WorldWideScience

Sample records for weerie radioactive release

  1. Sellafield (release of radioactivity)

    Energy Technology Data Exchange (ETDEWEB)

    Cunningham, J; Goodlad, A; Morris, M

    1986-02-06

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

  2. Released radioactivity reducing facility

    International Nuclear Information System (INIS)

    Tanaka, Takeaki.

    1992-01-01

    Upon occurrence of a reactor accident, penetration portions of a reactor container, as a main leakage source from a reactor container, are surrounded by a plurality of gas-tight chambers, the outside of which is surrounded by highly gas-tightly buildings. Branched pipelines of an emergency gas processing system are introduced to each of the gas-tight chambers and they are joined and in communication with an emergency gas processing device. With such a constitution, radioactive materials are prevented from leaking directly from the buildings. Further, pipeline openings of the emergency gas processing facility are disposed in the plurality highly gas-tight penetration chambers. If the radioactive materials are leaked from the reactor to elevate the pressure in the penetration chambers, the radioactive materials are introduced to a filter device in the emergency gas processing facility by way of the branched pipelines, filtered and then released to the atmosphere. Accordingly, the reliability and safety of the system can be improved. (T.M.)

  3. 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.)

  4. Experience with radioactivity releases

    International Nuclear Information System (INIS)

    Anderson, T.V.; Johnson, A.G.; Ringle, J.C.

    1972-01-01

    On December 11, 1970, the reactor top continuous air monitor (CAM) showed an increase in particulate air activity of an unusual nature. A check of the CAM filter with a multi-channel analyzer indicated that the majority of the activity was due to Cs-138 , Cs-139 , Rb-89 , and Rb-90 , which indicated a probable fuel element leak. The CAM filter was changed and rechecked several times, but the rubidium and cesium radionuclides were consistently identified. The procedure was followed by removing three fuel elements at a time. Since the CAM was the only instrument picking up radioactivity, it was used as the primary radiation monitor. During the search for the leaky fuel element, it was found that the element in position E-18 (triangle cut-out) was leaning against the top of the element in E-17. Particulate air activity originating from the rotating rack loading port on the reactor top was reported by OSU during the previous TRIGA Owner's Seminar. Short term relief can be obtained by inserting a standard CAM filter paper over the rotating rack loading tube opening, but this has not proved satisfactory for runs of one hour or longer. A simple filter system for the rotating rack was built, and is operated as part of the argon ventilation system. This appears to have solved the problem

  5. Radioactive materials released from nuclear power plants

    International Nuclear Information System (INIS)

    Tichler, J.; Norden, K.; Congemi, J.

    1991-05-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1988 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1988 release data are summarized in tabular form. Data covering specific radionuclides are summarized. 16 tabs

  6. Offsite doses from SRP radioactive releases - 1985

    International Nuclear Information System (INIS)

    Marter, W.L.

    1986-01-01

    This memorandum summarizes the offsite doses from releases of radioactive materials to the environment from SRP operations in 1985. These doses were calculated for inclusion in the environmental report for 1985 to be issued by the Health Protection Department (DPSPU-86-30-1). The environmental report is prepared annually for distribution to state environmental agencies, the news media, and interested members of the public. More detailed data on offsite exposures by radionuclide and exposure pathway will be included in the environmental report

  7. Atmospheric dispersion models of radioactivity releases

    International Nuclear Information System (INIS)

    Oza, R.B.

    2016-01-01

    In view of the rapid industrialization in recent time, atmospheric dispersion models have become indispensible 'tools' to ensure that the effects of releases are well within the acceptable limits set by the regulatory authority. In the case of radioactive releases from the nuclear facility, though negligible in quantity and many a times not even measurable, it is required to demonstrate the compliance of these releases to the regulatory limits set by the regulatory authority by carrying out radiological impact assessment. During routine operations of nuclear facility, the releases are so low that environmental impact is usually assessed with the help of atmospheric dispersion models as it is difficult to distinguish negligible contribution of nuclear facility to relatively high natural background radiation. The accidental releases from nuclear facility, though with negligible probability of occurrence, cannot be ruled out. In such cases, the atmospheric dispersion models are of great help to emergency planners for deciding the intervention actions to minimize the consequences in public domain and also to workout strategies for the management of situation. In case of accidental conditions, the atmospheric dispersion models are also utilized for the estimation of probable quantities of radionuclides which might have got released to the atmosphere. Thus, atmospheric dispersion models are an essential tool for nuclear facility during routine operation as well as in the case of accidental conditions

  8. Methodology for estimating accidental radioactive releases in nuclear waste management

    International Nuclear Information System (INIS)

    Levy, H.B.

    1979-01-01

    Estimation of the risks of accidental radioactive releases is necessary in assessing the safety of any nuclear waste management system. The case of a radioactive waste form enclosed in a barrier system is considered. Two test calculations were carried out

  9. Nuclear refugees after large radioactive releases

    International Nuclear Information System (INIS)

    Pascucci-Cahen, Ludivine; Groell, Jérôme

    2016-01-01

    However improbable, large radioactive releases from a nuclear power plant would entail major consequences for the surrounding population. In Fukushima, 80,000 people had to evacuate the most contaminated areas around the NPP for a prolonged period of time. These people have been called “nuclear refugees”. The paper first argues that the number of nuclear refugees is a better measure of the severity of radiological consequences than the number of fatalities, although the latter is widely used to assess other catastrophic events such as earthquakes or tsunami. It is a valuable partial indicator in the context of comprehensive studies of overall consequences. Section 2 makes a clear distinction between long-term relocation and emergency evacuation and proposes a method to estimate the number of refugees. Section 3 examines the distribution of nuclear refugees with respect to weather and release site. The distribution is asymmetric and fat-tailed: unfavorable weather can lead to the contamination of large areas of land; large cities have in turn a higher probability of being contaminated. - Highlights: • Number of refugees is a good indicator of the severity of radiological consequences. • It is a better measure of the long-term consequences than the number of fatalities. • A representative meteorological sample should be sufficiently large. • The number of refugees highly depends on the release site in a country like France.

  10. Consequences of severe radioactive releases to Nordic Marine environment

    DEFF Research Database (Denmark)

    Iosjpe, M.; Isaksson, M.; Joensen, H.P.

    - or minor – radioactive releases to Nordic marine environment. As a reference, the release amounts from a 3000 MWth reactor size were used. Based on source term analyses, the chosen release fractions in the study were: iodine 20% (of the total core inventory), caesium 10%, tellurium 10%, strontium 0...

  11. Radioactive iodine releases from nuclear power plant, (2)

    International Nuclear Information System (INIS)

    Naritomi, Mitsuo

    1974-01-01

    Internal radiation dose through the respiratory intake of fission products is predominantly due to radioactive iodine not only at the time of reactor accidents but also in normal operation of nuclear facilities. Technological studies in this field have thus been quite active to this day. With the rapid advance of nuclear power generation in recent years, the efforts to reduce environmental release of radioactive iodine and to enhance environmental safety are all the more emphasized. Experiences in the Japan Atomic Energy Research Institute during past about six years are described concerning the radioactive iodine release to the atmosphere in 131 I production and the measures taken to reduce the release. Then, problems are expounded regarding the radioactive iodine release at the time of reactor accidents and in spent fuel reprocessing. (Mori, K.)

  12. Radioactive releases into the environment under accidental conditions

    International Nuclear Information System (INIS)

    Beninson, D.

    1976-01-01

    Although accidents involving the release of radioactive materials and the unplanned exposure of people can occur at any stage of the nuclear fuel cycle, most attention has been focused on reactor accidents. Although no power reactor accidents involving exposure of the public have yet occured, it should be recognized that the probability of such accidental releases cannot be reduced to zero. Since the inventory of radioactive materials in power reactors is very large, it is usual to postulate, for safety assessments, that a release of fission products takes place in spite of all protective measures. This postulated release is of importance for reactor siting and for preparing emergency plans. (HP) [de

  13. Radioactive release during nuclear accidents in Chernobyl and Fukushima

    Science.gov (United States)

    Nur Ain Sulaiman, Siti; Mohamed, Faizal; Rahim, Ahmad Nabil Ab

    2018-01-01

    Nuclear accidents that occurred in Chernobyl and Fukushima have initiated many research interests to understand the cause and mechanism of radioactive release within reactor compound and to the environment. Common types of radionuclide release are the fission products from the irradiated fuel rod itself. In case of nuclear accident, the focus of monitoring will be mostly on the release of noble gases, I-131 and Cs-137. As these are the only accidents have been rated within International Nuclear Events Scale (INES) Level 7, the radioactive release to the environment was one of the critical insights to be monitored. It was estimated that the release of radioactive material to the atmosphere due to Fukushima accident was approximately 10% of the Chernobyl accident. By referring to the previous reports using computational code systems to model the release rate, the release activity of I-131 and Cs-137 in Chernobyl was significantly higher compare to Fukushima. The simulation code also showed that Chernobyl had higher release rate of both radionuclides on the day of accident. Other factors affecting the radioactive release for Fukushima and Chernobyl accidents such as the current reactor technology and safety measures are also compared for discussion.

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

    International Nuclear Information System (INIS)

    1986-01-01

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

  15. Generation and release of radioactive gases in LLW disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Yim, M.S. [Harvard School Public Health, Boston, MA (United States); Simonson, S.A. [Massachusetts Institute of Technology, Cambridge, MA (United States)

    1995-02-01

    The atmospheric release of radioactive gases from a generic engineered LLW disposal facility and its radiological impacts were examined. To quantify the generation of radioactive gases, detailed characterization of source inventory for carbon-14, tritium, iodine-129, krypton-85, and radon-222, was performed in terms of their activity concentrations; their distribution within different waste classes, waste forms and containers; and their subsequent availability for release in volatile or gaseous form. The generation of gases was investigated for the processes of microbial activity, radiolysis, and corrosion of waste containers and metallic components in wastes. The release of radionuclides within these gases to the atmosphere was analyzed under the influence of atmospheric pressure changes.

  16. Airborne radioactive effluents: releases and processing

    International Nuclear Information System (INIS)

    Grissom, M.C.

    1982-10-01

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

  17. Radioactive materials released from nuclear power plants (1976)

    International Nuclear Information System (INIS)

    Decker, T.R.

    1978-11-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1976 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1976 release data are compared with previous year releases in tabular form. Data covering specific radionuclides are summarized

  18. Radioactive materials released from nuclear power plants. Annual report 1977

    International Nuclear Information System (INIS)

    Decker, T.R.

    1978-11-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1977 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1977 release data are compared with previous years releases in tabular form. Data covering specific radionuclides are summarized

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-04-01

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

  20. Radioactive materials released from nuclear power plants: Annual report, 1984

    Energy Technology Data Exchange (ETDEWEB)

    Tichler, J.; Norden, K.; Congemi, J.

    1987-08-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1984 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1984 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

  1. 10 CFR 61.41 - Protection of the general population from releases of radioactivity.

    Science.gov (United States)

    2010-01-01

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

  2. Discussion on the methods for calculation release limits for low-level radioactive waste

    International Nuclear Information System (INIS)

    Cao Fengbo; Liu Xiaochao

    2012-01-01

    The release request for low-level radioactive waste are briefly described in this paper. Associating with the conditions of low-level radioactive waste of some radioactive waste processing station, the methods and gist for calculating release limits for low-level radioactive waste with national release limits and annual effective dose limit for the public or the occupation are discussed. Then release limits for the low-level radioactive waste are also proposed. (authors)

  3. Hazard of radioactive releases resulted from coal burning

    International Nuclear Information System (INIS)

    Gabbard, V.

    1995-01-01

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

  4. Atmospheric dispersion of radioactive releases: Computer code DIASPORA

    International Nuclear Information System (INIS)

    Synodinou, B.M.; Bartzis, J.M.

    1982-05-01

    The computer code DIASPORA is presented. Air and ground concentrations of an airborne radioactive material released from an elevated continuous point source are calculated using Gaussian plume models. Dry and wet deposition as well as plume rise effects are taken into consideration. (author)

  5. Response to a radioactive materials release having a transboundary impact

    International Nuclear Information System (INIS)

    1989-01-01

    Compared with an accidental release of radioactive material which is confined to the accident State, a transboundary release has added dimensions which were not fully anticipated in publications dealing with response to accidents at nuclear facilities. The new aspects to the problem may be summarized as follows: (1) A transboundary release of radioactive material, as distinct from a release which affects only the accident State, has international repercussions in the following ways: Potentially at least, the difficulties associated with a transboundary release may be magnified in those States that have no nuclear facilities of their own and may, therefore, have foreseen no need for resources to assess and deal with radioactive contamination of their food supplies, their water and their environment appropriately. International trade, in food commodities particularly, may be severely affected. Issues of compensation may arise for which the dispute settlement mechanisms are weak or non-existent. (2) Many Member States are in such geographic locations that they could be affected by a transboundary release occurring in any of their surrounding neighbour States. Planning for and responding to such an event is necessarily more difficult than planning for an accidental release from a single, identified nuclear facility. (3) Deposits of radioactive material from a distant source are apt to be highly unpredictable. Depending on weather conditions, they may be localized in a random fashion or widespread. Because of the international dimension of the problem and its essentially unpredictable character it is recommended here that planning for such events should be carried at the national or federal government level rather than at provincial government level. 14 refs

  6. Prevention and mitigation of groundwater contamination from radioactive releases

    International Nuclear Information System (INIS)

    1988-10-01

    This document gives basic information on potential pathways and mechanisms, by which radioactive materials from releases can reach man, and on modelling considerations to predict the behaviour of radioactive materials in the ground. The main objective is to present an overview of existing techniques for preventing the offsite releases of contaminants into the groundwater systems and techniques for mitigation of effects of such releases should they occur. The recommended techniques are fully applicable to any hazardous materials, such as organic liquids, and toxic materials or otherwise dangerous materials, the presence of which in the accessible biosphere can represent health risks as well as economic losses to the general public. 11 refs, 2 figs, 8 tabs

  7. Stochastic Modeling of Radioactive Material Releases

    Energy Technology Data Exchange (ETDEWEB)

    Andrus, Jason [Idaho National Lab. (INL), Idaho Falls, ID (United States); Pope, Chad [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    Nonreactor nuclear facilities operated under the approval authority of the U.S. Department of Energy use unmitigated hazard evaluations to determine if potential radiological doses associated with design basis events challenge or exceed dose evaluation guidelines. Unmitigated design basis events that sufficiently challenge dose evaluation guidelines or exceed the guidelines for members of the public or workers, merit selection of safety structures, systems, or components or other controls to prevent or mitigate the hazard. Idaho State University, in collaboration with Idaho National Laboratory, has developed a portable and simple to use software application called SODA (Stochastic Objective Decision-Aide) that stochastically calculates the radiation dose associated with hypothetical radiological material release scenarios. Rather than producing a point estimate of the dose, SODA produces a dose distribution result to allow a deeper understanding of the dose potential. SODA allows users to select the distribution type and parameter values for all of the input variables used to perform the dose calculation. SODA then randomly samples each distribution input variable and calculates the overall resulting dose distribution. In cases where an input variable distribution is unknown, a traditional single point value can be used. SODA was developed using the MATLAB coding framework. The software application has a graphical user input. SODA can be installed on both Windows and Mac computers and does not require MATLAB to function. SODA provides improved risk understanding leading to better informed decision making associated with establishing nuclear facility material-at-risk limits and safety structure, system, or component selection. It is important to note that SODA does not replace or compete with codes such as MACCS or RSAC, rather it is viewed as an easy to use supplemental tool to help improve risk understanding and support better informed decisions. The work was

  8. Stochastic Modeling of Radioactive Material Releases

    International Nuclear Information System (INIS)

    Andrus, Jason; Pope, Chad

    2015-01-01

    Nonreactor nuclear facilities operated under the approval authority of the U.S. Department of Energy use unmitigated hazard evaluations to determine if potential radiological doses associated with design basis events challenge or exceed dose evaluation guidelines. Unmitigated design basis events that sufficiently challenge dose evaluation guidelines or exceed the guidelines for members of the public or workers, merit selection of safety structures, systems, or components or other controls to prevent or mitigate the hazard. Idaho State University, in collaboration with Idaho National Laboratory, has developed a portable and simple to use software application called SODA (Stochastic Objective Decision-Aide) that stochastically calculates the radiation dose associated with hypothetical radiological material release scenarios. Rather than producing a point estimate of the dose, SODA produces a dose distribution result to allow a deeper understanding of the dose potential. SODA allows users to select the distribution type and parameter values for all of the input variables used to perform the dose calculation. SODA then randomly samples each distribution input variable and calculates the overall resulting dose distribution. In cases where an input variable distribution is unknown, a traditional single point value can be used. SODA was developed using the MATLAB coding framework. The software application has a graphical user input. SODA can be installed on both Windows and Mac computers and does not require MATLAB to function. SODA provides improved risk understanding leading to better informed decision making associated with establishing nuclear facility material-at-risk limits and safety structure, system, or component selection. It is important to note that SODA does not replace or compete with codes such as MACCS or RSAC, rather it is viewed as an easy to use supplemental tool to help improve risk understanding and support better informed decisions. The work was

  9. PWR-GALE, Radioactive Gaseous Release and Liquid Release from PWR

    International Nuclear Information System (INIS)

    Chandrasekaran, T.; Lee, J.Y.; Willis, C.A.

    1988-01-01

    1 - Description of program or function: The PWR-GALE (Boiling Water Reactor Gaseous and Liquid Effluents) Code is a computerized mathematical model for calculating the release of radioactive material in gaseous and liquid effluents from pressurized water reactors (PWRs). The calculations are based on data generated from operating reactors, field tests, laboratory tests, and plant-specific design considerations incorporated to reduce the quantity of radioactive materials that may be released to the environment. 2 - Method of solution: GALE calculates expected releases based on 1) standardized coolant activities derived from ANS Standards 18.1 Working Group recommendations, 2) release and transport mechanisms that result in the appearance of radioactive material in liquid and gaseous waste streams, 3) plant-specific design features used to reduce the quantities of radioactive materials ultimately released to the environs, and 4) information received on the operation of nuclear power plants. 3 - Restrictions on the complexity of the problem: The liquid release portion of GALE uses subroutines taken from the ORIGEN (CCC-217) to calculate radionuclide buildup and decay during collection, processing, and storage of liquid radwaste. Memory requirements for this part of the program are determined by the large nuclear data base accessed by these subroutines

  10. Conditioning the radioactive oils released from the Cernavoda NPP operation

    International Nuclear Information System (INIS)

    Popescu, I.; Deneanu, N.; Dulama, M.; Baboiescu, E.

    2001-01-01

    The radioactive oils released during the Cernavoda NPP operation are lubricating oils used in the primary circuit pumps, hydraulic oils used in the reactor charging machine, as well as, waste turbine oils. The primary cooling circuit is the main way of contamination. This waste contain variable amounts of tritium of activities up to 10 8 Bq/l and relatively small amounts of β/γ emitting radionuclides. The radioactive oils resulting of the heat transport system may contain as much as 1.8 TBq/l of tritium. At INR Pitesti, Department of Radioactive Waste Processing, studies were done concerning the radioactive oils conditioning in concrete. It was found that the minimal compression level required for disposal, of 50 MPa, was exceeded. As consequence, the conditioned waste fulfils the conditions of acceptance provided by the Radioactive Waste National Repository at Baita-Bihor. The main stages of the process are: - dosing the radioactive oil, water and NOFOX9 and NOFOX4 emulsion additives for the 220 l or 80 l barrel; - mixing these ingredients up to reaching the emulsion state; - dosing the cement and lime; - adding the enhancing silicate and shaking the mixture to get a homogeneous matrix; - closing the barrel; - conditioning the 80 l barrel within the 220 l container. The production capacity is of 5 to 8 barrels/shift

  11. 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.)

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

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  13. Applied exposure modeling for residual radioactivity and release criteria

    International Nuclear Information System (INIS)

    Lee, D.W.

    1989-01-01

    The protection of public health and the environment from the release of materials with residual radioactivity for recycle or disposal as wastes without radioactive contents of concern presents a formidable challenge. Existing regulatory criteria are based on technical judgment concerning detectability and simple modeling. Recently, exposure modeling methodologies have been developed to provide a more consistent level of health protection. Release criteria derived from the application of exposure modeling methodologies share the same basic elements of analysis but are developed to serve a variety of purposes. Models for the support of regulations for all applications rely on conservative interpretations of generalized conditions while models developed to show compliance incorporate specific conditions not likely to be duplicated at other sites. Research models represent yet another type of modeling which strives to simulate the actual behavior of released material. In spite of these differing purposes, exposure modeling permits the application of sound and reasoned principles of radiation protection to the release of materials with residual levels of radioactivity. Examples of the similarities and differences of these models are presented and an application to the disposal of materials with residual levels of uranium contamination is discussed. 5 refs., 2 tabs

  14. 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

  15. Releases of radioactivity at the Savannah River Plant, 1954--1985

    International Nuclear Information System (INIS)

    Zeigler, C.C.; Lawrimore, I.B.

    1988-07-01

    Radioactive releases from Savannah River Plant (SRP) facilities to air, water and earthen seepage basins have been monitored and tabulated throughout the history of the site. The purpose of this report is to provide a source of data on routine releases of radioactivity to air, water and seepage basins that can be used for analyses of trends, environmental impact, etc. As used in this report, routine radioactive releases means radioactive materials that are released through established effluents from process facilities. This report provides a summary of radioactive releases that inflects the release values contained m records and documents from startup through 1985

  16. Radioactive iodine releases from nuclear power plant, (1)

    International Nuclear Information System (INIS)

    Hashimoto, Tatsuya

    1974-01-01

    Concerning the release of radioactive iodine from nuclear power plants, the guidelines and data both in Japan and abroad are briefed, including those in the United States, Tsuruga nuclear power station and working Group of the Environmental Radiation Study Committee. In case of the Tsuruga nuclear power station, the radiation dose and other data for a few years are presented. Parameters and factors proposed by the working group cover such as the dose through food intake and respiration, concentration factor, etc. (Mori, K.)

  17. Monitoring water for radioactive releases in the United States

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  18. PAVAN, Atmospheric Dispersion of Radioactive Releases from Nuclear Power Plants

    International Nuclear Information System (INIS)

    2001-01-01

    1 - Description of program or function: PAVAN estimates down-wind ground-level air concentrations for potential accidental releases of radioactive material from nuclear facilities. Options can account for variation in the location of release points, additional plume dispersion due to building wakes, plume meander under low wind speed conditions, and adjustments to consider non-straight trajectories. It computes an effective plume height using the physical release height which can be reduced by inputted terrain features. 2 - Method of solution: Using joint frequency distributions of wind direction and wind speed by atmospheric stability, the program provides relative air concentration (X/Q) values as functions of direction for various time periods at the exclusion area boundary (EAB) and the outer boundary of the low population zone (LPZ). Calculations of X/Q values can be made for assumed ground-level releases or evaluated releases from free-standing stacks. The X/Q calculations are based on the theory that material released to the atmosphere will be normally distributed (Gaussian) about the plume centerline. A straight-line trajectory is assumed between the point of release and all distances for which X/Q values are calculated. 3 - Restrictions on the complexity of the problem: - The code cannot handle multiple emission sources

  19. Air concentration and ground deposition following radioactive airborne releases

    International Nuclear Information System (INIS)

    Brofferio, C.; Cagnetti, P.; Ferrara, V.

    1985-01-01

    The fundamental aim of this report is to provide the mathematical and physical operational basis for the evaluation of air concentration and ground deposition, following radioactive airborne releases from a nuclear power plant, both during normal operations and in accidental conditions. As far as accidental releases are concerned, the basical assumptions on meteorological and diffusive situation are considered from a safety point of view: namely those pessimistic but realistically representative situation are taken into account which lead to maximum air concentration and ground deposition values, even if characterized by low recurrence probability. Those elements are the inputs for many environmental transfer models of maximum consequence evaluations up to man. As far as routine releases are concerned, it is shown, together with the usual models based on long term averaged meteorological conditions, also models studied to estimate atmospheric diffusion and deposition in low wind situations and in fog conditions, being those latter very frequent in the Po valley. Finally, the main operations and modalities of collecting and elaborating meteorological data for for radioprotection evaluations are also shown. It is to be pointed out that the methods and the models developed and considered in this work are of a more general validity, and can be also used for applications concerning non-radioactive releases, as it is the case when dealing with conventional power plants

  20. Risk assessment methodology for evaluating releases of radioactively contaminated materials

    International Nuclear Information System (INIS)

    Chen, S.Y.

    1993-01-01

    Extensive decontamination and decommissioning (D ampersand D) activities are expected to be required in the near future in association with license termination of nuclear power facilities and cleanup efforts at the U.S. Department of Energy's (DOE's) weapons production facilities. In advance of these D ampersand D activities, it is becoming increasingly urgent that standards be established for the release of materials with residual radioactive contamination. The only standards for unrestricted release that currently exist address surface contamination. The methods used to justify those standards were developed some 20 yr ago and may not satisfy today's criteria. Furthermore, the basis of setting standards has moved away from the traditional open-quotes instrumentation-basedclose quotes concept toward a open-quotes risk-basedclose quotes approach. Therefore, as new release standards are developed, it will be necessary that risk assessment methodology consistent with modern concepts be incorporated into the process. This paper discusses recent developments in risk methodology and issues and concerns regarding the future development of standards for the release of radioactively contaminated materials

  1. Assessment of consequences from airborne releases of radioactive material

    International Nuclear Information System (INIS)

    McGrath, P.E.; Blond, R.M.

    1976-01-01

    Over the past several years, the manner in which assessments have been made of the consequences of large airborne releases of radioactive material has not changed much conceptually. The models to describe the atmospheric dispersion of the radioactive material have generally been time-invariant, i.e., the meteorological conditions (thermal stability, wind speed, and precipitation) are invariant during release and the subsequent period of radiation exposure of the population to the airborne material. The frequency distribution of the meteorological conditions are determined by analyzing several years of weather data from the appropriate geographical location. In reality, weather is continuously changing over short time periods (hours) following the release. It is to be expected that the changing meteorological conditions would have important effects on the potential consequences of the release. A time-dependent atmospheric dispersion model was developed and implemented in the Reactor Safety Study. This paper provides a description of the model and the nature of the results generated. Emphasis is given to an explanation of how, and why, these results differ from those estimated with time-invariant models

  2. Underground Nuclear Explosions and Release of Radioactive Noble Gases

    Science.gov (United States)

    Dubasov, Yuri V.

    2010-05-01

    Over a period in 1961-1990 496 underground nuclear tests and explosions of different purpose and in different rocks were conducted in the Soviet Union at Semipalatinsk and anovaya Zemlya Test Sites. A total of 340 underground nuclear tests were conducted at the Semipalatinsk Test Site. One hundred seventy-nine explosions (52.6%) among them were classified as these of complete containment, 145 explosions (42.6%) as explosions with weak release of radioactive noble gases (RNG), 12 explosions (3.5%) as explosions with nonstandard radiation situation, and four excavation explosions with ground ejection (1.1%). Thirty-nine nuclear tests had been conducted at the Novaya Zemlya Test Site; six of them - in shafts. In 14 tests (36%) there were no RNG release. Twenty-three tests have been accompanied by RNG release into the atmosphere without sedimental contamination. Nonstandard radiation situation occurred in two tests. In incomplete containment explosions both early-time RNG release (up to ~1 h) and late-time release from 1 to 28 h after the explosion were observed. Sometimes gas release took place for several days, and it occurred either through tunnel portal or epicentral zone, depending on atmospheric air temperature.

  3. Consequences of severe radioactive releases to Nordic Marine environment

    Energy Technology Data Exchange (ETDEWEB)

    Iosjpe, M. [Norwegian Radiation Protection Authority (NRPA) (Norway); Isaksson, M. [Univ. of Gothenburg (Sweden); Joensen, H.P. [Froskaparsetur Foeroya. Faroe Islands, Torshavn (Denmark); Lahtinen, J. [Radiation and Nuclear Safety Authority (Finland); Logemann, K. [Univ. of Iceland (Iceland); Palsson, S.E. [Geislavarnir Rikisins (Iceland); Roos, P. [Technical Univ. of Denmark. Risoe DTU, Roskilde (Denmark); Suolanen, V. [Technical Research Centre of Finland (Finland)

    2013-02-15

    In the report, consequences of hypothetical severe nuclear accidents releases to Nordic marine environment are preliminary considered. The considered marine area comprises the Baltic Sea (Sweden, Denmark, Finland) and the North Atlantic (Iceland, Faroes, Norway) areas. The hypothetical severe nuclear accidents can be related to nuclear power plants, nuclear powered submarines or ice-breakers. Quite comprehensive survey on radioactive source terms of extremely severe nuclear power and submarine accidents has been done. This enables to estimate more realistically possible radioactive releases of various elements and nuclides to marine environment. One recent reference is of course the Fukushima accident and estimated releases there. The marine flows and dilution circumstances around the Nordic nuclear power plants and in the Baltic Sea area in general, has been studied. Respectively marine flows related to Iceland and Faroes coasts are considered with measured data and with preliminary 3D-model simulations. The substantial depth of sea water in the North Atlantic affect vertical concentration profiles to some extent. At Icelandic or Faroese waters, a potential submarine accident would likely occur in a well defined water mass, and radioactivity from the accident would be detected and spread with the flow regime of the water mass in the world ocean. Based on hypothetical severe accidents scenarios, preliminary consequence calculations has been done. It should be emphasised that the considered severe accident cases, considered in this study, do not directly attach any specific Nordic nuclear power plant or any specific submarine type. The considered radioactive releases will, however, provide specified references for more extensive consideration of environmental consequences of severe - or minor - radioactive releases to Nordic marine environment. As a reference, the release amounts from a 3000 MW{sub th} reactor size were used. Based on source term analyses, the

  4. Consequences of severe radioactive releases to Nordic Marine environment

    International Nuclear Information System (INIS)

    Iosjpe, M.; Isaksson, M.; Joensen, H.P.; Lahtinen, J.; Logemann, K.; Palsson, S.E.; Roos, P.; Suolanen, V.

    2013-02-01

    In the report, consequences of hypothetical severe nuclear accidents releases to Nordic marine environment are preliminary considered. The considered marine area comprises the Baltic Sea (Sweden, Denmark, Finland) and the North Atlantic (Iceland, Faroes, Norway) areas. The hypothetical severe nuclear accidents can be related to nuclear power plants, nuclear powered submarines or ice-breakers. Quite comprehensive survey on radioactive source terms of extremely severe nuclear power and submarine accidents has been done. This enables to estimate more realistically possible radioactive releases of various elements and nuclides to marine environment. One recent reference is of course the Fukushima accident and estimated releases there. The marine flows and dilution circumstances around the Nordic nuclear power plants and in the Baltic Sea area in general, has been studied. Respectively marine flows related to Iceland and Faroes coasts are considered with measured data and with preliminary 3D-model simulations. The substantial depth of sea water in the North Atlantic affect vertical concentration profiles to some extent. At Icelandic or Faroese waters, a potential submarine accident would likely occur in a well defined water mass, and radioactivity from the accident would be detected and spread with the flow regime of the water mass in the world ocean. Based on hypothetical severe accidents scenarios, preliminary consequence calculations has been done. It should be emphasised that the considered severe accident cases, considered in this study, do not directly attach any specific Nordic nuclear power plant or any specific submarine type. The considered radioactive releases will, however, provide specified references for more extensive consideration of environmental consequences of severe - or minor - radioactive releases to Nordic marine environment. As a reference, the release amounts from a 3000 MW th reactor size were used. Based on source term analyses, the chosen

  5. A Bayesian Analysis of the Radioactive Releases of Fukushima

    DEFF Research Database (Denmark)

    Tomioka, Ryota; Mørup, Morten

    2012-01-01

    the types of nuclides and their levels of concentration from the recorded mixture of radiations to take necessary measures. We presently formulate a Bayesian generative model for the data available on radioactive releases from the Fukushima Daiichi disaster across Japan. From the sparsely sampled...... the Fukushima Daiichi plant we establish that the model is able to account for the data. We further demonstrate how the model extends to include all the available measurements recorded throughout Japan. The model can be considered a first attempt to apply Bayesian learning unsupervised in order to give a more......The Fukushima Daiichi disaster 11 March, 2011 is considered the largest nuclear accident since the 1986 Chernobyl disaster and has been rated at level 7 on the International Nuclear Event Scale. As different radioactive materials have different effects to human body, it is important to know...

  6. Individual dose due to radioactivity accidental release from fusion reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nie, Baojie [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); University of Science and Technology of China, Hefei, Anhui, 230027 (China); Ni, Muyi, E-mail: muyi.ni@fds.org.cn [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); Wei, Shiping [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); University of Science and Technology of China, Hefei, Anhui, 230027 (China)

    2017-04-05

    Highlights: • Conservative early dose of different unit fusion radioactivity release were assessed. • Data of accident level in INES for fusion reactor were proposed. • Method of environmental restoration time after fusion accident was proposed. • The maximum possible accident level for ITER like fusion reactor is 6. • We need 34–52 years to live after the fusion hypothetical accident. - Abstract: As an important index shaping the design of fusion safety system, evaluation of public radiation consequences have risen as a hot topic on the way to develop fusion energy. In this work, the comprehensive public early dose was evaluated due to unit gram tritium (HT/HTO), activated dust, activated corrosion products (ACPs) and activated gases accidental release from ITER like fusion reactor. Meanwhile, considering that we cannot completely eliminate the occurrence likelihood of multi-failure of vacuum vessel and tokamak building, we conservatively evaluated the public radiation consequences and environment restoration after the worst hypothetical accident preliminarily. The comparison results show early dose of different unit radioactivity release under different conditions. After further performing the radiation consequences, we find it possible that the hypothetical accident for ITER like fusion reactor would result in a level 6 accident according to INES, not appear level 7 like Chernobyl or Fukushima accidents. And from the point of environment restoration, we need at least 69 years for case 1 (1 kg HTO and 1000 kg dust release) and 34–52 years for case 2 (1 kg HTO and 10kg–100 kg dust release) to wait the contaminated zone drop below the general public safety limit (1mSv per year) before it is suitable for human habitation.

  7. Parametric study of radioactive release from a breached containment

    International Nuclear Information System (INIS)

    Kenigsberg, A.; Hasan, D.; Elias, E.

    1980-01-01

    A hypothetical accident is analyzed, in which an external (out-of-plant) natural or man-made event causes a loss-of-coolant accident after penetrating the containment wall. The computer codes CONTEMPT and RELAP4 have been used to study the containment thermal-hydraulic behavior during the accident. Results are given in the form of graphs showing the thermal-hydraulic response of the containment and the profile of radioactive release to the atmosphere. The physical model and input data are discussed. 13 refs

  8. Environmental system applied to radioactive liquid effluent release

    International Nuclear Information System (INIS)

    Nisti, Marcelo Bessa

    2009-01-01

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

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

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  10. Cask for radioactive material and method for preventing release of neutrons from radioactive material

    International Nuclear Information System (INIS)

    Gaffney, M.F.; Shaffer, P.T.

    1981-01-01

    A cask for radioactive material, such as nuclear reactor fuel or spent nuclear reactor fuel, includes a plurality of associated walled internal compartments for containing such radioactive material, with neutron absorbing material present to absorb neutrons emitted by the radioactive material, and a plurality of thermally conductive members, such as longitudinal copper or aluminum castings, about the compartment and in thermal contact with the compartment walls and with other such thermally conductive members and having thermal contact surfaces between such members extending, preferably radially, from the compartment walls to external surfaces of the thermally conductive members, which surfaces are preferably in the form of a cylinder. The ends of the shipping cask also preferably include a neutron absorber and a conductive metal covering to dissipate heat released by decay of the radioactive material. A preferred neutron absorber utilized is boron carbide, preferably as plasma sprayed with metal powder or as particles in a matrix of phenolic polymer, and the compartment walls are preferably of stainless steel, copper or other corrosion resistant and heat conductive metal or alloy. The invention also relates to shipping casks, storage casks and other containers for radioactive materials in which a plurality of internal compartments for such material, e.g., nuclear reactor fuel rods, are joined together, preferably in modular construction with surrounding heat conductive metal members, and the modules are joined together to form a major part of a finished shipping cask, which is preferably of cylindrical shape. Also within the invention are methods of safely storing radioactive materials which emit neutrons, while dissipating the heat thereof, and of manufacturing the present shipping casks

  11. Radioactive release from VVER-1000 reactors after a terror attack

    International Nuclear Information System (INIS)

    Sdouz, G.

    2005-01-01

    Full text: One of the terror scenarios for nuclear power plants is a severe damage of the reactor containment caused by a plane crash or a missile. Due to the loss of electric power the cooling of the core is not maintained leading to a core melt accident. Normally in the course of severe accidents an intact containment has the ability to retain a large part of the radioactive inventory. The goal of this work is the investigation of the behavior of the radioactive release from a VVER-1000-type reactor during a severe accident with a large containment leak from the beginning of the accident. The results are compared with the release in a severe accident via a very small leakage due to the untightness of the containment. This work supplements a series of studies investigating the behavior of a VVER-1000-type reactor during severe accidents under different accident management strategies. The focus in this study is on the 'station blackout'-sequence (or TMLB' in the WASH-1400 nomenclature). The calculations were performed using the Source Term Code Package (STCP), hydrogen explosions are not considered. Up to the melt-through of the cavity bottom the thermal-hydraulics phenomena are almost identical to the TMLB'-case with an intact containment from the beginning. The phenomena occur slightly delayed due to the large containment leak. When the core-concrete-interaction begins the resulting gases leave the containment through the large leak and do not cause a pressure increase. The containment pressure remains at ambient pressure. Due to the different behavior and to the different release times of the nuclides the deviations to the scenario with an intact containment show a great variety. From this comparison it can be shown that the intact containment retains the nuclides up to a factor of 6000. (author)

  12. Monitoring for radioactive materials releasing to environment in M310 reformatived nuclear power plant

    International Nuclear Information System (INIS)

    Yin Zhenyu; Yang Guangli; Xu Guang

    2012-01-01

    Airborne radioactive materials of nuclear power plant (NPP) releases to the environment from the stack of NPP. Radioactive liquid waste releases of the ocean, the fluvial and the lake through the liquid waste letdyke of NPP. Further more, a few radioactive waste may be taken out of the NPP by vehicle or personnel. For the purpose of strict management and control above-mentioned waste, we use detect equipment monitoring radioactive waste of NPP. Management and control for the releasing of radioactive material to the environment in M310 reformatived NPP is strict and safety. (authors)

  13. Monitoring of the release of gaseous and aerosol-bound radioactive materials. Pt. 2

    International Nuclear Information System (INIS)

    1992-01-01

    KTA 1503 contains requirements on technical installations and supplementary organizational measures considered necessary in order to monitor the release of gaseous and aerosol-bound radioactive materials. It consists of part 1: Monitoring of the release of radioactive materials together with stack gas during normal operation; part 2: Monitoring of the release of radioactive materials together with stack gas in the event of incidents; part 3: Monitoring of radioactive materials not released together with stack gas. The concept on which this rule is based is to ensure that in the case of incidents during which the result of effluent monitoring remains meaningful, such monitoring can be reliably performed. (orig./HSCH) [de

  14. Historical releases of radioactivity to the environment from ORNL

    International Nuclear Information System (INIS)

    Ohnesorge, W.F.

    1986-05-01

    This report gives a brief history and assessment of ORNL radionuclide releases to the environment. A short history and an inventory of radioactivity disposed of by shallow land burial and hydrofracture techniques are given along with a brief discussion of the potential environmental impact of these disposed materials. The data available for this report varied greatly in quality. Data on contaminated liquid waste and liquids discharged to the environment are much more reliable than early data on contaminated air discharges and contaminated solid waste. Data for more recent years are more complete and reliable than data obtained from records dating back to the early history of the laboratory. The data presented here do not include materials retrievably stored (with the exception of uranium solid waste data) or inventories of materials stored in operating or surplus facilities since these materials presently have no contact with or loss to the environment

  15. Release of the radioactive patient following radiation therapy

    Energy Technology Data Exchange (ETDEWEB)

    Powers, J.; Cancer Board, A.

    2004-07-01

    Patients walk out of medical facilities containing as much as a complete therapeutic dose of radiation on a daily basis. This presents a significant challenge to the radiation protection community, as most patients have no prior education related to radiation and may not have the aptitude to assimilate such knowledge. In the case of targeted radiation therapy in which radionuclides are used to selectively target the cancer, patients are typically released only after adequate elimination and decay of the radionuclide administered. Established modalities of targeted radiotherapy include the use of iodine for thyroid cancer, strontium for bone pain, phosphorous for haematological diseases, 131I-mIBG for neuroblastoma, and most recently Y-90 labelled monoclonal antibodies for lymphoma. In the case of permanent implants, implants of encapsulated radioactive sources are left permanently in the tissues, thus patients are released containing their complete therapeutic dose. Isotopes used in permanent implants include I-125, Pd-103 and Au-198. Radiation safety considerations for both cases, the release of a patient who has received targeted radiotherapy, and the release of a patient who has received a permanent implant, will be discussed. A summary of applicable regulations will serve as a starting point for each of the following considerations; i) Security and source control ii) Instructions to patient and family members iii) Risk to the public As the incidence of cancer increases, and the popularity of targeted radiotherapy and permanent seed implants grows, the event of having an untrained person in possession of a therapeutic dose of radiation becomes more and more common. It is essential to stop and examine the risk of this practice, whether current strategies to reduce the risk to an acceptable level are indeed effective, and whether control over these sources is even feasible. (Author)

  16. Release of the radioactive patient following radiation therapy

    International Nuclear Information System (INIS)

    Powers, J.; Cancer Board, A.

    2004-01-01

    Patients walk out of medical facilities containing as much as a complete therapeutic dose of radiation on a daily basis. This presents a significant challenge to the radiation protection community, as most patients have no prior education related to radiation and may not have the aptitude to assimilate such knowledge. In the case of targeted radiation therapy in which radionuclides are used to selectively target the cancer, patients are typically released only after adequate elimination and decay of the radionuclide administered. Established modalities of targeted radiotherapy include the use of iodine for thyroid cancer, strontium for bone pain, phosphorous for haematological diseases, 131I-mIBG for neuroblastoma, and most recently Y-90 labelled monoclonal antibodies for lymphoma. In the case of permanent implants, implants of encapsulated radioactive sources are left permanently in the tissues, thus patients are released containing their complete therapeutic dose. Isotopes used in permanent implants include I-125, Pd-103 and Au-198. Radiation safety considerations for both cases, the release of a patient who has received targeted radiotherapy, and the release of a patient who has received a permanent implant, will be discussed. A summary of applicable regulations will serve as a starting point for each of the following considerations; i) Security and source control ii) Instructions to patient and family members iii) Risk to the public As the incidence of cancer increases, and the popularity of targeted radiotherapy and permanent seed implants grows, the event of having an untrained person in possession of a therapeutic dose of radiation becomes more and more common. It is essential to stop and examine the risk of this practice, whether current strategies to reduce the risk to an acceptable level are indeed effective, and whether control over these sources is even feasible. (Author)

  17. PABLM, Doses from Radioactive Releases to Atmosphere and Food Chain

    International Nuclear Information System (INIS)

    Napier, B.A.; Kennedy, W.E. Jr.; Soldat, J.K.

    1983-01-01

    1 - Description of problem or function: PABLM calculates internal radiation doses to man from radionuclides in food products and external radiation doses from radionuclides in the environment. Radiation doses from radionuclides in the environment may be calculated from deposition on the soil or plants during an atmospheric or liquid release, or from exposure to residual radionuclides after the releases have ended. Radioactive decay is considered during the release, after deposition, and during holdup of food after harvest. The radiation dose models consider exposure to radionuclides deposited on the ground or crops from contaminated air or irrigation water, radionuclides in contaminated drinking water, aquatic foods raised in contaminated water, and radionuclides in bodies of water and sediments where people might fish, boat, or swim. For vegetation, the radiation dose model considers both direct deposition and uptake through roots. Doses may be calculated for either a maximum-exposed individual or for a population group. The program is designed to calculate accumulated radiation doses from the chronic ingestion of food products that contain radionuclides and doses from the external exposure to radionuclides in the environment. A first-year committed dose is calculated as well as an integrated dose for a selected number of years. 2 - Method of solution: A chain decay scheme including branching for transitions to and from isomeric states is used for radioactive decay. The equations for calculating internal radiation doses are derived from those given by the International Commission on Radio- logical Protection (ICRP) for body burdens and the maximum possible concentration (MPC) for each radionuclide. These doses are calculated as a function of radionuclide concentration in food products, ingestion rates, and a radionuclide-specific dose- commitment factor. Radiation doses from external exposure to contaminated water and soil are calculated using the basic assumption

  18. Incident involving radioactive material at IAEA Safeguards Laboratory - No radioactivity released to environment

    International Nuclear Information System (INIS)

    2008-01-01

    Full text: Pressure build-up in a small sealed sample bottle in a storage safe resulted in plutonium contamination of a storage room at about 02:30 today at the IAEA's Safeguards Analytical Laboratory in Seibersdorf. All indications are that there was no release of radioactivity to the environment. Further monitoring around the laboratory will be undertaken. No one was working in the laboratory at the time. The Laboratory's safety system detected plutonium contamination in the storage room where the safe was located and in two other rooms - subsequently confirmed by a team of IAEA radiation protection experts. The Laboratory is equipped with multiple safety systems, including an air-filtering system to prevent the release of radioactivity to the environment. There will be restricted access to the affected rooms until they are decontaminated. A full investigation of the incident will be conducted. The IAEA has informed the Austrian regulatory authority. The IAEA's Laboratory in Seibersdorf is located within the complex of the Austrian Research Centers Seibersdorf (ARC), about 35 km southeast of Vienna. The laboratory routinely analyses small samples of nuclear material (uranium or plutonium) as part of the IAEA's safeguards verification work. (IAEA)

  19. Natural radioactivity releases from lignite power plants in Southwestern Anatolia

    International Nuclear Information System (INIS)

    Yaprak, G.; Guer, F.; Cam, F.; Candan, O.

    2006-01-01

    The Mugla basin is one of the most productive lignite basins in Southwestern Anatolia, Turkey. Mining activities started in 1979 and total reserves were estimated during exploration at 767.5 million tonnes. Total mean annual lignite production of the Mugla basin is estimated at about 10 million tonnes per year. Most of the lignite production supplies three thermal power plants (Yatagan 630 MW, Yenikoey 420 MW, Kemerkoey 630 MW) with a total capacity of 1680 MW. It is well known that the lignite contains naturally occurring primordial radionuclides arising from the uranium and thorium series as well as from 4 0K. Lignite burning is, therefore, one of the sources of technologically enhanced exposure to humans from natural radionuclides. The investigation reported here deals with the determination of the 2 26Ra, 2 32Th and 4 0K concentrations in the lignite feeding 3 thermal power plants in Mugla region and in the product ash. Samples of lignite feeding the power plants and fly and bottom ashes produced in the same power plants were collected over a period of 1 year and therefore systematic sampling allowed for the determination of mean representative values for the natural radioactivity content of above materials and also estimation of the radioactivity releases to the environment. Furthermore, grid soil sampling within 10-15 km around the power plants allowed for the mapping of the surface soil activity of natural radionuclides. Dosimetric calculations from terrestrial gamma radiation for the population living around the power plants were performed based on the guidance of UNSCEAR 2000 report

  20. RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

    International Nuclear Information System (INIS)

    KOZLOWSKI, S.D.

    2007-01-01

    This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below

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

    CERN Document Server

    Vojtyla, P

    2005-01-01

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

  2. Radioactive releases of nuclear power plants: the code ASTEC

    International Nuclear Information System (INIS)

    Sdouz, G.; Pachole, M.

    1999-11-01

    In order to adopt potential countermeasures to protect the population during the course of an accident in a nuclear power plant a fast prediction of the radiation exposure is necessary. The basic input value for such a dispersion calculation is the source term, which is the description of the physical and chemical behavior of the released radioactive nuclides. Based on a source term data base a pilot system has been developed to determine a relevant source term and to generate the input file for the dispersion code TAMOS of the Zentralanstalt fuer Meteorologie und Geodynamik (ZAMG). This file can be sent directly as an attachment of e-mail to the TAMOS user for further processing. The source terms for 56 European nuclear power plant units are included in the pilot version of the code ASTEC (Austrian Source Term Estimation Code). The use of the system is demonstrated in an example based on an accident in the unit TEMELIN-1. In order to calculate typical core inventories for the data bank the international computer code OBIGEN 2.1 was installed and applied. The report has been completed with a discussion on the optimal data transfer. (author)

  3. ARRRG/FOOD, Doses from Radioactive Release to Food Chain

    International Nuclear Information System (INIS)

    Napier, B.A.; Roswell, R.L.; Kennedy, W.E. Jr.; Strenge, D.L.

    1984-01-01

    1 - Description of problem or function: ARRRG calculates radiation doses to humans for radionuclides released to bodies of water from which people might obtain fish, other aquatic foods, or drinking water, and in which they might fish, swim, or boat. FOOD calculates radiation doses to humans from deposition on farm or garden soil and crops during either an atmospheric or water release of radionuclides. Deposition may be either directly from the air or from irrigation water. With both programs, doses may be calculated for either a maximum- exposed individual or for a population group. Doses calculated are a one-year dose and a committed dose from one year of exposure. The exposure is usually considered as chronic; however, equations are included to calculate dose and dose commitment from acute, one-time, exposure. 2 - Method of solution: The radiation doses from external exposure to contaminated farm fields or shorelines are calculated assuming an 'infinite' flat plane source of radionuclides. A factor of two is included for surface roughness, and a modifying factor is used to compensate for finite extent in the shoreline calculations. The radionuclide concentrations in aquatic and irrigated food products are based on the radionuclide concentration in the contaminated water, which is based on the release rate of radioactive contamination and the characteristics of the receiving water body. Concentration of radionuclides in plants depends on the concentrations in the soil, air, and water. Concentration of radionuclides in farm animal products, such as milk, meat, or eggs, depends on the animal's consumption of feed, forage, and water containing radionuclides. For persons swimming in contaminated water, the dose is calculated assuming that the body of water is an infinite medium relative to the range of emitted radiations. Persons boating on the water are assumed to be exposed to a dose rate half that of swimmers. Internal doses are calculated as a function of

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  5. The environmental impact of radioactive releases from accidents in nuclear power reactors

    International Nuclear Information System (INIS)

    Beattie, J.R.; Griffiths, R.F.; Kaiser, G.D.; Kinchin, G.H.

    1978-01-01

    A survey of accidental releases of radioactivity from thermal and fast reactors is presented. Following a general discussion on the hazards involved, the nature of the environmental impact of radioactive releases is examined. This includes a brief review of the natural radiation background, the effect on human health of various levels of radiation and radioactivity, permissible and reference levels, and the type of hazards from both passing clouds of airbourne radioactive material and from ground deposited material. The problem of atmospheric dispersion and methods of calculations of radioactive materials in the atmosphere are examined in order for the consequences of accidental release to be analysed. National accidents and their environmental consequences are then examined. Finally there is a review of the risks to which man is always exposed because of his environment. Common and collective risks are also considered. Conclusions are reached as to the acceptibility or otherwise of the environmental impact of reactor accidents. (U.K.)

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

    International Nuclear Information System (INIS)

    Gong Quan; Zhou Jing; Liu Yu

    2014-01-01

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

  7. The cleanup of releases of radioactive materials from commercial low-level radioactive waste disposal sites: Whose jurisdiction?

    International Nuclear Information System (INIS)

    Hartnett, C.

    1994-01-01

    There exists an overlap between the Comprehensive Environmental Response, Compensation and Recovery Act (open-quotes CERCLAclose quotes) and the Atomic Energy Act (open-quotes AEAclose quotes) regarding the cleanup of releases of radioactive materials from commercial low-level radioactive waste sites. The Nuclear Regulatory Commission (open-quotes NRCclose quotes) and Agreement States have jurisdiction under the AEA, and the Environmental Protection Agency (open-quotes EPAclose quotes) has jurisdiction pursuant to CERCLA. This overlapping jurisdiction has the effect of imposing CERCLA liability on parties who have complied with AEA regulations. However, CERCLA was not intended to preempt existing legislation. This is evidenced by the federally permitted release exemption, which explicitly exempts releases from CERCLA liability pursuant to an AEA license. With little guidance as to the applicability of this exemption, it is uncertain whether CERCLA's liability is broad enough to supersede the Atomic Energy Act. It is the purpose of this paper to discuss the overlapping jurisdiction for the cleanup of releases of radioactive materials from commercial low-level radioactive waste disposal sites with particular emphasis on the cleanup at the Maxey Flats, West Valley and Sheffield sites

  8. Evaluation Of Radioactivity Of Released Air During Postirradiation Examination At The RMI

    International Nuclear Information System (INIS)

    Prayitno, B.; Eko, Pudjadi

    1998-01-01

    Radioactivity evaluation of released air during post-irradiation examination at RMI has been done since january 1993 to december 1996. The released air radioactivity has been observed during post-irradiation examinations of irradiated fuels and structure materials in the hot cell. Analysis method employed has been by air sampling and measurement of the alpha and beta activities by using alpha beta aerosol LB 150 D model. Air release from RMI was sucked by using an air pump having 40 m3/hour capacity which is equipped with a 200 mm diameter filter paper. The filter paper is automatically counted by the detector of the instrument. The average of the daily maximum counting result in a month has been used as monthly data. It has been shown that there have been increase in the released air radioactivity caused by the post-irradiation examination activity. The data of the released air activity obtained have been used to calculate the radioactivity concentration and radioactivity on the soil surface based on Gauss Plumes. The calculation result have shown that the alpha and beta radioactivity concentration at stacks and on the soil surface are less then the set maximum permissible concentration (MPC)

  9. ARANO - a computer program for the assessment of radiological consequences of atmospheric radioactive releases

    International Nuclear Information System (INIS)

    Savolainen, I.; Vuori, S.

    1980-09-01

    A short description of the calculation possibilities, methods and of the structure of the computer code system ARANO is given, in addition to the input quide. The code can be employed in the calculation of environmental radiological consequences caused by radioactive materials released to atmosphere. Results can be individual doses for different organs at given distances from the release point, collective doses, numbers of persons exceeding given dose limits, numbers of casualties, areas polluted by deposited activity and losses of investments or production due to radioactive contamination. Both a case with a single release and atmospheric dispersion situation and a group of radioactive release and dispersions with discrete probability distributions can be considered. If the radioactive releases or the dispersion conditions are described by probability distributions, the program assesses the magnitudes of the specified effects in all combinations of the release and dispersion situations and then calculates the expectation values and the cumulative probability distributions of the effects. The vertical mixing in the atmosphere is described with a Ksub(Z)-model. In the lateral direction the plume is assumed to be Gaussian, and the release duration can be taken into account in the σsub(y)-values. External gamma dose from the release plume is calculated on the basis of a data file which has been created by 3-dimensional integration. Dose due to inhalation and due to gamma radiation from the contaminated ground are calculated by using appropriate dose conversion factors, which are collected into two mutually alternative block data subprograms. (author)

  10. Use of OND-86 recommendations for calculation of the Shelter radioactive release

    International Nuclear Information System (INIS)

    Bogatov, S.A.

    2000-01-01

    A model of radioactive release from the Shelter has been considered under current operation conditions. Integral assessment of current dust release has been done on the base of natural ventilation rate. Model predictions are consistent (20% accuracy) with experimental results of air contamination measurements at the earth surface. 12 refs., 1 tab., 6 figs

  11. Savannah River Site Ingestion Pathway Methodology Manual for Airborne Radioactive Releases

    Energy Technology Data Exchange (ETDEWEB)

    Vincent, A.W. III

    2001-01-03

    This manual documents a recommended methodology for determining the ingestion pathway consequences of hypothetical accidental airborne radiological releases from facilities at the Savannah River Site. Both particulate and tritiated radioactive contaminants are addressed. Other approaches should be applied for evaluation of routine releases.

  12. RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

    International Nuclear Information System (INIS)

    KOZLOWSKI, D.S.

    2005-01-01

    The body of this document analyzes scenarios involving releases of dried tank waste from the DBVS dried waste transfer system and OGTS HEPA filters. Analyses of dried waste release scenarios from the CH-TRUM WPU are included as Appendix D

  13. Accumulation of radioactive cesium released from Fukushima Daiichi Nuclear Power Plant in terrestrial cyanobacteria Nostoc commune.

    Science.gov (United States)

    Sasaki, Hideaki; Shirato, Susumu; Tahara, Tomoya; Sato, Kenji; Takenaka, Hiroyuki

    2013-01-01

    The Fukushima Daiichi Nuclear Power Plant accident released large amounts of radioactive substances into the environment and contaminated the soil of Tohoku and Kanto districts in Japan. Removal of radioactive material from the environment is an urgent problem, and soil purification using plants is being considered. In this study, we investigated the ability of 12 seed plant species and a cyanobacterium to accumulate radioactive material. The plants did not accumulate radioactive material at high levels, but high accumulation was observed in the terrestrial cyanobacterium Nostoc commune. In Nihonmatsu City, Fukushima Prefecture, N. commune accumulated 415,000 Bq/kg dry weight (134)Cs and 607,000 Bq kg(-1) dry weight (137)Cs. The concentration of cesium in N. commune tended to be high in areas where soil radioactivity was high. A cultivation experiment confirmed that N. commune absorbed radioactive cesium from polluted soil. These data demonstrated that radiological absorption using N. commune might be suitable for decontaminating polluted soil.

  14. Release procedures and disposal of radioactive residual substances at the Medical University Hanover (MHH)

    International Nuclear Information System (INIS)

    Scheller, F.; Behrendt, R.; Harke, H.

    2005-01-01

    The disposal of all radioactive residual packages of the MHH is regulated by the German radiation protection ordinance from 26 th July 2001; shown in appendix III, table 1, column 5: unrestricted release of solid materials and liquids. All radioactive waste packages are collected and handled by the central MHH department for radiation protection. They are sorted for type, nuclide and specific radioactivity. A few packages can directly be released as conventional waste after performing incoming measurements showing very low activity concentrations. Longer living radionuclides with specific activities above the release limits have to be delivered to the national waste disposal. For direct measurements of gamma-emitting radionuclides we use two in-situ-measuring units (ISOCS, Canberra) and a special release unit with 9 plastic scintillators in a fixed geometry (FR-9 PVT, MED Medizintechnik). Fluid beta-emitting radionuclides are measured by taking a fraction and using liquid scintillation counting (LSC). Solid beta-emitting radionuclides activity are calculated. (orig.)

  15. Summary of accidental releases of radioactivity detected off the Nevada Test Site, 1963--1986

    International Nuclear Information System (INIS)

    Patzer, R.G.; Phillips, W.G.; Grossman, R.F.; Black, S.C.; Costa, C.F.

    1988-08-01

    Of the more than 450 underground nuclear explosives tests conducted at the Nevada Test Site from August 1963 (signing of the Limited Test Ban Treaty) through the end of 1986, only 23 accidentally released radioactivity that was detectable beyond the boundary of the NTS. Of these 23, 4 were detectable off the NTS only by aircraft while the remainder were detectable by ground monitoring instruments. Since the Baneberry venting of December 1970, only two tests released radioactivity that was detectable off the NTS, and this was a seepage of radioactive noble gases. None of these releases from underground tests designed for complete containment caused exposure of the population living in the area that exceeded standards recommended by national and international radiation protection agencies. This report summarizes the releases from each of the tests, describes the monitoring that was conducted, and lists the location of the maximum exposure

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

    International Nuclear Information System (INIS)

    Hebert, Jean.

    1978-01-01

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

  17. Ignalina RBMK-1500 building capability in retaining radioactive releases

    International Nuclear Information System (INIS)

    Nilsson, Lars; Johansson, K.

    1993-01-01

    The Ignalina reactor building structures are capable of retaining substantial fractions of radioactive emissions from the fuel core, in those accident sequences where pressurization failure of structures can be averted by pressure relief arrangements. In stage 1 of the IBBA project it was demonstrated that enhanced retention of radioactive fission products within the plant can be achieved if natural convection is facilitated in the upper building compartments. In this report of stage 2 is discussed for which accident sequences the introduction of natural convection in combination with the existing forced convection ventilation and the accident localization system can improve the total safety of Ignalina 1-2. The purpose of this stage is to provide a basis for further review and more detailed studies of the natural convection concept, its benefits and disadvantages, and of the feasability to introduce the concept in existing plants

  18. Influence of target thickness on the release of radioactive atoms

    Energy Technology Data Exchange (ETDEWEB)

    Guillot, Julien, E-mail: guillotjulien@ipno.in2p3.fr [Institut de Physique Nucléaire CNRS/IN2P3 UMR 8608 – Université Paris Sud – Université Paris Saclay, F-91406 Orsay Cedex (France); Roussière, Brigitte [Institut de Physique Nucléaire CNRS/IN2P3 UMR 8608 – Université Paris Sud – Université Paris Saclay, F-91406 Orsay Cedex (France); Tusseau-Nenez, Sandrine [Physique de la Matière Condensée Ecole Polytechnique/CNRS UMR 7643 – Université Paris Saclay, F-91128 Palaiseau Cedex (France); Barré-Boscher, Nicole; Borg, Elie; Martin, Julien [Institut de Physique Nucléaire CNRS/IN2P3 UMR 8608 – Université Paris Sud – Université Paris Saclay, F-91406 Orsay Cedex (France)

    2017-03-01

    Nowadays, intense exotic beams are needed in order to study nuclei with very short half-life. To increase the release efficiency of the fission products, all the target characteristics involved must be improved (e.g. chemical composition, dimensions, physicochemical properties such as grain size, porosity, density…). In this article, we study the impact of the target thickness. Released fractions measured from graphite and uranium carbide pellets are presented as well as Monte-Carlo simulations of the Brownian motion.

  19. Releases of radioactivity at the Savannah River Plant, 1954--1975

    International Nuclear Information System (INIS)

    Ashley, C.; Zeigler, C.C.

    1976-07-01

    This report contains summaries of releases of radioactivity to the environs from the Savannah River Plant for each year since plant startup (1954-1975). It also contains monthly summaries of 1975 releases from major emission sources (Separations and Reactor Areas). Releases for the years 1954 through 1959 are reassessed and assigned release values for long-lived specific radionuclides. These long-lived radionuclides (half lives greater than one year) are the only radionuclides included for the years 1954 through 1970. Beginning in 1971 all detectable radionuclides are included. The tabulated data, now compiled by computer, will be updated annually. All measured migration of radioactivity from the F- and H-Area seepage basin systems to Four Mile Creek, and from the K-Area containment basin to Pen Branch is listed in the release summaries and will be updated annually

  20. Models and methods to evaluate consequences of the release of airborne radioactivity from NNPs

    International Nuclear Information System (INIS)

    Anh, T.H.

    1989-01-01

    To examine the radioactive contamination and possible consequences of a nuclear power plant on living organisms during its operation periodes, the computer programmes were elaborated for assessing its fluences on the environment. The authors have resolved the following problems: i) Calculation of fission product inventories in the reactor core; ii) Calculation of the atmospheric dispersion of the released radionuclides under the meteorological conditions as well as the deposition of the radioactive substances on the soil; iii) Calculation of the irradiation doses

  1. Release of radioactive fission products from BN-600 reactor untight fuel elements

    International Nuclear Information System (INIS)

    Osipov, S.L.; Tsikunov, A.G.; Lisitsin, E.C.

    1996-01-01

    The experimental data on the release of radioactive fission products from BN-600 reactor untight fuel elements are given in the report. Various groups of radionuclides: inert gases Xe, Kr, volatile Cs, J, non-volatile Nb, and La are considered. The results of calculation-experimental study of transfer and distribution of radionuclides in the reactor primary circuit, gas system and sodium coolant are considered. It is shown that some complex radioactivity transfer processes can be described by simple mathematical models. (author)

  2. Release mechanisms from shallow engineered trenches used as repositories for radioactive wastes

    International Nuclear Information System (INIS)

    Locke, J.; Wood, E.

    1987-05-01

    This report has been written for the Department of the Environment as part of their radioactive waste management research programme. The aim has been to identify release mechanisms of radioactivity from fully engineered trenches of the LAND 2 type and, to identify the data needed for their assessment. No direct experimental work has been involved. The report starts with a brief background to UK strategy and outlines a basic disposal system. It gives reviews of existing experience of low level radioactive waste disposal from LAND 1 trenches and of UK experience of toxic waste disposal to provide a practical basis for the next section which covers the implications of identified release mechanisms on the design requirements for an engineered trench. From these design requirements and their interaction with potential site conditions (both saturated and unsaturated zone sites are considered) an assessment of radionuclide release mechanism is made. (author)

  3. Massive radioactive releases have a great impact on the accident costs

    International Nuclear Information System (INIS)

    Pascucci-Cahen, L.; Momal, P.

    2013-01-01

    This article investigates the costs of the consequences of a nuclear accident. The importance of the costs is very dependant on the amount of radioactivity released in the environment during the accident. 2 severe accidents are considered, each accident involves the fusion of the core but the first is characterized by a limited amount of radioactivity released in the atmosphere while the second involves massive radioactive releases. The list of consequences is as comprehensive as possible: site decontamination and dismantlement, land decontamination, sanitary impacts, population displacement, agricultural and economical losses, impact on tourism, impact on the production of electricity...In the first case the total cost reaches 120 billion euros which is still manageable at the scale of a country whereas in the second case the bill reaches 430 billion euros which is unbearable for a country. The very slight probability of such events does not compensate for their catastrophic potentials. (A.C.)

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

    International Nuclear Information System (INIS)

    Tolksdorf, P.; Buehling, A.

    1981-01-01

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

  5. Influence of plume rise on the consequences of radioactive material releases

    International Nuclear Information System (INIS)

    Russo, A.J.; Wayland, J.R.; Ritchie, L.T.

    1977-01-01

    Estimates of health consequences resulting from a postulated nuclear reactor accident can be strongly dependent on the buoyant rise of the plume of released radioactive material. The sensitivity of the consequences of a postulated accident to two different plume rise models has been investigated. The results of these investigations are the subject of this report. One of the models includes the effects of emission angle, momentum, and radioactive heating of the released material. The difference in the consequence estimates from the two models can exceed an order of magnitude under some conditions, but in general the results are similar

  6. Modelling of motorway tunnels scenario for utilization of conditionally released radioactive materials

    International Nuclear Information System (INIS)

    Hrncir, Tomas; Panik, Michal; Necas, Vladimir

    2011-01-01

    Considerable amount of solid radioactive waste with radioactivity slightly above the limits for unconditional release is generated during the decommissioning of the nuclear installations. Conditional release deals with precisely this type of materials with activity slightly above limits in order to save considerable financial resources, which would be otherwise spend on treatment, conditioning and disposal of these materials at appropriate repository. The basic principles of conditional release as well as possibilities of reusing of the conditionally released materials are described. One of these possibilities of the reusing was chosen and application proposal of conditional release of metal waste - steel reinforcement in the concrete, which could be used for construction of motorway tunnels, was created. The computer code Visiplan 4.0 3D ALARA planning tool software was used for the calculation of effective individual dose for personnel constructing the tunnel and for critical group related to scenario. Particular models for individual scenarios of conditional release have been developed within the scope of this software code. The aim of the paper is to determine a level of the radioactivity of conditional released materials to avoid over exceeding the value of annual individual effective dose 10μSv/year established by international recommendations. (author)

  7. Digital processing method for monitoring the radioactivity of stack releases

    International Nuclear Information System (INIS)

    Vialettes, H.; Leblanc, P.; Perotin, J.P.; Lazou, J.P.

    1978-01-01

    The digital processing method proposed is adapted for data supplied by a fixed-filter detector normally used for analogue processing (integrator system). On the basis of the raw data (pulses) from the detector, the technique makes it possible to determine the rate of activity released whereas analogue processing gives only the released activity. Furthermore, the method can be used to develop alarm systems on the basis of a possible exposure rate at the point of fall-out, and by including in the program a coefficient which allows for atmospheric diffusion conditions at any given time one can improve the accuracy of the results. In order to test the digital processing method and demonstrate its advantages over analogue processing, various atmospheric contamination situations were simulated in a glove-box and analysed simultaneously, using both systems, from the pulses transmitted by the same sampling and fixed-filter detection unit. The experimental results confirm the advantages foreseen in the theoretical research. (author)

  8. Evaluation and surveillance of radioactive releases of nuclear installations

    International Nuclear Information System (INIS)

    Hartmann, Ph.

    2002-01-01

    The two days organised by the section Environment of the SFRP have to objective to connect experts in radiation protection in order to debate around the following questions: the actual evaluations modes of releases impacts from nuclear installations, the organisation of the surveillance, to favour the implication of local actors in the evaluation and surveillance around nuclear facilities, the evolutions to envisage. (N.C.)

  9. Radioactive materials released from nuclear power plants. Annual report, 1982. Volume 3

    International Nuclear Information System (INIS)

    Tichler, J.; Norden, K.

    1986-02-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1982 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1982 release data are summarized in tabular form. Data covering specific radionuclides are summarized

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

    International Nuclear Information System (INIS)

    Chen Xiaoqiu

    2009-01-01

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

  11. Evaluation and mitigation of accidental releases of radioactivity

    International Nuclear Information System (INIS)

    Bruessermann, K.

    1982-12-01

    One result of the workshop was, that even in the case of severe accident sequences in modern nuclear power plants (other facilities were not discussed), there will be enough time to take active measures in order to lower the emissions and to diminish the consequences inside and outside of the plant. On the whole, new evidence from Harrisburg show that previously estimated accidental emissions, especially of radiologically relevant nuclides, have been rather conservative and that much lower emissions are possible, if the above measures are considered. Under accident conditions, models to predict radiation exposure must be applied under the event of a short-term release. (orig./DG) [de

  12. Shroud cutting techniques and collection systems for secondary radioactivity release

    International Nuclear Information System (INIS)

    Yokoi, H.; Watanabe, A.; Uetake, N.; Shimura, T.; Omote, T.; Adachi, H.; Murakami, S.; Kobayashi, H.; Gotoh, M.

    2001-01-01

    Replacement of in-core shroud has been conducted as part of the preventive maintenance program in Tsuruga-1. The EDM (electric discharged machining) and plasma cutting methods were applied to in-core shroud cutting and secondary cutting in the DSP (dryer/separator pool), respectively. The cutting systems were improved in order to decrease radioactive secondary products. 1) Fundamental EDM cutting tests: fundamental EDM cutting tests were carried out in order to study secondary products. It could be presumed that volatile Co-carbonyl compound was generated by using a carbon electrode. The Ag/W electrode was effective as EDM electrode for in-core shroud cutting to prevent generation of Co-carbonyl compound and to decrease the total amount of secondary products. 2) In-core shroud cutting in RPV (reactor pressure vessel): EDM cutting system with the Ag/W electrode and collection system could keep a good environment during in-core shroud cutting in Tsuruga-1. Activity concentration was lower value than limitation of mask charge level, 4E-6 Bq/cm 3 , even near the water surface. 3) Secondary plasma cutting in DSP: the secondary cutting work was successful in the point of reduction of working period and radiation exposure. The amount of radiation exposure was reduced to 60% of the planned value, because of adequate decontamination of the working environment and reduction of number of torch maintenance tasks by improvements of the underwater cutting device

  13. Radioactive releases from a thorium-contaminated site in Wayne, New Jersey

    International Nuclear Information System (INIS)

    Wang, J.; Yang, J.; Merry-Libby, P.

    1985-01-01

    Various residues and wastes from the production of thorium and rare earths from monazite ore are buried on a hillside in Wayne, New Jersey. In addition, contaminated materials (primarily soils) from nearby vicinity properties are being consolidated onto the Wayne site. The US Department of Energy plans to stabilize all the contaminated materials on an interim basis (20 years) until funding is available to remove them to another location. In order to evaluate the effectiveness of interim stabilization measures, pre-remedial action radioactive releases are compared to estimated releases under a reference stabilization option (one meter of soil cover). Two potential pathways are examined: (1) airborne radioactive gases (thoron and radon) and particulates, and (2) seepage into the near-surface groundwater. The relative reduction of releases into the air and groundwater for the reference stabilization option is analyzed using mathematical models for radioactive gas fluxes and atmospheric dispersion as well as groundwater transport and dispersion. The consequent health implications for nearby individuals and the general population are also estimated. Health effects due to radioactive releases are estimated to be insignificant

  14. 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

  15. Hazard of radioactive releases resulted from coal burning; Opasnost` vysvobozhdeniya radioaktivnykh produktov pri szhiganii uglya

    Energy Technology Data Exchange (ETDEWEB)

    Gabbard, V

    1995-09-01

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

  16. Site-sensitive hazards of potential airborne radioactive release from sources on the Kola peninsula

    International Nuclear Information System (INIS)

    Bergman, R.; Thaning, L.; Baklanov, A.

    1998-02-01

    In this work we focus on cases of airborne releases from some of the sources on the Kola Peninsula - primarily nuclear reactors on submarines and the Kola Nuclear Power Plant (KNPP). The purpose of our study is to illustrate, and discuss some features - dependent on site and release characteristics - of the deposition patterns resulting from assumed unit radioactive releases to the atmosphere from a location at a fjord and from the KNPP in Polyarnye Zori. Using meteorological data for one real weather situation, the analysis is based on simulating the transport in air of assumed radioactive releases and estimating the deposition pattern on local, meso- and regional scales. By allowing unit releases to occur simultaneously from the site at the fjord and from the power plant (and with the same release profile in time) comparisons are made of differences in deposition patterns in and outside the Kola region. In this case study a set of assumed release heights, durations of the release, and particle size distributions are applied to indicate the dependence for the resulting deposition pattern on these parameters

  17. Release pathways for deep seabed disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Anderson, D.R.; Bishop, W.P.; Bowen, V.T.; Brannen, J.P.; Caudle, W.N.; Detry, R.J.; Ewart, T.E.; Hayes, D.E.; Heath, G.R.; Hessler, R.R.; Hollister, C.D.; Keil, K.; McGowan, J.A.; Rohde, R.W.; Schimmel, W.P.; Schuster, C.L.; Silva, A.J.; Smyrl, W.H.; Taft, B.A.; Talbert, D.M.

    1975-01-01

    The concept of disposal of high-level solidified and encapsulated radioactive wastes into the deep sea floor has recently been discussed. Such a scheme has conceptual advantages in that the areas of the mid-plate/mid-gyre regions of the oceans are relatively unproductive biologically and relatively devoid of cataclysmic events, and natural processes there are generally quite slow. Given a lack of singular events, a set of barriers against the dispersion of the radioisotopes may be defined. The inverse of these barriers is the set of mechanisms by which the isotopes are transported from the burial site through the barriers to parts of the ocean of immediate significance to mankind. These include: corrosion of the cask; leaching of the waste material; upward transport of the isotopes with the upward moving pore water (mediated by ion-exchange processes); biological transport through bioturbition in the upper sediment layers and lowest water layer; the slow throughput currents of the deep basins; advection and diffusion through the water column; thermally driven transport through the sediments or the water column; biological transport of incorporated isotopes across the seabed or upward through the water column. In principle, the rates of all these processes are measurable or capable of being estimated. Such estimates are given on the basis of present knowledge of the processes in the deep basins. A methodology is discussed for the analytical treatment of the set of processes to give the amount of the isotopes reaching some part of the environment (e.g., and oceanic regime of immediate significance to man) as a function of time. The authors conclude that disposal in the deep seabed is conceptually attractive because of the stability and predictablity of the environment, but that it is not possible to give a firm estimate of the safety of such a scheme from the current knowledge of the mid-plate/mid-gyre regions. (author)

  18. Portable Filtered Air Suction System for Released Radioactive Gases Prevention under a Severe Accident of NPPs

    International Nuclear Information System (INIS)

    Gu, Beom W.; Choi, Su Y.; Rim, Chun T.

    2013-01-01

    In this paper, the portable filtered air suction system (PoFASS) for released radioactive gases prevention under a severe accident of NPP is proposed. This technology can prevent the release of the radioactive gases to the atmosphere and it can be more economical than FVCS because PoFASS can cover many NPPs with its high mobility. The conceptual design of PoFASS, which has the highest cost effectiveness and robustness to the environment condition such as wind velocity and precipitation, is suggested and the related previous research is introduced in this paper. The portable filtered air suction system (PoFASS) for released radioactive gases prevention can play a key role to mitigate the severe accident of NPP with its high cost effectiveness and robustness to the environment conditions. As further works, the detail design of PoFASS to fabricate a prototype for a demonstration will be proceeded. When released radioactive gases from the broken containment building in the severe accident of nuclear power plants (NPPs) such as the Chernobyl and Fukushima accidents occur, there are no ways to prevent the released radioactive gases spreading in the air. In order to solve this problem, several European NPPs have adopted the filtered vented containment system (FVCS), which can avoid the containment failure through a pressure relief capability to protect the containment building against overpressure. However, the installation cost of FVCS for a NPP is more than $10 million and this system has not been widely welcomed by NPP operating companies due to its high cost

  19. International comparison on radioactive releases of PWR between 1975 and 1988

    International Nuclear Information System (INIS)

    Benedittini, M.; Tabare, M.

    1990-02-01

    This report presents the main results of a comparison on radioactive releases from 135 PWRs in the following countries: Belgium, Federal Republic of Germany, Finland, France, Japan, Sweden, Switzerland and the United States. For liquid releases, distinctions have been undertaken between tritium and no tritium activities and for gaseous releases between noble gases and halogens-aerosols. Data has been collected from literature published or by contacting utilities administrative staff or authorities in order to constitute a data base. As regards this comparison however, reactors, the commercial operation of which started prior to July 1974, have been excluded [fr

  20. Radioactivity release vs probability for a steam generator tube rupture accident

    International Nuclear Information System (INIS)

    Buslik, A.J.; Hall, R.E.

    1978-01-01

    A calculation of the probability of obtaining various radioactivity releases from a steam generator tube rupture (SGTR) is presented. The only radioactive isotopes considered are Iodine-131 and Xe-133. The particular accident path considered consists of a double-ended guillotine SGTR followed by loss of offsite power (LOSP). If there is no loss of offsite power, and no system fault other than the SGTR, it is judged that the consequences will be minimal, since the amount of iodine released through the condenser air ejector is expected to be quite small; this is a consequence of the fact that the concentration of iodine in the vapor released from the condenser air ejector is very small compared to that dissolved in the condensate water. In addition, in some plants the condenser air ejector flow is automatically diverted to containment or a high-activity alarm. The analysis presented here is for a typical Westinghouse PWR such as described in RESAR-3S

  1. Sensitivity Analysis of Dousing Spray Trip on Radioactive Release in Pressure Tube Rupture Accident with Both End Fitting Failures

    Energy Technology Data Exchange (ETDEWEB)

    Jang, M. S.; Kang, H. S; Kim, S. R. [NESS, Daejeon (Korea, Republic of)

    2015-10-15

    We analyzed the sensitivity analysis of dousing spray trip conditions on radioactive release. In terms of conservativeness, the set 1 trip would be more appropriate in RR analysis than set 2 trip, which is the general condition of RR analysis. Radioactive releases from the containment building is related to containment air pressure, which increases by the coolant discharge from loss of coolant accident and the actuation conditions of dousing spray and so on. In LOCA analysis, the dousing spray trip conditions are set for the analysis objectives; for peak pressure (PP), for pressure signal (PS), for radioactive release (RR) and etc. In RR analysis, we would determine the dousing spray trip condition to increase radioactive release to the public for conservatism. Therefore, we carried out the sensitivity analysis of dousing spray trip condition on radioactive release from containment building using GOTHIC and SMART program for CANDU.

  2. Experimentation of nuclear weapons, releases and storages of radioactive wastes in the Kara sea and in New Zemble

    International Nuclear Information System (INIS)

    Charmasson, S.

    1996-01-01

    132 nuclear weapons were tested from 1955 to 1990 in New Zemble. From 1959 to 1993, low level liquid radioactive wastes, low and medium level solid radioactive wastes, reactor core and fuel of submarine and nuclear propelled ships were released in the Kara and the Barentz seas. For these two seas, a recapitulation of the different radioactive sources and the found level of radioactivity of the marine environment are presented. (A.B.). 22 refs. 4 figs., 6 tabs

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  5. Methodology for assessing the radiological consequences of radioactive releases from the BPX Facility at PPPL

    International Nuclear Information System (INIS)

    McKenzie-Carter, M.A.; Lyon, R.E.; Rope, S.K.

    1991-04-01

    This report contains information to support the Environmental Assessment for the Burning Plasma Experiment (BPX) Project proposed for the Princeton Plasma Physics Laboratory (PPPL). The assumptions and methodology used to assess the impact to members of the public from operational and accidental releases of radioactive material from the proposed BPX during the operational period of the project are described. A description of the tracer release tests conducted at PPPL by NOAA is included; dispersion values from these tests are used in the dose calculations. Radiological releases, doses, and resulting health risks are calculated and summarized. The computer code AIRDOS- EPA, which is part of the computer code system CAP-88, is used to calculate the individual and population doses for routine releases; FUSCRAC3 is used to calculate doses resulting from off-normal releases where direct application of the NOAA tracer test data is not practical. Where applicable, doses are compared to regulatory limits and guideline values. 48 refs., 16 tabs

  6. Release of Radioactive Scrap Metal/Scrap Metal (RSM/SM) at Nevada Test Site (NTS)

    International Nuclear Information System (INIS)

    1993-01-01

    Reynolds Electrical and Engineering Company, Inc. (REECo) is the prime contractor to the US Department of Energy (DOE) in providing service and support for NTS operations. Mercury Base Camp is the main control point for the many forward areas at NTS, which covers 1,350 square miles. The forward areas are where above-ground and underground nuclear tests have been performed over the last 41 years. No metal (or other material) is returned to Mercury without first being tested for radioactivity. No radioactive metals are allowed to reenter Mercury from the forward areas, other than testing equipment. RAMATROL is the monitor check point. They check material in various ways, including swipe tests, and have a large assortment of equipment for testing. Scrap metal is also checked to address Resource Conservation and Recovery Act concerns. After addressing these issues, the scrap metals are categorized. Federal Property Management Regulations (FPMR) are followed by REECo. The nonradioactive scrap material is sold through the GSA on a scheduled basis. Radioactive scrap metal are presently held in forward areas where they were used. REECo has gained approval of their Nevada Test Site Defense Waste Acceptance Criteria, Certification, and Transfer Requirements, NVO-325 application, which will allow disposal on site, when RSM is declared a waste. The guideline that REECo uses for release limits is DOE Order 5480.11, Radiation Protection for Occupational Works, Attachment 2, Surface Radioactivity Guides, of this order, give release limits for radioactive materials. However, the removal of radioactive materials from NTS require approval by DOE Nevada Operations Office (DOE/NV) on a case-by-case basis. Requirements to consider before removal are found in DOE Order 5820.2A, Radioactive Waste Management

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

    International Nuclear Information System (INIS)

    Cook, J.R.

    1981-08-01

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

  8. Freedom: a transient fission-product release model for radioactive and stable species

    International Nuclear Information System (INIS)

    Macdonald, L.D.; Lewis, B.J.; Iglesias, F.C.

    1989-05-01

    A microstructure-dependent fission-gas release and swelling model (FREEDOM) has been developed for UO 2 fuel. The model describes the transient release behaviour for both the radioactive and stable fission-product species. The model can be applied over the full range of operating conditions, as well as for accident conditions that result in high fuel temperatures. The model accounts for lattice diffusion and grain-boundary sweeping of fusion products to the grain boundaries, where the fission gases accumulate in grain-face bubbles as a result of vacancy diffusion. Release of fission-gas to the free void of the fuel element occurs through the interlinkage of bubbles and cracks on the grain boundaries. This treatment also accounts for radioactive chain decay and neutron-induced transmutation effects. These phenomena are described by mass balance equations which are numerically solved using a moving-boundary, finite-element method with mesh refinement. The effects of grain-face bubbles on fuel swelling and fuel thermal conductivity are included in the ELESIM fuel performance code. FREEDOM has an accuracy of better than 1% when assessed against an analytic solution for diffusional release. The code is being evaluated against a fuel performance database for stable gas release, and against sweep-gas and in-cell fission-product release experiments at Chalk River for active species

  9. Simulated atmospheric disperison of radioactive material released in an urban area

    International Nuclear Information System (INIS)

    Akins, R.E.; Church, H.W.; Tierney, M.S.

    1977-01-01

    A combination of Gaussian plume and particle-in-cell techniques is used to simulate the atmospheric transport and dispersion of a puff release of radioactive material. The release is caused by an accident that is assumed to occur during the shipment of the radioactive material through central New York City. The simulation provides estimates of volumetric and surface concentrations of the dispersed material that are used to predict radiation doses incurred by the City's population in the event of an accidental release. In the simulation, the release point is arbitrary and the material is assumed to be either a gas or fine particles. The Gaussian plume model follows cloud concentrations from the release time until times when transport over distances up to 500 m has been achieved. The released cloud may stabilize at street level or above the mean buildings height; at a street intersection or in the middle of the block. The possibility of the formation of multiple clouds, owing to circumstances of wind flow direction and street geometry, is allowed

  10. Gaseous release of radioactive iodine from decaying plants. I. Release following foliar and root uptake

    International Nuclear Information System (INIS)

    Saas, Arsene; Grauby, Andre

    1975-12-01

    Iodine uptake by plants is a significant link in the contamination of the food chain. Long half-live iodine was studied considering foliar and root uptake, loss by rain scavenging, residue decay or outgassing in order to assess two aspects of the problem: the importance of outgassing and the effect of the route of transfer on iodine losses. It appeared that iodine release was a function of the vegetal type, there were differences according to the pattern of absorption (via leaf or root) and the processes of iodine release were usually related to biochemical mechanisms [fr

  11. Air modelling as an alternative to sampling for low-level radioactive airborne releases

    International Nuclear Information System (INIS)

    Morgenstern, M.Y.; Hueske, K.

    1995-01-01

    This paper describes our efforts to assess the effect of airborne releases at one DOE laboratory using air modelling based on historical data. Among the facilities affected by these developments is Los Alamos National Laboratory (LANL) in New Mexico. RCRA, as amended by the Hazardous and Solid Waste Amendments (HSWA) in 1984, requires all facilities which involve the treatment, storage, and disposal of hazardous waste obtain a RCRA/HSWA waste facility permit. LANL complied with CEARP by initiating a process of identifying potential release sites associated with LANL operations prior to filing a RCRA/HSWA permit application. In the process of preparing the RCRA/HSWA waste facility permit application to the U.S. Environmental Protection Agency (EPA), a total of 603 Solid Waste Management Units (SWMUs) were identified as part of the requirements of the HSWA Module VIH permit requirements. The HSWA Module VIII permit requires LANL to determine whether there have been any releases of hazardous waste or hazardous constituents from SWMUs at the facility dating from the 1940's by performing a RCRA Facility Investigation to address known or suspected releases from specified SWMUs to affected media (i.e. soil, groundwater, surface water, and air). Among the most troublesome of the potential releases sites are those associated with airborne radioactive releases. In order to assess health risks associated with radioactive contaminants in a manner consistent with exposure standards currently in place, the DOE and LANL have established Screening Action Levels (SALs) for radioactive soil contamination. The SALs for each radionuclide in soil are derived from calculations based on a residential scenario in which individuals are exposed to contaminated soil via inhalation and ingestion as well as external exposure to gamma emitters in the soil. The applicable SALs are shown

  12. New approaches to deriving limits of the release of radioactive material into the environment

    International Nuclear Information System (INIS)

    Lindell, B.

    1977-01-01

    During the last few years, new principles have been developed for the limitation of the release of radioactive material into the environment. It is no longer considered appropriate to base the limitation on limits for the concentrations of the various radionuclides in air and water effluents. Such limits would not prevent large amounts of radioactive material from reaching the environment should effluent rates be high. A common practice has been to identify critical radionuclides and critical pathways and to base the limitation on authorized dose limits for local ''critical groups''. If this were the only limitation, however, larger releases could be permitted after installing either higher stacks or equipment to retain the more short-lived radionuclides for decay before release. Continued release at such limits would then lead to considerably higher exposure at a distance than if no such installation had been made. Accordingly there would be no immediate control of overlapping exposures from several sources, nor would the system guarantee control of the future situation. The new principles described in this paper take the future into account by limiting the annual dose commitments rather than the annual doses. They also offer means of controlling the global situation by limiting not only doses in critical groups but also global collective doses. Their objective is not only to ensure that individual dose limits will always be respected but also to meet the requirement that ''all doses be kept as low as reasonably achievable''. The new approach is based on the most recent recommendations by the ICRP and has been described in a report by an IAEA panel (Procedures for establishing limits for the release of radioactive material into the environment). It has been applied in the development of new Swedish release regulations, which illustrate some of the problems which arise in the practical application

  13. New approaches to deriving limits of the release of radioactive material into the environment

    International Nuclear Information System (INIS)

    Lindell, B.

    1977-01-01

    During the last few years, new principles have been developed for the limitation of the release of radioactive material into the environment. It is no longer considered appropriate to base the limitation on limits for the concentrations of the various radionuclides in air and water effluents. Such limits would not prevent large amounts of radioactive material from reaching the environment should effluent rates be high. A common practice has been to identify critical radionuclides and critical pathways and to base the limitation on authorized dose limits for local ''critical groups''. If this were the only limitation, however, larger releases could be permitted after installing either higher stacks or equipment to retain the more shortlived radionuclides for decay before release. Continued release at such limits would then lead to considerably higher exposure at a distance than if no such installation had been made. Accordingly there would be no immediate control of overlapping exposures from several sources, nor would the system guarantee control of the future situation. The new principles described in this paper take the future into account by limiting the annual dose commitments rather than the annual doses. They also offer means of controlling the global situation by limiting not only doses in critical groups but also global collective doses. Their objective is not only to ensure that individual dose limits will always be respected but also to meet the requirement that ''all doses be kept as low as reasonably achievable''. The new approach is based on the most recent recommendations by the ICRP and has been described in a report by an IAEA panel (Procedures for Establishing Limits for the Release of Radioactive Material into the Environment). It has been applied in the development of new Swedish release regulations, which illustrate some of the problems which arise in the practical application. (author)

  14. Radioactivity of French coast of the Channel due to the release of technectium 99 and iodine 129: modelisation and measurements

    International Nuclear Information System (INIS)

    Robeau, D.; Patti, F.; Charmasson, S.

    1988-01-01

    Radioactive releases of Iodine 129 are controlled by measurements of the radioactivity in the liquid effluents before it is released in to the sea from the outlet of the reprocessing plant of La Hague. The effects on the marine environment are examined by a radioactive survey of Technecium 99 and Iodine 129 in Fucus (common seaweed). This radioactivity is measured along the north coast of France from Roscoff in the west of Brittany to Wimereux close to the Belgian frontier. The theoretical study of dispersion of radionuclides in the Channel has permitted a simulation model of the transfer of pollutants and particularly Technecium 99 and Iodine 129 to be formulated. (author)

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  16. An update on radioactive release and exposures after the Fukushima Dai-ichi nuclear disaster.

    LENUS (Irish Health Repository)

    McLaughlin, P D

    2012-09-01

    On 11 March 2011, the Richter scale 0.9-magnitude Tokohu earthquake and tsunami struck the northeast coast of Japan, resulting in widespread injury and loss of life. Compounding this tragic loss of life, a series of equipment and structural failures at the Fukushima Dai-ichi nuclear power plant (FDNP) resulted in the release of many volatile radioisotopes into the atmosphere. In this update, we detail currently available evidence about the nature of immediate radioactive exposure to FDNP workers and the general population. We contrast the nature of the radioactive exposure at FDNP with that which occurred at the Chernobyl power plant 25 years previously. Prediction of the exact health effects related to the FDNP release is difficult at present and this disaster provides the scientific community with a challenge to help those involved and to continue research that will improve our understanding of the potential complications of radionuclide fallout.

  17. Fate of gaseous tritium and carbon-14 released from buried low-level radioactive waste

    International Nuclear Information System (INIS)

    Striegl, R.G.

    1988-01-01

    Microbial decomposition, chemical degradation, and volatilization of buried low-level radioactive waste results in the release of gases containing tritium ( 3 H) and carbon-14 ( 14 C) to the surrounding environment. Water vapor, carbon dioxide, and methane that contain 3 H or 14 C are primary products of microbial decomposition of the waste. Depending on the composition of the waste source, chemical degradation and volatilization of waste also may result in the production of a variety of radioactive gases and organic vapors. Movement of the gases in materials that surround waste trenches is affected by physical, geochemical, and biological mechanisms including sorption, gas-water-mineral reactions, isotopic dilution, microbial consumption, and bioaccumulation. These mechanisms either may transfer 3 H and 14 C to solids and infiltrating water or may result in the accumulation of the radionuclides in plant or animal tissue. Gaseous 3 H or 14 C that is not transferred to other forms is ultimately released to the atmosphere

  18. Simulation Studies of Diffusion-Release and Effusive-Flow of Short-Lived Radioactive Isotopes

    CERN Document Server

    Zhang, Yan; Kawai, Yoko

    2005-01-01

    Delay times associated with diffusion release from targets and effusive-flow transport of radioactive isotopes to ion sources are principal intensity limiters at ISOL-based radioactive ion beam facilities, and simulation studies with computer models are cost effective methods for designing targets and vapor transport systems with minimum delay times to avoid excessive decay losses of short lived ion species. A finite difference code, Diffuse II, was recently developed at the Oak Ridge National Laboratory to study diffusion-release of short-lived species from three principal target geometries. Simulation results are in close agreement with analytical solutions to Fick’s second equation. Complementary to the development of Diffuse II, the Monte-Carlo code, Effusion, was developed to address issues related to the design of fast vapor transport systems. Results, derived by using Effusion, are also found to closely agree with experimental measurements. In this presentation, the codes will be used in conc...

  19. Retention and subsequent release of radioactivity from the incineration of wastes containing microspheres

    International Nuclear Information System (INIS)

    Emery, R.J.; Watson, J.E. Jr.

    1990-01-01

    Incineration is the preferred method for disposing of animal carcasses containing radioactive microspheres at the authors University. Routine surveys of ash from successive nonradioactive burns revealed significant contamination from previously incinerated microspheres. Past studies on microsphere incineration quantified the amount of activity retained in ash, but did not address any subsequent releases. This topic was not considered in earlier studies because, in most cases, the carcasses were placed in some type of container to facilitate recovery of ash, preventing contamination of the incinerator refractory. In this study, five sets of controlled burns were performed to quantify the subsequent releases of the microsphere radioisotopes 141 Ce, 113 Sn, 102 Ru, 95 Nb, and 46 Sc. Each set consisted of three successive burns. The first burn of each set incinerated a non-radioactive carcass, the second burn, a radioactive carcass, and the third, a non-radioactive carcass. In all of the burns, the carcasses were placed directly on the incinerator refractory floor, which is the standard procedure during normal operations

  20. Review of calculational models and computer codes for environmental dose assessment of radioactive releases

    International Nuclear Information System (INIS)

    Strenge, D.L.; Watson, E.C.; Droppo, J.G.

    1976-06-01

    The development of technological bases for siting nuclear fuel cycle facilities requires calculational models and computer codes for the evaluation of risks and the assessment of environmental impact of radioactive effluents. A literature search and review of available computer programs revealed that no one program was capable of performing all of the great variety of calculations (i.e., external dose, internal dose, population dose, chronic release, accidental release, etc.). Available literature on existing computer programs has been reviewed and a description of each program reviewed is given

  1. Review of calculational models and computer codes for environmental dose assessment of radioactive releases

    Energy Technology Data Exchange (ETDEWEB)

    Strenge, D.L.; Watson, E.C.; Droppo, J.G.

    1976-06-01

    The development of technological bases for siting nuclear fuel cycle facilities requires calculational models and computer codes for the evaluation of risks and the assessment of environmental impact of radioactive effluents. A literature search and review of available computer programs revealed that no one program was capable of performing all of the great variety of calculations (i.e., external dose, internal dose, population dose, chronic release, accidental release, etc.). Available literature on existing computer programs has been reviewed and a description of each program reviewed is given.

  2. Assessment of the Potential Release of Radioactivity from Installations at AERE, Harwell. Implications for Emergency Planning

    Energy Technology Data Exchange (ETDEWEB)

    Flew, Elizabeth M.; Lister, B. A.J. [Atomic Energy Research Establishment, Harwell, Didcot, Berks. (United Kingdom)

    1969-10-15

    As part of a review of the site emergency organization at AERE, a realistic reappraisal has been made of the potential hazard to the establishment and district of all the buildings containing significant amounts of radioactive materials. To assess the amount of radioactive material which might be released under specified accident conditions, four factors have been applied to the total building stock: (a) the fraction of the stock involved, (b) the percentage conversion to an aerosol form, (c) release from primary containment and (d) release from the building. These potential release figures have been compared with ''site hazardous release'' figures for relevant radionuclides i.e., amounts which could give rise to exposure above defined reference levels. Those buildings with more than one tenth of the potential for causing; a site or district hazard have been designated ''risk buildings''. Such a quantitative assessment, although necessarily very approximate, has been of considerable value in determining the type and complexity of the central emergency organization required and in producing the right emphasis on exercises, training, liaison with outside bodies, etc. (author)

  3. 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

  4. Technical committee meeting on evaluation of radioactive materials release and sodium fires in fast reactors

    International Nuclear Information System (INIS)

    1996-01-01

    The objectives of the Technical Committee Meeting was to review the activities of research on radioactive materials release and sodium fires in fast reactors in each of the participating countries. It covered: out-of-pile experiments and analysis codes on source term; in-pile experiments on source term; core disruptive accidents; sodium leak experience in liquid metal fast reactors; evaluation of sodium fire; and aerosol behaviour

  5. Maxine: A spreadsheet for estimating dose from chronic atmospheric radioactive releases

    Energy Technology Data Exchange (ETDEWEB)

    Jannik, Tim [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Bell, Evaleigh [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, Kenneth [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-07-24

    MAXINE is an EXCEL© spreadsheet, which is used to estimate dose to individuals for routine and accidental atmospheric releases of radioactive materials. MAXINE does not contain an atmospheric dispersion model, but rather doses are estimated using air and ground concentrations as input. Minimal input is required to run the program and site specific parameters are used when possible. Complete code description, verification of models, and user’s manual have been included.

  6. Risk assessment based on current release standards for radioactive surface contamination

    International Nuclear Information System (INIS)

    Chen, S.Y.

    1993-09-01

    Standards for uncontrolled releases of radioactive surface contamination have been in existence in the United States for about two decades. Such standards have been issued by various agencies, including the US Department of Energy. This paper reviews the technical basis of published standards, identifies areas in need of revision, provides risk interpretations based on current technical knowledge and the regulatory environment, and offers suggestions for improvements

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

    International Nuclear Information System (INIS)

    Beninson, D.

    1978-01-01

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

  8. Technical committee meeting on evaluation of radioactive materials release and sodium fires in fast reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-01

    The objectives of the Technical Committee Meeting was to review the activities of research on radioactive materials release and sodium fires in fast reactors in each of the participating countries. It covered: out-of-pile experiments and analysis codes on source term; in-pile experiments on source term; core disruptive accidents; sodium leak experience in liquid metal fast reactors; evaluation of sodium fire; and aerosol behaviour.

  9. The minimization of radioactive releases to the sea from the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Sugiyama, T.; Yoshikawa, K.; Ishii, T.

    1996-01-01

    The Tokai Reprocessing Plant (TRP) started hot operation in September 1977. The total amount of about 790 tU of spent fuel, generated in Japan, has been successfully reprocessed as of December 1994. Low-level liquid wastes have been treated safely with the low-level waste treatment process. The design of TRP was based on foreign technology. In the early stage of designing, the radioactivity released to the sea was estimated at approximately 2.6 TBq/day (70 Ci/day) for beta activity (except for tritium). Later, PNC added an evaporator to the process to reduce the level down to 1/100, i.e. 9.6 TBq/year (260 Ci/year) or 2.6 x 10 -2 TBq/day (0.7 Ci/day). In addition, under the supervision of the government, PNC started R and D to further decrease the radioactivity released to the sea in terms of ALARA. Aiming at reducing the activity from 9.6 TBq/year (260 Ci/year) to 1/10 of that value (i.e. 26 Ci/year), the release reduction technology development facility was added. This facility was incorporated into the low-level waste treatment process in 1980, before starting the regular operation of TRP. Since the fuel reprocessing commenced, total radioactivity discharged to the sea has been 1.9 x 10 -2 TBq (0.51 Ci) for beta activity, as of December 1994. Before incorporating the release reduction technology development facility, the yearly level was 3.7 x 10 -3 - 7.4 x 10 -3 TBq (0.1 - 0.2 Ci). After incorporation of the facility, radioactivity released to the sea was greatly decreased to non-detection levels in recent years, in spite of increasing annual reprocessing amounts. Although serious equipment failures have occurred such as the acid recovery evaporator and the dissolvers, there was no influence on radioactivity released to the sea. (author)

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

    International Nuclear Information System (INIS)

    Mierzwa, Jose Carlos

    1996-01-01

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

  11. Regulatory analysis on criteria for the release of patients administered radioactive material

    International Nuclear Information System (INIS)

    Schneider, S.; McGuire, S.A.

    1994-05-01

    The Nuclear Regulatory Commission (NRC) has received two petitions to amend its regulations in 10 CFR Parts 20 and 35 as they apply to doses received by members of the public exposed to patients released from a hospital after they have been administered radioactive material. While the two petitions are not identical they both request that the NRC establish a dose limit of 5 millisieverts (0.5 rem) per year for individuals exposed to patients who have been administered radioactive materials. This Regulatory Analysis evaluates three alternatives. Alternative 1 is for the NRC to amend its patient release criteria in 10 CFR 35.75 to use the more stringent dose limit of 1 millisievert per year in 10 CFR 20.1301(a) for its patient release criteria. Alternative 2 is for the NRC to continue using the existing patient release criteria in 10 CFR 35.75 of 1,110 megabecquerels of activity or a dose rate at one meter from the patient of 0.05 millisievert per hour. Alternative 3 is for the NRC to amend the patient release criteria in 10 CFR 35.75 to specify a dose limit of 5 millisieverts for patient release. The evaluation indicates that Alternative 1 would cause a prohibitively large increase in the national health care cost from retaining patients in a hospital longer and would cause significant personal and psychological costs to patients and their families. The choice of Alternatives 2 or 3 would affect only thyroid cancer patients treated with iodine-131. For those patients, Alternative 3 would result in less hospitalization than Alternative 2. Alternative 3 has a potential decrease in national health care cost of $30,000,000 per year but would increase the potential collective dose from released therapy patients by about 2,700 person-rem per year, mainly to family members

  12. Regulatory analysis on criteria for the release of patients administered radioactive material

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, S.; McGuire, S.A. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Regulatory Applications; Behling, U.H.; Behling, K.; Goldin, D. [Cohen (S.) and Associates, Inc., McLean, VA (United States)

    1994-05-01

    The Nuclear Regulatory Commission (NRC) has received two petitions to amend its regulations in 10 CFR Parts 20 and 35 as they apply to doses received by members of the public exposed to patients released from a hospital after they have been administered radioactive material. While the two petitions are not identical they both request that the NRC establish a dose limit of 5 millisieverts (0.5 rem) per year for individuals exposed to patients who have been administered radioactive materials. This Regulatory Analysis evaluates three alternatives. Alternative 1 is for the NRC to amend its patient release criteria in 10 CFR 35.75 to use the more stringent dose limit of 1 millisievert per year in 10 CFR 20.1301(a) for its patient release criteria. Alternative 2 is for the NRC to continue using the existing patient release criteria in 10 CFR 35.75 of 1,110 megabecquerels of activity or a dose rate at one meter from the patient of 0.05 millisievert per hour. Alternative 3 is for the NRC to amend the patient release criteria in 10 CFR 35.75 to specify a dose limit of 5 millisieverts for patient release. The evaluation indicates that Alternative 1 would cause a prohibitively large increase in the national health care cost from retaining patients in a hospital longer and would cause significant personal and psychological costs to patients and their families. The choice of Alternatives 2 or 3 would affect only thyroid cancer patients treated with iodine-131. For those patients, Alternative 3 would result in less hospitalization than Alternative 2. Alternative 3 has a potential decrease in national health care cost of $30,000,000 per year but would increase the potential collective dose from released therapy patients by about 2,700 person-rem per year, mainly to family members.

  13. Release process for non-real property containing residual radioactive material

    International Nuclear Information System (INIS)

    Ranek, N.L.; Chen, S.Y.; Kamboj, S.; Hensley, J.; Burns, D.; Fleming, R.; Warren, S.; Wallo, A.

    1997-01-01

    It is DOE's objective to operate its facilities and to conduct its activities so that radiation exposures to members of the public are maintained within acceptable limits and exposures to residual radioactive materials are controlled. To accomplish this, DOE has adopted Order DOE 5400.51 'Radiation Protection of the Public and the Environment', and will be promulgating IO CR Part 834 to codify and clarify the requirements of DOE 5400.5. Under both DOE 5400.5 and 10 CR Part 834, radioactively contaminated DOE property is prohibited from release unless specific actions have been completed prior to the release. This paper outlines a ten-step process that, if followed, will assist DOE Operations and contractor personnel in ensuring that the required actions established by Order DOE 5400.5 and 10 CR Part 834 have been appropriately completed prior to the release for reuse or recycle of non-real property (e.g., office furniture, computers, hand tools, machinery, vehicles and scrap metal). Following the process will assist in ensuring that radiological doses to the public from the released materials will meet applicable regulatory standards and be as low as reasonably achievable (ALARA)

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

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  15. Comparison of the accident process, radioactivity release and ground contamination between Chernobyl and Fukushima-1

    International Nuclear Information System (INIS)

    Imanaka, Tetsuji; Hayashi, Gohei; Endo, Satoru

    2015-01-01

    In this report, we have reviewed the basic features of the accident processes and radioactivity releases that occurred in the Chernobyl accident (1986) and in the Fukushima-1 accident (2011). The Chernobyl accident was a power-surge accident that was caused by a failure of control of a fission chain reaction, which instantaneously destroyed the reactor and building, whereas the Fukushima-1 accident was a loss-of-coolant accident in which the reactor cores of three units were melted by decay heat after losing the electricity supply. Although the quantity of radioactive noble gases released from Fukushima-1 exceeded the amount released from Chernobyl, the size of land area severely contaminated by 137 Cesium ( 137 Cs) was 10 times smaller around Fukushima-1 compared with around Chernobyl. The differences in the accident process are reflected in the composition of the discharged radioactivity as well as in the composition of the ground contamination. Volatile radionuclides (such as 132 Te- 132 I, 131 I, 134 Cs and 137 Cs) contributed to the gamma-ray exposure from the ground contamination around Fukishima-1, whereas a greater variety of radionuclides contributed significantly around Chernobyl. When radioactivity deposition occurred, the radiation exposure rate near Chernobyl is estimated to have been 770 μGy h −1 per initial 137 Cs deposition of 1000 kBq m −2 , whereas it was 100 μGy h −1 around Fukushima-1. Estimates of the cumulative exposure for 30 years are 970 and 570 mGy per initial deposition of 1000 kBq m −2 for Chernobyl and Fukusima-1, respectively. Of these exposures, 49 and 98% were contributed by radiocesiums ( 134 Cs + 137 Cs) around Chernobyl and Fukushima-1, respectively

  16. 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)

  17. A model to assess exposure from releases of radioactivity into the seas of northern Europe

    International Nuclear Information System (INIS)

    Clark, M.J.; Webb, G.A.M.

    1981-01-01

    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. A local/regional interface is included whereby releases are assumed to first enter a local marine compartment before 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. In general, results of the regional model are expressed as collective intakes of activity from ingestion of marine seafoods. These quantities can be converted into collective doses per unit discharge, given a knowledge of local depletion factors and the dose per unit intake of radionuclides. Results for caesium-137 and plutonium-239 released into United Kingdom coastal waters are discussed. (author)

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

    International Nuclear Information System (INIS)

    1988-06-01

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

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

    International Nuclear Information System (INIS)

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

    1978-06-01

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

  20. Releases of radioactivity at the Savannah River Plant, 1954-1980

    Energy Technology Data Exchange (ETDEWEB)

    Ashley, C.; Zeigler, C. C.; Culp, P. A.

    1982-01-01

    This report contains summaries of releases of radioactivity to onsite seepage basins and to plant effluents for each year since plant startup (1954 through 1980). Releases for the years 1954 through 1959 were reassessed in 1974 and assigned release values for specific long-lived radionuclides. These long-lived radionuclides (half-lives greater than 1 year) are the only radionuclides included for the years 1954 through 1970. Since 1970 all detectable radionuclides have been included. Measured migration o radionuclides from F-, H-, and K-Area seepage basins and desorption of /sup 137/Cs from the Four Mile Creek stream bed are included in Summary B of this report. Summaries of monthly releases for 1979 and 1980 and total SRP releases by radionuclide in three categories: liquid to seepage basins, liquid to streams, and atmospheric are also included. Monthly releases for 1979 are included because the 1979 issue of this report was not published. All 1979 data are included in this report.

  1. Regulatory analysis on criteria for the release of patients administered radioactive material. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, S.; McGuire, S.A.

    1997-02-01

    This regulatory analysis was developed to respond to three petitions for rulemaking to amend 10 CFR parts 20 and 35 regarding release of patients administered radioactive material. The petitions requested revision of these regulations to remove the ambiguity that existed between the 1-millisievert (0.1-rem) total effective dose equivalent (TEDE) public dose limit in Part 20, adopted in 1991, and the activity-based release limit in 10 CFR 35.75 that, in some instances, would permit release of individuals in excess of the current public dose limit. Three alternatives for resolution of the petitions were evaluated. Under Alternative 1, NRC would amend its patient release criteria in 10 CFR 35.75 to match the annual public dose limit in Part 20 of 1 millisievert (0.1 rem) TEDE. Alternative 2 would maintain the status quo of using the activity-based release criteria currently found in 10 CFR 35.75. Under Alternative 3, the NRC would revise the release criteria in 10 CFR 35.75 to specify a dose limit of 5 millisieverts (0.5 rem) TEDE.

  2. Regulatory analysis on criteria for the release of patients administered radioactive material. Final report

    International Nuclear Information System (INIS)

    Schneider, S.; McGuire, S.A.

    1997-02-01

    This regulatory analysis was developed to respond to three petitions for rulemaking to amend 10 CFR parts 20 and 35 regarding release of patients administered radioactive material. The petitions requested revision of these regulations to remove the ambiguity that existed between the 1-millisievert (0.1-rem) total effective dose equivalent (TEDE) public dose limit in Part 20, adopted in 1991, and the activity-based release limit in 10 CFR 35.75 that, in some instances, would permit release of individuals in excess of the current public dose limit. Three alternatives for resolution of the petitions were evaluated. Under Alternative 1, NRC would amend its patient release criteria in 10 CFR 35.75 to match the annual public dose limit in Part 20 of 1 millisievert (0.1 rem) TEDE. Alternative 2 would maintain the status quo of using the activity-based release criteria currently found in 10 CFR 35.75. Under Alternative 3, the NRC would revise the release criteria in 10 CFR 35.75 to specify a dose limit of 5 millisieverts (0.5 rem) TEDE

  3. 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)

  4. Methodology for calculating radiation doses from radioactivity released to the environment

    International Nuclear Information System (INIS)

    Killough, G.G.; McKay, L.R.

    1976-03-01

    This document represents a compilation of the principal environmental transport and dosimetry models developed, adapted, and implemented by the Radiological Analyses and Applications Group of the Environmental Sciences Division of the Oak Ridge National Laboratory. The transport of released radioactivity through the natural environment is discussed in four sections: atmospheric dispersion, resuspension of material by wind action, terrestrial transport, and movement of material in underground water seepage. The discussion of dose to man and biota is divided into internal and external exposure sections. And finally, a developmental model (CONDOS) which estimates the dose to a population resulting from the manufacture, storage, distribution, use, and disposal of consumer products which contain radioactivity is described. Numerous tables are included

  5. Analysis of a Radioactive Release in a Nuclear Waste Disposal Facility

    International Nuclear Information System (INIS)

    Poppiti, James; Nelson, Roger; MacMillan, Walter J.; Cunningham, Scott

    2017-01-01

    The Waste Isolation Pilot Plant (WIPP) is a 655-meter deep mine near Carlsbad, New Mexico, used to dispose the nation's defense transuranic waste. Limited airborne radioactivity was released from a container of radioactive waste in WIPP on 14 February, 2014. As designed, a mine ventilation filtration system prevented the large scale release of contamination from the underground. However, isolation dampers leaked, which allowed the release of low levels of contaminants after the event until they were sealed. None of the exposed individuals received any recordable dose. While surface contamination was limited, contamination in the ventilation system and portions of the underground was substantial. High efficiency particulate air (HEPA) filters in the operating ventilation system ensure continued containment during recovery and resumption of disposal operations. However, ventilation flow is restricted since the incident, with all exhaust air directed through the filters. Decontamination and natural fixation by the hygroscopic nature of the salt host rock has reduced the likelihood of further contamination spread. Contamination control and ventilation system operability are crucial for resumption of operations. This article provides an operational assessment and evaluation of these two key areas.

  6. Analysis of a Radioactive Release in a Nuclear Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Poppiti, James [Dept. of Energy, Washington, DC (United States); Nelson, Roger [Dept. of Energy, Carlsbad, NM (United States); MacMillan, Walter J. [Nuclear Waste Partners, Carlsbad, NM (United States); Cunningham, Scott

    2017-07-01

    The Waste Isolation Pilot Plant (WIPP) is a 655-meter deep mine near Carlsbad, New Mexico, used to dispose the nation’s defense transuranic waste. Limited airborne radioactivity was released from a container of radioactive waste in WIPP on 14 February, 2014. As designed, a mine ventilation filtration system prevented the large scale release of contamination from the underground. However, isolation dampers leaked, which allowed the release of low levels of contaminants after the event until they were sealed. None of the exposed individuals received any recordable dose. While surface contamination was limited, contamination in the ventilation system and portions of the underground was substantial. High efficiency particulate air (HEPA) filters in the operating ventilation system ensure continued containment during recovery and resumption of disposal operations. However, ventilation flow is restricted since the incident, with all exhaust air directed through the filters. Decontamination and natural fixation by the hygroscopic nature of the salt host rock has reduced the likelihood of further contamination spread. Contamination control and ventilation system operability are crucial for resumption of operations. This article provides an operational assessment and evaluation of these two key areas.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  8. Compliance of the Vaalputs national radioactive waste disposal facility to a frequency-magnitude release criterion as required for licensing

    International Nuclear Information System (INIS)

    Adrian, H.W.W.; Gerber, H.H.; Kruger, J.; Weygand, J.

    1986-01-01

    Accidental releases of radioactivity from the Vaalputs nuclear waste repository have been quantified and release frequencies have been attached to a number of accident scenarios of human or natural origin. These have then been compared to a frequency-magnitude release criterion according to South African licensing requirements. It was shown that the criterion was applicable in three release bands. In two of these the criterion was met by some orders of magnitude. In the third band the permitted release frequency was a factor 55 below the limit in spite of pessimistic release assumptions

  9. Radiation exposure in an urban dwelling following an accidental release of radioactivity

    International Nuclear Information System (INIS)

    Cannell, Robert J.

    1988-01-01

    The intent of this work is the improved knowledge of how much protection would be afforded to the occupants of a dwelling in the event of a release of radioactivity into the environment. Fundamental to this is the question of how radioactive aerosols and dusts outside of a dwelling affect the inhabitants, what proportion of and by what routes radioactive materials penetrate the structural fabric of the dwelling, and again, how these materials affect the occupants once inside the dwelling. Whilst related research has already provided some answers to this question, experimental work on the tracking of radioactive materials or their analogues was, and still is, required. The major effort of this research has been in the development of an image gathering and processing system which provides a measurement of the mass and spatial distribution of a fluorescent tracer deposited on a surface. Although capable of further refinement, the technique is usable experimentally and its initial use in studying the transport of tracer analogues of radioactive materials is described. One of the main determinants of the behaviour of aerosols is their deposition rate and measurements of this rate for several aerosol-bound radionuclides were made in a test house. The results of these measurements and the dust transport experiments are collated and together with current values from the literature provide the input data for a computer house model. This simple house model has been developed with the primary purpose of indicating which parameters, specifically related to the characteristics of a dwelling, are most influential in determining what degree of protection the occupants will gain. The estimates of protection resulting from the model are summarised, and its sensitivity to the input parameters is used to indicate where further experimental work needs to be undertaken. (author)

  10. Off-gases cleaning and release from a radioactive waste incinerator protection and safety aspects

    International Nuclear Information System (INIS)

    Caramelle, D.; Chevalier, G.

    1985-01-01

    The function of an off-gas cleaning and release installation being environmental protection, the means allowing the installation operation and the quality control of this function must be available. The chief risk then in normal operation is occupational exposure in the vicinity of the points of radioactive products accumulation. The accidental risks are mainly related to an outage of the installation, or a tightness failure resulting from either internal perturbation (filter tear, exhauster failure, washing-column clogging) or external incidents (electricity cut off, furnace disarrangement, fire or explosion in the building, etc.). (orig.)

  11. The Risoe model for calculating the consequences of the release of radioactive material to the atmosphere

    International Nuclear Information System (INIS)

    Thykier-Nielsen, S.

    1980-07-01

    A brief description is given of the model used at Risoe for calculating the consequences of releases of radioactive material to the atmosphere. The model is based on the Gaussian plume model, and it provides possibilities for calculation of: doses to individuals, collective doses, contamination of the ground, probability distribution of doses, and the consequences of doses for give dose-risk relationships. The model is implemented as a computer program PLUCON2, written in ALGOL for the Burroughs B6700 computer at Risoe. A short description of PLUCON2 is given. (author)

  12. Parametric study of the Ignalina reactor building capability as barrier against accidental releases of radioactivity

    International Nuclear Information System (INIS)

    Blomquist, R.; Johansson, Kjell; Nilsson, Lars.

    1993-01-01

    The results of a parametric study are offered to the Ignalina plant management staff and to the Lithuanian and Swedish nuclear inspectorates as a basis for a decision whether there is mutual interest in a project for the purpose of strengthening the Ignalina reactor buildings inherent capabilities to provide a barrier against accidental releases of radioactivity. Practical measures to consider are: * establish natural convection of warm air from the steam drums to the tall stack of 150 m height. * reduce the resulting draught of air through the reactor hall floor between the fuel channel shield blocks into the steam drum compartments. * apply filtration to the stack air flow. 18 refs

  13. Effect of the foodchain in radioactivities released from thermal power plants

    International Nuclear Information System (INIS)

    Okamoto, K.

    1980-01-01

    Food chains involving 210 Pb and 210 Po have been investigated in Japan, with special reference to the vegetable and sea food chain. Although much smaller than the natural background, the collective dose of coal burning including this food chain was 100 to 1000 times larger than that excluding it, the Suess effect being too small to cancel it. The dose due to coal burning was comparable to or even greater than that of nuclear energy. The need for further investigation of radioactive release due to the oil and natural gas industries is also emphasised, with particular reference to radon and its daughters 210 Pb and 210 Po. (U.K.)

  14. COCO-1: model for assessing the cost of offsite consequences of accidental releases of radioactivity

    International Nuclear Information System (INIS)

    Haywood, S.M.; Robinson, C.A.; Heady, C.

    1991-09-01

    This report describes a new model, called COCO-1 (Cost Of Consequences Offsite), for assessing the offsite economic consequences of an accident involving the release of radioactive material. The costs calculated are a measure of the benefit foregone as a result of the accident, and in addition to tangible monetary costs the model attempts to include costs arising from the effect of the accident on individuals, for instance the disruption caused by the loss of homes. The approach has limitations, which are discussed, but offers a broadly applicable and robust technique for estimating the economic impact of most accidents. (author)

  15. Mathematical modeling of radionuclide release through a borehole in a radioactive waste repository

    International Nuclear Information System (INIS)

    Choi, Heui Joo

    1996-02-01

    The effects of inadvertent human intrusion as a form of direct drilling into a radioactive waste repository are discussed in this thesis. It has been mentioned that the inadvertent direct drilling into the repository could provide a release pathway for radionuclides even with its low occurrence probability. The following analyses are carried out regarding the problem. The maximum concentration in a water-filled borehole penetrating a repository is computed with a simple geometry. The modeling is based upon the assumption of the diffusive mass transfer in the waste forms and the complete mixing in the borehole. It is shown that the maximum concentrations of six radionuclides in the borehole could exceed the Maximum Permissible Concentration. Also, the diffusive mass transport in a water-filled borehole is investigated with a solubility-limited boundary condition. An analytic solution is derived for this case. Results show that the diffusive mass transport is fast enough to justify the assumption of the complete mixing compared with the considered time span. The axial diffusive mass transport along a water-filled borehole is modeled to compute the release rate taking account of the rock matrix diffusion. The results show that the release of short-lived radionuclides are negligible due to the low concentration gradient in early time and the rock matrix diffusion. The release rates of four long-lived radionuclides are computed. It is also shown that the model developed could be applied to a borehole at a non-cylindrically shaped repository and the off-center drilling of a cylindrical repository. The release rates of long-lived nuclides through a porous material-filled borehole are computed. The results show that the release of all the long-lived nuclides is negligible up to half million years in the case that the borehole is filled with the porous material. The radiological effects of the nuclides released through the borehole penetrating the repository are computed

  16. Experiments to quantify airborne release from packages with dispersible radioactive materials under accident conditions

    Energy Technology Data Exchange (ETDEWEB)

    Martens, R.; Lange, F. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Schwertnergasse 1, 50667 Koeln (Germany); Koch, W.; Nolte, O. [Fraunhofer-Institut fuer Toxikologie und Experimentelle Medizin (ITEM), Nikolai-Fuchs-Str.1, 30625 Hannover (Germany)

    2005-07-01

    For transport or handling accidents involving packages with radioactive materials and the assessment of potential radiological consequences, for the review of current requirements of the IAEA Transport Regulations, and for their possible further development reliable release data following mechanical impact are required. Within this context a research project was carried out which extends the basis for a well-founded examination of the contemporary system of requirements of 'Low Specific Activity' (LSA)-type materials and allows for its further development where appropriate. This project comprises a prior system-analytical examination and an experimental programme aiming at improving the general physical understanding of the release process as well as the quantity and the characteristics of airborne released material for non-fixed dispersible LSA-II material upon mechanical impact. Impaction experiments applying small, medium and real sized specimens of different dispersible materials revealed that the release behaviour of dispersible powders strongly depends upon material properties, e.g. particle size distribution and cohesion forces. The highest experimentally determined release fraction of respirable mass (AED < 10 {mu}m) amounted to about 2 % and was obtained for 2 kg of un-contained easily dispersible pulverized fly ash (PFA). For larger un-contained PFA specimen the release fraction decreases. However, packaging containing powdery material substantially reduces the airborne release fraction. The measured airborne release fractions for a 200 l drum with Type A certificate containing PFA were about a factor of 50 to 100 lower than for un-contained material. For a drop height of 9 m the airborne release fraction amounted to about 4 x 10{sup -5}. This value should be applicable for most of transport and handling accidents with mechanical impact. For a metal container of Type IP-2 or better which contains powder masses of 100 kg or more this release

  17. Sensitivity study of the Continuous Release Dispersion Model (CRDM) for radioactive pollutants

    International Nuclear Information System (INIS)

    Camacho, F.

    1987-08-01

    The Continuous Release Dispersion Model (CRDM) is used to calculate spatial distribution of pollutants and their radiation doses in the event of accidental releases of radioactive material from Nuclear Generation Stations. A sensitivity analysis of the CRDM was carried out to develop a method for quantifying the expected output uncertainty due to inaccuracies and uncertainties in the input values. A simulation approach was used to explore the behaviour of the sensitivity functions. It was found that the most sensitive variable is wind speed, the least sensitive is the ambient temperature, and that largest values of normalized concentrations are likely to occur for small values of wind speed and highly stable atmospheric conditions. It was also shown that an error between 10% and 25% should be expected in the output values for a 1% overall error in the input values, and this factor could be much larger in certain situations

  18. Simplified analytical model to simulate radionuclide release from radioactive waste trenches

    International Nuclear Information System (INIS)

    Sa, Bernardete Lemes Vieira de

    2001-01-01

    In order to evaluate postclosure off-site doses from low-level radioactive waste disposal facilities, a computer code was developed to simulate the radionuclide released from waste form, transport through vadose zone and transport in the saturated zone. This paper describes the methodology used to model these process. The radionuclide released from the waste is calculated using a model based on first order kinetics and the transport through porous media was determined using semi-analytical solution of the mass transport equation, considering the limiting case of unidirectional convective transport with three-dimensional dispersion in an isotropic medium. The results obtained in this work were compared with other codes, showing good agreement. (author)

  19. Restoration of water environment contaminated by radioactive cesium released from Fukushima Daiichi NPP

    Energy Technology Data Exchange (ETDEWEB)

    Takeshita, K.; Takahashi, H. [Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 Ookayama, Meguro-ku, Tokyo 157-8550 (Japan); Jinbo, Y. [CDM Cosulting Co.Ltd., 1-13-13 Tsukiji Chuo-ku Tokyo 104-0045 (Japan); Ishido, A. [Radwaste and Decommissioning Center, 1-7-6 Toranomon, Minato-ku, Tokyo 105-0001 (Japan)

    2013-07-01

    In the Fukushima Daiichi NPP Accident, large amounts of volatile radioactive nuclides, such as {sup 131}I, {sup 134}Cs and {sup 137}Cs, were released to the atmosphere and huge areas surrounding the nuclear site were contaminated by the radioactive fallout. In this study, a combined process with a hydrothermal process and a coagulation settling process was proposed for the separation of radioactive Cs from contaminated soil and sewage sludge. The coagulation settling operation uses Prussian Blue (Ferric ferrocyanide) and an inorganic coagulant. The recovery of Cs from sewage sludge sampled at Fukushima city (100.000 Bq/kg) and soil at a nearby village (55.000 Bq/kg), was tested. About 96% of Cs in the sewage sludge was removed successfully by combining simple hydrothermal decomposition and coagulation settling. However, Cs in the soil was not removed sufficiently by the combined process (Cs removal is only 56%). The hydrothermal decomposition with blasting was carried out. The Cs removal from the soil was increased to 85%. When these operations were repeated twice, the Cs recovery was over 90%. The combined process with hydrothermal blasting and coagulation settling is applicable to the removal of Cs from highly contaminated soil.

  20. 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

  1. Development of DOE complexwide authorized release protocols for radioactive scrap metals

    International Nuclear Information System (INIS)

    Chen, S. Y.

    1998-01-01

    Within the next few decades, several hundred thousand tons of metal are expected to be removed from nuclear facilities across the U.S. Department of Energy (DOE) complex as a result of decontamination and decommissioning (D and D) activities. These materials, together with large quantities of tools, equipment, and other items that are commonly recovered from site cleanup or D and D activities, constitute non-real properties that warrant consideration for reuse or recycle, as permitted and practiced under the current DOE policy. The provisions for supporting this policy are contained in the Draft Handbook for Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material published by DOE in 1997 and distributed to DOE field offices for interim use and implementation. The authorized release of such property is intended to permit its beneficial use across the entire DOE complex. The objective of this study is to develop readily usable computer-based release protocols to facilitate implementation of the Handbook in evaluating the scrap metals for reuse and recycle. The protocols provide DOE with an effective oversight tool for managing release activities

  2. Application of dynamic modeling for assessing the impact of radioactive releases to water sewer systems

    International Nuclear Information System (INIS)

    Sundell-Bergman, Synnove; Avila, Rodolfo; Cruz, Idalmis de la

    2008-01-01

    Full text: Potential radiological emergencies due to accidental or malicious acts involving nuclear materials requires tools for emergency dose assessment to help in the planning of countermeasures. In urban areas, the municipal sewage systems will receive the wastewater from households, industries and hospitals as well as the run-off water. Investigations have shown that sewage sludge is a sensitive indicator for radionuclides released from hospitals or spread via the atmosphere and thus simulation modelling of the fate of radionuclides entering sewage treatment plants via urban drainage systems could prove useful in emergency situations. A dynamic model (LUCIA) has been developed to assess the radiological consequences of non-homogenous releases of radionuclides to the sewage plants. In the first step the focussing has been on radioactive liquid releases from hospitals and the predictions show that there is a significant probability (> 0,2) that the sewage worker doses exceed 10 μSv/y while doses to farmers or fishermen (downstream plants) are marginal. Comparison of measured and estimated concentration values for iodine-131 reveal that the predictions made by LUCIA are reasonably good and fall within a factor of 2. For the purpose of emergency preparedness, scenarios have been defined and the fate of released radionuclides has been assessed. The main features of the LUCIA model will be presented and the application of the tool for emergency preparedness will be discussed. (author)

  3. Approach and issues toward development of risk-based release standards for radioactive scrap metal recycle and reuse

    International Nuclear Information System (INIS)

    Chen, S.Y.; Nieves, L.A.; Nabelssi, B.K.; LePoire, D.J.

    1994-01-01

    The decontamination and decommissioning of nuclear facilities is expected to generate large amounts of slightly radioactive scrap metal (RSM). It is likely that some of these materials will be suitable for recycling and reuse. The amount of scrap steel from DOE facilities, for instance, is estimated to be more than one million tons (Hertzler 1993). However, under current practice and without the establishment of acceptable recycling standards, the RSM would be disposed of primarily as radioactive low-level waste (LLW). In the United States, no specific standards have been developed for the unrestricted release of bulk contaminated materials. Although standards for unrestricted release of radioactive surface contamination (NRC 1974) have existed for about 20 years, the release of materials is not commonly practiced because of the lack of risk-based justifications. Recent guidance from international bodies (IAEA 1988) has established a basis for deriving risk-based release limits for radioactive materials. It is important, therefore, to evaluate the feasibility of recycling and associated issues necessary for the establishment of risk-based release limits for the radioactive metals

  4. Conceptual Design of Portable Filtered Air Suction Systems For Prevention of Released Radioactive Gas under Severe Accidents of NPP

    Energy Technology Data Exchange (ETDEWEB)

    Gu, Beom W.; Choi, Su Y.; Yim, Man S.; Rim, Chun T. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2014-05-15

    It becomes evident that severe accidents may occur by unexpected disasters such as tsunami, heavy flood, or terror. Once radioactive material is released from NPP through severe accidents, there are no ways to prevent the released radioactive gas spreading in the air. As a remedy for this problem, the idea on the portable filtered air suction system (PoFASS) for the prevention of released radioactive gas under severe accidents was proposed. In this paper, the conceptual design of a PoFASS focusing on the number of robot fingers and robot arm rods are proposed. In order to design a flexible robot suction nozzle, mathematical models for the gaps which represent the lifted heights of extensible covers for given convex shapes of pipes and for the covered areas are developed. In addition, the system requirements for the design of the robot arms of PoFASS are proposed, which determine the accessible range of leakage points of released radioactive gas. In this paper, the conceptual designs of the flexible robot suction nozzle and robot arm have been conducted. As a result, the minimum number of robot fingers and robot arm rods are defined to be four and three, respectively. For further works, extensible cover designs on the flexible robot suction nozzle and the application of the PoFASS to the inside of NPP should be studied because the radioactive gas may be released from connection pipes between the containment building and auxiliary buildings.

  5. Impact on the marine environment of radioactive releases resulting from the Fukushima-Daiichi nuclear accident. April 4, 2011

    International Nuclear Information System (INIS)

    2011-01-01

    After having outlined that measurements taken over several days in the sea water in the vicinity of the power station have revealed severe contamination of the marine environment by various radionuclides released as a result of the accident at the Fukushima-Daiichi nuclear power station, this report describes the origins of the contamination of the marine environment (release of liquid effluents directly into the sea in the vicinity of the damaged reactors, atmospheric fallout onto the surface of the sea, conveyance of radioactive pollution by rainout of contaminated ground). Then, while proposing several maps, the authors analyse and comment the dispersion in the sea of radioactive pollutants by addressing the following issues: topography of the sea bed and sea currents off the Japanese coast, immediate or short term dispersion (a few days), mid-term dispersion (weeks and months), long term and large scale future of the radioactive pollutants. Finally, the report briefly discusses the impact of radioactive pollution on living species

  6. Update: Tests confirm no radioactivity release to environment from IAEA Seibersdorf Lab after 3 August incident

    International Nuclear Information System (INIS)

    2008-01-01

    Full text: Independent analysis has confirmed that there was no release of radioactive material to the environment following an incident at the IAEA's Seibersdorf Laboratory on 3 August. The test results were provided by the Austrian Research Centers (ARC), from analysis of soil, plant and water samples collected from outside the IAEA's Laboratories in Seibersdorf, where the incident occurred. The radiation protection experts of the ARC confirmed the initial findings from the laboratory's automatic monitoring system which indicated that there had been no release of radioactivity to the environment. Since the incident, constant air monitoring near the laboratory, undertaken by the IAEA, has also provided no evidence of any radioactive contamination. A tiny amount of plutonium contained in an acid solution spilled from five small glass vials when one of them burst after a build up of pressure in it. The vials were stored in a secure steel safe. In total there was less than one gram of plutonium in the five vials. The material was in the laboratory for scientific reference purposes and virtually all of the contamination was confined within the steel walled safe. As previously reported, the automatic alarm was triggered when highly sensitive detectors of the continuous air monitoring system identified minor amounts of radioactive aerosols in the storage room containing the safe. The air contamination was trapped entirely in the filters of the ventilation system. No one was working in the laboratory at the time of the accident, which occurred at 02:31. The IAEA emergency response team promptly secured and sealed off the windowless storage room. An investigation into the circumstances and causes of the incident is still underway. In the meantime the first stage of the clean-up of the storage room was successfully completed on Friday, 22 August. According to the IAEA's nuclear regulator's assessment of the incident, the lab's safety systems worked properly and

  7. Update: Tests confirm no radioactivity release to environment from IAEA Seibersdorf Lab after 3 August incident

    International Nuclear Information System (INIS)

    2008-01-01

    Full text: Independent analysis has confirmed that there was no release of radioactive material to the environment following an incident at the IAEA's Seibersdorf Laboratory on 3 August. The test results were provided by the Austrian Research Centers (ARC), from analysis of soil, plant and water samples collected from outside the IAEA's Laboratories in Seibersdorf, where the incident occurred. The radiation protection experts of the ARC confirmed the initial findings from the laboratory's automatic monitoring system which indicated that there had been no release of radioactivity to the environment. Since the incident, constant air monitoring near the laboratory, undertaken by the IAEA, has also provided no evidence of any radioactive contamination. A tiny amount of plutonium contained in an acid solution spilled from five small glass vials when one of them burst after a build up of pressure in it. The vials were stored in a secure steel safe. In total there was less than one gram of plutonium in the five vials. The material was in the laboratory for scientific reference purposes and virtually all of the contamination was confined within the steel walled safe. As previously reported, the automatic alarm was triggered when highly sensitive detectors of the continuous air monitoring system identified minor amounts of radioactive aerosols in the storage room containing the safe. The air contamination was trapped entirely in the filters of the ventilation system. No one was working in the laboratory at the time of the accident, which occurred at 02:31. The IAEA emergency response team promptly secured and sealed off the windowless storage room. An investigation into the circumstances and causes of the incident is still underway. In the meantime the first stage of the clean-up of the storage room was successfully completed on Friday, 22 August. According to the IAEA's nuclear regulator's assessment of the incident, the lab's safety systems worked properly and

  8. Regulatory Initiatives for Control and Release of Technologically Enhanced Naturally-Occurring Radioactive Materials

    Energy Technology Data Exchange (ETDEWEB)

    Egidi, P.V.

    1999-03-02

    Current drafts of proposed standards and suggested State regulations for control and release of technologically-enhanced naturally-occurring radioactive material (TENORM), and standards for release of volumetrically-contaminated material in the US are reviewed. These are compared to the recommendations of the International Atomic Energy Association (IAEA) Safety Series and the European Commission (EC) proposals. Past regulatory efforts with respect to TENORM in the US dealt primarily with oil-field related wastes. Currently, nine states (AK, GA, LA, MS, NM, OH, OR SC, TX) have specific regulations pertaining to TENORM, mostly based on uranium mill tailings cleanup criteria. The new US proposals are dose- or risk-based, as are the IAEA and EC recommendations, and are grounded in the linear no threshold hypothesis (LNT). TENORM wastes involve extremely large volumes, particularly scrap metal and mine wastes. Costs to control and dispose of these wastes can be considerable. The current debate over the validity of LNT at low doses and low dose rates is particularly germane to this discussion. Most standards setting organizations and regulatory agencies base their recommendations on the LNT. The US Environmental Protection Agency has released a draft Federal Guidance Report that recommends calculating health risks from low-level exposure to radionuclides based on the LNT. However, some scientific and professional organizations are openly questioning the validity of LNT and its basis for regulations, practices, and costs to society in general. It is not clear at this time how a non-linear regulatory scheme would be implemented.

  9. Regulatory Initiatives for Control and Release of Technologically Enhanced Naturally-Occurring Radioactive Material

    International Nuclear Information System (INIS)

    Egidi, P.V.

    1999-01-01

    Current drafts of proposed standards and suggested State regulations for control and release of technologically-enhanced naturally-occurring radioactive material (TENORM), and standards for release of volumetrically-contaminated material in the US are reviewed. These are compared to the recommendations of the International Atomic Energy Association (IAEA) Safety Series and the European Commission (EC) proposals. Past regulatory efforts with respect to TENORM in the US dealt primarily with oil-field related wastes. Currently, nine states (AK, GA, LA, MS, NM, OH, OR SC, TX) have specific regulations pertaining to TENORM, mostly based on uranium mill tailings cleanup criteria. The new US proposals are dose- or risk-based, as are the IAEA and EC recommendations, and are grounded in the linear no threshold hypothesis (LNT). TENORM wastes involve extremely large volumes, particularly scrap metal and mine wastes. Costs to control and dispose of these wastes can be considerable. The current debate over the validity of LNT at low doses and low dose rates is particularly germane to this discussion. Most standards setting organizations and regulatory agencies base their recommendations on the LNT. The US Environmental Protection Agency has released a draft Federal Guidance Report that recommends calculating health risks from low-level exposure to radionuclides based on the LNT. However, some scientific and professional organizations are openly questioning the validity of LNT and its basis for regulations, practices, and costs to society in general. It is not clear at this time how a non-linear regulatory scheme would be implemented

  10. The terrestrial environmental dynamics of radioactive nuclides released by the Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Furukawa, Jun

    2014-01-01

    Research into environmental dynamics of radioactive nuclides released by the Fukushima nuclear accident, especially radiocesium 137 Cs (half-life, 30.1 years), is highly focused especially on diffusion processes of radiocesium into ecosystems, which is high-priority knowledge. Because of relatively sparse knowledge about the reallocation of radiocesium contained in organic matter in terrestrial ecosystems, the effects of diffused rediocesium into ecosystem cannot be accurately estimated. In this article, the terrestrial environmental dynamics of radiocesium mainly in the processes of plant uptake and the possibility of release from plants will be discussed. Plants uptake minerals from soil and these minerals are likewise ingested by animals that feed on plants, including humans. Therefore one of the main gateways of radiocesium into ecosystem is via plants. From the viewpoint of human dietary consumption, rice contamination with radiocesium has been energetically investigated and useful data are accumulating. Processes of radiocesium uptake mechanisms by plants are being researched using legumes, e.g. soybean. Speculation on the possibility of radiocesium release into forest atmosphere via plant activity will be introduced. (author)

  11. Intercomparison of numerical simulations on oceanic dispersion of the radioactive cesium released because of the Fukushima disaster

    Energy Technology Data Exchange (ETDEWEB)

    Kawamura, H.; Kobayshi, T.; Furuno, A. [Japan Atomic Energy Agency, Ibaraki (Japan); Usui, N.; Kamachi, M. [Japan Meteorological Agency, Meteorological Research Inst., Ibaraki (Japan); Nishikawa, S.; Ishikawa, Y. [Japan Agency for Marine-Earth Science and Tech., Kanagawa (Japan)

    2014-07-01

    We conducted numerical simulations on oceanic dispersion of the radioactive cesium released because of the Fukushima disaster in the North Pacific. Two independent oceanic reanalysis data were used in the simulations. Both simulations suggested that the {sup 137}Cs concentration had been reduced to the pre-Fukushima level around 2.5 years after the disaster. The intercomparison revealed that meso-scale eddies accompanied by the Kuroshio Extension may have efficiently diluted the radioactive cesium at the sea surface. The meso-scale eddies also played an important role in transporting the surface radioactive cesium into the intermediate layer. (author)

  12. Malicious release of radioactive materials in urban area. Exposure of the public and emergency staff, protective measures

    International Nuclear Information System (INIS)

    Koch, Wolfgang; Lange, Florentin

    2016-01-01

    The preparedness for hypothetical radiological scenarios is part of the tasks for governmental authorities, safety and emergency organizations and the staff in case of the incident. The EURATOM guideline for radiation protection has to be implemented into national laws. According to the guidelines it is required that emergency planning has to be prepared for hypothetical radiological scenarios including terroristic or other maliciously motivated attacks using radioactive materials. The study includes assumptions on the released respirable radioactivity, restriction of the hazardous area, wind induced re-suspension of radioactive dusts and inhalation exposure, and mitigation measures.

  13. Compilation of documented computer codes applicable to environmental assessment of radioactivity releases

    International Nuclear Information System (INIS)

    Hoffman, F.O.; Miller, C.W.; Shaeffer, D.L.; Garten, C.T. Jr.; Shor, R.W.; Ensminger, J.T.

    1977-04-01

    The objective of this paper is to present a compilation of computer codes for the assessment of accidental or routine releases of radioactivity to the environment from nuclear power facilities. The capabilities of 83 computer codes in the areas of environmental transport and radiation dosimetry are summarized in tabular form. This preliminary analysis clearly indicates that the initial efforts in assessment methodology development have concentrated on atmospheric dispersion, external dosimetry, and internal dosimetry via inhalation. The incorporation of terrestrial and aquatic food chain pathways has been a more recent development and reflects the current requirements of environmental legislation and the needs of regulatory agencies. The characteristics of the conceptual models employed by these codes are reviewed. The appendixes include abstracts of the codes and indexes by author, key words, publication description, and title

  14. Release consequence analysis for a hypothetical geologic radioactive waste repository in hard rock

    International Nuclear Information System (INIS)

    1979-12-01

    This report makes an evaluation of the long-term behaviour of the wastes placed in a hard rock repository. Impacts were analyzed for the seven reference fuel cycles of WG 7. The reference repository for this study is for granitic rock or gneiss as the host rock. The descriptions of waste packages and repository facilities used in this study represent only one of many possible designs based on the multiple barriers concept. The repository's size is based on a nuclear economy producing 100 gigawatts of electricity per year for 1 year. The objective of the modeling efforts presented in this study is to predict the rate of transport of radioactive contaminants from the repository through the geosphere to the biosphere and thus determine an estimate of the potential dose to humans so that the release consequence impacts of the various fuel cycles can be compared. Currently available hydrologic, leach, transport, and dose models were used in this study

  15. The European Community dimension to the problem of accidental radioactive releases to the environment

    International Nuclear Information System (INIS)

    Bennett, E.

    1989-01-01

    The European Community has to comply with the provisions of the Euratom Treaty, 1957. As well as providing the conditions necessary for the growth of nuclear industries it lays down the task to establish uniform Safety Standards to protect the health of workers and of the general public. This includes emergency planning in case of nuclear accidents. As a result the Community followed the guide, published in 1982 by the International Commission on Radiological Protection, on the radiological protection criteria for controlling doses to the public in the event of accidental releases of radioactive materials. However when the Chernobyl accident occured the Community and International arrangements proved to be inadequate to respond to the consequent widespread contamination over Europe. Measures have been taken since then to improve the preparedness of the Community. They include better exchange of information, control of contaminated foodstuffs and better information to the public. (U.K.)

  16. Conversion factors for estimating release rate of gaseous radioactivity by an aerial survey

    International Nuclear Information System (INIS)

    Saito, Kimiaki; Moriuchi, Shigeru

    1988-02-01

    Conversion factors necessary for estimating release rate of gaseous radioactivity by an aerial survey are presented. The conversion factors were determined based on calculation assuming a Gaussian plume model as a function of atmospheric stability, down-wind distance and flight height. First, the conversion factors for plumes emitting mono-energy gamma rays were calculated, then, conversion factors were constructed through convolution for the radionuclides essential in an accident of a nuclear reactor, and for mixtures of these radionuclides considering elapsed time after shutdown. These conversion factors are shown in figures, and also polynomial expressions of the conversion factors as a function of height have been decided with the least-squares method. A user can easily obtain proper conversion factors from data shown here. (author)

  17. Control of synthesis and release of radioactive acetylcholine in brain slices from the rat. Effects of neurotropic drugs

    Science.gov (United States)

    Grewaal, D. S.; Quastel, J. H.

    1973-01-01

    1. Studies of the synthesis and release of radioactive acetylcholine in rat brain-cortex slices incubated in Locke–bicarbonate–[U-14C]glucose media, containing paraoxon as cholinesterase inhibitor, revealed the following phenomena: (a) dependence of K+-or protoveratrine-stimulated acetylcholine synthesis and release on the presence of Na+ and Ca2+ in the incubation medium, (b) enhanced release of radioactive acetylcholine by substances that promote depolarization at the nerve cell membrane (e.g. high K+, ouabain, protoveratrine, sodium l-glutamate, high concentration of acetylcholine), (c) failure of acetylcholine synthesis to keep pace with acetylcholine release under certain conditions (e.g. the presence of ouabain or lack of Na+). 2. Stimulation by K+ of radioactive acetylcholine synthesis was directly proportional to the external concentration of Na+, but some synthesis and release of radioactive acetylcholine occurred in the absence of Na+ as well as in the absence of Ca2+. 3. The Na+ dependence of K+-stimulated acetylcholine synthesis was partly due to suppression of choline transport, as addition of small concentrations of choline partly neutralized the effect of Na+ lack, and partly due to the suppression of the activity of the Na+ pump. 4. Protoveratrine caused a greatly increased release of radioactive acetylcholine without stimulating total radioactive acetylcholine synthesis. Protoveratrine was ineffective in the absence of Ca2+ from the incubation medium. It completely blocked K+ stimulation of acetylcholine synthesis and release. 5. Tetrodotoxin abolished the effects of protoveratrine on acetylcholine release. It had blocking effects (partial or complete) on the action of high K+, sodium l-glutamate and lack of Ca2+ on acetylcholine synthesis and release. 6. Unlabelled exogenous acetylcholine did not diminish the content of labelled tissue acetylcholine, derived from labelled glucose, suggesting that no exchange with vesicular acetylcholine took

  18. Release consequence analysis for a hypothetical geologic radioactive waste repository in salt

    International Nuclear Information System (INIS)

    1979-08-01

    One subtask conducted under the INFCE program is to evaluate and compare the health and safety impacts of different fuel cycles in which all radioactive wastes (except those from mining and milling) are placed in a geologic repository in salt. To achieve this objective, INFCE Working Group 7 examined the radiologic dose to humans from geologic repositories containing waste arisings as defined for seven reference fuel cycles. This report examines the release consequences for a generic waste repository in bedded salt. The top of the salt formation and the top of the repository are assumed to be 250 and 600 m, respectively, below the surface. The hydrogeologic structure above the salt consists of two aquifers and two aquitards. The aquifers connect to a river 6.2 km from the repository. The regional gradient to the river is 1 m/km in all aquifers. Hydrologic, transport, and dose models were used to model two release scenarios for each fuel cycle, one without a major disturbance and one in which a major geologic perturbation breached the repository immediately after it was sealed. The purpose of the modeling was to predict the rate of transport of radioactive contaminants from the repository through the geosphere to the biosphere, and to determine the potential dose to humans. Of the many radionuclides in the waste, only 129 I and 226 Ra arrived at the river in sufficient concentrations for a measurable dose calculation. Radionuclide concentrations in the ground water pose no threat to man because the ground water is a concentrated brine and it is diluted by a factor of 10 6 to 10 7 upon entering the river

  19. Screening calculations for radioactive waste releases from non-nuclear facilities

    International Nuclear Information System (INIS)

    Xu, Shulan; Soederman, Ann-Louis

    2009-02-01

    A series of screening calculations have been performed to assess the potential radiological consequences of discharges of radioactive substances to the environment arising from waste from non-nuclear practices. Solid waste, as well as liquids that are not poured to the sewer, are incinerated and ashes from incineration and sludge from waste water treatment plants are disposed or reused at municipal disposal facilities. Airborne discharges refer to releases from an incineration facility and liquid discharges refer both to releases from hospitals and laboratories to the sewage system, as well as leakage from waste disposal facilities. The external exposure of workers is estimated both in the waste water treatment plant and at the disposal facility. The calculations follow the philosophy of the IAEA's safety guidance starting with a simple assessment based on very conservative assumptions which may be iteratively refined using progressively more complex models, with more realistic assumptions, as necessary. In the assessments of these types of disposal, with cautious assumptions, carried out in this report we conclude that the radiological impacts on representative individuals in the public are negligible in that they are small with respect to the target dose of 10 μSv/a. A Gaussian plume model was used to estimate the doses from airborne discharges from the incinerator and left a significant safety margin in the results considering the conservative assumptions in the calculations. For the sewage plant workers the realistic approach included a reduction in working hours and the shorter exposure time resulted in maximum doses around 10 μSv/a. The calculations for the waste disposal facility show that the doses are higher or in the range of the target dose. The excess for public exposure is mainly caused by H-3 and C-14. The assumption used in the calculation is that all of the radioactive substances sent to the incineration facility and waste water treatment plant

  20. Evaluation of release amount of radioactivity from Chernobyl accident and of resulting radiological consequence in China

    International Nuclear Information System (INIS)

    Zhang Yongxing

    1987-01-01

    Three kinds of methods are used to evaluate the release amount from Chernoby1 RBMK-1000 reactor accident, i.e. (1) estimation by comparison with Windscale accident; (2) estimation in terms of the stock in the core; and (3) estimation according to the available monitoring data form adjacent countries such as Poland and Finland. The results obtained are as follows: the release of I-131 was 0.1-1.5 EBq, which is approximately 4-50% of the stock in the core; the release amount of Ru-103 was comparable to that of Cs-137, both approximately 5-10% of that of I-131; the volatile nuclides such as Mo-99, Ru-103, Te-132, Cs-137 etc., were in the order of 0.4 EBq; involatile nuclides were 0.2 EBq; noble gases and other fission products 10 EBq; and the total amount released was about 20 EBq, which taken together 8% of the stock in the core. The radioactive cloud cluster passed through over the area of China in the beginning of May. It was estimated that the total amount of I-131 in air over China area was about 1.6 PB q , Cs-137 about 0.3 PB q , Ru-103 about 0.2 PB q ; the total fallout in the area of China was about 3 PB q for I-131, about 0.1 PB q for Cs-137, about 0.3 PB q for Ru-103. The resulting effective dose equavalent commitment to critical group individual was about 60 μSv, collective effective dose equavalent commitment received by the population of China was about 1 x 10 4 man.Sv

  1. Forensic Reconstructions of Radioactive Particulate Releases at the Chernobyl and the Al Tuwaitha Nuclear Facilities

    International Nuclear Information System (INIS)

    Chesser, R. K.; Rogers, B. E.; Philips, C. J.

    2007-01-01

    Evaluating dispersion of nuclear materials released by accidental, operational, or clandestine means is important to the international community. Our research team has performed forensic reconstructions of radionuclide releases at the Chernobyl Nuclear Power Plant (ChNPP) in Ukraine and the Al Tuwaitha Nuclear Facility (ATNF) near Baghdad, Iraq. Our objectives at ChNPP were to determine the influences of extant atmospheric conditions on particle size distributions and their depositions in the near-field (less than 12 km) regions surrounding the complex. We derived mathematical models of particulate fluid-flow in varying velocity and turbulence fields to fit with 3000 geographically-referenced measurements. Conformity of predicted and empirical fallout patterns was excellent, enabling accurate reconstructions of the particle size contributions, weather conditions, and release energies from the accident. The objectives at ATNF were to evaluate means of dispersion and characterization of nuclear materials within and outside of the compound. Normal facility operations, military actions, and looting of the facility could have contributed to the release of radioactivity, but would yield quite different geographic and radionuclide profiles. Detailed gamma, alpha, and beta radiation profiles were examined for 400 geographically-referenced soil samples collected from ATNF and the villages of Ishtar and Al Ryhad. Natural uranium clusters were identified in several locations clearly showing that looting of yellowcake was the primary means of dispersion. No dispersion of nuclear materials was shown to result from military operations at the site. Our programs demonstrate the precision of geographic-based forensic reconstructions and show that forecast models are robust.(author)

  2. Analytics of Radioactive Materials Released in the Fukushima Daiichi Nuclear Accident

    Energy Technology Data Exchange (ETDEWEB)

    Egarievwe, Stephen U. [Nuclear Engineering and Radiological Science Center, Alabama A and M University, Huntsville, AL (United States); Nuclear Engineering Department, University of Tennessee, Knoxville, TN (United States); Coble, Jamie B.; Miller, Laurence F. [Nuclear Engineering Department, University of Tennessee, Knoxville, TN (United States)

    2015-07-01

    The 2011 Fukushima Daiichi nuclear accident in Japan resulted in the release of radioactive materials into the atmosphere, the nearby sea, and the surrounding land. Following the accident, several meteorological models were used to predict the transport of the radioactive materials to other continents such as North America and Europe. Also of high importance is the dispersion of radioactive materials locally and within Japan. Based on the International Atomic Energy Agency (IAEA) Convention on Early Notification of a nuclear accident, several radiological data sets were collected on the accident by the Japanese authorities. Among the radioactive materials monitored, are I-131 and Cs-137 which form the major contributions to the contamination of drinking water. The radiation dose in the atmosphere was also measured. It is impractical to measure contamination and radiation dose in every place of interest. Therefore, modeling helps to predict contamination and radiation dose. Some modeling studies that have been reported in the literature include the simulation of transport and deposition of I-131 and Cs-137 from the accident, Cs-137 deposition and contamination of Japanese soils, and preliminary estimates of I-131 and Cs-137 discharged from the plant into the atmosphere. In this paper, we present statistical analytics of I-131 and Cs-137 with the goal of predicting gamma dose from the Fukushima Daiichi nuclear accident. The data sets used in our study were collected from the IAEA Fukushima Monitoring Database. As part of this study, we investigated several regression models to find the best algorithm for modeling the gamma dose. The modeling techniques used in our study include linear regression, principal component regression (PCR), partial least square (PLS) regression, and ridge regression. Our preliminary results on the first set of data showed that the linear regression model with one variable was the best with a root mean square error of 0.0133 μSv/h, compared

  3. Analytics of Radioactive Materials Released in the Fukushima Daiichi Nuclear Accident

    International Nuclear Information System (INIS)

    Egarievwe, Stephen U.; Coble, Jamie B.; Miller, Laurence F.

    2015-01-01

    The 2011 Fukushima Daiichi nuclear accident in Japan resulted in the release of radioactive materials into the atmosphere, the nearby sea, and the surrounding land. Following the accident, several meteorological models were used to predict the transport of the radioactive materials to other continents such as North America and Europe. Also of high importance is the dispersion of radioactive materials locally and within Japan. Based on the International Atomic Energy Agency (IAEA) Convention on Early Notification of a nuclear accident, several radiological data sets were collected on the accident by the Japanese authorities. Among the radioactive materials monitored, are I-131 and Cs-137 which form the major contributions to the contamination of drinking water. The radiation dose in the atmosphere was also measured. It is impractical to measure contamination and radiation dose in every place of interest. Therefore, modeling helps to predict contamination and radiation dose. Some modeling studies that have been reported in the literature include the simulation of transport and deposition of I-131 and Cs-137 from the accident, Cs-137 deposition and contamination of Japanese soils, and preliminary estimates of I-131 and Cs-137 discharged from the plant into the atmosphere. In this paper, we present statistical analytics of I-131 and Cs-137 with the goal of predicting gamma dose from the Fukushima Daiichi nuclear accident. The data sets used in our study were collected from the IAEA Fukushima Monitoring Database. As part of this study, we investigated several regression models to find the best algorithm for modeling the gamma dose. The modeling techniques used in our study include linear regression, principal component regression (PCR), partial least square (PLS) regression, and ridge regression. Our preliminary results on the first set of data showed that the linear regression model with one variable was the best with a root mean square error of 0.0133 μSv/h, compared

  4. 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.)

  5. Radioactive release data from Canadian nuclear generating stations 1872-1987

    International Nuclear Information System (INIS)

    1989-03-01

    All nuclear generating stations emit small quantities of radioactive effluent both into the atmosphere and in the form of liquid effluent, into the adjoining water body, be it river, lake or sea. The purpose of this document is to report on the magnitude of these emissions for each nuclear generating station in Canada and to indicate how these emissions compare with the relevant limitations imposed by the Atomic Energy Control Board as part of its regulatory and licensing program. This report incorporates histograms indicating the annual releases of tritium in air, noble gases, iodine-131, airborne particulates, tritium in water and waterborne gross beta activity for each nuclear generating station. In addition, for Pickering NGS 'A', annual released of carbon-14 are depicted for the years 1986 and 1987. In each case the emission data are compared to the Derived Emission Limit (DEL) in order that the data may be placed in perspective. At present, only Pickering NGS 'A' is required to monitor and report carbon-14 emissions. Environmental monitoring for C-14 is conducted around the Bruce site to determine the environmental impact of its emission and whether effluent monitoring will be necessary in future years. Three nuclear generating stations have been permanently taken out of service during the last few years (Gentilly NGS-1, Douglas Point NGS and NPD NGS). Some small emissions from these sites do still occur, however, due to decontamination and decommissioning operations. (11 tabs., 26 figs.)

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

    International Nuclear Information System (INIS)

    Solomah, A.G.

    1984-01-01

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

  7. A guide to TIRION 4 - a computer code for calculating the consequences of releasing radioactive material to the atmosphere

    International Nuclear Information System (INIS)

    Fryer, L.S.

    1978-12-01

    TIRION 4 is the most recent program in a series designed to calculate the consequences of releasing radioactive material to the atmosphere. A brief description of the models used in the program and full details of the various control cards necessary to run TIRION 4 are given. (author)

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

    International Nuclear Information System (INIS)

    1975-07-01

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

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

    International Nuclear Information System (INIS)

    1975-01-01

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

  10. Spatiotemporal distribution of radioactive cesium released from Fukushima Daiichi Nuclear Power Station in the sediment of Tokyo Bay, Japan

    International Nuclear Information System (INIS)

    Nakagawa, Ryota; Ishida, Masanobu; Baba, Daisuke; Tanimoto, Satomi; Okamoto, Yuichi; Yamazaki, Hideo

    2013-01-01

    The spatial and temporal distribution of "1"3"4Cs and "1"3"7Cs released from Fukushima Daiichi Nuclear Power Station in the Tokyo Bay sediments were investigated. The total radioactivity of "1"3"4Cs and "1"3"7Cs detected in the Tokyo Bay sediment ranged from 240 to 870 Bq/kg-dry in the estuary of Arakawa River, but the activities detected in other sites were about 90 Bq/kg-dry or less. These results suggested that radioactive cesium, which precipitated to the ground, was carried to the river along with clay particles by rainfall and transported to the estuary. The vertical distribution of radioactive cesium showed that it invaded deeper than estimated based on the accumulation rate of the sediment. It was described that the vertical distribution of radioactive cesium was affected by physical mixing of sediments by tidal current, flood, and bioturbation of benthos. (author)

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

    International Nuclear Information System (INIS)

    1989-08-01

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

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

    International Nuclear Information System (INIS)

    Ahmed, J.U.

    1988-01-01

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

  13. Reconcentration of radioactive material released to sanitary sewers in accordance with 10 CFR Part 20

    International Nuclear Information System (INIS)

    Ainsworth, C.C.; Hill, R.L.; Cantrell, K.J.; Kaplan, D.I.; Norton, M.V.; Aaberg, R.L.; Stetar, E.A.

    1994-12-01

    The US Nuclear Regulatory Commission (NRC), in accordance with 10 CFR 20, and agreement states, in accordance with state regulations, regulates the discharge of radioactive materials into sanitary sewer systems. A one-year study was conducted by Pacific Northwest Laboratory (PNL) for the NRC to assess whether radioactive materials that are dischared to sanitary sewer systems undergo significant reconcentration within the wastewater treatment plants (WWTP) and to determine the physical and/or chemical processes that may result in radionuclide reconcentration within the WWTPs. The study objectives were addressed by collecting information and data on wastewater treatment, relevant geochemical processes, and individual radionuclide behavior in WWTPs from the open literature, NRC reports, EPA surveys, and interviews with NRC licensees and staff of WWTPs that may be impacted by these discharges. Radionuclide mass balance and removal efficiencies were calculated for WWTPs at Oak Ridge, TN; and Erwin, TN, but were not shown to be reliable since the licensee release data generally underestimated the mass of radionuclide that was ultimately found in the sludge. This disparity may be due, in part, to the fact that data available for use in this study were collected to address regulatory concerns and not to perform mass balance calculations. A limited modeling study showed some promise for predicting radionuclide behavior in WWTPS, however, the general applicability of using these empirical models remains uncertain. With the data and models currently available, it is not possible to quantitatively determine the physical and chemical processes that cause reconcentration or to calculate, a priori, reconcentration factors for specific WWTP unit processes or WWTPs in general

  14. Illustration of probabilistic approach in consequence assessment of accidental radioactive releases

    International Nuclear Information System (INIS)

    Pecha, P.; Hofman, R.; Kuca, P.

    2008-01-01

    We are describing a certain application of uncertainty analysis of environmental model HARP applied on atmospheric and deposition sub-model. Simulation of uncertainties propagation through the model is basic inevitable task bringing data for advanced techniques of probabilistic consequence assessment and further improvement of reliability of model predictions based on statistical procedures of assimilation with measured data. The activities are investigated in the institute IITA AV CR within the grant project supported by GACR (2007-2009). The problem is solved in close cooperation with section of information systems in institute NRPI. The subject of investigation concerns evaluation of consequences of radioactivity propagation after an accidental radioactivity release from nuclear facility.Transport of activity is studied from initial atmospheric propagation, deposition of radionuclides on terrain and spreading through food chains towards human body .Subsequent deposition processes of admixtures and food chain activity transport are modeled. In the final step a hazard estimation based on doses on population is integrated into the software system HARP. Extension to probabilistic approach has increased the complexity substantially, but offers much more informative background for modem methods of estimation accounting for inherent stochastic nature of the problem. Example of probabilistic assessment illustrated here is based on uncertainty analysis of input parameters of SGPM model. Predicted background field of Cs-137 deposition are labelled with index p. as P X SGPM . Final goal is estimation of a certain unknown true background vector χ true , which accounts also for deficiencies of the SGPM formulation in itself insisting in insufficient description of reality. We must have on mind, that even if we know true values of all input parameters θ m true (m= 1 ,..., M) of SGPM model, the χ true still remain uncertain. One possibility how to approach reality insists

  15. Illustration of probabilistic approach in consequence assessment of accidental radioactive releases

    International Nuclear Information System (INIS)

    Pecha, P.; Hofman, R.; Kuca, P.

    2009-01-01

    We are describing a certain application of uncertainty analysis of environmental model HARP applied on atmospheric and deposition sub-model. Simulation of uncertainties propagation through the model is basic inevitable task bringing data for advanced techniques of probabilistic consequence assessment and further improvement of reliability of model predictions based on statistical procedures of assimilation with measured data. The activities are investigated in the institute IITA AV CR within the grant project supported by GACR (2007-2009). The problem is solved in close cooperation with section of information systems in institute NRPI. The subject of investigation concerns evaluation of consequences of radioactivity propagation after an accidental radioactivity release from nuclear facility.Transport of activity is studied from initial atmospheric propagation, deposition of radionuclides on terrain and spreading through food chains towards human body .Subsequent deposition processes of admixtures and food chain activity transport are modeled. In the final step a hazard estimation based on doses on population is integrated into the software system HARP. Extension to probabilistic approach has increased the complexity substantially, but offers much more informative background for modem methods of estimation accounting for inherent stochastic nature of the problem. Example of probabilistic assessment illustrated here is based on uncertainty analysis of input parameters of SGPM model. Predicted background field of Cs-137 deposition are labelled with index p. as P X SGPM . Final goal is estimation of a certain unknown true background vector χ true , which accounts also for deficiencies of the SGPM formulation in itself insisting in insufficient description of reality. We must have on mind, that even if we know true values of all input parameters θ m true (m= 1 ,..., M) of SGPM model, the χ true still remain uncertain. One possibility how to approach reality insists

  16. Probabilistic siting analysis of nuclear power plants emphasizing atmospheric dispersion of radioactive releases and radiation-induced health effects

    International Nuclear Information System (INIS)

    Savolainen, Ilkka

    1980-01-01

    A presentation is made of probabilistic evaluation schemes for nuclear power plant siting. Effects on health attributable to ionizing radiation are reviewed, for the purpose of assessment of the numbers of the most important health effect cases in light-water reactor accidents. The atmospheric dispersion of radioactive releases from nuclear power plants is discussed, and there is presented an environmental consequence assessment model in which the radioactive releases and atmospheric dispersion of the releases are treated by the application of probabilistic methods. In the model, the environmental effects arising from exposure to radiation are expressed as cumulative probability distributions and expectation values. The probabilistic environmental consequence assessment model has been applied to nuclear power plant site evaluation, including risk-benefit and cost-benefit analyses, and the comparison of various alternative sites. (author)

  17. Screening calculations for radioactive waste releases from non-nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Shulan Xu; Soederman, Ann-Louis

    2009-02-15

    A series of screening calculations have been performed to assess the potential radiological consequences of discharges of radioactive substances to the environment arising from waste from non-nuclear practices. Solid waste, as well as liquids that are not poured to the sewer, are incinerated and ashes from incineration and sludge from waste water treatment plants are disposed or reused at municipal disposal facilities. Airborne discharges refer to releases from an incineration facility and liquid discharges refer both to releases from hospitals and laboratories to the sewage system, as well as leakage from waste disposal facilities. The external exposure of workers is estimated both in the waste water treatment plant and at the disposal facility. The calculations follow the philosophy of the IAEA's safety guidance starting with a simple assessment based on very conservative assumptions which may be iteratively refined using progressively more complex models, with more realistic assumptions, as necessary. In the assessments of these types of disposal, with cautious assumptions, carried out in this report we conclude that the radiological impacts on representative individuals in the public are negligible in that they are small with respect to the target dose of 10 muSv/a. A Gaussian plume model was used to estimate the doses from airborne discharges from the incinerator and left a significant safety margin in the results considering the conservative assumptions in the calculations. For the sewage plant workers the realistic approach included a reduction in working hours and the shorter exposure time resulted in maximum doses around 10 muSv/a. The calculations for the waste disposal facility show that the doses are higher or in the range of the target dose. The excess for public exposure is mainly caused by H-3 and C-14. The assumption used in the calculation is that all of the radioactive substances sent to the incineration facility and waste water treatment

  18. Source term estimation and the isotopic ratio of radioactive material released from the WIPP repository in New Mexico, USA

    International Nuclear Information System (INIS)

    Thakur, P.

    2016-01-01

    After almost 15 years of operations, the Waste Isolation Pilot Plant (WIPP) had one of its waste drums breach underground as a result of a runaway chemical reaction in the waste it contained. This incident occurred on February 14, 2014. Moderate levels of radioactivity were released into the underground air. A small portion of the contaminated underground air also escaped to the surface through the ventilation system and was detected approximately 1 km away from the facility. According to the source term estimation, the actual amount of radioactivity released from the WIPP site was less than 1.5 mCi. The highest activity detected on the surface was 115.2 μBq/m 3 for 241 Am and 10.2 μBq/m 3 for 239+240 Pu at a sampling station located 91 m away from the underground air exhaust point and 81.4 μBq/m 3 of 241 Am and 5.8 μBq/m 3 of 239+240 Pu at a monitoring station located approximately 1 km northwest of the WIPP facility. The dominant radionuclides released were americium and plutonium, in a ratio that matches the content of the breached drum. Air monitoring across the WIPP site intensified following the first reports of radiation detection underground to determine the extent of impact to WIPP personnel, the public, and the environment. In this paper, the early stage monitoring data collected by an independent monitoring program conducted by the Carlsbad Environmental Monitoring & Research Center (CEMRC) and an oversight monitoring program conducted by the WIPP's management and operating contractor, the Nuclear Waste Partnership (NWP) LLC were utilized to estimate the actual amount of radioactivity released from the WIPP underground. The Am and Pu isotope ratios were measured and used to support the hypothesis that the release came from one drum identified as having breached that represents a specific waste stream with this radionuclide ratio in its inventory. This failed drum underwent a heat and gas producing reaction that overpowered its vent and

  19. A high-performance liquid chromatography method for the serotonin release assay is equivalent to the radioactive method.

    Science.gov (United States)

    Sono-Koree, N K; Crist, R A; Frank, E L; Rodgers, G M; Smock, K J

    2016-02-01

    The serotonin release assay (SRA) is considered the gold standard laboratory test for heparin-induced thrombocytopenia (HIT). The historic SRA method uses platelets loaded with radiolabeled serotonin to evaluate platelet activation by HIT immune complexes. However, a nonradioactive method is desirable. We report the performance characteristics of a high-performance liquid chromatography (HPLC) SRA method. We validated the performance characteristics of an HPLC-SRA method, including correlation with a reference laboratory using the radioactive method. Serotonin released from reagent platelets was quantified by HPLC using fluorescent detection. Results were expressed as % release and classified as positive, negative, or indeterminate based on previously published cutoffs. Serum samples from 250 subjects with suspected HIT were tested in the HPLC-SRA and with the radioactive method. Concordant classifications were observed in 230 samples (92%). Sera from 41 healthy individuals tested negative. Between-run imprecision studies showed standard deviation of performance characteristics, equivalent to the historic radioactive method, but avoids the complexities of working with radioactivity. © 2015 John Wiley & Sons Ltd.

  20. Determination of safe radioactive releases to the atmosphere from the nuclear power site, Dynefontein

    International Nuclear Information System (INIS)

    Basson, J.K.; Van As, D.

    1976-01-01

    South Africa's first nuclear power station, Koeberg A, is to be built by Escom at Dynefontein, 28 km north of Cape Town, and the experience gained at the National Nuclear Research Centre, Pelindaba, has been used by the AEB as basis for the pre-operational investigation. The capacity of the environment to accept airborne radioactive effluent safely depends on various local factors such as dispersion conditions, the ecology, the habits of the local population and the accumulation, through critical pathways, of pertinent radionuclides. Long-term average dilution factors at varying distances from a 100m stack have been calculated by ESCOM from mesometeorological data collected by the CSIR. On the basis of available data, permissible release rates are derived for radioisotopes of the noble gases (critical pathway:external cloud exposure), 131 I, 137 Cs, 106 Ru, 125 Sb and 114 Ce and tritium. Although final confirmation of these values can only be obtained after operation, such a pre-operational survey may serve as an example to conventional industry [af

  1. Aerial spraying to capture released radioactivity from NPP in a severe accident

    Energy Technology Data Exchange (ETDEWEB)

    Younus, Irfan; Yim, Man Sung [KAIST, Daejeon (Korea, Republic of); Medard, Thiphaine [Ecole des Mines de Saint-Etienne, Daejeon (Korea, Republic of)

    2016-05-15

    The proposed strategy in this paper is the use of aqueous spray (water/foam) mixed with suitable chemical additives to capture, dissolve and stabilize the radioactive gases and aerosol particles released from leaked reactor containment and auxiliary building. The spray system can be approached to the leaked reactor building through the use of a truck with high rising cranes, unmanned aerial vehicles (UAVs, such as helicopters), aerostats, or by installing fixed piping structure around the containment building depending on the accident situation. Laboratory-scale experimental system was setup to examine the performance of such systems. The alkaline water (aqueous NaOH.Na{sub 2}S{sub 2}O{sub 3}) and foam-based spray material (sodium lauryl sulphate) were used to examine capture efficiency of gaseous iodine and aerosol particles. The gaseous iodine and aerosol removal efficiency of foam-based spray is higher when compared with alkaline water-based spray. 2. The nozzle producing full cone spray provides the better removal efficiency than nozzle producing hollow cone spray patterns.

  2. Aerial spraying to capture released radioactivity from NPP in a severe accident

    International Nuclear Information System (INIS)

    Younus, Irfan; Yim, Man Sung; Medard, Thiphaine

    2016-01-01

    The proposed strategy in this paper is the use of aqueous spray (water/foam) mixed with suitable chemical additives to capture, dissolve and stabilize the radioactive gases and aerosol particles released from leaked reactor containment and auxiliary building. The spray system can be approached to the leaked reactor building through the use of a truck with high rising cranes, unmanned aerial vehicles (UAVs, such as helicopters), aerostats, or by installing fixed piping structure around the containment building depending on the accident situation. Laboratory-scale experimental system was setup to examine the performance of such systems. The alkaline water (aqueous NaOH.Na_2S_2O_3) and foam-based spray material (sodium lauryl sulphate) were used to examine capture efficiency of gaseous iodine and aerosol particles. The gaseous iodine and aerosol removal efficiency of foam-based spray is higher when compared with alkaline water-based spray. 2. The nozzle producing full cone spray provides the better removal efficiency than nozzle producing hollow cone spray patterns.

  3. Interleukin-2 stimulates osteoclastic activity: Increased acid production and radioactive calcium release

    International Nuclear Information System (INIS)

    Ries, W.L.; Seeds, M.C.; Key, L.L.

    1989-01-01

    Recombinant human interleukin-2 (IL-2) was studied to determine effects on acid production by individual osteoclasts in situ on mouse calvarial bones. This analysis was performed using a microspectrofluorimetric technique to quantify acid production in individual cells. Radioactive calcium release was determined using calvarial bones in a standard tissue culture system. This allowed us to correlate changes in acid production with a measure of bone resorption. IL-2 stimulated acid production and bone resorbing activity. Both effects were inhibited by calcitonin. No stimulation of bone resorption occurred when IL-2-containing test media was incubated with a specific anti-IL-2 antibody and ultrafiltered. Our data demonstrated a correlation between acid production and bone resorbing activity in mouse calvaria exposed to parathyroid hormone (PTH). The data obtained from cultured mouse calvaria exposed to IL-2 demonstrated similar stimulatory effects to those seen during PTH exposure. These data suggest that calvaria exposed to IL-2 in vitro have increased osteoclastic acid production corresponding with increased bone resorption. (author)

  4. Isopleths of surface concentration and surface exposure rate due to a radioactive cloud released from a stack

    International Nuclear Information System (INIS)

    Kobayashi, Hideo; Yabuta, Hajimu; Katagiri, Hiroshi; Obata, Kazuichi; Kokubu, Morinobu

    1982-03-01

    Various calculations are made to estimate the distributions of concentration and γ-exposure rate due to a radioactive cloud released from a point source to the atmosphere. In this report, the isopleths of concentration and γ-exposure rate which were calculated are given in graphs to enable rapid prediction of the influence of released radioactive material in the emergency situation. Recently there are facilities which are equipped with a system to display the calculation results on CRT; but such practice is rather rare. By placing the calculated isopleths of reduction scale 1/25000 or 1/50000 on the usual map, any facilities without the CRT system can readily estimate the influence of an accidental release. The graphs of isopleths are given with the release height (11 values of 0 to 200 m at about 20 m intervals) and the atmospheric stability (6 classes) as parameters. Calculations of γ-exposure rates were made using the computer code GAMPUL developed by T. Hayashi and T. Shiraishi. In the calculation of radioactive concentrations and γ-exposure rates, the vertical diffusion depths, σsub(z), exceeding 1000 m are taken to be 1000 m according to the Meteorological Guide for the Safety Analysis of Power Reactor (J.AEC). The comparison between with and without this limitation in σsub(z) is made in the case of downwind axial surface distributions. (author)

  5. Radioactivity

    International Nuclear Information System (INIS)

    Chelet, Y.

    2006-01-01

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

  6. Radioactivity

    International Nuclear Information System (INIS)

    2002-01-01

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

  7. Impact on the marine environment of radioactive releases resulting from the Fukushima-Daiichi nuclear accident. May 13, 2011

    International Nuclear Information System (INIS)

    2011-01-01

    This information note updates and supplements the previous note of 4 April on the same subject. It describes the origins of the contamination of the marine environment (Direct releases into the sea close to the damaged reactors, atmospheric fall-out onto the surface of the sea, transport of radioactive pollution by leaching of contaminated soil). Then, while proposing several maps, the authors analyse and comment the dispersion in the sea of radioactive pollutants: ocean currents off the Japanese coasts, charts showing the distribution of caesium 137 in seawater, and results of simulations of dispersion. The report briefly discusses the impact of radioactive pollution on living species: concentrations observed in fish, expected concentrations based on the seawater measurements. Finally, it briefly discusses the presence of radionuclides in sediments

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

    International Nuclear Information System (INIS)

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

    1978-12-01

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

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

    International Nuclear Information System (INIS)

    Miller, S.R.

    1987-01-01

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

  10. Formulation and evaluation of gas release scenarios for the silo in Swedish Final Repository for Radioactive Waste (SFR)

    International Nuclear Information System (INIS)

    Carlsson, J.; Moreno, L.

    1992-01-01

    The Swedish Final Repository for Radioactive Waste (SFR) has been in operation since 1988 and is located in the crystalline rock, 60 m below the Baltic Sea. In the licensing procedure for the SFR the safety assessment has been complemented with a detailed scenario analysis of the performance of the repository. The scenarios include the influence on radionuclide release by gas formation and gas transport processes in the silo. The overall conclusion is that the release of most radionuclides from the silo is only marginally affected by the formation and release of gas, even for scenarios considering unexpected events. The largest effects were found for short-lived radionuclides and radionuclides that have no or low sorption ability. Except for very extreme scenarios for the silo the overall impact from repository on the environment is by far dominated by the release of radionuclides from the rock vaults. 10 refs., 6 figs

  11. Impacts of accidental radioactive releases to the hydrosphere from floating and land-based nuclear power plants

    International Nuclear Information System (INIS)

    Vollmer, R.H.

    1978-01-01

    To assess the impacts of accidental radioactive releases to the hydrosphere from floating and land-based nuclear power plants, the Liquid Pathway Generic Study was initiated. The objective of this study was to compare the risks associated with releases through the liquid pathway from accidents that may reasonably be expected and those that are very improbable. Consequences were estimated in terms of radiation dose to man from drinking water ingestion, shell-fish and fish flesh consumption, and direct exposure (swimming, beach) as well as long-term effects, such as genetic effects or aquatic species degradation. (author)

  12. Manufacturing and test of a low cost polypropylene bag to reduce the radioactive gas released by a radiopharmaceutical production facility

    Energy Technology Data Exchange (ETDEWEB)

    Tavares, Jose Carlos Freitas; Lacerda, Marco Aurelio de Sousa, E-mail: jcft@cdtn.b, E-mail: masl@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (SEPRA/ CDTN/CNEN-MG) Belo Horizonte, MG (Brazil). Servico de Protecao Radiologica; Nascimento, Leonardo Tafas Constantino do; Silva, Juliana Batista da, E-mail: ltcn@cdtn.b, E-mail: silvajb@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (SECPRA/ CDTN/CNEN-MG) Belo Horizonte, MG (Brazil). Secao de Producao de Radiofarmacos

    2011-07-01

    The main objective of this work was to evaluate the efficiency of a plastic gas storage bag to reduce the radioactive gas released by the chimney of a radiopharmaceutical production facility during the 2-[{sup 18}F]fluoro-2- deoxy-D-glucose ({sup 18}FDG) synthesis. The studied facility was the Development Centre of Nuclear Technology (CDTN/CNEN) in Belo Horizonte, Brazil. The bag was manufactured utilizing foils of polypropylene of 360 x 550 x 0.16 mm and disposable components of the cassette of the synthesizer. Two synthesis of {sup 18}FDG were done using the same hot cell and synthesizer to evaluate the efficiency of the bag. The manufactured bag was put in the gas exit of the synthesizer and the activity reported by the online radiation monitoring system in the first synthesis. These results were compared to the activity released in a synthesis performed without the bag. We observed when the bag was used the amount released was about 0.2% in 270 minutes. The second synthesis was performed without the bag, about 7,1% of the input activity was released by the exhaust of the facility in the same time interval. The bag presented a very good efficiency in the reducing of the radioactive gas released by the chimney of the radiopharmaceutical production facility. (author)

  13. Manufacturing and test of a low cost polypropylene bag to reduce the radioactive gas released by a radiopharmaceutical production facility

    International Nuclear Information System (INIS)

    Tavares, Jose Carlos Freitas; Lacerda, Marco Aurelio de Sousa; Nascimento, Leonardo Tafas Constantino do; Silva, Juliana Batista da

    2011-01-01

    The main objective of this work was to evaluate the efficiency of a plastic gas storage bag to reduce the radioactive gas released by the chimney of a radiopharmaceutical production facility during the 2-[ 18 F]fluoro-2- deoxy-D-glucose ( 18 FDG) synthesis. The studied facility was the Development Centre of Nuclear Technology (CDTN/CNEN) in Belo Horizonte, Brazil. The bag was manufactured utilizing foils of polypropylene of 360 x 550 x 0.16 mm and disposable components of the cassette of the synthesizer. Two synthesis of 18 FDG were done using the same hot cell and synthesizer to evaluate the efficiency of the bag. The manufactured bag was put in the gas exit of the synthesizer and the activity reported by the online radiation monitoring system in the first synthesis. These results were compared to the activity released in a synthesis performed without the bag. We observed when the bag was used the amount released was about 0.2% in 270 minutes. The second synthesis was performed without the bag, about 7,1% of the input activity was released by the exhaust of the facility in the same time interval. The bag presented a very good efficiency in the reducing of the radioactive gas released by the chimney of the radiopharmaceutical production facility. (author)

  14. Human exposure to radiation following the release of radioactivity from a reactor accident: a quantitative assessment of the biological consequences

    International Nuclear Information System (INIS)

    Smith, H.; Stather, J.W.

    1976-11-01

    The objective of this review is to provide a biological basis upon which to assess the consequences of the exposure of a population to radioactivity released after a reactor accident. Depending upon the radiation dose, both early and late somatic damage could occur in the exposed population and hereditary effects may occur in their descendants. The development of dose-effect relationships has been based upon the limited amount of information available on humans, supplemented by data obtained from experiments on animals. (author)

  15. Atmospheric plume progression as a function of time and distance from the release point for radioactive isotopes.

    Science.gov (United States)

    Eslinger, Paul W; Bowyer, Ted W; Cameron, Ian M; Hayes, James C; Miley, Harry S

    2015-10-01

    The radionuclide network of the International Monitoring System comprises up to 80 stations around the world that have aerosol and xenon monitoring systems designed to detect releases of radioactive materials to the atmosphere from nuclear explosions. A rule of thumb description of plume concentration and duration versus time and distance from the release point is useful when designing and deploying new sample collection systems. This paper uses plume development from atmospheric transport modeling to provide a power-law rule describing atmospheric dilution factors as a function of distance from the release point. Consider the plume center-line concentration seen by a ground-level sampler as a function of time based on a short-duration ground-level release of a nondepositing radioactive tracer. The concentration C (Bq m(-3)) near the ground varies with distance from the source with the relationship C=R×A(D,C) ×e (-λ(-1.552+0.0405×D)) × 5.37×10(-8) × D(-2.35) where R is the release magnitude (Bq), D is the separation distance (km) from the ground level release to the measurement location, λ is the decay constant (h(-1)) for the radionuclide of interest and AD,C is an attenuation factor that depends on the length of the sample collection period. This relationship is based on the median concentration for 10 release locations with different geographic characteristics and 365 days of releases at each location, and it has an R(2) of 0.99 for 32 distances from 100 to 3000 km. In addition, 90 percent of the modeled plumes fall within approximately one order of magnitude of this curve for all distances. Copyright © 2015 Elsevier Ltd. All rights reserved.

  16. Proposal of the concept of selection of accidents that release large amounts of radioactive substances in the high temperature engineering test reactor

    International Nuclear Information System (INIS)

    Ono, Masato; Honda, Yuki; Takada, Shoji; Sawa, Kazuhiro

    2015-01-01

    In Position, construction and equipment of testing and research reactor to be subjected to the use standards for rules Article 53 (prevention of expansion of the accident to release a large amount of radioactive material) generation the frequency is a lower accident than design basis accident, when what is likely to release a large amount of radioactive material or radiation from the facility has occurred, and take the necessary measures in order to prevent the spread of the accident. There is provided a lower accident than frequency design basis accidents, for those that may release a large amount of radioactive material or radiation. (author)

  17. 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

  18. Development of an air flow calorimeter prototype for the measurement of thermal power released by large radioactive waste packages.

    Science.gov (United States)

    Razouk, R; Beaumont, O; Failleau, G; Hay, B; Plumeri, S

    2018-03-01

    The estimation and control of the thermal power released by the radioactive waste packages are a key parameter in the management of radioactive waste geological repository sites. In the framework of the European project "Metrology for decommissioning nuclear facilities," the French National Agency of Radioactive Waste Management (ANDRA) collaborates with Laboratoire National de Métrologie et D'essais in order to measure the thermal power up to 500 W of typical real size radioactive waste packages (of at least 0.175 m 3 ) with an uncertainty better than 5% by using a measurement method traceable to the international system of units. One of the selected metrological approaches is based on the principles of air flow calorimetry. This paper describes in detail the development of the air flow calorimeter prototype as well as the design of a radioactive waste package simulator used for its calibration. Results obtained from the calibration of the calorimeter and from the determination of thermal powers are presented here with an investigation of the measurement uncertainties.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-12-15

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

  20. Development of an air flow calorimeter prototype for the measurement of thermal power released by large radioactive waste packages

    Science.gov (United States)

    Razouk, R.; Beaumont, O.; Failleau, G.; Hay, B.; Plumeri, S.

    2018-03-01

    The estimation and control of the thermal power released by the radioactive waste packages are a key parameter in the management of radioactive waste geological repository sites. In the framework of the European project "Metrology for decommissioning nuclear facilities," the French National Agency of Radioactive Waste Management (ANDRA) collaborates with Laboratoire National de Métrologie et D'essais in order to measure the thermal power up to 500 W of typical real size radioactive waste packages (of at least 0.175 m3) with an uncertainty better than 5% by using a measurement method traceable to the international system of units. One of the selected metrological approaches is based on the principles of air flow calorimetry. This paper describes in detail the development of the air flow calorimeter prototype as well as the design of a radioactive waste package simulator used for its calibration. Results obtained from the calibration of the calorimeter and from the determination of thermal powers are presented here with an investigation of the measurement uncertainties.

  1. Barriers to communication and cooperation in addressing community impacts of radioactive releases from research facilities

    International Nuclear Information System (INIS)

    Harrach, R J; Peterson, S.

    1999-01-01

    Two instances of research facilities responding to public scrutiny will be discussed. The first concerns emissions from a tritium labeling facility operated at Lawrence Berkeley National Laboratory (LBNL); the second deals with releases of plutonium from Lawrence Livermore National Laboratory (LLNL). There are many parallels between these two cases, both of which are still ongoing. In both, the national laboratory is the acknowledged source of low-level (by regulatory standards) radioactive contamination in the community. A major purpose of both investigations is to determine the degree of the contamination and the threat it poses to public health and the environment. The examining panel or committee is similarly constituted in the two cases, including representatives from all four categories of stakeholders: decision makers; scientists and other professionals doing the analysis/assessment; environmental activist or public interest groups; and ordinary citizens (nearly everyone else not in one or more of the first three camps). Both involved community participation from the beginning. The levels of outrage over the events triggering the assessment are comparable; though discovered or appreciated only a few years ago, the release of radiation in both cases occurred or began occurring more than a decade ago. The meetings have been conducted in a similar manner, with comparable frequency, often utilizing the services of professional facilitators. In both cases, the sharply contrasting perceptions of risk commonly seen between scientists and activists were present from the beginning, though the contrast was sharper and more problematical in the Berkeley case. Yet, the Livermore case seems to be progressing towards a satisfactory resolution, while the Berkeley case remains mired in ill-will, with few tangible results after two years of effort. We perceive a wide gap in negotiation skills (at the very least), and a considerable difference in willingness to compromise

  2. Complete release from regulatory control via the density of radioactive contamination of soil of the Chornobyl exclusion zone

    International Nuclear Information System (INIS)

    Bondarenko, Oleg; Fadeev, Mykhaylo; Kireev, Serhiy; Proskura, Mykola

    2008-01-01

    Full text: In this work a general procedure of establishment the criterion of complete release from regulatory control via the density of radioactive contamination of soil of alone areas of the Chornobyl exclusion zone is represented by the following three stages, namely: 1) Justification of the dose criterion of complete release by applying the fundamental approaches of regulating the prolonged exposure of the public on a basement of ICRP Publication No. 82; 2) Justification of a procedure for establishment of dose constraint through evaluation of the statistical distribution of a controlled radiation value through determination of the high boundary of the confidence interval; 3) Generalization of conversion coefficients (via the density of radioactive contamination of soil) and coverage coefficients for the dose forming factors of the public (inhalation intake of transuranium radionuclides both at natural and technogenic dust resuspension, peroral intake of 137 Cs and 90 Sr via food stuff, external exposure from 137 Cs); on a basis of these coefficients average doses and dose constraint of a critical group of the public are calculated. As it is shown in the work, the generalized criterion of complete release from regulatory control via the density of radioactive contamination of soil of the Chornobyl exclusion zone can be defined by dividing the recommended ICRP dose clearance level for situation of the post-accidental prolonged exposure of a critical group of the public, namely, 0.3 mSv·year -1 to the dose conversion coefficient (i.e. transfer from the superficial soil contamination of radioactivity to the dose constraint for the Chornobyl exclusion zone), namely, 12.9 μSv·year -1 /((kBq·M -2 ). Thus, a level of the density of radioactive contamination of soil, that provides the complete release from regulatory control makes 23.3 kBq·M -2 . For completion of the work on justification of the criterion of complete territory release in the conditions of

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

    International Nuclear Information System (INIS)

    2003-01-01

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

  4. Rates and mechanisms of radioactive release and retention inside a waste disposal canister - in Can Processes

    Energy Technology Data Exchange (ETDEWEB)

    Oversby, V.M. (ed.) [and others

    2003-10-01

    the system that will not be present under long term disposal conditions. A simulation of long-term conditions can be done using uranium dioxide that contains a short-lived isotope of uranium, but this will not include the effects of fission product and higher actinide elements on the behaviour of the spent fuel. We designed a project that had as its objective to improve the scientific understanding of the processes that control release of radioactive species from spent fuel inside a disposal canister and the chemical changes in those species that might limit release of radioactivity from the canister. If the mechanisms that control dissolution of the fuel matrix, including self-irradiation effects, can be clarified, a more realistic assessment of the long-term behaviour of spent fuel under disposal conditions can be made. By removing uncertainties concerning waste form performance, a better assessment of the individual and collective role of the engineered barriers can be made. To achieve the overall objective of the project, the following scientific and technical objectives were set. 1. Measure the actual rate of matrix dissolution of uranium dioxide under oxidising and reducing conditions. 2. Measure the effect of alpha radiolysis on the dissolution rate of uranium dioxide under oxidising and reducing conditions. 3. Measure the dissolution rate of the matrix material of spent fuel and thereby determine the additional effects of beta and gamma radiation on uranium dioxide dissolution rate under oxidising and reducing conditions. 4. Measure the ability of actively corroding iron to reduce oxidised U(VI) to U(IV) when U is present as the complex ion uranyl carbonate. 5. Measure the rate of reduction of Np(V) species in the presence of actively corroding iron. 6. Calculate the expected equilibrium and steady state concentrations of U under the conditions of the experiments used for meeting objectives 1 through 3 and compare the calculated results with those measured in

  5. Influence of the conditional release of the materials with very low level of radioactivity on the environment - 59132

    International Nuclear Information System (INIS)

    Prvakova, Slavka; Mrskova, Adela; Pritrsky, Jozef

    2012-01-01

    Significant amount of solid materials (metals, non-metals, building structures) that could be contaminated or activated is produced during operation and especially decommissioning of nuclear power plants. Considerable fraction of these materials has level of radioactivity close to the radiological limits allowing its safe release into the environment thereby could be potentially recycled within the special constructions, as for example tunnels, roads or bridges. If the requirements of legislation on the radiological limits for handling such material and long-term safety of the constructions are met, contaminated material can be incorporated in the form of recycled concrete, remelted steel, etc. The paper presents implementation of the IAEA and EC recommendations into the form of detailed analytical approaches with the aim to develop integrated scenarios and to analyse long-term influence of the conditional release of the material with very low level of radioactivity on the environment. Further, an estimation of the key input parameters characteristic for the specific conditions of Slovak case in order to fulfil the radiological limits according to the Slovak legislation is included. Analysed integrated scenarios represent surface or underground civil construction with radionuclides released directly into the geosphere and transported by a groundwater flow to the biosphere. The migration of radionuclides is modelled in the near-surface conditions with the advection as a dominant transport mechanism. Computer code GoldSim is used to evaluate the long-term safety assessment of the conditionally released material on the environment. (authors)

  6. Standard guide for radioactive pathway methodology for release of sites following decommissioning

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    The purpose of this guide is to provide guidance in determining site-specific conversion factors for translating between dose limits and residual radioactive contamination levels on equipment structures, and land areas. This guide is to serve as a guide to acceptable methodology for translating the yet to be determined dose limits into allowable levels of residual radioactive materials that can be left at a site following decommissioning

  7. Geographical distribution of radioactive nuclides released from the Fukushima Daiichi Nuclear Power Station accident in eastern Japan

    International Nuclear Information System (INIS)

    Ishida, Masanobu; Umetsu, Kohei; Sugimoto, Miyabi; Yamaguchi, Yuta; Yamazaki, Hideo; Nakagawa, Ryota

    2013-01-01

    The geographical distribution of radioactive nuclides released from the Fukushima Daiichi Nuclear Power Station accident in metropolitan areas located in eastern Japan was investigated. The radioactive contamination of environmental samples, including soil and biological materials, was analyzed. The concentrations of 131 I, 134 Cs, and 137 Cs in the soil samples collected from Fukushima City were 122000, 11500 and 14000 Bq/kg on 19th March 2011 and 129000, 11000 and 13700 Bq/kg on 26th March 2011, for the three nuclides respectively. The concentrations of 131 I, 134 Cs and 137 Cs in the soil samples collected from March-June 2011 from study sites ranged from 240 to 101000, 28 to 26200, and 14 to 33700 Bq/kg, respectively. In Higashiosaka City, it began to detect those radioactive nuclides in the atmospheric airborne dust from 25th March. Radioactive fission products 95 Zr- 95 Nb were detected on 18th April 2011. Biological samples collected from Tokyo Bay were studied. The maximum concentrations of 134 Cs and 137 Cs detected in the biological samples were 12.2 and 19.2 Bq/kg, which were measured in goby. 131 I was not detected in the biological samples however, trace amounts of the short half-life nuclide 110m Ag were found in the shellfish samples. (author)

  8. A computer code to estimate accidental fire and radioactive airborne releases in nuclear fuel cycle facilities: User's manual for FIRIN

    International Nuclear Information System (INIS)

    Chan, M.K.; Ballinger, M.Y.; Owczarski, P.C.

    1989-02-01

    This manual describes the technical bases and use of the computer code FIRIN. This code was developed to estimate the source term release of smoke and radioactive particles from potential fires in nuclear fuel cycle facilities. FIRIN is a product of a broader study, Fuel Cycle Accident Analysis, which Pacific Northwest Laboratory conducted for the US Nuclear Regulatory Commission. The technical bases of FIRIN consist of a nonradioactive fire source term model, compartment effects modeling, and radioactive source term models. These three elements interact with each other in the code affecting the course of the fire. This report also serves as a complete FIRIN user's manual. Included are the FIRIN code description with methods/algorithms of calculation and subroutines, code operating instructions with input requirements, and output descriptions. 40 refs., 5 figs., 31 tabs

  9. Effect of the alkaloid (-)cathinone on the release of radioactivity from rabbit atria prelabelled with 3H-norepinephrine

    International Nuclear Information System (INIS)

    Kalix, P.

    1983-01-01

    In certain countries of East Africa and the Arab Peninsula, fresh leaves of the khat shrub are used as a stimulant. The effect of the plant material can be explained by the presence of the phenylalklamine alkaloid (-)cathinone in the leaves, since this substance has been shown to have an amphetamine-like releasing effect on CNS tissue prelabelled with 3 H-dopamine. Characteristically, the chewing of khat is accompanied by sympathomimetic effects, especially at the cardiovascular level. To test whether these might be due to release of neurotransmitter from adrenergic nerve endings, the effect of (-)cathinone on the efflux of radioactivity from isolated rabbit atrium tissue prelabelled with 3 H-norepinephrine was investigated. It was found that, at concentrations below 1 μM, (-)cathinone caused an immediate increase of efflux. The effect was dose-dependent and was potentiated by pretreatment of the rabbits with reserpine. Preincubation of the tissue with desipramine and cocaine prevented the induction of release by (-)cathinone. The results indicate that the alkaloid (-)cathinone has an amphetamine-like releasing effect on noradrenergic nerve endings and they suggest that the cardiovascular symptoms observed during khat consumption are due to release of neurotransmitter from physiologicl storage sites

  10. Evaluation of food contamination and health risks caused by radioactive fallout released from atmospheric nuclear detonation tests

    International Nuclear Information System (INIS)

    Shimada, Yoko; Ito, Yoshihiko; Yoneda, Minoru; Morisawa, Shinsuke

    2011-01-01

    Before Fukushima Daiichi nuclear disaster, radionuclide like 137 Cs released from atmospheric nuclear detonation tests and Chernobyl disaster has been transported worldwide in the environment and finally taken up by humans through various pathways. In this research, dietary intake of 137 Cs and the related health risks to Japanese caused by chronic global radioactive food contamination from 1945 to 2010 were evaluated by using the mathematical model for the evaluation of global distribution of 137 Cs with food ingestion and domestic and international food supply model. The results of this evaluation can show a background situation before Fukushima disaster and give important information for the risk assessment of this disaster. (author)

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

    International Nuclear Information System (INIS)

    Filipiak, B.; Nowicki, K.

    1979-01-01

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

  12. Isopleths of surface air concentration and surface air kerma rate due to a radioactive cloud released from a stack (3)

    International Nuclear Information System (INIS)

    Tachibana, Haruo; Kikuchi, Masamitsu; Sekita, Tsutomu; Yamaguchi, Takenori

    2004-06-01

    This report is a revised edition of 'Isopleths of Surface Air Concentration and Surface Air Absorbed Dose Rate due to a Radioactive Cloud Released from a Stack(II) '(JAERI-M 90-206) and based on the revised Nuclear Safety Guidelines reflected the ICRP1990 Recommendation. Characteristics of this report are the use of Air Karma Rate (Gy/h) instead of Air Absorbed Dose Rate (Gy/h), and the record of isopleths of surface air concentration and surface air karma rate on CD-ROM. These recorded data on CD-ROM can be printed out on paper and/or pasted on digital map by personal computer. (author)

  13. Barriers of repository under the conditions of underground isolation of heat releasing radioactive waste in permafrost

    International Nuclear Information System (INIS)

    Kazakov, A.N.; Fedorovich, L.N.

    1995-01-01

    The main positions and the leading principle of the ensuring of the environmental safety of the method of the underground isolation of radioactive waste in permafrost rock are presented in this work and it is shown here the peculiarities in realization of the principle of the multibarrier protection. It is substantiated here the principle of the optimal time of the capacity for work of the repository's engineered barriers. The possibility of the exclusion of the radionuclides migration beyond the working volume of the repository during the time of the potential danger of radioactive waste is also substantiated in these papers

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

    International Nuclear Information System (INIS)

    1988-01-01

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

  15. Release of radioactive materials in simulation test of a postulated solvent fire in a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Nishio, G.; Hashimoto, K.

    1989-01-01

    This paper reports on small- and large-scale fire tests performed to examine the adequacy of a safety evaluation method for a solvent fire in the extraction process of a nuclear fuel reprocessing plant. The test objectives were to obtain information on the confinement of radioactive materials during a 30% tri-n-butyl phosphate-n-dodecane fire while air ventilation is operating in the cell. The rates of release of cesium, strontium, cerium, ruthenium, and uranium from a burning solvent were determined. The quantities of species released were obtained from the solvent burning rate, smoke generation rate, partition coefficients of species between solvent and water, and coefficients of species entrainment to atmosphere in cell

  16. A comparison of alternative methods of calculating complementary cumulative distribution functions of health effects following an atmospheric radioactive release

    International Nuclear Information System (INIS)

    Ponting, A.C.; Nair, S.

    1984-04-01

    A concept extensively used in studying the consequences of accidental atmospheric radioactive releases is that of the Complementary Cumulative Distribution Function, CCDF. Various methods of calculating CCDFs have been developed with particular applications in putting degraded core accidents in perspective and in identifying release sequences leading to high risks. This note compares three methods with specific reference to their accuracy and computational efficiency. For two of the methods (that used in the US Reactor Safety Study code CRAC2 and extended version of that method), the effects of varying the sector width and considering site-specific population distributions have been determined. For the third method it is only necessary to consider the effects of site-specific population distributions. (author)

  17. A separate effect study of the influence of metallic fission products on CsI radioactive release from nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Di Lemma, F.G., E-mail: fidelma.dilemma@gmail.com [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, 76125 Karlsruhe (Germany); Department of Radiation Science and Technology, Faculty of Applied Sciences, Delft University of Technology, Delft, 2629 JB (Netherlands); Colle, J.Y., E-mail: jean-yves.colle@ec.europa.eu [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, 76125 Karlsruhe (Germany); Beneš, O. [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, 76125 Karlsruhe (Germany); Konings, R.J.M. [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, 76125 Karlsruhe (Germany); Department of Radiation Science and Technology, Faculty of Applied Sciences, Delft University of Technology, Delft, 2629 JB (Netherlands)

    2015-10-15

    The chemistry of cesium and iodine is of main importance to quantify the radioactive release in case of a nuclear reactor accident, or sabotage involving irradiated nuclear materials. We studied the interaction of CsI with different metallic fission products such as Mo and Ru. These elements can be released from nuclear fuel when exposed to oxidising conditions, as in the case of contact of overheated nuclear fuel with air (e.g. in a spent fuel cask sabotage, uncovering of a spent fuel pond, or air ingress accidents). Experiments were performed by vaporizing mixtures of the compounds in air, and analysing the produced aerosols in view of a possible gas–gas and gas–aerosol reactions between the compounds. These results were compared with the gaseous species predicted by thermochemical equilibrium calculations and experimental equilibrium vaporization tests using Knudsen Effusion Mass Spectrometry.

  18. Release studies of a thin foil tantalum target for the production of short-lived radioactive nuclei

    CERN Document Server

    Bennett, J R J; Drumm, P V; Lettry, Jacques; Nilsson, T; Catherall, R; Jonsson, O C; Ravn, H L; Simon, H

    2002-01-01

    Measurements have been made at ISOLDE, of the release curves and yields of radioactive beams of lithium, sodium and beryllium from a target constructed from 2 $\\mu$m thick foils. The release curves have been analysed by fitting to a mathematical model to determine the coefficients of diffusion of the particles in the foils and effusion through the target and ionizer at several temperatures. Through a better understanding of the rate of transport of the particles, it is possible to design targets and ionizers with improved yields. This is most important for the rare, short-lived isotopes in which there is considerable interest for physics experiments. This target has demonstrated large increases in the yields of $^{11}$Li and $^{12}$Be, in agreement with the predictions of the model. (11 refs).

  19. Medical irradiation, radioactive waste and misinformation. A press release from the French Academy of Medicine

    International Nuclear Information System (INIS)

    The, G. de; Tubiana, M.

    2002-01-01

    The Academy of Medicine, worried by the problems that poses for public opinion the medical irradiation, the radioactive wastes and some erroneous information that these subjects give rise to, considers useful to give an advice based on objective data. (N.C.)

  20. Role of radon in comparisons of effects of radioactivity releases from nuclear power, coal burning and phosphate mining

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, B L [Argonne National Lab., IL (USA); Pittsburgh Univ., PA (USA))

    1981-01-01

    It is shown that radon emissions are the predominant source of radiation exposure from nuclear power, coal burning or phosphate mining. For very long time spans, erosion of the continents must be considered, and in this perspective bringing uranium to the earth's surface has no effect since it would eventually reach the surface anyhow, so coal burning and phosphate mining have no net effect; however, nuclear power saves lives by removing the radon source, the net effect ultimately being a saving of 350 lives/GWe-yr. If only effects over 500 yr are considered, lives saved by removal of uranium in mining exceed lives lost due to radon emissions from the nuclear industry under regulations now being instituted, and the net fatalities per GWe-yr caused by all radioactivity releases are 0.017 for nuclear vs 0.045 for coal burning; the effects of radioactivity releases by 1-yr of present annual operations are 10 times larger for phosphate mining than for coal burning.

  1. Free release measurement of radioactive waste on the basis of the Bayes theory

    International Nuclear Information System (INIS)

    Sokcic-Kostic, M.; Langer, F.; Schultheis, R.

    2013-01-01

    The application of Bayesian theory in the evaluation of the free release measurements requires complex co-ordination between experiment and analysis. The algorithms are more complex compared to those used in the frequentist data analysis and partly to those of the Monte Carlo methods. The user can get an objective treatment of parameters of the measurement error and - as a result - a reliable indication of confidence intervals. For release measurement, the upper limit of the confidence interval must be compared with the limit given by the Radiation Protection Regulations (StrlSchV) to decide on a possible release of the material under test. (orig.)

  2. Alarm inhalation dosemeter for long living radioactive dust due to an uncontrolled release

    Science.gov (United States)

    Streil, T.; Oeser, V.; Rambousky, R.; Buchholz, F. W.

    2008-08-01

    MyRIAM is the acronym for My Radioactivity In Air Monitor and points out that the device was designed for personal use to detect any radioactivity in the air at the place and at the moment of danger. The active air sampling process enables a detection limit several orders of magnitude below that of Gamma detectors. Therefore, it is the unique way to detect dangerous exposures in time. Individual protection against inhalation of long living radioactive dust (LLRD) saves human life and health. LLRD may occur in natural environment as well as in case of nuclear accidence or military and terrorist attacks. But in any case, the immediate warning of the population is of great importance. Keep in mind: it is very easy to avoid LLRD inhalation—but you have to recognize the imminent danger. The second requirement of gap-less documentation and reliable assessment of any derived LLRD exposure is building the link to Dosimetry applications. The paper demonstrates the possibility to design small and low cost air samplers, which can be used as personal alarm dosimeters and fulfil the requirements mentioned above. Several test measurements taken by a mobile phone sized MyRIAM, shall be used to demonstrate the correctness of this statement.

  3. Alarm inhalation dosemeter for long living radioactive dust due to an uncontrolled release

    International Nuclear Information System (INIS)

    Streil, T.; Oeser, V.; Rambousky, R.; Buchholz, F. W.

    2008-01-01

    MyRIAM is the acronym for My Radioactivity In Air Monitor and points out that the device was designed for personal use to detect any radioactivity in the air at the place and at the moment of danger. The active air sampling process enables a detection limit several orders of magnitude below that of Gamma detectors. Therefore, it is the unique way to detect dangerous exposures in time.Individual protection against inhalation of long living radioactive dust (LLRD) saves human life and health. LLRD may occur in natural environment as well as in case of nuclear accidence or military and terrorist attacks. But in any case, the immediate warning of the population is of great importance. Keep in mind: it is very easy to avoid LLRD inhalation--but you have to recognize the imminent danger. The second requirement of gap-less documentation and reliable assessment of any derived LLRD exposure is building the link to Dosimetry applications.The paper demonstrates the possibility to design small and low cost air samplers, which can be used as personal alarm dosimeters and fulfil the requirements mentioned above.Several test measurements taken by a mobile phone sized MyRIAM, shall be used to demonstrate the correctness of this statement

  4. Individual protection against inhalation of long living radioactive dust due to an uncontrolled release

    International Nuclear Information System (INIS)

    Streil, T.; Oeser, V.; Rambousky, R.; Buchholz, F.W.

    2005-01-01

    Full text: Individual protection against inhalation of long living radioactive dust (LLRD) saves human life and health. LLRD may occur in natural environment as well as in case of nuclear accidence or military (DU- munitions) and terrorist attacks (dirty bombs). MyRIAM is the acronym for my radioactivity in air monitor and points out that the device was designed for personal use to detect any radioactivity in the air at the place and at the moment of the danger. Therefore, it is the unique way to detect dangerous exposures in time to warn the public. The active air sampling process enables a detection limit several orders of magnitude below that of Gamma detectors. But in any case, the immediate warning of the population is from major meaning. Keep in mind: it is very easy to avoid LLRD inhalation - but you have to recognize the imminent danger. The second requirement of gap-less documentation and reliable assessment of any derived LLRD exposure is building the bridge to dosimetry applications. The paper demonstrates the possibility to design small and low cost air samplers, which can be used as personal, alarm dosimeters and fulfil the requirements mentioned above. The system is able to warn with a time resolution of 1 minute in the order of 10 % of the yearly radiation limit of 20 mSv/y. Several test measurements taken by a mobile phone sized MyRIAM, shall be used to demonstrate the correctness of this statement. (author)

  5. Radioactive material releases in the nuclear fuel cycle - Recent experience and improvements

    International Nuclear Information System (INIS)

    Allan, C.J.; Allsop, P.J.; Anderson, R.W.; Boss, C.R.; Frost, S.E.

    1997-01-01

    The nuclear fuel cycle involves a wide range of activities and technologies from the mining of uranium, to the production of electricity and radioisotopes for medical and industrial applications, to the reprocessing and recycling of used fuel, to decommissioning and waste disposal. Worker exposures and releases to the environment are carefully controlled in: (a) all stages of uranium mining, refining and fuel fabrication, where occupational exposures and releases have decreased while production has increased; (b) the operation of nuclear power plants, where occupational exposures and releases have decreased as reactor vendors evolve their products and reactor operators optimize their procedures; (c) fuel reprocessing facilities in the U.K. and France, where occupational exposures and releases have decreased while the amount of fuel processed has increased; and in (d) decommissioning nuclear facilities and waste management activities. The nuclear industry's recent record of achievement in controlling its releases and ensuring the radiological protection of its employees has been excellent. It is clear that releases and occupational exposures from modem nuclear facilities of all types contribute negligibly to the radiation environment to which all biota are exposed. But the general public seems not to appreciate the low environmental impact of nuclear activities. The future of nuclear power and of other applications of nuclear technology applications in medicine, in agriculture and in industry will depend on maintaining a high standard of performance so that the public and decision makers can be assured that the industry is safe. (author)

  6. Evaluation of the dose assessment models for routine radioactive releases to the environment

    International Nuclear Information System (INIS)

    Rossi, J.

    1998-05-01

    The aim of the work was to evaluate the needs of development concerning the dose calculation models for routine releases and application of the models for exceptional release situations at the NPP plants operated by Imatran Voima Ltd. and Teollisuuden Voima Ltd. in Finland. First, the differences of the calculation models concerning input data, models themselves and output are considered. Subsequently some single features like importance of nuclides in exposure pathways due to change of the release composition, dose calculation for children and importance of time period of particle releases are considered. The existing dose calculation model used by the radiation safety authorities is aimed at a tool for checking the results from calculations of doses arising from routine releases by the power companies. Characteristics of an independent, foreign model and its suitability for safety authorities for dose calculations of releases in normal operation is also assessed. The needs of improvements in the existing calculation models and characteristics of a comprehensive model for safety authorities are discussed as well

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

    Science.gov (United States)

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

    2011-12-01

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

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  9. PAVAN: an atmospheric-dispersion program for evaluating design-basis accidental releases of radioactive materials from nuclear power stations

    International Nuclear Information System (INIS)

    Bander, T.J.

    1982-11-01

    This report provides a user's guide for the NRC computer program, PAVAN, which is a program used by the US Nuclear Regulatory Commission to estimate downwind ground-level air concentrations for potential accidental releases of radioactive material from nuclear facilities. Such an assessment is required by 10 CFR Part 100 and 10 CFR Part 50. The program implements the guidance provided in Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants. Using joint frequency distributions of wind direction and wind speed by atmospheric stability, the program provides relative air concentration (X/Q) values as functions of direction for various time periods at the exclusion area boundary (EAB) and the outer boundary of the low population zone (LPZ). Calculations of X/Q values can be made for assumed ground-level releases (e.g., through building penetrations and vents) or elevated releases from free-standing stacks. Various options may be selected by the user. They can account for variation in the location of release points, additional plume dispersion due to building wakes, plume meander under low wind speed conditions, and adjustments to consider non-straight trajectories. It computes an effective plume height using the physical release height which can be reduced by inputted terrain features. It cannot handle multiple emission sources. A description of the main program and all subroutines is provided. Also included as appendices are a complete listing of the program and two test cases with the required data inputs and the resulting program outputs

  10. On release of radionuclides from a near-surface radioactive waste repository to the environment

    Directory of Open Access Journals (Sweden)

    Gudelis Arūnas

    2015-09-01

    Full Text Available A closed near-surface radioactive waste repository is the source of various radionuclides causing the human exposure. Recent investigations confirm an effectiveness of the engineering barriers installed in 2006 to prevent the penetration of radionuclides to the environment. The tritium activity concentration in groundwater decreased from tens of kBq/l to below hundreds of Bq/l. The monitoring and groundwater level data suggest the leaching of tritium from previously contaminated layers of unsaturated zone by rising groundwater while 210Pb may disperse as a decay product of 226Ra daughters.

  11. International coordination of activities for establishing protective measures for the case of accidental release of radioactivity

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    The document discussed here has been submitted to the WHO Regional Committee as a basis for discussion on the international coordination of protective measures in case of large-area radioactive contamination. The document presents the following: a summary of actions taken by the regional office in response to the Chernobyl reactor accident, and of the national and international measures for public health protection after the accident; brief review of actions taken by other international organisations, and the activities proposed by the WHO on a European and on a global level. (orig./HSCH).

  12. Assessment of inhalation risk due to radioactivity released from coal-based thermal power plant

    International Nuclear Information System (INIS)

    Sahu, S.K.; Pandit, G.G.; Shukla, V.K.; Puranik, V.D.; Kushwaha, H.S.

    2006-01-01

    In India, the coal based thermal power plants have been the major source of power generation in the past and would continue for decades to come. As the coal contains naturally occurring primordial radionuclides the burning of pulverized coal to produce energy for generation of electricity in thermal power plants will result in the emission of a variety of natural radioactive elements into the environment in the vicinity of thermal power plants. In this paper we have used two different methods for characterization of uncertainty in inhalation risk to the general public around 10 Kms radius in the neighborhood of a coal-fired thermal power plant. (author)

  13. Focus on the legislative approach to short half life radioactive hospital waste releasing.

    Science.gov (United States)

    Petrucci, Caterina; Traino, Antonio Claudio

    2015-11-01

    We propose to summarize the advancements introduced by the new Directive 2013/59/Euratom concerning the concept of clearance, for which the radioactive medical waste represents a typical candidate. We also intend to spotlight disputable points in the regulatory scheme in force in Italy, as well to make a contribution to evaluate whether the practice of patients' urine storing, stated by it, can be regarded to be proper. With directing our interest to radionuclides used in Nuclear Medicine, we first present an overview of how the clearance concept, and that of exemption closely related to it, have been developed from the previous Directive 96/29 to the new one; then we describe the implementation of these concepts in the Italian legislation. Subsequently we estimate the exposure due both to keeping the effluent on site and to direct discharging it to the environment. In line with a well established international consensus, the Directive 2013/59 drives simple and harmonized regulation of clearance. On the contrary, some complexity and lack of consistency can be found in the framework of the national legislation affecting the radioactive medical waste handling. In addition the practice of excreta storing is disputed not to be really beneficial. The opportunity should be taken to make the whole system of these requirements simpler and more consistent and effective when it is revised to transpose the new Directive. Copyright © 2015 Associazione Italiana di Fisica Medica. Published by Elsevier Ltd. All rights reserved.

  14. Maximum permissible dietary contamination after the accidental release of radioactive materials from a nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Pochin, E E; Rock Carling, Ernest; Court Brown, W M [Medical Research Council, Committee on Protection against Ionizing Radiations, London (United Kingdom); and others

    1960-12-01

    After the accident to No. 1 pile at Windscale on October 10, 1957 (Atomic Energy Office, 1957), the Atomic Energy Authority asked the Medical Research Council for advice on the maximum intake of certain radioactive isotopes that should be regarded as permissible, under emergency conditions, for members of the general population living in, or deriving food from, an area contaminated owing to an accident to a reactor. The Council's Committee on Protection against Ionizing Radiations, together with its Subcommittees on Internal and External Radiations, has considered this problem, and concludes that the intake of radioactive materials by ingestion of contaminated food would generally be the limiting source of hazard after any such accident. Intake by inhalation, or radiation from the exterior, would become of importance only in rather special circumstances. In the following report, therefore, the Committee proposes maximum permissible levels of dietary contamination for the relevant isotopes in the emergency conditions envisaged. In proposing these levels, the Protection Committee has used the fullest information available on the radiation doses that would be delivered to different body tissues and at different ages by the isotopes concerned, and on the ways in which these materials would enter the body.

  15. Maximum permissible dietary contamination after the accidental release of radioactive materials from a nuclear reactor

    International Nuclear Information System (INIS)

    Pochin, E.E.; Rock Carling, Ernest; Court Brown, W.M.

    1960-01-01

    After the accident to No. 1 pile at Windscale on October 10, 1957 (Atomic Energy Office, 1957), the Atomic Energy Authority asked the Medical Research Council for advice on the maximum intake of certain radioactive isotopes that should be regarded as permissible, under emergency conditions, for members of the general population living in, or deriving food from, an area contaminated owing to an accident to a reactor. The Council's Committee on Protection against Ionizing Radiations, together with its Subcommittees on Internal and External Radiations, has considered this problem, and concludes that the intake of radioactive materials by ingestion of contaminated food would generally be the limiting source of hazard after any such accident. Intake by inhalation, or radiation from the exterior, would become of importance only in rather special circumstances. In the following report, therefore, the Committee proposes maximum permissible levels of dietary contamination for the relevant isotopes in the emergency conditions envisaged. In proposing these levels, the Protection Committee has used the fullest information available on the radiation doses that would be delivered to different body tissues and at different ages by the isotopes concerned, and on the ways in which these materials would enter the body

  16. Review of uncertainty estimates associated with models for assessing the impact of breeder reactor radioactivity releases

    International Nuclear Information System (INIS)

    Miller, C.; Little, C.A.

    1982-08-01

    The purpose is to summarize estimates based on currently available data of the uncertainty associated with radiological assessment models. The models being examined herein are those recommended previously for use in breeder reactor assessments. Uncertainty estimates are presented for models of atmospheric and hydrologic transport, terrestrial and aquatic food-chain bioaccumulation, and internal and external dosimetry. Both long-term and short-term release conditions are discussed. The uncertainty estimates presented in this report indicate that, for many sites, generic models and representative parameter values may be used to calculate doses from annual average radionuclide releases when these calculated doses are on the order of one-tenth or less of a relevant dose limit. For short-term, accidental releases, especially those from breeder reactors located in sites dominated by complex terrain and/or coastal meteorology, the uncertainty in the dose calculations may be much larger than an order of magnitude. As a result, it may be necessary to incorporate site-specific information into the dose calculation under these circumstances to reduce this uncertainty. However, even using site-specific information, natural variability and the uncertainties in the dose conversion factor will likely result in an overall uncertainty of greater than an order of magnitude for predictions of dose or concentration in environmental media following shortterm releases

  17. Radioactive Release from Aluminum-Based Spent Nuclear Fuel in Basin Storage

    Energy Technology Data Exchange (ETDEWEB)

    Sindelar, R.L.

    1999-10-21

    The report provides an evaluation of: (1) the release rate of radionuclides through minor cladding penetrations (breaches) on aluminum-based spent nuclear fuel (AL SNF), and (2) the consequences of direct storage of breached AL SNF relative to the authorization basis for SRS basin operation.

  18. Radioactive Release from Aluminum-Based Spent Nuclear Fuel in Basin Storage

    International Nuclear Information System (INIS)

    Sindelar, R.L.

    1999-01-01

    The report provides an evaluation of: (1) the release rate of radionuclides through minor cladding penetrations (breaches) on aluminum-based spent nuclear fuel (AL SNF), and (2) the consequences of direct storage of breached AL SNF relative to the authorization basis for SRS basin operation

  19. Uncertainties in radioactivity release from LWR plants under LOCA conditions - magnitude and consequences

    International Nuclear Information System (INIS)

    Mattila, L.J.

    1977-01-01

    Standardized, deterministic, and supposedly conservative calculation methods and parameter values are applied in radiological safety analyses required for licensing individual nuclear power plants. As realistic as possible and comprehensive analyses are, however, absolutely necessary for many purposes, such as developing improved designs, comparisons between nuclear and non-nuclear power plant alternatives or entire energy production strategies, and also formulating improved acceptance criteria for plant licensing. A specific type of LOCA, called design basis accident (DBA), has obtained an exceptionally important status in the licensing procedure of light water reactor nuclear power plants. This postulated accident has a decisive influence on plant siting and on the design of the various engineered safety features. To avoid certain potential negative effects of the highly standardized guideline-based accident analysis procedure - such as introduction of apparent design ''improvements'', wrong priorization of research efforts, etc. - and to provide a realistic view about the safety of light water reactors to supplement the conservative results from regulatory analyses, a comprehensive understanding of the radiological consequences of LOCA's is indispensable. Estimates of fission product release from LWR plants under different LOCA conditions are associated with uncertainties due to deficient knowledge and truly random variability. The following steps of the fission product transport chain are discussed: generation of activity, fission product release from fuel to fuel pin voids prior to the accident, fuel rod puncturing and fission product release from punctured rods during the accident, further release from fuel during the transient, transport to the containment and finally removal in and leakage from the containment. Numerical examples are given by comparing assumptions, parameter values, and results from the following four analyses: the present guideline

  20. User's guide to MARINRAD: model for assessing the consequences of release of radioactive material into the oceans

    International Nuclear Information System (INIS)

    Koplik, C.M.; Kaplan, M.F.; Nalbandian, J.Y.; Simonson, J.H.; Clark, P.G.

    1984-05-01

    Marine Radionuclide Transport and Dose (MARINRAD) is a system of the computer programs designed to evaluate the consequences from release of radioactive waste into the ocean. The FORTRAN program MARRAD, which is part of the MARINRAD software, computes nuclide concentration caused by ocean transport and generates food chain concentration factors. The FORTRAN program MAROUT, which is also part of MARINRAD, evaluates a pathways-to-man dose model, generates print reports, and produces graphic plots. MARINRAD's top-down modular design provides flexible software that can be easily modified for a user's specific problem. MARINRAD was developed under contract with the Sandia National Laboratories in Albuquerque, New Mexico. 18 references, 23 figures, 42 tables

  1. Comparison of the MARC and CRAC2 programs for assessing the radiological consequences of accidental releases of radioactive material

    CERN Document Server

    Hemming, C R; Charles, D; Ostmeyer, R M

    1983-01-01

    This report describes a comparison of the MARC (Methodology for Assessing Radiological Consequences) and CRAC2 (Calculation of Reactor Accident Consequences, version 2) computer programs for assessing the radiological consequences of accidental releases of radioactive material. A qualitative comparison has been made of the features of the constituent sub-models of the two codes, and potentially the most important differences identified. The influence of these differences has been investigated quantitatively by comparison of the predictions of the two codes in a wide variety of circumstances. Both intermediate quantities and endpoints used as a measure of risk have been compared in order to separate the variables more clearly. The results indicate that, in general, the predictions of MARC and CRAC2 are in good agreement.

  2. Models for the evaluation of ingestion doses from the consumption of terrestrial foods following an atmospheric radioactive release

    International Nuclear Information System (INIS)

    Nair, S.

    1984-04-01

    Various methods are described which have been incorporated in the FOODWEB module of the CEGB's NECTAR environmental code and are currently being used within CEGB to assess ingestion doses from consumption of terrestrial foods following an atmospheric radioactive release. Four foodchain models which have been developed within CEGB are fully described and results of typical calculations presented. Also given are the results of a validation of the dynamic model against measured 90 Sr and 137 Cs levels in milk in the U.K. resulting from weapons fallout. Methods are also described for calculating individual and population doses from ingestion using the results of the model calculations. The population dose calculations utilise a data base describing the spatial distribution of production of a wide range of agricultural products. The development of such a data base for Great Britain is described, based on the 1972 land use and livestock census, and maps are presented for each agricultural product. (U.K.)

  3. Evidence Theory Based Uncertainty Quantification in Radiological Risk due to Accidental Release of Radioactivity from a Nuclear Power Plant

    International Nuclear Information System (INIS)

    Ingale, S. V.; Datta, D.

    2010-01-01

    Consequence of the accidental release of radioactivity from a nuclear power plant is assessed in terms of exposure or dose to the members of the public. Assessment of risk is routed through this dose computation. Dose computation basically depends on the basic dose assessment model and exposure pathways. One of the exposure pathways is the ingestion of contaminated food. The aim of the present paper is to compute the uncertainty associated with the risk to the members of the public due to the ingestion of contaminated food. The governing parameters of the ingestion dose assessment model being imprecise, we have approached evidence theory to compute the bound of the risk. The uncertainty is addressed by the belief and plausibility fuzzy measures.

  4. Titanium carbide-carbon porous nanocomposite materials for radioactive ion beam production: processing, sintering and isotope release properties

    CERN Document Server

    AUTHOR|(CDS)2081922; Stora, Thierry

    2017-01-26

    The Isotope Separator OnLine (ISOL) technique is used at the ISOLDE - Isotope Separator OnLine DEvice facility at CERN, to produce radioactive ion beams for physics research. At CERN protons are accelerated to 1.4 GeV and made to collide with one of two targets located at ISOLDE facility. When the protons collide with the target material, nuclear reactions produce isotopes which are thermalized in the bulk of the target material grains. During irradiation the target is kept at high temperatures (up to 2300 °C) to promote diffusion and effusion of the produced isotopes into an ion source, to produce a radioactive ion beam. Ti-foils targets are currently used at ISOLDE to deliver beams of K, Ca and Sc, however they are operated at temperatures close to their melting point which brings target degradation, through sintering and/or melting which reduces the beam intensities over time. For the past 10 years, nanostructured target materials have been developed and have shown improved release rates of the produced i...

  5. A cost/benefit analysis of methods for controlling the release of radioactive materials in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Blanco, R.E.; Dahlman, R.C.; Davis, W. Jr.; Finney, B.C.; Groenier, W.S.; Hill, G.S.; Kibbey, A.H.; Kitts, F.G.; Lindauer, R.B.; Moore, R.E.; Pechin, W.H.; Roddy, J.W.; Ryon, A.D.; Seagren, R.D.; Sears, M.B.; Witherspoon, J.P.

    1977-01-01

    Cost/benefit surveys were made to determine the cost (in dollars) and effectiveness of radwaste treatment systems for decreasing the release of radioactive materials from model fuel cycle facilities, and to determine the benefits in terms of reduction in radiological dose commitment to individuals and populations in the surrounding areas. The studies include milling of uranium ores, conversion of virgin uranium and recycle uranium to UF 6 , fabrication of light-water reactor (LWR) fuels containing enriched uranium or enriched uranium and plutonium, fabrication of high-temperature gas-cooled reactor (HTGR) fuels containing 233 U and thorium, and reprocessing of LWR and HTGR fuels. Conceptual flowsheets were prepared for each model facility illustrating the treatment methods for gaseous and liquid effluents. The ''base'' case represents the lowest treatment cost, current treatment technology, and highest radiological dose. In succeeding cases, increasingly efficient radwaste treatment equipment is added to the ''base'' plant to reduce the amounts of radioactive materials released. The technology ranges from that currently available to that which may be developed over the next 30 years. The status of development for these technologies is discussed. The dose estimates are for maximum individual total body and organ doses at the plant boundary and for population total-body and organ doses out to 89 km. Comparisons of the doses vs annual costs in dollars are presented. In summary, they indicate that (1) the annual doses can be reduced to very low fractions of the natural background dose by the successful development and application of the radwaste treatment methods; and (2) excluding mills, the capital costs for the treatment methods vary from 0.02 to 8% of the capital cost of the base plants and the total annual operating costs (fixed charges plus operating costs) vary from 0.009 to 7.0% of the capital costs for the plant

  6. Patient release criteria following radioactive iodine-131 treatment in the light of international practice: where does South Africa fit in?

    Science.gov (United States)

    Mongane, Modisenyane S; Rae, William I D

    2017-10-01

    The release from hospital of patients treated with radioactive iodine-131 (I) remains a controversial issue as a result of the range of guidelines implemented by national regulatory bodies responsible for radiation protection in various countries worldwide. The aim of this study was to review and analyse the literature on patient release criteria (PRC) applied internationally in an attempt to achieve a justifiable approach to setting equivalent criteria in South Africa. In 2016, the South African Department of Health, Directorate: Radiation Control added conditions (numbers 50 and 90), to licences to use radioactive nuclides. These conditions state that patients must be hospitalized when the dose rate at 1 m is above 25 μSv/h, or more than 555 MBq of iodine-131 was administered to the patient. However, these criteria do not consider patients' socioeconomic conditions. A literature survey was carried out of articles detailing PRC from high-income countries as well as those in the middle-income and lower-income groups. Socioeconomic conditions within countries were determined using the International Monetary Fund lists of gross domestic product. The results from the literature have shown that in setting PRC, several countries have considered the socioeconomic conditions prevailing in their countries to achieve harmony between public protection and cost associated with hospitalization. The South African authority conditions must be seen in the context of the approach followed by other countries. Considering the international context, a justifiable, and potentially implementable, guideline or policy for improving individualized and more caring patient management is advocated.

  7. Evaluating the Effect of Nuclear Power Plant Buildings on the Atmospheric Dispersion Behavior of Released Radioactive Materials

    International Nuclear Information System (INIS)

    Nassar, N.N.; Tawfik, F.S.; Agamy, S.A.; Nagla, T.F.

    2017-01-01

    One of the most important principles in air pollution is to minimize the release of pollutants to the atmosphere, deposition on the ground and promote sufficient dilution of released pollutants within the atmosphere. Building down wash describes the effect that wind flowing over or around buildings create a cavity of reticulating winds in the are a near the buildings. These cavities cause increased vertical dispersion of plumes emitted from stacks on or near the buildings . Often it leads to elevated concentrations downwind of affected stacks. The aim of this work is to evaluate the effect of the building down wash phenomena on the atmospheric dispersion behavior of released radioactive materials from NPP. In this study, a hypothetical scenario is presented involving a point source with varying stack parameters and rectangular shaped buildings (Mille stone Nuclear Power Plant) using meteorological parameters of a chosen day. The concentrations of assumed released radionuclides, taking into consideration the building down wash effect and without are calculated using the AERMOD Model taking into consideration the effect of the type of atmospheric stability class. Also the analysis includes the model predictions for the highest 1-hour cavity concentration. The results show that the size of the cavity zone is not affected by the type of stability class, but is affected by the stack location and buildings shape. On other hand, the distance at which the plume touches the ground is affected by the type of stability class, the stack location and buildings shape. So, strategies for locating buildings need to be considered to maximize dispersion when planning for constructing several reactors and accessory buildings at a nuclear site

  8. Real time simulation of the release and transport of radioactive contaminants

    International Nuclear Information System (INIS)

    Popa, F.; Weber, M.

    1991-01-01

    Calculating the responses of the radiation monitoring system (RMS) remains one of the most difficult aspects of nuclear power plant simulation to bring into the post-TMI, first principles simulator era. This task requires the simulation of the transport of radioactive contaminants, the transport of the radiation itself, and the instrument channel including the detector. The complex physics and lack of knowledge of input parameters have made these models lag the general simulator trend away from logical/heuristic modeling of physical systems. This paper describes a series of advances to the modeling methodology to change this situation. The objective in the design of this real time simulation model was to always calculate qualitatively reasonable radiation detector readings

  9. Contamination of the Northern Oceans from Releases of Radioactivity from the Former Soviet Union

    International Nuclear Information System (INIS)

    Gomez, Leo S.

    1999-01-01

    During the Cold War the handling of Soviet military nuclear wastes was a classified topic--kept secret to hide the status and readiness of Soviet military forces. Following the end of the Cold War information about the handling of nuclear wastes by agencies of the Former Soviet Union (FSU) became available. The US Government response to the disclosure of disposal of radioactive wastes into the Arctic Ocean and into rivers that drain into the Arctic Ocean was the finding of the Arctic Nuclear Waste Assessment Program (ANWAP) in the Office of Naval Research (ONR). Projects were aided by ANWAP to study the behavior, transport, and fate of radionuclides in the Arctic Ocean. One of the research teams, the Risk Assessment Integration Group (RAIG) assessed the potential risks to humans and to the environment, particularly in the US Alaskan Arctic

  10. Population dose commitments due to radioactive releases from nuclear power plant sites in 1975

    International Nuclear Information System (INIS)

    Baker, D.A.; Soldat, J.K.; Watson, E.C.

    1977-10-01

    Population radiation dose commitments were estimated from reported radionuclide releases from commercial power reactors operating during 1975. Fifty-year dose commitments from one year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teenager and adult) residing between 2 and 80 km from each site. Results are given in the form of tables giving the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within the 2 to 80-km region around each site receiving various average dose commitments from the airborne pathways. The total dose commitment from both liquid and airborne pathways ranged from a high of 750 person-rem to a low of 0.008 person-rem with an arithmetic mean of 34 person-rem

  11. Atmospheric dilution factors for radioactive releases from Inshas research reactor, Egypt

    International Nuclear Information System (INIS)

    Abdel Aal, M.M.; Aly, A.I.M.; Tawfik, F.S.

    1994-01-01

    In the frame of assessing the suitability of Inshas site for constructing a new research reactor 20 MW, the meteorological condition are analyzed to determine the most affected population sectors. The atmospheric stability classes are estimated by a developed computer program in which the meteorological data for one year are used as input data. The results indicate that stability class F (moderately stable) is predominant one. The dilution factor is calculated using the computer code XOQDOQ for meteorological evaluation of routine effluent releases at nuclear power stations, which implements regulatory Guide 1.111 for both normal and desert conditions and for ground and elevated releases. The concentration isopleths are plotted and the most affected sector is the southern one with higher values for desert condition than the corresponding normal condition at same distance from the source. 4 fig., 3 tab

  12. TRADOS - an air trajectory dose model for long range transport of radioactive release to the atmosphere

    International Nuclear Information System (INIS)

    Rossi, J.; Valkama, I.

    1985-01-01

    A model for estimating radiation doses resulting from long range atmospheric transport of released radionuclides in accidents is precented. The model (TRADOS) is able to treat changing diffusion conditions. For example the plume can be exposed to temporary rain, changes in turbulence and mixing depth. This can result in considerable changes in individual doses. The method is applied to an example trajectory and the doses caused by a serious reactor accident are calculated

  13. Population dose commitments due to radioactive releases from Nuclear-Power-Plant Sites in 1979

    International Nuclear Information System (INIS)

    Baker, D.A.; Peloquin, R.A.

    1982-12-01

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1979. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each site. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitment from both liquid and airborne pathways ranged from a high of 1300 person-rem to a low of 0.0002 person-rem with an arithmetic mean of 38 person-rem. The total population dose for all sites was estimated at 1800 person-rem for the 94 million people considered at risk. The average individual dose commitment from all pathways on a site basis ranged from a low of 2 x 10 - 6 mrem to a high of 0.7 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites

  14. Assessment of radioactive material released from a fuel fabrication plant under accidental conditions

    International Nuclear Information System (INIS)

    1981-01-01

    This report evaluates the amounts of fissile material released both inside and outside a mixed oxide fuel fabrication plant (MOFFP) for light water reactors. The first section begins with a descriptive study of fissile material containment systems, and the methods available for quantifying accident occurrence probabilities. In addition to accidents common to all industrial facilities, other much rarer accidents were considered, such as aircraft crashes. The minimum occurrence probability limit for consideration in this study was set at 10 -6 per annum. The second part of this report attempts to assess the consequences of the accidents considered (i.e. with occurrence probabilities exceeding 10 -6 per annum) by determining maximum values for such accidents. Acts of sabotage and other accidents of this type are beyond the scope of this study and were not taken into consideration. The most serious potential accident would be a fire involving all of the glove boxes in the PuO 2 powder calcination and preparation cell, which could release 76.5 mg of PuO 2 powder into the atmosphere; the occurrence probability of such an accident, however, is slight (less than 10 -5 per annum). The second possibility, is a specially nuclear hazard that would release fission products into the atmosphere. The occurrence probability of such an accident is currently evaluated at 10 -3 per annum

  15. Population dose commitments due to radioactive releases from nuclear power plant sites in 1987

    International Nuclear Information System (INIS)

    Baker, D.A.

    1990-08-01

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1987. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 70 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for reach of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The site average individual dose commitment from all pathways ranged from a low of 2 x 10 -6 mrem to a high of 0.009 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites. However, licensee calculation of doses to the maximally exposed individual at some sites indicated values of up to approximately 100 times average individual doses (on the order of a few millirem per year). 2 refs., 2 figs., 7 tabs

  16. Population dose commitments due to radioactive releases from nuclear power plant sites in 1982. Volume 4

    International Nuclear Information System (INIS)

    Baker, D.A.; Peloquin, R.A.

    1986-06-01

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1982. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 51 sites. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments from both liquid and airborne pathways ranged from a high of 30 person-rem to a low of 0.007 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 3 person-rem. The total population dose for all sites was estimated at 130 person-rem for the 100 million people considered at risk. The average individual dose commitment from all pathways on a site basis ranged from a low of 6 x 10 -7 mrem to a high of 0.06 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites

  17. Population dose commitments due to radioactive releases from nuclear-power-plant sites in 1978

    International Nuclear Information System (INIS)

    Peloquin, R.A.; Schwab, J.D.; Baker, D.A.

    1982-06-01

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1978. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each site. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitment from both liquid and airborne pathways ranged from a high of 200 person-rem to a low of 0.0004 person-rem with an arithmetic mean of 14 person-rem. The total population dose for allsites was estimated at 660 person-rem for the 93 million people considered at risk. The average individual dose commitment from all pathways on a site basis ranged from a low of 3 x 10 -6 mrem to a high of 0.08 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites

  18. Population dose commitments due to radioactive releases from nuclear power plant sites in 1986

    International Nuclear Information System (INIS)

    Baker, D.A.

    1989-10-01

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1986. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 66 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 31 person-rem to a low of 0.0007 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 1.7 person-rem. The total population dose for all sites was estimated at 110 person-rem for the 140 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 2 x 10 -6 mrem to a high of 0.02 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites. 12 refs

  19. Population dose commitments due to radioactive releases from nuclear power plant sites in 1984

    International Nuclear Information System (INIS)

    Baker, D.A.

    1988-01-01

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1984. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 56 sites. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 110 person-rem to a low of 0.002 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 5 person-rem. The total population dose for all sites was estimated at 280 person-rem for the 100 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 6 x 10 -6 mrem to a high of 0.04 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites

  20. Population dose commitments due to radioactive releases from nuclear power plant sites in 1985

    International Nuclear Information System (INIS)

    Baker, D.A.

    1988-08-01

    Population radiation dose commitments have been estimated from reported radionuclide releases from commericial power reactors operating during 1985. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 61 sites. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 73 person-rem to a low of 0.011 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 3 person-rem. The total population dose for all sites was estimated at 200 person-rem for the 110 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 5 /times/ 10/sup /minus/6/ mrem to a high of 0.02 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites

  1. Population dose commitments due to radioactive releases from nuclear power plant sites in 1988

    International Nuclear Information System (INIS)

    Baker, D.A.

    1992-01-01

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1988. Fifty-year commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 71 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 16 person-rem to a low of 0.0011 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 1.1 person-rem. The total population dose for all sites was estimated at 75 person-rem for the 150 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 3 x 10 -7 mrem to a high of 0.02 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites. However, licensee calculation of doses to the maximally exposed individual at some sites indicated values of up to approximately 100 times average individual doses (on the order of a few millirem per year)

  2. Identification of release scenarios for a repository of radioactive waste in a salt dome in the Netherlands

    International Nuclear Information System (INIS)

    Glasbergen, P.; Hamstra, J.

    1981-01-01

    A review is presented of the long-term scenarios used in the safety analysis which was carried out for the disposal of radioactive waste in salt domes in the Netherlands. The long-term analysis involved the following natural processes or events: climatological and sea-level changes, glacial erosion, diapirism, subsidence, faulting and dissolution. The model calculations which were carried out showed the dominant parameters: the rate of diapirism and the rate of subsurface dissolution of rock salt. During the operational period the intrusion of water in the repository was considered to be the most hazardous event. Because the layout of the disposal mine, the disposal geometry and the disposal mining procedures were still under consideration, the first approach of a release scenario was made on a generic basis. A generic scenario is presented for the events during the flooding of the repository. The transport ways of water through the repository and its surroundings are indicated. It is concluded that release scenario analysis for long-term periods and for the operational period provides essential information to optimize the overall disposal system in an iterative process

  3. Uranium pollution in an estuary affected by pyrite acid mine drainage and releases of naturally occurring radioactive materials

    International Nuclear Information System (INIS)

    Villa, M.; Manjon, G.; Hurtado, S.; Garcia-Tenorio, R.

    2011-01-01

    Highlights: → Huelva estuary is affected by former phosphogypsum releases and pyrite acid mine drainage. → Time evolution of uranium concentration is analyzed after halting of NORM releases. → Two new contamination sources are preventing the complete uranium cleaning: (1) The leaching of phosphogypsum stacks located close to Tinto River. (2) Pyrite acid mine drainage. → High uranium concentrations are dissolved in water and precipitate subsequently. - Abstract: After the termination of phosphogypsum discharges to the Huelva estuary (SW Spain), a unique opportunity was presented to study the response of a contaminated environmental compartment after the cessation of its main source of pollution. The evolution over time of uranium concentrations in the estuary is presented to supply new insights into the decontamination of a scenario affected by Naturally Occurring Radioactive Material (NORM) discharges. The cleaning of uranium isotopes from the area has not taken place as rapidly as expected due to leaching from phosphogypsum stacks. An in-depth study using various techniques of analysis, including 234 U/ 238 U and 230 Th/ 232 Th ratios and the decreasing rates of the uranium concentration, enabled a second source of uranium contamination to be discovered. Increased uranium levels due to acid mine drainage from pyrite mines located in the Iberian Pyrite Belt (SW Spain) prevent complete uranium decontamination and, therefore, result in levels nearly twice those of natural background levels.

  4. Population dose commitments due to radioactive releases from nuclear power plant sites in 1980

    International Nuclear Information System (INIS)

    Baker, D.A.; Peloquin, R.A.

    1983-08-01

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1980. In addition doses derived from the shutdown reactors at the Three Mile Island site were included. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each site. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitment from both liquid and airborne pathways ranged from a high of 40 person-rem to a low of 0.02 person-rem with an arithmetic mean of 4 person-rem. The total population dose for all sites was estimated at 180 person-rem for the 96 million people considered at risk

  5. Dose commitments due to radioactive releases from nuclear power plant sites in 1992. Volume 14

    International Nuclear Information System (INIS)

    Aaberg, R.L.; Baker, D.A.

    1996-03-01

    Population and individual radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1992. Fifty-year dose commitments for a 1-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teenager, and adult) residing between 2 and 80 km from each of 72 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is an estimate of individual doses, which are compared with 10 CFR Part 50, Appendix I, design objectives. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 3.7 person-rem to a low of 0.0015 person-rem for the sites with plants in operation and producing power during the year. The arithmetic mean was 0.66 person-rem. The total population dose for all sites was estimated at 47 person-rem for the 130-million people considered at risk. The individual dose commitments estimated for all sites were below the 10 CFR 50, Appendix I, design objectives

  6. Population dose commitments due to radioactive releases from nuclear power plant sites in 1981. Volume 3

    International Nuclear Information System (INIS)

    Baker, D.A.; Peloquin, R.A.

    1985-01-01

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1981. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teenager and adult) residing between 2 and 80 km from each site. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitment from both liquid and airborne pathways from 48 sites ranged from a high of 20 person-rem to a low of 0.008 person-rem with an arithmetic mean of 3 person-rem. The total population dose for all sites was estimated at 160 person-rem for the 98 million people considered at risk

  7. Dose commitments due to radioactive releases from nuclear power plant sites in 1991. Volume 13

    Energy Technology Data Exchange (ETDEWEB)

    Baker, D.A. [Pacific Northwest Lab., Richland, WA (United States)

    1995-04-01

    Population and individual radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1991. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teenager and adult) residing between 2 and 80 km from each of 72 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is an estimate of individual doses which are compared with 10 CFR Part 50, Appendix 1 design objectives. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 22 person-rem to a low of 0.002 person-rem for the sites with plants in operation and producing power during the year. The arithmetic mean was 1.2 person-rem. The total population dose for all sites was estimated at 88 person-rem for the 130 million people considered at risk. The individual dose commitments estimated for all sites were below the Appendix 1 design objectives.

  8. Dose commitments due to radioactive releases from nuclear power plant sites in 1992. Volume 14

    Energy Technology Data Exchange (ETDEWEB)

    Aaberg, R.L.; Baker, D.A.

    1996-03-01

    Population and individual radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1992. Fifty-year dose commitments for a 1-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teenager, and adult) residing between 2 and 80 km from each of 72 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is an estimate of individual doses, which are compared with 10 CFR Part 50, Appendix I, design objectives. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 3.7 person-rem to a low of 0.0015 person-rem for the sites with plants in operation and producing power during the year. The arithmetic mean was 0.66 person-rem. The total population dose for all sites was estimated at 47 person-rem for the 130-million people considered at risk. The individual dose commitments estimated for all sites were below the 10 CFR 50, Appendix I, design objectives.

  9. Dose commitments due to radioactive releases from nuclear power plant sites in 1991. Volume 13

    International Nuclear Information System (INIS)

    Baker, D.A.

    1995-04-01

    Population and individual radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1991. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teenager and adult) residing between 2 and 80 km from each of 72 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is an estimate of individual doses which are compared with 10 CFR Part 50, Appendix 1 design objectives. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 22 person-rem to a low of 0.002 person-rem for the sites with plants in operation and producing power during the year. The arithmetic mean was 1.2 person-rem. The total population dose for all sites was estimated at 88 person-rem for the 130 million people considered at risk. The individual dose commitments estimated for all sites were below the Appendix 1 design objectives

  10. Population dose commitments due to radioactive releases from nuclear power plant sites in 1983

    International Nuclear Information System (INIS)

    Baker, D.A.; Peloquin, R.A.

    1987-04-01

    Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1983. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 52 sites. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 45 person-rem to a low of 0.002 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 3 person-rem. The total population dose for all sites was estimated at 170 person-rem for the 100 million people considered at risk

  11. Dose commitments due to radioactive releases from nuclear power plant sites in 1989

    International Nuclear Information System (INIS)

    Baker, D.A.

    1993-02-01

    Population and individual radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1989. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 72 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is an estimate of individual doses which are compared with 10 CFR Part 50, Appendix I design objectives. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 14 person-rem to a low of 0.005 person-rem for the sites with plants in operation and producing power during the year. The arithmetic mean was 1.2 person-rem. The total population dose for all sites was estimated at 84 person-rem for the 140 million people considered at risk. The individual dose commitments estimated for all sites were below the Appendix I design objectives

  12. Effect of the foodchain in radioactivities released from thermal power plants

    International Nuclear Information System (INIS)

    Okamoto, K.

    1980-01-01

    Among many radionuclides released when burning fossil fuel 210 Pb and 210 Po are especially important, because they are very volatile, are released at higher rates than others, and are concentrated very strongly in marine organisms. This is particularly important in Japan, because most power plants in Japan are built near the seacoast and seawater contamination is likely. 210 Pb and 210 Po could also contaminate leafy vegetables by fallout. Since Japanese consume large amounts of seafoods and vegetables, this foodchain is important. The dose due to this foodchain is estimated. Although uncertainties are large and a definite conclusion cannot be drawn, the dose is one to three orders of magnitude higher when considering this foodchain than when not considering it. The average individual dose of Japanese due to this foodchain is of the order of several mrem/y. Although much smaller than the natural background, it is comparable to the dose of the total fuel cycle of full scale nuclear electricity generation, and so its social implication cannot be overlooked. (H.K.)

  13. Dose commitments due to radioactive releases from nuclear power plant sites in 1989

    Energy Technology Data Exchange (ETDEWEB)

    Baker, D.A. (Pacific Northwest Lab., Richland, WA (United States))

    1993-02-01

    Population and individual radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1989. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 72 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is an estimate of individual doses which are compared with 10 CFR Part 50, Appendix I design objectives. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 14 person-rem to a low of 0.005 person-rem for the sites with plants in operation and producing power during the year. The arithmetic mean was 1.2 person-rem. The total population dose for all sites was estimated at 84 person-rem for the 140 million people considered at risk. The individual dose commitments estimated for all sites were below the Appendix I design objectives.

  14. Dose commitments due to radioactive releases from nuclear power plant sites in 1990: Volume 12

    International Nuclear Information System (INIS)

    Baker, D.A.

    1994-11-01

    Population and individual radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1990. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 72 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is an estimate of individual doses which are compared with 10 CFR Part 50, Appendix 1 design objectives. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 15 person-rem to a low of 0.002 person-rem for the sites with plants in operation and producing power during the year. The arithmetic mean was 1.1 person-rem. The total population dose for all sites was estimated at 78 person-rem for the 130 million people considered at risk. The individual dose commitments estimated for all sites were below the Appendix 1 design objectives

  15. Inverse modelling for real-time estimation of radiological consequences in the early stage of an accidental radioactivity release.

    Science.gov (United States)

    Pecha, Petr; Šmídl, Václav

    2016-11-01

    A stepwise sequential assimilation algorithm is proposed based on an optimisation approach for recursive parameter estimation and tracking of radioactive plume propagation in the early stage of a radiation accident. Predictions of the radiological situation in each time step of the plume propagation are driven by an existing short-term meteorological forecast and the assimilation procedure manipulates the model parameters to match the observations incoming concurrently from the terrain. Mathematically, the task is a typical ill-posed inverse problem of estimating the parameters of the release. The proposed method is designated as a stepwise re-estimation of the source term release dynamics and an improvement of several input model parameters. It results in a more precise determination of the adversely affected areas in the terrain. The nonlinear least-squares regression methodology is applied for estimation of the unknowns. The fast and adequately accurate segmented Gaussian plume model (SGPM) is used in the first stage of direct (forward) modelling. The subsequent inverse procedure infers (re-estimates) the values of important model parameters from the actual observations. Accuracy and sensitivity of the proposed method for real-time forecasting of the accident propagation is studied. First, a twin experiment generating noiseless simulated "artificial" observations is studied to verify the minimisation algorithm. Second, the impact of the measurement noise on the re-estimated source release rate is examined. In addition, the presented method can be used as a proposal for more advanced statistical techniques using, e.g., importance sampling. Copyright © 2016 Elsevier Ltd. All rights reserved.

  16. The development of the American national standard, ''control of radioactive surface contamination on materials, equipment and facilities to be released for uncontrolled use''

    International Nuclear Information System (INIS)

    Shapiro, J.

    1980-01-01

    The American National Standard, Control of Radioactive Surface Contamination on Materials, Equipment and Facilities to be Released for Uncontrolled Use, was developed under the procedures of ANSI for ANSI Main Committee N13 (Radiation Protection) by a working group of the Health Physics Society Standards Committee. This standard provides criteria for the control of materials, equipment and facilities contaminated with radioactivity proposed to be released for uncontrolled use. Permissible contamination limits are specified as well as methods assessing the levels of contamination. This paper reviews the proceedings of the Subcommittee on Radioactive Surface Contamination, the comments received by reviewers of the standard, the resolution of the committee, and the bases for reaching the final limits, recommendations, and measurement procedures. (H.K.)

  17. An application of cost-effectiveness analysis to restrict the damage caused by an accidental release of radioactive material to the environment

    International Nuclear Information System (INIS)

    Frittelli, L.; Tamburrano, A.

    1980-01-01

    When an accidental release of radioactive material occurs health effects in the exposed population can be mitigated by remedial actions applied to individuals or their environment. A cost-effectiveness analysis is performed by comparing the cost of remedial action with the monetary value of the collective dose avoided. (H.K.)

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

    International Nuclear Information System (INIS)

    1974-01-01

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

  19. A guide to the use of TIRION. A computer programme for the calculation of the consequences of releasing radioactive material to the atmosphere

    International Nuclear Information System (INIS)

    Kaiser, G.D.

    1976-11-01

    A brief description is given of the contents of TIRION, which is a computer program that has been written for use in calculations of the consequences of releasing radioactive material to the atmosphere. This is followed by a section devoted to an account of the control and data cards that make up the input to TIRION. (author)

  20. Optimization and control of planned radioactive releases of pressurized water in France

    International Nuclear Information System (INIS)

    Lochard, J.; Maccia, C.; Pages, P.

    1980-01-01

    The planning of waste treatment systems for the PWRs of the French nuclear program is discussed considering the ALARA doses recommended by the ICRP. First, the economic and health impacts associated with available waste treatment systems are quantitatively assessed. Through a sequence of models based partly on available data and/or reasonable assumptions, the following results are obtained: capital and operating costs of the different waste treatment systems, liquid and/or gaseous activities released, air and water concentration after dilution in the environment, individual and collective doses and resulting health effects. The systems are then compared on the basis of their cost-effectiveness. Here effectiveness is expressed by means of the different risk indicators calculated above: individual whole body exposure (at the site boundary), collective dose commitment or the associated potential health effects for the regional or general population. Finally the selection of optimal waste treatment systems is discussed. (H.K.)

  1. Transfer into the biosphere of radionuclides released from deep storage of radioactive wastes. Bibliographical study

    International Nuclear Information System (INIS)

    Guedon, V.; Siclet, F.

    1995-03-01

    Most countries with civilian nuclear programs today are encountering difficulty in implementing a nuclear waste management policy that is both technically safe in the long term and accepted by the public. To meet both criteria, the solution most generally envisaged is deep storage either of untreated spent nuclear fuel or of highly radioactive wastes resulting from reprocessing. In order to predict the potential impact of such storage on man, one needs to understand the path followed by radionuclides in the geosphere, and later in the biosphere. Given the time scales involved and the critical nature of the elements concerned, it is indispensable to turn to mathematical modeling of the phenomena. This, however, does not preclude the essential need for in-depth knowledge of the phenomena and of the physico-chemical characteristics of radionuclides. This report presents what is hoped to be a complete inventory of the radionuclides contained in ''high level'' wastes (categories B AND C). The elements concerned in studies on deep storage are essentially long-life radionuclides (both actinides and certain fission and activation products). Their physico-chemical characteristics and their behavior in various ecological compartments are examined. Bibliographical data bearing on: solubility (in an oxidizing, reducing medium), distribution factors (water/rock-sediment-soil), concentration and transfer factors (in aquatic and terrestrial mediums), dose conversion factors (in the case of internal and external irradiation), principal paths of exposure for each radionuclide studied, are presented in this report. Initial results from international projects to model what happens to radionuclides in the biosphere are also presented. In general, they are optimistic as to the future, but nonetheless point to a need to improve the conceptual base of the models, to ensure that all major phenomena and processes are taken into consideration and to examine any possible amplification

  2. Environmental impact of radioactive releases from recycle of thorium-based fuel using current containment technology

    International Nuclear Information System (INIS)

    Tennery, V.J.; Bomar, E.S.; Bond, W.D.; Morse, L.E.; Meyer, H.R.; Till, J.E.; Yalcintas, M.G.

    1980-01-01

    The analysis of thorium mining and milling suggests that the resulting doses should be similar to those from uranium operations. An absolute comparison cannot be made at this time, however, due to differences in some assumptions utilized by the various investigators and the lack in some cases of site-specific meteorology and population data at thorium resource sites in the western United States. A distinct difference resulting from the short half-life of 220 Rn (T/sub 1/2/ = 55.6 s) in the thorium decay chain compared to that for 222 Rn (T/sub 1/2/ = 3.82 d) in uranium decay was noted for emissions following mill shutdown. This effect is to make potential releases following thorium mill shutdown of lesser consequence than in the uranium case. Thorium tailings activity would also decrease relatively rapidly due to the comparatively short half-life (T/sub 1/2 = 5.75 y) of 228 Ra. Doses due to airborne releases from thorium-uranium carbide fuel refabrication are significantly less than that due to fuel reprocessing. Tritium is the principal contributor to reprocessing plant doses while carbon-14, 131 Cs, and 232 U account for most of the remaining dose. A tenfold increase in reprocessing plant CF for tritium reduces both individual and population doses by about 60%. For refabrication operations, a near linear dependence upon dose with 232 U content of the fuel was calculated between concentrations of 10 ppM and 5000 ppM. Comparison of (Th, U)C and (U, Pu)C showed little difference in dose commitment, but the presence of 232 U in the (Th, U) fuel causes a notable increase in the refabrication plant dose over that previously calculated for (U, Pu) type fuels

  3. Guidelines for calculating radiation doses to the public from a release of airborne radioactive material under hypothetical accident conditions in nuclear reactors

    International Nuclear Information System (INIS)

    1991-04-01

    This standard provides guidelines and a methodology for calculating effective doses and thyroid doses to people (either individually or collectively) in the path of airborne radioactive material released from a nuclear facility following a hypothetical accident. The radionuclides considered are those associated with substances having the greatest potential for becoming airborne in reactor accidents: tritium (HTO), noble gases and their daughters, radioiodines, and certain radioactive particulates (Cs, Ru, Sr, Te). The standard focuses on the calculation of radiation doses for external exposures from radioactive material in the cloud; internal exposures for inhalation of radioactive material in the cloud and skin penetration of tritium; and external exposures from radionuclides deposited on the ground. It uses as modified Gaussian plume model to evaluate the time-integrated concentration downwind. (52 refs., 12 tabs., 21 figs.)

  4. Limits on the thermal energy release from radioactive wastes in a mined geologic repository

    International Nuclear Information System (INIS)

    Scott, J.A.

    1983-03-01

    The theraml energy release of nuclear wastes is a major factor in the design of geologic repositories. Thermal limits need to be placed on various aspets of the geologic waste disposal system to avoid or retard the degradation of repository performance because of increased temperatures. The thermal limits in current use today are summarized in this report. These limits are placed in a hierarchial structure of thermal criteria consistent with the failure mechanism they are trying to prevent. The thermal criteria hierarchy is used to evaluate the thermal performance of a sample repository design. The design consists of disassembled BWR spent fuel, aged 10 years, close packed in a carbon steel canister with 15 cm of crushed salt backfill. The medium is bedded salt. The most-restrictive temperature for this design is the spent-fuel centerline temperature limit of 300 0 C. A sensitivity study on the effects of additional cooling prior to disposal on repository thermal limits and design is performed

  5. Determination of radioactivity released from fuel to be considered in accident safety analysis

    International Nuclear Information System (INIS)

    1980-01-01

    RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to define a margin of conservatism on activity values used in the following safety analysis - determination of instrumentation ranges - definition of equipment accessibility to personnel - qualification of equipment to post-accident conditions - determination of waste release to the environment

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

    International Nuclear Information System (INIS)

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

    1976-04-01

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

  7. Environmental processes and parameters influencing the consequences of an accidental release of radioactivity weather and season

    International Nuclear Information System (INIS)

    Boeri, G.C.

    1989-01-01

    Seasonal, climatic and meteorological conditions may have a substantial influence on the physical factors involved in transport and deposition of airborne contaminants, and on the transfer and accumulation of radionuclides in terrestrial and aquatic ecosystems. As well, these environmental conditions can also have a significant influence on living habits and practices, and thus on potential radiological and economical impacts. Moreover, these conditions may affect the features and the impact of countermeasures which are adopted for the protection of the public in case of an accidental release. During a Special Session that the Committee of Radiation Protection and Public Health (CRPPH) held on the 1st-2nd September 1986 to review the radiological aspects of the Chernobyl nuclear accident, it was agreed that a consultant should prepare a report reviewing different accident consequences in a radiation protection and public health perspective, and identify the influence of such parameters as time of the year, weather and environmental conditions on the overall impact and the determination of appropriate countermeasures. A Consultant Report on this issue was prepared, by Dr. G. Boeri, and submitted to the CRPPH for review and consideration at its meeting of 22nd-24th November 1987. The CRPPH subsequently agreed that the Consultant Report should be revised and completed, taking into account comments and suggestions sent to the Secretariat and focussing especially on the effect of seasonal and weather conditions in terms of their influence on the radiological impact of an accident and on the emergency countermeasures to be taken. It was decided that the Consultant Report should be developed into an Overview Paper for a workshop on this issue to be organised by the NEA in 1988

  8. Development of Public Training System for Emergency Exercise Using Virtual Reality Technology Based on Radioactive Release Accident

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Il; Park, Seong Jun; Lee, Dewhey; Song, Sub Lee; Park, Younwon [BEES Inc., Daejeon (Korea, Republic of)

    2016-10-15

    An exercise is normally conducted for a day or two days depending on the scale of the exercise. What we have experienced up to date there are several limitations in the radiological emergency exercises such as low public acceptance, poor enthusiasm in the exercise participation, not very attracting exercise scenarios, low efficiency in conducting an exercise, and so on. In order to overcome the limitations of the present exercising system, we would like to develop a radiological emergency exercise system using VR (virtual reality) technology based on a radioactive release accident. In this paper, we just introduce some basic development methods and event tree based scenario as a beginning stage. After the accident in Fukushima Daiichi NPP, the importance of emergency exercise especially for the public is far more emphasized around the world more and more. However, the human labor focused radiological emergency exercise up to now has many limitations. After developing this system properly and by using it, we could even expect to estimate the weak points of the emergency arrangements and strategy we have.

  9. Simulation of short-term fluctuations in gamma exposure rate due to radioactive cloud released from nuclear power plant

    International Nuclear Information System (INIS)

    Ichikawa, Yoichi; Shikata, Hiroshi; Ishida, Kenji; Ohba, Tachimori.

    1981-01-01

    The measured γ-exposure rate around nuclear power plants is due mainly to natural causes and radioactive clouds emitted from the plants. An exposure calculation method based on puff model has been already proposed to identify the plant contributions and to estimate values in response to short-term fluctuations of meteorological condition and the release rate. However, the calculation method by this model consumes a lot of computer time, since the calculation requires a three-dimensional integration of the distribution of the concentration from each puff. Hence, we propose a simplified method using approximate polynominal equations and interpolations. The computer time needed for the calculation with the simplified method is reduced to 1/30 of that required by the previous method. The calculation results by simplified method are compared with those by the previous method and with the measured exposure rate less natural background. The results of two different methods are in good agreement. The calculated exposure rate is within the range from half to twice as much as the measured exposure rate less background. (author)

  10. Development of Public Training System for Emergency Exercise Using Virtual Reality Technology Based on Radioactive Release Accident

    International Nuclear Information System (INIS)

    Lee, Byung Il; Park, Seong Jun; Lee, Dewhey; Song, Sub Lee; Park, Younwon

    2016-01-01

    An exercise is normally conducted for a day or two days depending on the scale of the exercise. What we have experienced up to date there are several limitations in the radiological emergency exercises such as low public acceptance, poor enthusiasm in the exercise participation, not very attracting exercise scenarios, low efficiency in conducting an exercise, and so on. In order to overcome the limitations of the present exercising system, we would like to develop a radiological emergency exercise system using VR (virtual reality) technology based on a radioactive release accident. In this paper, we just introduce some basic development methods and event tree based scenario as a beginning stage. After the accident in Fukushima Daiichi NPP, the importance of emergency exercise especially for the public is far more emphasized around the world more and more. However, the human labor focused radiological emergency exercise up to now has many limitations. After developing this system properly and by using it, we could even expect to estimate the weak points of the emergency arrangements and strategy we have

  11. Guidelines for calculating radiation doses to the public from a release of airborne radioactive material under hypothetical accident conditions in nuclear reactors

    International Nuclear Information System (INIS)

    1989-09-01

    This Standard provides guidelines and a methodology for calculating effective doses and thyroid doses to people (either individually or collectively) in the path of airborne radioactive material released from a nuclear facility following a hypothetical accident. The specific radionuclides considered in the Standard are those associated with substances having the greatest potential for becoming airborne in reactor accidents (eg, tritium (HTO), noble gases and their daughters (Kr-Rb, Xe-Cs), and radioiodines (I)); and certain radioactive particulates (eg, Cs, Ru, Sr, Te) that may become airborne under exceptional circumstances

  12. Idaho National Engineering Laboratory response to the December 13, 1991, Congressional inquiry on offsite release of hazardous and solid waste containing radioactive materials from Department of Energy facilities

    International Nuclear Information System (INIS)

    Shapiro, C.; Garcia, K.M.; McMurtrey, C.D.; Williams, K.L.; Jordan, P.J.

    1992-05-01

    This report is a response to the December 13, 1991, Congressional inquiry that requested information on all hazardous and solid waste containing radioactive materials sent from Department of Energy facilities to offsite facilities for treatment or disposal since January 1, 1981. This response is for the Idaho National Engineering Laboratory. Other Department of Energy laboratories are preparing responses for their respective operations. The request includes ten questions, which the report divides into three parts, each responding to a related group of questions. Part 1 answers Questions 5, 6, and 7, which call for a description of Department of Energy and contractor documentation governing the release of waste containing radioactive materials to offsite facilities. ''Offsite'' is defined as non-Department of Energy and non-Department of Defense facilities, such as commercial facilities. Also requested is a description of the review process for relevant release criteria and a list of afl Department of Energy and contractor documents concerning release criteria as of January 1, 1981. Part 2 answers Questions 4, 8, and 9, which call for information about actual releases of waste containing radioactive materials to offsite facilities from 1981 to the present, including radiation levels and pertinent documentation. Part 3 answers Question 10, which requests a description of the process for selecting offsite facilities for treatment or disposal of waste from Department of Energy facilities. In accordance with instructions from the Department of Energy, the report does not address Questions 1, 2, and 3

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

    International Nuclear Information System (INIS)

    Cruz L, C. A.

    2015-01-01

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

  14. Box model of radionuclide dispersion and radiation risk estimation for population in case of radioactivity release from nuclear submarine number-sign 601 dumped in the Kara Sea

    International Nuclear Information System (INIS)

    Yefimov, E.I.; Pankratov, D.V.; Ignatiev, S.V.

    1997-01-01

    When ships with nuclear reactors or nuclear materials aboard suffer shipwreck or in the case of burial or dumping of radioactive wastes, atmospheric fallout, etc., radionuclides may be released and spread in the sea, contaminating the sea water and the sea bottom. When a nuclear submarine (NS) is dumped this spread of activity may occur due to gradual core destruction by corrosion over many years. The objective of this paper is to develop a mathematical model of radionuclide dispersion and to assess the population dose and radiation risk for radionuclide release from the NS No. 601, with Pb-Bi coolant that was dumped in the Kara Sea

  15. Release of immunoreactive and radioactively prelabelled endogenous (pro-)insulin from isolated islets of rat pancreas in the presence of exogenous insulin

    Energy Technology Data Exchange (ETDEWEB)

    Schatz, H [Giessen Univ. (Germany, F.R.). Zentrum fuer Innere Medizin; Pfeiffer, E F

    1977-01-01

    To study the influence of insulin on its secretion, collagenase-isolated islets of rat pancreas were prelabelled with (/sup 3/H)leucine for 2 h. After washing the islets, (pro-)insulin release was stimulated by glucose in the presence or absence of exogenous insulin (up to 2.5 mu./ml. Hormone release was unchanged by the presence of exogenous insulin as judged by determination of both immunoreactive insulin and radioactivity incorporated into the proinsulin and insulin fractions of the medium. No direct feedback mechanism for insulin secretion was apparent from this study.

  16. The impact of ambient dose rate measuring network and precipitation radar system for detection of environmental radioactivity released by accident

    International Nuclear Information System (INIS)

    Bleher, M; Stoehlker, U.

    2003-01-01

    For the surveillance of environmental radioactivity, the German measuring network of BfS consists of more than 2000 stations where the ambient gamma dose rate is continuously measured. This network is a helpful tool to detect and localise enhanced environmental contamination from artificial radionuclides. The threshold for early warning is so low, that already an additional dose rate contribution of 0,07 μGy/h is detectable. However, this threshold is frequently exceeded due to precipitation events caused by washout of natural activity in air. Therefore, the precipitation radar system of the German Weather Service provides valuable information on the problem, whether the increase of the ambient dose rate is due to natural or man-made events. In case of an accidental release, the data of this radar system show small area precipitation events and potential local hot spots not detected by the measuring network. For the phase of cloud passage, the ambient dose rate measuring network provides a reliable database for the evaluation of the current situation and its further development. It is possible to compare measured data for dose rate with derived intervention levels for countermeasures like ''sheltering''. Thus, critical regions can be identified and it is possible to verify implemented countermeasures. During and after this phase of cloud passage the measured data of the monitoring network help to adapt the results of the national decision support systems PARK and RODOS. Therefore, it is necessary to derive the actual additional contribution to the ambient dose rate. Map representations of measured dose rate are rapidly available and helpful to optimise measurement strategies of mobile systems and collection strategies for samples of agricultural products. (orig.)

  17. Determination of potential radiation exposure via terrestrial food chains by the release of radioactive material from nuclear facilities

    International Nuclear Information System (INIS)

    Handge, P.; Meurin, G.

    1978-01-01

    The radiation exposure level caused by consumption of vegetable and animal products in the environment of nuclear power plants is determined to a large extent by the release of 90 Sr, 134 Cs, and 137 Cs. For long-lived nuclides, especially 90 Sr, transfer from the soil into vegetation makes the essential contribution to plant contamination after several years of power plant operation. The relevant transfer coefficients for the different plant species vary, depending on the soil properties, between 0.02 and 6.0 [pCi/kg fresh weigth of vegetation : pCi/kg dry weight of soil] for Sr and between 1.10 -3 and 0.2 [pCi/kg fresh weight of vegetation : pCi/kg dry weight of soil] for Cs. The sensitivity analysis shows that already a variation of the transfer coefficients for Sr from 0.5 up to 2.5 [pCi/kg fresh weight of vegetation : pCi/kg dry weight of soil] and for Cs from 3.10 -2 up to 2.10 -1 cause variations in the level of radiation exposure for individual exposure pathways by factors fo 2 to 4. Correspondingly higher values are to be expected by still larger transfer of Sr and Cs from the ground to vegetation. For transfer coefficients >- 2.5 [pCi/kg fresh weight of vegetation : pCi/kg dry weight of soil], however, removal of radioactive substances from the ground by the plants must not remain without consideration any longer. (orig./HP) [de

  18. Simulating a radioactive release

    International Nuclear Information System (INIS)

    Nelson, B.

    1993-01-01

    A scenario was played out in a hotel conference room by representative from EPA and other federal agencies, Canada, the State of New York, the Nuclear Regulatory Commission, and the Departments of State, Energy, Agriculture, and Health and Human Services. The intense day-long session was conducted by ORIA last May. It was one of more than a dozen identical exercises conducted this past spring by Nuclear Energy Agency (NEA) member countries to increase their preparedness and to identify deficiencies in international radiological emergency response. The players concentrated on notification and communication, protective actions for people, safeguards for foot and agriculture, and international assistance. A follow-up meeting to present the results of all NEA exercises was held in Paris in June 1993. Of particular interest to other countries was the unique participation by the US and Canada in each other's exercises. To maintain the readiness of governments to respond to such disasters, another exercise is recommended two years hence

  19. Public exposure from environmental release of radioactive material under normal operation of unit-1 Bushehr nuclear power plant

    International Nuclear Information System (INIS)

    Sohrabi, M.; Parsouzi, Z.; Amrollahi, R.; Khamooshy, C.; Ghasemi, M.

    2013-01-01

    Highlights: ► The unit-1 Bushehr nuclear power plant is a VVER type reactor with 1000 MWe power. ► Doses of public critical groups living around the plant were assessed under normal reactor operation conditions. ► PC-CREAM 98 computer code developed by the HPA was applied to assess the public doses. ► Doses are comparable with those in the FSAR, in the ER and doses monitored. ► The doses assessed are lower than the dose constraint of 0.1 mSv/y associated with the plant. - Abstract: The Unit-1 Bushehr Nuclear Power Plant (BNPP-1), constructed at the Hallileh site near Bushehr located at the coast of the Persian Gulf, Iran, is a VVER type reactor with 1000 MWe power. According to standard practices, under normal operation conditions of the plant, radiological assessment of atmospheric and aquatic releases to the environment and assessment of public exposures are considered essential. In order to assess the individual and collective doses of the critical groups of population who receive the highest dose from radioactive discharges into the environment (atmosphere and aquatic) under normal operation conditions, this study was conducted. To assess the doses, the PC-CREAM 98 computer code developed by the Radiation Protection Division of the Health Protection Agency (HPA; formerly called NRPB) was applied. It uses a standard Gaussian plume dispersion model and comprises a suite of models and data for estimation of the radiological impact assessments of routine and continuous discharges from an NPP. The input data include a stack height of 100 m annual radionuclides release of gaseous effluents from the stack and liquid effluents that are released from heat removal system, meteorological data from the Bushehr local meteorological station, and the data for agricultural products. To assess doses from marine discharges, consumption of sea fish, crustacean and mollusca were considered. According to calculation by PC-CREAM 98 computer code, the highest individual

  20. User's guide for the KBERT 1.0 code: For the knowledge-based estimation of hazards of radioactive material releases from DOE nuclear facilities

    International Nuclear Information System (INIS)

    Browitt, D.S.; Washington, K.E.; Powers, D.A.

    1995-07-01

    The possibility of worker exposure to radioactive materials during accidents at nuclear facilities is a principal concern of the DOE. The KBERT software has been developed at Sandia National Laboratories under DOE support to address this issue by assisting in the estimation of risks posed by accidents at chemical and nuclear facilities. KBERT is an acronym for Knowledge-Based system for Estimating hazards of Radioactive material release Transients. The current prototype version of KBERT focuses on calculation of doses and consequences to in-facility workers due to accidental releases of radioactivity. This report gives detailed instructions on how a user who is familiar with the design, layout and potential hazards of a facility can use KBERT to assess the risks to workers in that facility. KBERT is a tool that allows a user to simulate possible accidents and observe the predicted consequences. Potential applications of KBERT include the evaluation of the efficacy of evacuation practices, worker shielding, personal protection equipment and the containment of hazardous materials

  1. Contaminative Influence of Beef Due to the Inhalation of Air and the Ingestion of Soil of Livestock from an Acute Release of Radioactive Materials

    International Nuclear Information System (INIS)

    Hwang, Won Tae; Kim, Eun Han; Suh, Kyung Suk; Jeong, Hyo Jeon; Han, Moon Hee

    2004-01-01

    The contaminative influence of beef due to the inhalation of air and the ingestion of soil of livestock, both of which are dealt with as minor contaminative pathways in most radioecological models but may not be neglected, was comprehensively investigated with the improvement of the Korean food chain model DYNACON. As the results, it was found that both pathways can not be neglected at all in the contamination of beef in the case of an accidental release during the non-grazing period of livestock. The ingestion of soil was more influential in the contamination of beef than the inhalation of air over most time following an release. If precipitation is encountered during an accidental release, contaminative influence due to the ingestion of soil was far greater compared with the cases of no precipitation. This fact was more distinct for a long-lived radionuclide 137 Cs than a short-lived radionuclide '1 31 I (elemental iodine). Compared with the results for milk performed prior to this study, the contaminative pathways due to the inhalation of air and the ingestion of soil were more important in beef because of longer biological half-lives. On the other hand, in the case of an accidental release during the grazing period of livestock, radioactive contamination due to the ingestion of pasture was dominant irrespective of the existence of precipitation during an accidental release. It means that contaminative influence due to the inhalation of air and the ingestion of soil is negligible, like the cases of milk.

  2. Contaminative influence of beef due to the inhalation of air and the ingestion of soil of cattle in an accidental release of radioactive materials

    International Nuclear Information System (INIS)

    Hwang, W. T.; Kim, E. H.; Seo, K. S.; Jung, H. J.; Lee, S. M.; Hang, M. H.

    2004-01-01

    The contaminative influence of beef due to the inhalation of air and the ingestion of soil of cattle, both of which are dealt with as minor contaminative pathways in most radioecological models but may not be neglected, was comprehensively investigated with the improvement of the Korean dynamic food chain model DYNACON. As the results, it was found that both pathways can not be neglected at all in the contamination of beef in the case of an accidental release during the non-grazing period of cattle. The ingestion of soil was more influential in the contamination of beef than the inhalation of air over most time following an release. If precipitation is encountered during an accidental release, contaminative influence due to the ingestion of soil was far greater compared with the cases of no precipitation. This fact was more distinct for a long-lived radionuclide 137 Cs than a short-lived radionuclide 131 I (elemental iodine). Compared with the results for milk performed prior to this study, the contaminative pathways due to the inhalation of air and the ingestion of soil were more important in beef because of longer biological half-lives. In the meantime, in the case of an accidental release during the grazing period of cattle, radioactive contamination due to the ingestion of pasture was dominant irrespective of the existence of precipitation during an accidental release. It means that contaminative influence due to the inhalation of air and the ingestion of soil is negligible like the cases of milk

  3. A Monte Carlo procedure for the construction of complementary cumulative distribution functions for comparison with the EPA release limits for radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Helton, J.C.; Shiver, A.W.

    1994-10-01

    A Monte Carlo procedure for the construction of complementary cumulative distribution functions (CCDFs) for comparison with the US Environmental Protection Agency (EPA) release limits for radioactive waste disposal (40 CFR 191, Subpart B) is described and illustrated with results from a recent performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP). The Monte Carlo procedure produces CCDF estimates similar to those obtained with stratified sampling in several recent PAs for the WIPP. The advantages of the Monte Carlo procedure over stratified sampling include increased resolution in the calculation of probabilities for complex scenarios involving drilling intrusions and better use of the necessarily limited number of mechanistic calculations that underlie CCDF construction.

  4. Updated synthesis of knowledge related to the impact of radioactive releases from the damaged nuclear site of Fukushima Dai-Ichi on the marine environment - 13 July 2012

    International Nuclear Information System (INIS)

    2012-01-01

    Illustrated by tables, figures and graphs, this report first comments the evolution of the radioactive pollution of sea water: main radionuclides notices in sea water since the 21 March 2011 (with two main origins: atmospheric fallouts, liquid releases from the site), evolution of sea water contamination along the coast at the vicinity of the power station, simulation of caesium 137 dispersion in sea water off Japan. Then, it comments the evolution of the presence of radionuclides in sediments and in marine species (species with contamination level exceeding the admissible level for consumption, concentrations noticed by sea animals, expected evolution for marine species, other published data)

  5. A Monte Carlo procedure for the construction of complementary cumulative distribution functions for comparison with the EPA release limits for radioactive waste disposal

    International Nuclear Information System (INIS)

    Helton, J.C.; Shiver, A.W.

    1994-10-01

    A Monte Carlo procedure for the construction of complementary cumulative distribution functions (CCDFs) for comparison with the US Environmental Protection Agency (EPA) release limits for radioactive waste disposal (40 CFR 191, Subpart B) is described and illustrated with results from a recent performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP). The Monte Carlo procedure produces CCDF estimates similar to those obtained with stratified sampling in several recent PAs for the WIPP. The advantages of the Monte Carlo procedure over stratified sampling include increased resolution in the calculation of probabilities for complex scenarios involving drilling intrusions and better use of the necessarily limited number of mechanistic calculations that underlie CCDF construction

  6. GAMMA-CLOUD: a computer code for calculating gamma-exposure due to a radioactive cloud released from a point source

    Energy Technology Data Exchange (ETDEWEB)

    Sugimoto, O [Chugoku Electric Power Co. Inc., Hiroshima (Japan); Sawaguchi, Y; Kaneko, M

    1979-03-01

    A computer code, designated GAMMA-CLOUD, has been developed by specialists of electric power companies to meet requests from the companies to have a unified means of calculating annual external doses from routine releases of radioactive gaseous effluents from nuclear power plants, based on the Japan Atomic Energy Commission's guides for environmental dose evaluation. GAMMA-CLOUD is written in FORTRAN language and its required capacity is less than 100 kilobytes. The average ..gamma..-exposure at an observation point can be calculated within a few minutes with comparable precision to other existing codes.

  7. Well bore Flow Treatment Used to Predict Radioactive Brine Releases to the Surface from Future Drilling Penetrations into the Waste Isolation Pilot Plant (WIPP), New Mexico, USA

    International Nuclear Information System (INIS)

    Brien, D.G.O.; Stoelzel, D.M.; Hadgu, T.

    1999-01-01

    The Waste Isolation Pilot Plant (WIPP) is the U.S. Department of Energy's (DOE) mined geologic repository in southeastern New Mexico, USA.This site is designed for the permanent burial of transuranic radioactive waste generated by defense related activities.The waste produces gases when exposed to brine. This gas generation may result in increased pressures over time. Therefore, a future driller that unknowingly penetrates through the site may experience a blowout. This paper describes the methodology used to predict the resultant volumes of contaminated brine released

  8. Criteria for selection of target materials and design of high-efficiency-release targets for radioactive ion beam generation

    CERN Document Server

    Alton, G D; Liu, Y

    1999-01-01

    In this report, we define criteria for choosing target materials and for designing, mechanically stable, short-diffusion-length, highly permeable targets for generation of high-intensity radioactive ion beams (RIBs) for use at nuclear physics and astrophysics research facilities based on the ISOL principle. In addition, lists of refractory target materials are provided and examples are given of a number of successful targets, based on these criteria, that have been fabricated and tested for use at the Holifield Radioactive Ion Beam Facility (HRIBF).

  9. Simplified analytical model to simulate radionuclide release from radioactive waste trenches; Modelo simplificado para simulacao da liberacao de radionuclideos de repositorios de rejeitos radioativos

    Energy Technology Data Exchange (ETDEWEB)

    Sa, Bernardete Lemes Vieira de

    2001-07-01

    In order to evaluate postclosure off-site doses from low-level radioactive waste disposal facilities, a computer code was developed to simulate the radionuclide released from waste form, transport through vadose zone and transport in the saturated zone. This paper describes the methodology used to model these process. The radionuclide released from the waste is calculated using a model based on first order kinetics and the transport through porous media was determined using semi-analytical solution of the mass transport equation, considering the limiting case of unidirectional convective transport with three-dimensional dispersion in an isotropic medium. The results obtained in this work were compared with other codes, showing good agreement. (author)

  10. Modeling of release of radionuclides from an engineered disposal facility for shallow-land disposal of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Matsuzuru, H.; Suzuki, A.

    1989-01-01

    The computer code, ENBAR-1, for the simulation of radionuclide releases from an engineered disposal facility has been developed to evaluate the source term for subsequent migration of radionuclides in and through a natural barrier. The system considered here is that a waste package (waste form and container) is placed, together with backfill materials, into a concrete pit as a disposal unit for shallow-land disposal of low-level radioactive wastes. The code developed includes the following modules: water penetration into a concrete pit, corrosion of a drum as a container, leaching of radionuclides from a waste form, migration of radionuclides in backfill materials, release of radionuclides from the pit. The code has the advantage of its simplicity of operation and presentation while still allowing comprehensive evaluation of each element of an engineered disposal facility to be treated. The performance and source term of the facility might be readily estimated with a few key parameters to define the problem

  11. Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956)- An Assessment of Quantities released, Off-Site Radiation Doses, and Potential Excess Risks of Thyroid Cancer, Volume 1

    International Nuclear Information System (INIS)

    Apostoaei, A.I.; Burns, R.E.; Hoffman, F.O.; Ijaz, T.; Lewis, C.J.; Nair, S.K.; Widner, T.E.

    1999-01-01

    In the early 1990s, concern about the Oak Ridge Reservation's past releases of contaminants to the environment prompted Tennessee's public health officials to pursue an in-depth study of potential off-site health effects at Oak Ridge. This study, the Oak Ridge dose reconstruction, was supported by an agreement between the U.S. Department of Energy (DOE) and the State of Tennessee, and was overseen by a 12-member panel appointed by Tennessee's Commissioner of Health. One of the major contaminants studied in the dose reconstruction was radioactive iodine, which was released to the air by X-10 (now called Oak Ridge National Laboratory) as it processed spent nuclear reactor fuel from 1944 through 1956. The process recovered radioactive lanthanum for use in weapons development. Iodine concentrates in the thyroid gland so health concerns include various diseases of the thyroid, such as thyroid cancer. The large report, ''Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956) - An Assessment of Quantities Released, Off-site Radiation Doses, and Potential Excess Risks of Thyroid Cancer,'' is in two volumes. Volume 1 is the main body of the report, and Volume 1A, which has the same title, consists of 22 supporting appendices. Together, these reports serve the following purposes: (1) describe the methodologies used to estimate the amount of iodine-131 (I-131) released; (2) evaluate I-131's pathway from air to vegetation to food to humans; (3) estimate doses received by human thyroids; (4) estimate excess risk of acquiring a thyroid cancer during ones lifetime; and (5) provide equations, examples of historical documents used, and tables of calculated values. Results indicate that females born in 1952 who consumed milk from a goat pastured a few miles east of X-10 received the highest doses from I-131 and would have had the highest risks of contracting thyroid cancer. Doses from cow's milk are considerably less . Detailed

  12. Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956)- An Assessment of Quantities released, Off-Site Radiation Doses, and Potential Excess Risks of Thyroid Cancer, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Apostoaei, A.I.; Burns, R.E.; Hoffman, F.O.; Ijaz, T.; Lewis, C.J.; Nair, S.K.; Widner, T.E.

    1999-07-01

    In the early 1990s, concern about the Oak Ridge Reservation's past releases of contaminants to the environment prompted Tennessee's public health officials to pursue an in-depth study of potential off-site health effects at Oak Ridge. This study, the Oak Ridge dose reconstruction, was supported by an agreement between the U.S. Department of Energy (DOE) and the State of Tennessee, and was overseen by a 12-member panel appointed by Tennessee's Commissioner of Health. One of the major contaminants studied in the dose reconstruction was radioactive iodine, which was released to the air by X-10 (now called Oak Ridge National Laboratory) as it processed spent nuclear reactor fuel from 1944 through 1956. The process recovered radioactive lanthanum for use in weapons development. Iodine concentrates in the thyroid gland so health concerns include various diseases of the thyroid, such as thyroid cancer. The large report, ''Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956) - An Assessment of Quantities Released, Off-site Radiation Doses, and Potential Excess Risks of Thyroid Cancer,'' is in two volumes. Volume 1 is the main body of the report, and Volume 1A, which has the same title, consists of 22 supporting appendices. Together, these reports serve the following purposes: (1) describe the methodologies used to estimate the amount of iodine-131 (I-131) released; (2) evaluate I-131's pathway from air to vegetation to food to humans; (3) estimate doses received by human thyroids; (4) estimate excess risk of acquiring a thyroid cancer during ones lifetime; and (5) provide equations, examples of historical documents used, and tables of calculated values. Results indicate that females born in 1952 who consumed milk from a goat pastured a few miles east of X-10 received the highest doses from I-131 and would have had the highest risks of contracting thyroid cancer. Doses from cow

  13. LEAF: a computer program to calculate fission product release from a reactor containment building for arbitrary radioactive decay chains

    International Nuclear Information System (INIS)

    Lee, C.E.; Apperson, C.E. Jr.; Foley, J.E.

    1976-10-01

    The report describes an analytic containment building model that is used for calculating the leakage into the environment of each isotope of an arbitrary radioactive decay chain. The model accounts for the source, the buildup, the decay, the cleanup, and the leakage of isotopes that are gas-borne inside the containment building

  14. Radioactive pollution

    International Nuclear Information System (INIS)

    Steiner, R.

    1987-01-01

    In the wake of the Chernobyl reactor accident on April 26, 1986, many individual values for radioactivity in the air, in foodstuffs and in the soil were measured and published. Prof. Dr. Rolf Steiner, Wiesbaden, the author of this paper, evaluated the host of data - mostly official pollution data -, drew conclusions regarding the radioactivity actually released at Chernobyl, and used the data to test the calculation model adotped by the Radiation Protection Ordinance. (orig./RB) [de

  15. Combining scenarios in a calculation of the overall probability distribution of cumulative releases of radioactivity from the Waste Isolation Pilot Plant, southeastern New Mexico

    International Nuclear Information System (INIS)

    Tierney, M.S.

    1991-11-01

    The Waste Isolation Pilot Plant (WIPP), in southeastern New Mexico, is a research and development facility to demonstrate safe disposal of defense-generated transuranic waste. The US Department of Energy will designate WIPP as a disposal facility if it meets the US Environmental Protection Agency's standard for disposal of such waste; the standard includes a requirement that estimates of cumulative releases of radioactivity to the accessible environment be incorporated in an overall probability distribution. The WIPP Project has chosen an approach to calculation of an overall probability distribution that employs the concept of scenarios for release and transport of radioactivity to the accessible environment. This report reviews the use of Monte Carlo methods in the calculation of an overall probability distribution and presents a logical and mathematical foundation for use of the scenario concept in such calculations. The report also draws preliminary conclusions regarding the shape of the probability distribution for the WIPP system; preliminary conclusions are based on the possible occurrence of three events and the presence of one feature: namely, the events ''attempted boreholes over rooms and drifts,'' ''mining alters ground-water regime,'' ''water-withdrawal wells provide alternate pathways,'' and the feature ''brine pocket below room or drift.'' Calculation of the WIPP systems's overall probability distributions for only five of sixteen possible scenario classes that can be obtained by combining the four postulated events or features

  16. The radiological consequences of notional accidental releases of radioactivity from fast breeder reactors: sensitivity to the dose-effect relationships adopted for early biological effects

    International Nuclear Information System (INIS)

    Kelly, G.N.; Simmonds, J.R.; Smith, H.; Stather, J.W.

    1979-07-01

    This study considered the sensitivity to the dose-response relationships adopted for the estimation of early biological effects from notional accidental releases of radioactivity from fast breeder reactors. Two distinct aspects were considered: the sensitivity of the predicted consequences to variation in the dose-mortality relationships for irradiation of the bone marrow and the lung; and the influence of simple supportive medical treatment in reducing the incidence of early deaths in the exposed population. The numbers of early effects estimated in the initial study were relatively insensitive to variation in the dose-mortality relationships within the bounds proposed. The few exceptions concerned releases of particular nuclide composition, and the variation in the predicted consequences could be around an order of magnitude; the absolute numbers of effects however were in general small when the sensitivity was most pronounced. The reduction in the incidence of early deaths when using simple supportive treatment varied markedly with the nuclide composition of the release. Areas of uncertainty were identified where further research and investigation might most profitably be directed with a view to improving the reliability of the dose-effect relationships adopted and hence of the predicted consequences of the release considered. (author)

  17. Liquid pathway generic study. Impacts of accidental radioactive releases to the hydrosphere from floating and land-based nuclear power plants

    International Nuclear Information System (INIS)

    1978-02-01

    The staff concludes that for representative sites, there are differences in the impacts of accidental radioactive releases to the hydrosphere between floating nuclear plants (FNPs) and land-based plants (LBPs) of the ice-condenser type. The consequences of releases from design basis accidents are found to be lower for an FNP than for an LBP. For core-melt events which we consider to be of very low probability, the staff results indicate that the expected liquid pathway consequences are higher at an FNP than at an LBP, and that interdiction at the site is not likely for an FNP. The staff considers this combination of differences in release magnitude and interdiction potential to be significant. An assessment of the overall significance of the total risk associated with potential releases to liquid and airborne pathways will be considered in a forthcoming environmental impact statement for the FNP. This environmental impact statement will include a consideration of the environmental, social, and economic impacts of the operation of the FNP, as well as a value-impact analysis of alternatives which may avoid or mitigate radiological impacts to the environment

  18. An optimisation technology for more precise determination of a source for modelling radioactive releases to the atmosphere

    International Nuclear Information System (INIS)

    Golubenkov, A.V.; Borodin, R.V.

    1993-01-01

    This paper deals with refining meteorological parameters and source term characteristics required for models of atmospheric dispersion and deposition of radioactivity in the area adjacent to facilities affected by a nuclear accident. The proposed methodology involves the minimisation of an objective function that is the sum of weighted norms of deviations between measured and model values. The measured values are spatially interpolated and the weights determined by the type of measurement and the precision of interpolation. Consideration is given to a technique of initial approximation based on calculating regression functions for the parameters to be refined using measured radioactivity. Coefficients for these functions are calculated by analysis of a multitude of simulated situations. Also discussed is a heuristic method, using multiple random perturbations on the data, for assessing the validity of the solution. Based on these calculations confidence intervals are determined for the refined model parameters. (author)

  19. Inverse modelling for real-time estimation of radiological consequences in the early stage of an accidental radioactivity release

    Czech Academy of Sciences Publication Activity Database

    Pecha, Petr; Šmídl, Václav

    2016-01-01

    Roč. 164, č. 1 (2016), s. 377-394 ISSN 0265-931X R&D Projects: GA MŠk(CZ) 7F14287; GA MV VG20102013018 Institutional support: RVO:67985556 Keywords : Inverse modelling * recursive radioactive plume tracking * Improvement of population protection * monitoring network capability Subject RIV: AQ - Safety, Health Protection, Human - Machine Impact factor: 2.310, year: 2016 http://library.utia.cas.cz/separaty/2016/AS/pecha-0460631.pdf

  20. Stowing of radioactive packages, materials or objects for their transport. Guide nr 27, Release of 30 August 2016

    International Nuclear Information System (INIS)

    2016-01-01

    A good package stowing is part of an in-depth defence approach to ensure the safety of transport operations in the case of radioactive materials. This guide thus presents a set of recommendations to ensure this safety, recalls regulatory requirements, and presents recommendations made by the ASN for specific stowing training. This document concerns all kinds of transports (road, rail, river, sea, and air). After having indicated the different regulatory references, standards and recommendations, it proposes an overview of the applicable regulatory framework and technical requirements for stowing in France and in the EU in the case of road transport, of rail transport and of sea transport, and in France and in the world for the case of air transport. The next part details regulatory requirements and recommendations made by the ASN for the stowing of radioactive loads: commitment of the company's management, specific training for concerned personnel, definition of packing and stowing plans or of specific instructions, selection of the stowing system, adequacy of the used stowing equipment, documentation to achieve a good stowing, stowing quality control. Then, recommendations are made for the undertaking of a specific training on radioactive load stowing: training modalities, training content, training objectives (for designers, operators and controllers)

  1. The radiological consequences of notional accidental releases of radioactivity from fast breeder reactors: the influence of the meteorological conditions

    International Nuclear Information System (INIS)

    Hemming, C.R.; Hallam, J.; Kelly, G.N.

    1980-04-01

    The radiological consequences of a wide range of notional accidental releases from a 1300 MW(e) LMFBR (liquid Metal-cooled Fast Breeder Reactor) were assessed in a previous study by the National Radiological Protection Board. In the present study the sensitivity of the predicted consequences to the meteorological conditions was investigated. The influence of the wind direction, and hence the distribution of the exposed population, and of atmospheric stability at the time of the release are considered separately. Conclusions are reached on the precision required in specifying atmospheric stability conditions to estimate reliably the distribution of possible consequences following a given release of activity. The probability distributions of consequences for selected releases from two locations are evaluated taking account of the frequency distribution of wind direction and atmospheric stability at each location. The variation is large and demonstrates the importance of taking account of the whole range of meteorological conditions when assessing the risk presented by an accidental release of activity. (author)

  2. Development of three-dimensional trajectory model for detecting source region of the radioactive materials released into the atmosphere

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Kyung Suk; Park, Ki Hyun; Min, Byung Il; Kim, Sora; Yang, Byung Mo [Nuclear Environmental Safety Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-05-15

    It is necessary to consider the overall countermeasure for analysis of nuclear activities according to the increase of the nuclear facilities like nuclear power and reprocessing plants in the neighboring countries including China, Taiwan, North Korea, Japan and South Korea. South Korea and comprehensive nuclear-test-ban treaty organization (CTBTO) are now operating the monitoring instruments to detect radionuclides released into the air. It is important to estimate the origin of radionuclides measured using the detection technology as well as the monitoring analysis in aspects of investigation and security of the nuclear activities in neighboring countries. A three-dimensional forward/backward trajectory model has been developed to estimate the origin of radionuclides for a covert nuclear activity. The developed trajectory model was composed of forward and backward modules to track the particle positions using finite difference method. A three-dimensional trajectory model was validated using the measured data at Chernobyl accident. The calculated results showed a good agreement by using the high concentration measurements and the locations where was near a release point. The three-dimensional trajectory model had some uncertainty according to the release time, release height and time interval of the trajectory at each release points. An atmospheric dispersion model called long-range accident dose assessment system (LADAS), based on the fields of regards (FOR) technique, was applied to reduce the uncertainties of the trajectory model and to improve the detective technology for estimating the radioisotopes emission area. The detective technology developed in this study can evaluate in release area and origin for covert nuclear activities based on measured radioisotopes at monitoring stations, and it might play critical tool to improve the ability of the nuclear safety field.

  3. Derived emergency reference levels for the introduction of countermeasures in the early to intermediate phases of emergencies involving the release of radioactive materials to atmosphere

    International Nuclear Information System (INIS)

    Linsley, G.S.; Crick, M.J.; Simmonds, J.R.; Haywood, S.M.

    1986-03-01

    Derived Emergency Reference Levels (DERLs) are practical quantities intended for use in the aftermath of an accident involving the release of radioactive materials to atmosphere and for use in preparing emergency plans for the protection of the public. The results of environmental measurements may be compared with them as a means of assessing the seriousness of the release and in order to form judgements on the need to institute protective countermeasures. DERLs are the practical expression of Emergency Reference Levels, the radiological criteria for planning the introduction of emergency countermeasures. DERLs have been evaluated for a range of radionuclides which could be released in the event of an accident and for a number of different exposure pathways that are relevant in the initial phase of an accident. These pathways are: inhalation of activity both in the plume and resuspended from the ground; skin irradiation by β-emitting noble gases in the cloud; doses from β-emitters deposited on the skin; and external γ irradiation from ground deposits. (author)

  4. A reliability study on influence of the geosphere thickness over the activity release from a near surface radioactive waste repository

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, Lais Alencar de, E-mail: laguiar@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil); Damaso, Vinicius Correa, E-mail: vcdamaso@gmail.com [Estado-Maior do Exercito (EME/EB), Brasilia, DF (Brazil)

    2013-07-01

    Infiltration of water into a waste disposal facility and into the waste region is the main factor inducing the release of radionuclides from a disposal facility. Since infiltrating water flow is dependent on the natural percolation at the site and the performance of engineered barriers, its prediction requires modelling of unsaturated water flow through intact or partially/completely failed components of engineered barriers and through the rock layer of the geosphere on which the repository is constructed. The engineered barriers include the cover systems, concrete vault, backfill, waste forms, and overpacks. This paper aims to carry out a performance study regarding a near surface repository in terms of reliability engineering. It is assumed that surface water infiltrates through the barriers reaching the matrix where radionuclides are contained, thus releasing them into the environment. The repository consists of a set of barriers which are considered saturated porous medium. As results, this paper presents the relation between the thickness of the geosphere layer and the radionuclide release rate in terms of activity. Such results represent a useful information for choosing the repository sites in order to keep the released activity in acceptable levels over time. (author)

  5. 10 CFR 50.34a - Design objectives for equipment to control releases of radioactive material in effluents-nuclear...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Design objectives for equipment to control releases of... out in appendix I to this part provide numerical guidance on design objectives for light-water-cooled... unrestricted areas be kept as low as is reasonably achievable. These numerical guides for design objectives and...

  6. A reliability study on influence of the geosphere thickness over the activity release from a near surface radioactive waste repository

    International Nuclear Information System (INIS)

    Aguiar, Lais Alencar de; Damaso, Vinicius Correa

    2013-01-01

    Infiltration of water into a waste disposal facility and into the waste region is the main factor inducing the release of radionuclides from a disposal facility. Since infiltrating water flow is dependent on the natural percolation at the site and the performance of engineered barriers, its prediction requires modelling of unsaturated water flow through intact or partially/completely failed components of engineered barriers and through the rock layer of the geosphere on which the repository is constructed. The engineered barriers include the cover systems, concrete vault, backfill, waste forms, and overpacks. This paper aims to carry out a performance study regarding a near surface repository in terms of reliability engineering. It is assumed that surface water infiltrates through the barriers reaching the matrix where radionuclides are contained, thus releasing them into the environment. The repository consists of a set of barriers which are considered saturated porous medium. As results, this paper presents the relation between the thickness of the geosphere layer and the radionuclide release rate in terms of activity. Such results represent a useful information for choosing the repository sites in order to keep the released activity in acceptable levels over time. (author)

  7. Malicious release of radioactive materials in urban area. Exposure of the public and emergency staff, protective measures; Boeswillige Freisetzung radioaktiver Stoffe in urbanen Bereichen. Exposition von Bevoelkerung und Einsatzpersonal, Schutzmassnahmen

    Energy Technology Data Exchange (ETDEWEB)

    Koch, Wolfgang [Fraunhofer-Institut fuer Toxikologie und Experimentelle Medizin ITEM, Hannover (Germany). Bereich Aerosolforschung und Analytische Chemie; Lange, Florentin

    2016-07-01

    The preparedness for hypothetical radiological scenarios is part of the tasks for governmental authorities, safety and emergency organizations and the staff in case of the incident. The EURATOM guideline for radiation protection has to be implemented into national laws. According to the guidelines it is required that emergency planning has to be prepared for hypothetical radiological scenarios including terroristic or other maliciously motivated attacks using radioactive materials. The study includes assumptions on the released respirable radioactivity, restriction of the hazardous area, wind induced re-suspension of radioactive dusts and inhalation exposure, and mitigation measures.

  8. Radioactive Waste.

    Science.gov (United States)

    Blaylock, B. G.

    1978-01-01

    Presents a literature review of radioactive waste disposal, covering publications of 1976-77. Some of the studies included are: (1) high-level and long-lived wastes, and (2) release and burial of low-level wastes. A list of 42 references is also presented. (HM)

  9. The Use of Radioactive Marker as a Tool to Evaluate the Drug Release in Plasma and Particle Biodistribution of Block Copolymer Nanoparticles

    Directory of Open Access Journals (Sweden)

    Sharon Johnstone

    2011-01-01

    Full Text Available Diblock copolymer nanoparticles encapsulating a paclitaxel prodrug, Propac 7, have been used to demonstrate the usefulness of a nonmetabolizable radioactive marker, cholesteryl hexadecyl ether (CHE, to evaluate nanoparticle formulation variables. Since CHE did not exchange out of the nanoparticles, the rate of clearance of the CHE could be used as an indicator of nanoparticle stability in vivo. We simultaneously monitored prodrug circulation and carrier circulation in the plasma and the retention of CHE relative to the retention of prodrug in the plasma was used to distinguish prodrug release from nanoparticle plasma clearance. Nanoparticles labelled with CHE were also used to evaluate accumulation of nanoparticles in the tumour. This marker has provided relevant data which we have applied to optimise our nanoparticle formulations.

  10. Ecotoxicological screen of Potential Release Site 50-006(d) of Operable Unit 1147 of Mortandad Canyon and relationship to the Radioactive Liquid Waste Treatment Facilities project

    International Nuclear Information System (INIS)

    Gonzales, G.J.; Newell, P.G.

    1996-04-01

    Potential ecological risk associated with soil contaminants in Potential Release Site (PRS) 50-006(d) of Mortandad Canyon at the Los Alamos National Laboratory was assessed by performing an ecotoxicological risk screen. The PRS surrounds Outfall 051, which discharges treated effluent from the Radioactive Liquid Waste Treatment Facility. Discharge at the outfall is permitted under the Clean Water Act National Pollution Discharge Elimination System. Radionuclide discharge is regulated by US Department of Energy (DOE) Order 5400.5. Ecotoxicological Screening Action Levels (ESALSs) were computed for nonradionuclide constituents in the soil, and human risk SALs for radionuclides were used as ESALs. Within the PRS and beginning at Outfall 051, soil was sampled at three points along each of nine linear transects at 100-ft intervals. Soil samples from 3 depths for each sampling point were analyzed for the concentration of a total of 121 constituents. Only the results of the surface sampling are reported in this report

  11. The development of the American National Standard 'control of radioactive surface contamination on materials equipment and facilities to be released for uncontrolled use'

    International Nuclear Information System (INIS)

    Shapiro, J.

    1980-01-01

    A new standard submitted by the Health Physics Society Standards Committee to the American National Standards Institute concerning radioactive surface contamination of materials and equipment is discussed. The chronological events in the development of this standard are given. The standard provides criteria for the release for uncontrolled use of materials, equipment and facilities contaminated or potentially contaminated with radioactivity. Permissible contamination limits are specified for: 1) long lived alpha emitters except natural uranium and thorium, 2) more hazardous beta-gamma emitters, 3) less hazardous beta-gamma emitters and 4) natural uranium and thorium. A contamination reference level of 1000 dpm/100 cm 2 for 90 Sr was set as the basis for assigning limits to radionuclides presenting an ingestion hazard and other radionuclides were grouped based on the values of their maximum permissible concentration (MPC) in water relative to 90 Sr. The contamination limit for 239 Pu was chosen as the basis for assigning limits based on MPC in air to radionuclides presenting an inhalation hazard; a value of 100 dpm/100 cm 2 was adopted in the standard. An upper limit of 5000 dpm/100 cm 2 for surface contamination was selected for the standard. (UK)

  12. Examination of a measuring method for fallout radioactivity released by the accident of the Fukushima Dai-ichi NPS. Surface contamination measurement

    International Nuclear Information System (INIS)

    Yoshii, Taiki; Kawasaki, Satoru

    2013-08-01

    Radioactive nuclides were released in the atmosphere by the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station in March, 2011, and they are detected on the materials that had no artificial radioactive nuclides before the accident. Confronted with this situation, NISA issued a guideline titled 'A guideline regarding treatment of materials in nuclear facilities considering the influence of fallout released from the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station' on March 30, 2012. Nuclear Regulatory Authority refers to applying the existing bylaw until the time to make decision of the updated bylaw. The guideline shows that after judging whether there is the influence of fallout or not, the conventional clearance and NR systems can be used when there is no influence of fallout. On the other hand, the special treatment is required when it is judged that there is the influence. This report describes a specific example of measuring method to evaluate the influence of fallout, in case of surface contamination. This report focused surface contamination of flat object as target. Preliminary investigation shows that the distribution of surface contamination due to fallout is near to lognormal distribution. Therefore, the sampling measurement can be adopted. The average surface contamination of target is decided from sampling data by using 90% upper confidence limit of Chebyshev inequality. Also, the minimum sampling number is decided. The evaluation of the influence of fallout is judged from the result of surface contamination measurement, weight of target and surface area of target. (author)

  13. Dose and dose commitment calculations from groundwaterborne radio-active elements released from a repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    Bergstroem, U.

    1983-05-01

    The turnover of radioactive matter entering the biosphere with groundwater has been studied with regard to exposure and doses to critical groups and populations. Two main recipients, a well and a lake, have been considered for the inflow of groundwaterborne nuclides. Mathematical models of a set of coupled ecosystems on regional, intermediate and global levels have been used for calculations of doses. The intermediate system refers to the Baltic Sea. The mathematical treatment of the model is based upon compartment theory with first order kinetics and also includes products in decay chains. The time-dependent exposures have been studied for certain long-lived nuclides of radiological interest in waste from disposed fuel. Dose and dose commitment have been calculated for different episodes for inflow to the biosphere. (author)

  14. Vortex-Concept for Radioactivity Release Prevention at NPP: Development of Computational Model of Lab-Scale Experimental Setup

    Energy Technology Data Exchange (ETDEWEB)

    Ullah, Sana; Sung, Yim Man; Park, Jin Soo; Sung Hyung Jin [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    The experimental validation of the vortex-like air curtain concept and use of an appropriate CFD modelling approach for analyzing the problem becomes crucial. A lab-scale experimental setup is designed to validate the proposed concept and CFD modeling approach as a part of validation process. In this study, a computational model of this lab-scale experiment setup is developed using open source CFD code OpenFOAM. The computational results will be compared with experimental data for validation purposes in future, when experimental data is available. 1) A computation model of a lab-scale experimental setup, designed to validate the concept of artificial vortex-like airflow generation for application to radioactivity dispersion prevention in the event of severe accident, was developed. 2) The mesh sensitivity study was performed and a mesh of about 2 million cells was found to be sufficient for this setup.

  15. Preliminary scenarios for the release of radioactive waste from a hypothetical repository in basalt of the Columbia Plateau

    International Nuclear Information System (INIS)

    Hunter, R.L.

    1983-10-01

    Nine release phenomena - normal flow of water, tectonic disturbance of the fracture network, intersection of a new fault with the repository, glaciation, fluvia erosion, thermomechanical disturbances, subsidence, seal failure, and drilling - give rise to 318 preliminary scenarios for the release of waste from a hypothetical high-level-waste repository in basalt. The scenarios have relative probabilities that range over several orders of magnitude. The relative probabilities provide a means of screening the scenarios for the more limited set to be subjected to consequence analysis. Lack of data and of preliminary modeling, however, lead to great uncertainties in the highly conservative probabilities assigned here. As a result, the recommendations in this report are directed at resolution of the major uncertainties in the relative probabilities of the preliminary scenarios. The resolution of some of the uncertainties should help in the selection of the suite of scenarios for final consequence analysis. 38 references, 22 figures, 18 tables

  16. Dose estimation and prediction of radiation effects on aquatic biota resulting from radioactive releases from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Blaylock, B.G.; Witherspoon, J.P.

    1975-01-01

    Aquatic organisms are exposed to radionuclides released to the environment during various steps of the nuclear fuel cycle. Routine releases from these processes are limited in compliance with technical specifications and requirements of federal regulations. These regulations reflect I.C.R.P. recommendations which are designed to provide an environment considered safe for man. It is generally accepted that aquatic organisms will not receive damaging external radiation doses in such environments; however, because of possible bioaccumulation of radionuclides there is concern that aquatic organisms might be adversely affected by internal doses. The objectives of this paper are: to estimate the radiation dose received by aquatic biota from the different processes and determine the major dose-contributing radionuclides, and to assess the impact of estimated doses on aquatic biota. Dose estimates are made by using radionuclide concentration measured in the liquid effluents of representative facilities. This evaluation indicates the potential for the greatest radiation dose to aquatic biota from the nuclear fuel supply facilities (i.e., uranium mining and milling). The effects of chronic low-level radiation on aquatic organisms are discussed from somatic and genetic viewpoints. Based on the body of radiobiological evidence accumulated up to the present time, no significant deleterious effects are predicted for populations of aquatic organisms exposed to the estimated dose rates resulting from routine releases from conversion, enrichment, fabrication, reactors and reprocessing facilities. At the doses estimated for milling and mining operations it would be difficult to detect radiation effects on aquatic populations; however, the significance of such radiation exposures to aquatic populations cannot be fully evaluated without further research on effects of chronic low-level radiation. (U.S.)

  17. Dose commitments due to radioactive releases from nuclear power plant sites: Methodology and data base. Supplement 1

    Energy Technology Data Exchange (ETDEWEB)

    Baker, D.A. [Pacific Northwest National Lab., Richland, WA (United States)

    1996-06-01

    This manual describes a dose assessment system used to estimate the population or collective dose commitments received via both airborne and waterborne pathways by persons living within a 2- to 80-kilometer region of a commercial operating power reactor for a specific year of effluent releases. Computer programs, data files, and utility routines are included which can be used in conjunction with an IBM or compatible personal computer to produce the required dose commitments and their statistical distributions. In addition, maximum individual airborne and waterborne dose commitments are estimated and compared to 10 CFR Part 50, Appendix 1, design objectives. This supplement is the last report in the NUREG/CR-2850 series.

  18. Dose commitments due to radioactive releases from nuclear power plant sites: Methodology and data base. Supplement 1

    International Nuclear Information System (INIS)

    Baker, D.A.

    1996-06-01

    This manual describes a dose assessment system used to estimate the population or collective dose commitments received via both airborne and waterborne pathways by persons living within a 2- to 80-kilometer region of a commercial operating power reactor for a specific year of effluent releases. Computer programs, data files, and utility routines are included which can be used in conjunction with an IBM or compatible personal computer to produce the required dose commitments and their statistical distributions. In addition, maximum individual airborne and waterborne dose commitments are estimated and compared to 10 CFR Part 50, Appendix 1, design objectives. This supplement is the last report in the NUREG/CR-2850 series

  19. The radiological situation at the atolls of Mururoa and Fangataufa. Technical report. V. 6. Doses due to radioactive materials present in the environment or released from the atolls

    Energy Technology Data Exchange (ETDEWEB)

    International Advisory Committee, Task Group A

    1998-08-01

    In the previous volumes of this Report the concentrations of residual radioactivity in the environment of Mururoa and Fangataufa atolls have been described, and assessment made of the releases to the environment in the future. The further step in radiological assessment is the derivation of radiation doses that arise to actually or potentially exposed populations, from these concentrations and releases. These doses are estimated in this report. The existence of a hypothetical population resident on Mururoa is postulated as the group which would be most exposed. Doses to this group are estimated together with doses to maximally exposed residents on nearby South Pacific islands, and further afield. An assessment of the potential environmental impact of the residual contaminant radionuclides from the nuclear weapons testing at Mururoa and Fangataufa requires estimates of the incremental dose rates to a variety of marine organisms inhabiting a number of different ecological niches. These estimated dose rates provide the only secure basis for an assessment of the potential radiation effects in the organisms. The approach adopted for this assessment is that employed in a number of recent studies and adapts the dosimetry models for the particular organisms of interest in the atoll environment Refs, figs, tabs. In six volumes

  20. The radiological situation at the atolls of Mururoa and Fangataufa. Technical report. V. 6. Doses due to radioactive materials present in the environment or released from the atolls

    International Nuclear Information System (INIS)

    1998-08-01

    In the previous volumes of this Report the concentrations of residual radioactivity in the environment of Mururoa and Fangataufa atolls have been described, and assessment made of the releases to the environment in the future. The further step in radiological assessment is the derivation of radiation doses that arise to actually or potentially exposed populations, from these concentrations and releases. These doses are estimated in this report. The existence of a hypothetical population resident on Mururoa is postulated as the group which would be most exposed. Doses to this group are estimated together with doses to maximally exposed residents on nearby South Pacific islands, and further afield. An assessment of the potential environmental impact of the residual contaminant radionuclides from the nuclear weapons testing at Mururoa and Fangataufa requires estimates of the incremental dose rates to a variety of marine organisms inhabiting a number of different ecological niches. These estimated dose rates provide the only secure basis for an assessment of the potential radiation effects in the organisms. The approach adopted for this assessment is that employed in a number of recent studies and adapts the dosimetry models for the particular organisms of interest in the atoll environment

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  2. Review of infrastructures and preparedness systems in France, Germany and United Kingdom for potential releases of radioactivity into the environment

    International Nuclear Information System (INIS)

    Fiedler, I.; Voigt, G.; Lochard, J.; Croueail, P.; Nisbet, A.; Mercer, J.; Green, N.; Wilkins, B.

    2004-01-01

    For the European SAGE-Project a review of the existing infrastructures and preparedness systems in France, Germany and United Kingdom concerning radiation protection with regard to a long term contamination after a nuclear accident was made. This review clearly shows that the infrastructure in all three countries regulates the situation during and shortly after a nuclear incident but not in case that a radioactive contamination will last for long time. For that situation it is necessary to install local information centres in the affected area with sufficient trained staff. To improve the confidence of the population in possible measures implemented by the authorities a copious and understandable information and education must be provided. Especially doctors, teachers, kindergarten teachers and mothers have to get the possibility to be educated in a reasonable way how to deal with a short, middle and long term contamination. The concerned population must be able to control the own radiological situation by measuring their environment and their food and by reducing food contamination by appropriate reasonable measures. (orig.)

  3. Review of infrastructures and preparedness systems in France, Germany and United Kingdom for potential releases of radioactivity into the environment

    Energy Technology Data Exchange (ETDEWEB)

    Fiedler, I.; Voigt, G. [International Atomic Energy Agency, Vienna (Austria); Lochard, J.; Croueail, P. [Centre d' Etudes sur l' Evaluation de la Protection dans le Domaine Nucleaire, Paris (France); Nisbet, A.; Mercer, J.; Green, N.; Wilkins, B. [National Radiological Protection Board, Chilton (United Kingdom)

    2004-07-01

    For the European SAGE-Project a review of the existing infrastructures and preparedness systems in France, Germany and United Kingdom concerning radiation protection with regard to a long term contamination after a nuclear accident was made. This review clearly shows that the infrastructure in all three countries regulates the situation during and shortly after a nuclear incident but not in case that a radioactive contamination will last for long time. For that situation it is necessary to install local information centres in the affected area with sufficient trained staff. To improve the confidence of the population in possible measures implemented by the authorities a copious and understandable information and education must be provided. Especially doctors, teachers, kindergarten teachers and mothers have to get the possibility to be educated in a reasonable way how to deal with a short, middle and long term contamination. The concerned population must be able to control the own radiological situation by measuring their environment and their food and by reducing food contamination by appropriate reasonable measures. (orig.)

  4. Natural analogue approach for estimating the health risks from release and migration of radionuclides from radioactive waste

    International Nuclear Information System (INIS)

    Gilbert, T.L.

    1983-01-01

    The health risks from radioactive waste may be expressed as a sum of products of transfer factors that characterize the causal chain of events between disposal of radionuclides in a waste field and the consequent health effects. Model estimates for the transfer factors are commonly obtained by modeling transport and other mechanisms in the subsystems that form the links in the causal chain. Natural estimates of some conversion factors for naturally occurring radionuclides can be obtained from data on the concentrations of naturally occurring radionuclides in soil, food, and the human body. These model and natural estimates can be used with scaling procedures to estimate the uncertainties and to obtain better estimates of the values. The scaling procedures take into account the differences in the source characteristics for radionuclides in a waste field of limited size and for radionuclides generally distributed in the natural environment. The ratios of the natural estimates to the model estimates for several transfer factors and several radionuclides belonging to the U-238 decay series have been determined. These ratios range from 1/8 to 4/1 for food-concentration/source-concentration transfer factors for the food pathways and from 1 to 77 for dose-rate/source-concentration transfer factors for the internal radiation dose pathways to various organs. 14 references

  5. Dose rates as a function of time due to postulated radionuclide releases from the U.S. Yucca Mountain high-level radioactive waste repository

    International Nuclear Information System (INIS)

    Moeller, Dade W.; Sun, Lin-Shen C.; Cherry, Robert

    2008-01-01

    The Yucca Mountain repository, which is located in a remote area in the State of Nevada, is being constructed for the long-term care and disposal of spent nuclear fuel and vitrified high-level radioactive waste. In accordance with U.S. law, the U.S. Environmental Protection Agency (USEPA) promulgated Standards that limit the dose rates to members of the public due to the consumption of ground water, alone, and the consumption of ground water plus agricultural products irrigated with the contaminated ground water, and other exposures, such as those from external sources and the inhalation of airborne radioactive materials. As part of this exercise, the USEPA identified eight specific radionuclides to which their Standards are to apply. These are: 14 C, 99 Tc, 129 I, 226 Ra, 228 Ra, 237 Np, 239 Pu, and 241 Am. For purposes of the associated dose rate estimates, a range of conservative assumptions have been applied, all of which are designed to assure that the estimated dose rates are well above what might be expected under 'real-world' conditions. As a first step, it was assumed that: (1) at 10 4 year after repository closure, a fractional release of 10 -5 of the entire repository radionuclide inventory occurred; (2) the only prior reduction in the inventory was that due to radioactive decay; and (3) the sole path of exposure to neighboring population groups was through the consumption of 2 L d -1 of contaminated ground water. The accompanying analyses revealed that, of the eight radionuclides, only 226 Ra, 237 Np, and 239 Pu, will represent a significant source of dose at that time. To provide perspective and insights, the next step was to estimate the committed effective dose rates for all eight radionuclides based on an assumed fractional release each year of 10 -5 of the inventory from the time of repository closure up through the 10 6 year. For purposes of providing perspective, it was assumed that each dose rate estimate was independent, that is, no releases

  6. The choice of individual dose criterion at which to restrict agricultural produce following an unplanned release of radioactive material to atmosphere

    International Nuclear Information System (INIS)

    Dionian, J.; Simmonds, J.R.

    1985-06-01

    In the event of an accidental release of radioactive material to atmosphere, the introduction of emergency countermeasures will be based on the need to limit the risk to individuals. However, it has been suggested that a form of cost-benefit analysis may be used as an input to decisions on the withdrawal of countermeasures, although it is recognised that these decisions may be influenced by factors other than those directly related to radiological protection. In this study, a method based on cost-benefit analysis is illustrated for assessing the optimum level of individual dose at which restrictions on agricultural production may be considered. This requires monetary values to be assigned to both the lost food production and to the health detriment, expressed as the collective effective dose equivalent commitment. It has been assumed in this analysis that food-supply restrictions are both introduced and withdrawn at the same projected level of annual individual dose. The effect on the optimum dose level of the following parameters is examined: the type of produce restricted; the size of the release; the site and direction of the release; the weather conditions; and the cost assigned to unit collective dose. It is shown that the optimum dose criterion, based on the effective dose equivalent received by an individual from a years intake of food, varies over practically the whole range of individual dose considered, i.e., 0.1 to 50 mSv. However, it is concluded that 5 mSv would represent the optimum dose criterion in a substantial number of cases. (author)

  7. Hypothesis of a nuclear accident to the nuclear power plant of Gravelines with important radioactive release out of the site: risks prevention, intervention strategies. Evaluation of the sensitization to the nuclear risk of the physician practicing near the site

    International Nuclear Information System (INIS)

    Mraovic, Th.

    1998-01-01

    This thesis has for hypothesis a nuclear accident at the nuclear power plant of Gravelines with radioactive release out of the site: the risks prevention and the strategies of intervention are studied. An evaluation of the sensitization to a nuclear risk is made for the general practitioner that practices near the site. (N.C.)

  8. Real-time computing of the environmental consequences of an atmospheric accidental release of radioactive material: user's point of view

    International Nuclear Information System (INIS)

    Boeri, G.; Caracciolo, R.; Dickerson, M.

    1985-07-01

    All calculations of the consequences of an atmospheric release must start with atmospheric dispersion calculations. Time factors make external and inhalation dose estimates of immediate concern closely followed by ground contamination of land, pastures and onch agricultural crops. In general, the difficulties in modeling the source term and atmospheric transport and diffusion account for most of the error in calculating the dose to man. Thus, sophisticated treatment of the dose part of the calculating is not usually justified, though the relative distribution of dose in individual organs may be needed for correct decision marking. This paper emphasizes the atmospheric transport and diffusion part of the dose estimate and relates how this calculation can be used to estimate dose. 12 refs

  9. Evaluation of the impact and inter-generation risk transfers related to the release and disposal of radioactive waste from the nuclear fuel cycle: a methodological exercise

    International Nuclear Information System (INIS)

    Croueail, P.; Schneider, T.; Sugier, A.

    2000-01-01

    Reflections about the consequences of decisions involving the long term raise various theoretical and complex issues related to the validity of the quantitative assessment of what could be future risks, but also to the ethical position we are adopting towards future generations. In this perspective, decision-making in the field of radioactive waste management, with a view to maintaining present and future radiation exposures as low as reasonably achievable, implies being able to discriminate among alternative options, i.e., being in a position to evaluate the differences in terms of radiological impacts between the options. Because of the complex and multi-dimensional nature of the distant future consequences of waste management options, their comparison involves expressing these impacts using various aggregated or disaggregated indicators, taking into account the time during which radionuclides remain in the environment and their local, regional, or world-wide dispersion. This paper is an attempt to contribute to the development of such a framework. It is mainly focused on the risk transfer dimension inherent to waste disposal management. Any decision to protect people now against the potential impacts of radioactive releases into the environment leads inevitably to the exposure of current generations and potentially of future generations. In this perspective, one of the key questions related to waste management is to decide on the best compromise between present dilution-dispersion into the environment or concentration in surface or underground disposal sites. The objective of this paper is to illustrate, the relative impact of different waste management options, focusing especially on inter-generational risk transfers. For the sake of the exercise, calculations have been performed for six particular radionuclides and for the current waste management options combining underground disposal and releases as well as for extreme alternative waste management options

  10. A review of public concerns and reactions about food safety following a release of food contaminants (radioactive or otherwise)

    International Nuclear Information System (INIS)

    Lambert, B.

    1999-01-01

    This study was carried out, by questionnaire and personal interview, to assess the extent of the public's knowledge of the procedures employed by MAFF, and other agencies following a food contamination incident involving radioactive contamination. It was also designed to gauge the public's perception of relative risk from routine discharges into the environment and other agents. The study populations were located in 5 locations - 3 near nuclear facilities, and 2 control groups (1 close to a potential chemical polluting plant). The study was not intended to be rigorous (in terms of sex, age and socio-economic group) in random selection of subjects for interview but it was judged that a fairly representative selection of views was obtained from about 50 people at each location. Overall, and importantly, although about 60% claimed that some their diet was locally grown, most people even in these rural areas purchased nearly all of their food and milk in supermarkets. It was difficult to get the interviewees to take the concept of a large incident involving food bans seriously but they seemed to expect the local authority and the police to be prominent in announcing the news. They did not seem to have much confidence in the broadcast media but, when prompted, thought that a MAFF 'hot-line' would be of greatest use in obtaining on-going information. House to house leaf letting was also mentioned as an effective means of disseminating information. Every-one seemed to want more clear information about food contamination in advance of it becoming a real problem - although how they would react to this information was not clear. All groups were fairly conservative when asked about personal risk but became more extreme over risks to society as a whole, particularly in relation to transport and the environment. Overall, as expected, the public perception of relative risk was somewhat divorced from reality. Because of their geographical location and confidents, the study group

  11. A mobile dose prediction system based on artificial neural networks for NPP emergencies with radioactive material releases

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Claudio M.N.A.; Schirru, Roberto; Gomes, Kelcio J.; Cunha, José Luiz, E-mail: cmnap@ien.gov.br, E-mail: schirru@lmp.ufrj.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Coordenacao dos Programas de Pos-Graduacao em Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil)

    2017-11-01

    This work presents the approach of a mobile dose prediction system for NPP emergencies with nuclear material release. The objective is to provide extra support to field teams decisions when plant information systems are not available. However, predicting doses due to atmospheric dispersion of radionuclide generally requires execution of complex and computationally intensive physical models. In order to allow such predictions to be made by using limited computational resources such as mobile phones, it is proposed the use of artificial neural networks (ANN) previously trained (offline) with data generated by precise simulations using the NPP atmospheric dispersion system. Typical situations for each postulated accident and respective source terms, as well as a wide range of meteorological conditions have been considered. As a first step, several ANN architectures have been investigated in order to evaluate their ability for dose prediction in hypothetical scenarios in the vicinity of CNAAA Brazilian NPP, in Angra dos Reis, Brazil. As a result, good generalization and a correlation coefficient of 0.99 was achieved for a validation data set (untrained patterns). Then, selected ANNs have been coded in Java programming language to run as an Android application aimed to plot the spatial dose distribution into a map.In this paper, the general architecture of the proposed system is described; numerical results and comparisons between investigated ANN architectures are discussed; performance and limitations of running the Application into a commercial mobile phone are evaluated and possible improvements and future works are pointed. (author)

  12. Development of a mobile dose prediction system based on artificial neural networks for NPP emergencies with radioactive material releases

    International Nuclear Information System (INIS)

    Pereira, Claudio M.N.A.; Schirru, Roberto; Gomes, Kelcio J.; Cunha, José L.

    2017-01-01

    This work presents the approach of a mobile dose prediction system for NPP emergencies with nuclear material release. The objective is to provide extra support to field teams decisions when plant information systems are not available. However, predicting doses due to atmospheric dispersion of radionuclide generally requires execution of complex and computationally intensive physical models. In order to allow such predictions to be made by using limited computational resources such as mobile phones, it is proposed the use of artificial neural networks (ANN) previously trained (offline) with data generated by precise simulations using the NPP atmospheric dispersion system. Typical situations for each postulated accident and respective source terms, as well as a wide range of meteorological conditions have been considered. As a first step, several ANN architectures have been investigated in order to evaluate their ability for dose prediction in hypothetical scenarios in the vicinity of CNAAA Brazilian NPP, in Angra dos Reis, Brazil. As a result, good generalization and a correlation coefficient of 0.99 was achieved for a validation data set (untrained patterns). Then, selected ANNs have been coded in Java programming language to run as an Android application aimed to plot the spatial dose distribution into a map. In this paper, the general architecture of the proposed system is described; numerical results and comparisons between investigated ANN architectures are discussed; performance and limitations of running the Application into a commercial mobile phone are evaluated and possible improvements and future works are pointed.

  13. A mobile dose prediction system based on artificial neural networks for NPP emergencies with radioactive material releases

    International Nuclear Information System (INIS)

    Pereira, Claudio M.N.A.; Schirru, Roberto; Gomes, Kelcio J.; Cunha, José Luiz

    2017-01-01

    This work presents the approach of a mobile dose prediction system for NPP emergencies with nuclear material release. The objective is to provide extra support to field teams decisions when plant information systems are not available. However, predicting doses due to atmospheric dispersion of radionuclide generally requires execution of complex and computationally intensive physical models. In order to allow such predictions to be made by using limited computational resources such as mobile phones, it is proposed the use of artificial neural networks (ANN) previously trained (offline) with data generated by precise simulations using the NPP atmospheric dispersion system. Typical situations for each postulated accident and respective source terms, as well as a wide range of meteorological conditions have been considered. As a first step, several ANN architectures have been investigated in order to evaluate their ability for dose prediction in hypothetical scenarios in the vicinity of CNAAA Brazilian NPP, in Angra dos Reis, Brazil. As a result, good generalization and a correlation coefficient of 0.99 was achieved for a validation data set (untrained patterns). Then, selected ANNs have been coded in Java programming language to run as an Android application aimed to plot the spatial dose distribution into a map.In this paper, the general architecture of the proposed system is described; numerical results and comparisons between investigated ANN architectures are discussed; performance and limitations of running the Application into a commercial mobile phone are evaluated and possible improvements and future works are pointed. (author)

  14. NSR&D Program Fiscal Year 2015 Funded Research Stochastic Modeling of Radioactive Material Releases Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Andrus, Jason P. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Pope, Chad [Idaho State Univ., Pocatello, ID (United States); Toston, Mary [Idaho State Univ., Pocatello, ID (United States); Maas, Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-12-01

    Nonreactor nuclear facilities operating under the approval authority of the U.S. Department of Energy use unmitigated hazard evaluations to determine if potential radiological doses associated with design basis events challenge or exceed dose evaluation guidelines. Unmitigated design basis events that sufficiently challenge dose evaluation guidelines or exceed the guidelines for members of the public or workers, merit selection of safety structures, systems, or components or other controls to prevent or mitigate the hazard. Idaho State University, in collaboration with Idaho National Laboratory, has developed a portable and simple to use software application called SODA (Stochastic Objective Decision-Aide) that stochastically calculates the radiation dose distribution associated with hypothetical radiological material release scenarios. Rather than producing a point estimate of the dose, SODA produces a dose distribution result to allow a deeper understanding of the dose potential. SODA allows users to select the distribution type and parameter values for all of the input variables used to perform the dose calculation. Users can also specify custom distributions through a user defined distribution option. SODA then randomly samples each distribution input variable and calculates the overall resulting dose distribution. In cases where an input variable distribution is unknown, a traditional single point value can be used. SODA, developed using the MATLAB coding framework, has a graphical user interface and can be installed on both Windows and Mac computers. SODA is a standalone software application and does not require MATLAB to function. SODA provides improved risk understanding leading to better informed decision making associated with establishing nuclear facility material-at-risk limits and safety structure, system, or component selection. It is important to note that SODA does not replace or compete with codes such as MACCS or RSAC; rather it is viewed as an

  15. Radioactive substances

    International Nuclear Information System (INIS)

    Butler, G.C.; Hyslop, C.

    1980-01-01

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

  16. The contribution of the CSNI Principal Working Group on Confinement of Accidental Radioactive Releases to the technical consensus and spreading of knowledge on severe accidents

    International Nuclear Information System (INIS)

    De Boeck, B.; Royen, J.

    1999-01-01

    The Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) is an international committee made up of scientists and engineers. It was set up 1973 to develop and co-ordinate the activities of the NEA concerning the technical aspects of the design, construction and operation of nuclear installations insofar as they affect the safety of such installations. The Committee's purpose is to foster international cooperation in nuclear safety amongst the Member countries. Five Principal Working Groups (PWG) operate under the leadership of CSNI. PWG4 is named 'Confinement of Accidental Radioactive Releases' and its main activities are State of the Art Reports, International Standard Problem exercises, Specialist Meetings and Technical Opinion Papers. Together with other groups of experts involved in severe accident work, PWG4 has strongly contributed to the understanding of phenomena and the development of the knowledge base in that area, to the resolution of technical issues, and to the dissemination of the results. Taking examples from the products of the work of PWG4, the paper shows how this working group fosters international co-operation in the area of severe accidents and their management, and contributes to the development of a technical consensus. (author)

  17. Preliminary evaluation of the impact and inter-generation risk transfers related to the release and disposal of radioactive waste from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Tort, V.; Lochard, J.; Schneider, T.; Sugier, A.

    1997-12-01

    This report is an attempt to contribute to the complex issue of the decision-making in the field of radioactive waste management. Because of the complex and multidimensional nature of the distant future consequences of waste management options, their analysis implies the taking into considerations of various aggregated indicators which depend on the elapse of time during which the radionuclides remain in the environment and their local, regional or world-wide dispersion. This report is a preliminary work sponsored by IPSN mainly focused on the risk transfer dimension, inherent to waste disposal management. Its objective is to illustrate, using the French nuclear fuel cycle context, the relative impact of some simple waste management options, outlining particularly the issue of inter-generation risk transfer. Even though the selected six radionuclides are the most important, a complete assessment should include all the radionuclides contained in the waste, what is particularly important in case of underground waste disposal were both normal evolution scenarios and intrusion must be considered. The extreme alternatives, i.e. the total disposal or total release of the radionuclides are analyzed but realistic are the intermediate options, which should be thoroughly examined from the technical point of view. The analysis of intermediate management options could give an estimation of the most appropriate solution in an ALARA perspective

  18. The choice of individual dose criterion at which to restrict agricultural produce following an unplanned release of radioactive material to atmosphere

    CERN Document Server

    Dionian, J

    1985-01-01

    In the event of an accidental release of radioactive material to atmosphere, the introduction of emergency countermeasures will be based on the need to limit the risk to individuals. However, it has been suggested that a form of cost-benefit analysis may be used as an input to decisions on the withdrawal of countermeasures, although it is recognised that these decisions may be influenced by factors other than those directly related to radiological protection. In this study, a method based on cost-benefit analysis is illustrated for assessing the optimum level of individual dose at which restrictions on agricultural production may be considered. This requires monetary values to be assigned to both the lost food production and to the health detriment, expressed as the collective effective dose equivalent commitment. It has been assumed in this analysis that food-supply restrictions are both introduced and withdrawn at the same projected level of annual individual dose. The effect on the optimum dose level of th...

  19. Numerical model to simulate the isotopic and heat release and transport through the geosphere from a geological repository of radioactive wastes

    International Nuclear Information System (INIS)

    Hidalgo Lopez, A.

    2002-01-01

    The aim of this research is to simulate the isotopic and heat release and transport through the geosphere, from a geological repository of high level nuclear waste. in order to achieve it, different physical processes, that have to do with the problem, are considered: groundwater flow, radioactive decay, nuclide dissolution in groundwater, heat generation, mass and heat transport. Some of these phenomena are related among the, which allows to build a coupled model,which is the starting point to generate a FORTRAN code. The flow and transport models are developed in two spatial dimensions and are integrated in space by means of a finite volume method. The time integration is fulfilled by a θ-method. Moreover, the advection-diffusion equation is solved by two finite volume techniques. In the first one a linear interpolation is used whereas in the second it is used a quadratic one. Also, a consistency an stability study of both methods is carried out in order to compare their stability zones and the errors appearing. Stability is analysed by applying the von Neumann method, which is based upon Fourier series. Although it is a classical technique when dealing with finite-difference schemes, it is here applied to two finite volume schemes. (Author)

  20. Verification of computer system PROLOG - software tool for rapid assessments of consequences of short-term radioactive releases to the atmosphere

    Energy Technology Data Exchange (ETDEWEB)

    Kiselev, Alexey A.; Krylov, Alexey L.; Bogatov, Sergey A. [Nuclear Safety Institute (IBRAE), Bolshaya Tulskaya st. 52, 115191, Moscow (Russian Federation)

    2014-07-01

    In case of nuclear and radiation accidents emergency response authorities require a tool for rapid assessments of possible consequences. One of the most significant problems is lack of data on initial state of an accident. The lack can be especially critical in case the accident occurred in a location that was not thoroughly studied beforehand (during transportation of radioactive materials for example). One of possible solutions is the hybrid method when a model that enables rapid assessments with the use of reasonable minimum of input data is used conjointly with an observed data that can be collected shortly after accidents. The model is used to estimate parameters of the source and uncertain meteorological parameters on the base of some observed data. For example, field of fallout density can be observed and measured within hours after an accident. After that the same model with the use of estimated parameters is used to assess doses and necessity of recommended and mandatory countermeasures. The computer system PROLOG was designed to solve the problem. It is based on the widely used Gaussian model. The standard Gaussian model is supplemented with several sub-models that allow to take into account: polydisperse aerosols, aerodynamic shade from buildings in the vicinity of the place of accident, terrain orography, initial size of the radioactive cloud, effective height of the release, influence of countermeasures on the doses of radioactive exposure of humans. It uses modern GIS technologies and can use web map services. To verify ability of PROLOG to solve the problem it is necessary to test its ability to assess necessary parameters of real accidents in the past. Verification of the computer system on the data of Chazhma Bay accident (Russian Far East, 1985) was published previously. In this work verification was implemented on the base of observed contamination from the Kyshtym disaster (PA Mayak, 1957) and the Tomsk accident (1993). Observations of Sr-90

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-01-01

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

  2. ORNL radioactive waste operations

    International Nuclear Information System (INIS)

    Sease, J.D.; King, E.M.; Coobs, J.H.; Row, T.H.

    1982-01-01

    Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards

  3. Methodologies for evaluation of environmental capacity and impact due to radioactive releases by critical path analysis and their application to the IPEN's aquatic environment as a typical case study

    International Nuclear Information System (INIS)

    Chandra, U.

    1986-01-01

    A brief description of the tested concepts, for determination of environmental capacity and impact by critical path analysis technique and of dose limitation/optmization for radioactive releases is made. These concepts/methodologies are being applied in the environment of IPEN. The aquatic environment of IPEN is dealt with in detal with a view to evaluate the possible critical paths, its capacity, and present and future radiological impacts. (Author) [pt

  4. Contribution to the study of TRH (thyrotropin-releasing hormone) conformation using circular dichroism. Physico-chemical studies, radioactive labelling and biological applications

    International Nuclear Information System (INIS)

    Pradelles, Philippe.

    1977-01-01

    In an attempt to reach a better understanding at the molecular level of phenomena connected with the action of TRF the conformation and radioactive labelling of this hormone were investigated. The specific detection of a hormone at its action site is only possible if labelled substances of very high specific activity are used. TRF was tritium labelled by three methods: direct catalytic exchange; catalytic dehalogenation of mono- and di-iodo TRF; catalytic denitrogenation of mono-azo-TRF. Whatever the method used the tritiated TRF has a very high specific activity and keeps all its biological properties. Biological activity measurements carried out on labelled TRF, in vivo in rats and in vitro on a TRF-sensitive prolactine cell clone, are described. TRF tritiated by the above methods is shown to have the same biological activity as standard TRF. Some results are given concerning the application of labelled TRF to research on the hormone action mechanism. The tritiated TRF distribution kinetics were examined in vivo and in vitro. The kinetics of hormone fixation on the antehypophysary tissue match those of in vivo release of the plasma thyreotropic hormone, confirming the relationships between the hormone fixation on its target tissue and its biological effect. Finally an outline is given of work on the interaction of tritiated TRF with prolactine cell receptors and on the penetration of intact tritiated TRF into these cells. In addition the radioimmunological analysis of TRF was developed by the use of 125 I-mono-iodo-TRF at high specific activity (above 2000 Ci/mmole) [fr

  5. SU-G-IeP4-05: Experience with a Practical Approach to the Release of Radioactive Patients from Radiation Safety Isolation

    Energy Technology Data Exchange (ETDEWEB)

    Wendt, R; Erwin, W; Fisher, A; Jones, S; Jimenez, S; Wong, F; Jessop, A [UT MD Anderson Cancer Center, Houston, TX (United States)

    2016-06-15

    Purpose: The radioactive patient releases of the nuclear medicine department in a large cancer center were analyzed to compare the estimated doses to others to the regulatory limit and institutional targets and to gauge how onerous the patients’ instructions were. Methods: In-house software that implements the NUREG 1556 approach and further considers fellow travelers, children and pregnant women and members of the public following Siegel, et al., is used to calculate release timing and to provide patients with individualized instructions. A retrospective analysis of the 218 releases in 2015 that required instructions included all I-131 and Lu-177 treatments. Results: There were 87 male and 131 female patients. They were 45.5±16.5 (8-84) years old, weighed 83.3±21.8 kg and stood 168±10 cm tall with a body mass index of 29.3±6.7 kg/m2. 195 patients received 2.96±2.23 GBq of I-131-NaI for differentiated thyroid carcinoma and eight received 636±231 MBq of I-131-NaI for hyperthyroidism. There were eight administrations of 18.5 GBq of I-131-mIBG and seven administrations of 7.4 GBq of Lu-177-DOTATATE. The dose to the most exposed person was 1.67±1.05 (mode=0.60, median=1.15) mSv. The dose to a fellow traveler was 0.31±0.31 (mode=0.1, median=0.17) mSv. The dose to children and pregnant women was 0.51±0.34 (mode=1.0, median=0.42) mSv. The duration of isolation was 7.7±17.3 (mode=2, median=1.7) hours. The duration of sleeping alone was 60.4±127 (mode=0, median=15.5) hours. The time to delay traveling was 12.2±11 (mode=median=0) hours. The time to completely avoid children and pregnant women was 23.3±26.5 (0–254, mode=median=24) hours followed by limited contact for 20.6±68.1 (0–491, mode=median=0) hours. The time to avoid others (e.g., to wait to return to work) was 12.1±101 (0–1465, mode=median=0) hours. Conclusion: The estimated doses to others were often well below the limits set by regulation, 5 mSv, or prudent practice, 1 mSv. Most patients

  6. SU-G-IeP4-05: Experience with a Practical Approach to the Release of Radioactive Patients from Radiation Safety Isolation

    International Nuclear Information System (INIS)

    Wendt, R; Erwin, W; Fisher, A; Jones, S; Jimenez, S; Wong, F; Jessop, A

    2016-01-01

    Purpose: The radioactive patient releases of the nuclear medicine department in a large cancer center were analyzed to compare the estimated doses to others to the regulatory limit and institutional targets and to gauge how onerous the patients’ instructions were. Methods: In-house software that implements the NUREG 1556 approach and further considers fellow travelers, children and pregnant women and members of the public following Siegel, et al., is used to calculate release timing and to provide patients with individualized instructions. A retrospective analysis of the 218 releases in 2015 that required instructions included all I-131 and Lu-177 treatments. Results: There were 87 male and 131 female patients. They were 45.5±16.5 (8-84) years old, weighed 83.3±21.8 kg and stood 168±10 cm tall with a body mass index of 29.3±6.7 kg/m2. 195 patients received 2.96±2.23 GBq of I-131-NaI for differentiated thyroid carcinoma and eight received 636±231 MBq of I-131-NaI for hyperthyroidism. There were eight administrations of 18.5 GBq of I-131-mIBG and seven administrations of 7.4 GBq of Lu-177-DOTATATE. The dose to the most exposed person was 1.67±1.05 (mode=0.60, median=1.15) mSv. The dose to a fellow traveler was 0.31±0.31 (mode=0.1, median=0.17) mSv. The dose to children and pregnant women was 0.51±0.34 (mode=1.0, median=0.42) mSv. The duration of isolation was 7.7±17.3 (mode=2, median=1.7) hours. The duration of sleeping alone was 60.4±127 (mode=0, median=15.5) hours. The time to delay traveling was 12.2±11 (mode=median=0) hours. The time to completely avoid children and pregnant women was 23.3±26.5 (0–254, mode=median=24) hours followed by limited contact for 20.6±68.1 (0–491, mode=median=0) hours. The time to avoid others (e.g., to wait to return to work) was 12.1±101 (0–1465, mode=median=0) hours. Conclusion: The estimated doses to others were often well below the limits set by regulation, 5 mSv, or prudent practice, 1 mSv. Most patients

  7. Argentina's radioactive waste disposal policy

    International Nuclear Information System (INIS)

    Palacios, E.

    1986-01-01

    The Argentina policy for radioactive waste disposal from nuclear facilities is presented. The radioactive wastes are treated and disposed in confinement systems which ensure the isolation of the radionucles for an appropriate period. The safety criteria adopted by Argentina Authorities in case of the release of radioactive materials under normal conditions and in case of accidents are analysed. (M.C.K.) [pt

  8. Comparison of the effects of stimulators and inhibitors of resorption on the release of lysosomal enzymes and radioactive calcium from fetal bone in organ culture

    International Nuclear Information System (INIS)

    Eilon, G.; Raisz, L.G.

    1978-01-01

    The release of lysosomal enzymes, collagenase, and previously incorporated 45 Ca from fetal rat long bones cultured in a chemically defined medium is compared. Parathyroid hormone (PTH) and prostaglandin E 2 increased the release of β-glucuronidase, acetylglucosaminidase, and cathepsin D, but showed little effect on collagenase activity in the medium at 48 h. The dose-response relations for β-glucuronidase and 45 Ca release were similar. However, the increase in lysosomal enzyme release was proportionally greater and occurred earlier than the increase in 45 Ca release. PTH also caused a significant increase in total β-glucuronidase activity in bone plus medium. Several agents which stimulate 45 Ca release at an optimal concentration, but not at a higher concentration, including dibutyryl cAMP, isobutylmethylxanthine, and the calcium ionophore, A23187, all increased lysosomal enzyme release at the concentration which increased 45 Ca release. Three inhibitors of bone resorption (calcitonin, cortisol, and colchicine) blocked lysosomal enzyme release at the same time that 45 Ca release decreased. When the bones escaped from calcitonin inhibition, both 45 Ca and lysosomalenzyme release increased. While colchicine blocked both lysosomal enzymes and 45 CA release, it actually increased the release of bone collagenase, and together with PTH or prostaglandin E 2 caused a large increase in free collagenase activity in the medium. These data indicate that lysosomal enzyme release is closely linked to bone resorption and suggest that lysosomal enzymes may have a primary role in initiating resorption, perhaps by acting on noncollagenous matrix or tissue components before mineral removal and collagen degradation

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1987-05-01

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

  10. Renewal of release and sampling authorizations of the Cattenom nuclear power plant. Complementary note on the authorizations demands of radioactive release; Renouvellement des autorisations de rejets et de prelevements de la centrale nucleaire de Cattenom. Note complementaire sur les demandes d'autorisation de rejets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Marignac, Y.; Coeytaux, X

    2003-10-15

    The present note follows the exchanges with the contracting authority, the Cattenom nuclear power plant, during the public hearing stood on the 10. of october 2003 at Cattenom. In the frame of the evaluation of the inquiry file by WISE -Paris, this note constitutes a deepening on the question of authorization demands for the radioactive releases. The elements supplied by E.D.F in the file submitted to the inquiry, and the presentation of these demands and the information complements brought during the meeting of the 10. of october, raise different problems of evaluation and justification relative to the evolution of radioactive release of Cattenom. The note analyses in particular, the increasing of dosimetry impact expected from the progression of real release forecasted by the operator, and the weight linked to the feedback of clad failure problem. It discusses the justification brought by E.D.F. to the standing and even the increasing of liquid tritium release instead of the expected reduction, facing the arguments of the operator to the experience feedback on the park and to the uncertainties on the future progress. (N.C.)

  11. Medical irradiation, radioactive waste and misinformation. A press release from the French Academy of Medicine; Irradiation medicale, dechets, desinformation: un avis de l'Academie de medecine

    Energy Technology Data Exchange (ETDEWEB)

    The, G. de; Tubiana, M

    2002-07-01

    The Academy of Medicine, worried by the problems that poses for public opinion the medical irradiation, the radioactive wastes and some erroneous information that these subjects give rise to, considers useful to give an advice based on objective data. (N.C.)

  12. General Atomic's radioactive gas recovery system

    International Nuclear Information System (INIS)

    Mahn, J.A.; Perry, C.A.

    1975-01-01

    General Atomic Company has developed a Radioactive Gas Recovery System for the HTGR which separates, for purposes of retention, the radioactive components from the non-radioactive reactor plant waste gases. This provides the capability for reducing to an insignificant level the amount of radioactivity released from the gas waste system to the atmosphere--a most significant improvement in reducing total activity release to the environment. (U.S.)

  13. The radiological consequences of notional accidental releases of radioactivity from fast breeder reactors: sensitivity of the incidence of early effects to the duration

    International Nuclear Information System (INIS)

    Hemming, C.R.; Hallam, J.; Kelly, G.N.

    1979-12-01

    The radiological consequences of a wide range of notional accidental releases from a 1300 MW(e) LMFBR were assessed in a study published in 1977 (NRPB-R53). In that study representative values were in general adopted for each of the important parameters while recognising that in reality they could vary considerably. In this study the sensitivity of the predicted incidence of early effects to the release duration, in so far as it affects the crosswind spread of the activity, is investigated. Two situations are considered; a short release in which the crosswind distribution of the activity is assumed to be Gaussian and a more prolonged release (as modelled in the initial study) in which the crosswind distribution of activity is assumed uniform over a 30 0 sector. For the particular conditions and population distributions considered, the incidence of early effects is greater for the short compared with the more prolonged release. The size of the increase depends upon the radionuclide composition, the magnitude of the release, the distribution of the exposed population, and the prevailing meteorological conditions, but in general the increase is not large. This relatively limited sensitivity indicates that the results obtained in the initial study can be assumed, to a good approximation, to be applicable irrespective of the release duration. (author)

  14. Radioactive Decay

    Science.gov (United States)

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

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

    International Nuclear Information System (INIS)

    1988-01-01

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

  16. Radioactive waste containment

    International Nuclear Information System (INIS)

    Beranger, J.-C.

    1978-01-01

    The problem of confining the radioactive wastes produced from the nuclear industry, after the ore concentration stage, is envisaged. These residues being not released into the environment are to be stored. The management policy consists in classifying them in view of adapting to each type of treatment, the suitable conditioning and storage. This classification is made with taking account of the following data: radioactivity (weak, medium or high) nature and lifetime of this radioactivity (transuranians) physical nature and volume. The principles retained are those of volume reduction and shaping into insoluble solids (vitrification) [fr

  17. Radioactive wastes

    International Nuclear Information System (INIS)

    Straub, C.P.

    1975-01-01

    A review is presented on the environmental behavior of radioactive wastes. The management of high-level wastes and waste disposal methods were discussed. Some topics included were ore processing, coagulation, absorption and ion exchange, fixation, ground disposal, flotation, evaporation, transmutation and extraterrestrial disposal. Reports were given of the 226 Ra, 224 Ra and tritium activity in hot springs, 90 Sr concentrations in the groundwater and in White Oak Creek, radionuclide content of algae, grasses and plankton, radionuclides in the Danube River, Hudson River, Pacific Ocean, Atlantic Ocean, Lake Michigan, Columbia River and other surface waters. Analysis showed that 239 Pu was scavenged from Lake Michigan water by phytoplankton and algae by a concentration factor of up to 10,000. Benthic invertebrates and fish showed higher 239 Pu concentrations than did their pelagic counterparts. Concentration factors are also given for 234 Th, 60 Co, Fe and Mr in marine organisms. Two models for predicting the impact of radioactivity in the food chain on man were mentioned. In an accidental release from a light-water power reactor to the ocean, the most important radionuclides discharged were found to be 90 Sr, 137 Cs, 239 Pu and activation products 65 Zr, 59 Fe, and 95 Zr

  18. The influence of the physico-chemical form of the aerosol on the radiological consequences of notional accidental releases of radioactivity from a fast breeder reactor

    International Nuclear Information System (INIS)

    Kelly, G.N.; Jones, J.A.; Simmonds, J.R.

    1979-01-01

    The radiological consequences of a wide range of notional accidental releases from a 1300 MW(e) LMFBR (Liquid Metal-cooled Fast Breeder Reactor) were assessed in a study published by the National Radiological Protection Board (NRPB) in 1977. In that study representative values were in general adopted for each of the important parameters while recognising that in reality they could vary considerably. The present study is concerned with the sensitivity of the predicted consequences to the physico-chemical form of the released aerosol. Of particular interest is the importance of a mixed sodium-transuranium element aerosol which may be formed in accidental releases of activity from sodium cooled FBRs. Two significant findings emerge from the study. First the predicted consequences in general are relatively insensitive to the range of physico-chemical forms analysed. For generic assessments therefore it is sufficient to assume the properties of the aerosol adopted in the initial study (1 μm AMAD and each element in the oxide form); the exception concerns the estimation of the incidence of early morbidity, and to a lesser extent early mortality, but only for a limited range of release composition. The second finding is that the radiological consequences are not, contrary to what might have been expected, significantly increased for the release of a mixed sodium-element aerosol

  19. Using radioactivity

    International Nuclear Information System (INIS)

    1982-10-01

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

  20. Radioactive aerosols

    International Nuclear Information System (INIS)

    Chamberlain, A.C.

    1991-01-01

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

  1. Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956)- An Assessment of Quantities released, Off-Site Radiation Doses, and Potential Excess Risks of Thyroid Cancer- APPENDICES Appendices-Volume 1A

    International Nuclear Information System (INIS)

    Apostoaei, A.I.; Burns, R.E.; Hoffman, F.O.; Ijaz, T.; Lewis, C.J.; Nair, S.K.; Widner, T.E.

    1999-01-01

    This report consists of all the appendices for the report described below: In the early 1990s, concern about the Oak Ridge Reservation's past releases of contaminants to the environment prompted Tennessee's public health officials to pursue an in-depth study of potential off-site health effects at Oak Ridge. This study, the Oak Ridge dose reconstruction, was supported by an agreement between the U.S. Department of Energy (DOE) and the State of Tennessee, and was overseen by a 12-member panel appointed by Tennessee's Commissioner of Health. One of the major contaminants studied in the dose reconstruction was radioactive iodine, which was released to the air by X-10 (now called Oak Ridge National Laboratory) as it processed spent nuclear reactor fuel from 1944 through 1956. The process recovered radioactive lanthanum for use in weapons development. Iodine concentrates in the thyroid gland so health concerns include various diseases of the thyroid, such as thyroid cancer. The large report, ''Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956) - An Assessment of Quantities Released, Off-site Radiation Doses, and Potential Excess Risks of Thyroid Cancer,'' is in two volumes. Volume 1 is the main body of the report, and Volume 1A, which has the same title, consists of 22 supporting appendices. Together, these reports serve the following purposes: (1) describe the methodologies used to estimate the amount of iodine-131 (I-131) released; (2) evaluate I-131's pathway from air to vegetation to food to humans; (3) estimate doses received by human thyroids; (4) estimate excess risk of acquiring a thyroid cancer during ones lifetime; and (5) provide equations, examples of historical documents used, and tables of calculated values as appendices. Results indicate that females born in 1952 who consumed milk from a goat pastured a few miles east of X-10 received the highest doses from I-131 and would have had the highest

  2. Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956)- An Assessment of Quantities released, Off-Site Radiation Doses, and Potential Excess Risks of Thyroid Cancer- APPENDICES Appendices-Volume 1A

    Energy Technology Data Exchange (ETDEWEB)

    Apostoaei, A.I.; Burns, R.E.; Hoffman, F.O.; Ijaz, T.; Lewis, C.J.; Nair, S.K.; Widner, T.E.

    1999-07-01

    This report consists of all the appendices for the report described below: In the early 1990s, concern about the Oak Ridge Reservation's past releases of contaminants to the environment prompted Tennessee's public health officials to pursue an in-depth study of potential off-site health effects at Oak Ridge. This study, the Oak Ridge dose reconstruction, was supported by an agreement between the U.S. Department of Energy (DOE) and the State of Tennessee, and was overseen by a 12-member panel appointed by Tennessee's Commissioner of Health. One of the major contaminants studied in the dose reconstruction was radioactive iodine, which was released to the air by X-10 (now called Oak Ridge National Laboratory) as it processed spent nuclear reactor fuel from 1944 through 1956. The process recovered radioactive lanthanum for use in weapons development. Iodine concentrates in the thyroid gland so health concerns include various diseases of the thyroid, such as thyroid cancer. The large report, ''Iodine-131 Releases from Radioactive Lanthanum Processing at the X-10 Site in Oak Ridge, Tennessee (1944-1956) - An Assessment of Quantities Released, Off-site Radiation Doses, and Potential Excess Risks of Thyroid Cancer,'' is in two volumes. Volume 1 is the main body of the report, and Volume 1A, which has the same title, consists of 22 supporting appendices. Together, these reports serve the following purposes: (1) describe the methodologies used to estimate the amount of iodine-131 (I-131) released; (2) evaluate I-131's pathway from air to vegetation to food to humans; (3) estimate doses received by human thyroids; (4) estimate excess risk of acquiring a thyroid cancer during ones lifetime; and (5) provide equations, examples of historical documents used, and tables of calculated values as appendices. Results indicate that females born in 1952 who consumed milk from a goat pastured a few miles east of X-10 received the highest doses from

  3. 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

  4. Levels of radioactivity in Qatar

    International Nuclear Information System (INIS)

    Al-Thani, A.A.; Abdul-Majid, S.; Mohammed, K.

    1995-01-01

    The levels of natural and man-made radioactivity in soil and seabed were measured in Qatar to assess radiation exposure levels and to evaluate any radioactive contamination that may have reached the country from fallout or due to the Chernobyl accident radioactivity release. Qatar peninsula is located on the Arabian Gulf, 4500 km from Chernobyl, and has an area of ∼11,600 km 2 and a population of ∼600,000

  5. Measures of caution undertaken in Germany in case of accident or incidents susceptible to bear upon humans and environment due to a radioactivity release

    International Nuclear Information System (INIS)

    Kaspar, Dieter

    1997-01-01

    After Chernobyl accident a low concerning the population protection against the effects of ionizing radiation has been promulgated in Germany (Strahlenschutzvorsorgegesetz) in order to unify on a federal scale the radiation protection legislation. A Land can make recommendations and actuate measures only when radioactivity levels concern zones placed under its jurisdiction. Special stipulations concerning the roles of Land and Federal Government are specified for the case of severe accidents at nuclear power plants followed by catastrophic consequences in the nearby areas. The measures and intervention thresholds are based on the publication No. 40 of CIPR. These actions are contained in a catalogue currently under revision. All the measures indicated aim at avoiding any contamination in the agricultural sector and bock or diminish as much as possible the radionuclide transfer in food stuffs and forages. A table is presented indicating the limit doses relative to whole body, thyroid or lung exposure requiring accordingly sealing of dwelling houses, iodine addition or population evacuation. Also doses indicating renouncement to direct use of the food stuffs and reinstalling the population previously relocated are presented. Finally two tables are given, one containing caution measures of protection before radioactive cloud passage and the other the threshold values of the atmospheric concentration for cereal, milk, fruit and vegetable storages corresponding to the radionuclides 131 I, 137 Cs and 90 Sr

  6. Development of new radioactive labelling methods (3H and 11C) in luteizing hormone (LH) and its releasing hormone (LRF). Study of physico-chemical properties of LRF by circular dichroism and emission spectroscopy

    International Nuclear Information System (INIS)

    Marche, Pierre.

    1975-01-01

    After a brief review of present knowledge on the hypothalamus-hypophysis this thesis falls into three parts. The first situates the peptide hormones studied in their biological context. Research on the radioactive labelling of hormonal peptides is dealt with in part two which includes, besides the application of already known tritiation methods to particular problems, the description of a new tritium labelling method and the use of carbon 11 for the kinetic distribution study of a hormone. Part three concerns the physico-chemical study of a hypothalamic hormone. As a contribution towards research on the hypophysary gonadotrophic function regulation, the work involved in all the above three sections was directed towards the luteinising hormone (LH) and its hypothalamic release factor (LRF). During the study of this latter the problem of peptides containing tryptophane arose and was consequently investigated [fr

  7. Radioactivity in the environment

    International Nuclear Information System (INIS)

    Valkovic, V.

    2000-01-01

    Numerous sources of ionizing radiation can lead to human exposure: natural sources, nuclear explosions, nuclear power generation, use of radiation in medical, industrial and research purposes, and radiation emitting consumer products. Before assessing the radiation dose to a population one requires a precise knowledge of the activity of a number of radionuclides. The basis for the assessment of the dose to a population from a release of radioactivity to the environment, the estimation of the potential clinical heath effects due to the dose received and, ultimately, the implementation of countermeasures to protect the population, is the measurement of radioactive contamination in the environment after the release. It is the purpose of this book to present the facts about the presence of radionuclides in the environment, natural and man made. There is no aspect of radioactivity, which has marked the passing century, not mentioned or discussed in this book. refs

  8. Review of decontamination and clean-up techniques for use in the UK following accidental releases of radioactivity to the environment

    International Nuclear Information System (INIS)

    Brown, J.; Cooper, J.R.; Jones, J.A.; Flaws, L.; McGeary, R.; Spooner, J.

    1996-10-01

    This review examines decontamination and clean-up methodologies that may be applied following an accidental release of radionuclides to the atmosphere in the UK. An accidental release of radionuclides to the environment could cause contamination of land and property, and may necessitate movement of the resident population to reduce their exposure. Decontamination procedures may reduce the level of contamination and, in determining whether to implement such procedures in an affected area, it is necessary to weigh the effectiveness of the techniques against the associated economic costs and other disadvantages. The report gives a review of available methods of decontamination and clean-up in terms of the effectiveness of the various methods to remove activity from building or land surfaces and dose saved. It also considers associated disadvantages, costs, clean-up rates for land and buildings, waste disposal implications, and personnel and resource requirements. On the basis of these factors, the techniques are prioritised and overall strategies for decontamination following releases of both fission products and alpha emitters are presented. (author)

  9. 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.

  10. 49 CFR 175.705 - Radioactive contamination.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Radioactive contamination. 175.705 Section 175.705... Regulations Applicable According to Classification of Material § 175.705 Radioactive contamination. (a) A... (radioactive) materials that may have been released from their packagings. (b) When contamination is present or...

  11. Environmental standard review plan for ES Section 7.1.1. Environmental impacts of postulated accidents involving releases of radioactive materials to groundwater

    International Nuclear Information System (INIS)

    1985-11-01

    Environmental Standard Review Plan (ESRP) 7.1.1 provides guidance to the staff for preparation of environmental assessments of ''Radiological Impacts - Releases to Groundwater,'' an input to the staff's environmental statement which addresses the groundwater pathway consequences from postulated reactor core-melt accidents. The ESRP lists the type of information which should be collected, references that may be useful, and provides a procedure for uniform staff review of applicant analyses. The ESRP is applicable to both Construction Permit and Operating License Stage reviews

  12. Impact of the filtered venting system design upon the total radioactive release in case of a severe accident and a comparison of European requirements

    International Nuclear Information System (INIS)

    Cederqvist, H.; Elisson, K.; Loewenhielm, G.; Appelgren, E.

    1991-01-01

    Filtered containment venting systems have been introduced in several nuclear power plants in Europe. The objective is to relieve the containment overpressure in a controlled way during a severe accident involving core-melt. The release of fission products when operating the venting system has been compared to that resulting from diffuse leakage from the containment. The conclusion is that the diffuse leakage of gaseous and particulate species can not be neglected in comparison to that resulting from operating the filtered containment venting system. Representative European requirements related to filtered containment venting have been analyzed and compared

  13. Release of radioactive materials from nuclear power plants. Report No. 2. Dispersion mechanisms, transport paths, and concentration factors for radionuclides in the cooling water recipient

    International Nuclear Information System (INIS)

    Rygg, B.

    The discharge of radioactive materials in the cooling water from a nuclear power plant may involve consequences for the interests involved in the recipient and its organisms. Of special interest is the transport of radionuclides in water, sediments, and organisms to man. The most important elements are H, Na, P, Cr, Mn, Fe, Co, Zn, Sr, Mo, Ru, I, Cs, and Ce. Metals with high affinity for organic material will be sorbed to sediments rich in organic material, while other elements will be enriched in algaes and arrive in the sediment through decay or excrement. Elements in particulate form will normally precipitate. Ions will generally not be enriched in sediments. Marine organisms may take up nuclides directly from the water and from food. The concentration factor is dependent on the chemical properties of the element and the physiology of the organism. The occurrence of elements in water and organisms in the Oslofjord district is poorly known and tables have therefore been derived from literature data to indicate the concentration factors to be expected

  14. HERALD, a programme enumerating the radiation doses to the population following the release of radioactive gases and aerosols into the atmosphere after a nuclear reactor accident

    International Nuclear Information System (INIS)

    Veverka, O.

    1986-01-01

    Program HERALD computes radiation doses to the population following an accident of a fission nuclear reactor, the destruction of the primary coolant circuit (LOCA), etc. The program was written with the intention to obtain a tool which would enable the user to follow numerically a radioactive cloud, its physical behaviour and its consequences up to extremely long distances of several thousands kilometres. Therefore the usual model of Gaussian distribution was avoided and the considerably simpler ''box model'' was chosen. This can be replaced by the ''semi-box model''. The fallout velocity of gases and particles is calculated using a simple model including the dependence on the Pasquillian stability class and on the local surface roughness. So is the scavenging coefficient for gases and particles, removed by either rainfalls, or snowfall or fogs. It is possible to employ corresponding empirical data. The program utilizes an ample data library holding nuclear data for approximately 500 fission products in 121 decay chains of at most 10 members, the corresponding dose factors for external gamma and beta irradiation from the cloud and the surface and from the inhaled and ingested radionuclides (ICRP-30). This library is now being extended to approximately 1,200 nuclides (products of activation, fission products and fuels including transuranium elements) for the purposes of normal operation and of heavy accidents. The program is written in standard language FORTRAN IV and is run on computer M 4030-1. (author) 5 figs., 34 tabs., 26 refs

  15. Updated synthesis of the knowledge about the impact on marine environment of the radioactive releases from Fukushima Dai-ichi damaged site - October 26, 2011

    International Nuclear Information System (INIS)

    2011-01-01

    A strong radioactive contamination of the marine environment close to the damaged Fukushima Dai-ichi power plant has been observed since March 21. The high concentration of some nuclides ( 131 I, 137 Cs, 134 Cs, 136 Cs, 132 Te, 132 I) comes from three possible sources: the liquid effluents from the damaged site, the atmospheric fallouts, and the weathering of contaminated soils. This information note presents and comments the most recent informations gathered by the French institute of radiation protection and nuclear safety (IRSN) since the previous information note from July 11 and devoted to the same topic. It presents the estimation of the relative contribution of each contamination source and the evolution with time of the marine contamination. The mapping of 137 Cs concentrations in surface seawater allows to estimate the amount of total 137 Cs in the marine environment and its evolution with time. 137 Cs and 134 Cs concentrations were measured both in samples of surface coastal sediments and in river fishes and seafood products (mainly fishes and molluscs). Results are reported in graphs showing their evolution with time. (J.S.)

  16. Radioactivity in vegetation at the Fukushima area. A study on contamination by radionuclides released from TEPCO's Fukushima Daiichi nuclear power plants

    International Nuclear Information System (INIS)

    Momoshima, Noriyuki; Sugihara, Sinji; Ozawa, Ryosuke; Nakama, Akimitsu; Ichikawa, Ryohei; Maekawa, Akihiro

    2013-01-01

    Leaves of Kudzu collected from the Fukushima Daiichi NPP accident contamination area are shown to exhibit high levels of "1"3"4Cs and "1"3"7Cs activity. Radioactive dusts that attached to the leaf surface were measured at significant levels (as confirmed by IP) for a sample collected in 2011, but at lower levels for samples collected in 2012. This suggests that root uptake would be considered a major source of internal contamination prior to collection of the 2012 samples. The surface and internal contamination was evaluated for two leaves of the 2011 sample and the radiocesium attached contributed to 13% and 63% of the total activity, respectively. The "1"3"4"+"1"3"7Cs activity of the 2012 samples showed a positive correlation with the radiation dose rate measured at the sampling points; however, the "1"3"4"+"1"3"7Cs activity estimated as an internal fraction still seemed high when compared to that of the 2011 sample. These results suggest that the surface absorption of radiocesium from attached dusts is likely responsible for the observed high internal activity. (author)

  17. Analysis of release and transport of aerial radioactive materials in accident of evaporation to dryness caused by boiling of reprocessed high-level liquid waste

    International Nuclear Information System (INIS)

    Yoshida, Kazuo; Ishikawa, Jun; Abe, Hitoshi

    2015-01-01

    An accident of evaporation to dryness caused by boiling of high-level liquid waste (HLLW) is postulated as one of the severe accidents caused by the loss of cooling function at a fuel reprocessing plant. In this case, some amount of fission products (FPs) will be transferred to the vapor phase in the tank, and could be released to the environment. Therefore, the quantitative estimation of the transport and release behavior of FPs is one of the key issues in the assessment of the accident consequence. To resolve this issue, a systematic analysis method with computer codes has been developed on the basis of the phenomenological behavior in the accident of evaporation to dryness caused by boiling of HLLW. A simulation study demonstrated that the behavior of liquid waste temperature and the entrainment of mists were in good agreement with the experimental results during the early boiling stage, and that some issues to be resolved were pointed out for the estimation of the amount of transferred Ru to the vapor phase at the late boiling stage. (author)

  18. Long term behavior of radioactive plume of TEPCO FNPP1 released 134Cs and 137Cs in the North Pacific Ocean through the end of 2014

    Science.gov (United States)

    Aoyama, Michio; Tsumune, Daisuke; Tsubono, Takaki; Hamajima, Yasunori; Kumamoto, Yuichiro

    2015-04-01

    134Cs and 137Cs, hereafter radiocaesium, were released to the North Pacific Ocean by two major likely pathways, direct discharge from the Fukushima NPP1 accident site and atmospheric deposition off Honshu Islands of Japan, east and northeast of the site. High density observations of 134Cs and 137Cs in the surface water were carried out by 17 cruises of cargo ships and several research vessel cruises since March 2011 till March 2012. Thereafter we and our collaborators continue to collect seawater samples in 2013 and 2014 in the North Pacific Ocean. We also conduct to measure radiocaesium in coastal waters at Tomioka and Hasaki, Japan through the end of 2014. TEPCO and Japanese government also continue to monitor radiocaesium in seawaters close to the site. In this presentation, we present long term behavior of TEPCO FNPP1 released radiocaesium in the coastal region and the North Pacific Ocean based on the observations and model simulations during the period from just after the accident to summer in 2014. In the coastal region very close to TEPCO FNPP1 site, the data show peak ocean discharges in early April 2011, one month after the earthquake and a factor of 1000 decrease in the month following. The 137Cs activity through the end of September 2014 remain higher than expected, ca. 1000 Bq m-3, implying continued releases from the reactors. Since directly discharged radiocaesium were transported dominantly southward along the coastline of northeastern Honshu, the 137Cs activities in coastal seawater collected at Tomioka and Hasaki were still one or two order of magnitude higher, several to 100 Bq m-3, rather than pre-Fukushima level in summer 2014. In the North Pacific Ocean main body of radiocaesium surface plume of which activity exceed 10 Bq m-3 had been travelling along 40 °N, and reached International Date Line on March 2012 one year after the accident. A feature was that the radiocaesium plume was confined along 40 °N when the plume reached International

  19. Radioactive source

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  20. Radioactivity metrology

    International Nuclear Information System (INIS)

    Legrand, J.

    1979-01-01

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

  1. Radioactive wastes

    International Nuclear Information System (INIS)

    Teillac, J.

    1988-01-01

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

  2. The Adoption of Urgent Measures to Protect the Population in the Event of an Accidental Release of Radioactivity into the Environment; 041f 0420 0414

    Energy Technology Data Exchange (ETDEWEB)

    Dikobes, I. K.; Il' In, L. A.; Kozlov, V. M.; Moiseev, A. A. [Ministerstvo Zdravoohranenija SSSR, Moskva, SSSR (Russian Federation); Konstantinov, Ju. O.; Tarasov, S. I.; Shamov, V. P. [Nauchno-Issledovatel' skij Institut Radiacionnoj Gigieny Ministerstva Zdravoohranenija RSFSR, Leningrad, SSSR (Russian Federation)

    1969-10-15

    The authors consider a situation in which there is a risk of the population being seriously exposed to radiation through the accidental entry of radioactive material into the environment. The specific features of the situation under consideration are such that the appropriate protective measures can only be effective if implemented in time, i.e. within the first few hours or days of the emergency. Hence a programme providing for protection of the population against radiation in an emergency should include (a) methods by which the dosimetric information required for a rapid evaluation of the potential radiation hazard can be promptly obtained, and (b) criteria for the . adoption of urgent measures, i.e., the levels of radioactive contamination or irradiation justifying or not justifying the need for the implementation of specific protective measures. The authors make recommendations (draft regulations) on which to base such decisions. The criterion for the decisions is based on two hazard levels (A and B) for each of the irradiation paths, potentially significant in the given situation: external and contact irradiation, inhalation, and contamination of foodstuffs. Decisions to adopt immediate protective measures should be based on a comparison between the evaluated (predicted) hazard levels and the critical levels, defined as those hazard levels at which implementation of the protective measures under consideration is (A) desirable or (B) obligatory, irrespective of the specific circumstances. Figures for the critical levels are chosen with regard to the specific nature of the situation and protective measures, maximum permissible levels for occupational exposure, and known information on the biological risk of certain exposure levels. (author) [Russian] Rassmatrivaetsja takaja situacija, kogda v rezul'tate avarijnogo postuplenija radioaktivnyh veshhestv vo vneshnjuju sredu sozdaetsja opasnost' sushhestvennogo obluchenija naselenija. Specifika rassmatrivaemoj

  3. Method of assessment of the environmental risk associated with releases of radioactive substances. Adaptation to the case of mining sites in Haute-Vienne

    International Nuclear Information System (INIS)

    Beaugelin-Seiller, K.; Garnier-Laplace, J.

    2007-01-01

    This report presents methods which aim at proposing a first quantification (screening) of the potential impact and risk of releases from mining installations at the scale of a drainage basin for a given period, and at refining the characterization of the radiological and/or chemical risk when a potential risk is revealed by the screening step. The screening method allows a parallel assessment of the radio-ecological risk (for the whole set of radionuclides belonging to the uranium family) and of the chemical risk associated with uranium. The refinement is based on the use of probabilistic methods. These approaches lead to the calculation of a deterministic risk index by comparing Predicted Environmental Concentrations (PECs) with Predicted No-Effect Concentrations (PNECs) in the same media

  4. 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.)

  5. Environmental radioactivity

    International Nuclear Information System (INIS)

    1985-01-01

    Outline summary of a report prepared under contract to the DOE: Research Priorities and UK Estuaries: An Overview identifying Research Requirements. Topics considered include the study of radionuclides released into the NE Irish Sea from BNFL, Sellafields, differences in the isotopic composition of stable lead in various sediments, the concentration and distribution of 'hot particles' derived from BNFL in the Irish Sea and adjacent areas, together with attempts to separate hot particles from sediments, and the composition and properties of marine surfaces in relation to uptake and loss of radionuclides, particularly in relation to the common mussel, Mytilus edulis. The problem of the presence of transuranic radionuclides in the bottom sediments of the NE Irish Sea is considered. Profiles of radioactivity are being developed at the shelf-break in order to determine the transfer of radionuclides from the sea surface to the deep sea and to coastal waters; organisms examined include phytoplankton, zooplankton and crustacea (shrimps). Organisms such as Acantharia have been examined to determine transfer of elements and radionuclides to skeletal structures eg Sr, Ba and Si. (U.K.)

  6. Radioactive battery

    International Nuclear Information System (INIS)

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

    1975-01-01

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

  7. A European network of experts with direct responsibility for monitoring and dosimetry after a deliberate release of radioactive material or a deliberate radiation exposure

    International Nuclear Information System (INIS)

    Rahola, Tua; Muikku, Maarit; Pellow, Peter G.D.; Etherington, George; Hodgson, Alan; Youngman, Mike J.; Le Guen, Bernard; Berard, Philippe; Lopez, Maria A.

    2008-01-01

    In the event of an accidental or deliberate release of radionuclides to the environment, individual monitoring and dose assessment may be needed for large numbers of people. The consequences of such incidents are not limited by national boundaries. However, within the European Union (EU), there has not been any coordinated strategy for individual monitoring and dose assessment. CONRAD (CO-ordination Action for Radiation Dosimetry) is an EC 6 th Framework Programme Co-ordination Action sponsored by EURADOS (the European Radiation Dosimetry Group, http://www.eurados.org). The objective of Task 5.4 of Work Package 5 of the CONRAD project, coordinated by HPA (UK) and STUK (Finland), is the development of a network of people and organisations with responsibilities for emergency monitoring of emergency services personnel and members of the public. The network (named EUREMON) aims to promote sharing of information between countries on plans and arrangements for individual monitoring. It currently has 51 individual members from 22 EU countries, 8 non-EU countries and two international organisations. After it was established, the network was used in a survey of plans and arrangements for emergency personal monitoring in EU countries. Information is also being compiled on portable and transportable monitoring facilities and equipment in the EU. (author)

  8. Depth profiles of radioactive cesium and iodine released from the Fukushima Daiichi nuclear power plant in different agricultural fields and forests

    International Nuclear Information System (INIS)

    Ohno, Takeshi; Muramatsu, Yasuyuki; Oda, Kazumasa; Inagawa, Naoya; Ogawa, Hiromu; Yamazaki, Atsuko; Toyama, Chiaki; Miura, Yoshinori; Sato, Mutsuto

    2012-01-01

    In order to understand the behavior of radionuclides released from the Fukushima Daiichi nuclear power plant, the depth distributions of radiocesium and radioiodine were investigated in a wheat field, a rice paddy, an orchard, and a cedar forest in Koriyama, Fukushima Prefecture. Our results demonstrate that, following the nuclear power plant disaster, more than 90% of the radionuclides were distributed in the upper 6 cm of the soil column in the wheat field and within 4 cm of the surface in the rice paddy, orchard, and cedar forest. According to the measurement of radionuclides in the three adjacent agricultural fields, the variation of deposition densities in the wheat field was smaller than that of the orchard and rice paddy, suggesting that the low permeability of the orchard and paddy soils may cause horizontal migration of radionuclides during the initial deposition. This result indicates that the deposition densities in the wheat field should be appropriate for estimating the amount of fallout in the area. The deposition densities of 134 Cs, 137 Cs, and 131 I in this area were estimated to be 512 ± 76 (SD, n = 5), 522 ± 80 (SD, n = 5), and 608 ± 79 (SD, n = 5) kBq/m 2 (decay corrected to April 1, 2011), respectively. A comparison of the deposition density between the wheat field and the cedar forest suggests that more than half of the radionuclides are distributed in the tree canopies of the evergreen forestland. (author)

  9. Doses from radioactive methane

    International Nuclear Information System (INIS)

    Phipps, A.W.; Kendall, G.M.; Fell, T.P.; Harrison, J.D.

    1990-01-01

    A possible radiation hazard arises from exposure to methane labelled with either a 3 H or a 14 C nuclide. This radioactive methane could be released from a variety of sources, e.g. land burial sites containing radioactive waste. Standard assumptions adopted for vapours would not apply to an inert alkane like methane. This paper discusses mechanisms by which radioactive methane would irradiate tissues and provides estimates of doses. Data on skin thickness and metabolism of methane are discussed with reference to these mechanisms. It is found that doses are dominated by dose from the small fraction of methane which is inhaled and metabolised. This component of dose has been calculated under rather conservative assumptions. (author)

  10. Technical subsidies for the operation of IRD/CNEN emergency vehicles in the case of a nuclear accident at the Angra Nuclear Power Plant with associated radioactive releases to the atmosphere

    International Nuclear Information System (INIS)

    Leao, J.L.B.

    1982-03-01

    Technical support is provided for the operation of an emergency vehicle of Instituto de Radioprotecao e Dosimetria/Comissao Nacional de Energia Nuclear, Rio de Janeiro, Brazil, in the event of uncontrolled release of radioactivity from the Angra Nuclear Power Plant (NPP) to the atmosphere. It is based on internationally adopted emergency decision process philosophy, the concept of 'Protective Action Guide' (PAG), the exposure pathways relevant to nuclear accidents, the measuring systems to be used in obtaining the exposure rate in the effluent 'plume', the methods utilized to predict dose to the population, radioiodine suppression measures, the monitoring instrumentation available to the emergency group, some post-accident considerations and finally, the monitoring that may be carried out from an aircraft. Information is given about the NPP operator's responsabilities with respect to the prediction of the consequences of an accident, as well as methods for thyroid and whole body dose estimation based on exposure to the radioiodine and noble gases present in the effluent plume. The example of the Three Mile Island's incident is used to formulate some observations regarding collective dose to the public estimates derived from measurements made from a helicopter. (Author) [pt

  11. New radioactivities

    International Nuclear Information System (INIS)

    Greiner, W.; Sandulescu, A.

    1996-01-01

    Some atomic nuclei reorganize their structure by ejection of big protons and neutrons aggregates. The observation of these new radioactivities specifies the theories of the nuclear dynamics. (authors)

  12. 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.)

  13. Radioactivity Handbook

    International Nuclear Information System (INIS)

    Firestone, R.B.; Browne, E.

    1985-01-01

    The Radioactivity Handbook will be published in 1985. This handbook is intended primarily for applied users of nuclear data. It will contain recommended radiation data for all radioactive isotopes. Pages from the Radioactivity Handbook for A = 221 are shown as examples. These have been produced from the LBL Isotopes Project extended ENDSF data-base. The skeleton schemes have been manually updated from the Table of Isotopes and the tabular data are prepared using UNIX with a phototypesetter. Some of the features of the Radioactivity Handbook are discussed here

  14. Radioactive pollution

    International Nuclear Information System (INIS)

    Pohl, R.O.

    1976-01-01

    The widely published claims that the public health effects resulting from routine emissions are between 0.01 and 0.1 serious health effects per gigawattyear, and hence are at least a thousand times smaller than those resulting from air pollution by the burning of coal, cannot be true, for two reasons. The authors of these claims have ignored at least two of the more important isotopes, radon-222 and carbon-14, which are presently released to the environment, and thus contribute greatly to the health impact of nuclear energy. The health effects calculated in the earlier work cover only those which occur during the year in which the energy is generated. This means, figuratively speaking, that the authors have confused an annual installment payment with the full cost. This is unacceptable. The contribution to the health impact of nuclear energy arising from the single isotopic species radon-222 emanating from the mill tailings is estimated to 400 lung cancer deaths/GW(e)y, larger even than the most pessimistic estimates of the health impact of energy from coal through atmospheric pollution. We have no assurance that other long-lived isotopes do not contribute comparable amounts to the health impact of nuclear energy. The discussion of the health impact of radon-222 raises the fundamental moral question--how far into the future our responsibility extends. If such a long-termresponsibility is rejected, then we must at least try to predict the environmental buildup of radioactive pollutants, in order to avoid unacceptable and irreversible levels of radiation dose rate. The potential health consequences from long-lived radioisotopes seem to have been largely ignored so far, and should be explored in detail

  15. Radioactivity. Centenary of radioactivity discovery

    International Nuclear Information System (INIS)

    Charpak, G.; Tubiana, M.; Bimbot, R.

    1997-01-01

    This small booklet was edited for the occasion of the exhibitions of the celebration of the centenary of radioactivity discovery which took place in various locations in France from 1996 to 1998. It recalls some basic knowledge concerning radioactivity and its applications: history of discovery, atoms and isotopes, radiations, measurement of ionizing radiations, natural and artificial radioactivity, isotope dating and labelling, radiotherapy, nuclear power and reactors, fission and fusion, nuclear wastes, dosimetry, effects and radioprotection. (J.S.)

  16. Chapter 2. Peculiarities of radioactive particle formation and isotope fractionation resulted from underground nuclear explosions

    International Nuclear Information System (INIS)

    1996-01-01

    Radioactive particles, forming terrain fallouts from underground nuclear explosion differ sufficiently from radioactive particles, produced by atmospheric nuclear explosions. Patterns of underground nuclear explosion development, release of radioactivity to the atmosphere, formation of a cloud and base surge, peculiarities of formed radioactive particles, data on isotope fractionation in radioactive particles are presented. Scheme of particle activation, resulted from underground explosions is given

  17. Effects of natural radioactivity on food radioactivity measurement

    International Nuclear Information System (INIS)

    Ennyu, Atsuhito

    2012-01-01

    Since the accident of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Company, groups and individuals including local governments, food manufacturers, distribution circles, retail circles, and citizens are eager to measure the radioactivity of food, in order to confirm the safety of food from the concerns about radioactive contamination. The measurement of radioactivity of food is done by quantitatively determining gamma rays due to radioactive cesium that was incorporated into the biosphere cycle after having been released into the environment. As for the radioactivity measurement of food using gamma-ray spectrometry with a potassium iodide scintillation detector, which is very commonly used, this paper describes the handling method of obtained data, the principle of erroneous detection of radioactive cesium and iodine interrupted by natural radionuclides, and countermeasures for it. Major natural radioactivity sources are uranium series and thorium series. This paper explains gamma rays, which are characteristic in the decay process of uranium series and often affect the measurement of radioactive cesium in food and water. (O.A.)

  18. Plant air quality following accidental radioactive releases

    International Nuclear Information System (INIS)

    Slawson, P.R.; Hitchman, G.J.

    1987-01-01

    Radionuclides exhausted to the atmosphere through vent stacks may contaminate the immediate building structure and/or nearby adjacent buildings resulting in hazardous contaminants entering the intake air. The objective of the work reported here was to obtain an overview of the analytical and experimental tools available to evaluate the transport and diffusion of vented effluents, and the nature of flows about structures, in order to predict the concentrations adjacent to an subsequently inside the immediate and nearby structures. A scaling analysis established the requirements for physical modelling of flows about structures in wind and/or water tunnels. Subsequently, a series of test model studies were conducted in a water tunnel in the Mechanical Engineering Department of the University of Waterloo. The expected result that increased stack height and structure separation have on reducing recirculation and interference is clearly illustrated. Interference was still significant on the downstream structure when the vent stack height was increased to its maximum of one model cube height above the cube. A literature survey was conducted to establish the nature and mathematical modelling of flows about structures. Also, mathematical modelling of the concentration field from roof-top vent effluents and subsequently the models for predicting concentrations within structures was investigated. No specific data on concentrations within structures were found. There is a strong need for well documented test on the concentration fields about model structures, with which more generic models may be developed. Very little data is available on multiple structures. It is recommended that physical model studies be conducted, that simulate realistic exhaust and intake air vents with measurement of both the inside and the outside concentration fields. (59 refs., 21 figs., 2 tabs.)

  19. Simulated Radioactivity

    Science.gov (United States)

    Boettler, James L.

    1972-01-01

    Describes the errors in the sugar-cube experiment related to radioactivity as described in Project Physics course. The discussion considers some of the steps overlooked in the experiment and generalizes the theory beyond the sugar-cube stage. (PS)

  20. Concentrating Radioactivity

    Science.gov (United States)

    Herrmann, Richard A.

    1974-01-01

    By concentrating radioactivity contained on luminous dials, a teacher can make a high reading source for classroom experiments on radiation. The preparation of the source and its uses are described. (DT)

  1. Radioactive Iodine

    Science.gov (United States)

    ... order to limit radiation exposure to others (see chart). I-131 may occasionally cause mild pain in ... Statement on Thyroid Shielding During Diagnostic Medical and Dental Radiology By ATA | 2013 News Releases , News Releases , ...

  2. Radioactive wastes

    International Nuclear Information System (INIS)

    Grass, F.

    1982-01-01

    Following a definition of the term 'radioactive waste', including a discussion of possible criteria allowing a delimitation of low-level radioactive against inactive wastes, present techniques of handling high-level, intermediate-level and low-level wastes are described. The factors relevant for the establishment of definitive disposals for high-level wastes are discussed in some detail. Finally, the waste management organization currently operative in Austria is described. (G.G.)

  3. Safety disposal studies of radioactive and hazardous wastes using cement

    International Nuclear Information System (INIS)

    Aly, M.M.E.

    2000-01-01

    radioactive waste is generated from the production of nuclear energy and from the use of radioactive materials applications, agriculture and medicine. the important of safe management of radioactive waste for the protection of human health and the environment has long been recognized. conditioning of radioactive waste is the transform of radioactive waste into a suitable form for storage and disposal. common immobilization methods include solidification of low radioactive waste in cement or bitumen.in order to improve cement properties to decrease the release of liquid radioactive waste into the environment and its dispersion to a level where the risks to individuals, population and the environment

  4. 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.)

  5. Sampling airborne radioactivity

    International Nuclear Information System (INIS)

    Cohen, B.S.

    1988-01-01

    Radioactive contaminants have historically been considered apart from chemical contaminants because it is their radiological properties that determine their biological and environmental impact. Additionally they have been regulated by special government agencies concerned with radiological protection. Radioactive contaminants are also distinguished by the specialized and very sensitive methods available for the detection of radioactivity. Measurements of a few thousand atoms per liter are not uncommon. Radiation detectors in common use are gas filled chambers, scintillation and semiconductor detectors, and the more recently developed thermoluminescent and etched track detectors. Solid-state nuclear track detectors consist of a large group of inorganic and organic dielectrics which register tracks when traversed by heavy charged particles. They do not respond to light, beta particles or gamma ray photons and thus provide a very low background system for the detection of extremely low levels of radioactivity. In addition, no power source or electronic equipment is required. Cellulose nitrate detectors are currently in use for long term integrated sampling of environmental radon. Thermoluminescent dosimeters (TID's) are crystalline materials, in which electrons which have been displaced by an interaction with ionizing radiation become trapped at an elevated energy level and emit visible light when released from that energy level. As which etched-track detectors no power or electronic equipment is needed for the TID's at a measurement site, but they respond to alpha, beta and gamma radiation. Thermoluminescent dosimeters are useful for long term environmental monitoring, and have also been newly incorporated into integrating radon detection systems

  6. Decontamination for free release

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, K A; Elder, G R [Bradtec Ltd., Bristol (United Kingdom)

    1997-02-01

    Many countries are seeking to treat radioactive waste in ways which meet the local regulatory requirements, but yet are cost effective when all contributing factors are assessed. In some countries there are increasing amounts of waste, arising from nuclear plant decommissioning, which are categorized as low level waste: however with suitable treatment a large part of such wastes might become beyond regulatory control and be able to be released as non-radioactive. The benefits and disadvantages of additional treatment before disposal need to be considered. Several processes falling within the overall description of decontamination for free release have been developed and applied, and these are outlined. In one instance the process seeks to take advantage of techniques and equipment used for decontaminating water reactor circuits intermittently through reactor life. (author). 9 refs, 1 fig., 3 tabs.

  7. Radioactive gas processing device

    International Nuclear Information System (INIS)

    Kita, Kaoru; Minemoto, Masaki; Takezawa, Kazuaki; Okazaki, Akira; Kumagaya, Koji.

    1982-01-01

    Purpose: To simplify the structure of a gas processing system which has hitherto been much complicated by the recyclic use of molecular sieve regeneration gas, by enabling to release the regeneration gas to outside in a once-through manner. Constitution: The system comprises a cooler for receiving and cooling gases to be processed containing radioactive rare gases, moisture-removing pipelines each connected in parallel to the exit of the cooler and having switching valves and a moisture removing column disposed between the valves and a charcoal absorber in communication with the moisture removing pipelines. Pipelines for flowing regeneration heating gases are separately connected to the moisture removing columns, and molecular sieve is charged in the moisture removing column by the amount depending on the types of the radioactive rare gases. (Aizawa, K.)

  8. Radioactivity in the oceans

    International Nuclear Information System (INIS)

    Templeton, W.L.

    1979-01-01

    While the revised ''Definition and Recommendations'' of the International Atomic Energy Agency (IAEA) restricts the dumping of the radioactive wastes that exceed specified concentration/mass limits, the acceptance of the concept of applying the release rate limits as developed by the IAEA provides a rational basis for further considering the emplacement of radioactive wastes in seabed as an attractive and acceptable alternative to terrestrial geological repositories. The technical basis for the present radiological assessment is on release rate limits and not on dumping rates. However, to meet the present requirements of the London Convention, it is necessary to express to Definition in terms of the concentration in a single site and the assumed upper limit on mass dumping rate at a single site of 100,000 tons/year with the added proviso of release rate limits for the finite ocean volume of 10 17 m 3 . This results in the concentration limits of a) 1 Ci/ton for α-emitters but limited to 10 -1 Ci/ton 226 Ra and supported 210 Po; b) 10 2 Ci/ton for β/γ-emitters with half-lives of at least 0.5 yr (excluding 3 H) and the mixtures of β/γ-emitters of unknown half-lives; and c) 10 6 Ci/ton for 3 H and the β/γ-emitters with half-lives less than 0.5 yr. (Yamashita, S.)

  9. Gaseous radioactive waste processing system

    International Nuclear Information System (INIS)

    Onizawa, Hideo.

    1976-01-01

    Object: To prevent explosion of hydrogen gas within gaseous radioactive waste by removing the hydrogen gas by means of a hydrogen absorber. Structure: A coolant extracted from a reactor cooling system is sprayed by nozzle into a gaseous phase (hydrogen) portion within a tank, thus causing slipping of radioactive rare gas. The gaseous radioactive waste rich in hydrogen, which is purged in the tank, is forced by a waste gas compressor into a hydrogen occlusion device. The hydrogen occlusion device is filled with hydrogen occluding agents such as Mg, Mg-Ni alloy, V-Nb alloy, La-Ni alloy and so forth, and hydrogen in the waste gas is removed through reaction to produce hydrogen metal. The gaseous radioactive waste, which is deprived of hydrogen and reduced in volume, is stored in an attenuation tank. The hydrogen stored in the hydrogen absorber is released and used again as purge gas. (Horiuchi, T.)

  10. Radioactive waste gas processing systems

    International Nuclear Information System (INIS)

    Kita, Kaoru; Minemoto, Masaki; Takezawa, Kazuaki.

    1981-01-01

    Purpose: To effectively separate and remove only hydrogen from hydrogen gas-containing radioactive waste gases produced from nuclear power plants without using large scaled facilities. Constitution: From hydrogen gas-enriched waste gases which contain radioactive rare gases (Kr, Xe) sent from the volume control tank of a chemical volume control system, only the hydrogen is separated in a hydrogen separator using palladium alloy membrane and rare gases are concentrated, volume-decreased and then stored. In this case, an activated carbon adsorption device is connected at its inlet to the radioactive gas outlet of the hydrogen separator and opened at its outlet to external atmosphere. In this system, while only the hydrogen gas permeates through the palladium alloy membrane, other gases are introduced, without permeation, into the activated carbon adsorption device. Then, the radioactive rare gases are decayed by the adsorption on the activated carbon and then released to the external atmosphere. (Furukawa, Y.)

  11. Radioactive wastes

    International Nuclear Information System (INIS)

    Dupuis, M.C.

    2007-01-01

    Managing radioactive wastes used to be a peripheral activity for the French atomic energy commission (Cea). Over the past 40 years, it has become a full-fledged phase in the fuel cycle of producing electricity from the atom. In 2005, the national radioactive waste management agency (ANDRA) presented to the government a comprehensive overview of the results drawn from 15 years of research. This landmark report has received recognition beyond France's borders. By broadening this agency's powers, an act of 28 June 2006 acknowledges the progress made and the quality of the results. It also sets an objective for the coming years: work out solutions for managing all forms of radioactive wastes. The possibility of recovering wastes packages from the disposal site must be assured as it was asked by the government in 1998. The next step will be the official demand for the creation of a geological disposal site in 2016

  12. 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

  13. Radioactivity measurement

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  14. 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)

  15. Measurement of gamma radioactivity in steel

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  16. Radioactivity measurements

    International Nuclear Information System (INIS)

    Schwach, G.

    1986-01-01

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

  17. Disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Dlouhy, Z.

    1982-01-01

    This book provides information on the origin, characteristics and methods of processing of radioactive wastes, as well as the philosophy and practice of their storage and disposal. Chapters are devoted to the following topics: radioactive wastes, characteristics of radioactive wastes, processing liquid and solid radioactive wastes, processing wastes from spent fuel reprocessing, processing gaseous radioactive wastes, fixation of radioactive concentrates, solidification of high-level radioactive wastes, use of radioactive wastes as raw material, radioactive waste disposal, transport of radioactive wastes and economic problems of radioactive wastes disposal. (C.F.)

  18. The situation of radioactive waste management in the fuel reprocessing facility (for fiscal 1979)

    International Nuclear Information System (INIS)

    1981-01-01

    In the fuel reprocessing facility of Power Reactor and Nuclear Fuel Development Corporation (PNC), the release of radioactive gaseous and liquid wastes was so controlled as not to exceed the set standards. Of the radioactive liquid wastes, concentrated wastes and sludge are stored in tanks. Radioactive solid wastes are suitably stored in containers. The situation of radioactive waste management in the fuel reprocessing facility in fiscal 1979 (from April, 1979, to March, 1980) is presented on the basis of the radiation control report made by PNC. The release of radioactive gaseous and liquid wastes was below the set standards. The following data are given in tables: the released quantity of radioactive gaseous and liquid wastes, the cumulative stored amount of radioactive liquid wastes, the produced quantity and cumulative stored amount of radioactive solid wastes; (for reference) the released quantity of radioactive gaseous and liquid wastes in fiscal 1977, 1978 and 1979. (J.P.N.)

  19. Thermosensitive shutter for radioactive source housing

    International Nuclear Information System (INIS)

    Fullagar, H.

    1986-01-01

    A shutter apparatus for a radioactive source housing comprises a movable member and a thermosensitive releasing means operative normally to hold the movable member in an open position but to release the movable member to move to a position closing the housing to contain the source when the temperature exceeds a predetermined value, for example as a result of fire. (author)

  20. Radioactive tracer system to indicate drill bit wear or failure

    International Nuclear Information System (INIS)

    Fries, B.A.

    1975-01-01

    A radioactive tracer system for indicating drill bit wear or failure utilizing radioactive krypton 85 in clathrate form, in the form of water-soluble kryptonates, or dissolved grease, is described. Preferably the radioactive krypton is placed so that when drill bit wear or failure occurs, the radioactive krypton 85 is relased and effectively becomes diffused in the circulating drilling fluid. At the surface, the radioactive krypton 85 gas is separated from the circulating drilling fluid by gas-mud separating means and is transported as a gas to a counting chamber where an accurate radioactivity count of beta rays released from the krypton is obtained. (Patent Office Record)

  1. Radioactive waste management

    International Nuclear Information System (INIS)

    2013-01-01

    This eighth chapter presents the radioactive wastes and waste disposal; classification of radioactive wastes; basis requests of the radioactive waste management; conditions for a radioactive waste disposal; registers and inventories; transport of radioactive wastes from a facility to another and the radioactive waste management plan

  2. Radioactive wastes handling facility

    International Nuclear Information System (INIS)

    Hirose, Emiko; Inaguma, Masahiko; Ozaki, Shigeru; Matsumoto, Kaname.

    1997-01-01

    There are disposed an area where a conveyor is disposed for separating miscellaneous radioactive solid wastes such as metals, on area for operators which is disposed in the direction vertical to the transferring direction of the conveyor, an area for receiving the radioactive wastes and placing them on the conveyor and an area for collecting the radioactive wastes transferred by the conveyor. Since an operator can conduct handling while wearing a working cloth attached to a partition wall as he wears his ordinary cloth, the operation condition can be improved and the efficiency for the separating work can be improved. When the area for settling conveyors and the area for the operators is depressurized, cruds on the surface of the wastes are not released to the outside and the working clothes can be prevented from being involved. Since the wastes are transferred by the conveyor, the operator's moving range is reduced, poisonous materials are fallen and moved through a sliding way to an area for collecting materials to be separated. Accordingly, the materials to be removed can be accumulated easily. (N.H.)

  3. Security of Radioactive Waste

    International Nuclear Information System (INIS)

    Goldammer, W.

    2003-01-01

    Measures to achieve radioactive waste security are discussed. Categorization of waste in order to implement adequate and consistent security measures based on potential consequences is made. The measures include appropriate treatment/storage/disposal of waste to minimize the potential and consequences of malicious acts; management of waste only within an authorised, regulated, legal framework; management of the security of personnel and information; measures to minimize the acquisition of radioactive waste by those with malicious intent. The specific measures are: deter unauthorized access to the waste; detect any such attempt or any loss or theft of waste; delay unauthorized access; provide timely response to counter any attempt to gain unauthorised access; measures to minimize acts of sabotage; efforts to recover any lost or stolen waste; mitigation and emergency plans in case of release of radioactivity. An approach to develop guidance, starting with the categorisation of sources and identification of dangerous sources, is presented. Dosimetric criteria for internal and external irradiation are set. Different exposure scenarios are considered. Waste categories and security categories based on the IAEA INFCIRC/225/Rev.4 are presented

  4. Artificial radioactivity in Lough Foyle

    International Nuclear Information System (INIS)

    Cunningham, J.D.; Ryan, T.P.; Lyons, S.; Smith, V.; McGarry, A.; Mitchell, P.I.; Leon Vintro, L.; Larmour, R.A.; Ledgerwood, F.K.

    1996-04-01

    The purpose of this study was to assess the extent to which the marine environment of Lough Foyle, situated on the north coast of Ireland, has been affected by artificial radioactivity released from Sellafield. Although traces of plutonium, americium and radiocaesium from Sellafield are detectable in Lough Foyle, the concentrations in various marine media are significantly lower than those found along the NE coast of Ireland and in the western Irish Sea. The minute quantities of artificial radioactivity found in Lough Foyle are of negligible radiological significance

  5. Radioactive contamination of sewage sludge

    International Nuclear Information System (INIS)

    Soeder, C.J.; Zanders, E.; Raphael, T.

    1986-01-01

    Because of the radioactivity released through the explosion of the nuclear reactor near Chernobyl radionuclides have been accumulated to a significant extent in sewage sludge in the Federal Republic of Germany. This is demonstrated for samples from four activated sludge plants according to a recent recommendation of the German Commission for Radiation Protection, there is until now no reason to deviate from the common practices of sludge disposal or incineration. The degree of radioactive contamination of plant materials produced on farm lands on which sewage sludge is being spread cannot be estimated with sufficient certainty yet. Additional information is required. (orig.) [de

  6. Radioactive waste

    International Nuclear Information System (INIS)

    Berkhout, F.

    1991-01-01

    Focusing on radioactive waste management and disposal policies in the United Kingdom, Sweden and the Federal Republic of Germany, this book gives a detailed historical account of the policy process in these three countries, and draws out the implications for theory and public policy. This comparative approach underlines how profoundly different the policy process has been in different countries. By comparing the evolution of policy in three countries, fundamental questions about the formation and resolution of technical decisions under uncertainty are clarified. The analysis of nuclear strategy, the politics of nuclear power, and the shifting emphasis of government regulation redefines the issue of radwaste management and sets it at the heat of the current debate about power, the environment and society. The combination of up-to-date technological assessment with an account of the social and political implications of radwaste management makes'Radioactive Waste'particularly useful to students of environmental studies, geography and public administration. (author)

  7. Radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Berkhout, F

    1991-01-01

    Focusing on radioactive waste management and disposal policies in the United Kingdom, Sweden and the Federal Republic of Germany, this book gives a detailed historical account of the policy process in these three countries, and draws out the implications for theory and public policy. This comparative approach underlines how profoundly different the policy process has been in different countries. By comparing the evolution of policy in three countries, fundamental questions about the formation and resolution of technical decisions under uncertainty are clarified. The analysis of nuclear strategy, the politics of nuclear power, and the shifting emphasis of government regulation redefines the issue of radwaste management and sets it at the heat of the current debate about power, the environment and society. The combination of up-to-date technological assessment with an account of the social and political implications of radwaste management makes'Radioactive Waste'particularly useful to students of environmental studies, geography and public administration. (author).

  8. Radioactive transformations

    CERN Document Server

    Rutherford, Ernest

    2012-01-01

    Radioactive Transformations describes Ernest Rutherford's Nobel Prize-winning investigations into the mysteries of radioactive matter. In this historic work, Rutherford outlines the scientific investigations that led to and coincided with his own research--including the work of Wilhelm Rӧntgen, J. J. Thomson, and Marie Curie--and explains in detail the experiments that provided a glimpse at special relativity, quantum mechanics, and other concepts that would shape modern physics. This new edition features a comprehensive introduction by Nobel Laureate Frank Wilczek which engagingly explains how Rutherford's early research led to a better understanding of topics as diverse as the workings of the atom's nucleus, the age of our planet, and the fusion in stars.

  9. Radioactive hazards

    International Nuclear Information System (INIS)

    Gill, J.R.

    1980-01-01

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

  10. Radioactive wastes

    International Nuclear Information System (INIS)

    Devarakonda, M.S.; Melvin, J.M.

    1994-01-01

    This paper is part of the Annual Literature Review issue of Water Environment Research. The review attempts to provide a concise summary of important water-related environmental science and engineering literature of the past year, of which 40 separate topics are discussed. On the topic of radioactive wastes, the present paper deals with the following aspects: national programs; waste repositories; mixed wastes; waste processing and decommissioning; environmental occurrence and transport of radionuclides; and remedial actions and treatment. 178 refs

  11. Report of radioactivity survey research in fiscal year 1996

    International Nuclear Information System (INIS)

    1997-12-01

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

  12. Report of radioactivity survey research in fiscal year 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

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

  13. Limits for the release of uranium compounds to the environment

    International Nuclear Information System (INIS)

    Lopez, F.; Ferruz, P.; Aguayo, A.

    1987-01-01

    A conservative criteria to be be followed by a Regulatory Body, in order to provide the limits of radioactive material release in the environment, When all the parameters are not available for the optimization of radiation protection is presented. This criteria can be applied to stablishment of radioactive release limits for uranium compounds from the nuclear fuel cycle facilities. (author)

  14. COMMERCIAL SNF ACCIDENT RELEASE FRACTIONS

    Energy Technology Data Exchange (ETDEWEB)

    S.O. Bader

    1999-10-18

    The purpose of this design analysis is to specify and document the total and respirable fractions for radioactive materials that are released from an accident event at the Monitored Geologic Repository (MGR) involving commercial spent nuclear fuel (CSNF) in a dry environment. The total and respirable release fractions will be used to support the preclosure licensing basis for the MGR. The total release fraction is defined as the fraction of total CSNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. The radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses. This subset of the total release fraction is referred to as the respirable release fraction. Potential accidents may involve waste forms that are characterized as either bare (unconfined) fuel assemblies or confined fuel assemblies. The confined CSNF assemblies at the MGR are contained in shipping casks, canisters, or disposal containers (waste packages). In contrast to the bare fuel assemblies, the container that confines the fuel assemblies has the potential of providing an additional barrier for diminishing the total release fraction should the fuel rod cladding breach during an accident. However, this analysis will not take credit for this additional bamer and will establish only the total release fractions for bare unconfined CSNF assemblies, which may however be

  15. COMMERCIAL SNF ACCIDENT RELEASE FRACTIONS

    International Nuclear Information System (INIS)

    S.O. Bader

    1999-01-01

    The purpose of this design analysis is to specify and document the total and respirable fractions for radioactive materials that are released from an accident event at the Monitored Geologic Repository (MGR) involving commercial spent nuclear fuel (CSNF) in a dry environment. The total and respirable release fractions will be used to support the preclosure licensing basis for the MGR. The total release fraction is defined as the fraction of total CSNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. The radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses. This subset of the total release fraction is referred to as the respirable release fraction. Potential accidents may involve waste forms that are characterized as either bare (unconfined) fuel assemblies or confined fuel assemblies. The confined CSNF assemblies at the MGR are contained in shipping casks, canisters, or disposal containers (waste packages). In contrast to the bare fuel assemblies, the container that confines the fuel assemblies has the potential of providing an additional barrier for diminishing the total release fraction should the fuel rod cladding breach during an accident. However, this analysis will not take credit for this additional bamer and will establish only the total release fractions for bare unconfined CSNF assemblies, which may however be

  16. Radioactivity telemetry

    International Nuclear Information System (INIS)

    Bouras, Florent; Legrand, Bernard; Montigaud, Jean-Marie; Grandin, Marc

    1969-05-01

    The authors present an assembly which aims at radio-transmitting from mobile stations information on radioactivity. It comprises 20 mobile stations which can be located within the Cadarache Centre or outside of it within a 10 km radius, and a central station which centralises information. The report proposes a general presentation of these stations, their characteristics and principles of operation. It describes operation sequences, central station functions (call programmer, address and memory management, recording, peripherals) and its energy supply, and mobile station functions. The last part presents the installation, its start-up and exploitation, its threshold devices and its safety device

  17. Radioactive waste management in a fuel reprocessing facility in fiscal 1982

    International Nuclear Information System (INIS)

    1984-01-01

    In the fuel reprocessing facility of the Power Reactor and Nuclear Fuel Development Corporation, radioactive gaseous and liquid waste are released not exceeding the respective permissible levels. Radioactive concentrated solutions are stored at the site. Radioactive solid waste are stored appropriately at the site. In fiscal 1982, the released quantities of radioactive gaseous and liquid waste were both below the permissible levels. The results of radioactive waste management in the fuel reprocessing facility in fiscal 1982 are given in the tables: the released quantities of radioactive gaseous and liquid waste, the produced quantities of radioactive solid waste, and the stored quantities of radioactive concentrated solutions and of radioactive solid waste as of the end of fiscal 1982. (Mori, K.)

  18. Environmental Radioactivity. Chapter 4

    International Nuclear Information System (INIS)

    Muhamat Omar; Ismail Sulaiman; Zalina Laili

    2015-01-01

    This chapter explains several things which consist radioactivity measurements, regular and high background radioactivity, radioactive contaminated soil and radioactivity in fertilizers, rocks, building materials, food, water, environments, sediments, flora and fauna. Besides, the natural radioactive gas concentration of radon and toron in the environment also been discussed specifically in this chapter.

  19. Radioactive waste handling at the Mochovce NPP, 1998-2008

    International Nuclear Information System (INIS)

    Vasickova, Gabriela

    2009-01-01

    The radioactive waste management system at the Mochovce NPP is described. The system addresses technical aspects as well as administrative provisions related to radioactive waste generated within the controlled area, from the waste generation phase to waste sorting, packaging, storage, recording, measurement, and transportation to the Bohunice waste processing facility or transfer to the Mochovce liquid radioactive waste treatment facility. The article also addresses conditions for release from the controlled area to the environment for radioactive waste which can be exempt from the institutional administrative control system or released to the environment on the basis of a valid permission issued by the relevant regulatory authority

  20. Development of an application simulating radioactive sources

    International Nuclear Information System (INIS)

    Riffault, V.; Locoge, N.; Leblanc, E.; Vermeulen, M.

    2011-01-01

    This paper presents an application simulating radioactive gamma sources developed in the 'Ecole des Mines' of Douai (France). It generates raw counting data as an XML file which can then be statistically exploited to illustrate the various concepts of radioactivity (exponential decay law, isotropy of the radiation, attenuation of radiation in matter). The application, with a spread sheet for data analysis and lab procedures, has been released under free license. (authors)

  1. Radiological testing of products containing radioactivity

    International Nuclear Information System (INIS)

    Dixon, D.W.; Knight, A.

    1980-01-01

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

  2. Solidification method of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Baba, Tsutomu; Chino, Koichi; Sasahira, Akira; Ikeda, Takashi

    1992-07-24

    Metal solidification material can completely seal radioactive wastes and it has high sealing effect even if a trace amount of evaporation should be caused. In addition, the solidification operation can be conducted safely by using a metal having a melting point of lower than that of the decomposition temperature of the radioactive wastes. Further, the radioactive wastes having a possibility of evaporation and scattering along with oxidation can be solidified in a stable form by putting the solidification system under an inert gas atmosphere. Then in the present invention, a metal is selected as a solidification material for radioactive wastes, and a metal, for example, lead or tin having a melting point of lower than that of the decomposition temperature of the wastes is used in order to prevent the release of the wastes during the solidification operation. Radioactive wastes which are unstable in air and scatter easily, for example, Ru or the like can be converted into a stable solidification product by conducting the solidification processing under an inert gas atmosphere. (T.M.).

  3. Surveillance of the environmental radioactivity

    International Nuclear Information System (INIS)

    Schneider, Th.; Gitzinger, C.; Jaunet, P.; Eberbach, F.; Clavel, B.; Hemidy, P.Y.; Perrier, G.; Kiper, Ch.; Peres, J.M.; Josset, M.; Calvez, M.; Leclerc, M.; Leclerc, E.; Aubert, C.; Levelut, M.N.; Debayle, Ch.; Mayer, St.; Renaud, Ph.; Leprieur, F.; Petitfrere, M.; Catelinois, O.; Monfort, M.; Baron, Y.; Target, A.

    2008-01-01

    The objective of these days was to present the organisation of the surveillance of the environmental radioactivity and to allow an experience sharing and a dialog on this subject between the different actors of the radiation protection in france. The different presentations were as follow: evolution and stakes of the surveillance of radioactivity in environment; the part of the European commission, regulatory aspects; the implementation of the surveillance: the case of Germany; Strategy and logic of environmental surveillance around the EDF national centers of energy production; environmental surveillance: F.B.F.C. site of Romans on Isere; steps of the implementation 'analysis for release decree at the F.B.F.C./C.E.R.C.A. laboratory of Romans; I.R.S.N. and the environmental surveillance: situation and perspectives; the part of a non institutional actor, the citizenship surveillance done by A.C.R.O.; harmonization of sampling methods: the results of inter operators G.T. sampling; sustainable observatory of environment: data traceability and samples conservation; inter laboratories tests of radioactivity measurements; national network of environmental radioactivity measurement: laboratories agreements; the networks of environmental radioactivity telemetry: modernization positioning; programme of observation and surveillance of surface environment and installations of the H.A.-M.A.V.L. project (high activity and long life medium activity); Evolution of radionuclides concentration in environment and adaptation of measurements techniques to the surveillance needs; the national network of radioactivity measurement in environment; modes of data restoration of surveillance: the results of the Loire environment pilot action; method of sanitary impacts estimation in the area of ionizing radiations; the radiological impact of atmospheric nuclear tests in French Polynesia; validation of models by the measure; network of measurement and alert management of the atmospheric

  4. Treatment of hyperthyroidism with radioactive iodine

    International Nuclear Information System (INIS)

    Bell, R.L.

    1974-01-01

    While radioactive iodine is clearly the therapy of choice for Graves' disease (even in younger patients) the use of radioactive iodine for therapy of the toxic multinodular or uninodular goiter presents an entirely different problem. Although these two entities can be treated with radioactive iodine provided there is some suppression of the tissue that is not autonomous, transient release of thyroid hormone may induce symptoms of thyroid storm in the very large multinodular toxic goiter treated with radioiodine therapy. These toxic nodules generally require much larger doses of radioiodine than is commonly used for classical Graves' disease and may either require fractional administration of radioisotopes or concomitant use of antithyroid drugs and iodides. In general, surgery remains the treatment of choice for large toxic multinodular goiters, after proper preparation by medical means including radioactive iodine. Radioactive iodine therapy for hyperthyroidism is contraindicated in pregnancy and generally is not used in children below five years of age. (U.S.)

  5. Storage of solid and liquid radioactive material

    International Nuclear Information System (INIS)

    Matijasic, A.; Gacinovic, O.

    1961-01-01

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

  6. Inventory of accidents and losses at sea involving radioactive material

    International Nuclear Information System (INIS)

    2001-09-01

    The present report describes the content of the inventory of accidents and losses at sea involving radioactive material. It covers accidents and losses resulting in the actual release of radioactive materials into the marine environment and also those which have the potential for release. For completeness, records of radioactive materials involved in accidents but which were recovered intact from the sea are also reported. Information on losses of sealed sources resulting in actual or potential release of activity to the marine environment nad of sealed sources that were recovered intact is also presented

  7. Radioactive waste treatment and handling in France

    International Nuclear Information System (INIS)

    Sivintsev, Yu.V.

    1984-01-01

    Classification of radioactive wastes customary in France and the program of radiation protection in handling them are discussed. Various methods of radioactive waste processing and burial are considered. The French classification of radioactive wastes differs from one used in the other countries. Wastes are classified under three categories: A, B and C. A - low- and intermediate-level radioactive wastes with short-lived radionuclides (half-life - less than 30 years, negligible or heat release, small amount of long-lived radionuclides, especially such as plutonium, americium and neptunium); B - low- and intermediate-level radioactive wastes with long-lived radionuclides (considerable amounts of long-lived radionuclides including α-emitters, low and moderate-level activity of β- and γ-emitters, low and moderate heat release); C - high-level radioactive wastes with long-lived radionuclides (high-level activity of β- and γ-emitters, high heat release, considerable amount of long-lived radionuclides). Volumetric estimations of wastes of various categories and predictions of their growth are given. It is noted that the concept of closed fuel cycle with radiochemical processing of spent fuel is customary in France

  8. Environmental Radioactive Pollution Sources and Effects on Man

    International Nuclear Information System (INIS)

    El-Naggar, A.M.

    1999-01-01

    The sources of environmental radioactivity are essentially the naturally occurring radionuclides in the earth,s crust and the cosmogenic radionuclides reaching the environmental ecosystems. The other sources of environmental radioactivity are the man made sources which result from the radioactive materials in human life. The naturally occurring environmental radioactivity is an integral component of the terrestrial and extraterrestrial creation, and therefore it is not considered a source of radioactive pollution to the environment. The radioactive waste from human activities is released into the environment, and its radionuclide content becomes incorporated into the different ecosystems. This results in a situation of environmental radioactive pollution. This review presents the main features of environmental radioactive pollution, the radionuclide behaviour in the ecosystems, pathway models of radionuclides in the body and the probability of associated health hazards. The dose effect relationship of internal radiation exposure and its quantitative aspects are considered because of their relevance to this subject

  9. Radioactivity from Plowshare applications - Safety considerations

    International Nuclear Information System (INIS)

    Tewes, H.A.

    1970-01-01

    When the Plowshare Program was first being seriously considered some 13 years ago, a number of applications immediately suggested themselves. However, it soon became obvious that most of these applications had the drawback of producing and distributing appreciable quantities of radioactivity to the environment. Thus, the Atomic Energy Commission, together with its contractors, formulated and put into effect a program aimed at dealing with this problem, both from the standpoint of reducing the amount of radioactivity released to the environment and understanding the impact of this radioactivity on the biosphere

  10. Radioactivity from Plowshare applications - Safety considerations

    Energy Technology Data Exchange (ETDEWEB)

    Tewes, H A [Lawrence Radiation Laboratory, University of California, Livermore, CA (United States)

    1970-05-01

    When the Plowshare Program was first being seriously considered some 13 years ago, a number of applications immediately suggested themselves. However, it soon became obvious that most of these applications had the drawback of producing and distributing appreciable quantities of radioactivity to the environment. Thus, the Atomic Energy Commission, together with its contractors, formulated and put into effect a program aimed at dealing with this problem, both from the standpoint of reducing the amount of radioactivity released to the environment and understanding the impact of this radioactivity on the biosphere.

  11. Simplified scheme or radioactive plume calculations

    International Nuclear Information System (INIS)

    Gibson, T.A.; Montan, D.N.

    1976-01-01

    A simplified mathematical scheme to estimate external whole-body γ radiation exposure rates from gaseous radioactive plumes was developed for the Rio Blanco Gas Field Nuclear Stimulation Experiment. The method enables one to calculate swiftly, in the field, downwind exposure rates knowing the meteorological conditions and γ radiation exposure rates measured by detectors positioned near the plume source. The method is straightforward and easy to use under field conditions without the help of mini-computers. It is applicable to a wide range of radioactive plume situations. It should be noted that the Rio Blanco experiment was detonated on May 17, 1973, and no seep or release of radioactive material occurred

  12. Radioactive colloids

    International Nuclear Information System (INIS)

    Bergqvist, L.

    1987-01-01

    Different techniques for the characterization of radioactive colloids, used in nuclear medicine, have been evaluated and compared. Several radioactive colloids have been characterized in vitro and in vivo and tested experimentally. Colloid biokinetics following interstitial or intravenous injection were evaluated with a scintillation camera technique. Lymphoscintigraphy with a Tc-99-labelled antimony sulphur colloid was performed in 32 patients with malignant melanoma in order to evaluate the technique. Based on the biokinetic results, absorbed doses in tissues and organs were calculated. The function of the reticuloendothelial system has been evaluated in rats after inoculation with tumour cells. Microfiltration and photon correlation spectroscopy were found to be suitable in determining activity-size and particle size distributions, respectively. Maximal lymph node uptake following subcutaneous injection was found to correspond to a colloid particle size between 10 and 50 nm. Lymphoscintigraphy was found to be useful in the study of lymphatic drainage from the primary tumour site in patients with malignant melanoma on the trunk. Quantitative analysis of ilio-inguinal lymph node uptake in patients with malignant melanoma on the lower extremities was, however, found to be of no value for the detection of metastatic disease in lymph nodes. High absorbed doses may be received in lymph nodes (up to 1 mGy/MBq) and at the injection site (about 10 mGy/MBq). In an experimental study it was found that the relative colloid uptake in bone marrow and spleen depended on the total number of intravenously injected particles. This may considerably affect the absorbed dose in these organs. (author)

  13. Environmental releases for calendar year 1996

    International Nuclear Information System (INIS)

    Greager, E.M.

    1997-01-01

    This report presents data on radioactive and nonradioactive materials released into the environment during calendar year 1996 from facilities and activities managed by the Fluor Daniel Hanford, Incorporated (formerly the Westinghouse Hanford Company) and Bechtel Hanford, Incorporated. Fluor Daniel Hanford, Incorporated provides effluent monitoring services for Bechtel Hanford, Incorporated, which includes release reporting. Both summary and detailed presentations of the environmental releases are provided. When appropriate, comparisons to data from previous years are made

  14. Environmental releases for calendar year 1996

    Energy Technology Data Exchange (ETDEWEB)

    Greager, E.M.

    1997-07-31

    This report presents data on radioactive and nonradioactive materials released into the environment during calendar year 1996 from facilities and activities managed by the Fluor Daniel Hanford, Incorporated (formerly the Westinghouse Hanford Company) and Bechtel Hanford, Incorporated. Fluor Daniel Hanford, Incorporated provides effluent monitoring services for Bechtel Hanford, Incorporated, which includes release reporting. Both summary and detailed presentations of the environmental releases are provided. When appropriate, comparisons to data from previous years are made.

  15. Incineration of radioactive waste

    International Nuclear Information System (INIS)

    Eid, C.

    1985-01-01

    The incineration process currently seems the most appropriate way to solve the problems encountered by the increasing quantities of low and medium active waste from nuclear power generation waste. Although a large number of incinerators operate in the industry, there is still scope for the improvement of safety, throughput capacity and reduction of secondary waste. This seminar intends to give opportunity to scientists working on the different aspects of incineration to present their most salient results and to discuss the possibilities of making headway in the management of LL/ML radioactive waste. These proceedings include 17 contributions ranging over the subjects: incineration of solid β-γ wastes; incineration of other radwastes; measurement and control of wastes; off-gas filtration and release. (orig./G.J.P.)

  16. Radioactive waste management

    International Nuclear Information System (INIS)

    Alfredson, P.G.; Levins, D.M.

    1975-08-01

    Present and future methods of managing radioactive wastes in the nuclear industry are reviewed. In the stages from uranium mining to fuel fabrication, the main purpose of waste management is to limit and control dispersal into the environment of uranium and its decay products, particularly radium and radon. Nuclear reactors produce large amounts of radioactivity but release rates from commercial power reactors have been low and well within legal limits. The principal waste from reprocessing is a high activity liquid containing essentially all the fission products along with the transuranium elements. Most high activity wastes are currently stored as liquids in tanks but there is agreement that future wastes must be converted into solids. Processes to solidify wastes have been demonstrated in pilot plant facilities in the United States and Europe. After solidification, wastes may be stored for some time in man-made structures at or near the Earth's surface. The best method for ultimate disposal appears to be placing solid wastes in a suitable geological formation on land. (author)

  17. Environmental radioactivity. Measurement and monitoring

    International Nuclear Information System (INIS)

    2009-11-01

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

  18. Applicant's guide related to requests of shipping approval and of acceptance of parcel models or radioactive products aimed at civilian use transported on public road - Guide nr 7 - Index 0, release of the 07/04/2009

    International Nuclear Information System (INIS)

    2009-01-01

    This guide presents the recommendations made by the ASN to applicants in order to facilitate approval requests and shipping approvals related to the transportation of radioactive products. After a recall of the legal context, these recommendations address the documents to be provided in support of an approval request or of a shipping approval, the content of the safety file, the instruction delay, the approval certificate, and changes brought to the parcel model. Appendices contain issues raised by expertise based on experiences, the European PDSR (Package Design Safety Report), and a model for the elaboration of a certificate project

  19. Radioactive kryptonates in the analysis of environmental samples

    International Nuclear Information System (INIS)

    Tolgyessy, J.

    1986-01-01

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

  20. Disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Blomeke, J.O.

    1979-01-01

    Radioactive waste management and disposal requirements options available are discussed. The possibility of beneficial utilization of radioactive wastes is covered. Methods of interim storage of transuranium wastes are listed. Methods of shipment of low-level and high-level radioactive wastes are presented. Various methods of radioactive waste disposal are discussed