on the international requirements and recommendations introduced, which also includes keeping and maintaining the Register of Sources, controlling and investigating events while illegally carrying on or in possession of radioactive material, decision making and performing the state radiation protection supervision and control of users of radioactive sources, controlling, within the limits of competence, the radioactive waste management activities in nuclear and non-nuclear power applications. According to the requirements set out in the Law on Radiation Protection and the Government Resolution 'On Establishment of the State Register of the Sources of Ionizing Radiation and Exposure of Workers' (1999) and supplementary legal acts, all licence-holders conducting their activities with sources of ionizing radiation have to present all necessary data to the State Register after annual inventory of sources, after installation of new sources, after decommissioning of sources, after disposal of spent sources, after finishing the activities with the generators of ionizing radiation. The information to the Radiation Protection Centre has to be presented every week from the Customs Department of the Ministry of Finance about all sources of ionizing radiation imported to or exported from Lithuania and the information about the companies performed these

  11. ESCLOUD: A computer program to calculate the air concentration, deposition rate and external dose rate from a continuous discharge of radioactive material to atmosphere

    International Nuclear Information System (INIS)

    Jones, J.A.

    1980-03-01

    Radioactive material may be discharged to atmosphere in small quantities during the normal operation of a nuclear installation as part of a considered waste management practice. Estimates of the individual and collective dose equivalent rates resulting from such a discharge are required in a number of contexts: for example, in assessing compliance with dose limits, in estimating the radiological impact of the discharge and as an input into optimisation studies. The suite of programs which has been developed to undertake such calculations is made up of a number of independent modules one of which, ESCLOUD, is described in this report. The ESCLOUD program evaluates, as a function of distance and direction from the release point, the air concentration, deposition rate and external β and γ doses from airborne and deposited activity. The air concentration and deposition rate can be used as input to other modules for calculating inhalation and ingestion doses. (author)

  12. Preliminary Studies on Aerodynamic Control with Direct Current Discharge at Hypersonic Speed

    Science.gov (United States)

    Watanabe, Yasumasa; Takama, Yoshiki; Imamura, Osamu; Watanuki, Tadaharu; Suzuki, Kojiro

    A new idea of an aerodynamic control device for hypersonic vehicles using plasma discharges is presented. The effect of DC plasma discharge on a hypersonic flow is examined with both experiments and CFD analyses. It is revealed that the surface pressure upstream of plasma area significantly increases, which would be preferable in realizing a new aerodynamic control devices. Such pressure rise is also observed in the result of analyses of the Navier-Stokes equations with energy addition that simulates the Joule heating of a plasma discharge. It is revealed that the pressure rise due to the existence of the plasma discharge can be qualitatively explained as an effect of Joule heating.

  13. Response of lead-acid batteries to chopper-controlled discharge: Preliminary results

    Science.gov (United States)

    Cataldo, R. L.

    1978-01-01

    The preliminary results of simulated electric vehicle, chopper, speed controller discharge of a battery show energy output losses up to 25 percent compared to constant current discharges at the same average discharge current of 100 amperes. These energy losses are manifested as temperature rises during discharge, amounting to a two-fold increase for a 400-ampere pulse compared to the constant current case. Because of the potentially large energy inefficiency, the results suggest that electric vehicle battery/speed controller interaction must be carefully considered in vehicle design.

  14. Response of lead-acid batteries to chopper-controlled discharge

    Science.gov (United States)

    Cataldo, R. L.

    1978-01-01

    The preliminary results of simulated electric vehicle, chopper, speed controller discharge of a battery show energy output losses at up to 25 percent compared to constant current discharges at the same average discharge current of 100 A. These energy losses are manifested as temperature rises during discharge, amounting to a two-fold increase for a 400-A pulse compared to the constant current case. Because of the potentially large energy inefficiency, the results suggest that electric vehicle battery/speed controller interaction must be carefully considered in vehicle design.

  15. 40 CFR 1700.4 - Discharges requiring control.

    Science.gov (United States)

    2010-07-01

    ... training, testing, or maintenance operations. (b) Catapult Water Brake Tank & Post-Launch Retraction... seawater. (j) Elevator Pit Effluent: the liquid that accumulates in, and is discharged from, the sumps of elevator wells on vessels. (k) Firemain Systems: the seawater pumped through the firemain system for...

  16. Nuclear medicine environmental discharge measurement. Final report

    International Nuclear Information System (INIS)

    Gesell, T.F.; Prichard, H.M.; Davis, E.M.; Pirtle, O.L.; DiPietro, W.

    1975-06-01

    The discharge of most man-made radioactive materials to the environment is controlled by Federal, State or local regulatory agencies. Exceptions to this control include the radioactive wastes eliminated by individuals who have undergone diagnostic or therapeutic nuclear medicine procedures. The purpose of this study is to estimate the amount of radioactivity released to the environment via the nuclear medicine pathway for a single sewage drainage basin and to measure the amounts discharged to the environment. The report is organized into a review of previous studies, scope of work, facility data, environmental measurements and estimates of population exposure

  17. Estimated radiological effects of the normal discharge of radioactivity from nuclear power plants in the Netherlands with a total capacity of 3500 MWe

    International Nuclear Information System (INIS)

    Lugt, G. van der; Wijker, H.; Kema, N.V.

    1977-01-01

    In the Netherlands discussions are going on about the installation of three nuclear power plants, leading with the two existing plants to a total capacity of 3500 MWe. To have an impression of the radiological impact of this program, calculations were carried out concerning the population doses due to the discharge of radioactivity from the plants during normal operation. The discharge via the ventilation stack gives doses due to noble gases, halogens and particulate material. The population dose due to the halogens in the grass-milk-man chain is estimated using the real distribution of grass-land around the reactor sites. It could be concluded that the population dose due to the contamination of crops and fruit is negligeable. A conservative estimation is made for the dose due to the discharge of tritium. The population dose due to the discharge in the cooling water is calculated using the following pathways: drinking water; consumption of fish; consumption of meat from animals fed with fish products. The individual doses caused by the normal discharge of a 1000 MWe plant appeared to be very low, mostly below 1 mrem/year. The population dose is in the order of some tens manrems. The total dose of the 5 nuclear power plants to the dutch population is not more than 70 manrem. Using a linear dose-effect relationship the health effects to the population are estimated and compared with the normal frequency

  18. Potential of electrical gas discharges for pollution control of large gas volumes

    International Nuclear Information System (INIS)

    Kogelschatz, U.

    1997-01-01

    Non-equilibrium gas discharges in many cases offer an innovative approach to the solution cf industrial air pollution problems. Negative corona discharges are used in electrostatic precipitators to collect dust and fly ash particles. Pulsed positive streamer coronas, dielectric-barrier discharges and possibly also flow-stabilised high pressure glow discharges are emerging technologies for the destruction of air pollutants like nitrogen oxides and sulfur dioxide in flue gases and volatile organic compounds (VOCs) in industrial effluents. The different discharge types are discussed with special emphasis on their potential for upscaling. Major applications are expected particularly in the removal of dilute concentrations of air pollutants, in odour control and in the simultaneous removal of different pollutants. Dielectric-barrier discharges exhibit disposal efficiencies similar to those of pulsed positive streamer coronas and require less sophisticated feeding circuits in large-scale industrial applications. (author)

  19. Control of high level radioactive waste-glass melters

    International Nuclear Information System (INIS)

    Bickford, D.F.; Choi, A.S.

    1991-01-01

    Slurry Fed Melters (SFM) are being developed in the United States, Europe and Japan for the conversion of high-level radioactive waste to borosilicate glass for permanent disposal. The high transition metal, noble metal, nitrate, organic, and sulfate contents of these wastes lead to unique melter redox control requirements. Pilot waste-glass melter operations have indicated the possibility of nickel sulfide or noble-metal fission-product accumulation on melter floors, which can lead to distortion of electric heating patterns, and decrease melter life. Sulfide formation is prevented by control of the redox chemistry of the melter feed. The redox state of waste-glass melters is determined by balance between the reducing potential of organic compounds in the feed, and the oxidizing potential of gases above the melt, and nitrates and polyvalent elements in the waste. Semiquantitative models predicting limitations of organic content have been developed based on crucible testing. Computerized thermodynamic computations are being developed to predict the sequence and products of redox reactions and is assessing process variations. Continuous melter test results have been compared to improved computer staged-thermodynamic-models of redox behavior. Feed chemistry control to prevent sulfide and moderate noble metal accumulations are discussed. 17 refs., 3 figs

  20. Loopholes of laws and regulations related to redevelopment of former sites of radioactive material control area

    International Nuclear Information System (INIS)

    Akatsuka, Hiroshi

    2003-01-01

    We found loopholes of laws and regulations for supervising radioactive materials. It is not obliged to measure the soil radioactivity of the sites that were formerly used as scientific or engineering institutes, or hospitals with a radioactive material control area. If the former institutes or hospitals made studies with radioactive materials before the enforcement of the law concerning prevention from radiation hazards due to isotopes and its detailed regulations, it is concluded that there was the period when the radioactive materials were not under management. If it is found that the radioactive materials were applied at the former site before the enforcement of the related laws and regulations, the radioactivity in the soil of the redeveloped area should be examined, which should be obliged by some laws or regulations. (author)

  1. Catchment heterogeneity controls emergent archetype concentration-discharge relationships

    Science.gov (United States)

    Musolff, A.; Fleckenstein, J. H.; Rao, P. S.; Jawitz, J. W.

    2017-12-01

    Relationships between in-stream dissolved solute concentrations (C) and discharge (Q) are often-used indicators of catchment-scale processes and their interference with human activities. Here we analyze observational C-Q relationships from 61 catchments and 8 different solutes across a wide range of land-uses and discharge regimes. This analysis is combined with a parsimonious stochastic modeling approach to test how C-Q relationships arise from spatial heterogeneity in catchment solute sources coupled with different timescales of biogeochemical reactions. The observational data exhibit archetypical dilution, enrichment, and constant C-Q patterns. Moreover, with land-use intensification we find decreasing C variability relative to Q variability (chemostatic export regime). Our model indicates that the dominant driver of emergent C-Q patterns was structured heterogeneity of solute sources implemented as correlation of source concentration to travel time. Regardless of the C-Q pattern, with decreasing source heterogeneity we consistently find lower variability in C than in Q and a dominance of chemostatic export regimes. Here, the variance in exported loads is determined primarily by variance of Q. We conclude that efforts to improve stream water quality and ecological integrity in intensely managed catchments should lead away from landscape homogenization by introducing structured source heterogeneity. References: Musolff, A., J. H. Fleckenstein, P. S. C. Rao, and J. W. Jawitz (2017), Emergent archetype patterns of coupled hydrologic and biogeochemical responses in catchments, Geophys. Res. Lett., 44(9), 4143-4151, doi: 10.1002/2017GL072630.

  2. Partial oxidation of methane in a temperature-controlled dielectric barrier discharge reactor

    KAUST Repository

    Zhang, Xuming; Cha, Min

    2015-01-01

    We studied the relative importance of the reduced field intensity and the background reaction temperature in the partial oxidation of methane in a temperature-controlled dielectric barrier discharge reactor. We obtained important mechanistic insight

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

    International Nuclear Information System (INIS)

    Esch, D.; Wittwer, C.

    2014-01-01

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

  4. 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

  5. Controlled structures in laterally patterned barrier discharges by illumination of the semiconductor electrode

    International Nuclear Information System (INIS)

    Wild, R; Schumann, T; Stollenwerk, L

    2014-01-01

    In this contribution, we present a possibility to actively control emerging patterns in laterally extended barrier discharges. One of the barriers is a high-ohmic semiconductive GaAs electrode. As the electrode is illuminated from its plasma-far side, the voltage inside the plasma gap is increased. If the gap voltage becomes higher than the ignition voltage of the gas, a discharge is started. A corresponding electrical model is given. The lateral resolution of control for a laterally homogeneous discharge is investigated. It is found that the luminescence of the discharge is controlled by both a variation of illumination power density and a variation of the applied voltage. However, during an increase in the applied voltage, the discharge may become larger than the area of illumination. Further, an investigation of the patterned discharge control shows that the number of current spots depends on the illumination power density and the area of illumination. The behaviour of current spot appearance suggests an inhibitory influence, preventing a discharge in its immediate surrounding and limiting the total number of current spots. (paper)

  6. Improving discharge care: the potential of a new organisational intervention to improve discharge after hospitalisation for acute stroke, a controlled before–after pilot study

    OpenAIRE

    Cadilhac, Dominique A; Andrew, Nadine E; Stroil Salama, Enna; Hill, Kelvin; Middleton, Sandy; Horton, Eleanor; Meade, Ian; Kuhle, Sarah; Nelson, Mark R; Grimley, Rohan

    2017-01-01

    Objective Provision of a discharge care plan and prevention therapies is often suboptimal. Our objective was to design and pilot test an interdisciplinary, organisational intervention to improve discharge care using stroke as the case study using a mixed-methods, controlled before–after observational study design. Setting Acute care public hospitals in Queensland, Australia (n=15). The 15 hospitals were ranked against a benchmark based on a composite outcome of three discharge care processes....

  7. Operation of controlled-air incinerators and design considerations for controlled-air incinerators treating hazardous and radioactive wastes

    International Nuclear Information System (INIS)

    McRee, R.E.

    1986-01-01

    This paper reviews the basic theory and design philosophies of the so-called controlled-air incinerator and examines the features of this equipment that make it ideally suited to the application of low-level radioactive waste disposal. Special equipment design considerations for controlled air incinerators treating hazardous and radioactive wastes are presented. 9 figures

  8. Radioactive contamination of Bunodosoma caissarum under controlled conditions

    International Nuclear Information System (INIS)

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

    The kinetics of uptake and release of radionuclides 137 Cs, 131 I, 133 Ba, 51 Cr (III and VI), 60 Co and 65 Zn in the 'cnidaria' Bunodosoma caissarum have been studied. This is an exclusively Brazilian species and easily collected on the Rio de Janeiro coastal waters. The kinetic experiments have been made in aquariums of 1000 cm 3 , in laboratory under controlled conditions and accompanied by single channel radiometry. The velocities of concentration were evident to radionuclides 131 I and 133 Ba. The larger concentration factors were registred to 51 Cr (III), 65 Zn and 51 Cr (VI), with middle values of 20,0 , 14,5 and 8,6 respectively. The same radionuclides stood out in the loss experiments, presenting the following biological half-lives : 292,2 h ( 51 Cr-III), 784,0 h ( 51 Cr-VI) and 823,0 h ( 65 Zn). This expressive value for the 65 Zn suggests a probable biological integration of this radionuclide by the species studied. The results allow us to indicate the 'anthozoa' Bunodosoma caissarum as a bioindicator of the radioactive contamination of the marine environment. (Author) [pt

  9. Radioactive waste tank ventilation system incorporating tritium control

    Energy Technology Data Exchange (ETDEWEB)

    Rice, P.D. [ICF Kaiser Hanford Company, Richland, WA (United States)

    1997-08-01

    This paper describes the development of a ventilation system for radioactive waste tanks at the U.S. Department of Energy`s (DOE) Hanford Site in Richland, Washington. The unique design of the system is aimed at cost-effective control of tritiated water vapor. The system includes recirculation ventilation and cooling for each tank in the facility and a central exhaust air clean-up train that includes a low-temperature vapor condenser and high-efficiency mist eliminator (HEME). A one-seventh scale pilot plant was built and tested to verify predicted performance of the low-temperature tritium removal system. Tests were conducted to determine the effectiveness of the removal of condensable vapor and soluble and insoluble aerosols and to estimate the operating life of the mist eliminator. Definitive design of the ventilation system relied heavily on the test data. The unique design features of the ventilation system will result in far less release of tritium to the atmosphere than from conventional high-volume dilution systems and will greatly reduce operating costs. NESHAPs and TAPs NOC applications have been approved, and field construction is nearly complete. Start-up is scheduled for late 1996. 3 refs., 4 figs., 2 tabs.

  10. 49 CFR 178.338-11 - Discharge control devices.

    Science.gov (United States)

    2010-10-01

    ... pump or compressor is used to open this valve, the control must be of fail-safe design and spring... activate the emergency control system. (ii) On a cargo tank motor vehicle of 3,500 gallons water capacity... control system. [Amdt. 178-77, 48 FR 27705, June 16, 1983, as amended by Amdt. 178-105, 59 FR 55173, Nov...

  11. Regulatory control of radioactivity and nuclear fuel cycle in Canada

    International Nuclear Information System (INIS)

    Hamel, P.E.; Jennekens, J.H.

    1977-01-01

    The mining of pitchblende for the extraction of radium some four decades ago resulted in a largely unwanted by-product, uranium, which set the stage for Canada to be one of the first countires in the world to embark upon a nuclear energy program. From this somewhat unusual beginning, the Canadian program expanded beyond mining of uranium-bearing ores to include extensive research and development in the field of radio-isotope applications, research and power reactors, nuclear-fuel conversion and fabrication facilities, heavy-water production plants and facilities for the management of radioactive wastes. As in the case of any major technological development, nuclear energy poses certain risks on the part of those directly engaged in the industry and on the part of the general public. What characterizes these risks is not so much their physical nature as the absence of long-term experience and the confidence resulting from it. The early development of regulatory controls in the nuclear field in Canada was very much influenced by security considerations but subsequently evolved to include radiological protection and safety requirements commensurate with the expanding application of nuclear energy to a wide spectrum of peaceful uses. A review of Canadian nuclear regulatory experience will reveal that the risks posed by the peaceful uses of nuclear energy can be controlled in such a manner as to ensure a high level of safety. Recent events and development have shown however that emphasis on the risks associated with low-probability, high-consequence events must not be allowed to mask the importance of health and safety measures covering the entire fuel cycle

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

    International Nuclear Information System (INIS)

    Pravdivyj, A.A.

    2003-01-01

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

  13. Controls exercised by the Army over radioactive consumer-type items

    International Nuclear Information System (INIS)

    Taras, D.N.

    1978-01-01

    There are considerations that must be taken into account in the selection of radioactive products for military use that are of less consequence in consumer use. Because of these considerations, the Army and the other military services exercise control over radioactive commodities for military use. This paper describes the requirements of the Army safety policy

  14. The importance of governmental control of radioactive sources used in industrial applications

    International Nuclear Information System (INIS)

    Anna Firpo Fuerth, Q.F.; Beatriz Souto Ameigenda, Q.F.

    1998-01-01

    Industrial applications of radioactive sources require good management practices dealing with control and registration. In the following case, a special event occurred between two routine inspections: trading. Then a new human factor came into scene: workers with no specific training and knowledge related to radioactive sources. The up going situation triggered emergency procedures. Finally, there were no negative consequences. (author)

  15. The control of the radioactive pollution of milk (1962); Comment concevoir une surveillance des pollutions radioactives du lait (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Milk, an essential foodstuff, is the object of a supervision and vigilant controls governed by numerous laws which protect its commercial and sanitary qualities. The development of the use of nuclear energy poses and will pose new problems of hygiene and the milk should benefit from controls concerning its possible contamination. Grass-eating animals are particularly subjected to radioactive contaminations and the milk which they produce does not escape contamination because of of its saline composition and of the particular metabolism of the mammary gland. As a result, milk is a contamination integrator and its analysis makes it possible to detect radioelements which can only be detected with great difficulty in an average size plant sample. (author) [French] Le lait, aliment essentiel, fait l'objet d'une surveillance et de controles vigilants regis par de nombreux textes legislatifs qui protegent ses qualites marchandes et sanitaires. Le developpement de l'utilisation de l'energie nucleaire pose et posera de nouveaux problemes d'hygiene et le lait doit beneficier de controles portant sur sa pollution radioactive eventuelle. Les, animaux herbivores sont particulierement exposes aux contaminations radioactives et les laits qu'ils produisent, du fait de leurs compositions salines et du metabolisme particulier de la glande mammaire, n'echappent point aux pollutions. De ce fait, le lait est un integrateur de contamination et son analyse permet de retrouver des radioelements que l'on ne decele qu'avec beaucoup de difficultes sur un echantillon vegetal de taille moyenne. (auteur)

  16. USING STATISTICAL PROCESS CONTROL TO MONITOR RADIOACTIVE WASTE CHARACTERIZATION AT A RADIOACTIVE FACILITY

    International Nuclear Information System (INIS)

    WESTCOTT, J.L.

    2006-01-01

    Two facilities for storing spent nuclear fuel underwater at the Hanford site in southeastern Washington State being removed from service, decommissioned, and prepared for eventual demolition. The fuel-storage facilities consist of two separate basins called K East (KE) and K West (KW) that are large subsurface concrete pools filled with water, with a containment structure over each. The basins presently contain sludge, debris, and equipment that have accumulated over the years. The spent fuel has been removed from the basins. The process for removing the remaining sludge, equipment, and structure has been initiated for the basins. Ongoing removal operations generate solid waste that is being treated as required, and then disposed. The waste, equipment and building structures must be characterized to properly manage, ship, treat (if necessary), and dispose as radioactive waste. As the work progresses, it is expected that radiological conditions in each basin may change as radioactive materials are being moved within and between the basins. It is imperative that these changing conditions be monitored so that radioactive characterization of waste is adjusted as necessary

  17. USING STATISTICAL PROCESS CONTROL TO MONITOR RADIOACTIVE WASTE CHARACTERIZATION AT A RADIOACTIVE FACILITY

    International Nuclear Information System (INIS)

    WESTCOTT, J.L.; JOCHEN; PREVETTE

    2007-01-01

    Two facilities for storing spent nuclear fuel underwater at the Hanford site in southeastern Washington State are being removed from service, decommissioned, and prepared for eventual demolition. The fuel-storage facilities consist of two separate basins called K East (KE) and K West (KW) that are large subsurface concrete pools filled with water, with a containment structure over each. The basins presently contain sludge, debris, and equipment that have accumulated over the years. The spent fuel has been removed from the basins. The process for removing the remaining sludge, equipment, and structure has been initiated for the basins. Ongoing removal operations generate solid waste that is being treated as required, and then disposed. The waste, equipment and building structures must be characterized to properly manage, ship, treat (if necessary), and dispose as radioactive waste. As the work progresses, it is expected that radiological conditions in each basin may change as radioactive materials are being moved within and between the basins. It is imperative that these changing conditions be monitored so that radioactive characterization of waste is adjusted as necessary

  18. User interaction concept for plasma discharge control on WENDELSTEIN 7-X

    International Nuclear Information System (INIS)

    Spring, Anett; Laqua, Heike; Niedermeyer, Helmut

    2006-01-01

    The requirements to the user interfaces arising from the concept of segmented discharges allowing short pulses and steady state operation and from the distributed hierarchical structure of the experiment are discussed. The modular design of the user interfaces is presented including specialised tools for preparation, manipulating, and monitoring the discharge operation. The user guidance and the mapping of complex control procedures onto a physically relevant view on the plasma discharge process will be vitally important. The feasibility of the user interaction concept could already be validated on a prototype installation and during commissioning of the first technical WENDELSTEIN 7-X (W7-X) components

  19. The Radioactive Waste Management Advisory Committee's. Advice on issues which need to be addressed in the Guidance to be given to the Environment Agencies on the Principles for determining Radioactive Waste Discharge Authorisations - the 'Principles Document'

    International Nuclear Information System (INIS)

    1998-07-01

    In January 1998, the Minister for the Environment, Mr Michael Meacher, informed the Radioactive Waste Management Advisory Committee (RWMAC) that, during the coming year, he would welcome the Committee's advice on proposals for guidance from the Department of the Environment, Transport and the Regions (DETR) to the Environment Agencies on assessment principles for determining radioactive waste discharge authorisations. This will hereafter be referred to as the Principles Document. The RWMAC has provided advice on the process of regulating radioactive waste discharges for many years. A summary of some of this activity is given in Annex 1. As a result, it has been pressing for this Principles Document guidance to be made available since its Twelfth Report in 1991. In response to the Minister's request, the RWMAC offered to assemble and submit early advice on what it believes the guidance needs to cover: this document fulfils that offer. The fundamental purpose of the advice is to help promote clarity of the regulatory regime for the benefit of the regulators themselves who must apply it, the industry to whom it is applied and, most importantly, the public whose safety it is designed to protect. Clarification of a number of aspects of the process is also likely to provide opportunity for efficiency gains. At a subsequent stage, the RWMAC will be happy to provide comment on any draft principles documentation prepared by the DETR. The RWMAC acknowledges that some of the issues it raises in this advice could be taken by others to be either outside the scope of the Principles Document or, by implying a need for more fundamental consideration of the discharge authorisation process, could potentially preclude its early publication. In the first instance, reference to an alternative source of relevant advice might suffice, providing this advice is itself easily accessible and understandable. In the second, the issue itself might be one to be fed into the Government's planned

  20. Dielectric Barrier Discharge Plasma Actuators for Aerodynamic Control, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — Flow control is critical to the effective operation of space vehicles where high velocities must be achieved with minimum power consumption. Recent studies at...

  1. Clearance of slightly radioactive material from radiological control in Germany

    International Nuclear Information System (INIS)

    Thierfeldt, S.

    1995-01-01

    Clearance from radiological control of slightly radioactive material arising from operation or decommissioning of nuclear installations has been practiced in Germany for nearly two decades. Meanwhile, for the clearance of metal generally approved and applicable recommendations for clearance levels have been issued. For other materials like building waste, case-by-case decisions are made by the state licensing authorities. Efforts to implement consistent sets of clearance levels for all kinds of material are under way. As several decommissioning projects will soon generate large amounts of materials from dismantling, a solution needs to be reached soon. The legal framework in Germany governing the use of atomic energy consists of the Atomic Energy Act and several ordinances. Rules and guidelines including the recommendations of the German Commission for Radiation Protection (SSK) exist on a lower level and are not legally binding. Several generic studies for the derivation of clearance levels for metals and building debris with alpha, beta, and gamma contamination have been performed on behalf of the Federal Ministry for Environment, Nature Conservation and Nuclear Safety, which oriented themselves on an individual dose of 10 microSv/a in agreement with IAEA recommendations. Stochastic models have been used for establishing the connection between specific activity of the material to be released and the resulting individual doses, with significant advantages over deterministic scenarios. In the future, for new SSK recommendations or an ordinance on clearance, the increase of masses from demolition of installations, higher recycling rates in the conventional sector and harmonization with international regulations and standards have to be taken into account

  2. Angina - discharge

    Science.gov (United States)

    Chest pain - discharge; Stable angina - discharge; Chronic angina - discharge; Variant angina - discharge; Angina pectoris - discharge; Accelerating angina - discharge; New-onset angina - discharge; Angina-unstable - discharge; ...

  3. Study on the improved evaluation of radioactivity of activated control rods in PWR

    International Nuclear Information System (INIS)

    Waki, Toshikazu; Yamada, Motoyuki; Horikawa, Yoshihiko; Miyake, Yusuke; Sakashita, Akira

    2009-01-01

    The evaluation method of radioactivity of activated materials has been developed as ORIGEN code. However, it is difficult to precisely evaluate the radioactivity of neutron absorption materials such as control rods. A control rod in PWR is made of Ag-In-Cd alloy that absorbs neutron greatly and the thermal neutron flux decreases rapidly in and around it. This phenomenon is called depression effect. The consideration of depression effect is necessary to evaluate radioactivity of the control rod. In this study we improved the reliability of the cross-section value of Ag-107(n,γ) Ag-108m by the irradiation examination in JRR3. In addition, we calculated (1) the neutron spectrum and neutron flux with depression effect by MCNP of Monte Carlo method and (2) the radioactivity of the activated control rod. The pieces of control rod were irradiated at JMTR of JAERI. As a result of the accuracy of the measurement data calculation results, we developed the method of evaluation for the radioactivity of activated control rod. The radioactivity of activated control rod in PWR was evaluated and compared with the measurement data, resulting in positive accuracy. Of special significance was confirmation of the value of Ag-108m, as an essential nuclide for long term dose estimation of disposal facility. The cross-section value of Ag-107(n,γ) Ag-108m was about one forty of existent library. This method was accurately confirmed and developed for evaluating activated control rods reasonably. (author)

  4. ASDEX Upgrade Discharge Control System—A real-time plasma control framework

    International Nuclear Information System (INIS)

    Treutterer, W.; Cole, R.; Lüddecke, K.; Neu, G.; Rapson, C.; Raupp, G.; Zasche, D.; Zehetbauer, T.

    2014-01-01

    Highlights: • The ASDEX Upgrade Discharge Control System (DCS) is a comprehensive control system to conduct fusion experiments. • DCS supports real-time diagnostic integration, adaptable feedback schemes, actuator management and exception handling. • DCS offers workflow management, logging and archiving, self-monitoring and inter-process communication. • DCS is based on a distributed, modular software framework architecture designed for real-time operation. • DCS is composed of re-usable generic but highly customisable components. - Abstract: ASDEX Upgrade is a fusion experiment with a size and complexity to allow extrapolation of technical and physical conditions and requirements to devices like ITER and even beyond. In addressing advanced physics topics it makes extensive use of sophisticated real-time control methods. It comprises real-time diagnostic integration, dynamically adaptable multivariable feedback schemes, actuator management including load distribution schemes and a powerful monitoring and pulse supervision concept based on segment scheduling and exception handling. The Discharge Control System (DCS) supplies all this functionality on base of a modular software framework architecture designed for real-time operation. It provides system-wide services like workflow management, logging and archiving, self-monitoring and inter-process communication on Linux, VxWorks and Solaris operating systems. By default DCS supports distributed computing, and a communication layer allows multi-directional signal transfer and data-driven process synchronisation over shared memory as well as over a number of real-time networks. The entire system is built following the same common design concept combining a rich set of re-usable generic but highly customisable components with a configuration-driven component deployment method. We will give an overview on the architectural concepts as well as on the outstanding capabilities of DCS in the domains of inter

  5. ASDEX Upgrade Discharge Control System—A real-time plasma control framework

    Energy Technology Data Exchange (ETDEWEB)

    Treutterer, W., E-mail: Wolfgang.Treutterer@ipp.mpg.de [Max-Planck-Institut für Plasmaphysik, EURATOM Association, Boltzmannstraße 2, 85748 Garching (Germany); Cole, R.; Lüddecke, K. [Unlimited Computer Systems GmbH, Iffeldorf (Germany); Neu, G.; Rapson, C.; Raupp, G.; Zasche, D.; Zehetbauer, T. [Max-Planck-Institut für Plasmaphysik, EURATOM Association, Boltzmannstraße 2, 85748 Garching (Germany)

    2014-03-15

    Highlights: • The ASDEX Upgrade Discharge Control System (DCS) is a comprehensive control system to conduct fusion experiments. • DCS supports real-time diagnostic integration, adaptable feedback schemes, actuator management and exception handling. • DCS offers workflow management, logging and archiving, self-monitoring and inter-process communication. • DCS is based on a distributed, modular software framework architecture designed for real-time operation. • DCS is composed of re-usable generic but highly customisable components. - Abstract: ASDEX Upgrade is a fusion experiment with a size and complexity to allow extrapolation of technical and physical conditions and requirements to devices like ITER and even beyond. In addressing advanced physics topics it makes extensive use of sophisticated real-time control methods. It comprises real-time diagnostic integration, dynamically adaptable multivariable feedback schemes, actuator management including load distribution schemes and a powerful monitoring and pulse supervision concept based on segment scheduling and exception handling. The Discharge Control System (DCS) supplies all this functionality on base of a modular software framework architecture designed for real-time operation. It provides system-wide services like workflow management, logging and archiving, self-monitoring and inter-process communication on Linux, VxWorks and Solaris operating systems. By default DCS supports distributed computing, and a communication layer allows multi-directional signal transfer and data-driven process synchronisation over shared memory as well as over a number of real-time networks. The entire system is built following the same common design concept combining a rich set of re-usable generic but highly customisable components with a configuration-driven component deployment method. We will give an overview on the architectural concepts as well as on the outstanding capabilities of DCS in the domains of inter

  6. Control of hydrocarbon radicals and film deposition by using an RF Whistler wave discharge

    International Nuclear Information System (INIS)

    Mieno, Tetsu; Shoji, Tatsuo; Kadota, Kiyoshi.

    1991-10-01

    Production of hydrocarbon radicals is controlled by using an RF Whistler wave discharge in a low pressure region (∼0.1 Pa). Plasma density of 10 10 - 10 13 cm -3 , electron temperature of 2-20 eV is obtained for the discharge of admixture of Ar and small content of source gases (CH 4 , C 2 H 2 , CO). Spectroscopic measurement indicates that densities of CH and H radicals and deposition rate of amorphous carbon:H film increase with electron density, electron temperature and source gas pressure. The etching effect of H atoms influences on the deposition rate and a high deposition rate (90 μm/hr for CO/Ar discharge) is obtained even in a low neutral pressure discharge. (author)

  7. International regulatory control of the transport of radioactive materials

    International Nuclear Information System (INIS)

    Swindell, G.E.

    1979-01-01

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

  8. Control of radioactive contamination of food in the country Somogy

    International Nuclear Information System (INIS)

    Varga, E.; Viragh, I.

    1980-01-01

    The radioactive contamination of spinach, sorrel, lettuce, animal bones, milk and fish was determined in the period 1961-1978. Peak values were measured in 1963 and 1976. The contamination of plants reached higher levels, however, it did not exceed 25 pCi per g dry weight. (L.E.)

  9. Radioactive gas solidification apparatus

    International Nuclear Information System (INIS)

    Kobayashi, Yoshihiro; Seki, Eiji; Yabu, Tomohiko; Matsunaga, Hiroyuki.

    1990-01-01

    Handling of a solidification container from the completion for the solidifying processing to the storage of radioactive gases by a remote control equipment such as a manipulator requires a great cost and is difficult to realize. In a radioactive gas solidification device for injection and solidification in accumulated layers of sputtered metals by glow discharge, radiation shieldings are disposed surrounding the entire container, and cooling water is supplied to a cooling vessel formed between the container and the shielding materials. The shielding materials are divided into upper and lower shielding materials, so that solidification container can be taken out from the shielding materials. As a result, the solidification container after the solidification of radioactive gases can be handled with ease. Further, after-heat can be removed effectively from the ion injection electrode upon solidifying treatment upon storage, to attain a radioactive gas solidifying processing apparatus which is safe, economical and highly reliable. (N.H.)

  10. Radioactive Cs-137 discharge from Headwater Forested Catchment in Fukushima after Fukushima Dai-ichi Nuclear Power Plant Accident

    Science.gov (United States)

    Iwagami, S.; Onda, Y.; Tsujimura, M.; Sakakibara, K.; Konuma, R.

    2015-12-01

    Radiocesium migration from headwater forested catchment is important perception as output from the forest which is also input to the subsequent various land use and downstream rivers after Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident. In this study, Cs-137 concentration of dissolved water, suspended sediment and coarse organic matter such as leaf and branch were monitored. Discharge amount of stream water, suspended sediment and coarse organic matter were measured to investigate the discharge amount of radiocesium and composition of radiocesium discharge form through the headwater stream. Observation were conducted at stream site in four headwater catchments in Yamakiya district, located ~35 km north west of FDNPP from June 2011 (suspended sediment and coarse organic matter: August 2012) to December 2014.The Cs-137 concentration of dissolved water was around 1Bq/l at June 2011. Then declined to 0.1 Bq/l at December 2011. And in December 2014, it declined to 0.01 Bq/l order. Declining trend of Cs-137 concentration in dissolved water was expressed in double exponential model. Also temporary increase was observed in dissolved Cs-137 during the rainfall event. The Cs-137 concentration of suspended sediment and coarse organic matter were 170-49000 Bq/kg and 350-14000 Bq/kg respectably. The Cs-137 concentration of suspended sediment showed good correlation with average deposition density of catchment. The effect of decontamination works appeared in declining of Cs-137 concentration in suspended sediment. Contribution rate of Cs-137 discharge by suspended sediment was 96-99% during a year. Total annual Cs-137 discharge from the catchment were 0.02-0.3% of the deposition.

  11. Transforming the ASDEX Upgrade discharge control system to a general-purpose plasma control platform

    International Nuclear Information System (INIS)

    Treutterer, Wolfgang; Cole, Richard; Gräter, Alexander; Lüddecke, Klaus; Neu, Gregor; Rapson, Christopher; Raupp, Gerhard; Zasche, Dieter; Zehetbauer, Thomas

    2015-01-01

    Highlights: • Control framework split in core and custom part. • Core framework deployable in other fusion device environments. • Adaptible through customizable modules, plug-in support and generic interfaces. - Abstract: The ASDEX Upgrade Discharge Control System DCS is a modern and mature product, originally designed to regulate and supervise ASDEX Upgrade Tokamak plasma operation. In its core DCS is based on a generic, versatile real-time software framework with a plugin architecture that allows to easily combine, modify and extend control function modules in order to tailor the system to required features and let it continuously evolve with the progress of an experimental fusion device. Due to these properties other fusion experiments like the WEST project have expressed interest in adopting DCS. For this purpose, essential parts of DCS must be unpinned from the ASDEX Upgrade environment by exposure or introduction of generalised interfaces. Re-organisation of DCS modules allows distinguishing between intrinsic framework core functions and device-specific applications. In particular, DCS must be prepared for deployment in different system environments with their own realisations for user interface, pulse schedule preparation, parameter server, time and event distribution, diagnostic and actuator systems, network communication and data archiving. The article explains the principles of the revised DCS structure, derives the necessary interface definitions and describes major steps to achieve the separation between general-purpose framework and fusion device specific components.

  12. Transforming the ASDEX Upgrade discharge control system to a general-purpose plasma control platform

    Energy Technology Data Exchange (ETDEWEB)

    Treutterer, Wolfgang, E-mail: Wolfgang.Treutterer@ipp.mpg.de [Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching (Germany); Cole, Richard [Unlimited Computer Systems, Seeshaupter Str. 15, 82393 Iffeldorf (Germany); Gräter, Alexander [Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching (Germany); Lüddecke, Klaus [Unlimited Computer Systems, Seeshaupter Str. 15, 82393 Iffeldorf (Germany); Neu, Gregor; Rapson, Christopher; Raupp, Gerhard; Zasche, Dieter; Zehetbauer, Thomas [Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching (Germany)

    2015-10-15

    Highlights: • Control framework split in core and custom part. • Core framework deployable in other fusion device environments. • Adaptible through customizable modules, plug-in support and generic interfaces. - Abstract: The ASDEX Upgrade Discharge Control System DCS is a modern and mature product, originally designed to regulate and supervise ASDEX Upgrade Tokamak plasma operation. In its core DCS is based on a generic, versatile real-time software framework with a plugin architecture that allows to easily combine, modify and extend control function modules in order to tailor the system to required features and let it continuously evolve with the progress of an experimental fusion device. Due to these properties other fusion experiments like the WEST project have expressed interest in adopting DCS. For this purpose, essential parts of DCS must be unpinned from the ASDEX Upgrade environment by exposure or introduction of generalised interfaces. Re-organisation of DCS modules allows distinguishing between intrinsic framework core functions and device-specific applications. In particular, DCS must be prepared for deployment in different system environments with their own realisations for user interface, pulse schedule preparation, parameter server, time and event distribution, diagnostic and actuator systems, network communication and data archiving. The article explains the principles of the revised DCS structure, derives the necessary interface definitions and describes major steps to achieve the separation between general-purpose framework and fusion device specific components.

  13. A Review on Battery Charging and Discharging Control Strategies: Application to Renewable Energy Systems

    Directory of Open Access Journals (Sweden)

    Edison Banguero

    2018-04-01

    Full Text Available Energy storage has become a fundamental component in renewable energy systems, especially those including batteries. However, in charging and discharging processes, some of the parameters are not controlled by the battery’s user. That uncontrolled working leads to aging of the batteries and a reduction of their life cycle. Therefore, it causes an early replacement. Development of control methods seeks battery protection and a longer life expectancy, thus the constant-current–constant-voltage method is mostly used. However, several studies show that charging time can be reduced by using fuzzy logic control or model predictive control. Another benefit is temperature control. This paper reviews the existing control methods used to control charging and discharging processes, focusing on their impacts on battery life. Classical and modern methods are studied together in order to find the best approach to real systems.

  14. Response of lead-acid batteries to chopper-controlled discharge. [for electric vehicles

    Science.gov (United States)

    Cataldo, R. L.

    1978-01-01

    The results of tests on an electric vehicle battery, using a simulated electric vehicle chopper-speed controller, show energy output losses up to 25 percent compared to constant current discharges at the same average current of 100 A. However, an energy output increase of 22 percent is noticed at the 200 A average level and 44 percent increase at the 300 A level using pulse discharging. Because of these complex results, electric vehicle battery/speed controller interactions must be considered in vehicle design.

  15. Theoretical investigation of phase-controlled bias effect in capacitively coupled plasma discharges

    International Nuclear Information System (INIS)

    Kwon, Deuk-Chul; Yoon, Jung-Sik

    2011-01-01

    We theoretically investigated the effect of phase difference between powered electrodes in capacitively coupled plasma (CCP) discharges. Previous experimental result has shown that the plasma potential could be controlled by using a phase-shift controller in CCP discharges. In this work, based on the previously developed radio frequency sheath models, we developed a circuit model to self-consistently determine the bias voltage from the plasma parameters. Results show that the present theoretical model explains the experimental results quite well and there is an optimum value of the phase difference for which the V dc /V pp ratio becomes a minimum.

  16. Significant improvements of electrical discharge machining performance by step-by-step updated adaptive control laws

    Science.gov (United States)

    Zhou, Ming; Wu, Jianyang; Xu, Xiaoyi; Mu, Xin; Dou, Yunping

    2018-02-01

    In order to obtain improved electrical discharge machining (EDM) performance, we have dedicated more than a decade to correcting one essential EDM defect, the weak stability of the machining, by developing adaptive control systems. The instabilities of machining are mainly caused by complicated disturbances in discharging. To counteract the effects from the disturbances on machining, we theoretically developed three control laws from minimum variance (MV) control law to minimum variance and pole placements coupled (MVPPC) control law and then to a two-step-ahead prediction (TP) control law. Based on real-time estimation of EDM process model parameters and measured ratio of arcing pulses which is also called gap state, electrode discharging cycle was directly and adaptively tuned so that a stable machining could be achieved. To this end, we not only theoretically provide three proved control laws for a developed EDM adaptive control system, but also practically proved the TP control law to be the best in dealing with machining instability and machining efficiency though the MVPPC control law provided much better EDM performance than the MV control law. It was also shown that the TP control law also provided a burn free machining.

  17. The control of the radioactive pollution of milk (1962); Comment concevoir une surveillance des pollutions radioactives du lait (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Milk, an essential foodstuff, is the object of a supervision and vigilant controls governed by numerous laws which protect its commercial and sanitary qualities. The development of the use of nuclear energy poses and will pose new problems of hygiene and the milk should benefit from controls concerning its possible contamination. Grass-eating animals are particularly subjected to radioactive contaminations and the milk which they produce does not escape contamination because of of its saline composition and of the particular metabolism of the mammary gland. As a result, milk is a contamination integrator and its analysis makes it possible to detect radioelements which can only be detected with great difficulty in an average size plant sample. (author) [French] Le lait, aliment essentiel, fait l'objet d'une surveillance et de controles vigilants regis par de nombreux textes legislatifs qui protegent ses qualites marchandes et sanitaires. Le developpement de l'utilisation de l'energie nucleaire pose et posera de nouveaux problemes d'hygiene et le lait doit beneficier de controles portant sur sa pollution radioactive eventuelle. Les, animaux herbivores sont particulierement exposes aux contaminations radioactives et les laits qu'ils produisent, du fait de leurs compositions salines et du metabolisme particulier de la glande mammaire, n'echappent point aux pollutions. De ce fait, le lait est un integrateur de contamination et son analyse permet de retrouver des radioelements que l'on ne decele qu'avec beaucoup de difficultes sur un echantillon vegetal de taille moyenne. (auteur)

  18. Border Control of Nuclear and Other Radioactive Materials

    International Nuclear Information System (INIS)

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

    2007-01-01

    In the second half of year 2006, stationary detection systems for nuclear and other radioactive materials were installed on Border Crossing Bregana, Croatia. Yantar 2U, which is the commercial name of the system, is integrated automatic system capable of detection of nuclear and other radioactive materials prepared for fixed-site customs applications (Russian origin). Installed system contains portal monitors, camera, communication lines and communication boxes and server. Two fully functional separate systems has been installed on BC Bregana, one on truck entrance and another one on car entrance. In this article the operational experience of installed system is presented. This includes statistical analysis of recorded alarms, evaluation of procedures for operational stuff and maintenance and typical malfunction experience, as well as some of the recommendation for future use of detection systems.(author)

  19. 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.)

  20. Supported Discharge Teams for older people in hospital acute care: a randomised controlled trial.

    Science.gov (United States)

    Parsons, Matthew; Parsons, John; Rouse, Paul; Pillai, Avinesh; Mathieson, Sean; Parsons, Rochelle; Smith, Christine; Kenealy, Tim

    2018-03-01

    Supported Discharge Teams aim to help with the transition from hospital to home, whilst reducing hospital length-of-stay. Despite their obvious attraction, the evidence remains mixed, ranging from strong support for disease-specific interventions to less favourable results for generic services. To determine whether older people referred to a Supported Discharge Team have: (i) reduced length-of-stay in hospital; (ii) reduced risk of hospital readmission; and (iii) reduced healthcare costs. Randomised controlled trial with follow-up to 6 months; 103 older women and 80 men (n = 183) (mean age 79), in hospital, were randomised to receive either Supported Discharge Team or usual care. Home-based rehabilitation was delivered by trained Health Care Assistants up to four times a day, 7 days a week, under the guidance of registered nurses, allied health and geriatricians for up to 6 weeks. Participants randomised to the Supported Discharge Team spent less time in hospital during the index admission (mean 15.7 days) in comparison to usual care (mean 21.6 days) (mean difference 5.9: 95% CI 0.6, 11.3 days: P = 0.03) and spent less time in hospital in the 6 months following discharge home. Supported discharge group costs were calculated at mean NZ$10,836 (SD NZ$12,087) compared to NZ$16,943 (SD NZ$22,303) in usual care. A Supported Discharge Team can provide an effective means of discharging older people home early from hospital and can make a cost-effective contribution to managing increasing demand for hospital beds. © The Author 2017. Published by Oxford University Press on behalf of the British Geriatrics Society.All rights reserved. For permissions, please email: journals.permissions@oup.com

  1. Sealed Radioactive Sources. Information, Resources, and Advice for Key Groups about Preventing the Loss of Control over Sealed Radioactive Sources

    International Nuclear Information System (INIS)

    2013-10-01

    Among its many activities to improve the safety and security of sealed sources, the IAEA has been investigating the root causes of major accidents and incidents since the 1980's and publishes findings so that others can learn from them. There are growing concerns today about the possibility that an improperly stored source could be stolen and used for malicious purposes. To improve both safety and security, information needs to be in the hands of those whose actions and decisions can prevent a source from being lost or stolen in the first place. The IAEA developed this booklet to help improve communication with key groups about hazards that may result from the loss of control over sealed radioactive sources and measures that should be implemented to prevent such loss of control. Many people may benefit from the information contained in this booklet, particularly those working with sources and those likely to be involved if control over a source is lost; especially: officials in government agencies, first responders, medical users, industrial users and the metal recycling industry. The general public may also benefit from an understanding of the fundamentals of radiation safety. This booklet is comprised of several stand-alone chapters intended to communicate with these key groups. Various accidents that are described and information that is provided are relevant to more than one key group and therefore, some information is repeated throughout the booklet. This booklet seeks to raise awareness of the importance of the safety and security of sealed radioactive sources. However, it is not intended to be a comprehensive 'how to' guide for implementing safety and security measures for sealed radioactive sources. For more information on these measures, readers are encouraged to consult the key IAEA safety and security-related publications identified in this booklet

  2. Control of radioactive contamination and radiation exposure in the environment - tasks, techniques, implementation

    International Nuclear Information System (INIS)

    Bayer, A.

    1997-01-01

    A brief historical abstract of the steps in the discovery of natural radioactivity and development of man-made radioactivity is presented, as well as the historical development of the control of radioactivity in the environment. The goals of control measures and the tasks, classified by the possible sources of release, are demonstrated and the required methods described (measuring methods, evaluation methods, and information techniques). The control measures, based on different legal principles, are introduced and their technological implementation, including their current status, described. Finally, an account is given of the progressive harmonisation of the national control systems, as well as of the integration of these control systems into international control and information networks. (orig.) [de

  3. Strengthening control over radioactive sources in authorized use and regaining control over orphan sources. National strategies

    International Nuclear Information System (INIS)

    2004-02-01

    The objective of this report is to provide practical guidance to States on the development of a national strategy for improving control over radioactive sources, particularly dangerous sources (Categories 1-3). Part of this process involves the determination of the magnitude of the potential problem with orphan and vulnerable sources and indeed, whether or not a national strategy is needed. The ultimate objective is that States will use this report to develop and then implement a plan of action that will result in all significant sources being managed in a safe and secure manner. This report attempts to provide both the background knowledge and the methodology necessary for an individual or small team of responsible persons to develop a national strategy for improving control over all radioactive sources, but especially orphan and vulnerable sources. The background knowledge given in Chapter 3 is an update of the information on practices that was given in IAEA-TECDOC-804, which focused on spent radioactive sources. After some introductory material, this report provides both the factual information and the general steps needed to develop and implement a national strategy. Part I contains background information for those who are not already familiar with the subject including the need for national strategies, the generic causes of loss of control of sources, with specific examples and the common applications of radioactive sources. Part II details the actual process for the development and implementation of a national strategy, which includes assessing the problem by first gathering specific and national information, determining the nature and magnitude of the problem, developing the national strategy by evaluating, and prioritizing possible solutions, implementing the strategy subsequent to a high level decision; and evaluating the effectiveness of the plan and making changes as a result until the desired objective is achieved. Searches for sources will be part of

  4. Quality control of concretes for conditioning of spent radioactive sources

    International Nuclear Information System (INIS)

    Gonzalez N, M.

    2015-01-01

    The spent sealed radioactive sources are considered as a specific type of radioactive wastes and should be properly stored to ensure their integrity and prevent or limit the release of radionuclides in the geosphere. For this, these sources can be put up in concrete matrices. This research presents the evaluation and characterization of five concretes prepared with 4 brands of commercial cements: CPC Extra RS, CPC 30R Impercem of Cemex, Cruz Azul CPC 30R and CPC 30R of Apasco; three sizes of coarse aggregate (<30 mm, 29-11 mm and <10 mm) and fine aggregate (0.0797 mm) used as matrices for conditioning of spent sealed radioactive sources, in order to verify if these specific concretes accredit the standard NOM-019-Nucl-1995. After hardening for 28 days the concrete specimens were subjected to the tests: compressive strength; thermal cycles, irradiation, leaching and permeability, later to be characterized by: 1) X-ray diffraction in order to meet their crystalline phases; 2) scanning electron microscopy, to determine changes in morphology; 3) infrared spectroscopy, to determine the structural changes of concrete from its functional groups; 4) Raman spectroscopy to determine their structural changes and 5) Moessbauer spectroscopy, which determines changes in the oxidation state of iron in the concrete. According to the results and the changes presented by each concrete after applying the tests set by NOM-019-Nucl-1995, is concluded that the concrete made with cement Cemex brand (CPC 30-RS Extra), gravel of particle size 11-29 mm and sieved sand (0.0797 mm) can be used as matrices of spent sealed sources conditioning. Is remarkable a morphological and structural change of the concrete due to gamma irradiation and heat treatment. (Author)

  5. A computer program for controlling a university radioactive material inventory: From confusion to computer to control

    International Nuclear Information System (INIS)

    Robb, D.B.; Riches, C.G.; O'Brian, M.J.; Riordan, F.J.

    1984-01-01

    The University of Washington is a large user of radioactive material. Over 250 authorized programs are working in over 600 labs with nearly 3500 orders of radioactive material per year. The state license sets limits on the total amount of material on campus. There are also limits on sewer disposal. To meet these needs it is necessary to know the amount of material on campus at any time. A computer program was developed which covered many aspects of the radiation safety record needs including inventory control. Inventory is now managed by tracking each order from purchase to disposal. A screen menu as part of the interactive program allows immediate and detailed information about the inventory at time of purchase approval and delivery. Because of this system our knowledge and control of radionuclide work on campus has increased dramatically. A description of how this system is used during ordering, delivery and disposal will be given. Details on the methods to check limits are included along with a summary of the reports made possible by the current data files

  6. Regulatory control of radiation sources and radioactive materials in Ireland

    International Nuclear Information System (INIS)

    McGarry, A.T.; Fenton, D.; O'Flaherty, T.

    2001-01-01

    The primary legislation governing safety in uses of ionizing radiation in Ireland is the Radiological Protection Act, 1991. This Act provided for the establishment in 1992 of the Radiological Protection Institute of Ireland, and gives the Institute the functions and powers which enable it to be the regulatory body for all matters relating to ionizing radiation. A Ministerial Order made under the Act in 2000 consolidates previous regulations and, in particular, provides for the implementation in Irish law of the 1996 European Union Directive which lays down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionizing radiation. Under the legislation, the custody, use and a number of other activities involving radioactive substances and irradiating apparatus require a licence issued by the Institute. Currently some 1260 licences are in force. Of these, some 850 are in respect of irradiating apparatus only and are issued principally to dentists and veterinary surgeons. The remaining licences involve sealed radiation sources and/or unsealed radioactive substances used in medicine, industry or education. A schedule attached to each licence fully lists the sealed sources to which the licence applies, and also the quantities of radioactive substances which may be acquired or held under the licence. It is an offence to dispose of, or otherwise relinquish possession of, any licensable material other than in accordance with terms and conditions of the licence. Disused sources are returned to the original supplier or, where this is not possible, stored under licence by the licensee who used them. Enforcement of the licensing provisions relies primarily on the programme of inspection of licensees, carried out by the Institute's inspectors. The Institute's Regulatory Service has a complement of four inspectors, one of whom is the Manager of the Service. The Manager reports to one of the Institute's Principal

  7. Control of radioactive waste disposal into the marine environment

    International Nuclear Information System (INIS)

    1983-01-01

    The body of this publication is intended to provide adequate information on the broad aspects of radioactive waste disposal into the sea. The introduction of radionuclides into the sea from uncontrollable sources, such as weapons test explosions, is outside the scope of this publication, as are releases of radionuclides from nuclear-powered vessels. It should be stressed that agreements on practices for the marine disposal of wastes are being developed and the understanding of oceanographic processes is rapidly progressing; therefore, the conclusions presented here should always be considered in the context of changes in both knowledge and practice that occur subsequent to the completion of this text

  8. Environmental effects of thermal and radioactive discharges from nuclear power plants in the boreal brackish-water conditions of the northern Baltic Sea

    International Nuclear Information System (INIS)

    Ilus, E.

    2009-08-01

    During recent decades, thermal and radioactive discharges from nuclear power plants into the aquatic environment have become the subject of lively debate as an ecological concern. Recently, an increasing demand for facts has appeared in context with the Environmental Impact Assessment procedures that are being in progress for planned new nuclear power units in Finland. The target of this thesis was to summarize the large quantity of results obtained in extensive monitoring programmes and studies carried out in recipient sea areas off the Finnish nuclear power plants at Loviisa and Olkiluoto during more than four decades. Especially in the conditions specific for the northern Baltic Sea, where biota is poor and adapted to relatively low temperatures and to seasonal variation with a cold ice winter and a temperate summer, an increase in temperature may cause increased environmental stress to the organisms. Furthermore, owing to the brackish-water character of the Baltic Sea, many organisms live there near the limit of their physiological tolerance. On the other hand, the low salinity increases the uptake of certain radionuclides by many organisms in comparison with oceanic conditions. The sea areas surrounding the Finnish nuclear power plants differ from each other in many respects (efficiency of water exchange, levels of nutrients and other water quality parameters, water salinity and consequent differences in species composition, abundance and vitality of biota). In addition, there are differences in the discharge quantities and discharge design of the power plants. In this thesis the environmental effects of the two power plants on the water recipients are compared and their relative significance is assessed

  9. Plasma actuators for active flow control based on a glow discharge

    International Nuclear Information System (INIS)

    Kühn, M.; Kühn-Kauffeldt, M.; Schein, J.; Belinger, A.

    2017-01-01

    In this work a glow discharge based active flow control for high flow velocities and low Reynolds numbers is presented. Unlike common plasma actuators such as dielectric barrier discharge (DBD) or spark jets, this actuator uses small impulse bits at frequencies. The actuator is optimized for frequencies up to 40 kHz to counter Tollmien Schlichting wave effects and so reduce overall air foil drag. Several measurements to prove the non-eroding effect of the actuator and the electrical properties were performed. It was found that the actuator is capable of operating at high frequencies without measurable erosion. (paper)

  10. Radiological effect of caesium-137 and strontium-90 on aquatic system of the pathway of the discharged liquid radioactive waste

    International Nuclear Information System (INIS)

    Sinakhom, F.; Pothipin, K.; Supaokit, P.

    1984-12-01

    The objective of this paper is to study the radiological effect from the release of treated liquid radioactive waste to the fresh water environment in order to the protection of human health. The emphasis in this program was concentrated on Sr-90 and Cs-137 analyses on Sr-90 and Cs-137 analyses in surface water, water-plants and fish collected during August 1980 to July 1981. Sr-90 concentration was separated by solvent extraction (TBP-tributyl phosphate) procedure. Beta radioactivity of the two nuclides were measured in the form of yttrium oxalate (Y-90, the daughter nuclide of Sr-90) and caesium phospho-molybdate using a low-background anticoincidence proportional counter. To interpret the result obtained, the analytical data were converted to percent derived working limits (%DWL) using Derived Working Limit acquired from the value of (MPC) and water consumption rate stipulated by ICRP as 100% DWL. The value of %DWL is a useful and convenient index to judge the hazardous from radiation exposed by a certain group of people. The interpretation of the result revealed the equivalence of %DWL of Sr-90 and Cs-137 in canal-fish and swamp cabbage for people resided nearby the canal who obtained their whole protein from consumption of that fish from canal and vegetation grown in that water. The value above was equal 2.5 percent which means that this critical group of people exposed to the radiation only 2.5 percent of that intake limit recommended by ICRP. Thus, the amounts of waste disposed of from waste treatment plant into the canal were too small to have a radiological effect on the environment

  11. Particle control in DIII-D with helium glow discharge conditioning

    International Nuclear Information System (INIS)

    Jackson, G.L.; Taylor, T.S.; Taylor, P.L.

    1990-01-01

    Helium glow discharge conditioning of DIII-D is routinely used before every tokamak discharge to desorb hydrogen from the graphite tiles, which are the plasma facing surfaces for the floor, inner wall and top of the vessel. In addition to reducing hydrogen fuelling of the plasma by the graphite surfaces, helium glow discharges are also effective in removing low-Z impurities, primarily in the form of carbon monoxide and hydrocarbons, and this has permitted higher current divertor operation and more rapid recovery from tokamak disruptions. Since the implementation of repetitive helium glow wall conditioning, the parameter space in which tokamak discharges in DIII-D can be obtained has been expanded to include the first observations of limiter H-mode confinement, the Ohmic H-mode with periods of up to 150 ms that are free of edge localized modes, more reliable low q operation with volume averaged beta of up to 9.3%, improved control over locked modes and plasma discharges at lower electron density. (author). 37 refs, 12 figs, 1 tab

  12. Numerical Simulation of a Nanosecond-Pulse Discharge for High-Speed Flow Control

    Science.gov (United States)

    Poggie, Jonathan; Adamovich, Igor

    2012-10-01

    Numerical calculations were carried out to examine the physics of the operation of a nanosecond-pulse, single dielectric barrier discharge in a configuration with planar symmetry. This simplified configuration was chosen as a vehicle to develop a physics based nanosecond discharge model, including realistic air plasma chemistry and compressible bulk gas flow. First, a reduced plasma kinetic model was developed by carrying out a sensitivity analysis of zero-dimensional plasma computations with an extended chemical kinetic model. Transient, one- dimensional discharge computations were then carried out using the reduced kinetic model, incorporating a drift-diffusion formulation for each species, a self-consistent computation of the electric potential using the Poisson equation, and a mass-averaged gas dynamic formulation for the bulk gas motion. Discharge parameters (temperature, pressure, and input waveform) were selected to be representative of recent experiments on bow shock control with a nanosecond discharge in a Mach 5 cylinder flow. The computational results qualitatively reproduce many of the features observed in the experiments, including the rapid thermalization of the input electrical energy and the consequent formation of a weak shock wave. At breakdown, input electrical energy is rapidly transformed (over roughly 1 ns) into ionization products, dissociation products, and electronically excited particles, with subsequent thermalization over a relatively longer time-scale (roughly 10 μs).

  13. A New Servo Control Drive for Electro Discharge Texturing System Industrial Applications Using Ultrasonic Technology

    Directory of Open Access Journals (Sweden)

    M. Shafik

    2013-07-01

    Full Text Available This paper presents a new ultrasonic servo control drive for electro discharge texturing system industrial applications. The new drive is aiming to overcome the current teething issues of the existing electro discharge texturing system, servo control drive level of precision, processing stability, dynamic response and surface profile of the machined products. The new ultrasonic servo control drive consists of three main apparatuses, an ultrasonic motor, electronic driver and control unit. The ultrasonic motor consists of three main parts, the stator, rotor and sliding element. The motor design process, basic configuration, principles of motion, finite element analysis and experimental examination of the main characteristics is discussed in this paper. The electronic driver of the motor consists of two main stages which are the booster and piezoelectric amplifier. The experimental test and validation of the developed servo control drive in electro discharge texturing platform is also discussed and presented in this paper. The initial results showed that the ultrasonic servo control drive is able to provide: a bidirectional of motion, a resolution of <50μm and a dynamic response of <10msec. The electron microscopic micro examination into the textured samples showed that: a clear improvement in machining stability, products surface profile, a notable reduction in the processing time, arcing and short-circuiting teething phenomena.

  14. Control of the surface radioactive contamination in the field of biological research

    International Nuclear Information System (INIS)

    Calvo, S.; Encina, A. de la; Gaspar, J.; Macias, M. T.; Sanchez, A.; Usera, F.

    2012-01-01

    The manipulation of unsealed sources in biomedical research involves significant risk of radioactive contamination. the aim of this study has been to analyze the radioactive contamination occurring in the field of biomedical research, assessing its magnitude, identifying the equipment that can be contaminated with higher probability and monitoring the evolution of the contaminations production taking into account the radioisotopes and the activities uses, and the radiation protection control applied. The data used for this study correspond to a very lengthy period of time and it have been collected in the radioactive facility, of the Centro Nacional de Biotecnologia (CSIC), a very large biological research centre that can be used perfectly as a reference for this area. The results obtained show a gradual and significant decrease in the incidence of the radioactive contamination. This is due to the optimization of radiation protection standards applied and the implementation or a systematic operational radiation protection program. (Author) 13 refs.

  15. Controlling radioactive sources. Stronger 'cradle-to-grave' security needed, IAEA says

    International Nuclear Information System (INIS)

    2002-01-01

    This article highlights the IAEA activities in the field of radiation safety and security of radiation sources and other radioactive materials in its Member States. The IAEA has been active in lending its expertise to search out and secure orphaned sources in several countries. Additionally more than 70 States have joined with the IAEA to collect and share information on trafficking incidents and other unauthorized movements of radioactive sources and other radioactive materials. In March 2002 the IAEA Board of Governors approved a multi-faceted Action plan to Combat Nuclear Terrorism that includes upgrading radiation safety and security. One programme is designed to ensure that significant, uncontrolled radioactive sources are brought under regulatory control and properly secured by providing assistance to Member States in their efforts to identify, locate and secure or dispose of orphan sources

  16. The fate of radioactivity in sewers

    International Nuclear Information System (INIS)

    2000-01-01

    The Environment Agencies authorise and monitor the disposal of low-level radioactive waste to sewers. Such discharges originate from non-nuclear sites such as hospitals, universities and research centres. Discharges are strictly controlled through authorisations, which place conditions and limits on the disposer. We commissioned the work summarised within this, leaflet to reassess the fate of these radioactive discharges and to ensure that this practice remains acceptable and is still the best option for disposal. In all cases the study found assessed radiation doses (associated with these discharges) to be a small fraction of the public dose limit. The Environment Agencies conclude from this study that the disposal of radioactive waste to sewers remains the best option available to ensure the safety of the public (including sewer workers) and to protect the environment

  17. Regulatory control and management of radioactive materials in the Philippines

    International Nuclear Information System (INIS)

    Borras, A.M.; Parami, V.K.; Domondon, D.B.

    2001-01-01

    The Philippine Nuclear Research Institute (PNRI) by virtue of Republic Act 2067, as amended, Republic Act 5207 and Executive Order 128 (1987), was mandated to promote, advance and regulate the safe and peaceful applications of nuclear science and technology in the Philippines. The PNRI was formerly the Philippine Atomic Energy Commission, established in 1958. This report aims to share the information and experience of PNRI as a regulatory authority on the administrative, technical and managerial aspects to ensure the safety and security of radioactive material in the country. It describes the country's regulatory framework, operational experiences, international co-operation including reporting system and database, and radiological safety assessment and compliance monitoring. It also briefly discusses the current development of the country's radiological emergency response plan and the radiation protection services offered by the PNRI. In the discussion and recommendations, some of the results of the regulatory information conferences conducted with the end-users are enumerated. (author)

  18. Coordinated Secondary Control for Balanced Discharge Rate of Energy Storage System in Islanded AC Microgrids

    DEFF Research Database (Denmark)

    Guan, Yajuan; Quintero, Juan Carlos Vasquez; Guerrero, Josep M.

    2016-01-01

    A coordinated secondary control approach based on an autonomous current-sharing control strategy for balancing the discharge rates of energy storage systems (ESSs) in islanded AC microgrids is proposed in this paper. The coordinated secondary controller can regulate the power outputs of distributed...... incidents and unintentional outages in DG units, but also aims to provide a fast transient response and an accurate output-current-sharing performance. A complete root locus analysis is given in order to achieve system stability and parameter sensitivity. Experimental results are presented to show...... the performance of the whole system and to verify the effectiveness of the proposed controller....

  19. design of a decoupler controller for forced circulation evaporator used in a radioactive treatment plant

    International Nuclear Information System (INIS)

    Abdel-Halim, H.A.

    2005-01-01

    evaporation is a proven method for a treatment of liquid radioactive wastes providing both good decontamination and high concentration . in a radioactive waste treatment plant, an evaporator is used to reduce the volume of medium radioactive liquid waste arising from different applications of nuclear industries. the control system objective is to limit the composition of the liquid waste at a prescribed value. for the safe operation, without damaging the installed equipment, a good control for the evaporator operating pressure and the level of liquid waste inside the separator part has been required. evaporator equipment is a complex process, which is a multivariable, nonlinear and has many disturbances. therefore, design a control strategy for the evaporator is bit difficult. the solution method is based on system decoupling eliminating the parasite interactions between input-output pairing variables and converting multi-inputs multi-outputs (MIMO) system to several single-inputs single-outputs (SISO) systems

  20. Radiation protection at the RA Reactor in 1985, Part -2, Annex 2b, Environmental Radioactivity control, Control of air contamination

    International Nuclear Information System (INIS)

    Patic, D.; Smiljanic, R.; Zaric, M.; Savic, Z.; Ristic, D.

    1985-01-01

    During the period from November 1984 - November 1985, within the radioactivity control on the Vinca Institute site air contamination radioactive aerosol contents was measured. Control was done on 4 measuring stations, two in the Institute and two locations in the direction of wind i.e. Belgrade, 2 km and 7 km away from the Institute respectively. This position of the measuring locations enables control of radiation safety of the Institute, as well as environment of Belgrade taking into account the existence of the reactor and other possible contaminants in the Institute [sr

  1. 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

  2. A study of direct-current surface discharge plasma for a Mach 3 supersonic flow control

    Science.gov (United States)

    Shin, Jichul

    A direct-current, non-equilibrium surface glow discharge plasma in the presence of a Mach 2.85 flow is studied experimentally for flow control applications. The discharge is generated with pin-like electrodes flush mounted on a ceramic plate with sustaining currents from 25 mA to 300 mA. In the presence of a supersonic flow, two distinct discharge modes - diffuse and constricted - are observed depending on the flow and discharge operating conditions. In cathode upstream location, both diffuse and constricted discharges are observed while in cathode downstream location, the discharge mostly exhibits either constricted mode or bistable mixed mode. The effect of the discharge on the flow ("plasma actuation'') is characterized by the appearance of a weak shock wave in the vicinity of the discharge. The shock is observed at low powers (˜10 W) for the diffuse discharge mode but is absent for the higher power (˜100 W) constricted mode. High speed laser schlieren imaging suggests that the diffuse mode plasma actuation is rapid as it occurs on a time scale that is less than 100 microsec. Rotational (gas) and vibrational temperatures within the discharge are estimated by emission spectral line fits of N 2 and N+2 rovibronic bands near 365-395 nm. The electronic temperatures are estimated by using the Boltzmann plot method for Fe(I) atomic lines. Rotational temperatures are found to be high (˜1500 K) in the absence of a flow but drop sharply (˜500 K) in the presence of a supersonic flow for both the diffuse and constricted discharge modes. The vibrational and electronic temperatures are measured to be about 3000 K and 1.25 eV (14500 K), respectively, and these temperatures are the same with and without flow. The gas (rotational) temperature spatial profiles above the cathode surface are found to be similar for the diffuse and constricted modes indicating that dilatational effects due to gas heating are similar. However, complete absence of flow actuation for the

  3. Study of the 60Co speciation in the aqueous radioactive waste of the la Hague nuclear reprocessing plant; environmental behaviour after discharges in the waters of the channel

    International Nuclear Information System (INIS)

    Gaudaire, J.M.

    1999-01-01

    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 μm) at the Goury site are close to or even below, the detection limit: 0.2 mBq.l -1 . The 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 μm), and then in the form of two soluble species: ionic divalent (Co 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 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 2+ and Ca 2+ ) go through a precipitation. This comes with the coprecipitation of the ion Co 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-conservative radionuclide). This sedimentary stock can

  4. Neuro-PID tracking control of a discharge air temperature system

    International Nuclear Information System (INIS)

    Zaheer-uddin, M.; Tudoroiu, N.

    2004-01-01

    In this paper, the problem of improving the performance of a discharge air temperature (DAT) system using a PID controller and augmenting it with neural network based tuning and tracking functions is explored. The DAT system is modeled as a SISO (single input single output) system. The architecture of the real time neuro-PID controller and simulation results obtained under realistic operating conditions are presented. The neural network assisted PID tuning method is simple to implement. Results show that the network assisted PID controller is able to track both constant and variable set point trajectories efficiently in the presence of disturbances acting on the DAT system

  5. The prediction of discharge from in-patient psychiatric rehabilitation: a case-control study

    Directory of Open Access Journals (Sweden)

    Mountain Debbie A

    2011-09-01

    Full Text Available Abstract Background At any time, about 1% of people with severe and enduring mental illness such as schizophrenia require in-patient psychiatric rehabilitation. In-patient rehabilitation enables individuals with the most challenging difficulties to be discharged to successful and stable community living. However, the length of rehabilitation admission that is required is highly variable and the reasons for this are poorly understood. There are very few case-control studies of predictors of outcome following hospitalisation. None have been carried out for in-patient rehabilitation. We aimed to identify the factors that are associated with achieving discharge from in-patient rehabilitation by carrying out a case-control study. Methods We compared two groups: 34 people who were admitted to the Rehabilitation Service at the Royal Edinburgh Hospital and discharged within a six year study period, and 31 people who were admitted in the same period, but not discharged. We compared the groups on demographic, illness, treatment and risk variables that were present at the point of their admission to rehabilitation. We used independent t tests and Pearson Chi-Square tests to compare the two groups. Results We found that serious self harm and suicide attempts, treatment with high dose antipsychotics, antipsychotic polypharmacy and previous care in forensic psychiatric services were all significantly associated with non-discharge. The non-discharged group were admitted significantly later in the six year study period and had already spent significantly longer in hospital. People who were admitted to rehabilitation within the first ten years of developing psychosis were more likely to have achieved discharge. Conclusions People admitted later in the study period required longer rehabilitation admissions and had higher rates of serious self harm and treatment resistant illness. They were also more likely to have had previous contact with forensic services. This

  6. Control of chemical usage in drilling fluid formulations to minimize discharge to the environment

    International Nuclear Information System (INIS)

    Geehan, T.; Forbes, D.M.; Moore, D.J.

    1991-01-01

    A reduction in the environmental footprint from drilling operations can best be addressed by minimizing the sources of that footprint. One of the principal sources of possible environmental damage is drilling fluid and drill solid discharge. The toxicity as measured by acute and/or sub-chronic testing regimes depends on the composition of the drilling fluid/drill solids slurry. The trend within the drilling fluids industry has been to direct its attention to finding drilling fluid products which alone and in combination are considered to be non-toxic as determined by required testing procedures. This paper goes on to describe a parallel approach in which the total volume of chemicals discharged (whether considered toxic or benign) is reduced. Both approaches can be considered complimentary. The reduction in volume/mass of discharge is achieved by increased monitoring of both drilling fluid properties, composition and solids control operational efficiency. Additionally the increased monitoring allows less complicated formulations to be used to produce the desired drilling fluid properties; as specified by the mud programme. The need for more complete rigsite monitoring packages, will become more important as oilbased muds are replaced by waterbased mud for difficult drilling situations with stricter environmental regulations on discharge of drilling waste. The paper also outlines how the optimization of the drilling fluid operation was linked to a reduction in drilling fluid costs at the same time maintaining drilling efficiency

  7. Analysis and development of numerical methodologies for simulation of flow control with dielectric barrier discharge actuators

    OpenAIRE

    Abdollahzadehsangroudi, Mohammadmahdi

    2014-01-01

    The aim of this thesis is to investigate and develop different numerical methodologies for modeling the Dielectric Barrier discharge (DBD) plasma actuators for flow control purposes. Two different modeling approaches were considered; one based on Plasma-fluid model and the other based on a phenomenological model. A three component Plasma fluid model based on the transport equations of charged particles was implemented in this thesis in OpenFOAM, using several techniques to redu...

  8. Coordinated Secondary Control for Balanced Discharge Rate of Energy Storage System in Islanded Microgrids

    DEFF Research Database (Denmark)

    Guan, Yajuan; Guerrero, Josep M.; Quintero, Juan Carlos Vasquez

    2015-01-01

    current and unintentional outage of DGs. Thus, the stability and reliability of islanded MG can be improved. The eigenvalues and root locus with the proposed controller are presented to design the parameters as well as analyzing the system stability. Simulation results based on Matlab......A coordinated secondary control based on a novel autonomous currents sharing control strategy for balanced discharge rate of energy storage systems in islanded microgrid (MG) is proposed in this paper. The coordinated secondary controller is able to regulate the output power of distributed...... generating (DG) systems according to their state-of-charge by adjusting the virtual resistances of their voltage controlled inverters. This controller can not only provide the faster response and accurate output current sharing control, but also avoid the potential operation failure resulting from the over...

  9. Storage of low-level radioactive waste and regulatory control of sealed sources in Finland

    International Nuclear Information System (INIS)

    Rahola, T.; Markkanen, M.

    2006-01-01

    This paper is concentrated on the non nuclear low-level radioactive waste. The cornerstone for maintaining radioactive sources under control in Finland is that all practices involving sources are subject to authorization and all licensing information, including information on each individual source, are entered into a register which is continuously updated based on applications and notifications received from the licenses. Experiences during the past twenty years have shown that source-specific records of sources combined with regular inspections at the places of use have prevented efficiency losing control over sealed radioactive sources. The current capacity in the interim storage for State owned waste is not adequate for all used sealed sources and other small user waste which are currently kept in the possession of the licensees. Thus, expansion of the storage capacity and other options for taking care of the small user waste is under consideration. (N.C.)

  10. Computer-based supervisory control and data acquisition system for the radioactive waste evaporator

    International Nuclear Information System (INIS)

    Pope, N.G.; Schreiber, S.B.; Yarbro, S.L.; Gomez, B.G.; Nekimken, H.L.; Sanchez, D.E.; Bibeau, R.A.; Macdonald, J.M.

    1994-12-01

    The evaporator process at TA-55 reduces the amount of transuranic liquid radioactive waste by separating radioactive salts from relatively low-level radioactive nitric acid solution. A computer-based supervisory control and data acquisition (SCADA) system has been installed on the process that allows the operators to easily interface with process equipment. Individual single-loop controllers in the SCADA system allow more precise process operation with less human intervention. With this system, process data can be archieved in computer files for later analysis. Data are distributed throughout the TA-55 site through a local area network so that real-time process conditions can be monitored at multiple locations. The entire system has been built using commercially available hardware and software components

  11. The use of ligneous plants for controlling the radioactive contamination of a soil; Utilisation des vegetaux ligneux au controle de la pollution radioactive d'un sol

    Energy Technology Data Exchange (ETDEWEB)

    Gagnaire, J; Heuze, C; Aubert, M T [Commissariat a l' Energie Atomique, Grenoble (France).Centre d' Etudes Nucleaires

    1961-07-01

    A method for checking on the possible radioactive pollution of CEN-G. soil, by taking samples of tissue of ligneous plants cultivated on the land in question, is proposed and investigated during the vegetation period. A preliminary study on the retention capacity of the CEN-G. soil for solutions containing {sup 32}P and chemical composition is given. (author) [French] Une methode de controle de la pollution radioactive eventuelle du sol du CEN-G., a l'aide de prelevements de tissus de vegetaux ligneux, cultives sur ce terrain est proposee et etudiee pendant la periode vegetative. Une etude preliminaire du pouvoir de retention du sol du CEN-G, vis-a-vis de solutions contenant du {sup 32}P et de composition chimique, est exposee. (auteur)

  12. Improving discharge care: the potential of a new organisational intervention to improve discharge after hospitalisation for acute stroke, a controlled before-after pilot study.

    Science.gov (United States)

    Cadilhac, Dominique A; Andrew, Nadine E; Stroil Salama, Enna; Hill, Kelvin; Middleton, Sandy; Horton, Eleanor; Meade, Ian; Kuhle, Sarah; Nelson, Mark R; Grimley, Rohan

    2017-08-04

    Provision of a discharge care plan and prevention therapies is often suboptimal. Our objective was to design and pilot test an interdisciplinary, organisational intervention to improve discharge care using stroke as the case study using a mixed-methods, controlled before-after observational study design. Acute care public hospitals in Queensland, Australia (n=15). The 15 hospitals were ranked against a benchmark based on a composite outcome of three discharge care processes. Clinicians from a 'top-ranked' hospital participated in a focus group to elicit their success factors. Two pilot hospitals then participated in the organisational intervention that was designed with experts and consumers. Hospital clinicians involved in discharge care for stroke and patients admitted with acute stroke or transient ischaemic attack. A four-stage, multifaceted organisational intervention that included data reviews, education and facilitated action planning. Three discharge processes collected in Queensland hospitals within the Australian Stroke Clinical Registry were used to select study hospitals: (1) discharge care plan; (2) antihypertensive medication prescription and (3) antiplatelet medication prescription (ischaemic events only). Primary measure: composite outcome. Secondary measures: individual adherence changes for each discharge process; sensitivity analyses. The performance outcomes were compared 3 months before the intervention (preintervention), 3 months postintervention and at 12 months (sustainability). Data from 1289 episodes of care from the two pilot hospitals were analysed. Improvements from preintervention adherence were: antiplatelet therapy (88%vs96%, p=0.02); antihypertensive prescription (61%vs79%, porganisational intervention. The intervention warrants further application and trialling on a larger scale. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2017. All rights reserved. No commercial use is

  13. 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

  14. Exemption from Regulatory Control of Goods Containing Small Amounts of Radioactive Material

    International Nuclear Information System (INIS)

    2012-01-01

    Small amounts of radioactive material may be added to various goods for functional reasons. Several such items are currently available for either professional or personal use. These include ionization chamber smoke detectors, thoriated-tungsten welding rods, luminous dials, electrical devices and electric discharge lamps. Some of these goods may be intended for particular types of market such as cinemas or other places to which the public may have access, but they are unlikely to be provided directly to members of the public. Other goods may be intended for wide scale use and therefore readily available on the market as consumer products through commercial outlets where personal and household products are normally purchased. Members of the public may be exposed to ionizing radiation as a consequence of activities such as transport, storage, use and disposal of such goods. The IAEA safety standards provide the basic requirements for regulatory control of such goods. The most relevant documents are the Governmental, Legal and Regulatory Framework for Safety and the International Basic Safety Standards (hereafter referred to as the BSS). These requirements include notification of a practice to the regulatory body and authorization of the practice by the regulatory body. Provision is made for the exemption of practices from these and other regulatory requirements based on general criteria given in the BSS or any exemption levels specified by the regulatory body on the basis of these criteria. The BSS, which are jointly sponsored by the IAEA and several other international organizations, apply to all facilities and all activities for peaceful purposes that give rise to exposure to radiation. In the interest of harmonization of approaches among Member States, some guidance on the application of the criteria for exemption has been provided in a number of Safety Guides, e.g. Regulatory Control of Radiation Sources, IAEA Safety Standards Series No. GS-G-1.5 (2004) and the

  15. Method of processing radioactive gas

    International Nuclear Information System (INIS)

    Saito, Masayuki.

    1978-01-01

    Purpose: To reduce the quantity of radioactive gas discharged at the time of starting a nuclear power plant. Method: After the stoppage of a nuclear power plant air containing a radioactive gas is extracted from a main condenser by operating an air extractor. The air is sent into a gaseous waste disposal device, and then introduced into the activated carbon adsorptive tower of a rare gas holdup device where xenon and krypton are trapped. Thereafter, the air passes through pipelines and returned to the main condenser. In this manner, the radioactive gas contained in air within the main condenser is removed during the stoppage of the operation of the nuclear power plant. After the plant has been started, when it enters the normal operation, a flow control valve is closed and another valve is opened, and a purified gas exhausted from the rare gas holdup device is discharged into the atmosphere through an exhaust cylinder. (Aizawa, K.)

  16. Effectiveness of granisetron in controlling pediatric gastroenteritis-related vomiting after discharge from the ED.

    Science.gov (United States)

    Qazi, Khajista; BinSalleeh, Hashim M; Shah, Ubaid H; AlGhamedi, Najwa; Tamim, Hani; Mubasher, Mohamed; Alrasheed, Faris; Alkanhal, Abdulrahman; AlTamimi, Saleh A

    2014-09-01

    The objective of the study is to determine the efficacy of oral granisetron (a long-acting 5-HT3 receptor antagonist) in stopping vomiting subsequent to discharge from emergency department (ED), in 6-month-old to 8-year-old patients with gastroenteritis-related vomiting and dehydration, who had failed an initial trial of oral rehydration (ORT). Eligible patients were offered ORT on a slowly advancing schedule. Patients who tolerated the initial ORT were discharged home. Patients who vomited were randomized to receive either 40 μg/kg of granisetron or placebo, and ORT was resumed. Patients who tolerated the postrandomization ORT were discharged home with another dose of the study drug. Parents were contacted by telephone every 24 hours until complete resolution of symptoms. The primary outcome was the proportion of patients with vomiting at 24 hours. Of the 900 eligible patients, 537 (60%) tolerated the initial ORT and were discharged home. Of the patients who vomited during the initial ORT, 165 were included in the final study sample (placebo, n = 82; granisetron, n = 83). There was no statistically significant difference in the proportion of patients with vomiting at 24 hours (granisetron, n = 38; placebo, n = 45; odds ratio, 0.64; 95% confidence interval, 0.34-1.19; P = .16). A similar trend in the proportion of patients with vomiting was noted for the entire follow-up period (granisetron, n = 43; placebo, n = 47; odds ratio, 0.73; P = .33; 95% confidence interval, 0.39-1.36). Granisetron was not effective in controlling gastroenteritis-related vomiting subsequent to discharge from ED. It did not change the expected course of the illness. Copyright © 2014 Elsevier Inc. All rights reserved.

  17. 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)

  18. 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

  19. Research on charging and discharging control strategy for electric vehicles as distributed energy storage devices

    Science.gov (United States)

    Zhang, Min; Yang, Feng; Zhang, Dongqing; Tang, Pengcheng

    2018-02-01

    A large number of electric vehicles are connected to the family micro grid will affect the operation safety of the power grid and the quality of power. Considering the factors of family micro grid price and electric vehicle as a distributed energy storage device, a two stage optimization model is established, and the improved discrete binary particle swarm optimization algorithm is used to optimize the parameters in the model. The proposed control strategy of electric vehicle charging and discharging is of practical significance for the rational control of electric vehicle as a distributed energy storage device and electric vehicle participating in the peak load regulation of power consumption.

  20. Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities

    Directory of Open Access Journals (Sweden)

    Nick R. Soelberg

    2013-01-01

    Full Text Available The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from used fuel reprocessing plants. The US DOE has sponsored, since 2009, an Off-gas Sigma Team to perform research and development focused on the most pressing volatile radionuclide control and immobilization problems. In this paper, we focus on the control requirements and methodologies for 85Kr and 129I. Numerous candidate technologies have been studied and developed at laboratory and pilot-plant scales in an effort to meet the need for high iodine control efficiency and to advance alternatives to cryogenic separations for krypton control. Several of these show promising results. Iodine decontamination factors as high as 105, iodine loading capacities, and other adsorption parameters including adsorption rates have been demonstrated under some conditions for both silver zeolite (AgZ and Ag-functionalized aerogel. Sorbents, including an engineered form of AgZ and selected metal organic framework materials (MOFs, have been successfully demonstrated to capture Kr and Xe without the need for separations at cryogenic temperatures.

  1. Control of high-level radioactive waste-glass melters

    International Nuclear Information System (INIS)

    Bickford, D.F.; Coleman, C.J.

    1990-01-01

    The Defense Waste Processing Facility (DWPF) will immobilize Savannah River Site High Level Waste as a durable borosilicate glass for permanent disposal in a repository. The DWPF will be controlled based on glass composition. The following discussion is a preliminary analysis of the capability of the laboratory methods that can be used to control the glass composition, and the relationships between glass durability and glass properties important to glass melting. The glass durability and processing properties will be controlled by controlling the chemical composition of the glass. The glass composition will be controlled by control of the melter feed transferred from the Slurry Mix Evaporator (SME) to the Melter Feed Tank (MFT). During cold runs, tests will be conducted to demonstrate the chemical equivalence of glass sampled from the pour stream and glass removed from cooled canisters. In similar tests, the compositions of glass produced from slurries sampled from the SME and MFT will be compared to final product glass to determine the statistical relationships between melter feed and glass product. The total error is the combination of those associated with homogeneity in the SME or MFT, sampling, preparation of samples for analysis, instrument calibration, analysis, and the composition/property model. This study investigated the sensitivity of estimation of property data to the combination of variations from sampling through analysis. In this or a similar manner, the need for routine glass product sampling will be minimized, and glass product characteristics will be assured before the melter feed is committed to the melter

  2. Global Model of Time-Modulated Electronegative Discharges for Neutral Radical and Electron Temperature Control

    Science.gov (United States)

    Kim, Sungjin; Lieberman, M. A.; Lichtenberg, A. J.

    2003-10-01

    Control and reduction of neutral radical flux/ion flux ratio and electron temperature Te is required for next generation etching in the microelectronics industry. We investigate time-modulated power for these purposes using a volume-averaged (global) oxygen discharge model, We consider pressures of 10-50 mTorr and plasma densities of 10^10-10^11 cm-3. In this regime, the discharge is found to be weakly electronegative. The modulation period and the duty ratio (on-time/period) are varied to determine the optimum conditions for reduction of FR= O-atom flux/ion flux and T_e. Two chambers with different height/diameter ratios (SMART Contract SM99-10051.

  3. Follow-up services for stroke survivors after hospital discharge--a randomized control study

    DEFF Research Database (Denmark)

    Andersen, Hanne Elkjaer; Eriksen, Karen; Brown, Anne

    2002-01-01

    OBJECTIVE: To evaluate whether follow-up services for stroke survivors could improve functional outcome and reduce readmission rate. In this paper results of functional outcome are reported. DESIGN: Randomized controlled trial allocating patients to one of three different types of aftercare: (1......) follow-up home visits by a physician, (2) physiotherapist instruction in the patient's home, or (3) standard aftercare. SUBJECTS: Stroke patients with persisting impairment and disability who, after completing inpatient rehabilitation, were discharged to their homes. OUTCOME MEASURES: Six months after...... discharge, functional outcome was assessed with Functional Quality of Movement, Barthel Index, Frenchay Activity Index and Index of Extended Activites of Daily Living. RESULTS: One-hundred and fifty-five stroke patients were included in the study. Fifty-four received follow-up home visits by a physician, 53...

  4. The exemption of regulatory control for the management of low level radioactive wastes

    International Nuclear Information System (INIS)

    Ortiz, M.T.; Carboneras, P.

    1993-01-01

    A high number of wastes produced in different fields of science and technology, as well as nuclear power plants, contain a significant volume of byproducts contaminated with radioisotopes, having a very low radioactive level. This kind of wastes might be managed as ordinary wastes by conventional methods or even reused. In order to carry out this procedure, a new regulation exempting these products from the regulatory control normatives would be necessary. This paper analyzes the big advantages of introducing these exemptions (costs recycling, radioactive wastes minimization) and how they follow the recommendations of ICRP, IAEA, EC and NRC

  5. Multi-fluid modelling of pulsed discharges for flow control applications

    Science.gov (United States)

    Poggie, J.

    2015-02-01

    Experimental evidence suggests that short-pulse dielectric barrier discharge actuators are effective for speeds corresponding to take-off and approach of large aircraft, and thus are a fruitful direction for flow control technology development. Large-eddy simulations have reproduced some of the main fluid dynamic effects. The plasma models used in such simulations are semi-empirical, however, and need to be tuned for each flowfield under consideration. In this paper, the discharge physics is examined in more detail with multi-fluid modelling, comparing a five-moment model (continuity, momentum, and energy equations) to a two-moment model (continuity and energy equations). A steady-state, one-dimensional discharge was considered first, and the five-moment model was found to predict significantly lower ionisation rates and number densities than the two-moment model. A two-dimensional, transient discharge problem with an elliptical cathode was studied next. Relative to the two-moment model, the five-moment model predicted a slower response to the activation of the cathode, and lower electron velocities and temperatures as the simulation approached steady-state. The primary reason for the differences in the predictions of the two models can be attributed to the effects of particle inertia, particularly electron inertia in the cathode layer. The computational cost of the five-moment model is only about twice that of the simpler variant, suggesting that it may be feasible to use the more sophisticated model in practical calculations for flow control actuator design.

  6. Experimental study of the pressure discharge process for the hydraulic control rod drive system stepped cylinder

    International Nuclear Information System (INIS)

    Wang, Jinhua; Bo, Hanliang; Zheng, Wenxiang

    2002-01-01

    The pressure discharge process from the stepped cylinder of the Hydraulic Control Rod Drive System (HCRDS) was studied experimentally in the HCRDS experimental loop for the 200 MW Nuclear Heating Reactor (NHR-200). The results showed that the differential pressure between the outside and the inside of the stepped cylinder increased rapidly to the desired value so that the force induced by the differential pressure which pushes the out tube of stepped cylinder was large enough. Therefore, if the hydraulic control rod were jammed, the pressure could push the hydraulic control rod to overcome the frictional resistance to insert the control rod into the reactor core. The experimental results verified that this design would solve the problem of hydraulic control rod jamming during an accident. (author)

  7. Guidelines for selecting preferred highway routes for highway-route-controlled quantity shipments of radioactive materials

    International Nuclear Information System (INIS)

    1989-01-01

    The document presents guidelines for use by State officials in selecting preferred routes for highway route controlled quantity shipments of radioactive materials. A methodology for analyzing and comparing safety factors of alternative routes is described. Technical information on the impacts of radioactive material transportation needed to apply the methodology is also presented. Application of the methodology will identify the route (or set of routes) that minimizes the radiological impacts from shipments of these radioactive materials within a given State. Emphasis in the document is on practical application of the methodology. Some details of the derivation of the methods and data are presented in the appendices. All references in the body of the report can be found listed in the Bibliography (Appendix F)

  8. Regulatory control of radioactive sources: an international perspective

    International Nuclear Information System (INIS)

    Flakus, F.N.

    1998-01-01

    Within its Regular Programme and its Technical Co-operation Programme, the IAEA undertakes a number of activities in support of national efforts aimed at strengthening national infrastructures for the control of radiation sources. The framework of these activities is described. (author)

  9. Corrosion control of carbon steel radioactive-liquid storage tanks

    International Nuclear Information System (INIS)

    Chang, Ji Young.

    1997-05-01

    As the West Valley Demonstration Project (WVDP) continues vitrification operation and begins decontamination activities, it is vital to continue to maintain the integrity of the high-level waste tanks and prevent further corrosion that may disrupt the operation. This report describes the current operational status and some corrosion concerns with corresponding control measure recommendations. 14 refs., 5 figs., 6 tabs

  10. Event detection and exception handling strategies in the ASDEX Upgrade discharge control system

    International Nuclear Information System (INIS)

    Treutterer, W.; Neu, G.; Rapson, C.; Raupp, G.; Zasche, D.; Zehetbauer, T.

    2013-01-01

    Highlights: •Event detection and exception handling is integrated in control system architecture. •Pulse control with local exception handling and pulse supervision with central exception handling are strictly separated. •Local exception handling limits the effect of an exception to a minimal part of the controlled system. •Central Exception Handling solves problems requiring coordinated action of multiple control components. -- Abstract: Thermonuclear plasmas are governed by nonlinear characteristics: plasma operation can be classified into scenarios with pronounced features like L and H-mode, ELMs or MHD activity. Transitions between them may be treated as events. Similarly, technical systems are also subject to events such as failure of measurement sensors, actuator saturation or violation of machine and plant operation limits. Such situations often are handled with a mixture of pulse abortion and iteratively improved pulse schedule reference programming. In case of protection-relevant events, however, the complexity of even a medium-sized device as ASDEX Upgrade requires a sophisticated and coordinated shutdown procedure rather than a simple stop of the pulse. The detection of events and their intelligent handling by the control system has been shown to be valuable also in terms of saving experiment time and cost. This paper outlines how ASDEX Upgrade's discharge control system (DCS) detects events and handles exceptions in two stages: locally and centrally. The goal of local exception handling is to limit the effect of an unexpected or asynchronous event to a minimal part of the controlled system. Thus, local exception handling facilitates robustness to failures but keeps the decision structures lean. A central state machine deals with exceptions requiring coordinated action of multiple control components. DCS implements the state machine by means of pulse schedule segments containing pre-programmed waveforms to define discharge goal and control

  11. Event detection and exception handling strategies in the ASDEX Upgrade discharge control system

    Energy Technology Data Exchange (ETDEWEB)

    Treutterer, W., E-mail: Wolfgang.Treutterer@ipp.mpg.de; Neu, G.; Rapson, C.; Raupp, G.; Zasche, D.; Zehetbauer, T.

    2013-10-15

    Highlights: •Event detection and exception handling is integrated in control system architecture. •Pulse control with local exception handling and pulse supervision with central exception handling are strictly separated. •Local exception handling limits the effect of an exception to a minimal part of the controlled system. •Central Exception Handling solves problems requiring coordinated action of multiple control components. -- Abstract: Thermonuclear plasmas are governed by nonlinear characteristics: plasma operation can be classified into scenarios with pronounced features like L and H-mode, ELMs or MHD activity. Transitions between them may be treated as events. Similarly, technical systems are also subject to events such as failure of measurement sensors, actuator saturation or violation of machine and plant operation limits. Such situations often are handled with a mixture of pulse abortion and iteratively improved pulse schedule reference programming. In case of protection-relevant events, however, the complexity of even a medium-sized device as ASDEX Upgrade requires a sophisticated and coordinated shutdown procedure rather than a simple stop of the pulse. The detection of events and their intelligent handling by the control system has been shown to be valuable also in terms of saving experiment time and cost. This paper outlines how ASDEX Upgrade's discharge control system (DCS) detects events and handles exceptions in two stages: locally and centrally. The goal of local exception handling is to limit the effect of an unexpected or asynchronous event to a minimal part of the controlled system. Thus, local exception handling facilitates robustness to failures but keeps the decision structures lean. A central state machine deals with exceptions requiring coordinated action of multiple control components. DCS implements the state machine by means of pulse schedule segments containing pre-programmed waveforms to define discharge goal and control

  12. Research on design method of main control room intake air radioactive monitoring

    International Nuclear Information System (INIS)

    Li Lei; Sun Yu; Wang Jiaoya; Liu Hongtao

    2014-01-01

    According to the design of the main control room intake gamma radiation dose rate monitoring channels in CPR1000 project and the study of relevant regulations and standards, a design method of main control room air inlet radioactive monitoring was presented. The measured object, equipment layout and chain operation were described. The threshold setting was explored using a calculation model established by MCNP software. The advantages, disadvantages and improvement ideas of this design were presented on the basis of calculation results. (authors)

  13. Proceedings of the AECB sponsored workshop on control of the ordering and receiving of radioactive material

    International Nuclear Information System (INIS)

    1997-07-01

    The workshop was held in Mississauga, Ontario, on February 4, 1997 for the purpose of bringing together radiation safety professionals to exchange information and propose options for action for the improved control of the ordering and receiving of radioactive materials. The focus was on unsealed radioisotopes and Type 'A' shipments. The workshop participants represented five major processors or distributors and five users who manage large radiation safety programs. These participants were invited because of their knowledge, experience and proximity. Workshop objectives were developed from a review of AECB files, from an AECB report which analysed, in a systematic manner, controls on the ordering and receiving of radioactive material, and from the participants' responses to a pre-workshop request for additional information. The objectives were to propose options for action: to prevent unauthorized persons from placing an order with a supplier; to prevent unauthorized persons from receiving radioactive material by establishing tighter control on the transfer of radioactive material and improving the control of radioactive material during and after delivery. This report provides a record of the presentations and discussions as well as the options for action developed during the workshop. The proposed options for action suggest additional regulatory requirements and guidance documents. Also identified was a need for better assessment, stricter enforcement and future discussions. Included in this report are new licence conditions which were developed as a result of this workshop, several 'parking lot' issues which were raised but considered outside the scope of the discussion and a list of participants. This workshop met the needs and expectation of the Materials Regulation Division (MRD) staff and addressed the needs of the participants. It also provided an opportunity to share information and ideas. It is MRDs intention to keep this collaborative workshop approach for

  14. Partial discharge measurements on 110kV current transformers. Setting the control value. Case study

    Science.gov (United States)

    Dan, C.; Morar, R.

    2017-05-01

    The case study presents a series of partial discharge measurements, reflecting the state of insulation of 110kV CURRENT TRANSFORMERS located in Sibiu county substations. Measurements were performed based on electrical method, using MPD600: an acquisition and analysis toolkit for detecting, recording, and analyzing partial discharges. MPD600 consists of one acquisition unit, an optical interface and a computer with dedicated software. The system allows measurements of partial discharge on site, even in presence of strong electromagnetic interferences because it provides synchronous acquisition from all measurement points. Therefore, measurements, with the ability to be calibrated, do render: - a value subject to interpretation according to IEC 61869-1:2007 + IEC 61869-2:2012 + IEC 61869-3:2011 + IEC 61869-5:2011 and IEC 60270: 2000; - the possibility to determine the quantitative limit of PD (a certain control value) to which the equipment can be operated safely and repaired with minimal costs (relative to the high costs implied by eliminating the consequences of a failure) identified empirically (process in which the instrument transformer subjected to the tests was completely destroyed).

  15. Preparation of Ag/Cu/Ti Nanofluids by Spark Discharge System and Its Control Parameters Study

    Directory of Open Access Journals (Sweden)

    Kuo-Hsiung Tseng

    2015-01-01

    Full Text Available This study selected silver, copper, and titanium as the research objects to explore the relationship between nanofluids properties and electrical discharge machining (EDM processes. Regarding the products, UV-visible spectroscopy (UV-Vis was applied to measure the concentration distribution of nanofluids; zeta-size analysis is applied for measuring nanometal particles’ Zeta-Potential and the size distribution of metallic particles in the fluid. Finally, various instruments, including scanning electron microscope (SEM, were applied to observe the shape, size, and composition ratio of metal particles after processing. According to the experimental results, the control of the discharge pulse time, in addition to affecting the concentration of metallic liquid and temperature in the process, affects the size of the metal particles after the process. As the resistivity of silver and copper is very low, at about 15×10-9 Ω·m, if TON is set to between 10~50 μs, good preparation efficiency can be obtained. The resistivity of titanium is 420×10-9 Ω·m, which is much larger than that of silver or copper. Hence, TON should be set to approximately 100 μs to achieve a good discharge success rate.

  16. A model for automation of radioactive dose control

    International Nuclear Information System (INIS)

    Ribeiro, Carlos Henrique Calazans; Zambon, Jose Waldir; Bitelli, Ricardo; Honaiser, Eduardo Henrique Rangel

    2009-01-01

    The paper presents a proposal for automation of the personnel dose control system to be used in nuclear medicine environments. The model has considered the Standards and rules of the National Commission of Nuclear Energy (CNEN) and of the Health Ministry. The advantages of the model is a robust management of the integrated dose and technicians qualification status. The software platform selected to be used was the Lotus Notes and an analysis of the advantages, disadvantages of the use of this platform is also presented. (author)

  17. A model for automation of radioactive dose control

    Energy Technology Data Exchange (ETDEWEB)

    Ribeiro, Carlos Henrique Calazans; Zambon, Jose Waldir; Bitelli, Ricardo; Honaiser, Eduardo Henrique Rangel [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Sao Paulo, SP (Brazil)], e-mail: calazans@ctmsp.mar.mil.br, e-mail: zambon@ctmsp.mar.mil.br, e-mail: bitelli@ctmsp.mar.mil.br, e-mail: honaiser@ctmsp.mar.mil.br

    2009-07-01

    The paper presents a proposal for automation of the personnel dose control system to be used in nuclear medicine environments. The model has considered the Standards and rules of the National Commission of Nuclear Energy (CNEN) and of the Health Ministry. The advantages of the model is a robust management of the integrated dose and technicians qualification status. The software platform selected to be used was the Lotus Notes and an analysis of the advantages, disadvantages of the use of this platform is also presented. (author)

  18. The Role of Automatic Radiation Monitoring in Control of Illicit Trafficking of Radioactive Materials in Slovenia

    International Nuclear Information System (INIS)

    Mitic, D.

    2003-01-01

    Automatic radiation monitoring in Slovenia comprises monitoring of external gamma radiation, aerosol radioactivity, radon progeny concentration, and radioactive deposition measurements. The officer on duty has an important part in assuring proper and undisturbed functioning of our automatic radiation monitoring. He is the one who gets the first alert message on radiation levels when exceeded pre-set values in the territory of Slovenia. Together with continuous control over the functioning of automatic radiation monitoring, the officer on duty has been also assigned for receiving messages from users, who carry the 'Radiation pager' (it is a trade mark for Sensor Technology Engineering, inc. from USA). All valuable experiences of the officer on duty who has been accepting reports from customs officers, police officers, from Slovenian radiation and nuclear safety inspectors, are described in this article. The officer on duty with his new role contributes to prevention of the illicit trafficking and inadvertent movement of radioactive materials over the territory of Slovenia. In the last year there where many different causes of emergency calls: from many cases of patient after radioisotopes medical treatment to serious rejected shipment with exceeded radiation. This is only a beginning of responsible task how to introduce and assure the control of the inadvertent movement of radioactive materials in Slovenia. (author)

  19. Wind tunnel experiments on flow separation control of an Unmanned Air Vehicle by nanosecond discharge plasma aerodynamic actuation

    International Nuclear Information System (INIS)

    Chen Kang; Liang Hua

    2016-01-01

    Plasma flow control (PFC) is a new kind of active flow control technology, which can improve the aerodynamic performances of aircrafts remarkably. The flow separation control of an unmanned air vehicle (UAV) by nanosecond discharge plasma aerodynamic actuation (NDPAA) is investigated experimentally in this paper. Experimental results show that the applied voltages for both the nanosecond discharge and the millisecond discharge are nearly the same, but the current for nanosecond discharge (30 A) is much bigger than that for millisecond discharge (0.1 A). The flow field induced by the NDPAA is similar to a shock wave upward, and has a maximal velocity of less than 0.5 m/s. Fast heating effect for nanosecond discharge induces shock waves in the quiescent air. The lasting time of the shock waves is about 80 μs and its spread velocity is nearly 380 m/s. By using the NDPAA, the flow separation on the suction side of the UAV can be totally suppressed and the critical stall angle of attack increases from 20° to 27° with a maximal lift coefficient increment of 11.24%. The flow separation can be suppressed when the discharge voltage is larger than the threshold value, and the optimum operation frequency for the NDPAA is the one which makes the Strouhal number equal one. The NDPAA is more effective than the millisecond discharge plasma aerodynamic actuation (MDPAA) in boundary layer flow control. The main mechanism for nanosecond discharge is shock effect. Shock effect is more effective in flow control than momentum effect in high speed flow control. (paper)

  20. Nondestructive techniques for the control of conditioned radioactive wastes

    International Nuclear Information System (INIS)

    Delprato, U.

    1987-01-01

    The final product of the radwaste conditioning process must satisfy certain requirments and physico-chemical properties in order to assure its safe long-term behaviour. Of course, the foreseen quality assurance and quality control should be conducted by means of non-destructive techniques. This work presents an over-view of various applicable non-destructive methods of analysis, showing their fields of investigation in testing waste packages, together with some arising practical problems. The most promising methods, such as eddy current testing, ultrasonic testing, γ-scanning, γ-spectroscopy, neutron counting and computerized tomography, are treated more deeply and some applications are presented. Particular attention is devoted to the development of a device based on computerized tomography; its essential components are reported and some design problems are also discussed

  1. ARCON96, Radioactive Plume Concentration in Reactor Control Rooms

    International Nuclear Information System (INIS)

    Ramsdell, J.V.; Simonen, C.A.

    2003-01-01

    1 - Description of program or function: ARCON96 was developed to calculate relative concentrations in plumes from nuclear power plants at control room air intakes in the vicinity of the release point. 2 - Methods: ARCON96 implements a straight-line Gaussian dispersion model with dispersion coefficients that are modified to account for low wind meander and building wake effects. Hourly, normalized concentrations (X/Q) are calculated from hourly meteorological data. The hourly values are averaged to form X/Qs for periods ranging from 2 to 720 hours in duration. The calculated values for each period are used to form cumulative frequency distributions. 3 - Restriction on the complexity of the problem: ARCON96 is a single user program. If expanded output is selected by the user, the file includes the hourly input and X/Qs and the intermediate computational results. The output file may exceed a megabyte size

  2. Early assisted discharge with generic community nursing for chronic obstructive pulmonary disease exacerbations: Results of a randomised controlled trial

    NARCIS (Netherlands)

    C.M.A. Utens (Cecile); L.M.A. Goossens (Lucas); F.W.J.M. Smeenk (Frank); M.P.M.H. Rutten-van Mölken (Maureen); M. van Vliet (Monique); M.W. Braken (Maria); L. van Eijsden (Loes); O.C.P. Schayck (Onno)

    2012-01-01

    textabstractObjectives: To determine the effectiveness of early assisted discharge for chronic obstructive pulmonary disease (COPD) exacerbations, with home care provided by generic community nurses, compared with usual hospital care. Design: Prospective, randomised controlled and multicentre trial

  3. Method for improving the electrostatics perforation pattern using power controlled discharges

    Energy Technology Data Exchange (ETDEWEB)

    Garzon, C; Miranda, E; GarcIa-Garcia, J [Departament d' Enginyeria Electronica, Universitat Autonoma de Barcelona, 08193 Bellaterra, Barcelona (Spain); Martinez-Cisneros, C; Alonso, J, E-mail: carolina.garzon@uab.cat [Departament de Quimica Analitica, Universitat Autonoma de Barcelona, 08193 Bellaterra, Barcelona (Spain)

    2011-06-23

    The aims of this work are to show the influence of adding a series resistance at the output of a discharge generator circuit and to point out that this component can be used to control the spark energy in electrostatic perforation systems. Analysis of the experimental results reveals that there exists a close connection between the resistor value and the obtained perforation pattern both in hole density and size. The use of a series resistor has a strong influence on the material porosity, which is an important industrial parameter for assessing the pattern perforation quality.

  4. Nuclear security recommendations on nuclear and other radioactive material out of regulatory control: Recommendations

    International Nuclear Information System (INIS)

    2011-01-01

    The purpose of this publication is to provide guidance to States in strengthening their nuclear security regimes, and thereby contributing to an effective global nuclear security framework, by providing: - Recommendations to States and their competent authorities on the establishment or improvement of the capabilities of their nuclear security regimes, for carrying out effective strategies to deter, detect and respond to a criminal act, or an unauthorized act, with nuclear security implications, involving nuclear or other radioactive material that is out of regulatory control; - Recommendations to States in support of international cooperation aimed at ensuring that any nuclear or other radioactive material that is out of regulatory control, whether originating from within the State or from outside that State, is placed under regulatory control and the alleged offenders are, as appropriate, prosecuted or extradited

  5. Main Activities to Improve the Control of Radioactive Sources and Maintain an Effective Regulatory Nuclear Systems in Brazil

    International Nuclear Information System (INIS)

    Marechal, M.H.

    2016-01-01

    Since 2006, the Directorate of Nuclear Safety and Security, DRS, of National Nuclear Energy Commission, CNEN, has gone through many improvements. In 2006 CNEN signed the commitment to the recommendations of the Code of Conduct on The Safety and Security of Radioactive Sources and the Guidance on The Import and Export of Radioactive Sources. The DRS is responsible for the licensing and control of nuclear facilities, fuel cycle, waste management and the control of radioactive sources and authorizations of medical and industrial installations. In 2009 the department responsible for the control of radioactive sources and authorizations of medical and industrial installations implemented an “Electronic Management System” in which this System integrates the transport department and waste management department. The Electronic Management System is linked to the register of radioactive sources and facilities and there is an access on line to the Customs, making the control of import and export of radioactive sources robust, efficient and fast. During the period from 2006 until 2015 the most relevant regulations related to the control of radioactive sources and authorizations of medical and industrial installations were reviewed and some were elaborated and issued. These documents were in line with the Categorization of Radioactive Sources and the International Basic Safety Standards, issued in the IAEA Safety Standard Series as General Safety Requirements Part 3 (GSR Part 3). The paper describes all the steps that were adopted in order to implement these systems and the improvements on our Nuclear Regulatory Systems. (author)

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

    International Nuclear Information System (INIS)

    Garnier, A.

    1966-01-01

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

  7. Development of a new discharge control system utilizing UNIX workstations and VME-bus systems for JT-60

    Energy Technology Data Exchange (ETDEWEB)

    Akasaka, Hiromi; Sueoka, Michiharu; Takano, Shoji; Totsuka, Toshiyuki; Yonekawa, Izuru; Kurihara, Kenichi; Kimura, Toyoaki [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

    2002-01-01

    The JT-60 discharge control system, which had used HIDIC-80E 16 bit mini-computers and CAMAC systems since the start of JT-60 experiment in 1985, was renewed in March, 2001. The new system consists of a UNIX workstation and a VME-bus system, and features a distributed control system. The workstation performs message communication with a VME-bus system and controllers of JT-60 sub-systems and processing for discharge control because of its flexibility to construction of a new network and modifications of software. The VME-bus system performs discharge sequence control because it is suitable for fast real time control and flexible to the hardware extension. The replacement has improved the control function and reliability of the discharge control system and also has provided sufficient performance necessary for future modifications of JT-60. The new system has been running successfully since April 2001. The data acquisition speed was confirmed to be twice faster than the previous one. This report describes major functions of the discharge control system, technical ideas for developing the system and results of the initial operation in detail. (author)

  8. Hydrogeologic controls on ground-water and contaminant discharge to the Columbia River near the Hanford Townsite

    International Nuclear Information System (INIS)

    Luttrell, S.P.; Newcomer, D.R.; Teel, S.S.; Vermeul, V.R.

    1992-11-01

    The purpose of this study is to quantify ground-water and contaminant discharge to the Columbia River in the Hanford Townsite vicinity. The primary objectives of the work are to: describe the hydrogeologic setting and controls on ground-water movement and contaminant discharge to the Columbia River; understand the river/aquifer relationship and its effects on contaminant discharge to the Columbia River; quantify the ground-water and contaminant mass discharge to the Columbia River; and provide data that may be useful for a three-dimensional model of ground-water flow and contaminant transport in the Hanford Townsite study area. The majority of ground-water contamination occurs within the unconfined aquifer; therefore, ground-water and contaminant discharge from the unconfined aquifer is the emphasis of this study. The period of study is primarily from June 1990 through March 1992

  9. Acceleration optimization of real-time equilibrium reconstruction for HL-2A tokamak discharge control

    Science.gov (United States)

    Rui, MA; Fan, XIA; Fei, LING; Jiaxian, LI

    2018-02-01

    Real-time equilibrium reconstruction is crucially important for plasma shape control in the process of tokamak plasma discharge. However, as the reconstruction algorithm is computationally intensive, it is very difficult to improve its accuracy and reduce the computation time, and some optimizations need to be done. This article describes the three most important aspects of this optimization: (1) compiler optimization; (2) some optimization for middle-scale matrix multiplication on the graphic processing unit and an algorithm which can solve the block tri-diagonal linear system efficiently in parallel; (3) a new algorithm to locate the X&O point on the central processing unit. A static test proves the correctness and a dynamic test proves the feasibility of using the new code for real-time reconstruction with 129 × 129 grids; it can complete one iteration around 575 μs for each equilibrium reconstruction. The plasma displacements from real-time equilibrium reconstruction are compared with the experimental measurements, and the calculated results are consistent with the measured ones, which can be used as a reference for the real-time control of HL-2A discharge.

  10. Nuclear Security Recommendations on Nuclear and other Radioactive Material out of Regulatory Control: Recommendations (Spanish Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication presents recommendations for the nuclear security of nuclear and other radioactive material that is out of regulatory control. It is based on national experiences and practices and guidance publications in the field of security as well as the nuclear security related international instruments. The recommendations include guidance for States with regard to the nuclear security of nuclear and other radioactive material that has been reported as being out of regulatory control as well as for material that is lost, missing or stolen but has not been reported as such, or has been otherwise discovered. In addition, these recommendations adhere to the detection and assessment of alarms and alerts and to a graded response to criminal or unauthorized acts with nuclear security implications.

  11. Nuclear Security Recommendations on Nuclear and Other Radioactive Material out of Regulatory Control: Recommendations (Arabic Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication presents recommendations for the nuclear security of nuclear and other radioactive material that is out of regulatory control. It is based on national experiences and practices and guidance publications in the ? field of security as well as the nuclear security related international instruments. The recommendations include guidance for States with regard to the nuclear security of nuclear and other radioactive material that has been reported as being out of regulatory control as well as for material that is lost, missing or stolen but has not been reported as such, or has been otherwise discovered. In addition, these recommendations adhere to the detection and assessment of alarms and alerts and to a graded response to criminal or unauthorized acts with nuclear security implications.

  12. Nuclear Security Recommendations on Nuclear and Other Radioactive Material out of Regulatory Control: Recommendations

    International Nuclear Information System (INIS)

    2011-01-01

    This publication presents recommendations for the nuclear security of nuclear and other radioactive material that is out of regulatory control. It is based on national experiences and practices and guidance publications in the field of security as well as the nuclear security related international instruments. The recommendations include guidance for States with regard to the nuclear security of nuclear and other radioactive material that has been reported as being out of regulatory control as well as for material that is lost, missing or stolen but has not been reported as such, or has been otherwise discovered. In addition, these recommendations adhere to the detection and assessment of alarms and alerts and to a graded response to criminal or unauthorized acts with nuclear security implications

  13. Los Alamos Controlled Air Incinerator for hazardous chemical and mixed radioactive wastes

    International Nuclear Information System (INIS)

    Vavruska, J.S.; Borduin, L.C.; Hutchins, D.A.; Koenig, R.A.; Warner, C.L.

    1986-01-01

    The Los Alamos Controlled Air Incinerator (CAI) is currently the only radioactive waste incineration facility in the US permitted to treat polychlorinated biphenyls (PCBs). The CAI was developed in the mid-1970's as a demonstration system for volume reduction of transuranic (TRU) contaminated combustible solid wastes. It has since undergone additions and modifications to accommodate hazardous chemical wastes in response to a need within the Department of Energy (DOE) to treat mixed radioactive/chemical wastes. An overview of these additions which include a liquid feed system, a high intensity liquid injection burner, and an activated carbon adsorption unit is presented here. Also included is a discussion of the procedures required for Toxic Substances Control Act (TSCA) and Resource Conservation and Recovery Act (RCRA) permitting of the CAI

  14. Nuclear Security Recommendations on Nuclear and Other Radioactive Material out of Regulatory Control: Recommendations (Russian Edition)

    International Nuclear Information System (INIS)

    2011-01-01

    This publication presents recommendations for the nuclear security of nuclear and other radioactive material that is out of regulatory control. It is based on national experiences and practices and guidance publications in the field of security as well as the nuclear security related international instruments. The recommendations include guidance for States with regard to the nuclear security of nuclear and other radioactive material that has been reported as being out of regulatory control as well as for material that is lost, missing or stolen but has not been reported as such, or has been otherwise discovered. In addition, these recommendations adhere to the detection and assessment of alarms and alerts and to a graded response to criminal or unauthorized acts with nuclear security implications.

  15. Observations on the use of cost-benefit analysis in the control of radioactive waste disposal

    International Nuclear Information System (INIS)

    Shepherd, J.G.; Hetherington, J.A.

    1975-10-01

    The disposal of radioactive waste to the environment can lead to the irradiation of large numbers of people, and although the individual doses may be very small compared with the ICRP dose limits the total population dose may not be insignificant. In these circumstances the control procedure is likely to be determined by the requirement that doses be kept 'as low as is readily achievable'(see ICRP-9, para. 52). This recommendation has been interpreted in ICRP-22, where the use of cost-benefit analysis is suggested as a means of application in practice. This paper discusses some of the implications of these recommendations in relation to the control of radioactive waste disposal, under the following headings: the use of collective dose; the costing of collective dose; the assessment and use of detrimental costs; and the payment of detrimental costs. (author)

  16. The role of the health physicist in the control of airborne radioactive hazards

    International Nuclear Information System (INIS)

    Basson, J.K.

    1978-01-01

    Health physics is based on the ease and sensitivity with which ionising radiations can be measured, as well as on the extensive medical knowledge of its long-term effects. Such studies have led to fundamental contributions to scientific health protection as well as practical occupational hygiene. The first aspect is illustrated with aerosol biophysics as example, while the practical control of airborne radioactive hazards in South Africa is described inside uranium plants as well as in the environment of nuclear installations [af

  17. Partial oxidation of methane in a temperature-controlled dielectric barrier discharge reactor

    KAUST Repository

    Zhang, Xuming

    2015-01-01

    We studied the relative importance of the reduced field intensity and the background reaction temperature in the partial oxidation of methane in a temperature-controlled dielectric barrier discharge reactor. We obtained important mechanistic insight from studying high-temperature and low-pressure conditions with similar reduced field intensities. In the tested range of background temperatures (297 < T < 773 K), we found that the conversion of methane and oxygen depended on both the electron-induced chemistry and the thermo-chemistry, whereas the chemical pathways to the products were overall controlled by the thermo-chemistry at a given temperature. We also found that the thermo-chemistry enhanced the plasma-assisted partial oxidation process. Our findings expand our understanding of the plasma-assisted partial oxidation process and may be helpful in the design of cost-effective plasma reformers. © 2014 The Combustion Institute.

  18. Development of a flight simulator for the control of plasma discharges

    Energy Technology Data Exchange (ETDEWEB)

    Ravenel, N.; Artaud, J.F.; Bremond, S.; Guillerminet, B.; Huynh, P.; Moreau, P.; Signoret, J. [CEA Cadarache, IRFM, 13 - Saint-Paul-lez-Durance (France)

    2009-07-01

    Over the years, feedback controls in fusion experiments become more and more crucial both for increasing performance, stability and ensuring machine protection. Advanced controls, such as current profile control, have to deal with nonlinear, complex physical processes that can hardly be addressed by 'trial and error' methods. Such issues highlight the necessity to build new tools based on plasma discharge flight simulator for the development, test and qualification of advanced control algorithms. A project aiming at developing such tools has started last year at Cea. A part of the project consists in the development of a flight simulator that will be integrated to the present Real Time Control and Acquisition System. Under the experimental program, it will facilitate the development and the implementation of new advanced controllers in the control units. The flight simulator will be based on the European Integrated Tokamak Modelling (ITM) simulation platform. Thus, it will benefit from the development made by the task force and it will be able to offer a development platform for the new controllers of present day European tokamaks and future machine. This paper will address the architecture of the project focussing on the following items: -) Development of a 'high level' interface to build plasma scenarios as a set in sequence; -) Interface of the Tore Supra data and parameters within the ITM data structure; -) Integration of the developments under the ITM simulation platform (Kepler) using Xcos software (produced by the Scilab Consortium) functionalities such as the automatic code generation for the implementation of the controllers; -) Modification of the present control unit software towards modular units in order to facilitate control algorithm development. This document is composed of an abstract followed by the presentation transparencies. (authors)

  19. Effectiveness of a discharge education program in reducing the severity of postpartum depression: a randomized controlled evaluation study.

    Science.gov (United States)

    Ho, Shiao-Ming; Heh, Shu-Shya; Jevitt, Cecilia M; Huang, Lian-Hua; Fu, Yu-Ying; Wang, Li-Lin

    2009-10-01

    The effectiveness of a hospital discharge education program including information on postnatal depression was evaluated to reduce psychological morbidity after childbirth. A randomized controlled trial (RCT) was conducted in a regional hospital in Taipei. Two hundred first-time mothers agreed to take part and were randomly allocated to an intervention group (n=100) or control group (n=100). The intervention group received discharge education on postnatal depression provided by postpartum ward nurses. The control group received general postpartum education. The main outcome measure was the Edinburgh Postnatal Depression Scale (EPDS) administered by postal questionnaire at six weeks and three months after delivery. Women who received discharge education intervention on postnatal depression were less likely to have high depression scores when compared to the control group at three months postpartum. A discharge educational intervention including postnatal depression information given to women during the postpartum stay benefits psychological well-being. A postpartum discharge education program including information on postnatal depression should be integrated into postpartum discharge care in general practice. 2009 Elsevier Ireland Ltd.

  20. Radiation monitoring in the NPP environment, control of radioactivity in NPP-environment system

    International Nuclear Information System (INIS)

    Egorov, Yu.A.

    1987-01-01

    Problems of radiation monitoring and control of the NPP-environment system (NPPES) are considered. Radiation control system at the NPP and in the environment provides for the control of the NPP, considered as the source of radioactive releases in the environment and for the environmental radiation climate control. It is shown, that the radiation control of the NPP-environment system must be based on the ecological normalization principles of the NPP environmental impacts. Ecological normalization should be individual for the NPP region of each ecosystem. The necessity to organize and conduct radiation ecological monitoring in the NPP regions is pointed out. Radiation ecological monitoring will provide for both environmental current radiation control and information for mathematical models, used in the NPPES radiation control

  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. Control and Management of Radioactive Material Inadvertently Incorporated into Scrap Metal. Proceedings of an International Conference

    International Nuclear Information System (INIS)

    2011-01-01

    Radioactive substances can become associated with scrap metal in various ways and if not discovered they can be incorporated into steel and non-ferrous metals through the melting process. This can cause health hazards as well as environmental concerns and there can be serious commercial implications. Numerous incidents have occurred in recent years involving the discovery of radioactive substances in scrap metal and, in some cases, in metal from the melting process. These incidents have proved to be very costly in relation to the recovery and cleanup operations required but also in terms of the potential loss of confidence of the industry in scrap metal as a resource. This has led the scrap metal industry to seek ways of managing the problem. In most countries, shipments of scrap metal are monitored but at different points in the distribution chain and to different extents and efficiencies. As yet, only limited efforts towards unifying and harmonizing monitoring strategies and methods in the context of scrap metal have been made at the international level. The Conference was organized into five sessions: the global perspective, national policies and strategies, compliance with radiological criteria, management of incidents with contaminated scrap metal, and improving confidence and protecting the interests of stakeholders. The aim of the first session was to present the views and perspectives of the different organizations concerned with radioactive material in scrap metal, scrap metal recycling, steel making, radiation source security and safety and international trade and economics. The second session covered some of the national policies and strategies being used to address the control of radioactive material that has been inadvertently incorporated into scrap metal were presented. In addition to the oral presentations, contributions describing the situation in many countries of the world in the form of posters were displayed. The many posters reporting national

  3. Control and Management of Radioactive Material Inadvertently Incorporated into Scrap Metal. Proceedings of an International Conference

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-15

    Radioactive substances can become associated with scrap metal in various ways and if not discovered they can be incorporated into steel and non-ferrous metals through the melting process. This can cause health hazards as well as environmental concerns and there can be serious commercial implications. Numerous incidents have occurred in recent years involving the discovery of radioactive substances in scrap metal and, in some cases, in metal from the melting process. These incidents have proved to be very costly in relation to the recovery and cleanup operations required but also in terms of the potential loss of confidence of the industry in scrap metal as a resource. This has led the scrap metal industry to seek ways of managing the problem. In most countries, shipments of scrap metal are monitored but at different points in the distribution chain and to different extents and efficiencies. As yet, only limited efforts towards unifying and harmonizing monitoring strategies and methods in the context of scrap metal have been made at the international level. The Conference was organized into five sessions: the global perspective, national policies and strategies, compliance with radiological criteria, management of incidents with contaminated scrap metal, and improving confidence and protecting the interests of stakeholders. The aim of the first session was to present the views and perspectives of the different organizations concerned with radioactive material in scrap metal, scrap metal recycling, steel making, radiation source security and safety and international trade and economics. The second session covered some of the national policies and strategies being used to address the control of radioactive material that has been inadvertently incorporated into scrap metal were presented. In addition to the oral presentations, contributions describing the situation in many countries of the world in the form of posters were displayed. The many posters reporting national

  4. Electron-induced dry reforming of methane in a temperature-controlled dielectric barrier discharge reactor

    KAUST Repository

    Zhang, Xuming

    2013-09-23

    Dry reforming of methane has the potential to reduce the greenhouse gases methane and carbon dioxide and to generate hydrogen-rich syngas. In reforming methane, plasma-assisted reforming processes may have advantages over catalytic processes because they are free from coking and their response time for mobile applications is quick. Although plasma-assisted reforming techniques have seen recent developments, systematic studies that clarify the roles that electron-induced chemistry and thermo-chemistry play are needed for a full understanding of the mechanisms of plasma-assisted reformation. Here, we developed a temperature-controlled coaxial dielectric barrier discharge (DBD) apparatus to investigate the relative importance of electron-induced chemistry and thermo-chemistry in dry reforming of methane. In the tested background temperature range 297-773 K, electron-induced chemistry, as characterized by the physical properties of micro-discharges, was found to govern the conversions of CH4 and CO2, while thermo-chemistry influenced the product selectivities because they were found to depend on the background temperature. Comparisons with results from arc-jet reformation indicated that thermo-chemistry is an efficient conversion method. Our findings may improve designs of plasma-assisted reformers by using relatively hotter plasma sources. However, detailed chemical kinetic studies are needed. © 2013 IOP Publishing Ltd.

  5. Electron-induced dry reforming of methane in a temperature-controlled dielectric barrier discharge reactor

    International Nuclear Information System (INIS)

    Zhang, Xuming; Cha, Min Suk

    2013-01-01

    Dry reforming of methane has the potential to reduce the greenhouse gases methane and carbon dioxide and to generate hydrogen-rich syngas. In reforming methane, plasma-assisted reforming processes may have advantages over catalytic processes because they are free from coking and their response time for mobile applications is quick. Although plasma-assisted reforming techniques have seen recent developments, systematic studies that clarify the roles that electron-induced chemistry and thermo-chemistry play are needed for a full understanding of the mechanisms of plasma-assisted reformation. Here, we developed a temperature-controlled coaxial dielectric barrier discharge (DBD) apparatus to investigate the relative importance of electron-induced chemistry and thermo-chemistry in dry reforming of methane. In the tested background temperature range 297–773 K, electron-induced chemistry, as characterized by the physical properties of micro-discharges, was found to govern the conversions of CH 4 and CO 2 , while thermo-chemistry influenced the product selectivities because they were found to depend on the background temperature. Comparisons with results from arc-jet reformation indicated that thermo-chemistry is an efficient conversion method. Our findings may improve designs of plasma-assisted reformers by using relatively hotter plasma sources. However, detailed chemical kinetic studies are needed. (paper)

  6. Critical zone structure controls concentration-discharge relationships and solute generation in forested tropical montane watersheds

    Science.gov (United States)

    Wymore, Adam S.; Brereton, Richard L.; Ibarra, Daniel E.; Maher, Kate; McDowell, William H.

    2017-07-01

    Concentration-discharge (C-Q) relationships are poorly known for tropical watersheds, even though the tropics contribute a disproportionate amount of solutes to the global ocean. The Luquillo Mountains in Puerto Rico offer an ideal environment to examine C-Q relationships across a heterogeneous tropical landscape. We use 10-30 years of weekly stream chemistry data across 10 watersheds to examine C-Q relationships for weathering products (SiO2(aq), Ca2+, Mg2+, and Na+) and biologically controlled solutes (dissolved organic carbon [DOC], dissolved organic nitrogen [DON], NH4+, NO3-, PO43-, K+, and SO42-). We analyze C-Q relationships using power law equations and a solute production model and use principal component analysis to test hypotheses regarding how the structure of the critical zone controls solute generation. Volcaniclastic watersheds had higher concentrations of weathering solutes and smaller tributaries were approximately threefold more efficient at generating these solutes than larger rivers. Lithology and vegetation explained a significant amount of variation in the theoretical maximum concentrations of weathering solutes (r2 = 0.43-0.48) and in the C-Q relationships of PO43- (r2 = 0.63) and SiO2(aq) (r2 = 0.47). However, the direction and magnitude of these relationships varied. Across watersheds, various forms of N and P displayed variable C-Q relationships, while DOC was consistently enriched with increasing discharge. Results suggest that PO43- may be a useful indicator of watershed function. Relationships between C-Q and landscape characteristics indicate the extent to which the structure and function of the Critical zone controls watershed solute fluxes.

  7. Demolition and removal of radioactively contaminated concrete soil: Aerosol control and monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Newton, G.J.; Hoover, M.D.; Grace, A.C. III

    1995-12-01

    From 1963 to 1985, two concrete-lined ponds were used to reduce the volume of radioactive liquids from the Institute`s research programs. Following withdrawal of the {open_quotes}hot ponds{close_quotes} from active use, the residual sludges and plastic liners of the ponds were removed and shipped to a radioactive waste disposal site. From 1987 to 1994, the concrete structures remained undisturbed pending environmental restoration on the site. Restoration began in 1994 and was completed in 1995. Restoration involved mechanical breakup and removal of the concrete structures and removal of areas of contaminated soils from the site. This report describes the design and results of the aerosol control and monitoring program that was conducted to ensure protection of workers and the environment during the restoration process. The aerosol control and monitoring strategy developed for remediation of the ITRI hot ponds was successful both in preventing dispersion of radioactive dusts and in demonstrating that exposures of workers and offsite releases were within statutory limits.

  8. Issues and Experiences on Radioactive Waste Quality Control / Quality Assurance with Regard to Future Disposal

    International Nuclear Information System (INIS)

    Beckmerhagen, I.; Brennecke, P.; Steyer, S.; Bandt, G.

    2006-01-01

    In the Federal Republic of Germany all types of radioactive waste (short-lived, long-lived) are to be disposed of in deep geological formations. Thus, the safe management of radioactive waste presupposes an appropriate conditioning of primary waste-to-waste packages suitable for emplacement in a repository as well as the documentation of pre-treatment, processing and packaging steps and the waste package characteristics being relevant for disposal. Due to the operation, decommissioning and dismantling of nuclear facilities as well as the application of radioisotopes in industry, medicine and research and development radioactive waste continuously arises in Germany. In order to manage this waste different measures and procedures regarding its conditioning and quality control/quality assurance were introduced and since many years successfully applied. Waste conditioning is especially characterized by a flexible application of the Konrad waste acceptance requirements. The rationale for this approach is due to the present non-availability of a repository in Germany. Several examples of a 'tailor-made' application of the waste acceptance requirements in treatment, conditioning and documentation processes as well as the quality assurance/quality control processes illustrate the current German approach. (authors)

  9. Measuring the absolute disintegration rate of a radioactive gas with a moveable endplate discharge counter (MEP) and theoretical calculation of wall effect

    International Nuclear Information System (INIS)

    Jaffey, A.H.; Gray, J.; Bentley, W.C.; Lerner, J.L.

    1987-09-01

    A precision built moveable endplate Geiger-Mueller counter was used to measure the absolute disintegration rate of a beta-emitting radioactive gas. A Geiger-Mueller counter used for measuring gaseous radioactivity has 85 Kr (beta energy, 0.67 MeV). The wall effect calculation is readily extendable to other beta energies

  10. A Review of Control Strategy of the Large-scale of Electric Vehicles Charging and Discharging Behavior

    Science.gov (United States)

    Kong, Lingyu; Han, Jiming; Xiong, Wenting; Wang, Hao; Shen, Yaqi; Li, Ying

    2017-05-01

    Large scale access of electric vehicles will bring huge challenges to the safe operation of the power grid, and it’s important to control the charging and discharging of the electric vehicle. First of all, from the electric quality and network loss, this paper points out the influence on the grid caused by electric vehicle charging behaviour. Besides, control strategy of electric vehicle charging and discharging has carried on the induction and the summary from the direct and indirect control. Direct control strategy means control the electric charging behaviour by controlling its electric vehicle charging and discharging power while the indirect control strategy by means of controlling the price of charging and discharging. Finally, for the convenience of the reader, this paper also proposed a complete idea of the research methods about how to study the control strategy, taking the adaptability and possibility of failure of electric vehicle control strategy into consideration. Finally, suggestions on the key areas for future research are put up.

  11. The control of radioactivity in the working environment in the factories for production of phosphate fertilizers

    International Nuclear Information System (INIS)

    Ajdacic, B.N.; Gnjatovic, S.S.; Vujovic, P.V.

    1980-01-01

    The results of dosimetric control in factories for the production of phosphoric acid and phosphate fertilizers in Serbia, and of the measurement of the total beta radioactivity of samples collected in these factories, are presented. An increase in the radiation dose, even up to 1000 times background, has been found at certain places in the plant. These results serve as a basis for conclusions on the existence, variation and collection of the radioactive component in particular phases of the technological process for the production of phosphate fertilizers. An attempt is made on the basis of the results obtained in three plants to evaluate the degree of danger in the working environment and in the area surrounding the factories and to propose protective measures. (Author)

  12. Current profile control and magnetohydrodynamic stability in Tore Supra discharges with edge-plasma control by the ergodic divertor

    International Nuclear Information System (INIS)

    Zabiego, M.; Friant, C.; Ghendrih, P.; Becoulet, M.; Bucalossi, J.; Saint-Laurent, F.

    1999-01-01

    Although ergodic divertors are primarily designed to control particle and heat fluxes at the plasma edge, they also happen to affect the MHD stability of tokamak discharges. On Tore Supra, the ergodic divertor has long been known to stabilize the m/n=2/1 tearing mode induced, for instance, by edge radiation and detachment processes, thus allowing safe high-current and high-density operations. More recently, though, in discharges where ergodic divertor operations were optimised relative to the control of the edge-plasma (i.e., with large divertor perturbation), a detrimental increase in the disruptiveness has been observed. The action that the ergodic divertor has on the MHD activity is interpreted in terms of a redistribution of the current profile. The latter results from a large increase in the edge resistivity, primarily induced by the degradation of the electron energy confinement in the ergodic layer. The possibility that a transport barrier develops in the vicinity of the separatrix strongly affects the considered modelling. (authors)

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

    International Nuclear Information System (INIS)

    Evseev, V.F.

    2012-01-01

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

  14. Regulatory control of radiation sources and radioactive materials in the Czech Republic

    International Nuclear Information System (INIS)

    Drabova, D.; Prouza, Z.

    2001-01-01

    The paper describes legal and regulatory provisions for radiation protection and safe use of sources of ionizing radiation in the Czech Republic with special emphasis on aspects of bringing activities under regulatory control and releasing them from it. It covers the development of a new legal framework, the work of the regulatory body, an overview of sources in use and provisions to achieve effective regulatory control of facilities and releases of radioactive material into the environment. Also, it describes reported unusual events with a proposed scheme for their classification and evaluation. (author)

  15. Ventilation of radioactive enclosures

    International Nuclear Information System (INIS)

    Caminade, F.; Laurent, H.

    1957-01-01

    Mechanical, physical and chemical manipulations on radioactive products must be carried out in properly ventilated enclosed places. The air extracted can only be discharged into the atmosphere after a correct filtration. The power of the ventilation systems is a function of the dimensions and purpose of the enclosure? The choice of types of filter is determined by the physical state and chemical nature of the radioactive materials to be manipulated. This study deals with the individual equipment of small installations: glove boxes, manipulation boxes with outside control and, if necessary, production chambers (maximum useful volume: 5 m 3 ). The performances of three types of 'ventilators', and the modifications provided by the addition of filters, are measured and compared. (author) [fr

  16. Securing a robust electrical discharge drilling process by means of flow rate control

    Science.gov (United States)

    Risto, Matthias; Munz, Markus; Haas, Ruediger; Abdolahi, Ali

    2017-10-01

    This paper deals with the increase of the process robustness while drilling cemented carbide using electrical discharge machining (EDM). A demand for high efficiency in the resulting diameter is equivalent with a high robustness of the EDM drilling process. Analysis were done to investigate the process robustness (standard deviation of the borehole diameter) when drilling cemented carbide. The investigation has shown that the dielectric flow rate changes over the drilling process. In this case the flow rate decreased with a shorter tool electrode due to an uneven wear of the tool electrode's cross section. Using a controlled flow rate during the drilling process has led to a reduced standard deviation of the borehole diameter, thus to a higher process robustness when drilling cemented carbide.

  17. Treatment of Radioactive Gaseous Waste

    International Nuclear Information System (INIS)

    2014-07-01

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

  18. Extended plasma channels created by UV laser in air and their application to control electric discharges

    International Nuclear Information System (INIS)

    Zvorykin, V. D.; Ionin, A. A.; Levchenko, A. O.; Seleznev, L. V.; Sinitsyn, D. V.; Smetanin, I. V.; Ustinovskii, N. N.; Shutov, A. V.

    2015-01-01

    Results are presented from a series of experimental and theoretical studies on creating weakly ionized extended plasma channels in atmospheric air by 248-nm UV laser radiation and their application to control long high-voltage discharges. The main mechanisms of air ionization by UV laser pulses with durations from 100 fs to 25 ns and intensities in the ranges of 3×10 11 –1.5×10 13 and 3×10 6 –3×10 11 W/cm 2 , respectively, which are below the threshold for optical gas breakdown, as well as the main relaxation processes in plasma with a density of 10 9 –10 17 cm −3 , are considered. It is shown that plasma channels in air can be efficiently created by amplitude-modulated UV pulses consisting of a train of subpicosecond pulses producing primary photoelectrons and a long UV pulse suppressing electron attachment and sustaining the density of free electrons in plasma. Different modes of the generation and amplification of trains of subterawatt subpicosecond pulses and amplitude-modulated UV pulses with an energy of several tens of joules were implemented on the GARPUN-MTW hybrid Ti:sapphire-KrF laser facility. The filamentation of such UV laser beams during their propagation in air over distances of up to 100 m and the parameters of the corresponding plasma channels were studied experimentally and theoretically. Laser initiation of high-voltage electric discharges and control of their trajectories by means of amplitude-modulated UV pulses, as well as the spatiotemporal structure of breakdowns in air gaps with length of up to 80 cm, were studied

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

    International Nuclear Information System (INIS)

    Lovjagina, Irina; Graveris, Visvaldis

    2008-01-01

    Full text: Taking into account Latvia geographical location, historical core stones (the dissolution of Soviet Union, join to European Community) and increasing of the international terrorism treats, control fissile and non-fissile radioactive material become one of high priorities. During past 2 years active work and practical exercise with representative from Ministry of Defense, Police, and Custom etc. on control of trafficking of such materials were performed and Operational Manual for Control on Radioactive Materials for Customs and Policy officers is issued. All land borders check points with Russian Federation and Byelorussian, all harbors and airports were equipped with a gamma/ neutrons or gamma control portals. To control unwanted material traffic within the country, as well as to ensure the recycled scrap metal is source-free use of monitoring portals and additional portable detectors in the past years strictly increased. Cases with alarm levels, when gamma dose rate exceeds more than 1.5 times the background level, are subject to reporting and analyzing by Radiation Safety Centre (RDC) experts (24 hours on duty). Consultative phone service for inhabitants is maintained; guidelines and working procedures within Authority and other Institutions involving were developed and implemented. As a result, in 2007 RDC has got 612 reports from the border. In 83% cases this was relevant to the trains, in 17%- to the trucks. Mostly enhanced activity was due to potassium compounds in fertilizers (85%), due to ceramics (4%), abrasives (2.5%), and refractory materials (3%). Controlling scrap metal there were revealed two sources in 2007 - one Sr-90 calibration source and other Cs-137 orphan source (origin unknown). The presence of radioactive sources in scrap in the past 3 years has been represented by Co-60, Cs-137 and Sr-90 sources, parts of statically electricity neutralizers, Ra-226. Several times NORM industries polluted materials were from scrap excluded

  20. Full Tokamak discharge simulation and kinetic plasma profile control for ITER

    International Nuclear Information System (INIS)

    Hee Kim, S.

    2009-10-01

    Understanding non-linearly coupled physics between plasma transport and free-boundary equilibrium evolution is essential to operating future tokamak devices, such as ITER and DEMO, in the advanced tokamak operation regimes. To study the non-linearly coupled physics, we need a simulation tool which can self-consistently calculate all the main plasma physics, taking the operational constraints into account. As the main part of this thesis work, we have developed a full tokamak discharge simulator by combining a non-linear free-boundary plasma equilibrium evolution code, DINA-CH, and an advanced transport modelling code, CRONOS. This tokamak discharge simulator has been used to study the feasibility of ITER operation scenarios and several specific issues related to ITER operation. In parallel, DINA-CH has been used to study free-boundary physics questions, such as the magnetic triggering of edge localized modes (ELMs) and plasma dynamic response to disturbances. One of the very challenging tasks in ITER, the active control of kinetic plasma profiles, has also been studied. In the part devoted to free-boundary tokamak discharge simulations, we have studied dynamic responses of the free-boundary plasma equilibrium to either external voltage perturbations or internal plasma disturbances using DINA-CH. Firstly, the opposite plasma behaviour observed in the magnetic triggering of ELMs between TCV and ASDEX Upgrade has been investigated. Both plasmas experience similar local flux surface expansions near the upper G-coil set and passive stabilization loop (PSL) when the ELMs are triggered, due to the presence of the PSLs located inside the vacuum vessel of ASDEX Upgrade. Secondly, plasma dynamic responses to strong disturbances anticipated in ITER are examined to study the capability of the feedback control system in rejecting the disturbances. Specified uncontrolled ELMs were controllable with the feedback control systems. However, the specifications for fast H-L mode

  1. Control of Reactive Species Generated by Low-frequency Biased Nanosecond Pulse Discharge in Atmospheric Pressure Plasma Effluent

    Science.gov (United States)

    Takashima, Keisuke; Kaneko, Toshiro

    2016-09-01

    The control of hydroxyl radical and the other gas phase species generation in the ejected gas through air plasma (air plasma effluent) has been experimentally studied, which is a key to extend the range of plasma treatment. Nanosecond pulse discharge is known to produce high reduced electric field (E/N) discharge that leads to efficient generation of the reactive species than conventional low frequency discharge, while the charge-voltage cycle in the low frequency discharge is known to be well-controlled. In this study, the nanosecond pulse discharge biased with AC low frequency high voltage is used to take advantages of these discharges, which allows us to modulate the reactive species composition in the air plasma effluent. The utilization of the gas-liquid interface and the liquid phase chemical reactions between the modulated long-lived reactive species delivered from the air plasma effluent could realize efficient liquid phase chemical reactions leading to short-lived reactive species production far from the air plasma, which is crucial for some plasma agricultural applications.

  2. Measures to detect and control radioactive contaminated metallurgical scrap at border checkpoints in Poland

    International Nuclear Information System (INIS)

    Smagala, G.

    1999-01-01

    The issue of radioactive contaminated metallurgical scrap has never received a high priority in Poland and in the international community. Since the dissolution of the former Soviet Union a higher attention has been given to the problem. Poland which is located between the West and East Europe has the obligation to develop and implement an effective prevention and detection system. The reasons to increase national control and detection system at the border checkpoints in Poland are to avoid the following risks: post Chernobyl contamination transports of commodities; transport of contaminated metal scrap; transfer of radioactive waste for their disposal or utilization; high risk of becoming a transit country of illicit trafficking of nuclear materials and radioactive sources. In order to avoid the above-mentioned risks, Poland initiated in 1990, a deployment of the portable radiation devices at the border checkpoints and, as of 1998, the number of installed instruments exceeded a hundred. This paper presents Poland's activities to detect contaminated scrap at its border checkpoints. (author)

  3. Management and control of radioactive wastes from uranium-milling operations

    International Nuclear Information System (INIS)

    Kennedy, R.H.; Deal, L.J.; Haywood, F.F.; Goldsmith, W.A.

    1977-01-01

    Of the 39 privately owned mills that produced and sold uranium to the U.S. Government during 1948 to 1971, 22 have closed down either due to exhaustion of reserves or lack of market. On the inactive mill sites there remains 24 million metric tons of tailings containing 14,000 curies of radium. Success in stabilization has been variable. In the past, theoretical models have had to be used in estimation of the environmental effects of uranium milling for lack of a sufficient factual base. ERDA in cooperation with the Environmental Protection Agency and the states involved is undertaking a comprehensive radiological assessment at each site. The results of this assessment should provide valuable basic information on the environmental impact of uranium ore processing. The current studies reveal that the inactive sites are a cause of small public exposure to radiation, primarily from radon-222 from the tailings piles. This paper reviews radioactivity management in uranium ore processing to control spread of radioactive materials, including methods used for stabilization to prevent wind and water erosion. Recent measurements of radioactivity levels in soils, ground and surface waters, and in air near tailings piles are summarized, and public health implications are evaluated. Guidelines have been developed for land decontamination, and procedures evaluated for long-term management of contaminated material to minimize future human exposure. Alternative methods for long-term tailings stabilization, their costs and benefits in terms of serious health effects avoided are presented

  4. Land cover controls on summer discharge and runoff solution chemistry of semi-arid urban catchments

    Science.gov (United States)

    Gallo, Erika L.; Brooks, Paul D.; Lohse, Kathleen A.; McLain, Jean E. T.

    2013-04-01

    SummaryRecharge of urban runoff to groundwater as a stormwater management practice has gained importance in semi-arid regions where water resources are scarce and urban centers are growing. Despite this trend, the importance of land cover in controlling semi-arid catchment runoff quantity and quality remains unclear. Here we address the question: How do land cover characteristics control the amount and quality of storm runoff in semi-arid urban catchments? We monitored summertime runoff quantity and quality from five catchments dominated by distinct urban land uses: low, medium, and high density residential, mixed use, and commercial. Increasing urban land cover increased runoff duration and the likelihood that a rainfall event would result in runoff, but did not increase the time to peak discharge of episodic runoff. The effect of urban land cover on hydrologic responses was tightly coupled to the magnitude of rainfall. At distinct rainfall thresholds, roads, percent impervious cover and the stormwater drainage network controlled runoff frequency, runoff depth and runoff ratios. Contrary to initial expectations, runoff quality did not vary in repose to impervious cover or land use. We identified four major mechanisms controlling runoff quality: (1) variable solute sourcing due to land use heterogeneity and above ground catchment connectivity; (2) the spatial extent of pervious and biogeochemically active areas; (3) the efficiency of overland flow and runoff mobilization; and (4) solute flushing and dilution. Our study highlights the importance of the stormwater drainage systems characteristics in controlling urban runoff quantity and quality; and suggests that enhanced wetting and in-stream processes may control solute sourcing and retention. Finally, we suggest that the characteristics of the stormwater drainage system should be integrated into stormwater management approaches.

  5. Calculation of the inventory and near-field release rates of radioactivity from neutron-activated metal parts discharged from the high flux isotope reactor and emplaced in solid waste storage area 6 at Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Kelmers, A.D.; Hightower, J.R.

    1987-05-01

    Emplacement of contaminated reactor components involves disposal in lined and unlined auger holes in soil above the water table. The radionuclide inventory of disposed components was calculated. Information on the composition and weight of the components, as well as reasonable assumptions for the neutron flux fueling use, the time of neutron exposure, and radioactive decay after discharge, were employed in the inventory calculation. Near-field release rates of /sup 152/Eu, /sup 154/Eu, and /sup 155/Eu from control plates and cylinders were calculated for 50 years after emplacement. Release rates of the europium isotopes were uncertain. Two release-rate-limiting models were considered and a range of reasonable values were assumed for the time-to-failure of the auger-hole linear and aluminum cladding and europium solubility in SWSA-6 groundwater. The bounding europium radionuclide near-field release rates peaked at about 1.3 Ci/year total for /sup 152,154,155/Eu in 1987 for the lower bound, and at about 420 Ci/year in 1992 for the upper bound. The near-field release rates of /sup 55/Fe, /sup 59/Ni, /sup 60/Co, and /sup 63/Ni from stainless steel and cobalt alloy components, as well as of /sup 10/Be, /sup 41/Ca, and /sup 55/Fe from beryllium reflectors, were calculated for the next 100 years, assuming bulk waste corrosion was the release-rate-limiting step. Under the most conservative assumptions for the reflectors, the current (1986) total radionuclide release rate was calculated to be about 1.2 x 10/sup -4/ Ci/year, decreasing by 1992 to a steady release of about 1.5 x 10/sup -5/ Ci/year due primarily to /sup 41/Ca. 50 refs., 13 figs., 8 tabs.

  6. The experience of Russian Federation in organization of customs control of fissionable and other radioactive materials

    International Nuclear Information System (INIS)

    Podchishaev, A.

    2001-01-01

    Among the routine inspection tasks of customs offices are tasks stemming from international commitments of Russia to prevent proliferation of nuclear weapons and material that can be used for making these weapons. These tasks are: radiation monitoring of all vehicles, passengers, their luggage and goods crossing the state border; inspection of fissionable and radioactive materials (FRM) legally transported by participants in the foreign trade activities with a view to checking that the declared data fully correspond to the actual radioactive cargo. Organizational measures involve the Sheremetyevo customs office has a department whose personnel is specially trained in radiation monitoring and can operate radiometric and spectrometric instruments. These specialists are included in shifts on duty responsible for customs clearing and inspection and carry out continuous radiation monitoring of passengers and their luggage, vehicles and goods crossing the border. They work on the 24-hour basis, which allows quickly and skillfully localizing the detected radiation source and avoiding direct contact of customs, officers, airport personnel, and passengers with the radioactive item. Technical measures include provision and everyday use of radiation monitoring instrumentation, classified as: stationary equipment of primary radiation monitoring (SEPRM); hand-held instruments for additional radiation monitoring (RM); spectrometric equipment for control of legal FRM transport. The customs procedure for monitoring of fissionable and radioactive materials is divided into three stages. Stage I, primary RM is carried out by stationary FRM detection systems Yantar for customs applications installed on the customs inspection line next to the X-ray inspection equipment (XIE). Stage II, additional RM is carried out by officer who uses hand-held instruments to check the passenger's luggage for surface contamination; to perform primary identification of the detected radioactive source

  7. General fundamentals of calculation for determining the radiation exposure due to radioactive discharge into surface waters. I. Flowing waters. Allgemeine Berechnungsgrundlagen fuer die Bestimmung der Strahlenexposition durch radioaktive Einleitungen in Oberflaechengewaesser. T. 1. Fliessgewaesser

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    The paper describes a mathematical model for estimating the internal radiation exposure via different exposure pathways through radioactive discharges from nuclear facilities (paragraph 45, rad. prot. law) into rivers. The connections between the compartments of an ecological system are shown in their main types. Not all exposure pathways described are relevant for all cases; the experts have to carry out the evaluation using their knowledge of the local circumstances. The model is only valid for running waters above the tidal limit with the plant operating according to the rules.

  8. Radioactive Control of Krsko Nuclear Power Plant Environment in the Year 1997

    International Nuclear Information System (INIS)

    Lulic, S.; Miklavzic, U.; Franic, Z.; Kanduc, M.

    1998-01-01

    Regular Krsko Nuclear Power Plant (NPPK) radioactivity control comprises the supervisions of the inventory of liquid and gaseous emissions at the source, and the independent supervisions of the input of radionuclides into larger environment (imisson). The controlled environment area consists primarily of a 12 kilometers large circle around the object, where the largest values of imission could be expected, and where possible changes in the Sava river and the underground waters could first be noticed. The circle has been enlarged upon the territory of the Republic of Croatia (RC) from Jesenice on Dolenjsko until Podsused (30 km of air - line distance). As reference points relevant for the readiness in the case of accident, especially for detection of iodine and aerosol air transport, the program comprises also measuring points in the RC at larger distances (from 14 to 27 km) in the direction of Zagreb its larger western surroundings (passive Thermoluminescent (TL) dosimeters in the each 42 km long). Continuous control of emission is performed by the radiological service of KNPP by routine procedures, supplemented by adequate measurements from other authorized institutions (intercomparisons, parallel measurements of representative and other samples). Summarised results of radioactive measurements for man-made and natural radionuclides are presented for different transfer media and exposure pathways in the form of assessed effective doses. Conservatively estimated dose burdens received by a member of the reference (critical) population group as the result of NPP emissions amount to a value of the committed effective dose equivalent smaller than 20 μSv/year. This value represents less than 1 % of the annual dose received on average from natural and artificial sources by a member of the general public in the normal environment. The yearly doses from natural radioactivity, global contamination (Chernobyl, atmospheric nuclear explosions), non-nuclear industries and

  9. Radioactive control of Krsko Nuclear Power Plant in the year 1995

    International Nuclear Information System (INIS)

    Lulic, S.; Miklavzic, U.; Franic, Z.; Kanduc, M.

    1996-01-01

    Regular Krsko Nuclear Power Plant (NPPK) radioactivity control comprises the supervisions of the inventory of liquid and gaseous emissions at the source, and the independent supervisions of the input of radionuclides into larger environment. The controlled environment area consist primarily of a 12 kilometers large circle around the object, where the largest values of immission could be expected, and where possible changes in the Sava river and the underground waters could first be noticed. The circle has been enlarged upon the territory of the Republic of Croatia (RC) from Jesenice on Dolenjsko until Podsused (30 km of air-line distance). As reference points relevant for the readiness in the case of accident, especially for detection of iodine and aerosol air transport, the program comprises also measuring points in the RC at larger distances (from 14 to 27 km) in the direction of Zagreb its larger western surroundings (passive Thermoluminescent (TL) dosimeters in each 42 km long). Continuous of control of emission is performed by the radiological service of (KNPP) by routine procedures, supplemented by adequate measurements from other authorized institutions. Summarized results of radioactive measurements for man-made and natural radionuclides are presented for different transfer media and exposure pathways in the form of assessed effective doses. Conservatively estimated dose burdens received by a member of the reference (critical) population group as the result of NPP emissions amount to a value of the committed effective dose equivalent smaller than 20 μSv/year. This value represents less than 1% of the annual dose received on average from natural and artificial sources by a member of the general public in the normal environment. The yearly doses from natural radioactivity, global contamination , non-nuclear industries and hospitals are also estimated from the measured data in some media. (author)

  10. The Influence of Relative Humidity on Dielectric Barrier Discharge Plasma Flow Control Actuator Performance

    Science.gov (United States)

    Wicks, M.; Thomas, F. O.; Corke, T. C.; Patel, M.

    2012-11-01

    Dielectric barrier discharge (DBD) plasma actuators possess numerous advantages for flow control applications and have been the focus of several previous studies. Most work has been performed in relatively pristine laboratory settings. In actual flow control applications, however, it is essential to assess the impact of various environmental influences on actuator performance. As a first effort toward assessing a broad range of environmental effects on DBD actuator performance, the influence of relative humidity (RH) is considered. Actuator performance is quantified by force balance measurements of reactive thrust while RH is systematically varied via an ultrasonic humidifier. The DBD plasma actuator assembly, force balance, and ultrasonic humidifier are all contained inside a large, closed test chamber instrumented with RH and temperature sensors in order to accurately estimate the average RH at the actuator. Measurements of DBD actuator thrust as a function of RH for several different applied voltage regimes and dielectric materials and thicknesses are presented. Based on these results, several important design recommendations are made. This work was supported by Innovative Technology Applications Company (ITAC), LLC under a Small Business Innovation Research (SBIR) Phase II Contract No. N00014-11-C-0267 issued by the U.S. Department of the Navy.

  11. Regulatory control and safety of radiation and radioactive sources in Bangladesh

    International Nuclear Information System (INIS)

    Mollah, A.S.

    2001-01-01

    The application of ionizing radiation and radioactive sources in different fields such as, medicine, industry, agriculture, research and teaching is constantly increasing in Bangladesh. Any system enacted to control exposure to ionizing radiation has as primary objective the protection of health of people against the deleterious effects of radiation. Establishing the appropriate level of radiological protection and safety of radiation sources used in practice or intervention attains this objective. The regulatory program governing the safe use of radioactive and radiation sources in Bangladesh is based on the legislation enacted as Nuclear Safety and Radiation Control (NSRC) Act-93 and NSRC Rules-97 and its implementation by the competent authority. The radiation control infrastructures and procedure are described as well as their functioning for the implementation of relevant activities such as licensing, regular inspection, personal dose monitoring, emergency preparedness, etc. The issue of security of radiation source is dealt in close relation with the preparation and use of the inventory of all radiation sources in the country

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

    International Nuclear Information System (INIS)

    Drews, P.; Fuchs, K.

    1990-01-01

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

  13. Radioactive waste problems in Russia

    International Nuclear Information System (INIS)

    Bridges, O.; Bridges, J.W.

    1995-01-01

    The collapse of the former Soviet Union, with the consequent shift to a market driven economy and demilitarisation, has had a profound effect on the nuclear and associated industries. The introduction of tighter legislation to control the disposal of radioactive wastes has been delayed and the power and willingness of the various government bodies responsible for its regulation is in doubt. Previously secret information is becoming more accessible and it is apparent that substantial areas of Russian land and surface waters are contaminated with radioactive material. The main sources of radioactive pollution in Russia are similar to those in many western countries. The existing atomic power stations already face problems in the storage and safe disposal of their wastes. These arise because of limited on site capacity for storage and the paucity of waste processing facilities. Many Russian military nuclear facilities also have had a sequence of problems with their radioactive wastes. Attempts to ameliorate the impacts of discharges to important water sources have had variable success. Some of the procedures used have been technically unsound. The Russian navy has traditionally dealt with virtually all of its radioactive wastes by disposal to sea. Many areas of the Barents, Kola and the Sea of Japan are heavily contaminated. To deal with radioactive wastes 34 large and 257 small disposal sites are available. However, the controls at these sites are often inadequate and illegal dumps of radioactive waste abound. Substantial funding will be required to introduce the necessary technologies to achieve acceptable standards for the storage and disposal of radioactive wastes in Russia. (author)

  14. Effectiveness of post-discharge case management in general-medical outpatients: a randomized, controlled trial

    NARCIS (Netherlands)

    Latour, Corine H. M.; de Vos, Rien; Huyse, Frits J.; de Jonge, Peter; van Gemert, Liesbeth A. M.; Stalman, Wim A. B.

    2006-01-01

    This study was initiated to determine the impact of post-discharge, nurse-led, home-based case management intervention on the number of emergency readmissions, level of care utilization, quality of life, and psychological functioning. Patients discharged home from a general hospital (N=147) were

  15. Effectiveness of post-discharge case management in general-medical outpatients: A randomized, controlled trial

    NARCIS (Netherlands)

    Latour-Delfgaauw, C.H.M.; Vos, R.; Huyse, F.J.; de Jonge, P.; van Gemert, L.A.M.; Stalman, W.A.B.

    2006-01-01

    This study was initiated to determine the impact of post-discharge, nurse-led, home-based case management intervention on the number of emergency readmissions, level of care utilization, quality of life, and psychological functioning. Patients discharged home from a general hospital (N=147) were

  16. Effectiveness of post-discharge case management in general-medical outpatients: A randomized, controlled trial

    NARCIS (Netherlands)

    Latour, C.H.M.; de Vos, R.; Huyse, F.J.; De Jonge, P.; van Gemert, L.A.M.; Stalman, W.A.B.

    2006-01-01

    This study was initiated to determine the impact of post- discharge, nurse- led, home- based case management intervention on the number of emergency readmissions, level of care utilization, quality of life, and psychological functioning. Patients discharged home from a general hospital (N = 147)

  17. Effectiveness of post-discharge case management in general-medical outpatients : A randomized, controlled trial

    NARCIS (Netherlands)

    Latour, Corine H. M.; de Vos, Rien; Huyse, Frits J.; de Jonge, Peter; van Gemert, Liesbeth A. M.; Stalman, Wim A. B.

    2006-01-01

    This study was initiated to determine the impact of post- discharge, nurse- led, home- based case management intervention on the number of emergency readmissions, level of care utilization, quality of life, and psychological functioning. Patients discharged home from a general hospital (N = 147)

  18. AUTOMATIC CONTROL SYSTEM OF THE DIFFERENCE BETWEEN DISCHARGE AND SUCTION PRESSURES OF THE HEAT PUMP STATION COMPRESSOR

    Directory of Open Access Journals (Sweden)

    Sit M.L.

    2009-04-01

    Full Text Available Possibility of realization is shown and the control system of a difference of pressure between an exit and an input of the compressor of the heat pump on carbon dioxide working at variable thermal load, and discharge and suction pressures by means of two control valves connected in series is developed. On an example a flow coefficient calculation procedure of control valves is shown.

  19. Controlling corrosion rate of Magnesium alloy using powder mixed electrical discharge machining

    Science.gov (United States)

    Razak, M. A.; Rani, A. M. A.; Saad, N. M.; Littlefair, G.; Aliyu, A. A.

    2018-04-01

    Biomedical implant can be divided into permanent and temporary employment. The duration of a temporary implant applied to children and adult is different due to different bone healing rate among the children and adult. Magnesium and its alloys are compatible for the biodegradable implanting application. Nevertheless, it is difficult to control the degradation rate of magnesium alloy to suit the application on both the children and adult. Powder mixed electrical discharge machining (PM-EDM) method, a modified EDM process, has high capability to improve the EDM process efficiency and machined surface quality. The objective of this paper is to establish a formula to control the degradation rate of magnesium alloy using the PM-EDM method. The different corrosion rate of machined surface is hypothesized to be obtained by having different combinations of PM-EDM operation inputs. PM-EDM experiments are conducted using an opened-loop PM-EDM system and the in-vitro corrosion tests are carried out on the machined surface of each specimen. There are four operation inputs investigated in this study which are zinc powder concentration, peak current, pulse on-time and pulse off-time. The results indicate that zinc powder concentration is significantly affecting the response with 2 g/l of zinc powder concentration obtaining the lowest corrosion rate. The high localized temperature at the cutting zone in spark erosion process causes some of the zinc particles get deposited on the machined surface, hence improving the surface characteristics. The suspended zinc particles in the dielectric fluid have also improve the sparking efficiency and the uniformity of sparks distribution. From the statistical analysis, a formula was developed to control the corrosion rate of magnesium alloy within the range from 0.000183 mm/year to 0.001528 mm/year.

  20. Numerical simulation of the manual operation of the charging/discharging machine (MID) control desk

    International Nuclear Information System (INIS)

    Doca, C; Dobre, A

    2004-01-01

    Since the year 2000 at 7th Division TAR of Institute for Nuclear Research - Pitesti continuous efforts were made to implement a software product package devoted to numerical simulation of operations at the test bench of charging/discharging machine (MID). Till now there were specified, designed, worked out and implemented on a computer the PUPITRU code, the present version fulfilling the following requirements: - graphical output specific for the computer/human operator interface: - design at a 1 : 4 scale for each of the 25 drawers of the control desk; - graphical and functional simulation of all the physical objects mounted in these drawers, namely: 12 measuring analog instruments with linear and non-linear dials (ampermeters), 21 measuring digital instruments (voltmeters), 24 two up/down settings switches, 13 switches with three up/down settings, 23 switches with two left/right hand settings, one switch with three left/right hand settings, one switch with four left/right hand settings, 2 switches with five left/right hand settings, 68, 16, 23, 53, 81 signaling lamps of white, yellow, orange, red and green light, respectively; implementation in the frame of PUPITRU code of the main notations used in the automation schemes in the execution design of the control desk, in view of a quick identification of the physical objects: switches, lamps, instruments, etc. ; - implementation in the frame of PUPITRU code of the full database (mnemonics and numerical values) used in the frame of MID tests; - implementation of over 1000 equations of numerical simulation appropriate to the situations characteristic for test bench and MID operation. At the moment, the final functional simulation for all the control desk components is finalized. In this paper a description and a demonstration run of the PUPITRU code is presented. (authors)

  1. Drainage of radioactive areas

    International Nuclear Information System (INIS)

    1981-04-01

    This Code of Practice covers all the drainage systems which may occur in the radioactive classified area of an establishment, namely surface water, foul, process and radioactive drainage. It also deals with final discharge lines. The Code of Practice concentrates on those aspects of drainage which require particular attention because the systems are in or from radioactive areas and typical illustrations are given in appendices. The Code makes references to sources of information on conventional aspects of drainage design. (author)

  2. The Periodic Measurement of the Airborne Radioactivity In Controlled Area of KOMAC

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jeong-Min; Park, Sung-Kyun; Min, Yi-Sub; Cho, Yong-Sub [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Korea Multipurpose Accelerator Complex (KOMAC) to start the performance operation in the second half of 2013, is currently operated in each beamline 20-MeV and 100-MeV. The accelerator operation period is simply divided by three operation cycles which are the maintenance checks period for accelerator device, the performance test period before driving accelerator and the operation period. During this operation period, beam is irradiated to target. At this time, the proton beams collide with the target material and a high dose of radiations such as gamma ray and neutron occurred. Radiation controlled area at the accelerator facility is divided into accelerator tunnel and beam utilization zone. As a result of measuring the airborne radioactivity in the controlled area in accordance with the operating cycle of the proton accelerator KOMAC, It was confirmed that the value of the airborne radioactivity does not significantly differ according to each accelerator operating cycles. And alpha and beta values measured inside the area that workers primarily work is very low indoor radon level than the value of the recommendations in multiple facilities.

  3. Project of an information integrated system to provide support to the regulatory control of the radioactive waste inventory

    International Nuclear Information System (INIS)

    Christovao, Marilia Tavares

    2005-05-01

    Sources and radioactive waste deriving from industry activities, medical practice and other areas are collected, received, and stored as waste on Brazilian Nuclear Energy Commission (CNEN) Institutes, that also generate, treat and store their own radioactive waste. The object of this project is to present an Integrated Information System named SICORR, having as guidelines, the referred processes to the radioactive waste regulatory control, under the responsibility of the Radioactive Waste Division (DIREJ), the General Coordination of Licensing and Control (CGLC), the Directorate of Safety and Radiation Protection (DRS) and the CNEN. The main objective of the work was reached, once the project SICORR modeling considers the radioactive waste control inventory, enclosing the treatment and integration of the radioactive waste and the radionuclides data and processes; the installations that produce, use, transport or store radiation sources data; and, CNEN Institutes responsible for the radioactive waste management data. The SICORR functions or essential modules involve the data treatment, integration, standardization and consistency between the processes. The SICORR specification and the analysis results are registered in documents, Software Specification Proposal (PESw) and Software Requirements Specification (ERSw), and are presented in text, in diagrams and user interfaces. Use cases have been used in the SICORR context diagram. The user interfaces for each use case have been detailed, defining the graphical layout, the relationships description with other interfaces, the interface details properties and the commands and the product entrances and exits. For objects radioactive waste and radionuclides, states diagrams have been drawn. The activities diagram represents the business model process. The class diagram represents the static objects and relationships that exist between them, under the specification point of view. The class diagram have been determined

  4. Hybrid radiation background monitoring in operational control and forecasting of environmental contamination by nuclear power station discharges

    International Nuclear Information System (INIS)

    Ermeev, I.S.; Eremenko, V.A.; Makarov, Y.A.; Matueev, V.V.; Zhernov, V.S.

    1986-01-01

    Rapid developments in nuclear power have stimulated research on monitoring and forecasting environmental radiation pollution (ERP), and in particular the amounts, compositions, and distributions of radionuclides in the environment. A conceptual model is presented for hybrid environmental radiation pollution monitoring. When there is an emergency, the model operates in a fashion most closely corresponding to the actual meteorological conditions, and the ERP data given by the model enable one to distinguish changes due to the man-made component from random fluctuations in the natural background. The measurement system in general includes mobile and stationary data-acquisition facilities linked by wire or radio to the central point. The system also accumulates and stores data on the radiation environment, which are edited on the basis of radioactive, chemical, and other transformations. The purpose of hybrid monitoring is ultimately to analyze trends in order to detect elevated discharges and thus to output data to the regional monitoring system

  5. Control of stationary crossflow modes in swept Hiemenz flows with dielectric barrier discharge plasma actuators

    Science.gov (United States)

    Wang, Zhefu; Wang, Liang; Fu, Song

    2017-09-01

    Sensitivity analyses and non-linear parabolized stability equations are solved to provide a computational assessment of the potential use of a Dielectric Barrier Discharge (DBD) plasma actuator for a prolonging laminar region in swept Hiemenz flow. The derivative of the kinetic energy with respect to the body force is deduced, and its components in different directions are defined as sensitivity functions. The results of sensitivity analyses and non-linear parabolized stability equations both indicate that the introduction of a body force as the plasma actuator at the bottom of a crossflow vortex can mitigate instability to delay flow transition. In addition, the actuator is more effective when placed more upstream until the neutral point. In fact, if the actuator is sufficiently close to the neutral point, it is likely to act as a strong disturbance over-riding the natural disturbance and dominating transition. Different operating voltages of the DBD actuators are tested, resulting in an optimal practice for transition delay. The results demonstrate that plasma actuators offer great potential for transition control.

  6. Potential of turbidity monitoring for real time control of pollutant discharge in sewers during rainfall events.

    Science.gov (United States)

    Lacour, C; Joannis, C; Gromaire, M-C; Chebbo, G

    2009-01-01

    Turbidity sensors can be used to continuously monitor the evolution of pollutant mass discharge. For two sites within the Paris combined sewer system, continuous turbidity, conductivity and flow data were recorded at one-minute time intervals over a one-year period. This paper is intended to highlight the variability in turbidity dynamics during wet weather. For each storm event, turbidity response aspects were analysed through different classifications. The correlation between classification and common parameters, such as the antecedent dry weather period, total event volume per impervious hectare and both the mean and maximum hydraulic flow for each event, was also studied. Moreover, the dynamics of flow and turbidity signals were compared at the event scale. No simple relation between turbidity responses, hydraulic flow dynamics and the chosen parameters was derived from this effort. Knowledge of turbidity dynamics could therefore potentially improve wet weather management, especially when using pollution-based real-time control (P-RTC) since turbidity contains information not included in hydraulic flow dynamics and not readily predictable from such dynamics.

  7. Contamination due to radioactive materials

    International Nuclear Information System (INIS)

    Woodhead, D.S.

    1984-01-01

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

  8. The pacemaker role of thalamic reticular nucleus in controlling spike-wave discharges and spindles

    Science.gov (United States)

    Fan, Denggui; Liao, Fucheng; Wang, Qingyun

    2017-07-01

    Absence epilepsy, characterized by 2-4 Hz spike-wave discharges (SWDs), can be caused by pathological interactions within the thalamocortical system. Cortical spindling oscillations are also demonstrated to involve the oscillatory thalamocortical rhythms generated by the synaptic circuitry of the thalamus and cortex. This implies that SWDs and spindling oscillations can share the common thalamocortical mechanism. Additionally, the thalamic reticular nucleus (RE) is hypothesized to regulate the onsets and propagations of both the epileptic SWDs and sleep spindles. Based on the proposed single-compartment thalamocortical neural field model, we firstly investigate the stimulation effect of RE on the initiations, terminations, and transitions of SWDs. It is shown that the activations and deactivations of RE triggered by single-pulse stimuli can drive the cortical subsystem to behave as the experimentally observed onsets and self-abatements of SWDs, as well as the transitions from 2-spike and wave discharges (2-SWDs) to SWDs. In particular, with increasing inhibition from RE to the specific relay nucleus (TC), rich transition behaviors in cortex can be obtained through the upstream projection path, RE → TC → Cortex . Although some of the complex dynamical patterns can be expected from the earlier single compartment thalamocortical model, the effect of brain network topology on the emergence of SWDs and spindles, as well as the transitions between them, has not been fully investigated. We thereby develop a spatially extended 3-compartment coupled network model with open-/closed-end connective configurations, to investigate the spatiotemporal effect of RE on the SWDs and spindles. Results show that the degrees of activations of RE 1 can induce the rich spatiotemporal evolution properties including the propagations from SWDs to spindles within different compartments and the transitions between them, through the RE 1 → TC 1 → Cortex 1 and Cortex 1 → Cortex 2

  9. The pacemaker role of thalamic reticular nucleus in controlling spike-wave discharges and spindles.

    Science.gov (United States)

    Fan, Denggui; Liao, Fucheng; Wang, Qingyun

    2017-07-01

    Absence epilepsy, characterized by 2-4 Hz spike-wave discharges (SWDs), can be caused by pathological interactions within the thalamocortical system. Cortical spindling oscillations are also demonstrated to involve the oscillatory thalamocortical rhythms generated by the synaptic circuitry of the thalamus and cortex. This implies that SWDs and spindling oscillations can share the common thalamocortical mechanism. Additionally, the thalamic reticular nucleus (RE) is hypothesized to regulate the onsets and propagations of both the epileptic SWDs and sleep spindles. Based on the proposed single-compartment thalamocortical neural field model, we firstly investigate the stimulation effect of RE on the initiations, terminations, and transitions of SWDs. It is shown that the activations and deactivations of RE triggered by single-pulse stimuli can drive the cortical subsystem to behave as the experimentally observed onsets and self-abatements of SWDs, as well as the transitions from 2-spike and wave discharges (2-SWDs) to SWDs. In particular, with increasing inhibition from RE to the specific relay nucleus (TC), rich transition behaviors in cortex can be obtained through the upstream projection path, RE→TC→Cortex. Although some of the complex dynamical patterns can be expected from the earlier single compartment thalamocortical model, the effect of brain network topology on the emergence of SWDs and spindles, as well as the transitions between them, has not been fully investigated. We thereby develop a spatially extended 3-compartment coupled network model with open-/closed-end connective configurations, to investigate the spatiotemporal effect of RE on the SWDs and spindles. Results show that the degrees of activations of RE 1 can induce the rich spatiotemporal evolution properties including the propagations from SWDs to spindles within different compartments and the transitions between them, through the RE 1 →TC 1 →Cortex 1 and Cortex 1 →Cortex 2 →Cortex 3

  10. Handling of radioactive sources in Ecuador

    International Nuclear Information System (INIS)

    Benitez, Manuel

    2000-01-01

    This document describes the following aspects: sealed and unsealed radioactive sources, radiation detectors, personnel and area monitoring, surface pollution, radioactive wastes control and radioactive sources transferring. (The author)

  11. Eighteenth annual report of: The Radioactive Waste Management Advisory Committee

    International Nuclear Information System (INIS)

    1998-07-01

    This annual report reviews the RWMAC's work programme and progress made in 1997-1998; discusses operational and administrative matters including financial management and policy review; and presents the 1998 RWMAC work programme. Particular chapters are devoted to the management of intermediate and high level radioactive waste and spent fuel; the Dounreay Nuclear Establishment; the radioactive waste discharge authorisations. The document presents the RWMAC's review of the Ministry of Defence's radioactive waste management practices. A separate chapter is devoted to the study of radioactive waste management practices in Spain. Annexes to the report include terms of reference and membership of the Radioactive Waste Management Advisory Committee; RWMAC financial statement; declaration and register of member's interests; the RWMAC's 1998 work programme; the RWMAC's response to the Government on Proposals for the control and remediation of radioactively contaminated land

  12. Initial demonstration of DWPF process and product control strategy using actual radioactive waste

    International Nuclear Information System (INIS)

    Andrews, M.K.; Bibler, N.E.; Jantzen, C.M.; Beam, D.C.

    1991-01-01

    The Defense Waste Processing Facility at the Savannah River Site (SRS) will vitrify high-level nuclear waste into borosilicate glass. The waste will be mixed with properly formulated glass-making frit and fed to a melter at 1150 degrees C. Process control and product quality are ensured by proper control of the melter feed composition. Algorithms have been developed to predict the processability of the melt and the durability of the final glass based on this feed composition. To test these algorithms, an actual radioactive waste contained in a shielded facility at SRS was analyzed and a frit composition formulated using a simple computer spreadsheet which contained the algorithms. This frit was then mixed with the waste and the resulting slurry fed to a research scale joule-heated melter operated remotely. Approximately 24 kg of glass were successfully prepared. This paper will describe the frit formulation, the vitrification process, and the glass durability

  13. Pancreatitis - discharge

    Science.gov (United States)

    Chronic pancreatitis - discharge; Pancreatitis - chronic - discharge; Pancreatic insufficiency - discharge; Acute pancreatitis - discharge ... You were in the hospital because you have pancreatitis. This is a swelling of the pancreas. You ...

  14. Fisheries Radiobiology and the Discharge of Radioactive Wastes; Radiobiologie des Pecheries et Evacuation des Dechets Radioactifs; 041f 0420 0418 014 ; Radiobiologia de las Pesquerias y Evacuacion de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Morgan, F. [Fisheries Radiobiological Laboratory, Ministry of Agriculture, Fisheries and Food (United Kingdom)

    1960-07-01

    In the United Kingdom authorizations to discharge radioactive wastes are granted by the Minister of Housing and Local Government, the Minister of Agriculture, Fisheries and Food, and by the Secretary of State for Scotland. The hazards arising from contamination of aquatic animals and plants concern the Department of Fisheries ; before authorizations to discharge liquid wastes have been given, the Department has made independent forecasts of permissible levels of discharge based on extensive studies carried out in its research vessels and radiobiological laboratory: for example, where fish have been affected this has meant studies of fish populations and fish migration: uptake of radioactivity by fish : public consumption of fish : commercial distribution of affected fish: L.D.{sub 50}: effects of radiation on tissue, etc. In the course of such work there has been close consultation with the Atomic Energy Authority, and agreement with the Atomic Energy Authority about the safety factor to be incorporated during the first two years of discharge. During these two years, monitoring data collected by the Atomic Energy Authority and the Ministry of Agriculture, Fisheries and Food enable checks and revisions of the original estimates to be made, and at the end of that time formal authorizations, based on operating experience, are issued. (author) [French] Au Royaume-Uni, les autorisations d'evacuer des dechets radioactifs sont accordees par le Ministre du logement et de l'administration locale, par le Ministre de l'agriculture, des pecheries et de l'alimentation et par le Secretaire d'Etat pour l'Ecosse. Les risques dus a la contamination des animaux et des plantes aquatiques relevent du Departement des pecheries; avant d'accorder des autorisations d'evacuer des dechets liquides, le Departement a evalue lui-meme les quantites dont l'evacuation pourrait etre admise, en se fondant sur des etudes approfondies qui sont faites dans ses bateaux de recherche et son laboratoire

  15. The Effects of Urbanization and Flood Control on Sediment Discharge of a Southern California River, Evidence of a Dilution Effect

    Science.gov (United States)

    Warrick, J. A.; Orzech, K. M.; Rubin, D. M.

    2004-12-01

    The southern California landscape has undergone dramatic urbanization and population growth during the past 60 years and currently supports almost 20 million inhabitants. During this time, rivers of the region have been altered with damming, channel straightening and hardening, and water transfer engineering. These changes have drastically altered water and sediment discharge from most of the region's drainage basins. Here we focus on changes in sediment discharge from the largest watershed of southern California, the Santa Ana River. Order-of-magnitude drops in the suspended sediment rating curves (the relationship between suspended sediment concentration and instantaneous river discharge) are observed between 1967 and 2001, long after the construction of a major flood control dam in 1941. These sediment concentration decreases do not, however, represent alteration of the total sediment flux from the basin (a common interpretation of sediment rating curves), but rather a dilution of suspended sediment by increases (approx. 4x) in stormwater discharge associated with urbanization. Increases in peak and total stormwater discharge are consistent with runoff patterns from urbanizing landscapes, supporting our hypothesis that the diluting water originated from stormwater runoff generated in urban areas both up- and downstream of dams. Our dilution hypothesis is further supported with water and sediment budgets, dilution calculations, and suspended and bed grain size information.

  16. Controlling the level of radioactivity of cigarettes sold in Kinshasa: Case Tumbaco light and Embassy

    International Nuclear Information System (INIS)

    Woto, M.L.; Lukanda, M.V.; Mulumba, L.C.P.; Musibondo-Eyul'Anki, D.; Kabangu, Y.; Disila, L.A.; Dizono, Z.R.B.

    2009-01-01

    At the anti-smoking, which continues to grow now in the world with positive results on the chemical vectors: tar and nicotine, as we know the harm in North America and Europe, nowadays, radioactivity is added. This second vector radiation-induced lung cancer, radon is hazardous and radioactive daughters 210P b and 210P o that Big Tobacco had hid the truth for 40 years. The surgeon C. Everett Ko op, a pioneer of Modern Pediatrics (Philadelphia, USA) showed that the radioactivity found in many tobacco 210P o, and that rather than derivatives of tar and nicotine, account for 90% of all lung cancers of smokers recounted. These assertions have prompted the current authors to control the level of alpha and beta radioactivity in cigarettes Tumbaco Embassy and light manufactured by Tabac Congo. These products are commonly consumed in the Democratic Republic of the Congo, particularly in the city of Kinshasa. Following this study, we present quantitative data related to lead the health authorities of the Democratic Republic of Congo to take necessary measures or to enact laws prohibiting smoking in public places and for monitoring production these cigarettes. Thus, the mean mass activities for gross alpha and beta measured for the cigarette lighter Tumbaco and Embassy appear respectively as follows: 11.32Bq/kg and 7.08Bq/kg for alpha cons 38.34Bq/kg and 29.5Bq/kg (Table 10). In addition, the estimated average effective dose for an annual consumption of cigarettes one pack per year worth 0.0726 mSv/ year (0.05 mSv/ hour) and light Tumbaco 0.04574 mSv/ year (0.02μSv/hour) for Embassy. These values are lower than the hourly limit or permissible annual dose for members of the public (or 1mSv/an 0.5μSv/hour) following radiation protection standards of the international Commission on Radiological Protection (ICRP 60, 1990). This means that these dose rates are below the threshold for non-stochastic effects, and these limits do not apply to stochastic or random effects (Tables

  17. Controlled study of the evolution of radon and its decay products in radioactive mine environments

    International Nuclear Information System (INIS)

    Calizaya A, F.

    1985-01-01

    This thesis discusses three aspects related to radon emissions and control of radon decay products in mine environments: (1) measurement of the effects of environmental parameters on radiation levels, (2) analysis of the data using ordinary linear regression and transfer function models and (3) prediction of the concentration of radioactive contaminants in the mine air. In-mine and laboratory experiments were conducted to develop the research data. In mine tests were conducted in a bulkhead isolated mine drift containing low grade uranium ore at the Colorado School of Mines, Experimental Mine with the US Bureau of Mines - Spokane Research Center (USBM, SRC) micro-computer based radiation monitoring system. Parameters such as amount of ore, amount of condensation nuclei in the mine air, temperature, air velocity, and barometric pressure were studied. The laboratory tests were conducted in an air-tight radon chamber equipped with a container of the radioactive material, various monitors, and the USBM, SRC Data Acquisition System. The effect of parameters such as ore grade, particle size, rock moisture, air temperature and relative humidity on radon concentrations were measured in the laboratory. Radiation levels, together with parameters affecting these levels, were measured over a period of one year (June 1984-July 1985) both in the laboratory model and in the field

  18. Radioactivity measuring and control method and the system for facility of nuclear power plant

    International Nuclear Information System (INIS)

    Urata, Megumu.

    1996-01-01

    In measurement and control for radioactivity in an inspection operation in radiation circumstance for nuclear power plant facilities, radioactive materials in air are sometimes suspended together with ordinary dusts. Then, when a radiation level is low, light is applied to the suspended dusts to measure the quantity and the number of the dusts thereby estimating the radiation level based on the amount of the dusts. Then, the level of the equipments is informed to an operator based on the estimated value, and an operation time is determined. Since the optical dust monitor is inexpensive, a number of dust monitors can be brought into an operation chamber. In addition, they are reduced in the size and the weight, an operator can carry and bring them into the operation chamber. A distribution of dusts can be determined by measuring the concentration of dusts using a plurality of dust monitors thereby enabling to improve safety and economical property of periodical inspection for nuclear power plant facilities. (T.M.)

  19. Radioactivity measuring and control method and the system for facility of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Urata, Megumu

    1996-12-03

    In measurement and control for radioactivity in an inspection operation in radiation circumstance for nuclear power plant facilities, radioactive materials in air are sometimes suspended together with ordinary dusts. Then, when a radiation level is low, light is applied to the suspended dusts to measure the quantity and the number of the dusts thereby estimating the radiation level based on the amount of the dusts. Then, the level of the equipments is informed to an operator based on the estimated value, and an operation time is determined. Since the optical dust monitor is inexpensive, a number of dust monitors can be brought into an operation chamber. In addition, they are reduced in the size and the weight, an operator can carry and bring them into the operation chamber. A distribution of dusts can be determined by measuring the concentration of dusts using a plurality of dust monitors thereby enabling to improve safety and economical property of periodical inspection for nuclear power plant facilities. (T.M.)

  20. Environmental radiation control and quality management system in design and operation of sealed radioactive sources

    International Nuclear Information System (INIS)

    Hussein, A.Z.

    2007-01-01

    New environmental regulations and radiation safety standards are being implemented almost daily to ensure radiation safety, in particular for practices causing exposures to undue radiation doses. A particular emphasis of real challenge for organizations and users of radiation sources has to be for proper radiological safety assessment and is becoming cost effectively to be prepared for auditing. Special concern for the environment is of global . nature, and hence environmental auditing has been and will continue to be an essential practice for improving the environment and for meeting the relevant regulations and standards. In general, most facilities that deal with radioactive sources undertake strict safety measures in terms of personnel radiation protection, handling procedures and security. Hence, those measures should comply with the requirements of the environmental protection standards. Accordingly, a successful quality management system must balance realities of organization and personnel in achieving quality objectives. Organizational principles are found in the technical aspects of' quality management, such as, charting, requirements, measurements, procedures, ... , etc. Human principles are found in the communication side of quality management (e.g. meetings, ,decision making, ,teams, ... , etc). The quality management must understand and balance skills needed to blend them together. Large gamma irradiators present a high potential radiation hazard to the surrounding environment, since the amount of radioactivity is of the order of (P Bq) and a very high dose rates are produced during irradiation. Application of environmental radiation control deemed by regulatory authority and a proper quality management system by the utility would serve public health and safety

  1. Heart pacemaker - discharge

    Science.gov (United States)

    Cardiac pacemaker implantation - discharge; Artificial pacemaker - discharge; Permanent pacemaker - discharge; Internal pacemaker - discharge; Cardiac resynchronization therapy - discharge; CRT - discharge; ...

  2. Criteria of exemption of regulatory control for radioactive material; Criterios de exencion del control regulatorio para material radiactivo

    Energy Technology Data Exchange (ETDEWEB)

    Medrano Lopez, Marco A [Gerencia de Seguridad Radiologica, Instituto Nacional de Investigaciones Nucleares, Salazar (Mexico)

    1991-07-01

    Being based on the information contained in the 10 CFR Part 20, of the section 20.301 until the 20.306 where the mechanisms by means of which can prepare the waste of low level are indicated. While the Nuclear Regulatory Commission (NRC) it amended in the year of 1985 the Act of Politics on Low level Wastes, in particular the section 10 of the amendment of the Act, relative to the concept BRC treats those groups of radioactive waste in that their activity contents are so low that they could be exempt of the regulatory control, either liberating them toward the environment or to exempt people or organizations of the regulatory control.

  3. Advanced Off-Gas Control System Design For Radioactive And Mixed Waste Treatment

    International Nuclear Information System (INIS)

    Nick Soelberg

    2005-01-01

    Treatment of radioactive and mixed wastes is often required to destroy or immobilize hazardous constituents, reduce waste volume, and convert the waste to a form suitable for final disposal. These kinds of treatments usually evolve off-gas. Air emission regulations have become increasingly stringent in recent years. Mixed waste thermal treatment in the United States is now generally regulated under the Hazardous Waste Combustor (HWC) Maximum Achievable Control Technology (MACT) standards. These standards impose unprecedented requirements for operation, monitoring and control, and emissions control. Off-gas control technologies and system designs that were satisfactorily proven in mixed waste operation prior to the implementation of new regulatory standards are in some cases no longer suitable in new mixed waste treatment system designs. Some mixed waste treatment facilities have been shut down rather than have excessively restrictive feed rate limits or facility upgrades to comply with the new standards. New mixed waste treatment facilities in the U. S. are being designed to operate in compliance with the HWC MACT standards. Activities have been underway for the past 10 years at the INL and elsewhere to identify, develop, demonstrate, and design technologies for enabling HWC MACT compliance for mixed waste treatment facilities. Some specific off-gas control technologies and system designs have been identified and tested to show that even the stringent HWC MACT standards can be met, while minimizing treatment facility size and cost

  4. Topological structures of vortex flow on a flying wing aircraft, controlled by a nanosecond pulse discharge plasma actuator

    Science.gov (United States)

    Du, Hai; Shi, Zhiwei; Cheng, Keming; Wei, Dechen; Li, Zheng; Zhou, Danjie; He, Haibo; Yao, Junkai; He, Chengjun

    2016-06-01

    Vortex control is a thriving research area, particularly in relation to flying wing or delta wing aircraft. This paper presents the topological structures of vortex flow on a flying wing aircraft controlled by a nanosecond plasma dielectric barrier discharge actuator. Experiments, including oil flow visualization and two-dimensional particle image velocimetry (PIV), were conducted in a wind tunnel with a Reynolds number of 0.5 × 106. Both oil and PIV results show that the vortex can be controlled. Oil topological structures on the aircraft surface coincide with spatial PIV flow structures. Both indicate vortex convergence and enhancement when the plasma discharge is switched on, leading to a reduced region of separated flow.

  5. Radioactive waste packages stored at the Aube facility for low-intermediate activity wastes. A selective and controlled storage

    International Nuclear Information System (INIS)

    2005-01-01

    The waste package is the first barrier designed to protect the man and the environment from the radioactivity contained in wastes. Its design is thus particularly stringent and controlled. This brochure describes the different types of packages for low to intermediate activity wastes like those received and stored at the Aube facility, and also the system implemented by the ANDRA (the French national agency of radioactive wastes) and by waste producers to safely control each step of the design and fabrication of these packages. (J.S.)

  6. Measurement of Gamma Radioactivity in a Group of Control Subjects from the Stockholm Area During 1959-1963

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, I Oe; Nilsson, I; Eckerstig, K

    1963-08-15

    Repeated measurements of the gamma radioactivity in a group of control subjects have been made since June 1959, using a whole body counter scintillation spectrometer. The body contents of cesium-137 and potassium-40 and their trends with time have been determined. The cesium-137 values have been compared with the results from measurements of the fallout rate of cesium-137 and the concentration of cesium-137 in milk. The control group study was carried out to obtain information about the gamma radioactivity situation in the general population. Such an investigation is necessary if one wants to measure occupational contamination at low levels.

  7. Quality control in the analysis of radioactivity from the oil exploration sector

    International Nuclear Information System (INIS)

    Landsberger, Sheldon; Morton, Jacob; Yoho, Michael

    2016-01-01

    The presence of 226 Ra, 228 Ra and 210 Pb in the production of oil is now a well-known phenomenon. An effort has been undertaken to establish quality control procedures and to produce an in-house reference material. Scale build-up has a significant amount of iron, barium and strontium and as such self-attenuation of photons, especially the 46.5 keV photon from 210 Pb can significantly underestimate the radioactivity concentration. A procedure was developed to prepare an in-house standard using only a 20-g sample of scale obtained from west Texas. An evaluation of the homogeneity, counting procedures and determination of the self-attenuation factors are presented. (author)

  8. Gas generation in deep radioactive waste repositories: a review of processes, controls and models

    International Nuclear Information System (INIS)

    Jones, M.A.

    1990-10-01

    Gas generation within radioactive waste repositories may produce two general problems: 1) breaching of engineered and natural barriers due to high gas pressures; 2) enhanced radiological risk due to reduced groundwater travel times and/or greater aqueous or gaseous activities reaching the biosphere. As a result of these concerns, HMIP must be aware of the current status of relevant research, together with any associated deficiencies. This report addresses the current status of published research on near-field gas generation from worldwide sources and documents the important gas generating processes, the factors controlling them and models available to simulate them. In the absence of suitable models, outline technical specifications for corrosion and microbial degradation gas generation models are defined and the deficiencies in the current understanding of gas generation are highlighted; a conceptual research programme to correct these deficiencies is presented. (author)

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

    International Nuclear Information System (INIS)

    Iwata, Ren; Yamazaki, Shigeki

    1990-01-01

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

  10. Radioactivity and wildlife

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  11. Prototype of Remote Controlled Robot Vehicle to Scan Radioactive Contaminated Areas

    International Nuclear Information System (INIS)

    Ratongasoandrazana, J.B.; Raoelina Andriambololona; Rambolamanana, G.; Andrianiaina, H.; Rajaobelison, J.

    2016-01-01

    The ionizing radiations are not directly audible by the organs of sense of the human being. Maintenance and handling of sources of such ionizing radiations present some risks of very serious and often irreversible accident for human organism. The works of experimentation and maintenance in such zone also present the risks requiring some minimum of precaution. Thus, the main objective of this work is to design and develop (hard- and software) a prototype of educational semi-autonomous Radio Frequency controlled robot-vehicle based on 8-bit AVR-RISC Flash microcontroller system (ATmega128L) able to detect, identify and map the radioactive contaminated area. An integrated video camera coupled with a UHF video transmitter module, placed in front of the robot, will be used as visual feedback control to well direct it toward a precise place to reach. The navigation information and the data collected are transmitted from the robot toward the Computer via 02 Radio Frequency Transceivers for peer-to-peer serial data transfer in half-duplex mode. A Joystick module which is connected to the Computer parallel port allows full motion control of the platform. Robot-vehicle user interface program for the PC has been designed to allow full control of all functions of the robot vehicles.

  12. Direct continuous multichannel γspectrometric measurements- one of the main methods for control and study of radioactive environmental pollution

    International Nuclear Information System (INIS)

    Khitrov, L.M.; Rumiantsev, O.V.

    1991-01-01

    In Chernobyl along with usual methods of environment radiation control there were used methods and equipment of direct continuous multichannel measurements. The necessary equipment was installed both on permanent observation stations (river Pripyat, Chernobyl, river Dnieper, Kiev) and on mobile units (helicopters, scientific river-boats, automobiles). Together with continuous control of radioactive situation and its estimation in time and space this equipment enabled to carry out the following: - determination of time-spatial structure of radioactive pollution in stationary points and on space (mapping); - selection of representative samples for subsequent radionuclide analysis; - direct data input into the computer, data storage and data base creation. The results and conclusions drawn are important not only for the situation on Chernobyl atomic station - they may and should be used for a continuous radioactive monitoring of the environment. Though the method and its realization remain to be modernized and unified. (author)

  13. Enhancing DC Glow Discharge Tube Museuum Displays using a Theremin Controlled Helmholtz Coil to Demonstrate Magnetic Confinement

    Science.gov (United States)

    Siu, Theodore; Wissel, Stephanie; Guttadora, Larry; Liao, Susan; Zwicker, Andrew

    2010-11-01

    Since their discovery in the mid 1800's, DC glow discharge apparatuses have commonly been used for spectral analysis, the demonstration of the Frank-Hertz experiment, and to study plasma breakdown voltages following from the Paschen Curve. A DC glow discharge tube museum display was outfitted with a Helmholtz Coil electromagnet in order to demonstrate magnetic confinement for a science museum display. A device commonly known as a ``theremin'' was designed and built in order to externally control the Helmholtz Coil current and the plasma current. Originally a musical instrument, a theremin has two variable capacitors connected to two radio frequency oscillators which determine pitch and volume. Using a theremin to control current and ``play'' the plasma adds appeal and durability by providing a new innovative means of interacting with a museum exhibit. Educationally, students can use the display to not only learn about plasma properties but also electronic properties of the human body.

  14. Heart attack - discharge

    Science.gov (United States)

    ... and lifestyle Cholesterol - drug treatment Controlling your high blood pressure Deep vein thrombosis - discharge Dietary fats explained Fast food tips Heart attack - discharge Heart attack - what to ask your doctor Heart bypass ... pacemaker - discharge High blood pressure - what to ask your doctor How to read ...

  15. Electron-induced dry reforming of methane in a temperature-controlled dielectric barrier discharge reactor

    KAUST Repository

    Zhang, Xuming; Cha, Min

    2013-01-01

    and thermo-chemistry in dry reforming of methane. In the tested background temperature range 297-773 K, electron-induced chemistry, as characterized by the physical properties of micro-discharges, was found to govern the conversions of CH4 and CO2, while

  16. Radioactivity in surface and coastal waters of the British Isles, 1980

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1982-01-01

    Results are presented for an environmental monitoring programme performed during 1980 by the Fisheries Radiobiological Loaboratory. The programme was set up to verify the satisfactory control of liquid radioactive waste discharges from UK nuclear establishments to the aquatic environment. The results showed that all exposures were well within the ICRP-recommended limit for members of the public. Discharges from BNFL's Sellafield Site gave rise to the highest exposures. The collective effective dose equivalent to the UK population from liquid radioactive discharges in 1980 was 100 man-Sv, a reduction from 130 man-Sv reported for 1979. (U.K.)

  17. Control of the surface radioactive contamination in the field of biological research; Control de la contaminacion radiactiva superficial en el ambito de la investigacion biologica

    Energy Technology Data Exchange (ETDEWEB)

    Calvo, S.; Encina, A. de la; Gaspar, J.; Macias, M. T.; Sanchez, A.; Usera, F.

    2012-11-01

    The manipulation of unsealed sources in biomedical research involves significant risk of radioactive contamination. the aim of this study has been to analyze the radioactive contamination occurring in the field of biomedical research, assessing its magnitude, identifying the equipment that can be contaminated with higher probability and monitoring the evolution of the contaminations production taking into account the radioisotopes and the activities uses, and the radiation protection control applied. The data used for this study correspond to a very lengthy period of time and it have been collected in the radioactive facility, of the Centro Nacional de Biotecnologia (CSIC), a very large biological research centre that can be used perfectly as a reference for this area. The results obtained show a gradual and significant decrease in the incidence of the radioactive contamination. This is due to the optimization of radiation protection standards applied and the implementation or a systematic operational radiation protection program. (Author) 13 refs.

  18. 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)

  19. Studies of environmental radioactivity in Cumbria. Part 6. The chronology of discharges of caesium-137, plutonium and americium-241 from BNFL Sellafield, as recorded in lake sediments

    Energy Technology Data Exchange (ETDEWEB)

    Eakins, J D; Cambray, R S

    1985-04-01

    A study has been made of the radionuclide content of lake sediments from Cumbria in order to determine the history of discharges of /sup 137/Cs and actinides from the Sellafield works of British Nuclear Fuels plc (BNFL). Sediment cores have been taken from Ullswater and Grasmere, which are remote from Sellafield, in order to establish the behaviour of nuclear weapon fallout nuclides. Cores have also been taken from Barfield Tarn, which is 19 km SE of Sellafield but close to the sea, and from Ponsonby and Harnsey Moss Tarns, close to Sellafield. All sediments were analysed for /sup 137/Cs and sup(239+240)Pu. Additional measurements of /sup 238/Pu and /sup 241/Am were made on samples from the closer tarns. The sediment cores were dated by the /sup 210/Pb method and, where appropriate, by the /sup 137/Cs technique also. The amounts of /sup 137/Cs and sup(239+240)Pu in sediments from Barfield Tarn could be accounted for by fallout from nuclear weapons, although the levels of /sup 241/Am were marginally greater. However in Harnsey Moss Tarn the levels of actinides indicated that they were derived mainly from material originally discharged to sea from Sellafield. Sediment from Ponsonby Tarn contained material derived mainly from discharges to atmosphere.

  20. Nuclear Security Systems and Measures for the Detection of Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide

    International Nuclear Information System (INIS)

    2013-01-01

    Nuclear terrorism and the illicit trafficking of nuclear and other radioactive material threaten the security of all States. There are large quantities of diverse radioactive material in existence, which are used in areas such as health, the environment, agriculture and industry. The possibility that nuclear and other radioactive material may be used for terrorist acts cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material, and to establish capabilities for detection and response to nuclear and other radioactive material out of regulatory control. Through its nuclear security programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This approach recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in nuclear and other radioactive material; national response plans; and contingency measures. Within its nuclear security programme, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. Each State carries the full responsibility for nuclear security, specifically: to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; to combat illicit trafficking; and to detect and respond to nuclear security events. This is an Implementing Guide on nuclear security systems and measures for the detection of nuclear and other radioactive material out of regulatory control. The objective of the publication is to provide guidance to Member States for the

  1. Radioactive gas storage device

    International Nuclear Information System (INIS)

    Seki, Eiji; Kobayashi, Yoshihiro.

    1989-01-01

    The present invention concerns a device of ionizing radioactive gases to be processed in gaseous nuclear fission products in nuclear fuel reprocessing plants, etc., and injecting them into metal substrates for storage. The device comprises a vessel for a tightly closed type outer electrode in which gases to be processed are introduced, an electrode disposed to the inside of the vessel and the target material, a high DC voltage power source for applying high voltage to the electrodes, etc. There are disposed a first electric discharging portion for preparting discharge plasma for ion injection of different electrode distance and a second electric discharging portion for causing stable discharge between the vessel and the electrode. The first electric discharging portion for the ion injection provides an electrode distance suitable to acceleration sputtering and the second electric discharging portion is used for stable discharge. Accordingly, if the gas pressure in the radioactive gas storage device is reduced by the external disturbance, etc., since the second electric discharging portion satisfies the electric discharging conditions, the device can continue electric discharge. (K.M.)

  2. Disposal of radioactive wastes from Czechoslovak nuclear power plants

    International Nuclear Information System (INIS)

    Neumann, L.

    In gaseous radioactive waste disposal, aerosol particles are filtered and gaseous wastes are discharged in the environment. The filters and filter materials used are stored on solid radioactive waste storage sites in the individual power plants. Liquid radioactive wastes are concentrated and the concentrates are stored. Distillates and low-level radioactive waste water are discharged into the hydrosphere. Solid radioactive wastes are stored without treatment in power plant bunkers. Bituminization and cementation of liquid radioactive wastes are discussed. (H.S.)

  3. Nipple Discharge

    Science.gov (United States)

    ... any unexpected nipple discharge evaluated by a doctor. Nipple discharge in men under any circumstances could be a problem and needs further evaluation. One or both breasts may produce a nipple discharge, either spontaneously or when you squeeze your ...

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

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  5. Customs control over the transportation of radiation sources and radioactive materials through the frontier of the Republic of Belarus

    International Nuclear Information System (INIS)

    Derevyashko, A.

    1998-01-01

    1. As it is shown in the name the main purpose of this Paper is to describe system of customs control over transportation of radiation sources and radioactive materials through the frontier of the Republic of Belarus, clarifying herewith influence of global situation on the creation of this system and noting technical needs of Customs Administration of Belarus in its activities aimed at strengthening the control system. 2. The Republic of Belarus has not the enterprises of atomic-industrial complex and does not produce radioactive and nuclear materials, so, control over them is largely connected with their transit through frontiers of Belarus and its territory. It is necessary to note, that the frontier of Belarus with the Ukraine, Poland and Baltic States is an external frontier of a Custom Union between Belarus, Russia, Kazakhstan and Kirghizia. On the territory of the last three states are concentrated extraction and production of radioactive and nuclear materials, part of which can be transported by the shortest way to the European countries through the territory and frontiers of the Republic of Belarus. 3. The significant part of the republic territory suffered from Chernobyl catastrophe. In a number of the polluted regions of Belarus there were created the zones of >, the residing on them is prohibited by legislation. On those territories there were created numerous burial grounds for the conditionally radioactive and low radioactive wastes. In this connection, there is also a danger of illegal importation of various radioactive wastes from contiguous countries to these zones and burial them there. On the other hand, there are known the numerous cases of exportation of various materials, subjects, food from the polluted zones even out of Belarus. 4. Taking into account the aforesaid the Customs Administration of the Republic of Belarus as well as other public authorities, clearly recognizes the necessity of organization of an effective radiation control on

  6. Survival in Malnourished Older Patients Receiving Post-Discharge Nutritional Support; Long-Term Results of a Randomized Controlled Trial.

    Science.gov (United States)

    Neelemaat, F; van Keeken, S; Langius, J A E; de van der Schueren, M A E; Thijs, A; Bosmans, J E

    2017-01-01

    Previous analyses have shown that a post-discharge individualized nutritional intervention had positive effects on body weight, lean body mass, functional limitations and fall incidents in malnourished older patients. However, the impact of this intervention on survival has not yet been studied. The objective of this randomized controlled study was to examine the effect of a post-discharge individualized nutritional intervention on survival in malnourished older patients. Malnourished older patients, aged ≥ 60 years, were randomized during hospitalization to a three-months post-discharge nutritional intervention group (protein and energy enriched diet, oral nutritional supplements, vitamin D3/calcium supplement and telephone counseling by a dietitian) or to a usual care regimen (control group). Survival data were collected 4 years after enrollment. Survival analyses were performed using intention-to-treat analysis by Log-rank tests and Cox regression adjusted for confounders. The study population consisted of 94 men (45%) and 116 women with a mean age of 74.5 (SD 9.5) years. There were no statistically significant differences in baseline characteristics. Survival data was available in 208 out of 210 patients. After 1 and 4 years of follow-up, survival rates were respectively 66% and 29% in the intervention group (n=104) and 73% and 30% in the control group (n=104). There were no statistically significant differences in survival between the two groups 1 year (HR= 0.933, 95% CI=0.675-1.289) and 4 years after enrollment (HR=0.928, 95% CI=0.671-1.283). The current study failed to show an effect of a three-months post-discharge multi-component nutritional intervention in malnourished older patients on long-term survival, despite the positive effects on short-term outcome such as functional limitations and falls.

  7. Regulatory Initiatives for Control and Release of Technologically Enhanced Naturally-Occurring Radioactive Materials

    Energy Technology Data Exchange (ETDEWEB)

    Egidi, P.V.

    1999-03-02

    Current drafts of proposed standards and suggested State regulations for control and release of technologically-enhanced naturally-occurring radioactive material (TENORM), and standards for release of volumetrically-contaminated material in the US are reviewed. These are compared to the recommendations of the International Atomic Energy Association (IAEA) Safety Series and the European Commission (EC) proposals. Past regulatory efforts with respect to TENORM in the US dealt primarily with oil-field related wastes. Currently, nine states (AK, GA, LA, MS, NM, OH, OR SC, TX) have specific regulations pertaining to TENORM, mostly based on uranium mill tailings cleanup criteria. The new US proposals are dose- or risk-based, as are the IAEA and EC recommendations, and are grounded in the linear no threshold hypothesis (LNT). TENORM wastes involve extremely large volumes, particularly scrap metal and mine wastes. Costs to control and dispose of these wastes can be considerable. The current debate over the validity of LNT at low doses and low dose rates is particularly germane to this discussion. Most standards setting organizations and regulatory agencies base their recommendations on the LNT. The US Environmental Protection Agency has released a draft Federal Guidance Report that recommends calculating health risks from low-level exposure to radionuclides based on the LNT. However, some scientific and professional organizations are openly questioning the validity of LNT and its basis for regulations, practices, and costs to society in general. It is not clear at this time how a non-linear regulatory scheme would be implemented.

  8. IAEA Reference Materials for Quality Assurance: A Study in the Quality Control of Marine Radioactivity

    International Nuclear Information System (INIS)

    Pham Mai Khanh; Bartocci, J.; Gastaud, J.; Nies, H.; Vasileva, E.; Betti, M.; Chamizo, E.; Gomez-Guzman, J.-M.

    2013-01-01

    The IAEA's Marine Environment Laboratories has assisted laboratories in Analytical Quality Control Services (AQCS) for the analysis of radionuclides in the marine environment since the early seventies. The AQCS programme, now named Reference Products for Environment and Trade, is recognized as an essential component of quality assurance and control and for the development and validation of analytical methods, through its worldwide and regional interlaboratory comparisons and the provision of reference methods and Reference Materials/Certified Reference Materials (RMs/CRMs). A total of 49 interlaboratory exercises were organized and 42 RMs/CRMs were produced for marine radioactivity studies. Different techniques such as radiometric methods with X ray, gamma spectrometry, alpha spectrometry, beta counter, liquid scintillation counter as well as mass spectrometry (ICP-MS, AMS, TIMS) are applied for the characterization during certification process. An overview of prepared Certified Reference Materials (CRMs) for radionuclides in marine matrices will be presented as well as lessons learned from interlaboratory comparisons (ICs) and Proficiency Tests (PTs). A characterization of a new CRM for radionuclides in IAEA-446, Baltic Sea seaweed (Fucus vesiculosus), as well as a specific case of using Accelerator Mass Spectrometry (AMS) technique to characterize I-129 in sea water (IAEA-418) and seaweed sample (IAEA-446), will be discussed. Available RMs/CRMs are listed and can be ordered and purchased through the IAEA website http://nucleus.iaea.org/rpst/. (author)

  9. IAEA Reference Materials for Quality Assurance: A Study in the Quality Control of Marine Radioactivity

    Energy Technology Data Exchange (ETDEWEB)

    Khanh, Pham Mai; Bartocci, J.; Gastaud, J.; Nies, H.; Vasileva, E.; Betti, M. [International Atomic Energy Agency, Environment Laboratory (Monaco); Chamizo, E.; Gomez-Guzman, J. -M. [Centro Nacional de Aceleradores, Seville (Spain)

    2013-07-15

    The IAEA's Marine Environment Laboratories has assisted laboratories in Analytical Quality Control Services (AQCS) for the analysis of radionuclides in the marine environment since the early seventies. The AQCS programme, now named Reference Products for Environment and Trade, is recognized as an essential component of quality assurance and control and for the development and validation of analytical methods, through its worldwide and regional interlaboratory comparisons and the provision of reference methods and Reference Materials/Certified Reference Materials (RMs/CRMs). A total of 49 interlaboratory exercises were organized and 42 RMs/CRMs were produced for marine radioactivity studies. Different techniques such as radiometric methods with X ray, gamma spectrometry, alpha spectrometry, beta counter, liquid scintillation counter as well as mass spectrometry (ICP-MS, AMS, TIMS) are applied for the characterization during certification process. An overview of prepared Certified Reference Materials (CRMs) for radionuclides in marine matrices will be presented as well as lessons learned from interlaboratory comparisons (ICs) and Proficiency Tests (PTs). A characterization of a new CRM for radionuclides in IAEA-446, Baltic Sea seaweed (Fucus vesiculosus), as well as a specific case of using Accelerator Mass Spectrometry (AMS) technique to characterize I-129 in sea water (IAEA-418) and seaweed sample (IAEA-446), will be discussed. Available RMs/CRMs are listed and can be ordered and purchased through the IAEA website http://nucleus.iaea.org/rpst/. (author)

  10. Regulatory Initiatives for Control and Release of Technologically Enhanced Naturally-Occurring Radioactive Material

    International Nuclear Information System (INIS)

    Egidi, P.V.

    1999-01-01

    Current drafts of proposed standards and suggested State regulations for control and release of technologically-enhanced naturally-occurring radioactive material (TENORM), and standards for release of volumetrically-contaminated material in the US are reviewed. These are compared to the recommendations of the International Atomic Energy Association (IAEA) Safety Series and the European Commission (EC) proposals. Past regulatory efforts with respect to TENORM in the US dealt primarily with oil-field related wastes. Currently, nine states (AK, GA, LA, MS, NM, OH, OR SC, TX) have specific regulations pertaining to TENORM, mostly based on uranium mill tailings cleanup criteria. The new US proposals are dose- or risk-based, as are the IAEA and EC recommendations, and are grounded in the linear no threshold hypothesis (LNT). TENORM wastes involve extremely large volumes, particularly scrap metal and mine wastes. Costs to control and dispose of these wastes can be considerable. The current debate over the validity of LNT at low doses and low dose rates is particularly germane to this discussion. Most standards setting organizations and regulatory agencies base their recommendations on the LNT. The US Environmental Protection Agency has released a draft Federal Guidance Report that recommends calculating health risks from low-level exposure to radionuclides based on the LNT. However, some scientific and professional organizations are openly questioning the validity of LNT and its basis for regulations, practices, and costs to society in general. It is not clear at this time how a non-linear regulatory scheme would be implemented

  11. Potential of turbidity monitoring for real time control of pollutant discharge in sewers during rainfall events

    OpenAIRE

    LACOUR, Céline; JOANNIS, Claude; GROMAIRE, MC; CHEBBO, Ghassan

    2009-01-01

    Turbidity sensors can be used to continuously monitor the evolution of pollutant mass discharge. For two sites within the Paris combined sewer system, continuous turbidity, conductivity and flow data were recorded at one-minute time intervals over a one-year period. This paper is intended to highlight the variability in turbidity dynamics during wet weather. For each storm event, turbidity response aspects were analysed through different classifications. The correlation between classification...

  12. Effectiveness of pharmaceutical care at discharge in the emergency department: study protocol of a randomized controlled trial.

    Science.gov (United States)

    Kuhmmer, Regina; Lima, Karine Margarites; Ribeiro, Rodrigo Antonini; Hammes, Luciano Serpa; Bastos, Gisele Alsina Nader; Cotta de Souza, Maria Claudia Schardosim; Polanczyk, Carisi Anne; Soares Rollin, Guilherme Alcides Flores; Caon, Suhelen; Guterres, Cátia Moreira; Araújo Leite, Leni Everson; Delabary, Tássia Scholante; Falavigna, Maicon

    2015-02-25

    Patient education on pharmacological therapy may increase medication adherence and decrease hospitalizations. Our aim is to evaluate the effectiveness of pharmaceutical care at emergency department discharge in patients with hypertension and/or diabetes. This is a randomized controlled trial. Participants will be recruited from a public emergency department at Restinga district in Porto Alegre, southern Brazil. A total of 380 patients will be randomly assigned into 2 groups at the moment of emergency department discharge after receiving medical orientations: an intervention group, consisting of a structured individual counseling session by a pharmacist in addition to written orientations, or a control group, consisting only of written information about the disease. Outcomes will be assessed in an ambulatory visit 2 months after the randomization. The primary outcome is the proportion of patients with high medication adherence assessed using the Morisky-Green Test and the Brief Medication Questionnaire. The secondary outcomes are reduction of blood pressure, glycated hemoglobin, fasting plasma glucose, quality of life and number of visits to the emergency department. Pharmaceutical care interventions have shown to be feasible and effective in increasing medication adherence in both hospital outpatient and community pharmacy settings. However, there have been no previous assessments of the effectiveness of pharmacy care interventions initiated in patients discharged from emergency departments. Our hypothesis is that pharmaceutical counseling is also effective in this population. ClinicalTrials.gov registration number: NCT01978925 (11 November 2013) and Brazilian Registry of Clinical Trials U1111-1149-8922 (5 November 2013).

  13. Radioactivity in surface and coastal waters of the British Isles, 1986

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1987-01-01

    The report presents the results of the environmental monitoring programme carried out during 1986 by staff of the Directorate of Fisheries Research, Lowestoft, United Kingdom. The programme was set up to verify the satisfactory control of liquid radioactive waste discharges to the aquatic environment, and to ensure that the resulting public radiation exposure is within nationally-accepted limits. The environmental programme includes monitoring the environmental consequences of discharges of liquid radioactive wastes from four British Nuclear Fuels plc sites - at Sellafield, Springfield, Capenhurst and Chapelcross, and monitoring the environment impact of liquid radioactive discharges from Winfrith and Dounraey. Monitoring is also carried out near nuclear power stations operated by the electricity boards, near Naval establishments, near Amersham International plc, and the marine environment of the Channel Islands States. Results are also presented on the monitoring of the freshwater environment for radioactivity from the Chernobyl reactor accident. (U.K.)

  14. Process for separating radioactive gases

    International Nuclear Information System (INIS)

    Kimura, Shigeru; Awada, Yoshihisa.

    1976-01-01

    Object: To efficiently and safely separate and recover raw gases such as krypton which requires radioactive attenuation by a long term storage. Structure: A mixture of krypton and xenon is separated by liquefaction from raw gases at a first distillation column, using latent heat of liquid nitrogen. The krypton and xenon mixture separated by liquefaction at the first distillation column is separated into krypton and xenon, by controlling operation pressure of a second distillation column at about 3 - 5 atm., using sensible heat of low temperature nitrogen gas discharged from a top of the first distillation column and a condenser. (Aizawa, K.)

  15. Fate and transport processes controlling the migration of hazardous and radioactive materials from the Area 5 Radioactive Waste Management Site (RWMS)

    International Nuclear Information System (INIS)

    Estrella, R.

    1994-10-01

    Desert vadose zones have been considered as suitable environments for the safe and long-term isolation of hazardous wastes. Low precipitation, high evapotranspiration and thick unsaturated alluvial deposits commonly found in deserts make them attractive as waste disposal sites. The fate and transport of any contaminant in the subsurface is ultimately determined by the operating retention and transformation processes in the system and the end result of the interactions among them. Retention (sorption) and transformation are the two major processes that affect the amount of a contaminant present and available for transport. Retention processes do not affect the total amount of a contaminant in the soil system, but rather decrease or eliminate the amount available for transport at a given point in time. Sorption reactions retard the contaminant migration. Permanent binding of solute by the sorbent is also possible. These processes and their interactions are controlled by the nature of the hazardous waste, the properties of the porous media and the geochemical and environmental conditions (temperature, moisture and vegetation). The present study summarizes the available data and investigates the fate and transport processes that govern the migration of contaminants from the Radioactive Waste Management Site (RWMS) in Area 5 of the Nevada Test Site (NTS). While the site is currently used only for low-level radioactive waste disposal, past practices have included burial of material now considered hazardous. Fundamentals of chemical and biological transformation processes are discussed subsequently, followed by a discussion of relevant results

  16. Fate and transport processes controlling the migration of hazardous and radioactive materials from the Area 5 Radioactive Waste Management Site (RWMS)

    Energy Technology Data Exchange (ETDEWEB)

    Estrella, R.

    1994-10-01

    Desert vadose zones have been considered as suitable environments for the safe and long-term isolation of hazardous wastes. Low precipitation, high evapotranspiration and thick unsaturated alluvial deposits commonly found in deserts make them attractive as waste disposal sites. The fate and transport of any contaminant in the subsurface is ultimately determined by the operating retention and transformation processes in the system and the end result of the interactions among them. Retention (sorption) and transformation are the two major processes that affect the amount of a contaminant present and available for transport. Retention processes do not affect the total amount of a contaminant in the soil system, but rather decrease or eliminate the amount available for transport at a given point in time. Sorption reactions retard the contaminant migration. Permanent binding of solute by the sorbent is also possible. These processes and their interactions are controlled by the nature of the hazardous waste, the properties of the porous media and the geochemical and environmental conditions (temperature, moisture and vegetation). The present study summarizes the available data and investigates the fate and transport processes that govern the migration of contaminants from the Radioactive Waste Management Site (RWMS) in Area 5 of the Nevada Test Site (NTS). While the site is currently used only for low-level radioactive waste disposal, past practices have included burial of material now considered hazardous. Fundamentals of chemical and biological transformation processes are discussed subsequently, followed by a discussion of relevant results.

  17. Mozart K.448 listening decreased seizure recurrence and epileptiform discharges in children with first unprovoked seizures: a randomized controlled study.

    Science.gov (United States)

    Lin, Lung-Chang; Lee, Mei-Wen; Wei, Ruey-Chang; Mok, Hin-Kiu; Yang, Rei-Cheng

    2014-01-13

    Increasing numbers of reports show the beneficial effects of listening to Mozart music in decreasing epileptiform discharges as well as seizure frequency in epileptic children. There has been no effective method to reduce seizure recurrence after the first unprovoked seizure until now. In this study, we investigated the effect of listening to Mozart K.448 in reducing the seizure recurrence rate in children with first unprovoked seizures. Forty-eight children who experienced their first unprovoked seizure with epileptiform discharges were included in the study. They were randomly placed into treatment (n = 24) and control (n = 24) groups. Children in the treatment group listened to Mozart K.448 daily before bedtime for at least six months. Two patients in the treatment group were excluded from analysis due to discontinuation intervention. Finally, forty-six patients were analyzed. Most of these patients (89.1%) were idiopathic in etiology. Seizure recurrence rates and reduction of epileptiform discharges were compared. The average follow-up durations in the treatment and control groups were 18.6 ± 6.6 and 20.1 ± 5.1 months, respectively. The seizure recurrence rate was estimated to be significantly lower in the treatment group than the control group over 24 months (37.2% vs. 76.8%, p = 0.0109). Significant decreases in epileptiform discharges were also observed after 1, 2, and 6 months of listening to Mozart K.448 when compared with EEGs before listening to music. There were no significant differences in gender, mentality, seizure type, and etiology between the recurrence and non-recurrence groups. Although the case number was limited and control music was not performed in this study, the study revealed that listening to Mozart K.448 reduced the seizure recurrence rate and epileptiform discharges in children with first unprovoked seizures, especially of idiopathic etiology. We believe that Mozart K.448 could be a promising alternative treatment in patients with

  18. The safe control of the transport of radioactive material in France

    International Nuclear Information System (INIS)

    Chaumette, L.

    2000-01-01

    The regulation of the transport of radioactive and fissile material for civil use concerns the protection of human beings and the environment against the radiological risk which can occur by these conveyed material. That's why this regulation particularly calls upon the law of the protection of the environment, upon the law of the transport of dangerous goods and upon the nuclear law. According to the International Atomic Energy Agency [I.A.E.A.], the implementation of this regulation gives the transport a high level of safety. It comes from I.A.E.A's recommendations which have taken into account lessons from the scientific research and from technical experiences. These recommendations are implemented in international binding modal regulations so that they can be adapted to the ways of transport. Their acceptance in the inner law goes with some national specific laws, mainly connected with the operator's missions and responsibilities. So this technical and administrative regulation is rather complex, and its codification would make it clearer. Nevertheless the whole regulation meets the double aim of the law in transport of dangerous goods which is to insure the safety of this transport of dangerous goods without prejudicing exchanges. In order to apply the regulation, the operators use supervision procedure to check their activities are in conformity with the law. In addition to these procedures, the Authorities supervise this conformity from time to time, by making boring. Operators and the Authorities involve their responsibility which is dependent either on the system of civil responsibility in case of damage, or on the system of administrative responsibility in case of error or risk, or on the system of penal responsibility in case of infraction of the law. So the operators have to apply the regulation and the Administration has to enforce this regulation they have built up. However, the self-control of the safety of the transport of radioactive

  19. 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

  20. Phase control of a Zeeman-split He-Ne gas laser by variation of the gaseous discharge voltage.

    Science.gov (United States)

    Shelton, W N; Hunt, R H

    1992-07-20

    Zeeman-split lasers are useful for precise positioning or motion control. In applications that employ such a laser to control closely the position of a moving system, phase noise in the Zeeman frequency is a serious problem. Control of low-frequency phase noise can be obtained through variation of the external magnetic field by way of a solenoid wound around the laser tube. It is the finding in this work that control of the residual higher-frequency noise of a He-Ne laser can be obtained through small variations of the high voltage that is used to effect the gaseous discharge in the laser tube. The application of the present system is to the control of the path difference in a Fourier-transform interferometric spectrometer.

  1. Method for burning radioactive wastes

    International Nuclear Information System (INIS)

    Hattori, Akinori; Tejima, Takaya.

    1987-01-01

    Purpose: To completely process less combustible radioactive wastes with no excess loads on discharge gas processing systems and without causing corrosions to furnace walls. Method: Among combustible radioactive wastes, chlorine-containing less combustible wastes such as chlorine-containing rubbers and vinyl chlorides, and highly heat generating wastes not containing chloride such as polyethylene are selectively packed into packages. While on the other hand, packages of less combustible wastes are charged into a water-cooled jacket type incinerator intermittently while controlling the amount and the interval of charging so that the temperature in the furnace will be kept to lower than 850 deg C for burning treatment. Directly after the completion of the burning, the packed highly heat calorie producing wastes are charged and subjected to combustion treatment. (Yoshihara, H.)

  2. Assesment of safe discharge limits in the nuclear industry

    International Nuclear Information System (INIS)

    Van As, D.

    1984-01-01

    Routine releases from the nuclear industry to the environment are controlled by three principles, viz. that the practice creating the effluents should be kept as low as reasonably achievable, and radiation dose limits should not be exceeded. In the nuclear industry, the discharge of radioactive effluent is controlled by a system of dose limitation. The application of this system to conventional effluents require: i) a quantitative relationship between intake and effect so as to establish intake limits; ii) environmental models that will allow calculation of the relationship between discharge and intake; iii) a measure of the total detriment due to the discharge. For such a system discharge limits can be established for the desired level of risk (safety)

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

    International Nuclear Information System (INIS)

    Kloes, H.

    1985-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

  5. Age-related decreases in motor unit discharge rate and force control during isometric plantar flexion

    DEFF Research Database (Denmark)

    Kallio, J; Søgaard, Karen; Avela, J

    2012-01-01

    Aging is related to multiple changes in muscle physiology and function. Previous findings concerning the effects of aging on motor unit discharge rate (DR) and fluctuations in DR and force are somewhat contradictory. Eight YOUNG and nine OLD physically active males performed isometric ramp (RECR......) and isotonic (ISO) plantar flexions at 10 and 20% of surface EMG at MVC. Motor unit (MU) action potentials were recorded with intramuscular fine-wire electrodes and decomposed with custom build software "Daisy". DR was lower in OLD in RECR-10% (17.9%, p...

  6. Modelling and Control of Stepper Motors for High Accuracy Positioning Systems Used in Radioactive Environments

    CERN Document Server

    Picatoste Ruilope, Ricardo; Masi, Alessandro

    Hybrid Stepper Motors are widely used in open-loop position applications. They are the choice of actuation for the collimators in the Large Hadron Collider, the largest particle accelerator at CERN. In this case the positioning requirements and the highly radioactive operating environment are unique. The latter forces both the use of long cables to connect the motors to the drives which act as transmission lines and also prevents the use of standard position sensors. However, reliable and precise operation of the collimators is critical for the machine, requiring the prevention of step loss in the motors and maintenance to be foreseen in case of mechanical degradation. In order to make the above possible, an approach is proposed for the application of an Extended Kalman Filter to a sensorless stepper motor drive, when the motor is separated from its drive by long cables. When the long cables and high frequency pulse width modulated control voltage signals are used together, the electrical signals difer greatl...

  7. Modular glovebox connector and associated good practices for control of radioactive and chemically toxic materials

    International Nuclear Information System (INIS)

    Hoover, M.D.; Mewhinney, C.J.; Newton, G.J.

    1999-01-01

    Design and associated good practices are described for a modular glovebox connector to improve control of radioactive and chemically toxic materials. The connector consists of an anodized aluminum circular port with a mating spacer, gaskets, and retaining rings for joining two parallel ends of commercially available or custom-manufactured glovebox enclosures. Use of the connector allows multiple gloveboxes to be quickly assembled or reconfigured in functional units. Connector dimensions can be scaled to meet operational requirements for access between gloveboxes. Options for construction materials are discussed, along with recommendations for installation of the connector in new or retrofitted systems. Associated good practices include application of surface coatings and caulking, use of disposable glovebags, and proper selection and protection of gasket and glove materials. Use of the connector at an inhalation toxicology research facility has reduced the time and expense required to reconfigure equipment for changing operational requirements, the dispersion of contamination during reconfigurations, and the need for decommissioning and disposal of contaminated enclosures

  8. Control of stress corrosion cracking in storage tanks containing radioactive waste

    International Nuclear Information System (INIS)

    Ondrejcin, R.S.; Rideout, S.P.; Donovan, J.A.

    1978-01-01

    Stress corrosion of carbon steel storage tanks containing alkaline nitrate radioactive waste, at the Savannah River Plant is controlled by specification of limits on waste composition and temperature. Cases of cracking have been observed in the primary steel shell of tanks designed and built before 1960 that were attributed to a combination of high residual stresses from fabrication welding and aggressiveness of fresh wastes from the reactor fuel reprocessing plants. The fresh wastes have the highest concentration of nitrate, which has been shown to be the cracking agent. Also as the waste solutions age and are reduced in volume by evaporation of water, nitrite and hydroxide ions become more concentrated and inhibit stress corrosion. Thus, by providing a heel of aged evaporated waste in tanks that receive fresh waste, concentrations of the inhibitor ions are maintained within specified ranges to protect against nitrate cracking. Tanks designed and built since 1960 have been made of steels with greater resistance to stress corrosion; these tanks have also been heat treated after fabrication to relieve residual stresses from construction operations. Temperature limits are also specified to protect against stress corrosion at elevated temperatures

  9. The magnetic field application for the gas discharge plasma control in processes of surface coating and modification

    International Nuclear Information System (INIS)

    Asadullin, T Ya; Galeev, I G

    2017-01-01

    In this paper the method of magnetic field application to control the gas discharge plasma effect on the various surfaces in processes of surface coating and modification is considered. The magnetic field directed perpendicular to the direction of electric current in the gas discharge plasma channel is capable to reject this plasma channel due to action of Lorentz force on the moving electrically charged particles [1,2]. The three-dimensional spatial structure of magnetic field is created by system of necessary quantity of the magnets located perpendicular to the direction of course of electric current in the gas-discharge plasma channel. The formation of necessary spatial distribution of magnetic field makes possible to obtain a required distribution of plasma parameters near the processed surfaces. This way of the plasma channel parameters spatial distribution management is the most suitable for application in processes of plasma impact on a surface of irregular shape and in cases when the selective impact of plasma on a part of a surface of a product is required. It is necessary to apply automated computer management of the process parameters [3] to the most effective plasma impact. (paper)

  10. Radioactivity in the environment

    International Nuclear Information System (INIS)

    Fernandez Niello, Jorge

    2005-01-01

    The book summarizes general concepts on radiation, nuclear structure, radioactivity and the interaction of the nuclear radiation with matter. It describes also the basic principles of radio dosimetry. Natural and artificial sources of radiation are reviewed as well as the effects of radiation in man. Medical and industrial applications of ionizing radiation and the pollution produced by the discharge of radioactive materials are outlined. A short review is made of the safety rules and the regulations concerning the protection of the environment [es

  11. Radioactive Substances Act 1960

    International Nuclear Information System (INIS)

    1960-01-01

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

  12. Transport of radioactive materials

    International Nuclear Information System (INIS)

    2013-01-01

    This ninth chapter presents de CNEN-NE--5.01 norm 'Transport of radioactive material'; the specifications of the radioactive materials for transport; the tests of the packages; the requests for controlling the transport and the responsibilities during the transport of radioactive material

  13. 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.)

  14. Problem considerations in the U.S. radioactivity control technology programme

    International Nuclear Information System (INIS)

    Humphreys, J.R. Jr.; Cash, R.J.; McPheeters, C.C.

    1976-01-01

    This paper deals with the ongoing US program in radioactivity transport and deposition in liquid metal fast breeder reactors. Experiments performed for the design and specifications of the Fast Flux Test Facility (FFTF) are reported

  15. IAEA programmes on controlled and accidental radioactive waste dumping at sea

    International Nuclear Information System (INIS)

    Sjoeblom, K.L.

    1993-01-01

    The IAEA data base on sources of radioactive material entering the marine environment consists of two modules at present. The module Sea Disposal of Radioactive Wastes includes information on wastes containing a total activity of 140 PBq dumped between 1946 and 1992. The second module Accidents and Losses at Sea contains confirmed information on 18 accidents involving nuclear submarines, aircraft etc., as well as losses in the sea of more than 100 sealed sources. (orig.)

  16. Regularity of the wear control of radioactive sources from the nuclear measurers

    International Nuclear Information System (INIS)

    Ferreira L, M.

    2006-01-01

    The control of radioactive sources in Brazil is regulated by the CNEN (National Comissao of Nuclear Energy). The Laboratory of Descontaminacao of the IPEN (Institute of Energy Y Nuclear Investigations) it offers to the companies that work with nuclear measurers, essays for control of the source wear according to the ISO 9978/1992 through the smear tests Y of leakage. The analyses are taken in alpha Y beta detectors of low bottom radiation with annual detection limits around 1 Bq. Certificates of the accepted analyses by the CNEN for sources that already passed its time of validity assured by the makers, but its continue operational are emitted. The smear test is repeated the whole year, while the leakage test repeats to every two years. A balance of the last two years of the activities of the laboratory shows the regularity of the clients Y the growth of companies specialized in radioprotection with official of radioprotection, credited by the regulatory authority that its act as intermediaries in the process, contacting the clients, gathering the samples next to the proprietors of sources Y hiring our services. Overalls, proves that the inspection activities by part of the regulatory authority are fulfil. In 2004, 192 sources were analyzed by the smear method Y 86 sources by leakage. In 2005, 232 sources were analyzed by the smear method Y 60 sources by leakage. All the leakage tests was made in sources of Americium of oneself Y only client that brings the sources so that they dismantle them to him in the Sources production laboratory of the IPEN. By the quantity Y age of the sources that were analyzed in those two years, it is proven that the number of sources without use conditions (total activity measured by the two added methods smaller than 180Bq) it doesn't arrive to 2%. (Author)

  17. Does Perturbation Training Prevent Falls after Discharge from Stroke Rehabilitation? A Prospective Cohort Study with Historical Control.

    Science.gov (United States)

    Mansfield, Avril; Schinkel-Ivy, Alison; Danells, Cynthia J; Aqui, Anthony; Aryan, Raabeae; Biasin, Louis; DePaul, Vincent G; Inness, Elizabeth L

    2017-10-01

    Individuals with stroke fall frequently, and no exercise intervention has been shown to prevent falls post stroke. Perturbation-based balance training (PBT), which involves practicing reactions to instability, shows promise for preventing falls in older adults and individuals with Parkinson's disease. This study aimed to determine if PBT during inpatient stroke rehabilitation can prevent falls after discharge into the community. Individuals with subacute stroke completed PBT as part of routine inpatient rehabilitation (n = 31). Participants reported falls experienced in daily life for up to 6 months post discharge. Fall rates were compared to a matched historical control group (HIS) who did not complete PBT during inpatient rehabilitation. Five of 31 PBT participants, compared to 15 of 31 HIS participants, reported at least 1 fall. PBT participants reported 10 falls (.84 falls per person per year) whereas HIS participants reported 31 falls (2.0 falls per person per year). When controlled for follow-up duration and motor impairment, fall rates were lower in the PBT group than the HIS group (rate ratio: .36 [.15, .79]; P = .016). These findings suggest that PBT is promising for reducing falls post stroke. While this was not a randomized controlled trial, this study may provide sufficient evidence for implementing PBT in stroke rehabilitation practice. Copyright © 2017 National Stroke Association. Published by Elsevier Inc. All rights reserved.

  18. Control of unauthorized transportation of nuclear and radioactive materials across state territories and borders: detection, response and decision support

    International Nuclear Information System (INIS)

    Stavrov, Andrei; Frymire, Allan; Kagan, Leonid; Karczewski, Jerzy

    2008-01-01

    A new solution to control the illicit transportation of nuclear and radioactive materials is proposed and described. This solution consists in the creation of a system of gamma and gamma-neutron radiation monitors and fundamentally new software/hardware package RAVEN (Radiation Alarm and Video Event Notification) which integrates different type monitors in a single network. The main purpose of this system is to analyze and store data coming from radiation monitors, to process these data and to help the user to interpret them. This ensures the user's correct response to all the alarms triggered by radiation monitors and indicating the presence of radioactive and/or nuclear materials in scanned objects. The developed system can integrate fixed radiation monitors that can be installed in different sites within not only one country but in different sites worldwide in a single network. The system can be adapted to the local conditions and allows the user: (i) To detect minimum quantities of special nuclear and radioactive materials (specified by the national and international requirements) by their gamma and/or neutron radiation; (ii) To acquire, store and analyze digital data and video images related to cargos with radioactive materials crossing a state border or an object limits; (iii) To make these data accessible to users at different levels ensuring effective operation of both central alarm stations (state, regional or agency center) and local alarm stations (border cross points or object limits). (author)

  19. A contribution to the study of the physical properties of natural and radioactive aerosols in controlled atmospheres

    International Nuclear Information System (INIS)

    Mouden, A.

    1986-01-01

    The major objective of this work was to study the properties of normal and radioactive particles produced by attachment of radon 222 daughters on environmental aerosol particles, in various and controlled atmospheres. In the first part, devoted to the radioactivity of radon 222, the influence of the number of nuclei on the radioactive equilibrium state and the size distribution of alpha radioactivity was demonstrated. In the second part, an experimental study of the C.E.A. α dosimeter was developed. We investigated the counting and the collection efficiency of the dosimeter for inlet particles in the 0.001-0.1 μm size range. The last part concerns aerosol-filtration behaviour. The comparison between experimental and theoretical procedures revealed a good agreement only in some circumstances for membrane filters. In the case of fibrous filters the agreement is quite satisfactory. Particularly, if the fiber size distribution is taken into account in the theoretical model, it results in an improved estimation of the collection efficiency [fr

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-01-20

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

  1. Control of discharge conditions to reduce hydrogen content in low Z films produced with DC glow

    International Nuclear Information System (INIS)

    Natsir, M.; Sagara, A.; Tsuzuki, K.; Tsuchiya, B.; Hasegawa, Y.; Motojima, O.

    1995-09-01

    Boronization at near room temperature has been performed in plasma processing teststand (PPT) by using a 5 % diborane gases B 2 H 6 in He on electrically floating or unfloating Al samples under various conditions on DC glow discharge power or total gas pressure. The hydrogen concentration was analyzed by using elastic recoil detection method (ERD) and a new modified normalizing technique with Rutherford back scattering (RBS). Results showed that a high growth rate of film formation and floating surface were effective in reducing hydrogen concentration in B films. This result was in good agreement with earlier measurements of H with flash filament (FF) desorption method. In particular the H/B ratio was reduced by decreasing ions but increasing radicals for B film formation. (author)

  2. Risk Informed Approach for Nuclear Security Measures for Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide

    International Nuclear Information System (INIS)

    2015-01-01

    This publication provides guidance to States for developing a risk informed approach and for conducting threat and risk assessments as the basis for the design and implementation of sustainable nuclear security systems and measures for prevention of, detection of, and response to criminal and intentional unauthorised acts involving nuclear and other radioactive material out of regulatory control. It describes concepts and methodologies for a risk informed approach, including identification and assessment of threats, targets, and potential consequences; threat and risk assessment methodologies, and the use of risk informed approaches as the basis for informing the development and implementation of nuclear security systems and measures. The publication is an Implementing Guide within the IAEA Nuclear Security Series and is intended for use by national policy makers, law enforcement agencies and experts from competent authorities and other relevant organizations involved in the establishment, implementation, maintenance or sustainability of nuclear security systems and measures related to nuclear and other radioactive material out of regulatory control

  3. Radioactive inputs to the North Sea and the Channel

    International Nuclear Information System (INIS)

    1984-01-01

    The subject is covered in sections: introduction (radioactivity; radioisotopes; discharges from nuclear establishments); data sources (statutory requirements); sources of liquid radioactive waste (figure showing location of principal sources of radioactive discharges; tables listing principal discharges by activity and by nature of radioisotope); Central Electricity Generating Board nuclear power stations; research and industrial establishments; Ministy of Defence establishments; other UK inputs of radioactive waste; total inputs to the North Sea and the Channel (direct inputs; river inputs; adjacent sea areas); conclusions. (U.K.)

  4. Institutional Control Policies and Implementation for the Area 5 and Area 3 Radioactive Waste Management Sites

    International Nuclear Information System (INIS)

    Vefa Yucel; Greg Shott; Denise Wieland

    2007-01-01

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) has implemented varying institutional control policies in performance assessment/composite analysis (PA/CA) calculations for the Area 5 and Area 3 Radioactive Waste Management Sites (RWMSs) (Shott et al., 1998; 2000; Bechtel Nevada [BN] and Neptune and Company Inc. [Neptune], 2006). The facilities are within the actively maintained boundaries of the Nevada Test Site (NTS) that are enforced by NNSA/NSO. Under current policies, access required for exposure of the member of public (MOP) or the inadvertent human intruder (IHI) is prohibited. Uncertainties affecting institutional control policies are the duration and effectiveness of the controls during the post-closure period. Implementing a uniform set of institutional control policies for the RWMSs that encompasses waste management and environmental restoration programs and is consistent with the end-state vision for the environmental management programs for the NTS (DOE, 2006) is a primary goal of the maintenance program. The NNSA/NSO Performance Management Plan (DOE, 2002) complies with DOE Policy P455.1, 'Use of Risk-Based End States' (DOE, 2003a). Expected future land uses are a driver in selecting acceptable end state conditions and clean-up goals for the NTS. NNSA/NSO Environmental Management's (EM's) land management assumptions and framework for Environmental Management activities are as follows: The NTS will remain under federal control in perpetuity as an NNSA test site, and the large buffer zone surrounding the NTS (the Nevada Test and Training Range) is assumed to remain under the control of the U.S. Air Force. There are no plans for transfer of any NTS lands to other agencies or public entities. Access will continue to be restricted to the NTS and the surrounding areas. For management purposes, NNSA/NV EM activities have been established based on the source of contamination and type of waste

  5. Institutional Control Policies and Implementation for the Area 5 and Area 3 Radioactive Waste Management Sites

    Energy Technology Data Exchange (ETDEWEB)

    Vefa Yucel, Greg Shott, Denise Wieland, et al.

    2007-11-01

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) has implemented varying institutional control policies in performance assessment/composite analysis (PA/CA) calculations for the Area 5 and Area 3 Radioactive Waste Management Sites (RWMSs) (Shott et al., 1998; 2000; Bechtel Nevada [BN] and Neptune and Company Inc. [Neptune], 2006). The facilities are within the actively maintained boundaries of the Nevada Test Site (NTS) that are enforced by NNSA/NSO. Under current policies, access required for exposure of the member of public (MOP) or the inadvertent human intruder (IHI) is prohibited. Uncertainties affecting institutional control policies are the duration and effectiveness of the controls during the post-closure period. Implementing a uniform set of institutional control policies for the RWMSs that encompasses waste management and environmental restoration programs and is consistent with the end-state vision for the environmental management programs for the NTS (DOE, 2006) is a primary goal of the maintenance program. The NNSA/NSO Performance Management Plan (DOE, 2002) complies with DOE Policy P455.1, 'Use of Risk-Based End States' (DOE, 2003a). Expected future land uses are a driver in selecting acceptable end state conditions and clean-up goals for the NTS. NNSA/NSO Environmental Management's (EM's) land management assumptions and framework for Environmental Management activities are as follows: The NTS will remain under federal control in perpetuity as an NNSA test site, and the large buffer zone surrounding the NTS (the Nevada Test and Training Range) is assumed to remain under the control of the U.S. Air Force. There are no plans for transfer of any NTS lands to other agencies or public entities. Access will continue to be restricted to the NTS and the surrounding areas. For management purposes, NNSA/NV EM activities have been established based on the source of contamination and

  6. National Program Initiative to Prevent Illicit Trafficking for Radioactive Materials Out of Regulatory Control at the Border

    International Nuclear Information System (INIS)

    Suharyanta, S.

    2016-01-01

    The existing function of regulatory authority in a country which use a lot of radioactive sources is important key. The regulatory body has to in a position independence from other operators and nuclear research centre activities, so that their justification on Regulatory objective of safety and security can be achieved. The essential function of regulatory authority has to be represented such as development regulations, perform review and assessment, inspection and enforcement, and emergency preparedness and response functions. Under regulatory object coverage is divided into two clusters i.e. licensed nuclear installation and radiation facilities clusters,. There is other regulatory object is radioactive material out of regulatory control. This kind object is new option in the county and there for need priority policy judgement. This paper will discuss the Regulatory infrastructure and functions and it focused on the experience about National Programme Initiative to Prevent Illicit Trafficking for Radioactive Materials out of Regulatory Control at the Border. Regulatory Infrastructure and Functions. In Indonesia the independent regulatory authority ''called BAPETEN'' has been established since early 2000 based on the Act No. 10 year 1997, independent from operator organization and other nuclear research centre. Organization structure of BAPETEN has defined main divisions dealing with developing regulations, perform review and assessments, inspection and enforcement, and emergency preparedness and response, and also covered assessment function as a backup technical support division as a think-tank functions. Regulatory objects are nuclear installations such as three research reactors, Fuel fabrication facility, Isotope production facility, and waste storage facility for spent fuel and dis-used radioactive sources is running well. Recently, Regulatory of radioactive sources out of regulatory control is a new challenges, they need strengthened

  7. Control, oversight and related terms in the international guidance on geological disposal of radioactive waste - Review of definitions and use

    International Nuclear Information System (INIS)

    2014-01-01

    This document presents the most complete analysis of the use of the words control, oversight, etc. as used in NEA, IAEA and ICRP literature connected to radioactive waste disposal. It reveals the many different ways the same word, 'control', has been used in international guidance and ambiguities than can arise, especially so for the post-closure phase of the repository. The newly introduced ICRP terminology, namely the use of the words 'oversight' and 'built-in controls', represents a step forward in terminology and resolves the ambiguity

  8. Shoulder replacement - discharge

    Science.gov (United States)

    Total shoulder arthroplasty - discharge; Endoprosthetic shoulder replacement - discharge; Partial shoulder replacement - discharge; Partial shoulder arthroplasty - discharge; Replacement - shoulder - discharge; Arthroplasty - shoulder - discharge

  9. Radiation protection at the RA Reactor in 1984, Part -2, Annex 2a: Radioactivity control of the RA reactor environment - atmospheric precipitations, dust, water, soil, plants, fruit.

    International Nuclear Information System (INIS)

    Ajdacic, N.; Martic, M.; Jovanovic, J.

    1984-01-01

    Control of radioactivity in the biosphere in the vicinity of the RA reactor is part of the radioactivity control done regularly for the whole territory of the Vinca institute. During 1984 control was conducted according to the plan. According to the measured data no significant changes have been found in the surroundings of the RA reactor. All the analysed samples have followed the activity values of the precipitations

  10. Controlling the Outcome of Melting Radioactive Sources in Scrap Metal: from Exclusion, Exemption and Clearance towards a 'Codex Metallarius'

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, A.J., E-mail: agonzale@sede.arn.gov.ar [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)

    2011-07-15

    Orphan radiation sources have been inadvertently incorporated into scrap metal and traces of radioactive residues have appeared in finished metal products causing public anxiety, despair in industry and governmental concern. The international principles of exclusion, exemption and clearance can be used to tackle this problem. They are described in detail, as they are becoming universally established for defining the scope of radiation protection regulations. However, notwithstanding the relevance of these principles, the paper suggests a straightforward professional consensus for discontinuing radiological control of commodities with minute traces of radioactive residues. The consensus should unambiguously specify a generic activity concentration in inedible commodities, including metals, below which radiological control may be effectively relinquished. A subsequent legally binding intergovernmental undertaking could resolve the current regulatory ambiguity, facilitate commercial exchange and ensure adequate public protection. For metals, it might take the form of a 'Codex Metallarius' (similar to the existing Codex Alimentarius for edible commodities) establishing a generic level of radiological acceptability for finished metal products. Furthermore, it is proposed that there should be an international convention to prevent radioactive sources becoming orphaned from regulatory control and then inadvertently appearing in trash and scrap. (author)

  11. Regulatory control of radiation sources and radioactive materials: The UK position

    International Nuclear Information System (INIS)

    Englefield, C.; Holyoak, B.; Ledgerwood, K.; Littlewood, K.

    2001-01-01

    The paper presents the organizations involved in the regulation of the safety of radiation sources and the security of radioactive materials across the UK. The safety of radiation sources is within the regulatory remit of the Health and Safety Executive, under the Health and safety of Work Act 1974 and associated regulations. Any employer using radiation sources has a statutory duty to comply with this legislation, thereby protecting workers and the public from undue risk. From a radioactive waste management perspective, the storage and use of radioactive materials and the accumulation and disposal of radioactive waste are regulated by the environment agencies of England and Wales, Scotland, and Northern Ireland, under the Radioactive Substances Act 1993. Special regulatory arrangements apply to nuclear sites, such as power stations and fuel cycle plants, and some additional bodies are involved in the regulation of the security of fissile materials. An explanation is given in the paper as to how these organizations to work together to provide a comprehensive and effective regulatory regime. An overview of how these regulators have recently started to work more closely with other enforcement bodies, such as the Police and Customs and Excise is also given, to illustrate the approach that is being applied in the UK to deal with orphan sources and illicit trafficking. (author)

  12. Simple DCM or CRM analog peak current controller for HV capacitor charge-discharge applications

    DEFF Research Database (Denmark)

    Trintis, Ionut; Dimopoulos, Emmanouil; Munk-Nielsen, Stig

    2013-01-01

    This paper presents a simple analog current controller suitable for buck and boost converter topologies. The controller operates in DCM or CRM, depending on the setup. The experimental results are presented to validate the proposed controller functionality for a high voltage capacitor charge...

  13. The control of the exposure of the general public to radioactive materials in the environs of the Atomic Weapons Research Establishment (AWRE) Aldermaston

    International Nuclear Information System (INIS)

    Gallop, R.G.C.; Warren, B.B.; Hannan, A.M.; Saxby, W.N.

    1987-01-01

    The Atomic Weapons Research Establishment (AWRE) at Aldermaston discharges very small amounts of radioactive materials to the local environment. Calculations based on source information indicate that the resultant dose to the general public is less than 0.1% of the local natural radiation background. This conclusion is confirmed by the detailed and extensive environmental monitoring programme carried out by AWRE in the surrounding locality. (author)

  14. Design and Control of a Buck–Boost Charger-Discharger for DC-Bus Regulation in Microgrids

    Directory of Open Access Journals (Sweden)

    Carlos Andrés Ramos-Paja

    2017-11-01

    Full Text Available In DC and hybrid microgrids (MG, the DC-bus regulation using Energy Storage Devices (ESD is important for the stable operation of both the generators and loads. There are multiple commercial voltage levels for both ESD and DC-bus; therefore, the ESD voltage may be higher, equal or lower than the DC-bus voltage depending on the application. Moreover, most of the ESD converter controllers are linear-based, hence they ensure stability in a limited operation range. This paper proposes a system to regulate the DC-bus voltage of an MG accounting for any voltage relation between the ESD and the DC-bus voltage. The proposed system is formed by an ESD connected to a DC-bus through a bidirectional Buck–Boost converter, which is regulated by a Sliding-Mode Controller (SMC to ensure the system stability in the entire operation range. The SMC drives the Buck–Boost charger–discharger to regulate the DC-bus voltage, at the desired reference value, by charging or discharging the ESD. This paper also provides detailed procedures to design the parameters of both the SMC and the charger–dischager. Finally, simulation and experimental results validate the proposed solution and illustrate its performance.

  15. 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

  16. Operation and control of ion-exchange processes for treatment of radioactive wastes

    International Nuclear Information System (INIS)

    Emelity, L.A.

    1967-01-01

    A manual dealing with the application of ion-exchange materials to the treatment of radioactive wastes and reviewing the facilities currently using this method. This book is one of three commissioned by the IAEA on the principal methods of concentrating radioactive wastes. The content of this document is: (i) Historical review related to removal of radioactivity; (ii) Principles of ion exchange (iii) Ion-exchange materials; (iv) Limitations of ion exchangers; (v) Application of ion exchange to waste processing; (vi) Operational procedures and experiences; (vii) Cost-of-treatment by ion-exchange. The document also gives a list of producers of ion-exchange material and defines some relevant terms. 101 refs, 31 figs, 27 tabs

  17. Operation and control of ion-exchange processes for treatment of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Emelity, L A [Los Alamos National Lab., NM (United States)

    1967-12-01

    A manual dealing with the application of ion-exchange materials to the treatment of radioactive wastes and reviewing the facilities currently using this method. This book is one of three commissioned by the IAEA on the principal methods of concentrating radioactive wastes. The content of this document is: (i) Historical review related to removal of radioactivity; (ii) Principles of ion exchange (iii) Ion-exchange materials; (iv) Limitations of ion exchangers; (v) Application of ion exchange to waste processing; (vi) Operational procedures and experiences; (vii) Cost-of-treatment by ion-exchange. The document also gives a list of producers of ion-exchange material and defines some relevant terms. 101 refs, 31 figs, 27 tabs.

  18. Development of radioactive standards in epoxy matrix for the control of quality of activimeters

    International Nuclear Information System (INIS)

    Fragoso, Maria da Conceicao de Farias; Monteiro, Luciane Carollyne de Oliveira Reis; Oliveira, Marcia Liane de

    2016-01-01

    In the present study, a new approach for development of the standards for positron emitting radionuclides in epoxy matrix is presented. Different formulations were prepared using epoxy resin (bisphenol A diglycidyl ether - DGEBA) and curing agents, to immobilize the radioactive material. The efficiency curve and standard sample methods were applied for activity determination of a long-lived positron emitter ("2"2Na). Satisfactory results were obtained in the 3"r"d combination. Thus, these radioactive standards can be used to evaluate the metrological behavior of the systems used for the measurement of the radiopharmaceuticals (activimeters) in the production centers and in nuclear medicine services. (author)

  19. The control of radioactivity in the working environment in the factories for production of phosphate fertilizers

    International Nuclear Information System (INIS)

    Ajdacic, B.N.; Gnjatovic, S.S.; Vujovic, P.V.

    1980-01-01

    A study was made of three chemical fertilizer plants to investigate the extent of radioactive contamination due to uranium. The following general conclusions were made: 1) Workers should be classified as professionally exposed to ionizing radiation. 2) Protective masks should be obligatory for personnel working in raw materials warehouses. 3) Waste materials should be classified as radioactive wastes, and special attention should be paid to the problem of waste water. 4) Personal dosimeters should be introduced for workers at particular posts. (U.K.)

  20. Travelling-wave-sustained discharges

    International Nuclear Information System (INIS)

    Schlueter, Hans; Shivarova, Antonia

    2007-01-01

    This review is on discharges maintained by travelling waves: new plasma sources, discovered in 1974 and considered as a prototype of the gas discharges according to their definition as nonlinear systems which unify in a self-consistent manner plasmas and fields. In the presentation here of the fluid-plasma models of the diffusion-controlled regime of the travelling-wave-sustained discharges (TWSDs), the basic features of the discharge maintenance-the discharge self-consistency and the electron heating in the high-frequency field-are stressed. Operation of stationary and pulsed discharges, discharge maintenance without and in external magnetic fields as well as discharge production in different gases (argon, helium, helium-argon gas mixtures and hydrogen) are covered. Modulation instability of diffusion-controlled discharges and discharge filamentation at higher gas pressures are also included in the review. Experimental findings which motivate aspects of the reported modelling are pointed out