WorldWideScience

Sample records for radioactive discharge control

  1. 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.)

  2. 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

  3. 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.)

  4. 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...

  5. 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)

  6. 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)

  7. 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)

  8. 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

  9. 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.

  10. 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

  11. 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

  12. 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.)

  13. 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

  14. 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)

  15. 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.

  16. 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)

  17. 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

  18. 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

  19. 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)

  20. 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

  1. 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

  2. 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)

  3. 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)

  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. 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. 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)

  7. 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)

  8. 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)

  9. 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)

  10. 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)

  11. 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

  12. 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)

  13. 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

  14. 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.)

  15. 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.)

  16. 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

  17. 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.

  18. 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)

  19. 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

  20. 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)

  1. 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

  2. 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)

  3. 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

  4. 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.)

  5. 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.)

  6. 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)

  7. 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)

  8. 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)

  9. 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)

  10. 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)

  11. 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)

  12. 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)

  13. 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

  14. 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

  15. 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.

  16. 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)

  17. 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)

  18. 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

  19. 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.)

  20. 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.

  1. 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

  2. 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

  3. 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

  4. 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)

  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

    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

  6. 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.

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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)

  18. 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)

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

    International Nuclear Information System (INIS)

    Allday, C.

    1977-01-01

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

  20. 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

  1. 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

  2. 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

  3. 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)

  4. 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

  5. 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)

  6. 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

  7. 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

  8. 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

  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. 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, ...

  11. 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.

  12. 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).

  13. 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

  14. 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.)

  15. 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)

  16. 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.)

  17. 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.)

  18. 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.)

  19. 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

  20. 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

  1. 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)

  2. 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...

  3. [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.

  4. 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

  5. Measurement of liquid radioactive materials for monitoring radioactive emissions

    International Nuclear Information System (INIS)

    1977-10-01

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

  6. 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

  7. Radioactive waste disposal by UKAEA establishments during 1979 and associated environmental monitoring results

    International Nuclear Information System (INIS)

    Flew, E.M.

    1980-07-01

    This report gives details of the amounts of solid and liquid radioactive waste disposed of by the principal establishments of the UKAEA during 1979. Waste arising at the UKAEA Nuclear Power Development Laboratories at Windscale and Springfields, which are both situated on British Nuclear Fuels Ltd. (BNFL) sites, is disposed of by BNFL and included in their authorisations. Discharges to atmosphere of airborne radioactive waste are also included in the report. A summary of the results of the environmental monitoring programmes carried out in connection with the radioactive waste discharges is given. To facilitate an appreciation of the standard of safety achieved, the discharges are, where appropriate, shown as a percentage of those authorised. In the case of atmospheric discharges no quantitative limits are yet specified in the authorisations, but the results and estimates of discharges from stacks are compared with Derived Working Limits (DWL's) (i.e. a limit derived from the dose limits recommended by The International Commission on Radiological Protection in such a way that compliance with it implies virtual certainty of compliance with the relevant dose limits). Environmental monitoring results are also compared with appropriate DWL's. The principles underlying the control of the discharge of radioactive waste to the environment are summarised in an Appendix to the report. (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. 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)

  10. 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.)

  11. 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.)

  12. 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

  13. 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)

  14. 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.)

  15. Control rod driving hydraulic pressure device

    International Nuclear Information System (INIS)

    Ishida, Kazuo.

    1990-01-01

    Discharged water after actuating control rod drives in a BWR type reactor is once discharged to a discharging header, then returned to a master control unit and, subsequently, discharged to a reactor by way of a cooling water header. The radioactive level in the discharging header and the master control unit is increased by the reactor water to increase the operator's exposure. In view of the above, a riser is disposed for connecting a hydraulic pressure control unit incorporating a directional control valve and the cooling water head. When a certain control rod is inserted, the pressurized driving water is supplied through a hydraulic pressure control unit to the control rod drives. The discharged water from the control rod drives is entered by way of the hydraulic pressure control unit into the cooling water header and then returned to the reactor by way of other hydraulic pressure control unit and the control rod drives. Thus, the reactor water is no more recycled to the master control unit to reduce the radioactive exposure. (N.H.)

  16. 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)

  17. 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.)

  18. Status of outdoor radioactive contamination at the Hanford Site

    International Nuclear Information System (INIS)

    McKinney, S.M.; Markes, B.M.

    1994-12-01

    This document summarizes the status of outdoor radioactive contamination near Hanford Site facilities and disposal sites. It defines the nature and areal extend of the radioactively contaminated areas and describes the historical, ongoing, and planned radiological monitoring and control activities. Radioactive waste has been disposed of to the soil column since shortly after the reactors and production facilities began operating. Radioactive liquid wastes were placed directly into the ground via liquid discharges to cribs, ponds, ditches, and reverse wells. Solid wastes were placed in trenches, burial vaults, and caissons. Although the Hanford Site covers 1,450 km 2 , the radioactively contaminated area is only about 36 km 2 or 2.5% of the original site. Over time, contamination has migrated from some of the waste management sites through various vectors (e.g., burrowing animals, deep-rooted vegetation, erosion, containment system failure) or has been deposited to the surface soil via spills and unplanned releases (e.g., line leaks/breaks, tank leaks, and stack discharges) and created areas of outdoor radioactivity both on and below the surface. Currently 26 km 2 are posted as surface contamination and 10 km 2 are posted as underground contamination

  19. 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)

  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. 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)

  2. 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.)

  3. 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

  4. 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)

  5. 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)

  6. 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.)

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

    International Nuclear Information System (INIS)

    Esch, D.; Wittwer, C.

    2014-01-01

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

  8. 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)

  9. 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.

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

    International Nuclear Information System (INIS)

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

    1984-03-01

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

  11. 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

  12. 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.

  13. Marine environmental radioactivity surveys at nuclear submarine berths 2001

    International Nuclear Information System (INIS)

    Cowling, E.; Ball, R.; Simpson, C.

    2002-01-01

    This report presents the results of the marine environmental radioactivity monitoring surveys of intertidal and underwater areas around nuclear submarine berths which were carried out by DRPS during 2001. Also included are results of smaller scale intertidal surveys carried out by local staff but co-ordinated by DRPS. Cobalt-60, the nuclide of major importance in naval discharges, was detected in a number of samples but in many cases was attributable to discharges by other operators. Concentrations in any case were found to be low, and at no survey location did the calculated annual radiation dose commitment to the most exposed members of the general public due to the presence of cobalt-60 exceed 1% of the ICRP principal dose limit for members of the public (1000μSv). These results are consistent with those obtained in the independent monitoring programmes as reported in the Radioactivity in Food and the Environment (RIFE) annual reports. It is concluded that existing discharge arrangements are providing effective control over environmental levels of radioactivity, and that there has been no radiological hazard to any member of the general public during 2001 from the operation of nuclear powered submarines. (author)

  14. 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

  15. Radioactivity in surface and coastal waters of the British Isles, 1987

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1988-01-01

    This report presents the results of the environmental monitoring programme carried out during 1987 by staff of the Directorate of Fisheries Research, Lowestoft. The monitoring programme supports the Ministry's functions under the Radioactive Substances Act, 1960 (Great Britain-Parliament, 1960). The programme is 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 monitoring is independent of similar programmes carried out by nuclear site operators as a condition of their authorisations to discharge radioactive wastes. This report also includes results of monitoring carried out on behalf of departments of the Scottish Office, the Welsh Office, the Department of the Environment for Northern Ireland [DOE (NI)] and the Channel Islands States. Where appropriate, the information presented is supplemented by results from our extensive programme of research into the behaviour of radioactivity in the aquatic environment. (author)

  16. 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.)

  17. 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

  18. 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)

  19. 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.)

  20. 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)

  1. 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.)

  2. Experience in radioactive waste management of research centre-CIAE

    International Nuclear Information System (INIS)

    Luo Shanggeng

    2001-01-01

    China Institute of Atomic Energy (CIAE) is the birthplace of China nuclear science and technology and the important base for nuclear science and technology implementing pioneering, basic and comprehensive studies. The major tasks and activities of CIAE are: (1) Fundamental research of nuclear science and technology; (2) Research and development of advanced nuclear energy; and (3) Application of nuclear technology. CIAE is equipped with three research reactors (15MW heavy water reactor, 3.5MW light water swimming pool reactor, 27kW neutron source reactor), four zero-power facilities, eleven accelerators, hot cells and a lot of glove boxes which produce various kinds of radioactive wastes. CIAE pays great attention to the safe management of radioactive waste. Many measurements were and are adopted. CIAE carries out the national policy of radioactive waste management and the international fundamental principles of radioactive waste management. To protect human body and environment both now and future generation minimizes the releasing amounts and activity, minimizes the solidified wastes to be disposed of. The principles of 'controlled generation, categorized collection, volume-reduction immobilization, reliable package, in-situ storage, safe transportation and disposal' are followed in managing LLW and ILW. The liquid wastes are separately treated by precipitation, evaporation, ion exchange or adsorption by organic or inorganic materials. The spent organic solvents are treated by incineration at a special incinerator. The low level radioactive gases and liquids can be discharged into the environment only when they are clean-up and permissible level is achieved. Such discharge is controlled by two factors: total discharge amount and specific activity. The solid wastes are separately collected in site according to their physical properties and specific activity. The storage waste is retrievable designed. The spent/sealed radiation sources are collected and stored with

  3. 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)

  4. 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

  5. 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)

  6. Selecting device for processing method of radioactive gaseous wastes

    International Nuclear Information System (INIS)

    Sasaki, Ryoichi; Komoda, Norihisa.

    1976-01-01

    Object: To extend the period of replacement of a filter for adsorbing radioactive material by discharging waste gas containing radioactive material produced from an atomic power equipment after treating it by a method selected on the basis of the results of measurement of wind direction. Structure: Exhaust gas containing radioactive material produced from atomic power equipment is discharged after it is treated by a method selected on the basis of the results of wind direction measurement. For Instance, in case of sea wind the waste gas passes through a route selected for this case and is discharged through the waste gas outlet. When the sea wind disappears (that is, when a land wind or calm sets in), the exhaust gas is switched to a route for the case other than that of the sea wind, so that it passes through a filter consisting of active carbon where the radioactive material is removed through adsorption. The waste gas now free from the radioactive material is discharged through the waste gas outlet. (Moriyama, K.)

  7. 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

  8. 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

  9. The radioactivity of the sea

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  10. 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

  11. 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)

  12. 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)

  13. 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

  14. 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

  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. 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

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

    International Nuclear Information System (INIS)

    Mizutani, Tomoko; Koarashi, Jun; Takeishi, Minoru

    2009-01-01

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

  18. Electrodeless light source provided with radioactive material

    International Nuclear Information System (INIS)

    1979-01-01

    Radioactive materials are used to assist in starting a discharge in an electrodeless light source. The radioactive emissions predispose on the inner surface of the lamp envelope loosely bound charges which thereafter assist in initiating discharge. The radioactive material can be enclosed within the lamp envelope in gaseous or non-gaseous form. Preferred materials are krypton 85 and americium 241. In addition, the radioactive material can be dispersed in the lamp envelope material or can be a pellet imbedded in the envelope material. Finally, the radioactive material can be located in the termination fixture. Sources of alpha particles, beta particles, or gamma rays are suitable. Because charges accumulate with time on the inner surface of the lamp envelope, activity levels as low as 10 -8 curie are effective as starting aids. (Auth.)

  19. International conference on issues and trends in radioactive waste management. Contributed papers

    International Nuclear Information System (INIS)

    2002-01-01

    This publication contains 78 contributed papers submitted on issues falling within the thematic scope of the Conference which were accepted by the Conference Programme Committee for consideration at the conference. The papers are grouped into the following chapters: control of discharges, environmental aspects; long-term storage; geological disposal; management of radioactive waste, including sealed sources; management of radioactive waste from past eras; regulatory infrastructure, decision making, stakeholders; retention of information, long-term control, standards; specific studies; and international co-operative efforts. Each of the papers was indexed separately

  20. International conference on issues and trends in radioactive waste management. Contributed papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This publication contains 78 contributed papers submitted on issues falling within the thematic scope of the Conference which were accepted by the Conference Programme Committee for consideration at the conference. The papers are grouped into the following chapters: control of discharges, environmental aspects; long-term storage; geological disposal; management of radioactive waste, including sealed sources; management of radioactive waste from past eras; regulatory infrastructure, decision making, stakeholders; retention of information, long-term control, standards; specific studies; and international co-operative efforts. Each of the papers was indexed separately.

  1. 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

  2. Boiling water reactor liquid radioactive waste processing system

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

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

  3. Radioactive liquid containing vessel

    International Nuclear Information System (INIS)

    Sakurada, Tetsuo; Kawamura, Hironobu.

    1993-01-01

    Cooling jackets are coiled around the outer circumference of a container vessel, and the outer circumference thereof is covered with a surrounding plate. A liquid of good conductivity (for example, water) is filled between the cooling jackets and the surrounding plate. A radioactive liquid is supplied to the container vessel passing through a supply pipe and discharged passing through a discharge pipe. Cooling water at high pressure is passed through the cooling water jackets in order to remove the heat generated from the radioactive liquid. Since cooling water at high pressure is thus passed through the coiled pipes, the wall thickness of the container vessel and the cooling water jackets can be reduced, thereby enabling to reduce the cost. Further, even if the radioactive liquid is leaked, there is no worry of contaminating cooling water, to prevent contamination. (I.N.)

  4. 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

  5. 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.)

  6. 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

  7. 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...

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

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  9. Radiological protection objectives for the disposal of solid radioactive wastes

    International Nuclear Information System (INIS)

    1983-10-01

    Guidance is given on the standards to be used in the UK in decisions on the radiological acceptability of disposal methods for solid radioactive wastes. The radiological protection objectives given in the report are intended to be applied to all types of solid radioactive waste, and to all the disposal methods which are in use or under consideration. This guidance complements and extends previous Board advice on radiological protection objectives which apply to the control of routine discharges of gaseous and liquid effluents. (author)

  10. 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)

  11. 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.

  12. Liquid radioactive wastes from hospitals by polymeric membrane

    International Nuclear Information System (INIS)

    Arnal, J.M.; Sancho, M.; Verdu, G.; Campayo, J.M.

    1998-01-01

    Streams containing I''125 produced from RIA process, classified as radioactive waste of low activity, are generated by all different treatments applied in IN VITRO techniques. Consequently, an accumulation of solutions containing I''125 is produced in the order of 50-100 L/month approximately. The storage at sanitary centres and the accumulation caused by it creates a serious problem in the hospital. According to the specific activity and the installation spill authorization, one can choose between three ways of handling: direct discharge, temporal storage until the radioactive waste come to decay and then discharged, waste management by the authorised company (ENRESA). If the third way of discharge is applied the treatment of waste using membranes should be considered. Using membranes, important reduction coefficients in volume in the order of 10:1 are obtained. The aim of this work is the declassification of the I''125 solutions as a liquid radioactive waste using membrane techniques. Both, a radioactive concentrated waste and non-contaminated waste are obtained. (Author)

  13. 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

  14. 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.

  15. 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)

  16. Management of wastes containing radioactivity from mining and milling uranium ores in Northern Australia

    International Nuclear Information System (INIS)

    Costello, J.M.

    1977-01-01

    The procedures and controls to achieve safe management of wastes containing radioactivity during the mining and processing of uranium ores are mainly site-specific depending on the nature, location and distribution of the ore and gangue material. Waste rock and below-ore-grade material containing low levels of radioactivity require disposal at the mine site. In open-cut mining the material is generally stockpiled above ground, with revegetation and collection of run-off water. Some material may be used to backfill open cuts. Management of these wastes requires a thorough investigation of groundwater hydrology and surface soil characteristics to control dissipation of radioactive material. Dust containing radon and radioactive particulate is produced during ore milling, and dusts of ore concentrate are generated during calcination and packaging of the yellowcake product. These dusts are managed by ventilation and filtration systems; working conditions and discharges to atmosphere will be according to the Australian Code of Practice on Radiation Protection during Mining and Milling of Uranium Ores. The chemical waste stream from leaching and processing of the uranium ores contains most of the radioactivity resulting from radium and its decay products. Neutralized effluent is discharged into holding ponds for settling solids. The paper describes the nature of wastes containing radioactivity resulting from the mining and milling of uranium, and illustrates modern engineering practices and monitoring procedures to manage the wastes, as described in the Environmental Impact Statement produced by Ranger Uranium Mines Pty Ltd (RUM) for public hearings. (author)

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

    Science.gov (United States)

    2012-01-01

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

  18. 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.)

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

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

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

  20. 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)

  1. 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

  2. Study of lag time of river chenab between marala barrage and khanki headworks using radioactive tracer technique

    International Nuclear Information System (INIS)

    Ahmed, A.; Tariq, J.A.; Ahmad, N.; Iqbal, N.

    2001-05-01

    During the flood season, sometimes discharge peaks in two tributaries of the Indus River System coincide at the point of confluence and their cumulative effect threatens the downstream barrage/headworks. Reasonably accurate lag time (transit time) between different control points in relation to discharge helps mange flood routing more safely. As a part of S tudy of Lag Time of the Indus River Suystem , radioactive tracer experiment was conducted to determine the lag time between Marala Barrage and Khanki Headworks at the river Chenab. Discharge data shows that the maximum flood peak appears in August. In the monsoon period of the year 1999 the floods were low. So the radiotracer experiment was carried out at low discharge of about 538 m/sup 3/ sec/sup-1/ (19000 cusecs). An activity of about 2 Ci of /sup 82/Br radioactive tracer was injected instantaneously in the river at Marala on 1st September 1999 at 0640 hours. Monitoring of radioactivity by scintillation detectors (sodium iodide) was done at Khanki Headworks. The peak value of activity was found on September 2, 1999 at 0005 hours. The lag time was determined as 17 hours and 25 minutes. At this discharge level the river water travelled with the average speed of 3.69 km/hr. (author)

  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. Hazardous chemical and radioactive wastes at Hanford

    International Nuclear Information System (INIS)

    Keller, J.F.; Stewart, T.L.

    1991-07-01

    The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities have been built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Area to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic (TRU) and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemical as well as radioactive constituents. This paper will focus on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location

  5. Hazardous chemical and radioactive wastes at Hanford

    International Nuclear Information System (INIS)

    Keller, J.F.; Stewart, T.L.

    1993-01-01

    The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities were built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Areas to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemicals as well as radioactive constituents. This paper focuses on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location

  6. Management of wastes containing radioactivity from mining and milling of uranium ores in Northern Australia

    International Nuclear Information System (INIS)

    Costello, J.M.

    1977-01-01

    The procedures and controls to achieve safe management of wastes containing radioactivity during the mining and processing of uranium ores are mainly site specific depending on the nature, location and distribution of the ore and gangue material. Waste rock and below-ore-grade material containing low levels of radioactivity require disposal at the mine site. In open cut mining the material is generally stockpiled above ground, with revegetation and collection of run-off water. Some material may be used to backfill open cuts. Management of these wastes requires a thorough investigation of ground water hydrology and surface soil characteristics to control dissipation of radioactive material. Dust containing radon and radioactive particulate is produced during ore milling, and dusts of ore concentrate are generated during calcination and packaging of the yellowcake product. These dusts are managed by ventilation and filtration systems, working conditions, and discharges to atmosphere will be according to the Australian Code of Practice on Radiation Protection during Mining and Milling of Uranium Ores. The chemical waste stream from leaching and processing of the uranium ores contains the majority of the radioactivity resulting from radium and its decay products. Neutralised effluent is discharged into holding ponds for settling of solids. This paper describes the nature of wastes containing radioactivity resulting from the mining and milling of uranium, and illustrates modern engineering practices and monitoring procedures to manage the wastes, as described in the Environmental Impact statement produced by Ranger Uranium Mines Proprietary Limited for public hearings

  7. 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)

  8. 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

  9. 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)

  10. 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)

  11. Pretreatment method for radioactive iodine-containing liquid wastes and pretreatment device

    International Nuclear Information System (INIS)

    Wakaida, Yasuo.

    1996-01-01

    Heretofore, radioactive iodine-containing liquid wastes have been discharged directly to a storing and decaying storage vessel to conduct a water draining treatment. In the present invention, the radioactive iodine-containing liquid wastes to be discharged are not discharged to the storage vessel directly but injected to a filling tank, as a pretreatment, to distinguish whether proteins are mixed in the liquid wastes or not. When proteins are mixed, miscellaneous materials such as proteins are recovered and removed by a protein processing system. When proteins are not mixed, radioactive iodine is recovered and removed directly by an iodine processing system. With such procedures, water draining treatment in the storing and decaying storage vessel is mitigated, and even when the amount of the radioactive iodine-containing liquid wastes is increased, the existent maintaining and decaying storage vessel can be used as it is. Accordingly, a safe water draining treatment with good efficiency can be conducted relative to radioactive iodine-containing liquid wastes at a reduced cost. (T.M.)

  12. 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)

  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. 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

  15. 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

  16. 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

  17. 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

  18. Method of processing radioactive liquid wastes

    Energy Technology Data Exchange (ETDEWEB)

    Sugimoto, Y; Kikuchi, M; Funabashi, K; Yusa, H; Horiuchi, S

    1978-12-21

    Purpose: To decrease the volume of radioactive liquid wastes essentially consisting of sodium hydroxide and boric acid. Method: The concentration ratio of sodium hydroxide to boric acid by weight in radioactive liquid wastes essentially consisting of sodium hydroxide and boric acid is adjusted in the range of 0.28 - 0.4 by means of a pH detector and a sodium concentration detector. Thereafter, the radioactive liquid wastes are dried into powder and then discharged.

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

    International Nuclear Information System (INIS)

    2010-01-01

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

  20. Environmental controls

    International Nuclear Information System (INIS)

    Brown, S.

    1996-01-01

    Members of the public are exposed to environmental radiations from a variety of sources. In terms of average dose received the major component is from natural sources of radiation for which there is little or no scope to reduce exposure. Where such opportunities do exist, in those homes with high radon concentrations, the householders tend to ignore the risks despite the availability of comparatively straightforward and inexpensive remediation measures. By comparison there is significant public concern about radioactive waste management and the disposal and discharge of radioactivity to the environment despite strict environmental controls. This paper describes the controls and the wider policy context for radioactive waste management following a major review of policy last year. (author)

  1. Plutonium discharges to the sanitary sewer: Health impacts at the Livermore Water Reclamation Plant

    International Nuclear Information System (INIS)

    Balke, B.K.

    1993-01-01

    The Lawrence Livermore National Laboratory (LLNL) is the largest discharger of sewage treated by the Livermore Water Reclamation (LWRP), contributing approximately 7% by volume of the LWRP influent LILNL operations, as potential sources both of industrial pollutants and radioactivity, are therefore of particular concern to the LWRP. For this reason, LLNL has maintained vigorous wastewater discharge control and monitoring programs. In particular, the monitoring program has demonstrated that, except in a few rare instances, the concentration of contaminants in LLNL effluent have always remained below the appropriate regulatory standards. The exceptions have generally been due to inadvertent discharges of metals-bearing solutions produced by metal plating or cleaning operations

  2. 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

  3. 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.

  4. 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

  5. Analysis through indicators of the management of radioactive waste in a radioactive facility

    International Nuclear Information System (INIS)

    Amador Balbona, Zayda; Argudin Bocourt, William

    2013-01-01

    The evaluation of the management of radioactive waste in the center of isotopes of the Republic of Cuba is the objective of this work. To do so, all the operations of the management system are evaluated through indicators used by this radioactive facility over a decade ago. Available information is processed from 1996 until 2012. The major waste generators are identified through the indicator of annual generation of each working group by local and by worker and it were analyzed the available store radioactive inventory, the relationship between the variation of annual technological waste volume of waste and the annual total manipulated activity, the relationship generation-declassification and the percent of liquid effluents managed as waste. Indicators of unconditional clearance, as well as the of the gaseous and liquid discharges are presented. It is concluded, with all these indicators, that it is possible to determine where are the causes of the behavior in the generation of radioactive waste if it is an increase of manipulated activity int the places of work or of worker, or improper application of the procedures of collection. It is controlled not only management, but also determines in which aspects can work to achieve the objective of minimizing the formation of these wastes, to be able to reduce the production costs. National shedding environmental regulations are met and the results are acceptable)

  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. 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

  8. 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

  9. 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.

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

    Science.gov (United States)

    Bigu, J; Grenier, M G

    1989-07-01

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

  11. 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)

  12. 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

  13. 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)

  14. 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

  15. 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.)

  16. Monitoring programme. Radioactive substances report for 1994

    International Nuclear Information System (INIS)

    1995-09-01

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

  17. 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

  18. 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...

  19. Radioactivity in surface and coastal waters of the British Isles, 1979

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1981-01-01

    A report is presented on the results of an environmental monitoring programme carried out during 1979 by the Directorate's Aquatic Environment Protection Division at the Fisheries Radiobiological Laboratory (FRL). The programme was set up to verify the satisfactory control of liquid radioactive waste discharges from nuclear establishments to the aquatic environment and to ensure that the resulting public radiation exposure is within nationally-accepted limits. The monitoring results mainly concerned British Nuclear Fuels at Sellafield, Springfields, Capenhurst and Chapelcross; the United Kingdom Atomic Energy Authority at Winfrith and Dounreay; the nuclear power stations operated by the electricity boards at Berkeley, Bradwell, Dungeness, Hartlepool, Heysham, Hinkley Point, Hunterston, Sizewell, Trawsfyndd and Wylfa. Monitoring results are also presented for UK Naval establishments, Amersham International Limited and the Channel Islands. A summary of estimated public radiation exposures in 1979 resulting from liquid radioactive discharges to the aquatic environment from nuclear establishments monitored by FRL showed that all exposures were well within the ICRP dose equivalent limit. (U.K.)

  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. 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

  2. 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)

  3. 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)

  4. Atmospheric discharges from nuclear facilities during decommissioning: German experiences

    Energy Technology Data Exchange (ETDEWEB)

    Braun, H.; Goertz, R.; Weil, L.

    1997-08-01

    In Germany, a substantial amount of experience is available with planning, licensing and realization of decommissioning projects. In total, a number of 18 nuclear power plants including prototype facilities as well as 6 research reactors and 3 fuel cycle facilities have been shut down finally and are at different stages of decommissioning. Only recently the final {open_quotes}green field{close_quotes} stage of the Niederaichbach Nuclear Power Plant total dismantlement project has been achieved. From the regulatory point of view, a survey of the decommissioning experience in Germany is presented highlighting the aspects of production and retention of airborne radioactivity. Nuclear air cleaning technology, discharge limits prescribed in licences and actual discharges are presented. As compared to operation, the composition of the discharged radioactivity is different as well as the off-gas discharge rate. In practically all cases, there is no significant amount of short-lived radionuclides. The discussion further includes lessons learned, for example inadvertent discharges of radionuclides expected not to be in the plants inventory. It is demonstrated that, as for operation of nuclear power plants, the limits prescribed in the Ordinance on Radiological Protection can be met using existing air cleaning technology, Optimization of protection results in public exposures substantially below the limits. In the frame of the regulatory investigation programme a study has been conducted to assess the airborne radioactivity created during certain decommissioning activities like decontamination, segmentation and handling of contaminated or activated parts. The essential results of this study are presented, which are supposed to support planning for decommissioning, for LWRs, Co-60 and Cs-137 are expected to be the dominant radionuclides in airborne discharges. 18 refs., 2 figs., 1 tab.

  5. 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

  6. Measurement of radioactivity in water samples

    International Nuclear Information System (INIS)

    Richards, L.

    1990-01-01

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

  7. 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

  8. Radioactive waste management

    International Nuclear Information System (INIS)

    1984-07-01

    The purpose of this document is to set out the Government's current strategy for the long term in the management of radioactive wastes. It takes account of the latest developments, and will be subject to review in the light of future developments and studies. The subject is discussed under the headings: what are radioactive wastes; who is responsible; what monitoring takes place; disposal as the objective; low-level wastes; intermediate-level wastes; discharges from Sellafield; heat generating wastes; how will waste management systems and procedures be assessed; how much more waste is there going to be in future; conclusion. (U.K.)

  9. Radioactive lightning rods: radiologic evaluation and regulatory policy related to its use in Cuba

    International Nuclear Information System (INIS)

    Lopez Forteza, Yamil; Quevedo Garcia, Jose R.; Diaz Guerra, Pedro I.; Cruz Dumenico, Gonzalez; Fuente Puch, Andres de la

    2001-01-01

    The radioactive lightning rod employment for the protection of facilities against atmospheric discharges reached its maximum splendor in the eighties. It was in fact at the end of this decade when the technical considerations related to the justification of this practice finally conclude that the production of such teams was abolished. For the regulatory authorities, however, it continues having validity the question related to the control of lightning rod still in use as well as the question related to the establishment of a coherent with the international practice national policy. The paper shows the results of the last 10 years of control of the radioactive lightning rod use in Cuba and the radiological evaluation carried out on the base of this experience. Lastly, it exposes the regulatory policy referred to the employment of the radioactive lightning rod in the country. (author)

  10. International Conference on the Safety of Radioactive Waste Management. Book of Papers

    International Nuclear Information System (INIS)

    2016-01-01

    The purpose of the conference was to highlight the importance of an integrated long term approach to the management of radioactive waste and spent fuel. The objectives of the conference were: • To foster information exchange between Member States, • To provide inputs that will promote further harmonization of safety in the fields of predisposal management and disposal of radioactive waste, • To highlight progress made in the safety of all types of radioactive waste. The conference served as a forum for discussing past experiences and future challenges. Furthermore, it seeked to identify Member States’ needs in order to assist them — through specific activities under future IAEA programmes in this area — to develop and implement safe solutions for the management of their entire radioactive waste inventory. The conference addressed all aspects of predisposal management and disposal of radioactive waste and spent fuel, including waste arising from accidental situations. The management of radioactive waste and residues from mining activities, as well as the control of discharges from nuclear facilities and activities, were, however, outside of its scope.

  11. 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)

  12. 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.

  13. 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

  14. 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

  15. Radioactive waste disposal by UKAEA establishments during 1980 and associated environmental monitoring results

    International Nuclear Information System (INIS)

    Flew, E.M.

    1981-09-01

    This report gives details of the amounts of solid and liquid radioactive waste disposed of by the principal establishments of the UKAEA during 1980. Waste arising at the UKAEA Nuclear Power Development Laboratories at Windscale and Springfields, which are both situated on British Nuclear Fuels Ltd. (BNFL)-sites, is disposed of by BNFL and included in their authorisations. Discharges to atmosphere of airborne radioactive waste are also included in the report. A summary of the results of the environmental monitoring programmes carried out in connection with the radioactive waste discharges is given. (author)

  16. Radioactive waste disposal by UKAEA establishments during 1978 and associated environmental monitoring results

    International Nuclear Information System (INIS)

    Flew, E.M.

    1979-05-01

    This report gives details of the amounts of solid and liquid radioactive waste disposed of by the principal establishments of the UKAEA during 1978. Waste arising at the UKAEA Nuclear Power Development Laboratories at Windscale and Springfields, which are both situated on British Nuclear Fuels Ltd. (BNFL) sites, is disposed of by BNFL and included in their authorisations. Discharges to atmosphere of airborne radioactive waste are also included in the report. A summary of the results of the environmental monitoring programmes carried out in connection with the radioactive waste discharges is given. (author)

  17. Radioactive Effluents from Nuclear Power Plants Annual Report 2007

    International Nuclear Information System (INIS)

    2010-01-01

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

  18. Radioactive Effluents from Nuclear Power Plants Annual Report 2008

    International Nuclear Information System (INIS)

    2010-01-01

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

  19. ELECTRONIC ANALOG COMPUTER FOR DETERMINING RADIOACTIVE DISINTEGRATION

    Science.gov (United States)

    Robinson, H.P.

    1959-07-14

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

  20. Conveyor for sorting radioactive waste

    International Nuclear Information System (INIS)

    Prisco, A.J.; Johnson, A.N.

    1987-01-01

    An apparatus is described for detecting radioactive components in dry active waste, the apparatus comprising: means for reducing the waste to pieces of substantially uniform size, first and second conveyors and a housing for the conveyors; means for conveying the pieces from the means for reducing the waste to the first and second conveyors; each of the first and second conveyors includes a receiving portion and a discharge portion; the discharge portion is spaced above and upstream from the receiving portion to disperse the pieces as they are transferred from the first conveyor to the second conveyor so that pieces which are in clusters are separated from each other to increase the likelihood of detecting radiation emanating means for detecting radioactive radiation emanating from the pieces, at least one of radiation detector means is located on each of the conveyors. Each is disposed in close overlying relation to its respective conveyor so that low levels of radiation emanating from the pieces can be detected; each of the conveyors includes means for flattening the pieces of waste before the pieces pass under the radiation detector means; and the means for flattening disposed between the receiving portion of each conveyor and the radiation detector means; the housing is generally closed; and means for providing a generally closed connection between the housing and the means for reducing the waste so that air that is in the housing and in the means for reducing the waste can be controlled

  1. 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

  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. Disposal containers for radioactive waste materials and separation systems for radioactive waste materials

    International Nuclear Information System (INIS)

    Rubin, L.S.

    1986-01-01

    A separation system for dewatering radioactive waste materials includes a disposal container, drive structure for receiving the container, and means for releasably attaching the container to the drive structure. The separation structure disposed in the container adjacent the inner surface of the side wall structure retains solids while allowing passage of liquids. The inlet port structure in the container top wall is normally closed by first valve structure that is centrifugally actuated to open the inlet port and the discharge port structure at the container periphery receives liquid that passes through the separation structure and is normally closed by a second valve structure that is centrifugally actuated to open the discharge ports. The container also includes a coupling structure for releasable engagement with the centrifugal drive structure. The centrifugal force produced when the container is driven in rotation by the drive structure opens the valve structures, and radioactive waste material introduced into the container through the open inlet port is dewatered, and the waste is compacted. The ports are automatically closed by the valves when the container drum is not subjected to centrifugal force such that containment effectiveness is enhanced and exposure of personnel to radioactive materials is minimized. (author)

  4. Method for storing radioactive rare gases

    International Nuclear Information System (INIS)

    Watabe, Atsushi; Nagao, Hiroyuki; Takiguchi, Yukio; Kanazawa, Toshio; Soya, Masataka.

    1975-01-01

    Object: To safely and securely store radioactive rare gases for a long period of time. Structure: The waste gases produced in nuclear power plant are cooled by a cooler and then introduced into a low temperature adsorbing device so that the gases are adsorbed by adsorbents, and then discharged into atmosphere through the purifying gas discharge line. When the radioactive rare gases reach a level of saturation in the amount of adsorption, they are heated and extracted by a suction pump and heated by a heater. The gases are then introduced into an oxygen-impurity removing device and the purified rare gases containing no oxygen and impurities are cooled by a cooler and fed into a gas holder. When the amount of radioactive rare gases stored within the gas holder reaches a given level, they are compressed and sealed by a compressure into a storing cylinder and residual gases in the piping are sucked and recovered into the gas holder, after which the cylinder is removed and stored in a fixed room. (Kamimura, M.)

  5. The Radioactive Waste Management at Studsvik

    Energy Technology Data Exchange (ETDEWEB)

    Hedlund, R; Lindskog, A

    1966-04-15

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

  6. The Radioactive Waste Management at Studsvik

    International Nuclear Information System (INIS)

    Hedlund, R.; Lindskog, A.

    1966-04-01

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

  7. 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

  8. 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)

  9. 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

  10. Radioactive Waste Disposal into the Sea

    International Nuclear Information System (INIS)

    1961-01-01

    Preventing pollution of the seas from the discharge of radioactive wastes has been recognized as an international problem of considerable magnitude. In April 1958 the United Nations Conference on the Law of the Sea adopted a Convention on the High Seas, Article 25 of which provides that every State shall take measures to prevent pollution of the seas from the dumping of radioactive wastes, taking into account any standards and regulations which may be formulated by the competent international organizations. The Conference also adopted a resolution recommending that the IAEA pursue studies and take action to assist States in controlling the discharge of radioactive materials into the sea. Later the same year, a Panel of experts was invited by me to meet in Vienna to study the technical and scientific problems connected with radioactive waste disposal into the sea, and Mr. H. Brynielsson of Sweden was designated Chairman of the Panel. Representatives of the United Nations, the Food and Agriculture Organization of the United Nations, the World Health Organization and the United Nations Educational, Scientific and Cultural Organization participated in the work of the Panel. After a second series of meetings in 1959, the Panel completed its study, setting forth the result of its work in a report dated 6 April 1960, which has been submitted to the Agency's Scientific Advisory Committee and to Member States for their information. The Panel's report is now published in the present volume of the Agency's Safety Series in the form in which it was submitted by the Chairman of the Panel. I should like to add that the report represents the views of the experts participating in their individual capacity in the work of the Panel. It is offered as an information document and it should not be regarded as an official statement by the Agency of its views or policies in relation to the subject discussed.

  11. 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)

  12. 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.)

  13. 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.)

  14. 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

  15. Emitter depletion studies on electrodes of 50 Hz mercury/noble gas discharge lamps during ignition

    International Nuclear Information System (INIS)

    Hoek, W.J. van den; Thijssen, T.L.G.; Heijden, A.J.H. van der; Buijsse, B.; Haverlag, M.

    2002-01-01

    The depletion of emitter from the oxide cathodes during the glow switch starting of the discharge in 50 Hz operated low-pressure mercury/noble gas discharge lamps (fluorescent lamps) has been studied. It follows from pulse ignition studies and computer-controlled ignition experiments that two plasma modes exist during ignition: a glow discharge and a vapour-arc discharge. The occurrence of these modes depends on the point of interruption with respect to the phase of the 50 Hz preheat current. The vapour arc appears to be the dominant mechanism of emitter depletion. The average emitter loss per vapour-arc pulse has been quantified by radioactive Ba tracer experiments. The nature of the vapour arc has been studied by fast photography and SEM. The vapour arc involves dielectric breakdown over the non-conducting oxide mass and gives rise to explosive emitter vapourization. (author)

  16. Discharge reductions-value for money?

    International Nuclear Information System (INIS)

    Morley, R G; Coates, R; Taylor, R H

    2004-01-01

    Through the Nuclear Liabilities Management Authority White Paper, the UK Government and the Regulators have signalled a commitment to further improving 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 is 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. The paper uses the historical record of radioactive discharges from BNFL's Sellafield reprocessing site in the UK and seeks to identify what have been the key drivers for change, particularly over the past 20 years of significant discharge reductions. The paper examines the current context for ongoing and future discharges from the site, and the incorporation of the use of the concepts of best practicable environmental option and best practicable means. Intergovernmental commitments such as the OSPAR Sintra and Bremen statements and the developing UK policy framework are also considered, together with BNFL's work with a wide range of 'green' stakeholders. The paper outlines the principal components of BNFL's decision-making processes for discharge control and abatement; and how these interact with the relevant external pressures. It then analyses whether the overall drivers and outcomes align with the declared desire of the UK Government to ensure that the taxpayer receives value for money in the new national arrangements for managing historic nuclear liabilities

  17. Radioactive contamination of the Yenisei River

    International Nuclear Information System (INIS)

    Vakulovsky, S.M.; Kryshev, I.I.; Nikitin, A.I.; Savitsky, Y.V.; Malyshev, S.V.; Tertyshnik, E.G.

    1995-01-01

    Based on observational data in the period 1971-1993, radioactive contamination of the Yenisei River ecosystem was analysed within 2000 km of the site of discharges from the Krasnoyarsk Mining and Chemical Industrial Complex. Data on the content of 24 Na, 32 P, 46 Sc, 51 Cr, 54 Mn, 56 Mn, 58 Co, 60 Co, 59 Fe, 65 Zn, 90 Sr, 95 Zr, 95 Nb, 103 Ru, 106 Ru, 134 Cs, 137 Cs, 140 Ba, 141 Ce, 144 Ce and 239 Np in the river ecosystem components were generalised. Radioactive contamination of water in the near zone of discharges (within 15 km) was shown to be determine mainly by the short-lived nuclides, such as 24 Na, 32 P, 56 Mn and 239 Np, as well as 51 Cr. Outside the near zone the water contamination level decreased appreciably. According to observational data of 1973, the total contamination inventory of the river bottom in the near zone was as great as 5800 kBq m -2 . More than half was accounted for by two radionuclides: 51 Cr and 65 Zn. At a distance of 1930 km from the site of discharges a technogenic activity of bottom sediments amounted to 5 kBq m -2 and was accounted for by 137 Cs and 65 Zn. The main radionuclide accumulated in fish was 32 P. Exposure doses to aquatic organisms and population were assessed in the near and far zones of the Krasnoyarsk radioactive contamination trace. Within 250 km of the site of discharges the exposure dose to the population from a consumption of 1 kg of fish was shown to amount to an average of 10 μSv. (author)

  18. Modelling the combined impact of radionuclide discharges reaching rivers

    International Nuclear Information System (INIS)

    Hilton, J.; Small, S.; Hornby, D.; Scarlett, P.; Harvey, M.; Simmonds, J.; Bexon, A.; Jones, A.

    2003-01-01

    The Agency currently authorises direct and indirect (via sewerage systems) discharges of liquid radioactive wastes to rivers from nuclear sites and other registered users of radioactivity. Discharges are normally authorised on a site-by-site basis, taking into account the radiological assessment. Radiological assessments are normally made using dilution models to estimate radionuclide activities in the effluents themselves and in the receiving rivers. These data are then combined with information on habits and dose factor information to give a dose assessment for individuals exposed to the discharge. For each site the highest radiological impact is expected immediately downstream of the disposal point where concentrations of radionuclides and resulting doses are highest. The concentration and doses are expected to decline with increasing distance downstream of the disposal point. However, if discharges are made into the river from other establishments higher up the catchment, the total dose may be higher. Recent Environment Agency research projects provided evidence of the potential radiological significance of multiple discharges to a single river. In the light of these studies, the Agency require a robust modelling tool to assist in the assessment of the effects of combined discharges to river systems. The aim of this R and D project was to develop and test modelling tools that could be used to make assessments of the impact of multiple radiological discharge into river systems and to trial them on the upper Thames river system

  19. 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.)

  20. 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)

  1. 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

  2. Session 1984-1985. Radioactive waste. Minutes of evidence, Monday 13 May 1985. British Nuclear Fuels plc

    Energy Technology Data Exchange (ETDEWEB)

    1985-01-01

    The Environment Select Committee of the House of Commons received a memorandum from British Nuclear Fuels plc on the treatment and preparation for disposal of radioactive wastes, under the headings: introduction; waste categories; waste management policy; waste arisings; waste treatment plans; appendix I - British Nuclear Fuels plc; appendix II - the nuclear fuel cycle for Magnox, AGR and LWR reactors; appendix III - control of liquid radioactive discharges from Sellafield and their environmental impact. Representatives of BNF plc were examined on the subject of the memorandum and the minutes of evidence are recorded.

  3. Session 1984-85. Radioactive waste. Minutes of evidence, Monday 13 May 1985. British Nuclear Fuels plc

    International Nuclear Information System (INIS)

    1985-01-01

    The Environment Select Committee of the House of Commons received a memorandum from British Nuclear Fuels plc on the treatment and preparation for disposal of radioactive wastes, under the headings: introduction; waste categories; waste management policy; waste arisings; waste treatment plans; appendix I - British Nuclear Fuels plc; appendix II - the nuclear fuel cycle for Magnox, AGR and LWR reactors; appendix III - control of liquid radioactive discharges from Sellafield and their environmental impact. Representatives of BNF plc were examined on the subject of the memorandum and the minutes of evidence are recorded. (U.K.)

  4. 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)

  5. 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)

  6. Effect of Air-Curtain Discharge Speed on the Effectiveness of Vortex-like Air-Curtain Approach for Severe Accident Management

    International Nuclear Information System (INIS)

    Ullah, Sana; Yim, Man Sung

    2017-01-01

    The purpose of air-curtain installation is to isolate reactor containment from outside environment, confine the leaking radioactive material in a localized area, and minimize the impact of outside wind. The wind could blow away airborne radioactive material immediately after discharge leaving little room for effective capturing. Therefore, vortex-like air-curtain plays an important role in this process, and its effectiveness could severely influence the performance of overall system. An approach based on vortex-like air-curtain was proposed earlier for preventing spread of radioactive material to the environment and mitigate subsequent radiological consequences. Effect of air-curtain discharge speed, and discharge angle was studied, and a quantitative account of air curtain in terms of effectiveness parameter was performed in this work. It was found that for given wind speed, air-curtain effectiveness would improve with increase in air-curtain discharge speed to an extent, after which any increase in discharge velicity could deteriorate the performance, due to imbalance between discharge and wind speed. Keeping air-curtain discharge at an angle of 15° opposite to the predominant flow direction is devised.

  7. 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

  8. A national approach to the regulation of water discharge from uranium mines

    International Nuclear Information System (INIS)

    Willis, J.L.

    1985-09-01

    This paper is concerned with outlining the development of a national approach to the regulation of water discharge from uranium mines in Australia. The history of the Australian uranium industry is briefly sketched to illustrate the changes that have taken place in environmental management, and more particularly water management, over this period. The main focus of the paper is on the requirements relating to the establishment of effluent discharge limits contained in the Code of Practice on the Management of Radioactive Wastes from the Mining and Milling of Radioactive Ores, 1982. The code adopts a site specific approach to the formulation of discharge limits rather than providing generic recommendations. This approach requires the application of a rigorous and disciplined methodology

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

    International Nuclear Information System (INIS)

    Deere-Jones, T.

    1991-01-01

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

  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. 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

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

    International Nuclear Information System (INIS)

    Bessa Nisti, Marcelo; Godoy dos Santos, Adir Janete

    2008-01-01

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

  13. 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

  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. 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)

  16. 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

  17. 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.)

  18. Westinghouse Hanford Company effluent discharges and solid waste management report for calendar year 1989: 200/600 Areas

    International Nuclear Information System (INIS)

    Brown, M.J.; P'Pool, R.K.; Thomas, S.P.

    1990-05-01

    This report presents calendar year 1989 radiological and nonradiological effluent discharge data from facilities in the 200 Areas and the 600 Area of the Hanford Site. Both summary and detailed effluent data are presented. In addition, radioactive and nonradioactive solid waste storage and disposal data for calendar year 1989 are furnished. Where appropriate, comparisons to previous years are made. The intent of the report is to demonstrate compliance of Westinghouse Hanford Company-operated facilities with administrative control values for radioactive constituents and applicable guidelines and standards (including Federal permit limits) for nonradioactive constituents. 11 refs., 20 tabs

  19. Method and apparatus for removing radioactive gases from a nuclear reactor

    International Nuclear Information System (INIS)

    Frumerman, R.; Brown, W.W.

    1975-01-01

    A description is given of a method for removing radioactive gases from a nuclear reactor including the steps of draining coolant from a nuclear reactor to a level just below the coolant inlet and outlet nozzles to form a vapor space and then charging the space with an inert gas, circulating coolant through the reactor to assist the release of radioactive gases from the coolant into the vapor space, withdrawing the radioactive gases from the vapor space by a vacuum pump which then condenses and separates water from gases carried forward by the vacuum pump, discharging the water to a storage tank and supplying the separated gases to a gas compressor which pumps the gases to gas decay tanks. After the gases in the decay tanks lose their radioactive characteristics, the gases may be discharged to the atmosphere or returned to the reactor for further use

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-12-15

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

  2. Cuban regulatory politics with relationship to the Radioactive lightning rod employment

    International Nuclear Information System (INIS)

    Lopez Forteza; Yamil; Jerez Vegueria, Pablo F.; Quevedo Garcia, Jose R.; Diaz Guerra, Pedro; Dumenigo Gonzalez, Cruz

    2003-01-01

    The radioactive lightning rod employment for the protection of facilities against atmospheric discharges reached its maximum splendor in the years 80. It was in fact at the end of this decade when the technical considerations arose, with relationship to the justification of this practice that finally took to that the production of such teams was abolished. For the regulatory authorities, however, it continues having validity the question related with the control of those lightning rod that you/they stay in use, as well as the relative one to the establishment of a coherent national politics with the international practice. Presently work the results of the last 10 years of control of the radioactive lightning rod use are presented in Cuba and the radiological evaluation carried out on the base of this experience. Lastly, it exposes the Cuban regulatory politics established with relationship to the employment of this teams in the country

  3. Radioactivity Monitoring of the Irish Environment 2006

    International Nuclear Information System (INIS)

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

    2007-10-01

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

  4. 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

  5. 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

  6. 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)

  7. Performance of Models in Radiological Impact Assessment for Normal Operation. Report of Working Group 1 Reference Methodologies for Controlling Discharges of Routine Releases of EMRAS II Topical Heading Reference Approaches for Human Dose Assessment. Environmental Modelling for Radiation Safety (EMRAS II) Programme

    International Nuclear Information System (INIS)

    2017-01-01

    This publication provides the results from Working Group 1, on Reference Methodologies for Controlling Discharges of Routine Releases, of the IAEA’s EMRAS II (Environmental Modelling for Radiation Safety) programme, which ran from 2009 to 2011. This Working Group carried out an intercomparison of methods used for assessing radiological impacts to people and the environment due to authorized releases of radionuclides during normal operation of nuclear facilities. Three important types of exposure scenarios were considered, those related to atmospheric, marine and river releases. The publication describes the details of the hypothetical radioactive release scenarios, the environmental pathways considered, the environmental transfer models applied, the calculation methods and the results obtained. An analysis of the results and the main findings and conclusions relevant for the use of the described input data and methodologies in regulatory applications is included. The publication also presents considerations on selection of the ‘representative person’ and a summary of the different approaches in some States for the regulatory control of radioactive discharges. Input data is included in the annex.

  8. Processing vessel for high level radioactive wastes

    International Nuclear Information System (INIS)

    Maekawa, Hiromichi

    1998-01-01

    Upon transferring an overpack having canisters containing high level radioactive wastes sealed therein and burying it into an underground processing hole, an outer shell vessel comprising a steel plate to be fit and contained in the processing hole is formed. A bury-back layer made of dug earth and sand which had been discharged upon forming the processing hole is formed on the inner circumferential wall of the outer shell vessel. A buffer layer having a predetermined thickness is formed on the inner side of the bury-back layer, and the overpack is contained in the hollow portion surrounded by the layer. The opened upper portion of the hollow portion is covered with the buffer layer and the bury-back layer. Since the processing vessel having a shielding performance previously formed on the ground, the state of packing can be observed. In addition, since an operator can directly operates upon transportation and burying of the high level radioactive wastes, remote control is no more necessary. (T.M.)

  9. Discharge current characteristics as an 'electrical method' for glow discharge plasma diagnosis

    International Nuclear Information System (INIS)

    Toma, M.; Paraschivescu, Alina; Morminches, Anisoara

    2001-01-01

    In its simplest form, the glow discharge can be established by passing an electric current through gas between two electrodes. The gas and the electrodes are contained in an insulating envelope. In many technological applications, and not only, the plasma devices are often treated like a black box. There is a series of external parameters or control variables which can be adjusted to obtain a desired effect, namely, the operating voltage, gas pressure, gas nature, gas flow rate, magnetic field strength and magnetic field configuration, electric field geometry, interelectrode distance, and cathode characteristics. The discharge current can be controlled by each of the above control variables. The core idea of this work is the following: a lot of information about the phenomena from the discharge volume, at electrodes or at the discharge bounding wall surface, can be obtained knowing how the change of one of the control parameters influences the discharge current. The following regimes were analyzed: dark discharges (background ionization, saturation regime, Townsend regime, corona regime), glow discharge (the normal and abnormal discharge) and arc discharge (glow to arc transition, non-thermal arcs, thermal arcs). It was concluded that the nonlinearity in the shape of the discharge current characteristics as a function of an external control parameter, can be correlated with the elementary processes and the dynamics of different space charge structures generated in plasma devices. (authors)

  10. 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.

  11. Notice of intent to discharge water contaminants. Waste Isolation Pilot Plant, Eddy County, NM

    International Nuclear Information System (INIS)

    Hart, J.S.; Porter, K.R.; Register, J.K.

    1983-04-01

    This report provides information in support of a ''Notice of Intent to Discharge Water Contaminants,'' pursuant to Section 1-201 of the New Mexico Water Quality Control Commission Regulations. The anticipated discharges are not expected to move directly or indirectly into groundwater. These discharges will be caused by activities related to the construction of the Waste Isolation Pilot Plant (WIPP), a US Department of Energy (DOE) research and development program to demonstrate the safe disposal of radioactive wastes resulting from defense activities and programs of the United States. The facility is to be developed in deep layers of bedded salt. The WIPP site is located in Eddy County, New Mexico, about 26 miles east of Carlsbad. The US Department of Energy, WIPP Project Office, Albuquerque, New Mexico, as the sponsor of the project, is responsible for any discharges from the site. The following sections describe generally the WIPP construction activities. Pertinent site conditions, potential sources of discharges and their expected effects, and proposed groundwater monitoring efforts are also described

  12. 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.

  13. 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

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  15. Radioactive waste disposal areas and associated environmental surveillance data at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Oakes, T.W.; Shank, K.E.

    1979-12-01

    Environmental surveillance data have been collected around radioactive waste disposal areas for the past thirty years at Oak Ridge National Laboratory (ORNL). The wealth of data collected around the ORNL radioactive waste burial grounds is presented in this review. The purpose of this paper is to describe the solid waste burial grounds in detail along with the environmental monitoring data. The various monitoring systems are reviewed, and the liquid discharge trends are discussed. Monitoring at White Oak Dam, the last liquid control point for the Laboratory, was started in the late 1940's and is continuing. Presently, a network of five environmental monitoring stations is in operation to monitor the radionuclide content of surface waters in the White Oak Creek watershed. Facts observed during the lifetime of the disposal sites include: (1) a large amount of 106 Ru released during 1959 to 1964 due to the fact that Conasauga shale did not retain this element as well as it retained other radionuclides. (2) Large quantities of tritiated water have been released to the Clinch River in recent years, but, from a practical standpoint, little can be done to inhibit or control these releases. (3) A general downward trend in the number of curies released has been observed for all other radionuclides. A number of corrective measures that have been initiated at ORNL to reduce the radioactive liquid discharges are outlined in the paper

  16. Disposal of radioactive wastes arising in the United Kingdom from the peaceful uses of atomic energy

    CERN Document Server

    Bryant, P M

    1971-01-01

    This paper describes United Kingdom policy in relation to radioactive waste and summarises the relevant legislation ad methods of control. Data are given on the amounts of radioactivity discharged as waste from establishments of the United Kingdom Atomic Energy Authority, the nuclear power stations operated by the Electricity Generating Boards and other users of radioactive materials. Studies of the behaviour of radioactivity in the environment are reported with particular reference to food chains and other potential sources of irradiation of the public. The results of environmental monitoring are presented and estimates are made of radiation doses received by individual members of the public and larger population groups as a result of waste disposal. It is concluded that the doses received are all within the appropriate limits recommended by the International Commission on Radiological Protection, and in most cases are trivial.

  17. Manufacturing method for radioactive material containing vessel

    International Nuclear Information System (INIS)

    Kamino, Yoshikazu; Nishioka, Eiji; Toyota, Michinori.

    1997-01-01

    A containing vessel for radioactive materials (for example, spent fuels) comprises an inner cylinder made of stainless steel having a space for containing radioactive materials at the inside and an outer cylinder made of stainless steel disposed at the outer side of the inner cylinder. Lead homogenization is applied to a space between the inner and the outer cylinders to deposit a lead layer. Then, molten lead heated to a predetermined temperature is cast into the space between the inner and the outer cylinders. A valve is opened to discharge the molten lead in the space from a molten lead discharge pipe, and heated molten lead is injected from a molten lead supply pipe. Then, the discharge of the molten lead and the injection of the molten lead are stopped, and the lead in the space is coagulated. With such procedures, gaps are not formed between the lead of the homogenized portion and the lead of cast portion even when the thickness of the inner and the outer cylinders is great. (I.N.)

  18. 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

  19. Ventilation of radioactive enclosures; Ventilation des enceintes radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Caminade, F; Laurent, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    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{sup 3}). The performances of three types of 'ventilators', and the modifications provided by the addition of filters, are measured and compared. (author) [French] Les manipulations oceaniques, physiques et chimiques sur des produits radioactifs doivent s'effectuer dans des enceintes convenablement ventilees. L'air extrait ne peut etre rejete dans l'atmosphere qu'apres une filtration correcte. La puissance des installations de ventilation est fonction des dimensions de l'enceinte et de son utilisation. Le choix des types de filtres est determine par l'etat physique et la nature ehimique des corps radioactifs manipules. Notre etude porte sur l'equipement individuel d'installations de petites dimensions: boites a gants, boites a pinces et, a la rigueur, enceintes de production (volume maximum utilisable 5 m{sup 3}). Nous mesurons et comparons les performances de trois types de 'ventilateurs' et les modifications apportees par l'adjonction de filtres. (auteur)

  20. 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

  1. 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

  2. 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)

  3. Worldwide marine radioactivity studies assessing the picture

    International Nuclear Information System (INIS)

    Povinec, P.P.; Togawa, O.

    1998-01-01

    A growing number of sources of radioactivity from human activities are found in the marine environment. They are known to include global nuclear fallout following atmospheric weapons tests, the Chernobyl accident, discharges of radionuclides from nuclear installations, past dumping of radioactive wastes, nuclear submarine accidents, contributions from nuclear testing sites, loss of radioactive sources, and the burn-up of satellites using radioisotopes as power sources. Overall, the world's marine environment contains radionuclides that differ from one region to another. Differences are due to dynamic marine environmental processes and the particular source of radionuclides in a region. Scientific assessments of marine radioactivity, therefore, require knowledge of both the source terms and oceanic processes. Radioactivity now is deposited unevenly over the world's oceans. Global fallout is known to be mainly due to nuclear weapon tests carried out in the 1960s. On the other hand, discharges from nuclear fuel reprocessing plants or past dumping of liquid and solid radioactive wastes generally are confined to more localized areas. Even so, soluble radionuclides have been transported over long distances by prevailing ocean currents. To estimate radionuclide inputs from local sources, scientists need to better understand the distribution of radionuclides throughout the world's oceans and seas. The understanding is important for analysing the results from scientific investigations of localized areas, such as part dumping sites, which then can be reviewed more thoroughly. As a contribution to fuller understanding of the marine environment, the IAEA's Marine Environment Laboratory (MEL) started a five-year project in 1996 entitled ''Research on Worldwide Marine Radioactivity (MARS)''. The work is supported by Japan's Science and Technology Agency (STA). This article briefly review this project, and describes related research activities and scientific investigations of MEL

  4. Radioactivity in the northern seas of europe

    International Nuclear Information System (INIS)

    Carvalho, Fernando P.; Madruga, Maria Jose; Oliveira, Joao M.; Gouveia, Jorge M.; Silva, Lidia

    2004-01-01

    The recent accidents with nuclear powered Russian submarines, such as the Kursk and the K-159, that took place in the Arctic Seas, give rise to high concerns of the public and the media about the radioactive contamination of marine ecosystems and radiological safety of the European population. Those accidents were preceded by decades of discharges of radioactive liquid effluents into coastal seas of Europe and the dumping of packed radioactive waste into the North Atlantic. Being Portugal one country with high consumption rate of seafood caught in its own coastal waters as well as in far seas including the Ar tic seas, the investigation of the radioactive contamination of fish was investigated. Analysis of fish from the Sea of Labrador, Sea of Iceland and Barents Sea, has shown that gamma-emitting radionuclides of artificial origin are in general not detected. The only gamma emitting radionuclide present is Cs-137, in concentrations not higher than 0.3 Bq/kg. This radionuclide originates in the deposition of radioactive fallout following nuclear weapon tests performed in the fifties and sixties. Radionuclides in fish from northern regions and in fish from the Portuguese coast generally are present in concentrations lower than those currently reported for fish from the Irish Sea and the Baltic Sea, impacted with the discharges of radioactive waste from Sellafield and the deposition of fallout from Chernobyl, respectively. Nevertheless, the potential for future accidents and the radioactive waste dumped into the North Atlantic may in the future modify this scenario and potentially increase the currently very low radionuclide concentration in fish included in the Portuguese diet. Therefore, the research and radiological surveillance must be maintained in order to monitor the radiological risk and to ensure the quality of food available to consumers. (author)

  5. Technology of radioactive waste management avoiding environmental disposal

    International Nuclear Information System (INIS)

    1964-01-01

    This report considers present radioactive waste management methods and practices. In addition, present research and development activity designed to minimize discharges to the environment are noted. During its deliberations the Panel was able to define certain avenues of research and development which should be explored to enable the almost complete containment of wastes. The experience and practices at establishments, where, for geographical, geological or other reasons, discharges of radioactive material to the environment are extremely small, served as the starting point for the Panel's deliberations. Details of the experience and practice, together with the results obtained at these establishments, are summarized in Part I and described in more detail in Part II of this report. 48 refs, 89 figs, 11 tabs

  6. 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)

  7. The radiological exposure of man from radioactivity in the Baltic Sea.

    Science.gov (United States)

    Nielsen, S P; Bengtson, P; Bojanowsky, R; Hagel, P; Herrmann, J; Ilus, E; Jakobson, E; Motiejunas, S; Panteleev, Y; Skujina, A; Suplinska, M

    1999-09-30

    A radiological assessment has been carried out considering discharges of radioactivity to the Baltic Sea marine environment since 1950. The sources of radioactivity that have been evaluated are atmospheric nuclear-weapons fallout, fallout from the Chernobyl accident in 1986, discharges of radionuclides from Sellafield and La Hague transported into the Baltic Sea, and discharges of radionuclides from nuclear installations located in the Baltic Sea area. Dose rates from man-made radioactivity to individual members of the public (critical groups) have been calculated based on annual intake of seafood and beach occupancy time. The dose rates to individuals from the regions of the Bothnian Sea and Gulf of Finland are predicted to be larger than from any other area in the Baltic Sea due to the pattern of Chernobyl fallout. The dose rates are predicted to have peaked in 1986 at a value of 0.2 mSv year-1. Collective committed doses to members of the public have been calculated based on fishery statistics and predicted concentrations of radionuclides in biota and coastal sediments. The total collective dose from man-made radioactivity in the Baltic Sea is estimated at 2600 manSv, of which approximately two-thirds originate from Chernobyl fallout, approximately one-quarter from atmospheric nuclear-weapons fallout, approximately 8% from European reprocessing facilities, and approximately 0.04% from nuclear installations bordering the Baltic Sea area. An assessment of small-scale dumping of low-level radioactive waste in the Baltic Sea in the 1960s by Sweden and the Soviet Union has showed that doses to man from these activities are negligible. Dose rates and doses from natural radioactivity dominate except for the year 1986 where dose rates to individuals from Chernobyl fallout in some regions of the Baltic Sea approached those from natural radioactivity.

  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. 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

  10. Determination of radionuclides in discharged water from gold ...

    African Journals Online (AJOL)

    The levels of radionuclides concentrations in discharged water from gold processing into the environment of Bogoso (Ghana) were determined using radioanalytical techniques. Radioactivity screening was first carried out to identify physical and chemical processing stages that might be concentrating the radionuclides.

  11. Method of processing low-level radioactive liquid wastes

    International Nuclear Information System (INIS)

    Matsunaga, Ichiro; Sugai, Hiroshi.

    1984-01-01

    Purpose: To effectively reduce the radioactivity density of low-level radioactive liquid wastes discharged from enriched uranium conversion processing steps or the likes. Method: Hydrazin is added to low-level radioactive liquid wastes, which are in contact with iron hydroxide-cation exchange resins prepared by processing strongly acidic-cation exchange resins with ferric chloride and aqueous ammonia to form hydrorizates of ferric ions in the resin. Hydrazine added herein may be any of hydrazine hydrate, hydrazine hydrochloride and hydranine sulfate. The preferred addition amount is more than 100 mg per one liter of the liquid wastes. If it is less than 100 mg, the reduction rate for the radioactivety density (procession liquid density/original liquid density) is decreased. This method enables to effectively reduce the radioactivity density of the low-level radioactive liquid wastes containing a trace amount of radioactive nucleides. (Yoshihara, H.)

  12. 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

  13. 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

  14. Advantages of the segregation step for the radioactive waste management

    International Nuclear Information System (INIS)

    Medeiros, Regina Bitelli; Mattos, Maria Fernanda S.S.

    2002-01-01

    Due to the increasing use of radioactive materials in the research activities, the waste management is essential to guarantee personnel safety and the preservation of the environmental quality. It is possible to determine the date of discharge in the public sewage treatment system based on the estimated activity of the radioactive waste and on the solid waste discharge limit of 74 Bq/g as recommended by the radiation protection rules. The goal of this work is to demonstrate the advantages of the waste segregation by specific activity as a means of minimization of the stored waste. The residual specific activity and volume were estimated in the several steps of assays using 32 P and 3 H. The storage times were calculated and compared with the estimated time considering the residual activity as 2 % of the total activity used in the experiment. The segregation by steps of the assay allowed for the reduction of the waste volume and stored time. In the assays with 3 H only 20 % of the total waste generated was stored and in the assays with 32 P it was possible to discharge 90 % of the radioactive waste after 38 days. (author)

  15. 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)

  16. Radioactivity in the environment. Report for 2001 : a summary and radiological assessment of the Environment Agency's monitoring programmes

    International Nuclear Information System (INIS)

    2003-01-01

    The Environment Agency has wide-ranging responsibilities and powers to protect and, where necessary, improve the environment in England and Wales. The Agency also has a duty to protect the environment in a way that works towards sustainable development. This involves meeting the needs of the present generations without compromising the ability of future generations to meet their own needs. One of the Agency's functions is to administer and enforce the Radioactive Substances Act 1993 (RSA 93) in England and Wales. The Agency exercises regulatory control over the disposal of radioactive waste, by means of authorisations issued under the RSA 93. During 2001, 34 nuclear sites and 850 non-nuclear premises held authorisations to discharge radioactive waste. The Agency seeks to secure continuous improvement in the protection of the public and the environment from the disposal of radioactive wastes. In 1998, the Oslo and Paris Commission (OSPAR) strategy for radioactive substances was agreed by Ministers at Sintra, Portugal, to prevent pollution of the North East Atlantic maritime area through progressive and substantial reductions in discharges, emissions and losses of radioactive substances. In July 2002, the UK Government published the UK Strategy for Radioactive Discharges 2001-2002, which sets out the UK's plans to implement the OSPAR strategy. Achieving the requirements and targets in the UK strategy is a key objective of the Agency in implementing its long-term Vision for the Environment. The Government has also consulted upon draft Statutory Guidance to the Environment Agency on regulation of radioactive discharges from nuclear sites, which will provide the vehicle through which the UK strategy will be implemented. A key principle within the draft Statutory Guidance is the need for progressive reduction in discharges and discharge limits for sites as a whole. The Agency is taking account of the UK strategy and draft Statutory Guidance in its regulatory decisions on

  17. Marine environmental radioactivity surveys at nuclear submarine berths in the UK, 1989

    International Nuclear Information System (INIS)

    Fuller, D.; Casey, E.

    1990-12-01

    This report presents the results of the marine environmental radioactivity monitoring surveys of intertidal and underwater areas around nuclear submarine berths in the UK, including the US Naval Base at Holy Loch, which were carried out by Defence Radiological Protection Service (DRPS) during 1989. Also included are results of smaller scale intertidal surveys carried out by local staff but co-ordinated by DRPS, and as an Appendix a report by the US Navy detailing the results of their environmental radioactivity monitoring programme at Holy Loch. Cobalt-60, the nuclide of major importance in naval discharges, was detected in a number of samples but in most cases was attributable to discharges by other operators. Concentrations in any case were found to be low, and at no survey location did the calculated annual radiation dose commitment to the most exposed members of the general public due to the presence of cobalt-60 exceed 1% of the ICRP principal dose limit for members of the public (1mSv). It is concluded that existing discharge arrangements are providing effective control over environmental levels of cobalt-60, and that there has been no radiological hazard to any member of the general public during 1989 from the operation of nuclear powered submarines. These findings have been confirmed by independent monitoring undertaken by the Ministry of Agriculture, Fisheries and Food Directorate of Fisheries Research. (author)

  18. 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.

  19. 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.

  20. Assessment of long-term effects of radionuclides discharged from a phosphate ore processing plant to the environment

    International Nuclear Information System (INIS)

    Degetti, S.; Mazzoti, D.; Dall'Ara, S.; DeJoanna, C.

    1997-01-01

    The Northern Adriatic Sea was interested by continuous direct discharge of phosphogypsum from a local phosphate fertilizer industry up to 1985 following a productive activity of about twenty years.As it is known, due to the remarkable amounts of natural radioactivity connected with the productive cycle of fertilizers from phosphate ores, the release to the environment of huge amounts of potentially hazardous wastes might be in principle of major radioecological concern.In this respect Ra-226 and its decay products are expected to be the main responsible of radioactivity background enhancement.Taking into account that discharge at sea (depth 30-35 m) was interrupted over ten years ago, following the closing of the plant, the main scope of this investigation was to assess the long-term effect of the disposal of phosphogypsum in the marine environment and in particular the possible enrichment of the radioactive fraction after solubilization of the gypsum carrier. In order to assess the actual radioecological influence of discharged slurries on the marine environment a preliminary sampling was carried out.Radioactivity data obtained from sediment cores clearly indicate anomalies in respect to typical 'background' values obtained from homologous samples collected in an unaffected area in proximity of the disposal site.As an example, Ra-226 activities in sediment were found to be one hundred fold higher than natural background.Radioactivity data from sediments cores collected in sites interested by bottom sea currents coming from discharge area will be also reported and discussed.(authors)

  1. 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

  2. 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

  3. 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

  4. 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)

  5. United Kingdom government policy towards radioactive waste

    International Nuclear Information System (INIS)

    Pritchard, G.

    1986-01-01

    There are three areas of radioactive waste management which exemplify, beyond any reasonable doubt, that the United Kingdom has in the past (and intends in the future), to pursue a policy of dispersal and disposal of radioactive wastes: These are: (I) dumping of low-level waste in the deep ocean and, on a parallel, seabed emplacement of highly active waste; (II) the liquid discharges from Windscale into the Irish Sea; and (III) land dumping of low- and intermediate-level waste

  6. 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.

  7. Radioactivity Monitoring of the Irish Environment 2007

    International Nuclear Information System (INIS)

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

    2008-10-01

    This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) in 2007. This programme aims to assess the exposure of the Irish population to artificial radioactivity in the envorinment, to review the temporal and geographical distribution of contaminating radionuclides and to maintain systems and procedures which would allow a rapid assessment of environmental contamination to be made in the event of a radiological emergency. In additiopn, some natural radioactivity exposure pathways are included in the programme including radioactivity in surface and ground drinking water. Radioactivity is present in the environment due to natural oprocesses, the testing of nuclear weapons in the atmosphere, past nuclear accidents such as that at Chernobyl in the Ukraine and the routine discharge of radionuclides from nuclear installations. Liquid discharges from the British Nuclear Group reprocessing plant at Sellafield in Cumbria in the north-west of England continue to be the dominant source of artificial radioactivity in the Irish marine environment. The key elements of the monitoring programme implemented by the RPII in 2007 included; assessment of ambient radioactivity based on measurements of radioactivity in air and of external gamma dose rate at permanent monitoring stations located throughout the country; assessment of levels of radioactivity in drinking water; assessment of levels of radioactivity in foodstuffs based on measurements of total diet, milk and various ingredients; assessment of levels of radioactivity in the Irish marine environment based on sampling and measurement of seawater, sediment, seaweed, fish and shellfish. The RPII monitored airborne radioactivity at twelve stations located throughout the country. One of these stations is equipped with a high volume sampler, which allows background concentrations of caesium-137 to be measured; another is equipped to

  8. 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....

  9. Radioactivity in food and the environment, 2002

    International Nuclear Information System (INIS)

    2003-01-01

    This report contains the results of radiological monitoring of food and the environment throughout the United Kingdom, the Channel Islands and the Isle of Man. The primary purpose of the monitoring programmes is to provide an independent check on the effects of discharges made by users of radioactive materials in the United Kingdom, and to ensure that any radioactivity present in food and the environment does not compromise public health.' For the first time, it represents a comprehensive summary of results across the United Kingdom from programmes sponsored by the Environment Agency, the Environment and Heritage Service, the Food Standards Agency and the Scottish Environment Protection Agency. The results of these monitoring programmes demonstrate that in 2002 even the most exposed members of the public received radiation doses from food and other pathways that were below the statutory United Kingdom annual dose limit to members of the public of 1 mSv (millisievert), European Union limits and Government targets. Assessed doses at all major sites in the United Kingdom are shown in Figure S and are detailed in the Summary Table. The highest radiation doses were received by a group of high-rate consumers offish and shellfish in Cumbria. The doses received by these consumers are a combination of contributions from liquid discharges from both Sellafield and from radioactivity in the environment as a result of past discharges from the Rhodia Consumer Specialties Ltd. (formerly Albright and Wilson) plant at Whitehaven. The dose to these high-rate consumers (including external doses) from Sellafield discharges was estimated to be 0.19 mSv in 2002 compared with 0.15 mSv in 2001. Concentrations in food and dose rates were largely unchanged in 2002 though there were some small increases in concentrations of tritium, carbon-14 and technetium-99 in seafood. The main reason for the increase in dose was an increase in the amount of seafood eaten. This group also received an

  10. Treatment of short-lived radioactive wastes

    International Nuclear Information System (INIS)

    Yamaguchi, Chiri

    1976-01-01

    Recently short life nuclides have come to be utilized increasingly as diagnostic radioisotopes, and Tc-99m (half-life; 6.05 hours) and Ga-67 (half-life 7.79 hours) are replacing the most nuclides fomerly used in vivo test. Such development of radioactive products inevitably causes the rapid increase of their wastes. At present, the radioactive wastes produced by hospitals and university laboratories in Japan are collected by the Japan Radioisotope Association, and treated by the Japan Atomic Energy Research Institute. These wastes are divided into combustibles and incombustibles to store in the store house in the Japan Atomic Energy Research Institute. The present law in Japan contains the contradiction which treats the matter with one several millionth of radioactivity after decay same as the original radioactive matter. Thus solid must be stored permanently, while gas and liquid can be discharged after dilution. (Kobatake, H.)

  11. Liquid radioactive wastes from hospitals by polymeric membrane; Tratamiento de residuos liquidos radiactivos hospitalarios mediante membranas polimericas

    Energy Technology Data Exchange (ETDEWEB)

    Arnal, J M; Sancho, M; Verdu, G [Universidad Politecnica de Valencia (Spain); Campayo, J M [LAINSA (Spain)

    1998-12-01

    Streams containing I``125 produced from RIA process, classified as radioactive waste of low activity, are generated by all different treatments applied in IN VITRO techniques. Consequently, an accumulation of solutions containing I``125 is produced in the order of 50-100 L/month approximately. The storage at sanitary centres and the accumulation caused by it creates a serious problem in the hospital. According to the specific activity and the installation spill authorization, one can choose between three ways of handling: direct discharge, temporal storage until the radioactive waste come to decay and then discharged, waste management by the authorised company (ENRESA). If the third way of discharge is applied the treatment of waste using membranes should be considered. Using membranes, important reduction coefficients in volume in the order of 10:1 are obtained. The aim of this work is the declassification of the I``125 solutions as a liquid radioactive waste using membrane techniques. Both, a radioactive concentrated waste and non-contaminated waste are obtained. (Author)

  12. 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)

  13. Some bioindicators of radioactive contamination

    International Nuclear Information System (INIS)

    Cosma, C.; Cozmuta, I.; Micu, C.

    1996-01-01

    The lessons that could be learned from the Chernobyl accident were numerous and encompassed all areas. One of those lead to the discovery of new monitoring methods which also supply to cost-effective solutions to control contaminant radioactive discharges in the environment. Through the measurements performed, we discovered that some samples, because of their radioactive content restrained also for long periods of time, can be used as bioindicators. Hen eggs between May 1-30 1986 were analysed (identification of radionuclides with a Ge(Li) detector and measuring of total gamma activity with NaI(T1)). Various aspects pursued revealed that eggs are precious witness of vegetable food contamination with fission products, especially Ba-140 and I-131, behaving as radionuclide separators (Ba-140 in egg shell -301 Bq/egg and I-131 in the content - 182 Bq/egg). Some of the most important pharmaceutical plants from Transylvania measured during 1986-1994 period presents high cesium radioactivity. The perennial plants (as Lichen Islandicus) for the same period accumulated a greater activity that the annual ones. Especially the lichen, because of the their slow decreasing activity are suitable as biological detectors also in retrospective measurements. Measuring the activity of some pollen samples was rediscovered. The pollen grains, during their transport in air by the bees, are acting like a filter for radionuclides so that we could use they to monitor the deliverance of these substances in air. (author)

  14. Ignition method of corona discharge with modulation of the field in ion source of ion mobility spectrometer

    International Nuclear Information System (INIS)

    Gromov, Evgeniy

    2011-01-01

    The new method for the ignition of the corona discharge has been developed, which improves the stability of the ion mobility spectrometer and the resolution of the instrument. The system of forming a corona discharge without additional electrodes, which are used in a number of known structures for the pre-ionization, has been developed. This simplifies the design of the proposed source and an electronic control circuit. IMS technology is widely used in different civil and military fields for vapor-phase detection of explosive, narcotics, chemical warfare agents, biology molecules and so on. There are set of methods whose are used for the ionization of molecules under analysis. They are the following: radioactive ionization, ultraviolet photoionization, laser ionization, electric field ionization, corona spray ionization, electro spray ionization, roentgen ionization, and surface ionization. All these methods has their own advantages and disadvantages. A comparing of ion mobility spectra of non-polar hydrocarbons for photoionization, corona discharge ionization and 63 Ni ionization, had carried in. In our work we have investigated four types of IMS spectrometers whose use different sources for molecules under analysis ionization. They use radioactive ionization, ultraviolet photoionization, laser ionization, and roentgen ionization. The traditional explosives had investigated in experiments. In electricity, a corona discharge is an electrical discharge brought on by the ionization of a fluid surrounding a conductor, which occurs when the potential gradient (the strength of the electric field) exceeds a certain value, but conditions are insufficient to cause complete electrical breakdown or arcing.

  15. 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

  16. 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

  17. 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

  18. 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.

  19. Introduction to Part 3 - Pollution and protection of the seas: radioactive materials, heavy metals and oil

    International Nuclear Information System (INIS)

    Kinne, O.

    1984-01-01

    In the introduction to Vol 3. Pt 5. of Marine Ecology, the essentials of ocean management and pollution control are discussed. Human activities reducing the quality of life in the marine environment and causing negative effects on human health, resources and marine ecosystems must be controlled. In particular there must be international cooperation and control in the disposal of radioactive wastes, oils and pesticides and the discharge of organic chemicals. Long-term ecological research, monitoring and legislation are necessary to ensure the maximum degree of ecosystem protection. (U.K.)

  20. Apparatus for measuring a concentration of radioactivity

    International Nuclear Information System (INIS)

    Tabuchi, H.; Ogushi, A.

    1978-01-01

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

  1. 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).

  2. 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

  3. 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.

  4. 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

  5. Environmental monitoring for radioactivity in Scotland: 1981 to 1985

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1987-01-01

    A bulletin, prepared by Her Majesty's Industrial Pollution Inspectorate (HMIPI) of the Scottish Development Department (SDD), contains a summary of the environmental monitoring for radioactivity carried out in Scotland as part of the statutory procedure for ensuring the safety of radioactive waste disposals from nuclear facilities. The monitoring results for discharges to both the atmosphere and the sea over the period 1981 to 1985 are presented for BNFL's Chapelcross and Sellafield Works, UKAEA Dounreay Nuclear Power Development Establishment, SSEB Hunterston Power Station and MOD Naval Installations. It is concluded that public radiation exposure in Scotland from environmental radioactivity arising from radioactive waste disposal has been well within the internationally recommended limits.

  6. 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

  7. 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.

  8. A granular refillable filter for glas-flows contaminated by radioactive impurities

    International Nuclear Information System (INIS)

    Bonn, J.W.

    1975-01-01

    Description is given of a granular charcoal refillable filter adapted to adsorb the radioactive impurities of a gaseous flow. That flow comprises a number of filtering layers, the consumed charcoal of which can be discharged by a pneumatic device without exposing the personnel to radioactivity. This can be applied to emergency devices in nuclear facilities [fr

  9. Method of treating radioactive waste waters from uranium industry

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  10. Environmental system applied to radioactive liquid effluent release

    International Nuclear Information System (INIS)

    Nisti, Marcelo Bessa

    2009-01-01

    without monetary and environmental costs. The results showed that the dilution factors values varied according to the employed radioisotope, in increasing order from 3 H, 137 CS, 54 Mn, 60 Co to 65 Zn, following to each chemical element characteristics, significant variance among hydrogen, alkaline metal and transition metals was also showed. The dilution factor averages obtained in the first and second day of the releases were respectively 4,3 and 7,4 for 3 H, 12,0 and 16,1 for 54 Mn, 12,6 and 14,2 for 60 Co, 12,0 and 27,9 for 65 Zn, 6,2 and 13,9 for 137 Cs. This is the first study about intra-institutional dilution factor estimation using anthropic radiotracers, without any addition costs. The obtained results contribute with the subsidies to the improvement of the environmental conduct and to establish optimized procedures, under current legislation. The dilution factors were estimated in an operations and laboratory study, in only one controlled discharge of the storage tank TR1. This radioactive tracers study will have to be repeated, in order to create an institutional database. The environmental systemic study must be established by each case, depending on the characteristics of the area, the institution and the released effluents.(author)

  11. 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.)

  12. 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)

  13. 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)

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

    International Nuclear Information System (INIS)

    Ma Wenlin; Cao Jianzu; Fang Dong

    2008-01-01

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

  15. Electronic archive system for the management of historic radioactive waste

    International Nuclear Information System (INIS)

    Calin, M. R.; Garlea, C.; Petre, A. R.; Serbina, L.

    2005-01-01

    The development of nuclear activities in Magurele, Ilfov, during the last decades has led to the accumulation of an important quantity of radioactive waste. In addition to this, there is also a large number of former radioactive sources, now shut and removed from use, currently stored at IFIN-HH. This project deals with the discharge of historic waste storages belonging to the following nuclear units: - the WWR-S nuclear reactor - (the main reactor hall, the pump hall, the hot cells and annexes); - C.P.R. - used filters storage; - S.T.D.R. - storage for both historic radioactive waste and used filters; - shut sources in the storehouses in the 'Texas Bunker' building and annexes. For a modern management, including a proper system of quality insurance, an archiving system became needed. The electronic archive is based on several informational streams: the activity of storing historic radioactive waste; - the activity of locating historic radioactive waste; - the radiological descriptions of the storehouses and their influence areas; - the determination of the waste's composition. So as to reach these objectives, information regarding the following is necessary: the storehouse's inventory, the historic radioactive waste's characteristics and proprieties, the neighbors of this facility, the way in which the environment and the personnel involved in the operations are being influenced, the preparing of discharge operations, semblances. The data base conceived to tackle the problems of data related to nuclear waste management has been programmed in Microsoft Access (Microsoft Office). (authors)

  16. Radioactive waste management - a general and specific task of national and international importance

    International Nuclear Information System (INIS)

    Slavchev, A.

    2008-01-01

    Planning of a durable sustainable development requires balance between economic interests, social consequences and preservation and reproduction of the environment and human potential. For the profound investigation of the ecological problems it is particularly important to run alongside the analysis of the population health status and the growing emphasis on effective measures to be undertaken to solve them on a long-term basis in order to restrict and reduce the potential risk. One special task in this field concerns the radioactive waste in medicine, especially the unsealed radioactive sources for diagnostics and metabolic therapy and those handling after use. In the scope of the European legislature and the respective Bulgarian laws the radioactive waste is subject of severe requirements and special monitoring and control. The present paper describes the situation in the country linked to the organization of the RAW storage, processing and discharging including the prerequisites, the risks factors, the technological solutions and the potentialities for realization as well as the concerned responsible bodies. (author)

  17. Non-fuel cycle radioactive waste policy in Turkey

    International Nuclear Information System (INIS)

    Izmir, A.I.; Uslu, I.

    2001-01-01

    Full text: Introduction. Radioactive wastes generated in Turkey are mostly low level radioactive waste generated from the operation of one research reactor, research centers and universities, hospitals, and from radiological application of various industries. It involves both short-lived and long lived radionuclides. In general, this includes radioactive materials, which are no longer useful and have their origin from practice or intervention both with unsealed and sealed sources. Radioactive Waste Management in Turkey. Utilisation of radioactive materials in Turkey requires special authorisations and falls under legal rules, in particular under the Radiation Safety Regulation of 24th March 2000 (Official Gazette number: 20983) outlining a general regulation for the protection of the population and workers against the danger of ionising radiation and subsequent amendments. There is also a requirement enforced by the Regulations for Radioactive Wastes Exempt from Regulatory Authority Control (published on 15 January 2000, Official Gazette number: 23934) that identifies the limits and other conditions for the discharges of radioactive substances to the environment. Radioactive waste is generally understood as material for which no further use is foreseen, and which has been managed in a system of reporting, authorisation and control as specified in International Atomic Energy Agency (IAEA) recommendations or national legislation. In this paper radioactive waste is considered in two categories: as originated from unsealed sources or from sealed sources. a) Management of Unsealed Sources. Unsealed radionuclides are utilised in human medicine for in vivo diagnosis, metabolic therapy and in vitro biological analysis. The most common types of radionuclides used in Turkey are C-14, Co-57, Cr-51, Fe-59, Ga-67, H-3, I-123, I-125, I-131, In-111, Mo-99, P-32, P-33, Re-186, S-35, Sr-89, Sr-90, Tc-99, Tl-201, Xe-133, Y-90 which are import of radiopharmaceuticals to Turkey in

  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. Treatment of radioactive contaminated water in nuclear power plants

    International Nuclear Information System (INIS)

    1978-12-01

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

  20. 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.)

  1. Non-radioactive verification test of ZRF25 radioactive combustible solid waste incinerator

    International Nuclear Information System (INIS)

    Wang Peiyi; Li Xiaohai; Yang Liguo

    2013-01-01

    This paper mainly introduces the construction and test run of ZRF25 radioactive combustible solid waste incinerator, by a series of simulating waste tests, such as 24 h test, 72 h test, 168 h test, making a conclusion that the incinerator runs reliably. In addition, all of the indexes (such as treatment capacity, volume reduction coefficient, clinker ignition loss of incineration ash) meet the requirements of contract and pollution discharging standards. (authors)

  2. 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

  3. 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)

  4. Low-level radioactive wastes: Their treatment, handling, disposal

    Energy Technology Data Exchange (ETDEWEB)

    Straub, Conrad P [Robert A. Taft Sanitary Engineering Center, Radiological Health Research Activities, Cincinnati, OH(United States)

    1964-07-01

    The release of low level wastes may result in some radiation exposure to man and his surroundings. This book describes techniques of handling, treatment, and disposal of low-level wastes aimed at keeping radiation exposure to a practicable minimum. In this context, wastes are considered low level if they are released into the environment without subsequent control. This book is concerned with practices relating only to continuous operations and not to accidental releases of radioactive materials. It is written by use for those interested in low level waste disposal problems and particularly for the health physicist concerned with these problems in the field. It should be helpful also to water and sewage works personnel concerned with the efficiency of water and sewage treatment processes for the removal of radioactive materials; the personnel engaged in design, construction, licensing, and operation of treatment facilities; and to student of nuclear technology. After an introduction the following areas are discussed: sources, quantities and composition of radioactive wastes; collection, sampling and measurement; direct discharge to the water, soil and air environment; air cleaning; removal of radioactivity by water-treatment processes and biological processes; treatment on site by chemical precipitation , ion exchange and absorption, electrodialysis, solvent extraction and other methods; treatment on site including evaporation and storage; handling and treatment of solid wastes; public health implications. Appendices include a glossary; standards for protection against radiation; federal radiation council radiation protection guidance for federal agencies; site selection criteria for nuclear energy facilities.

  5. 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

  6. 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.

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

    International Nuclear Information System (INIS)

    1996-01-01

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

  8. 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)

  9. 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 ...

  10. 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

  11. Fifty years of studies on environmental radioactivity in Peru

    International Nuclear Information System (INIS)

    Osores, Jose M.; Gonzales, Susana; Martinez, Jorge; Lopez, Edith; Jara, Raul; Anaya, Aurelio

    2008-01-01

    In May of 1962, due to the explosions carried out by the Commission of Atomic Energy of the United States in the Christmas Island, a group of professionals of the 'Junta de Control de Energia Atomica' of Peru, created in 1957, carried out experimental evaluations of atmospheric radioactivity, obtaining acceptable results regarding those of Naval US Research Laboratory, this was the beginning of the Laboratory of Atmospheric Radioactivity that begins to operate permanently in February of 1964. In 1966, France began a program of nuclear tests in the French Polynesian, generating concern due to the meteorological conditions that could affect the peruvian population. With the support of experts and equipments on the part of the government from France, the Laboratory of Environmental Radioactivity began their activities in August of 1966. At the present time, the Laboratory of Environmental Radioactivity is located in the Nuclear Center RACSO of the 'Instituto Peruano de Energia Nuclear' and it carries out the following programs: Radiological Environmental Surveillance in the Influence Area of the Nuclear Center, Nationwide Radiological Environmental Surveillance, Marine Radiological Environmental Surveillance, Radiological Environmental Surveillance in the Peruvian Antarctic Region and Surveillance of the Radioactive Contamination of Foods. The results of the evaluations of the programs of radiological environmental surveillance, developed nationwide from 1962, show one gradual decrease of the levels of environmental radioactivity. Significant concentrations of Cs-137 and Be-7 were found in the Antarctic region, and, in the area of influence of the nuclear center RACSO, environmental discharges of I-131, Cs-137, Co-60, Cs- 134 and Te-123m were detected, however, the concentrations did not present radiological risk for the population. (author)

  12. 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.

  13. On levels unconditional declassification of solid materials with very low radioactive content and downloads liquids and gases to the environment

    International Nuclear Information System (INIS)

    2004-01-01

    This guide aims to establish radiological criteria for declassification (waiver) of the radioactive material of radiological regulatory control and levels unconditional clearance for solid materials and the authorized discharge limits for liquids and gases to the environment that meet these criteria for exposure scenarios acceptably conservative. This Guide to radioactive waste from the apply industrial, medical and research, which they will be managed as waste conventional. This guidance excludes from its scope the option of recycling and reuse of materials that have been declassified and wastes arising from activities and practices which naturally occurring radionuclides present are.

  14. 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

  15. 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.)

  16. A method for prevention of radioactive material release

    International Nuclear Information System (INIS)

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

    1975-01-01

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

  17. Management responsible for the radioactive waste in the University of Costa Rica

    International Nuclear Information System (INIS)

    Mora, P.; Varela, A.

    2003-01-01

    Through the University Plan de Seguridad Radiologica (PSR), established in 1990, radioactive wastes generated by the University of Costa Rica (UCR) personnel are handled. They are properly collected, stroraged and disposed. The waste room is used by the following centers: Laboratorio de Fisica Nuclear Aplicada, Instituto de Investigaciones en Salud, Centro de Biologia Celular y Molecular and Centro de Investigaciones en Contaminacion Ambiental. The PSR has prestorage procedures, internal controls inside the waste room, protocols for storage, withdraw of sources, and discharges to the environment according to national and international legislation. The main radioactive wastes in liquid or solid forms contain p 32 , I 125 , S 35 y C 14 that eventually be disposed as excempted materials. The waste room stores sources with the following radionuclides Cs 137 , U 238 , Th 232 , Sr 90 , Ra 226 , Cd 109 , Cf 252 and Am 241 . It has 96 permanent sources and 52 that will be disposed. The PSR allows the University to have a centralized facility for the safe management of all radioactive waste generated locally. (Author) [es

  18. Method of solidifying radioactive laundry wastes

    International Nuclear Information System (INIS)

    Yasumura, Keijiro

    1984-01-01

    Purpose: To enable to solidify radioactive laundry wastes containing non-ionic liquid detergents less solidifiable by plastic solidification process in liquid laundry wastes for cloths or the likes discharged from a nuclear power plant. Method: Radioactive laundry wastes are solidified by using plastic solidifying agent comprising, as a main ingredient, unsaturated polyester resins and methylmethacrylate monomers. The plastic solidifying agents usable herein include, for example, unsaturated polyester resins prepared by condensating maleic anhydride and phthalic anhydride with propylene glycol and incorporated with methylmethacrylate monomers. The mixing ratio of the methylmethacrylate monomers is preferably 30 % by weight based on the unsaturated polyester resins. (Aizawa, K.)

  19. 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.)

  20. The use of uranium fluxes as safety indicators of radioactive waste repositories

    International Nuclear Information System (INIS)

    Miller, W.M.; Hooker, P.J.

    2002-01-01

    Natural analogues based on uranium deposits are commonly used to represent the long-term behaviour of radioactive waste repositories or the processes that influence their radioactive contents. The geochemical dispersion of naturally occurring uranium can also be used to model natural radioactivity fluxes in the vicinity of a planned repository. These fluxes can be estimated for erosional and groundwater discharge processes and compared with calculated future fluxes of radioactivity that would be released from a repository. The methodology is outlined and the benefits of the approach for supporting the derivation of a safety case for a repository are indicated. (author)

  1. Radioactive starting aids for electrodeless light sources

    International Nuclear Information System (INIS)

    Proud, J.M.; Regan, R.J.; Haugsjaa, P.O.; Baird, D.H.

    1980-01-01

    The use of radioactive sources of α particles, β particles or γ rays as aids in starting a discharge in an electrodeless light source is discussed. The advantages of siting the sources at various positions in the device are discussed. Preferred materials are 85 Kr and 241 Am. (U.K.)

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

    International Nuclear Information System (INIS)

    1978-04-01

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

  3. Radioactivity Monitoring of the Irish Environment 2003-2005

    International Nuclear Information System (INIS)

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

    2007-05-01

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

  4. 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)

  5. 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

  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. Institutional storage and disposal of radioactive materials

    International Nuclear Information System (INIS)

    St Germain, J.

    1986-01-01

    Storage and disposal of radioactive materials from nuclear medicine operations must be considered in the overall program design. The storage of materials from daily operation, materials in transit, and long-term storage represent sources of exposure. The design of storage facilities must include consideration of available space, choice of material, occupancy of surrounding areas, and amount of radioactivity anticipated. Neglect of any of these factors will lead to exposure problems. The ultimate product of any manipulation of radioactive material will be some form of radioactive waste. This waste may be discharged into the environment or placed within a storage area for packaging and transfer to a broker for ultimate disposal. Personnel must be keenly aware of packaging regulations of the burial site as well as applicable federal and local codes. Fire codes should be reviewed if there is to be storage of flammable materials in any area. Radiation protection personnel should be aware of community attitudes when considering the design of the waste program

  8. RADWASS update. Radioactive Waste Safety Standards Programme

    International Nuclear Information System (INIS)

    Delattre, D.

    2000-01-01

    By the late 1980s, the issue of radioactive wastes and their management was becoming increasingly politically important. The IAEA responded by establishing a high profile family of safety standards, the Radioactive Waste Safety Standards (RADWASS). By this means, the IAEA intended to draw attention to the fact that well-established procedures for the safe management of radioactive wastes already were in place. The programme was intended to establish an ordered structure for safety documents on waste management and to ensure comprehensive coverage of all relevant subject areas. RADWASS documents are categorized under four subject areas - discharges, predisposal, disposal, and environmental restoration. The programme is overseen through a formalized review and approval mechanism that was established in 1996 for all safety standards activities. The Waste Safety Standards Committee (WASSC) is a standing body of senior regulatory officials with technical expertise in radioactive waste safety. To date, three Safety Requirements and seven Safety Guides have been issued

  9. Radiation protection. Radioactivity and health. 3. ed.

    International Nuclear Information System (INIS)

    Feinendegen, L.E.; Feldmann, A.; Muench, E.; Paschke, M.

    1986-09-01

    This booklet makes an attempt at elucidating the mutual influence of radioactivity and health in a way which is understandable to the non-expert. The basics of radioactivity are briefly explained by way of introduction, the next item to be described is exposure of man to natural and artificial radiation. Somatic and genetic effects of radiation on man are subsequently discussed. The whole area of radioecology - starting with radioactive discharge from nuclear plants and going on to the determination of man's exposure to radiation - is covered and supplemented by a description of the risks of radiation therapy. All this serves to describe the results of long-term research on questions of the radiobiological risks in an understandable way and provide useful information about this eminently important area. (orig.) [de

  10. 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

  11. Experience in the management of radioactive wastes from power reactors - scope for regional cooperation

    International Nuclear Information System (INIS)

    Thomas, K.T.; Khan, A.A.

    The paper presents the R and D and operational experience of India in the development of a viable technology in the field of radioactive waste management and examines the scope for regional cooperation between countries with comparable conditions with a view to minimise the discharge of radioactivity to the environment. (author)

  12. 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).

  13. 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)

  14. Longitudinal dispersion of radioactive substances in Federal waterways

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-08-15

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

  15. Treatment and disposal of radioactive waste, ch. 1

    International Nuclear Information System (INIS)

    Jonker, G.S.

    1976-01-01

    Low-level radioactive liquid wastes may be discharged into surface waters. However, discharge is rather severely restricted by internationally accepted regulations. Therefore, the liquid should be purified to an acceptable level before release into the environment. One of the techniques available for pretreatment of radioactive liquids is precipitation. Three methods have been worked out: the calcium chloride-sodium carbonate process, the barium sulphate and the calcium phosphate precipitation. The main attention was directed towards the removal of the potentially hazardous radiostrontium. Precipitation is not only suitable for the purification of radioactive waste waters but may also be used in case of an unguided contamination of the environment for the purification of surface waters before distribution as drinking water. In appendix I the chemical preparation of the calcium carbonate polymorphic forms calcite, aragonite and vaterite is described, because these play an important role in the first process. X-ray diffraction analysis of these compounds and the apparatus used are described in appendix II. Spectrophotometric analysis of phosphate and flame spectrophotometry for the analysis of calcium in presence of phosphate ions is described in appendix III. A literature survey is presented of the various precipitation methods which are already used in present day practice

  16. 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.

  17. 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.

  18. 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

  19. 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

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

    International Nuclear Information System (INIS)

    Nishiwaki, Y.

    1981-01-01

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

  1. Nuclear power, the environment and national control arrangements in the United Kingdom

    International Nuclear Information System (INIS)

    Wilson, J.A.; Stott, G.

    1982-01-01

    The national control arrangements for the prevention, monitoring and regulation of environmental pollution arising from discharges of radioactivity by nuclear fuel cycle operators are described. The regulation procedures arise from the provisions contained in the Radioactive Substances Act 1960 and embody a system of site specific Authorisation Certificates which permits the operators to release radioactive wastes to the surrounding environment. The Authorisation process is described together with the structure and inter-relationships of the enforcing Inspectorates. New responsibilities for radioactive waste management are also discussed in the light of changes in Government policy following the publication of the White Paper ''Nuclear Power and the Environment''. (author)

  2. Radioactive inventories and sources for contamination of the Kara Sea

    International Nuclear Information System (INIS)

    Bradley, D.J.; Jenquin, U.P.

    1995-01-01

    The focus of this paper is on detailing the magnitudes of the sources of radionuclides that may be available, or have already been released to the Ob and Yenisey river systems. The emphasis is on the amounts of radioactivity that have been discharged to the environment in the West Siberian Basin. This are potential source terms to the Kara Sea via the Ob and Yenisey rivers. Russian estimates of what has been discharged to the Barents and Kara Seas, including direct ocean discharges, are summarized to provide some perspective on contamination of the Kara Sea. 1 fig., 3 tabs

  3. 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

  4. Radioactive effluents from CANDU 6 reactors during normal operation

    International Nuclear Information System (INIS)

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

    1995-12-01

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

  5. 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

  6. The ASDEX Upgrade discharge schedule

    International Nuclear Information System (INIS)

    Neu, G.; Engelhardt, K.; Raupp, G.; Treutterer, W.; Zasche, D.; Zehetbauer, T.

    2007-01-01

    ASDEX Upgrade's recently commissioned discharge control system (DCS) marks the transition from a traditional programmed system to a highly flexible 'data driven' one. The allocation of application processes (APs) to controllers, the interconnection of APs through uniquely named signals, and AP control parameter values are all defined as data, and can easily be adapted to the requirements of a particular discharge. The data is laid down in a set of XML documents which APs request via HTTP from a configuration server before a discharge. The use of XML allows for easy parsing, and structural validation through (XSD) schemas. The central input to the configuration process is the discharge schedule (DS), which embodies the dynamic behaviour of a planned discharge as reference trajectories grouped in segments, concatenated through transition conditions. Editing, generation and validation tools, and version control through CVS allow for efficient management of DSs

  7. Radioactivity Monitoring of the Irish Environment 2009

    International Nuclear Information System (INIS)

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

    2010-12-01

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

  8. Radioactivity Monitoring of the Irish Environment 2008

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  9. 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

  10. 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

  11. Radioactive lobsters put squeeze on Sellafield

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1996-11-01

    British Nuclear Fuels is facing a new controversy over its Sellafield Works in Cumbria. Levels of the radioactive isotope technetium-99 in lobsters close to the works have risen 40-fold since 1993 -and now far exceed EC standards for contamination of food after a nuclear accident. Radioactive doses to local seafood consumers have been rising steeply since BNFL commissioned a new enhanced actinide removal plant (EARP) in 1994. The Environment Agency has now asked BNFL to consider ways of reducing technetium-99 discharges from the plant - but the company is also under pressure to maintain throughput to meet the safety concerns of the Nuclear Installations Inspectorate (NII) and avoid disrupting the reprocessing of spent Magnox reactor fuel. (UK).

  12. Radioactive lobsters put squeeze on Sellafield

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    British Nuclear Fuels is facing a new controversy over its Sellafield Works in Cumbria. Levels of the radioactive isotope technetium-99 in lobsters close to the works have risen 40-fold since 1993 -and now far exceed EC standards for contamination of food after a nuclear accident. Radioactive doses to local seafood consumers have been rising steeply since BNFL commissioned a new enhanced actinide removal plant (EARP) in 1994. The Environment Agency has now asked BNFL to consider ways of reducing technetium-99 discharges from the plant - but the company is also under pressure to maintain throughput to meet the safety concerns of the Nuclear Installations Inspectorate (NII) and avoid disrupting the reprocessing of spent Magnox reactor fuel. (UK)

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

    International Nuclear Information System (INIS)

    Nunez, Juan C.

    2005-01-01

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

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

    International Nuclear Information System (INIS)

    Nunez, Juan C.

    2005-01-01

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

  15. 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)

  16. 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).

  17. 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

  18. Monitoring system for detection of radioactive materials in trucks at Commissariat a l'Energie Atomique (CEA-France)

    International Nuclear Information System (INIS)

    Levelut, M.N.

    1998-01-01

    Radiation Monitoring to control the radioactivity in vehicles and trucks are in use inside the sites of Commissariat a l'Energie Atomique. The first function of these monitoring systems in the detection of radioactive source or contaminated materials inside all loads of vehicles, before going out the nuclear site for the discharge of their materials either in a proper waste disposal or in an industrial site for material recycling. Other radioactive controls are conducted for nuclear materials and radioactive wastes. The radiation monitoring system use 4 to 6 plastic scintillators mounted vertically on each side of the roadway near the truck and horizontally, above or below the vehicle. The functional components also include a microprocessor for processing the signals and algorithms for interpreting the data transmitted to the control unit. This system functions in a dynamic mode; radiation is detected while the truck is in motion taking a series of incremental observations based on a differential count rate with the respect to the background. Vehicle scan information is printed out on a ticket specifying the result of the control. In case of unexpected radiation, an alarm is emitted. The vehicle is submitted to further investigations to find the source with a hand held instrument, analyse the radionuclides by spectrometry and find its origin in order to manage the corrective actions. The paper describes the system named > (Controle de la Radioactivite des Chargements de Vehicules), its sensitivity and the results of routine monitoring for several years. Few examples of radiation alarm are developed. (author)

  19. Lessons from radioactive waste disposal applied to other pollutants

    International Nuclear Information System (INIS)

    Templeton, W.L.

    1983-01-01

    In order to manage scientifically the quantities and kinds of waste disposal in coastal waters and open oceans, one needs to assess the environment's capacity to assimilate these materials. This knowledge may help us avoid an unacceptable biological impact on components of the ecosystem and on humans who harvest its resources. One approach available is the one that has been demonstrated to be applicable for the management of the disposal of radioactive wastes in the ocean. New generic and site-specific methodologies can establish relationships between discharge or release rates and associated radiation doses. The International Commission on Radiological Protection (ICRP) has developed guidelines and recommendations that govern acceptable amounts of radiation that people can be exposed to. The ICRP recommendations on justification and optimization can be integrated into an overall management philosophy in order to quantify alternative waste disposal options. These methodologies, which were developed for the control of radioactive wastes, should be applied directly to public health protection from nonradioactive wastes such as metals and organochlorine pesticides

  20. 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

  1. Treatment and conditioning of radioactive organic liquids

    International Nuclear Information System (INIS)

    1992-07-01

    Liquid organic radioactive wastes are generated from the use of radioisotopes in nuclear research centres and in medical and industrial applications. The volume of these wastes is small by comparison with aqueous radioactive wastes, for example; nevertheless, a strategy for the effective management of these wastes is necessary in order to ensure their safe handling, processing, storage and disposal. A aqueous radioactive wastes may be discharged to the environment after the radioactivity has decayed or been removed. By contrast, organic radioactive wastes require management steps that not only take account of their radioactivity, but also of their chemical content. This is because both the radioactivity and the organic chemical nature can have detrimental effects on health and the environment. Liquid radioactive wastes from these applications typically include vacuum pump oil, lubricating oil and hydraulic fluids, scintillation cocktails from analytical laboratories, solvents from solvent extraction research and uranium refining, and miscellaneous organic solvents. The report describes the factors which should be considered in the development of appropriate strategies for managing this class of wastes from generation to final disposal. Waste sources and characterization, treatment and conditioning processes, packaging, interim storage and the required quality assurance are all discussed. The report is intended to provide guidance to developing Member States which do not have nuclear power generation. A range of processes and procedures is presented, though emphasis is given to simple, easy-to-operate processes requiring less sophisticated and relatively inexpensive equipment. 31 refs, 16 figs, 3 tabs

  2. Methods for determining the release of radioactive material into the environment

    International Nuclear Information System (INIS)

    Farges, L.; Daw, H.T.

    1976-01-01

    The current policy on the discharge of radioactive effluents calls for the containment of radioactive wastes in most instances. The resulting doses to individuals and populations have been shown by many surveys to be very small (UNSCEAR Report, 1972). Nevertheless, small amounts of radioactive releases are made to the environment during normal operation of nuclear facilities. Whenever discharge of radioactive effluents to the environment is permitted, careful consideration is made of all the relevant factors which might lead to exposure of man. However, with the expansion of nuclear power programmes, more sophistication is required in setting discharge limits to the environment, taking into consideration future sources as well as present sources. The IAEA's recommendations conform to the dose limitation system set out by the International Commission on Radiological Protection (ICRP). The system implies that the individual dose limits should never be exceeded. Furthermore, the ICRP guidelines require that doses be kept as low as reasonably possible, taking social and economic considerations into account. This second objective, usually called optimization, implies the use of differential cost-benefit analysis. At present, decisions are still made by other procedures, for example, by applying safety factors to release limits derived only from the dose limits. However, the ICRP system of dose limitation, including optimization, appears to be a more rational approach to the establishment of release limits. Thus, it is necessary to provide basic material on concepts which are intended for use and decision making by national authorities, and the Agency plans to publish a series of complementary documents on the application of these concepts to various specific cases. (author)

  3. A report on the aquatic dilution experiment carried out at discharge canal, KGS site

    International Nuclear Information System (INIS)

    Reji, T.K.; Nayak, P.D.; Sudhakar, J.; Ajith, T.L.; Vishnu, M.S.; Ravi, P.M.; James, J.P.; Joshi, R.M.; Naik, S.B.; Kudtharkar, A.M.; Gaonkar, S.M.; Verma, P.C.; Datta, D.; Dahiya, Sudhir; Brijkumar; Datta, Maduparna; Sajeevan, G.

    2009-08-01

    Under Nuclear Power Corporation of India Limited (NPCIL), three units of (each of capacity 220MWe) Nuclear Power Stations are operational and one unit of similar capacity is under advanced stage of construction at Kaiga site. The radioactive liquid effluents generated in the plant are diluted with Condenser Coolant Water Stream (CCW) which is then discharged into Kadra reservoir through an artificially made discharge canal. The basic objective of the present study is to estimate the Dilution Factors at various locations of discharge canal and to understand the process of dilution and dispersion of radioactive effluent in the discharge canal. The strategy of the experiment involved the collection of samples from discharge canal lengthwise, breadth wise and depth wise immediately after the routine release of one of the batches of effluent stream into the CCW stream. No additional activity was released for the purpose of this experiment. The study compared the experimentally obtained Dilution Factor with that calculated based on the flow rates of CCW pumps and active liquid effluent discharge pumps. In the present conditions of experiment, Dilution Factor, based on flow rates of CCW pumps and Liquid Effluent Discharge pump, works out to be 8.11 E -05 while experimentally observed Mean Dilution Factor in the discharge canal works out to be (7.75±2.15) E-05. Hence this experiment clearly demonstrate the validity of the method of calculating dilution factor based on the flow rates of CCW line and that of Effluent discharge pump. The data analysis indicates that mass flow seems to be the major process of dispersion in the discharge canal. The tritium activity was found to be moving faster in the midstream as compared to that near the shore. The conclusions are drawn purely based on experimental results. This experimental data can be used for validation of aquatic dispersion models. (author)

  4. Radiological and hygienic aspects in radioactive waste processing and disposal

    International Nuclear Information System (INIS)

    Stepanova, V.D.

    1978-01-01

    The present review of reports deals with radiation-hygienic aspects of treatment and bUrial of radioactive wastes from nuclear power plants (NPP). The main principle of handling these wastes, which has been accepted in the USSR, is the treatment of the wastes directly at NPP with subsequent burial of the concentrates at the site. It is permissible to store wastes with mean specific activity in metal containers only temporarily. The most reliable method for fixing radioactive substances from wastes composition with mean specific activity is the method of consolidation by enclosing them in bitumen. Only excessive (disbalanced waters) that have been subjected to special water treatment may be discharged into NPP cooling ponds - if the content of radionuclides in this water is not in excess of the accepted standard at the point of discharge. An indirect radiological method has been developed for obtaining information on 90 Sr content in water; it may be further accepted for other radionuclides. An improved method is suggested for purification of salt-containing liquid wastes with low specific activity by using filters with ionexchange resins. Evaluation of safety at the Central Station of Radioactive Wastes Burial showed reliability of the methods used for treatment and burial of radioactive wastes. Measures for further decrease in the level of personnel irradiation and for environmental protection are enumerated

  5. Radiological and hygienic aspects in radioactive waste processing and disposal

    Energy Technology Data Exchange (ETDEWEB)

    Stepanova, V D

    1978-01-01

    The present review of reports deals with radiation-hygienic aspects of treatment and burial of radioactive wastes from nuclear power plants (NPP). The main principle of handling these wastes, which has been accepted in the USSR, is the treatment of the wastes directly at NPP with subsequent burial of the concentrates at the site. It is permissible to store wastes with mean specific activity in metal containers only temporarily. The most reliable method for fixing radioactive substances from wastes composition with mean specific activity is the method of consolidation by enclosing them in bitumen. Only excessive (disbalanced waters) that have been subjected to special water treatment may be discharged into NPP cooling ponds - if the content of radionuclides in this water is not in excess of the accepted standard at the point of discharge. An indirect radiological method has been developed for obtaining information on /sup 90/Sr content in water; it may be further accepted for other radionuclides. An improved method is suggested for purification of salt-containing liquid wastes with low specific activity by using filters with ionexchange resins. Evaluation of safety at the Central Station of Radioactive Wastes Burial showed reliability of the methods used for treatment and burial of radioactive wastes. Measures for further decrease in the level of personnel irradiation and for environmental protection are enumerated.

  6. 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)

  7. Resource consequences of reducing disposal of radioactive waste to the environment

    International Nuclear Information System (INIS)

    Johnson, L.F.

    1988-01-01

    This paper considers some of the terms and definitions used in the optimisation of radioactive waste processing and looks at the background regulatory requirements and BNFL's own policy on waste management. It considers recent plants brought into operation and the impact that they have had on the discharge of low level radioactive effluent to the Irish Sea, and notes future plants to be installed at Sellafield. Plant improvements aimed at making further reductions of operator or public exposure will then be considered and the possible impact of the recent NRPB guidelines will be looked at against BNFL's overall policy on waste management. Finally, to bring the environmental impact of the Sellafield discharges into some perspective, consideration will be given to collective doses from other sources of radiation in the UK. (author)

  8. 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

  9. Radioactive gas storage device

    International Nuclear Information System (INIS)

    Sano, Yuji.

    1988-01-01

    Purpose: To easily and reliably detect the consumption of a sputtered cathode in a radioactive gas storage device using ion injection method. Constitution: Inert gases are sealed to the inside of a cathode. As the device is operated, the cathode is consumed and, if it is scraped to some extent, inert gases in the cathode gases are blown out to increase the inner pressure of the device. The pressure elevation is detected by a pressure detector connected with a gas introduction pipe or discharge pipe. Further, since the discharge current in the inside is increased along with the elevation of the pressure, it is possible to detect the increase of the electrical current. In this way, the consumption of the cathode can be recognized by detecting the elevation in the pressure or increase in the current. (Ikeda, J.)

  10. 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

  11. 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

  12. 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.

  13. Radioactive liquid waste processing device

    International Nuclear Information System (INIS)

    Murakami, Susumu; Kuroda, Noriko; Matsumoto, Hiroyo.

    1991-01-01

    The present device comprises a radioactive liquid wastes concentration means for circulating radioactive liquid wastes between each of the tank, a pump and a film evaporator thereby obtaining liquid concentrates and a distilled water recovery means for condensing steams separated by the film evaporator by means of a condenser. It further comprises a cyclizing means for circulating the resultant distilled water to the upstream after the concentration of the liquid concentrates exceeds a predetermined value or the quality of the distilled water reaches a predetermined level. Further, a film evaporator having hydrophilic and homogeneous films is used as a film evaporator. Then, the quality of the distilled water discharged from the present device to the downstream can always satisfy the predetermined conditions. Further, by conducting operation at high concentration while interrupting the supply of the processing liquids, high concentration up to the aimed concentration can be attained. Further, since the hydrophilic homogeneous films are used, carry over of the radioactive material accompanying the evaporation is eliminated to reduce the working ratio of the vacuum pump. (T.M.)

  14. Health risk assessment for radium discharged in produced waters

    International Nuclear Information System (INIS)

    Hamilton, L.D.; Meinhold, A.F.; Nagy, J.

    1991-01-01

    Produced water generated during the production of oil and gas can contain enhanced levels of radium. This naturally occurring radioactive material (NORM) is discharged into freshwater streams, estuarine, coastal and outer continental shelf waters. Large volumes of produced waters are discharged to coastal waters along the Gulf Coast of Louisiana. The Gulf of Mexico is an important producer of fish and shellfish, and there is concern that radium discharged to coastal Louisiana could contaminate fish and shellfish used by people for food, and present a significant increase in cancer risk. This paper describes a screening-level assessment of the potential cancer risks posed by radium discharged to coastal Louisiana in oil-field produced waters. This screening analysis was performed to determine if a more comprehensive and realistic assessment is necessary, and because of the conservative assumptions embedded in the analysis overestimates the risk associated with the discharge of radium in produced waters. Two isotopes of radium (Ra-226 and Ra-228) are the radionuclides of most concern in produced water in terms of potential human health effects

  15. 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

  16. 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

  17. 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)

  18. A general advection-diffusion model for radioactive substance dispersion released from nuclear power plants

    International Nuclear Information System (INIS)

    Buske, D.

    2011-01-01

    The present contribution focuses on the question of radioactive material dispersion after discharge from a nuclear power plant in the context of micro-meteorology, i.e. an atmospheric dispersion model. The advection-diffusion equation with Fickian closure for the turbulence is solved for the atmospheric boundary layer where the eddy diffusivity coefficients and the wind profile are assumed to be space dependent. The model is solved in closed form using integral transform and spectral theory. Convergence of the solution is discussed in terms of a convergence criterion using a new interpretation of the Cardinal Theorem of Interpolation theory and Parseval's theorem. The solution is compared to other methods and model adequacy is analyzed. Model validation is performed against experimental data from a controlled release of radioactive material at the Itaorna Beach (Angra dos Reis, Rio de Janeiro state, Brazil, 1985). (author)

  19. NRPA. Radioactivity in the marine environment 2008 and 2009. Results from the Norwegian national monitoring programme (RAME)

    International Nuclear Information System (INIS)

    Gaefvert, T.; Heldal, H. E.; Brungot, A. L.; Gwynn, J.; Svaeren, I.; Kolstad, A. K.; Moeller, B.; Straalberg, E.; Christensen, G. C.; Drefvelin, J.; Dowdall, M.; Lind, B.; Rudjord, A. L.

    2011-04-01

    The issue of present and potential radioactive contamination in the marine environment has received considerable attention in Norway. In the late 1980s several accidents and incidents involving nuclear-powered submarines,demonstrated that the risk of the release of radionuclides into the Barents Sea should be considered more carefully. In particular, it became evident that better documentation concerning the radioactivity levels in fish and other seafood was important for the seafood export industries. Furthermore, in the early 1990s, information concerning the dumping of nuclear waste emerged through bilateral environmental cooperation between Norway and Russia. In the years that followed, concern grew regarding the safety of military and civil nuclear installations in the northwest of Russia. This concern was associated not only with possible reactor accidents, but also with the prolonged or sudden release of radio-nuclides from radioactive waste facilities.In addition to the potential threats outlined above, radionuclides originating from nuclear weapons fallout, the Chernobyl accident and waste discharged from European reprocessing facilities have been detected in the Norwegian marine environment. In 1994 and 1995, the discharge of 99Tc from the reprocessing facility at Sellafield in the UK increased sharply, and although this discharge has been reduced, it continued at a high level up to 2003. There has been much public concern about the consequences of such kinds of release, as the radionuclides discharged to the Irish Sea are transported by ocean currents via the North Sea into the Norwegian coastal current and to the Barents Sea. In response to this concern, programmes for the monitoring of radioactivity in the marine environment have been established. Due to the economic importance of the fishing industry and its vulnerability to contamination, as well as any rumours of radioactive contamination, one of the main objectives of these programmes is to

  20. Analysis through indicators of the management of radioactive waste in a radioactive facility; Analisis por medio de indicadores de la gestion de desechos radiactivos en una instalacion radiactiva

    Energy Technology Data Exchange (ETDEWEB)

    Amador Balbona, Zayda; Argudin Bocourt, William, E-mail: zabalbona@centis.edu.cu [Centro de Isotopos (CENTIS), Mayabeque (Cuba)

    2013-07-01

    The evaluation of the management of radioactive waste in the center of isotopes of the Republic of Cuba is the objective of this work. To do so, all the operations of the management system are evaluated through indicators used by this radioactive facility over a decade ago. Available information is processed from 1996 until 2012. The major waste generators are identified through the indicator of annual generation of each working group by local and by worker and it were analyzed the available store radioactive inventory, the relationship between the variation of annual technological waste volume of waste and the annual total manipulated activity, the relationship generation-declassification and the percent of liquid effluents managed as waste. Indicators of unconditional clearance, as well as the of the gaseous and liquid discharges are presented. It is concluded, with all these indicators, that it is possible to determine where are the causes of the behavior in the generation of radioactive waste if it is an increase of manipulated activity int the places of work or of worker, or improper application of the procedures of collection. It is controlled not only management, but also determines in which aspects can work to achieve the objective of minimizing the formation of these wastes, to be able to reduce the production costs. National shedding environmental regulations are met and the results are acceptable)

  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. 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

  3. Outlook of the accident at Fukushima No.1 Nuclear Power Plants and issues concerning radioactive materials in environments

    International Nuclear Information System (INIS)

    Tanaka, Shun-ichi

    2011-01-01

    Fukushima No.1 Nuclear Power Plants (NPPs) affected by a great earthquake finally suffered reactor core meltdown with loss of all cooling capability and discharged a large amount of radioactive materials to the environment. Local areas in the northwest direction from NPPs were highly contaminated with radioactive materials. In order to reduce radiation exposure, several kinds of decontamination works had been tested in contaminated areas of primary school and kindergarten or residential houses with no evacuation. Radiation mini-hotspots were scattered. Contaminated soils and rubbles having cesium of high concentration in the order of several ten or hundreds kBq/kg were accumulated in large amounts of radioactive wastes and their disposal became a big issue. Related safety guidelines were proposed based on radioactive waste disposal for nuclear facilities as well as radiation dose control of neighboring residents and disposal workers, which would not be applicable to current state of Fukushima in a high radiation background. Establishment of new radiation protection rule was highly needed to deal with this emergency based on reality within and outside the Fukushima NPPs. (T. Tanaka)

  4. 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

  5. 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

  6. U.S. port commerce in radioactive materials

    International Nuclear Information System (INIS)

    Marti, B.E.

    1987-01-01

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

  7. 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

  8. 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

  9. 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)

  10. 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...

  11. Radioactive contamination of the marine environment

    International Nuclear Information System (INIS)

    Aarkrog, A.

    1997-01-01

    The major source of man-made radioactivity in the oceans is derived from nuclear weapons testing fallout, which occurred mostly in the late 1950s and early 1960s. For example, 0.9 EBq of 137 Cs and 0.6 EBq of 90 Sr were introduced in this way. Only 60% of the released activity was disposed of in the oceans, rather than 70%, because the nuclear weapons testing occurred mainly in the Northern hemisphere, and the land masses cover more of the Northern hemisphere than the Southern hemisphere. There have also been other releases into the oceans; for example, the water-borne discharges from the Sellafield reprocessing plant in the UK, which occurred from the mid-1970s to the mid-1980s. During this decade, in the order of 40 PBq of 137 Cs was discharged into the Irish sea, and from there it was transported into the north Atlantic ocean. The third important source of radioactivity was the Chernobyl accident. Although most of this radioactivity was distributed over the land masses, about 5 PBq was deposited into the Baltic Sea and about 3 PBq into the Black Sea. The radioactive debris from Chernobyl was distributed around the Northern hemisphere, so some of the radioactivity must have been deposited in the North Atlantic ocean. There have also been a number of local contaminations of the oceans. Among these are satellite failures. For example, the SNAP-9A satellite, which burned up over the South Atlantic ocean in the early 1960s, became a major source of 238 Pu pollution. This is the reason why there is an increased 238 Pu: 239 Pu ratio, mostly in the Southern hemisphere, in global fallout. There are also a number of nuclear submarines on the bottom of the sea; for example, the American Thresher submarine in the Atlantic ocean and the Comsomolets submarine in the Norwegian-Barents sea. Furthermore, there have been several accidents with nuclear weapons; for example, the Palomares accident in Spain in 1966 and the Thule accident in Greenland in 1968. Finally, nuclear

  12. Development of plastic scintillator based food radioactivity contamination monitoring system

    International Nuclear Information System (INIS)

    Parihar, A.; Sahani, R.M.; Mahala, V.K.; Vaijapurkar, S.G.

    2016-01-01

    Radioactivity is naturally present in soil, water and food stuffs. Food can be contaminated after discharge of radioactivity into the environment from industries that concentrate natural radionuclide and from civil or military nuclear operations. The contamination can be in three ways; by direct deposition, through the food chain and induced radioactivity due to exposure of high neutron flux. The health effects on human depend on the type of radionuclide and the length of time people are exposed to it. The studies of fission product behaviour in the food chain have revealed radionuclide Strontium-90, Caesium 137 and Iodine-131 are of major concern. Plastic scintillator is already developed indigenously at Defence Laboratory, Jodhpur. Efforts has been made to develop a portable field instrument using plastic scintillator for assessment of beta ( 90 Sr) and gamma ( 137 Cs and 131 I) radioactivity in food

  13. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-12-01

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

  15. 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

  16. Radioactivity and foods

    International Nuclear Information System (INIS)

    Olszyna-Marzys, A.E.

    1991-01-01

    The purpose of this article is to describe and contrast two relationships between radiation and food on the one hand, beneficial preservation of food by controlled exposure to ionizing radiation; and, on the other, contamination of food by accidental incorporation of radioactive nuclides within the food itself. In food irradiation, electrons or electromagnetic radiation is used to destroy microorganisms and insects or prevent seed germination. The economic advantages and health benefits of sterilizing food in this manner are clear, and numerous studies have confirmed that under strictly controlled conditions no undesirable changes or induced radioactivity is produced in the irradiated food. An altogether different situation is presented by exposure of food animals and farming areas to radioactive materials, as occurred after the major Soviet nuclear reactor accident at Chernobyl. This article furnishes the basic information needed to understand the nature of food contamination associated with that event and describes the work of international organizations seeking to establish appropriate safe limits for levels of radioactivity in foods

  17. Management of radioactive effluents from research Reactors and PHWRs

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  18. Transport of radioactive droplet moisture from a source in a nuclear power plant spray pond

    International Nuclear Information System (INIS)

    Elokhin, A.P.

    1995-01-01

    In addition to a change in the microclimate in the region surrounding a nuclear power plant resulting from the emission of vapor form a cooling tower, evaporation of water from the water surface of a cooling pond or a spray pond, in the latter case direct radioactive contamination of the underlying surface around the nuclear power plant can also occur due to discharge of process water (radioactive) into the pond and its transport in the air over a certain distance in the form of droplet moisture. A typical example may be the situation at the Zaporozhe nuclear power plant in 1986 when accidental discharge of process water into the cooling pond occurred. Below we present a solution for the problem of transport of droplet moisture taking into account its evaporation, which may be used to estimate the scale of radioactive contamination of the locality

  19. The existing state of sewage sludge containing radioactive substances

    International Nuclear Information System (INIS)

    Shirasaki, Makoto; Hisaoka, Natsuki

    2012-01-01

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

  20. 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

  1. General review of literature relevant to coastal water discharges

    International Nuclear Information System (INIS)

    Pentreath, R.J.

    1985-01-01

    This review on the behaviour of radionuclides released into coastal water from the radioactive discharges, prepared on the basis of existing publications and documents, is divided into parts on pathways of exposure, behaviour of radionuclides in coastal environments, biological avialability of radionuclides, habit surveys and critical groups, assessment of dose to man and the effects of radiation on aquatic organisms

  2. 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

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

    International Nuclear Information System (INIS)

    Maeda, Yoshiaki

    2011-01-01

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

  4. Radioactivity in surface and coastal waters of the British Isles, 1988

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1989-01-01

    This report presents the results of the aquatic environmental monitoring programme performed during 1988 by the Ministry of Agriculture, Fisheries and Food's (MAFF's) Directorate of Fisheries Research (DFR). Radioactivity measurements are made in aquatic organisms and environmental materials in the vicinity of nuclear establishments including BNFL, UKAEA, nuclear power stations operated by the electricity boards, defence establishments and Amersham International. A summary of estimated public radiation exposures in 1988, relating to liquid radioactive waste discharges from nuclear establishments is presented. (UK)

  5. 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

  6. Released radioactivity reducing device

    International Nuclear Information System (INIS)

    Miyamoto, Yumi.

    1995-01-01

    A water scrubber is disposed in a scrubber tank and a stainless steel fiber filter is disposed above the water scrubber. The upper end of the scrubber tank is connected by way of a second bent tube to a capturing vessel incorporating a moisture removing layer and an activated carbon filter. The exit of the capturing vessel is connected to a stack. Upon occurrence of an accident of a BWR-type power plant, gases containing radioactive materials released from a reactor container are discharged into the water scrubber from a first bent tube through a venturi tube nozzle, and water soluble and aerosol-like radioactive materials are captured in the water. Aerosol and splashes of water droplets which can not be captured thoroughly by the water scrubber are captured by the stainless steel fiber filter. Gases passing through the scrubber tank are introduced to a capturing vessel through a second bent tube, and organic iodine is captured by the activated carbon filter. (I.N.)

  7. 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'.

  8. The study on radioactivity reduction of spent PWR cladding hull

    International Nuclear Information System (INIS)

    Jung, I. H.; Kim, J. H.; Park, C. J.; Jung, Y. H.; Song, K. C.; Lee, J. W.; Park, J. J.; Yang, M. S.

    2003-01-01

    Hull arising from the spent PWR fuel elements is classified as a high-level radioactive waste. This report describes the radio-chemical characteristics of the hull-from PWR spent fuel of 32,000MWd/tU burn-up and 15 years cooling, discharged from Gori Unit I cycled 4-7-by examination and literature survey. On the basis of the results, a method of degradation to middle and low-level radioactive waste was proposed by dry process such as laser or plasma technique with removing the nuclides deposited on the surface of the hull

  9. The transport of radioactive waste

    International Nuclear Information System (INIS)

    Appleton, P.R.; Poulter, D.R.

    1989-01-01

    Regulations have been developed to ensure the safe transport of all radioactive materials by all modes (road, rail, sea and air). There are no features of radioactive waste which set it aside from other radioactive materials for transport, and the same regulations control all radioactive material transport. These regulations and their underlying basis are described in this paper, and their application to waste transport is outlined. (author)

  10. Method of processing radioactive metallic sodium with recycling alcohols

    International Nuclear Information System (INIS)

    Sakai, Takuhiko; Mitsuzuka, Norimasa.

    1980-01-01

    Purpose: To employ high safety alcohol procession and decrease the amount of wastes in the procession of radioactive metallic sodium discharged from LMFBR type reactors. Method: Radioactive metallic sodium containing long half-decay period nuclides such as cesium, strontium, barium, cerium, lanthanum or zirconium is dissolved in an alcohol at about 70% purity. After extracting the sodium alcoholate thus formed, gaseous hydrochloride is blown-in to separate the sodium alcoholate into alcohol and sodium chloride, and regenerated alcohol is used again for dissolving sodium metal. The sodium chloride thus separated is processed into solid wastes. (Furukawa, Y.)

  11. Case Study on Justification: High Intensity Discharge Lamps. Annex II

    International Nuclear Information System (INIS)

    2016-01-01

    High intensity discharge lamps produce bright white light of a high intensity in an energy efficient manner. These lamps are typically used in large numbers in public and professional settings such as shops, warehouses, hotels and offices. They are also used in outdoor applications to illuminate streets, buildings, statues, flags and gardens and further as architectural lighting. They also have applications associated with film projection in cinemas, manufacture of semiconductors, fluorescence endoscopy and microscopy, schlieren photography, hologram projection, ultraviolet curing, sky beamers and car headlights. Some types of high intensity discharge lamp, as well as certain other consumer products for lighting, contain radioactive substances for functional reasons. The radionuclides that are typically incorporated into high intensity discharge lamps are 85 Kr and 232 Th. Given the wide range of uses, specific decisions on justification may be required for different applications. A small number of safety assessments for high intensity discharge lamps have been carried out and published. No published decisions at the national level specifically addressing the justification of the use of high intensity discharge lamps have been identified

  12. Experience and projects concerning treatment, conditioning and storage of all radioactive wastes from Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Fukuda, G.; Matsumoto, K.; Miyahara, K.

    1984-01-01

    The active operation of Tokai reprocessing plant started in September 1977, and about 170 t U of spent fuel were reprocessed between then and December 1982. During this period, the low-level waste processing plant reduced the amount of radioactivity discharged into the environment. For radioactive liquid waste, the treatment procedures consist mainly of evaporation to keep the discharge into the sea at a low level. For combustible low-level solid waste and the solvent waste, which is of low tributyl phosphate content, incineration has been used successfully (burned: about 150 t of combined LLSW, about 50 m 3 of solvent waste, i.e. diluent waste). Most of the past R and D work was devoted to reducing the activity discharged into the environment. Current R and D work is concerned with the treatment of solvent waste, the conditioning of solid wastes, the bituminization of low-level liquid waste and the vitrification of high-level liquid waste. The paper describes present practices, R and D work and future aspects of the treatment, conditioning and storage of all radioactive wastes from Tokai reprocessing plant. (author)

  13. Analysis of radioactive cobalt

    International Nuclear Information System (INIS)

    1977-01-01

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

  14. 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

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

    International Nuclear Information System (INIS)

    Queiser, H.

    1976-01-01

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

  16. 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

  17. The discharges from Sellafield how big a risk for the Irish population?

    Energy Technology Data Exchange (ETDEWEB)

    O` Flaherty, T [Radiological Protection Inst. of Ireland (Ireland)

    1996-10-01

    The site operated by British Nuclear Fuels Ltd (BNFL) at Sellafield in Cumbria was established just after World War II to produce plutonium for the manufacture of nuclear weapons. Plutonium was obtained by extracting it from nuclear fuel which had been irradiated in an early type of nuclear reactor. This procedure was the forerunner of what ultimately became the main commercial activity at Sellafield, the reprocessing of spent nuclear fuel to recover re-usable uranium and plutonium An unavoidable consequence of nuclear fuel reprocessing is the necessity to discharge from the site very large volumes of low-level radioactive waste in liquid form. In the case of Sellafield this waste is discharged into the Irish Sea. Due to a plant malfunction the rates of discharge greatly increased in the mid-1970s, and became a matter of serious concern to the people of Ireland and to successive Irish Governments. In more recent years the rates of discharge have fallen again to lower levels, but this has not diminished concern in Ireland to any significant degree. This paper summarises the results of Irish monitoring of radioactivity levels in the Irish Sea which has been in progress since the late 1970s. From these results it quantifies the radiation doses received by people in Ireland in consequence of the discharges from Sellafield, and estimates the degree of risk of increased cancer levels in the Irish population as a result. The RPII`s monitoring programme has been expanded since 1993 in the light of the bringing into operation of the new Thermal Oxide Reprocessing Plant (Thorp) and now includes the monitoring of gaseous discharges to the atmosphere. The paper includes some initial results of this expanded programme.

  18. 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

  19. 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.

  20. Radioactivity in the Norwegian Marine Environment

    International Nuclear Information System (INIS)

    2002-01-01

    The national monitoring programme for radioactivity in the marine environment was established in 1999. The programme is coordinated by the Norwegian Radiation Protection Authority (NRPA) in cooperation with the Institute of Marine Research (IMR). The principal objective of the programme is to document levels, distributions and trends of radionuclides in the marine environment. Data regarding discharges of radionuclides from both Norwegian and other sources are collected, and assessments of the resulting radiation exposures of humans and biota will be carried out. Results from the analysis of environmental samples collected in 1999 are presented in a new NRPA report (NRPA, 2001:9 ''Radioactivity in the Marine Environment 1999''. Some results from the monitoring programme in 1999 are summarised below along with more recent data concerning concentrations of the radionuclide technetium-99. (author)

  1. 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)

  2. Processing method of radioactive metal wastes

    International Nuclear Information System (INIS)

    Uetake, Naoto; Urata, Megumu; Sato, Masao.

    1985-01-01

    Purpose: To reduce the volume and increase the density of radioactive metal wastes easily while preventing scattering of radioactivity and process them into suitable form to storage and treatment. Method: Metal wastes mainly composed of zirconium are discharged from nuclear power plants or fuel re-processing plants, and these metals such as zirconium and titanium vigorously react with hydrogen and rapidly diffuse as hydrides. Since the hydrides are extremely brittle and can be pulverized easily, they can be volume-reduced. However, since metal hydrides have no ductility, dehydrogenation is applied for the molding fabrication in view of the subsequent storage and processing. The dehydrogenation is easy like the hydrogenation and fine metal pieces can be molded in a small compression device. For the dehydrogenation, a temperature is slightly increased as compared with that in the hydrogenation, pressure is reduced through the vacuum evacuation system and the removed hydrogen is purified for reuse. The upper limit for the temperature of the hydrogenation is 680 0 C in order to prevent the scttering of radioactivity. (Kamimura, M.)

  3. Radioactive waste disposal: Regulations and Application

    International Nuclear Information System (INIS)

    Hebert, Jean.

    1977-01-01

    The regulation of radioactive discharges, i.e. solid radioactive waste resulting from operation of nuclear installations and liquid and gazeous effluents released by them may be dealt with from two angles: the receiving environment and the polluting agent. French law covers both. Law on atmospheric pollution is based mainly on the Act of 2 August 1961 while the Act of 16 December 1964 governs water pollution. Both Acts have been the subject of a great number of implementing decrees, certain of which contain standards specific to radioactive pollution. Regulations on the polluting agent, namely its activity, comply with the generally established distinction between large nuclear installations and others. There again, there are many applicable texts, in particular, the Act of 19 July 1976 for classified installations, and the Decree of 11 December 1963, supplemented by the Decrees of 6 November 1974 and 31 December 1974 for large nuclear installations. This detailed analysis of national regulations is followed by a presentation of the applicable provisions in the Communities law and in international public law. (N.E.A.) [fr

  4. Radioactivity and food

    International Nuclear Information System (INIS)

    Olszyna-Marzys, A.E.

    1990-01-01

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

  5. Principles for establishing limits for the release of radioactive materials into the environment

    International Nuclear Information System (INIS)

    1978-01-01

    The document provides a basic consideration of concepts and principles for use by national authorities in setting limits for planned releases of radioactive material. The following topics are discussed general concepts, assessment of dose to the critical group, assessment of collective dose commitments, application of optimization techniques to the determination of discharge limits, explanation and application of the concept of collective dose commitment, discharge limitations based on concentration indices

  6. Radioactive contamination of environment

    International Nuclear Information System (INIS)

    Chytil, I.

    1981-01-01

    A computer model is discussed describing radioactivity transport between the source and the organism. The model is to be applied in assessing the effect of a nuclear installation on the organism. Fortran and Pascal appear to be the most appropriate computer languages. With respect to internal memory requirements, the program file is estimated to consist of a control program and a number of subprograms. Upon setting the radioactivity transport and the output requirements the control program should recall the necessary subprograms. The program file should allow the complete data file and the solutions of all possible radioactivity transport variants to be inputted. It is envisaged that several subprograms will be available for one type of radioactivity transport, this depending on different accuracy of the transport description. Thus, the requirements for input data will also differ. (Z.M.)

  7. Dumping of radioactive waste in the Barents and Kara seas

    International Nuclear Information System (INIS)

    Salbu, B.; Christensen, G.C.

    1995-01-01

    To evaluate the level of radioactive contamination in the Kara Sea and to assess short- and long-term consequences of dumped radioactive waste, joint Russian-Norwegian expeditions have been performed annually since 1992. Results from the 1992 joint expedition to the Kara Sea demonstrated very low concentrations of radionuclides in waters and sediments. Contributions from different sources: global fallout, river transport, marine transport of discharges from European reprocessing plants and of fallout from Chernobyl, could be identified. From the expeditions in 1993 and 1994 to three bays at Novaya Zemlya, local contamination in the Stepovogo and the Abrosimov bays due to leakage from the dumped radioactive waste could be confirmed. Results from the 1994 expedition will be published in 1995. The levels of radioactivity in the Kara Sea are, however, very low and represent at present an extremely low impact on man and the marine ecosystem. (Author)

  8. 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)

  9. Safety and security of radioactive sources in Taiwan

    International Nuclear Information System (INIS)

    Tsay Yeousong; Guan Channan; Cheng Yungfu

    2008-01-01

    In Taiwan, the safety and security of radioactive sources is a high priority issue. Ionizing Radiation Protection Act (IRPA) and correlating regulations had been in place for effective control of the safety and security of radioactive sources since 2003. For increased control of sealed radioactive sources, Atomic Energy Council (AEC) established in March 2004 an online reporting system through the Internet, assisting source owners in reporting their sources every month. To conform to the Code of Conduct on the Safety and Security of Radioactive Sources and the Categorization of radioactive sources, published by the International Atomic Energy Agency (IAEA), AEC has taken the following actions: 1. Established an inventory of Categories 1 and 2 radioactive sources, and implemented the Import/Export Provisions of the Code. 2. Required that each licensee shall control access to Categories 1 and 2 radioactive sources, and AEC will conduct project inspection on Categories 1 and 2 radioactive sources. 3. Using a new radiation warning symbol by ISO for Categories 1 and 2 radioactive sources. The reinforcement of orphaned source control was implemented as early as 1995. All steel mills have installed radiation detectors to scan incoming metal scrap to prevent accidental smelting of radioactive sources. The results of this effort will be discussed in the paper. The above measures are examples for demonstrating AEC's commitment to reinforced control of radioactive sources. AEC will continue to protect public safety and security, ensuring that Taiwan's regulatory system in radiation protection conforms to international standards. (author)

  10. 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

  11. 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

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  13. 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

  14. Protection of atmospheric air against radioactive gas and aerosol contaminants

    International Nuclear Information System (INIS)

    Zykova, A.S.

    1984-01-01

    Measures for contamination protection of atmospheric air subdivided into active and passive ones, are considered. The active measures envisage: development and application of waste-free flowsheets, use of flowsheets which restrict formation of gaseous-aerosol discharges; application of highly efficient treatment facilities torage. Dispersion of radioactive substances, released with discharges to the atmosphere, using high stacks; development of the corresponding site-selection solutions and arrangement of sanitary protective zones belong to passive measures. Measures for protection of atmospheric air also include waste and air contamination monitoring. The measures described are considered as applied to NPPs

  15. Vadose zone monitoring plan using geophysical nuclear logging for radionuclides discharged to Hanford liquid waste disposal facilities

    International Nuclear Information System (INIS)

    Price, R.K.

    1995-11-01

    During plutonium production at Hanford, large quantities of hazardous and radioactive liquid effluent waste have been discharged to the subsurface (vadose zone). These discharges at over 330 liquid effluent disposal facilities (ie. cribs, ditches, and ponds) account for over 3,000,000 curies of radioactive waste released into the subsurface. It is estimated that 10% of the contaminants have reached the groundwater in many places. Continuing migration may further impact groundwater quality in the future. Through the RCRA Operational Monitoring Program, a Radionuclide Logging System (RLS) has been obtained by Hanford Technical Services (HTS) and enhanced to measure the distribution of contaminants and monitor radionuclide movement in existing groundwater and vadose zone boreholes. Approximately 100 wells are logged by HTS each year in this program. In some cases, movement has been observed years after discharges were terminated. A similar program is in place to monitor the vadose zone at the Tank Farms. This monitoring plan describes Hanford Programs for monitoring the movement of radioactive contamination in the vadose zone. Program background, drivers, and strategy are presented. The objective of this program is to ensure that DOE-RL is aware of any migration of contaminants in the vadose zone, such that groundwater can be protected and early actions can be taken as needed

  16. Radioactivity and environment

    Energy Technology Data Exchange (ETDEWEB)

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

    1977-12-01

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

  17. 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)

  18. 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

  19. 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)

  20. Devoluming method of acidic radioactive liquid waste and processing system therefor

    International Nuclear Information System (INIS)

    Shirai, Takamori; Honda, Tadahiro

    1998-01-01

    Radioactive liquid wastes such as liquid wastes discharged from chemical decontamination (containing free acids, metal salts dissolved in acids, not-dissolved iron rust and radioactive metals) are introduced to an acid recovering device using a diffusion permeation membrane and separated to a deacidified liquid and separated acid liquid. The separated acid liquid mainly comprising free acids is recovered to a tank for recovered acids, and used repeatedly for removing crud. The deacidified liquid mainly comprising salts is concentrated in a reverse osmosis membrane (RO) concentration device. RO concentrated liquid containing radioactive metals is dried, and salts are decomposed in a drying/salt-decomposing device and separated into metal oxides and a mixed gas of an acidic gas and steams. The gas is cooled in an acid absorbing device and recovered as free acids. The metal oxides containing radioactive metals are solidified. (I.N.)